...

Part 2 FSAR Revision 3 Update Tracking Report

by user

on
Category: Documents
3

views

Report

Comments

Transcript

Part 2 FSAR Revision 3 Update Tracking Report
August 1, 2013
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2
FSAR Revision 3
Update Tracking Report
Revision 2
Revision History
Revision
-
Date
6/28/2012
Update Description
COLA Revision 3 Transmittal
See Luminant Letter no. TXNB-12023 Date 6/28/2012
-
05/16/2012
Updated Chapters:
Ch. 8, 13
See Luminant Letter no. TXNB-12013 Date 05/16/2012
Incorporated responses to following RAIs
No. 249, 255
-
05/31/2012
Updated Chapters:
Ch. 9, 14, 19
See Luminant Letter no. TXNB-12016 Date 05/31/2012
Incorporated responses to following RAIs
No. 248, 251
-
6/13/2012
Updated Chapters:
Ch. 3, 6, 9
See Luminant Letter no. TXNB-12021 Date 6/13/2012
Incorporated responses to following RAIs
No. 52 Supplemental 01, 240 Supplemental 01, 244
Supplemental 01
-
6/21/2012
Updated Chapters:
Ch. 3, 9, 14
See Luminant Letter no. TXNB-12022 Date 6/21/2012
Incorporated responses to following RAIs
No. 254, 257
-
7/20/2012
Updated Chapters:
Ch. 14
See Luminant Letter no. TXNB-12026 Date 7/20/2012
Revision History - 1 of 5
-
-
-
-
-
-
-
-
7/24/2012
8/29/2012
9/10/2012
9/14/2012
9/24/2012
9/26/2012
11/12/2012
12/03/2012
Incorporated responses to following RAIs
No. 256
Updated Chapters:
Ch. 13
See Luminant Letter no. TXNB-12027 Date 7/24/2012
Incorporated responses to following RAIs
No. 261
Updated Chapters:
Ch. 9
See Luminant Letter no. TXNB-12030 Date 8/29/2012
Incorporated responses to following RAIs
No. 243 S01
Updated Chapters:
Ch. 3, 9, 14
See Luminant Letter no. TXNB-12031 Date 9/10/2012
Incorporated responses to following RAIs
No. 251 S01, 252 S01
Updated Chapters:
Ch. 1, 2, 3, 8, 9, 11, 19
See Luminant Letter no. TXNB-12032 Date 9/14/2012
Incorporated responses to following RAIs
No. 250
Updated Chapters:
Ch. 3, 9, 14
See Luminant Letter no. TXNB-12034 Date 9/24/2012
Incorporated responses to following RAIs
No. 254 S01, 257 S01
Updated Chapters:
Ch. 1, 3
See Luminant Letter no. TXNB-12035 Date 9/26/2012
Incorporated responses to following RAIs
No. 262
Updated Chapters:
Ch. 9, 14
See Luminant Letter no. TXNB-12036 Date 11/12/2012
Incorporated responses to following RAIs
No. 252 S02, 254 S02, 257 S02
Updated Chapters:
Ch. 1, 9, 14
Revision History - 2 of 5
-
-
-
-
-
-
-
12/06/2012
12/18/2012
12/18/2012
12/18/2012
12/18/2012
12/18/2012
01/17/2013
See Luminant Letter no. TXNB-12041 Date 12/03/2012
Incorporated responses to following RAIs
No. 251 S02
Updated Chapters:
Ch. 9, 10, 11, 12
See Luminant Letter no. TXNB-12042 Date 12/06/2012
Incorporated responses to following RAIs
No. 135 S04
Updated Chapters:
Ch. 9
See Luminant Letter no. TXNB-12043 Date 12/18/2012
Incorporated responses to following RAIs
No. 266
Updated Chapters:
Ch. 19
See Luminant Letter no. TXNB-12043 Date 12/18/2012
Incorporated responses to following RAIs
No. 267
Updated Chapters:
Ch. 19
See Luminant Letter no. TXNB-12043 Date 12/18/2012
Incorporated responses to following RAIs
No. 264
Updated Chapters:
Ch. 1, 19
See Luminant Letter no. TXNB-12043 Date 12/18/2012
Incorporated responses to following RAIs
No. 268
Updated Chapters:
Ch. 3, 9
See Luminant Letter no. TXNB-12043 Date 12/18/2012
Incorporated responses to following RAIs
No. 265
Updated Chapters:
Ch. 1, 6
See Luminant Letter no. TXNB-13001 Date 01/17/2013
Incorporated responses to following RAIs
No. 271
Revision History - 3 of 5
-
-
-
03/04/2013
03/04/2013
03/04/2013
0
2/26/2013
-
04/29/2013
1
05/10/2013
-
5/13/2013
-
-
5/28/2013
5/28/2013
Updated Chapters:
Ch. 1, 6
See Luminant Letter no. TXNB-13005 Date 03/04/2013
Incorporated responses to following RAIs
No. 272
Updated Chapters:
Ch. 9
See Luminant Letter no. TXNB-13006 Date 03/04/2013
Incorporated responses to following RAIs
No. 243 S02
Updated Chapters:
Ch. 8
See Luminant Letter no. TXNB-13007 Date 03/04/2013
Incorporated responses to following RAIs
No. 9 S03
Updated Chapters:
Ch 1, 2, 3, 8, 9, 12
Updated Chapters:
Ch. 2
See Luminant Letter no. TXNB-13013 Date 04/29/2013
Incorporated responses to following RAIs
No. 147 S01, 147 S04
Updated Chapters:
Ch 2, 6, 8, 9, 19
Updated Chapters:
Ch. 2
See Luminant Letter no. TXNB-13016 Date 5/13/2013
Incorporated responses to following RAIs
No. 139 S03
Updated Chapters:
Ch. 13
See Luminant Letter no. TXNB-13017 Date 5/28/2013
Incorporated responses to following RAIs
No. 270
Updated Chapters:
Ch. 2
See Luminant Letter no. TXNB-13018 Date 5/28/2013
Incorporated responses to following RAIs
No. 145 S02
Revision History - 4 of 5
-
2
6/18/2013
8/1/2013
Updated Chapters:
Ch. 3
See Luminant Letter no. TXNB-13019 Date 6/18/2013
Incorporated responses to following RAIs
No. 275
Updated Chapters:
Ch. 1, 2, 3, 8, 9, 13
Revision History - 5 of 5
Chapter 1
Chapter 1 Tracking Report Revision List
Change ID No.
Section
RCOL2_03.03.029
Table 1.8-201
(Sheets 4, 6, 10,
21 of 71)
FSAR
Rev. 3
Page
1.8-15
1.8-17
1.8-21
1.8-32
Table 1.9-201
(Sheet 12 of 12)
Reason for
change
Change Summary
Response to RAI
No. 250
Luminant Letter
no.TXNB-12032
Date 09/14/2012
Revised to
incorporate RG
1.221.
Rev.
of
FSAR
T/R
-
1.9-15
Table 1.9-206
(Sheet 1 of 2)
1.9-24
[1.9-25]
RCOL2_03.06.011
Table 1.8-201
(Sheets 7, 8 of
71)
1.8-18
1.8-19
Response to RAI
No. 262
Luminant Letter
no.TXNB-12035
Date 9/26/2012
Revised COL 3.6(1)
and COL 3.6(4).
-
RCOL2_09.02.019 S02
Table 1.8-201
(Sheet 39 of 71)
1.8-50
2nd Supplemental
Response to RAI
No. 251
Luminant Letter
no.TXNB-12041
Date 12/03/2012
Change the wording
to address the need
of COL evaluation
for a void detection
system.
-
RCOL2_19-24
Table 1.8-201
(Sheets 68, 70,
71 [68, 70, 72]
of 71 [72])
1.8-79,
1.8-81,
1.8-82
[1.8-79,
1.8-81,
1.8-83]
Response to RAI
No. 268
Luminant Letter
no.TXNB-12043
Date 12/18/2012
Table 1.8-201
(Sheet 70 [71] of
71 [72])
1.8-81
[1.8-82]
Response to RAI
No. 268
Luminant Letter
no.TXNB-12043
Date 12/18/2012
RCOL2_19-25
1_1
Clarified resolution
of combined license
items on site
specific information.
Included updated
FSAR reference
locations.
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
-
RCOL2_06.02.025
Table 1.8-201
(Sheet 26 of
71[72])
1.8-37
Response to RAI
No. 271
Luminant Letter
no.TXNB-13001
Date 01/17/2013
Added FSAR
Location and
Resolution Category
for COL Item 6.2(6).
RCOL2_06.02.026
Table 1.8-201
(Sheet 26 of 71
[72])
1.8-37
Response to RAI
No. 272
Luminant Letter
no.TXNB-13005
Date 03/04/2013
COL Item 6.2(5)
location made more
specific (Section
6.2.2.3 to Section
6.2.2.3.2)
-
CTS-01506
Figure 1.2-1R
1.2-5
1.2-6
Consistency with
DCD as
described in
Letter.
TXNB-12033
(ML12268A413)
and TXNB-12038
(ML12334A026)
Figure was updated
to reflect standard
plant and sitespecific layout
0
CTS-01506
Figure 1.2-201
1.2-8
Consistency with
DCD as
described in
Letter.
TXNB-12033
(ML12268A413)
and TXNB-12038
(ML12334A026)
Figure was updated
to reflect standard
plant and sitespecific layout and
general
arrangement design
changes.
0
CTS-01507
Figure
1.2-202
1.2-9
Design change as
described in
Letter TXNB12033
(ML12268A413)
Figure was revised
to reflect the
integration of the
north portions of the
ESWPT into the
south side of the
UHSRS
0
1_2
Change ID No.
CTS-01507
Section
FSAR
Rev. 3
Page
Reason for
change
Figures 1.2-203
through
1.2-210
1.2-10
through
1.2-17
Design change as
described in
Letter
TXNB-12033
(ML12268A413),
TXNB-12038
(ML12334A026),
and TXNB-12030
(ML12243A456)
Change Summary
Figures were
revised to reflect:
Rev.
of
FSAR
T/R
0
Integration of the
north portions of the
ESWPT into the
south side of the
UHSRS.
Integration of
adjacent UHSRS (C
and D) and (A and
B) on a single
foundation.
ESW Pump House
layout changes
described in
responses to RAIs
243 S01 and 254
S03.
Addition of an ESW
Pipe Removal Shaft
to the ESWPT
Segment integrated
to UHSRS C and D
CTS-01532
ACRONYMS
AND
ABBREVIATION
1-xxi
Acronym added
for consistency
with new
Fukushima
changes.
“NTTF” was added.
2
CTS-01532
Table 1.8-201
(Sheet 1[2] of
71[74])
1.8-12
[1.8-14
1.8-15]
COL items 1.9(2)
through 1.9(7) were
added.
2
1.9.6
1.9-3
[1.9-4]
Reflection of COL
items designated
by the US-APWR
DCD update
tracking report,
MUAP-11021,
Rev. 4
(ML13154A292)
1_3
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
CTS-01532
APPENDIX 1A
(new)
New
pages
after
1.10-10
[1A-i
1A-1]
Consistency with
DCD
Appendix 1A was
added consistent
with DCD Appendix
1A.
CTS-01532
1.9.5.2 (new)
APPENDIX 1B
(new)
1.9-3
New
pages
after
1.10-10
[1B-i,
1B-ii
1B-1
through
1B-36 ]
Addition of
Fukushimarelated actions
1.9.5.2 and
Appendix 1B were
added.
Rev.
of
FSAR
T/R
2
2
*Page numbers for the attached marked-up pages may differ from the revision 3 page numbers due to text additions
and deletions. When the page numbers for the attached pages do differ, the page number for the attached page is
shown in brackets.
1_4
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
ACRONYMS AND ABBREVIATIONS (Continued)
NR
NRC
NRCA
NRDS
NS
NSSS
NTTF
NUMARC
NUREG
O/B
OBE
OC
OD
ODCM
ODSCC/IGA
OECD
OEM
OEPS
OER
O/H
OHLHL
OLM
OLTC
OMCS
OMS
Oncor
OP
OP∆T
OPC
OPDMS
OPS
OPSDS
O-RAP
ORE
neutron reflector
U.S. Nuclear Regulatory Commission
non-radiological controlled area
non-radioactive drain system
non-seismic
nuclear steam supply system
CTS-01532
Near-Term Task Force
Nuclear Management and Resources Council
NRC Technical Report Designation (Nuclear Regulatory
Commission)
outside building
operating-basis earthquake
operator console
outside diameter
offsite dose calculation manual
outside diameter stress corrosion cracking/intergranular
attack
Organization for Economic Cooperation and
Development
original equipment manufacturer
onsite electrical power system
operating experience review
overhead
overhead heavy load handling system
on-line maintenance
on-load tap changer
off-microwave communication system
operation and monitoring system
Oncor Electric Delivery Company LLC
over-pressure
over power delta-T
overspeed protection controller
on-line power distribution monitoring system
offsite power system
onsite power system distribution system
operational reliability assurance program
occupational radiation exposure
1-xxi
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 1.8-201 (Sheet 2 of 74)
CP COL 1.8(2)
Resolution of Combined License Items for Chapters 1 - 19
COL Item No.
COL Item
FSAR Location
Resolution
Category
COL 1.9(2)
The COL Applicant is to address site-specific strategies to mitigate
beyond design basis external events per guidance in NRC Order EA
12-049, including, but not limited to:
1) evaluation of site-specific external hazards
2) protection of portable equipment
3) acquisition, staging, or installing of equipment
4) maintenance and testing of portable equipment
5) procedures and guidance and training on mitigation of
beyond-design-basis external events
1.9.5.2
Appendix 1B
1a
2
COL 1.9(2)-1
Evaluation of site-specific external hazards
1.9.5.2
Appendix 1B
Table 2.0-1R
2.3.1.2
2.4.2
2.4.3
2.5.2
3a
COL 1.9(2)-2
Protection of portable equipment
1.9.5.2
Appendix 1B
1a
2
COL 1.9(2)-3
Acquisition, staging, or installing of equipment for strategies for BDB
events
1.9.5.2
Appendix 1B
1a
COL 1.9(2)-4
Maintenance and testing of portable equipment
1.9.5.2
Appendix 1B
13.2.1.1.4
13.5.2.2
1a
2
1.8-14
CTS-01532
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 1.8-201 (Sheet 3 of 74)
CP COL 1.8(2)
Resolution of Combined License Items for Chapters 1 - 19
COL Item No.
COL Item
FSAR Location
Resolution
Category
COL 1.9(2)-5
Procedures and guidance and training on mitigation of
beyond-design-basis external events
1.9.5.2
Appendix 1B
13.2.1.1.4
13.5.2.2
1b
2
COL 1.9(3)
The COL Applicant is to address protection from beyond design basis
external flood for site-specific SSCs that is required to implement the
baseline coping strategies for a beyond design basis external flood as
specified in NEI 12-06.
1.9.5.2
Appendix 1B
3.4.1.2
3.4.1.4
3a
COL 1.9(4)
The COL Applicant is to address SFP level instrumentation
1.9.5.2
maintenance procedure development and perform training as specified Appendix 1B
in NRC Order EA-12-051.
13.2.1.1.4
13.5.2.2
Table 13.4-201
1a
2
COL 1.9(5)
The COL Applicant is to address development of EOPs, SAMGs, and
EDMGs which incorporate lessons learned from TEPCO’s
Fukushima-Daiichi Nuclear Power Plant Accident as addressed in
SECY-12-0025.
1.9.5.2
Appendix 1B
13.5.2.1
13.5.2.2
2
COL 1.9(6)
The COL Applicant is to address enhancement of offsite
1.9.5.2
communication system specified in Recommendation 9.3 in Enclosure Appendix 1B
7 to SECY-12-0025.
9.5.2.2.2.2
9.5.2.2.5.1
3a
COL 1.9(7)
The COL Applicant is to address staffing for large scale natural event 1.9.5.2
as specified in Recommendation 9.3 in Enclosure 7 to SECY-12-0025. Appendix 1B
13.3.2
13.3.5
1a
1.8-15
CTS-01532
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
NRC Bulletins and NRC Generic Letters as of December 12, 2007. The table
contains columns for the generic issue document (including number, title, and
date), language excerpted from the document that communicates the substance
of the issue, CPNPP Units 3 and 4 Comments on applicability, and references to
the relevant subject matter in the CPNPP Units 3 and 4 FSAR.
1.9.5.2
CTS-01532
Conformance with SECY-12-0025
Add the following paragraph after the last paragraph in DCD Subsection 1.9.5.2.
CP COL 1.9(1)
CP COL 1.9(2)
CP COL 1.9(2)-1
CP COL 1.9(2)-2
CP COL 1.9(2)-3
CP COL 1.9(2)-4
CP COL 1.9(2)-5
CP COL 1.9(3)
CP COL 1.9(4)
CP COL 1.9(5)
CP COL 1.9(6)
CP COL 1.9(7)
Site-specific responses to the NRC Fukushima Near-Term Task Force (NTTF)
recommendations and applicable guidance (including related orders issued but
not applicable to CPNPP Units 3 and 4) are summarized in Appendix 1B to the
FSAR Chapter 1.
Appendix 1B to FSAR Chapter 1 also compiles CPNPP Units 3 and 4 actions that
have been or will be taken to incorporate lessons learned from the Fukushima
events. Table 1B-201 in Appendix 1B provides a cross reference of all the NTTF
recommendations to the sections in the CPNPP Units 3 and 4 FSAR, the
US-APWR DCD and MUAP-13002. Table 1B-202 in Appendix 1B summarizes the
post-COL commitments and programs of CPNPP Units 3 and 4 that incorporate
the NTTF recommendations.
1.9.6
Combined License Information
Replace the content of DCD Subsection 1.9.6 with the following.
CP COL 1.9(1)
1.9(1) Conformance with regulatory guidance
This COL item is addressed in Section 1.9, Subsections 1.9.1 through 1.9.4, and
Tables 1.9-201 through 1.9-220.
CP COL 1.9(2)
CTS-01532
1.9(2) Mitigation of BDB external events
This COL item is addressed in Subsection 1.9.5.2 and Appendix 1B (1B.4.2).
CP COL 1.9(2)-1
1.9(2)-1 Evaluation of site-specific external BDB hazards
This COL item is addressed in Subsection 1.9.5.2, Appendix 1B (1B.2.1 and
1B.4.2), Table 2.0-1R, Subsections 2.3.1.2, 2.4.2, 2.4.3 and 2.5.2
CP COL 1.9(2)-2
1.9(2)-2 Protection of portable equipment used in strategies for BDB external
events
This COL item is addressed in Subsection 1.9.5.2 and Appendix 1B (1B.4.2).
CP COL 1.9(2)-3
1.9(2)-3 Acquisition, staging or installing equipment for strategies for BDB events
1.9-3
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
This COL item is addressed in Subsection 1.9.5.2 and Appendix 1B (1B.4.2).
CP COL 1.9(2)-4
1.9(2)-4 Maintenance and testing of portable equipment used in strategies for
BDB events
This COL item is addressed in Subsection 1.9.5.2, Appendix 1B (1B.4.2) and
Subsections 13.2.1.1.4 and 13.5.2.2.
CP COL 1.9(2)-5
1.9(2)-5 Procedures, guidance and training on strategies to mitigate BDB external
events
This COL item is addressed in Subsection 1.9.5.2, Appendix 1B (1B.4.2) and
Subsections 13.2.1.1.4 and 13.5.2.2.
CP COL 1.9(3)
1.9(3) Protection of SSCs for baseline coping strategies from BDB external flood
This COL item is addressed in Subsection 1.9.5.2, Appendix 1B (1B.2.1 and
1B.4.2), and Subsections 3.4.1.2 and 3.4.1.4.
CP COL 1.9(4)
1.9(4) SFP level instrumentation maintenance procedure development and
training
This COL item is addressed in Subsection 1.9.5.2, Appendix 1B (1B.7.1), Table
13.4-201, and Subsections 13.2.1.1.4 and 13.5.2.2.
CP COL 1.9(5)
1.9(5) Address EOPs, SAMGs and EDMGs addressed in SECY-12-0025
This COL item is addressed in Subsection 1.9.5.2, Appendix 1B (1B.8.1) and
Subsections 13.5.2.1 and 13.5.2.2
CP COL 1.9(6)
1.9(6) Enhancement of offsite communications specified in SECY-12-0025
This COL item is addressed in Subsection 1.9.5.2, Appendix 1B (1B.9.3.1.1) and
Subsections 9.5.2.2.2.2 and 9.5.2.2.5.1.
CP COL 1.9(7)
1.9(7) Address staffing for large scale natural events specified in SECY-12-0025
This COL item is addressed in Subsection 1.9.5.2 , Appendix 1B (1B.9.3.1.2) and
Subsections 13.3.2 and 13.3.5.
The applicable requirements of 10 CFR 30, 40, 70, 73 and 74 regarding
emergency protection and preparedness, security, non-licensed staff training and
fire protection program elements that will be in place prior to receipt of byproduct,
source or special nuclear material are located in Subsections 12.2.1.1.10,
13.5.2.2, 13.6, and Tables 1.9-220 and 13.4-201.
1.9-4
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
APPENDIX 1A
CTS-01532
INDEX OF TIER2* INFORMATION
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
TABLE OF CONTENTS
Section
1A
Title
Page
INDEX OF TIER 2* INFORMATION ...............................................1A-1
1A-i
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
1A
INDEX OF TIER 2* INFORMATION
CTS-01532
This appendix of the referenced DCD is incorporated by reference.
1A-1
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
APPENDIX 1B
CTS-01532
FUKUSHIMA NEAR TERM TASK FORCE RECOMMENDATIONS
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
TABLE OF CONTENTS
Section
1B
Title
Page
FUKUSHIMA NEAR TERM TASK FORCE
RECOMMENDATIONS ..................................................................1B-1
1B-i
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
LIST OF TABLES
Number
Title
1B-201
Cross Reference to Standard Plant
1B-202
Summary of Post-COL Commitment and Programs for NTTF
Recommendations
1B-ii
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP SUP 1B(1)
1B
FUKUSHIMA NEAR TERM TASK FORCE RECOMMENDATIONS
1B.0
INTRODUCTION
Following the Fukushima event, the NRC formed a Fukushima Near-Term Task
Force (NTTF). The NTTF published its recommendations on July 12, 2011, in
SECY-11-0093, “Near-Term Report and Recommendation for Agency Actions
Following the Events in Japan” (Reference 1B-2). Each of the recommendations
from the NTTF Report is addressed below and the “1B” subsection numbers
correspond with the recommendation numbers.
In SECY-11-0137, “Prioritization of Recommended Actions To Be Taken in
Response to Fukushima Lessons Learned,” dated October 3, 2011 (Reference
1B-4), the NRC staff grouped the recommendations into three tiers – Tier 1, Tier 2,
and Tier 3.
Additional recommendations, which the NRC staff added in SECY-12-0025,
“Proposed Orders and Requests for Information in Response to Lessons Learned
from Japan’s March 11, 2011, Great Tohoku Earthquake and Tsunami” dated
February 17, 2012 (Reference 1B-5), are also addressed in the subsection below.
Additional insights regarding several recommendations are contained in Order
EA-12-049, “Issuance of Order to Modify Licenses with Regard to Requirements
for Mitigation Strategies for Beyond-Design Basis External Events” (Reference
1B-7), in Order EA-12-051, “Issuance of Order to Modify Licenses with regard to
Reliable Spent Fuel Pool Instrumentation" (Reference 1B-8) and in the “Request
for Information Pursuant to Title 10 of the Code of Federal Regulations 50. 54 (f)
regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Force
Review of Insights from the Fukushima Dai-ichi Accident” issued on March 12,
2012 (Reference 1B-9). Although these orders and letter are not directly
applicable to CPNPP Units 3 and 4, the insights have been considered in
developing the responses below.
The strategies and design enhancements of the US-APWR to incorporate lessons
learned from the accidents at TEPCO’s Fukushima Dai-ichi Nuclear Power
Station, and the requirements/recommendations issued after the disaster by the
US NRC as presented in the referenced DCD, including MUAP-13002 (see
Reference 1B-12), are incorporated by reference with the departures and/or
supplements as identified below.
1B.1.0
NTTF 1.0 - Clarify the Regulatory Framework
Recommendation 1 from the NTTF report reads:
The Task Force recommends establishing a logical, systematic, and coherent
regulatory framework for adequate protection that appropriately balances
defense-in-depth and risk considerations.
1B-1
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CPNPP Units 3 and 4 Response
CTS-01532
See recommendations 1.1, 1.2, 1.3 and 1.4 below:
1B.1.1
NTTF 1.1
The NTTF Report made the following Recommendation:
1.1
Draft a Commission policy statement that articulates a risk-informed
defense-in-depth framework that includes extended design-basis
requirements in the NRC’s regulations as essential elements for ensuring
adequate protection.
CPNPP Units 3 and 4 Response
This recommendation is applicable to NRC not to CPNPP Units 3 and 4; however,
CPNPP Units 3 and 4 will comply with applicable new requirements, as
necessary, once they are issued.
1B.1.2
NTTF 1.2
The NTTF Report made the following Recommendation:
1.2
Initiate rulemaking to implement a risk-informed, defense-in-depth
framework consistent with the above recommended Commission policy
statement.
CPNPP Units 3 and 4 Response
This recommendation is applicable to NRC not to CPNPP Units 3 and 4; however,
CPNPP Units 3 and 4 will comply with applicable new requirements, as
necessary, once they are issued.
1B.1.3
NTTF 1.3
The NTTF Report made the following Recommendation:
1.3
Modify the Regulatory Analysis Guidelines to more effectively implement
the defense-in-depth philosophy in balance with the current emphasis on
risk-based guidelines.
CPNPP Units 3 and 4 Response
This recommendation is applicable to NRC not to CPNPP Units 3 and 4; however,
CPNPP Units 3 and 4 will comply with applicable new requirements, as
necessary, once they are issued.
1B-2
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
1B.1.4
NTTF 1.4
CTS-01532
The NTTF Report made the following Recommendation:
1.4
Evaluate the insights from the IPE and IPEEE efforts as summarized in
NUREG-1560, “Individual Plant Examination Program: Perspectives on
Reactor Safety and Plant Performance,” issued December 1997, and
NUREG-1742, “Perspectives Gained from the Individual Plant
Examination of External Events (IPEEE) Program,” issued April 2002, to
identify potential generic regulations or plant-specific regulatory
requirements.
CPNPP Units 3 and 4 Response
This recommendation is applicable to NRC not to CPNPP Units 3 and 4; however,
CPNPP Units 3 and 4 will comply with applicable new requirements, as
necessary, once they are issued.
1B.2.0
NTTF 2.0 - Seismic and Flooding Protection
The NTTF Report made the following Recommendation:
The Task Force recommends that the NRC require licensees to reevaluate and
upgrade as necessary the design-basis seismic and flooding protection of SSCs
for each operating reactor.
CPNPP Units 3 and 4 Response
See recommendation 2.1, 2.2 and 2.3 below
1B.2.1
NTTF 2.1 - Seismic and flood hazard reevaluations (Tier 1)
The NTTF Report made the following Recommendation:
2.1
Order licensees to reevaluate the seismic and flooding hazards at their
sites against current NRC requirements and guidance, and if necessary,
update the design basis and SSCs important to safety to protect against
the updated hazards.
In RAI 6527 (CP RAI #261) to CPNPP Units 3 and 4 (Reference 1B-10), the NRC
staff requested the following:
a) Evaluate the potential impacts of the newly released CEUS-SSC model, with
potential local and regional refinements as identified in the CEUS-SSC model, on
the seismic hazard curves and the site-specific ground motion response spectra
(GMRS)/foundation input response spectra (FIRS).
1B-3
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
For re-calculation of the probabilistic seismic hazard analysis (PSHA), please
follow either the cumulative absolute velocity (CAV) filter or minimum magnitude
specifications outlined in Attachment 1 to Seismic Enclosure 1 of the March 12,
2012 letter " Request for information pursuant to Title 10 of the Code of Federal
Regulations 50.54(f) regarding Recommendations 2.1, 2.3, and 9.3, of the
near-term task force review of insights from the Fukushima Dai-Ichi accident."
b) In your response, please identify the method you selected from the above
choices to perform the evaluation. Modify and submit the site-specific GMRS and
FIRS changes, as necessary, given the evaluation performed in part (a) above.
Provide the basis supporting your position.
CPNPP Units 3 and 4 Response
The seismic hazard at the CPNPP site was re-evaluated using the central and
eastern United States CEUS Seismic Source Characterization (CEUS-SSC)
model as described in NUREG-2115 and the results are provided in FSAR Table
2.0-1R and Section 2.5, “Geology, Seismology, and Geotechnical Engineering.”
Per Subsection 2.5.1.2.5.10.3, a minimum magnitude of 5.0 was used to
CP COL 1.9(2)-1 recalculate the PSHA. FSAR Subsection 2.5.2 “Vibratory Ground Motion”
addresses the re-evaluated Ground Motions Response Spectra (GMRS) and
Foundation Input Response Spectra (FIRS) for the CPNPP Units 3 and 4.
CP COL 1.9(3)
With regard to flood hazard evaluation, FSAR Subsection 2.4.2.2 discusses the
site-specific BDB external flood elevation, and FSAR Subsections 3.4.1.2 and
3.4.1.4 address protection from the BDB external flood.
1B.2.2
NTTF 2.2 - Ten-year confirmation of seismic and flooding hazards
(dependent on Recommendation 2.1) (Tier 3)
The NTTF Report made the following Recommendation:
2.2
Initiate rulemaking to require licensees to confirm seismic hazards and
flooding hazards every 10 years and address any new and significant
information. If necessary, update the design basis for SSCs important to
safety to protect against the updated hazards.
CPNPP Units 3 and 4 Response
This recommendation is applicable to NRC not to CPNPP Units 3 and 4; however,
CPNPP Units 3 and 4 will comply with new requirements, as necessary, once they
are issued.
1B.2.3
NTTF 2.3 - Seismic and Flooding Walkdowns
1B.2.3.1
NTTF 2.3.1 - Seismic Walkdowns (Tier 1)
The NTTF Report made the following Recommendation:
1B-4
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
2.3
Order licensees to perform seismic and flood protection walkdowns to
identify and address plant-specific vulnerabilities and verify the adequacy
of monitoring and maintenance for protection features such as watertight
barriers and seals in the interim period until longer term actions are
completed to update the design basis for external events.
The order described by SECY-12-0025 and issued on March 12, 2012 (Reference
1B-5) directed licensees to take the following actions:
Perform seismic walkdowns in order to identify and address plant specific
degraded, non-conforming, or unanalyzed conditions and verify the adequacy of
strategies, monitoring, and maintenance programs such that the nuclear power
plant can respond to external events. The walkdown will verify current plant
configuration with the current licensing basis, verify the adequacy of current
strategies, maintenance plans, and identify degraded, non-conforming, or
unanalyzed conditions.
CPNPP Units 3 and 4 Response
This order is not applicable to CPNPP Units 3 and 4 as this request has been
applied only to the licensees of operating reactors.
1B.2.3.2
NTTF 2.3.2 - Flooding Walkdowns (Tier 1)
The NTTF Report made the following Recommendation:
2.3
Order licensees to perform seismic and flood protection walkdowns to
identify and address plant-specific vulnerabilities and verify the adequacy
of monitoring and maintenance for protection features such as watertight
barriers and seals in the interim period until longer term actions are
completed to update the design basis for external events.
The order described by SECY-12-0025 and issued on March 12, 2012 (Reference
1B-5) directed licensees to take the following actions:
•
Perform flood protection walkdowns using an NRC-endorsed walkdown
methodology,
•
Identify and address plant-specific degraded, non-conforming, or
unanalyzed conditions as well as cliff-edge effects through the corrective
action program and consider these findings in the Recommendation 2.1
hazard evaluations, as appropriate,
•
Identify any other actions taken or planned to further enhance the site
flood protection,
•
Verify the adequacy of programs, monitoring and maintenance for
protection features, and,
1B-5
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
•
Report to the NRC the results of the walkdowns and corrective actions
taken or planned.
CPNPP Units 3 and 4 Response
This order is not applicable to CPNPP Units 3 and 4 as this request has been
applied only to the licensees of operating reactors.
1B.3.0
NTTF 3.0 - Potential enhancements to the capability to prevent or
mitigate seismically induced fires and floods (long-term
evaluation) (Tier 3)
The NTTF Report made the following Recommendation:
The Task Force recommends, as part of the longer term review, that the NRC
evaluate potential enhancements to the capability to prevent or mitigate
seismically induced fires and floods.
CPNPP Units 3 and 4 Response
This recommendation is applicable to NRC, not to CPNPP Units 3 and 4;
however, CPNPP Units 3 and 4 will comply with new requirements, as necessary,
once they are issued.
1B.4.0
NTTF 4.0 - Station Blackout Mitigation
The NTTF Report made the following Recommendation:
The Task Force recommends that the NRC strengthen SBO mitigation capability
at all operating and new reactors for design-basis and beyond-design-basis
external events.
CPNPP Units 3 and 4 Response
See recommendations 4.1 and 4.2 below.
1B.4.1
NTTF 4.1 - Station blackout regulatory actions (Tier 1)
The NTTF Report made the following Recommendation:
4.1
Initiate rulemaking to revise 10 CFR 50.63 to require each operating and
new reactor licensee to (1) establish a minimum coping time of 8 hours for
a loss of all ac power, (2) establish the equipment, procedures, and
training necessary to implement an “extended loss of all ac” coping time of
72 hours for core and spent fuel pool cooling and for reactor coolant
system and primary containment integrity as needed, and (3) preplan and
prestage offsite resources to support uninterrupted core and spent fuel
pool cooling, and reactor coolant system and containment integrity as
1B-6
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
needed, including the ability to deliver the equipment to the site in the time CTS-01532
period allowed for extended coping, under conditions involving significant
degradation of offsite transportation infrastructure associated with
significant natural disasters.
In SECY-11-0137 (Reference 1B-4), it was proposed to engage stakeholders in
support of rulemaking activities to enhance the capability to maintain safety
through a prolonged SBO. The SECY-11-0137 mentioned these activities would
include the development of the regulatory basis, a proposed rule, and
implementing guidance consistent with the rulemaking process and schedule
established in SECY-11-0032, “Consideration of Cumulative Effects of Regulation
in the Rulemaking Process” (Reference 1B-1).
CPNPP Units 3 and 4 Response
See CPNPP Units 3 and 4 response to the NTTF recommendation 4.2 in the next
Section.
1B.4.2
NTTF 4.2 - Equipment covered under Title 10 of the Code of
Federal Regulations (10CFR) 50.54(hh)(2) - Mitigation Strategies
for Beyond-Design-Basis External events (Tier 1)
The NTTF Report made the following Recommendation:
4.2 Order licensees to provide reasonable protection for equipment currently
provided pursuant to 10 CFR 50.54(hh)(2) from the effects of design-basis
external events and to add equipment as needed to address multiunit events
while other requirements are being revised and implemented.
NRC issued the following requirements via EA 12-049 (reference 1B-7) to the
licensees of operating reactors as of March 12, 2012:
(1) Licensees shall develop, implement, and maintain guidance and strategies to
maintain or restore core cooling, containment and SFP cooling capabilities
following a beyond-design-basis external event.
(2) These strategies must be capable of mitigating a simultaneous loss of all
alternating current (ac) power and loss of normal access to the ultimate heat
sink and have adequate capacity to address challenges to core cooling,
containment, and SFP cooling capabilities at all units on a site subject to this
Order.
(3) Licensees must provide reasonable protection for the associated equipment
from external events. Such protection must demonstrate that there is
adequate capacity to address challenges to core cooling, containment, and
SFP cooling capabilities at all units on a site subject to this Order.
(4) Licensees must be capable of implementing the strategies in all modes.
1B-7
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
(5) Full compliance shall include procedures, guidance, training, and acquisition,
staging, or installing of equipment needed for the strategies.
In RAI 6929 (CP RAI #269) Question 01.05-4 to CPNPP Units 3 and 4 (Reference
1B-11), the NRC staff requested the following:
The NRC staff has been directed by the Commission to implement the Fukushima
Near-Term Task Force Recommendations, as presented in SECY-12-0025,
“Proposed Orders and Requests for Information in Response to Lessons Learned
from Japan’s March 11, 2011, Great Tohoku Earthquake and Tsunami”, dated
February 12[17], 2012. This request for additional information specifically
addresses Recommendation 4.2 on Mitigating Strategies, as described in
Attachment 2 to Order EA-12-049. The NRC staff understands that MHI intends to
include a new COL item that would require a COL referencing the US-APWR
design to implement actions to address these provisions, and that you would
propose a license condition. In your response, please specifically include in the
text of any proposed license condition the extent of your commitment to follow the
guidance in JLD-ISG-21012-01, or any alternative approaches.
CPNPP Units 3 and 4 Response
Provision (1) of EA-12-049: CPNPP Units 3 and 4 incorporate by reference the
design changes in the US-APWR DCD Chapters 3, 7, 8, 9 and 10 and
CP COL 1.9(2)-1 descriptions in MUAP-13002 (Reference 1B-12), while evaluation of site-specific
external hazard is described in CPNPP Units 3 and 4 FSAR Sections 2.3.1.2,
CP COL 1.9(2)-2 2.4.2 and 2.5.2, 3.4.1.2, 3.4.1.4 and Table 2.0-1R. Regarding development of
site-specific guidance and strategies, CPNPP Units 3 and 4 will develop and
CP COL 1.9(2)-3
implement site-specific procedures and guidance prior to initial fuel load. (See
Table 1B-202 item 1).
CP COL 1.9(2)
CP COL 1.9(2)-4
Provision (2) of EA-12-049: CPNPP Units 3 and 4 incorporate by reference the
CP COL 1.9(2)-5 description changes in the US-APWR DCD Chapters 8 and MUAP-13002.
CP COL 1.9(3)
Provision (3) of EA-12-049: CPNPP Units 3 and 4 incorporate by reference the
description in MUAP-13002. Regarding provisions of the portable equipment
portion in provision (3) of EA-12-049, CPNPP Units 3 and 4 will develop
site-specific strategies prior to initial fuel load. (See Table 1B-202 item 1).
Provision (4) of EA-12-049: CPNPP Units 3 and 4 incorporate by reference the
description in the US-APWR DCD including MUAP-13002.
Provisions (1) to (4) of EA-12-049: FSAR Chapter 8 tables and figures include the
design information as needed to address the standard plant design and
site-specific design needed to address these provisions.
Provision (5) of EA-12-049: CPNPP Units 3 and 4 FSAR Sections 13.2.1.1.4,
13.5.2.1 and 13.5.2.2 include descriptions regarding implementation of the
procedure and training provisions of this order (see Table 1B-202 item 1), while a
1B-8
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
license condition that describes the required actions with respect to mitigation
strategies (including equipment acquisition, staging, or installation) ensures the
actions are taken prior to initial fuel load.
1B.5.0
NTTF 5.0 - Containment Hardened Vents
The NTTF Report made the following Recommendation:
The Task Force recommends requiring reliable hardened vent designs in BWR
facilities with Mark I and Mark II containments.
CPNPP Units 3 and 4 Response
See recommendations 5.1 and 5.2 below.
1B.5.1
NTTF 5.1 - Reliable hardened vents for Mark I and Mark II
containments (Tier 1)
The NTTF Report made the following Recommendation:
5.1
Order licensees to include a reliable hardened vent in BWR Mark I and
Mark II containments.
CPNPP Units 3 and 4 Response
This recommendation is not applicable to CPNPP Units 3 and 4.
1B.5.2
NTTF 5.2 - Reliable hardened vents for other containment designs
(long-term evaluation) (Tier 3)
The NTTF Report made the following Recommendation:
5.2
Reevaluate the need for hardened vents for other containment designs,
considering the insights from the Fukushima accident. Depending on the
outcome of the reevaluation, appropriate regulatory action should be taken
for any containment designs requiring hardened vents.
CPNPP Units 3 and 4 Response
CPNPP Units 3 and 4 will comply with new requirements, as necessary, once they
are issued.
1B.6.0
NTTF 6.0 - Hydrogen control and mitigation inside containment or
in other buildings (long-term evaluation) (Tier 3)
The NTTF Report made the following Recommendation:
1B-9
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
The Task Force recommends, as part of the longer term review, that the NRC
identify insights about hydrogen control and mitigation inside containment or in
other buildings as additional information is revealed through further study of the
Fukushima Dai-ichi accident.
CPNPP Units 3 and 4 Response
CPNPP Units 3 and 4 will comply with new requirements, as necessary, once they
are issued.
1B.7.0
NTTF 7.0 - Spent fuel pool makeup capability and instrumentaion
(7.1, 7.2, 7.3, 7.4, and 7.5)
The NTTF Report made the following Recommendation:
The Task Force recommends enhancing spent fuel pool makeup capability and
instrumentation for the spent fuel pool.
CPNPP Units 3 and 4 Response
See recommendations 7.1, 7.2, 7.3, 7.4 and 7.5 below.
1B.7.1
NTTF 7.1 - Spent Fuel Pool Instrumentation (Tier 1)
The NTTF Report made the following Recommendation:
7.1
Order licensees to provide sufficient safety-related instrumentation, able to
withstand design-basis natural phenomena, to monitor key spent fuel pool
parameters (i.e., water level, temperature, and area radiation levels) from
the control room.
NRC issued the following requirements to operating plant licensees and combined
license holders via EA 12-051 dated March 12, 2012 (reference 1B-8).
Licensee requires reliable indication of the water level in associated spent fuel
storage pools capable of supporting identification of the following pool water level
conditions by trained personnel: (1) level that is adequate to support operation of
the normal fuel pool cooling system, (2) level that is adequate to provide
substantial radiation shielding for a person standing on the spent fuel pool
operating deck, and (3) level where fuel remains covered and actions to
implement make-up water addition should no longer be deferred.
1.0 The spent fuel pool level instrumentation shall include the following design
features:
1.1 Arrangement: The spent fuel pool level instrument channels shall be arranged
in a manner that provides reasonable protection of the level indication function
against missiles that may result from damage to the structure over the spent
1B-10
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
fuel pool. This protection may be provided by locating the safety-related
instruments to maintain instrument channel separation within the spent fuel
pool area, and to utilize inherent shielding from missiles provided by existing
recesses and corners in the spent fuel pool structure.
1.2 Qualification: The level instrument channels shall be reliable at temperature,
humidity, and radiation levels consistent with the spent fuel pool water at
saturation conditions for an extended period.
1.3 Power supplies: Instrumentation channels shall provide for power connections
from sources independent of the plant alternating current (ac) and direct
current (dc) power distribution systems, such as portable generators or
replaceable batteries. Power supply designs should provide for quick and
accessible connection of sources independent of the plant ac and dc power
distribution systems. On-site generators used as an alternate power source
and replaceable batteries used for instrument channel power shall have
sufficient capacity to maintain the level indication function until offsite resource
availability is reasonably assured.
1.4 Accuracy: The instrument shall maintain its designed accuracy following a
power interruption or change in power source without recalibration.
1.5 Display: The display shall provide on-demand or continuous indication of
spent fuel pool water level.
2. The spent fuel pool instrumentation shall be maintained available and reliable
through appropriate development and implementation of a training program.
Personnel shall be trained in the use and the provision of alternate power to
the safety-related level instrument channels.
In RAI 6527 (CP RAI #261) (Reference 1B-10) Question 01.05-2 to CPNPP Units
3 and 4, the NRC staff requested the following:
By letter dated May 16, 2012, (ML12124A036), the NRC staff informed you that
the NRC staff has been directed by the Commission to implement the Fukushima
Near-Term Task Force recommendations contained in SECY-12-0025, “Proposed
Orders and Requests for Information in Response to Lessons Learned from
Japan’s March 11, 2011, Great Tohoku Earthquake and Tsunami” dated February
17, 2012. This request for additional information (RAI) specifically addresses
Recommendation 7.1, "Reliable Spent Fuel Pool Instrumentation." The NRC staff
requests that you address each of the provisions for monitoring key spent fuel
pool parameters as described in the March 12, 2012 Order, EA-12-051
(ML12054A679), including any proposals for changes to your current application.
CPNPP Units 3 and 4 Response
1B-11
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Provision 1 of EA-12-051: CPNPP Units 3 and 4 incorporate by reference the
design changes in the US-APWR DCD Chapter 9 that address spent fuel pool
level instrumentation.
CP COL 1.9(4)
Provision 2 of EA-12-051: FSAR Sections 13.2.1.1.4 and 13.5.2.2 include
descriptions regarding implementation of the procedure and training requirements
of Recommendation 7.1 and applicable training will be implemented 18 months
prior to initial fuel load. (See Table 1B-202 item 2).
1B.7.2
NTTF 7.2 (Tier 2)
The NTTF Report made the following Recommendation:
7.2
Order licensees to provide safety-related ac electrical power for the spent
fuel pool makeup system.
CPNPP Units 3 and 4 Response
CPNPP Units 3 and 4 incorporate by reference safety-related ac electrical power
configuration for the refueling water recirculation pumps in the spent fuel pool
makeup system as described in the US-APWR DCD Section 9.1.3.2 and Table
3.2-2.
1B.7.3
NTTF 7.3 (Tier 2)
The NTTF Report made the following Recommendation:
7.3
Order licensees to revise their technical specifications to address
requirements to have one train of onsite emergency electrical power
operable for spent fuel pool makeup and spent fuel pool instrumentation
when there is irradiated fuel in the spent fuel pool, regardless of the
operational mode of the reactor.
CPNPP Units 3 and 4 Response
CPNPP Units 3 and 4 will comply with the new requirements, as necessary, once
they are issued.
1B.7.4
NTTF 7.4 (Tier 2)
The NTTF Report made the following Recommendation:
7.4
Order licensees to have an installed seismically qualified means to spray
water into the spent fuel pools, including an easily accessible connection
to supply the water (e.g., using a portable pump or pumper truck) at grade
outside the building.
CPNPP Units 3 and 4 Response
1B-12
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CPNPP Units 3 and 4 incorporate by reference the US-APWR DCD Table 3.2-2,
Figure 9.1.3-1 and Subsections 9.1.3.2 and 9.1.3.3.2 to conform to the
recommendation.
1B.7.5
NTTF 7.5 (Tier 2)
The NTTF Report made the following Recommendation:
7.5
Initiate rulemaking or licensing activities or both to require the actions
related to the spent fuel pool described in detailed recommendations 7.1–
7.4.
CPNPP Units 3 and 4 Response
CPNPP Units 3 and 4 will comply with the new requirements, as necessary, once
they are issued.
1B.8.0
NTTF 8.0 - Strengthening and integration of emergency operating
procedures, severe accident management guidelines (SAMGs),
and extensive damage mitigation guidelines (Tier 1)
The NTTF Report made the following Recommendation:
The Task Force recommends strengthening and integrating onsite emergency
response capabilities such as EOPs, SAMGs, and EDMGs.
CPNPP Units 3 and 4 Response
See recommendations 8.1, 8.2, 8.3 and 8.4 below.
1B.8.1
NTTF 8.1 - Orders to Integrate Programs and Guidance (Tier 1)
The NTTF Report made the following Recommendation:
8.1
Order licensees to modify the EOP technical guidelines (required by
Supplement 1, “Requirements for Emergency Response Capability,” to
NUREG-0737, issued January 1983 (GL 82-33), to (1) include EOPs,
SAMGs, and EDMGs in an integrated manner, (2) specify clear command
and control strategies for their implementation, and (3) stipulate
appropriate qualification and training for those who make decisions during
emergencies.
CPNPP Units 3 and 4 Response
CP COL 1.9(5)
CPNPP Units 3 and 4 have addressed this recommendation in NTTF 4.2 in
response to EA-12-049. CPNPP Units 3 and 4 will comply with new requirements,
as necessary, once they are issued.
1B-13
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
1B.8.2
NTTF 8.2 - Standard Technical Specification Administrative
Controls
The NTTF Report made the following Recommendation:
8.2
Modify Section 5.0, “Administrative Controls,” of the Standard Technical
Specifications for each operating reactor design to reference the approved
EOP technical guidelines for that plant design.
CPNPP Units 3 and 4 Response
CPNPP Units 3 and 4 will comply with new requirements, as necessary, once they
are issued,
1B.8.3
NTTF 8.3 - Licensee Technical Specifications
The NTTF Report made the following Recommendation:
8.3
Order licensees to modify each plant’s technical specifications to conform
to the above changes.
CPNPP Units 3 and 4 Response
CPNPP Units 3 and 4 will comply with new requirements, as necessary, once they
are issued.
1B.8.4
NTTF 8.4 - Realistic Training and Exercises
The NTTF Report made the following Recommendation:
8.4
Initiate rulemaking to require more realistic, hands-on training and
exercises on SAMGs and EDMGs for all staff expected to implement the
strategies and those licensee staff expected to make decisions during
emergencies, including emergency coordinators and emergency directors.
CPNPP Units 3 and 4 Response
CPNPP Units 3 and 4 will comply with new requirements, as necessary, once they
are issued.
1B.9.0
NTTF 9.0 - Emergency Plans for Prolonged SBO and Multiunit
Events
The NTTF Report made the following Recommendation:
The Task Force recommends that the NRC require that facility emergency plans
address prolonged SBO and multiunit events.
1B-14
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CPNPP Units 3 and 4 Response
CTS-01532
See recommendations 9.1, 9.2, 9.3 and 9.4 below.
1B.9.1
NTTF 9.1 - Emergency preparedness (EP) enhancements for
prolonged station blackout (SBO) and multiunit events
(dependent on availability of critical skill sets) (Tier 3)
The NTTF Report made the following Recommendation:
9.1
Initiate rulemaking to require EP enhancements for multiunit events in the
following areas:
•
personnel and staffing
•
dose assessment capability
•
training and exercises
•
equipment and facilities
CPNPP Units 3 and 4 Response
CPNPP Units 3 and 4 will comply with new requirements, as necessary, once they
are issued.
1B.9.2
NTTF 9.2 - Emergency preparedness (EP) enhancements for
prolonged station blackout (SBO) and multiunit events
(dependent on availability of critical skill sets) (Tier 3)
The NTTF Report made the following Recommendation:
9.2
Initiate rulemaking to require EP enhancements for prolonged SBO in the
following areas:
•
communications capability
•
ERDS capability
•
training and exercises
•
equipment and facilities
CPNPP Units 3 and 4 Response
CPNPP Units 3 and 4 will comply with new requirements, as necessary, once they
are issued.
1B-15
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
1B.9.3
NTTF 9.3 - Emergency preparedness
CTS-01532
The NTTF Report made the following Recommendation:
9.3
Order licensees to do the following until rulemaking is complete:
•
Determine and implement the required staff to fill all necessary
positions for responding to a multiunit event.
•
Add guidance to the emergency plan that documents how to perform a
multiunit dose assessment (including releases from spent fuel pools)
using the licensee’s site-specific dose assessment software and
approach.
•
Conduct periodic training and exercises for multiunit and prolonged
SBO scenarios. Practice (simulate) the identification and acquisition of
offsite resources, to the extent possible.
•
Ensure that EP equipment and facilities are sufficient for dealing with
multiunit and prolonged SBO scenarios.
•
Provide a means to power communications equipment needed to
communicate onsite (e.g., radios for response teams and between
facilities) and offsite (e.g., cellular telephones, satellite telephones)
during a prolonged SBO.
•
Maintain ERDS capability throughout the accident.
In RAI 6527 (CP RAI #261) (Reference 1B-10) Question 01.05-3 to CPNPP Units
3 and 4, the NRC staff requested the following:
By letter dated May 16, 2012, (ML12124A036), the NRC staff informed you that
the NRC staff has been directed by the Commission to implement the Fukushima
Near-Term Task Force recommendations contained in SECY-12-0025, “Proposed
Orders and Requests for Information in Response to Lessons Learned from
Japan’s March 11, 2011, Great Tohoku Earthquake and Tsunami” dated February
17, 2012. This request for additional information (RAI) specifically addresses
Recommendation 9.3, "provisions for enhancing emergency preparedness." The
NRC staff requests that you address each of the provisions for enhancing
emergency preparedness as described in Enclosure 7 of SECY-12-0025,
including any proposals for changes to your current application.
CPNPP Units 3 and 4 Response
See 1B.9.3.1, 1B.9.3.2 and 1B.9.3.3 below.
1B-16
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
1B.9.3.1
NTTF 9.3.1 - Emergency preparedness regulatory actions
(communication and staffing) (Tier 1)
1B.9.3.1.1
NTTF 9.3.1.1 - Emergency preparedness regulatory actions
(communication) (Tier 1)
The section on Communications in Enclosure 7 to SECY-12-0025 (Reference
1B-5) requested the following information from licensees:
1. Provide an assessment of the current communications systems and
equipment used during an emergency event to identify any enhancements
that may be needed to ensure communications are maintained during a large
scale natural event meeting the conditions described above. The assessment
should:
•
Identify any planned or potential improvements to existing on-site
communications systems and their required normal and/or backup power
supplies,
•
Identify any planned or potential improvements to existing offsite
communications systems and their required normal and/or backup power
supplies,
•
Provide a description of any new communications system(s) or
technologies that will be deployed based upon the assumed conditions
described above, and
•
Provide a description of how the new and/or improved systems and power
supplies will be able to provide for communications during a loss of all ac
power,
2. Describe any interim actions that have been taken or are planned to be taken
to enhance existing communications systems power supplies until the
communications assessment and the resulting actions are complete,
3. Provide an implementation schedule of the time needed to conduct and
implement the results of the communications assessment.
CPNPP Units 3 and 4 Response
With respect to the onsite communications system aspects of SECY-12-0025
(Reference 1B-5) Enclosure 7 Recommendation 9.3 (Communications section)
provision 1, CPNPP Units 3 and 4 incorporates by reference the design changes
in the US-APWR DCD to enhance emergency preparedness for a beyond designbasis (BDB) external event associated with simultaneous loss of all ac power as
described in the US-APWR DCD Subsections 9.5.2.1.1, 9.5.2.2.2.4, 9.5.2.2.3 and
9.5.2.6.
1B-17
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 1.9(6)
Offsite communications system aspects of provision 1 are described in CPNPP
Units 3 and 4 FSAR Subsections 9.5.2.2.2.2 and 9.5.2.2.5.1.
The request for interim actions of provision 2 is not applicable to CPNPP Units 3
and 4 because the actions associated with this recommendation will be completed
prior to initial fuel load.
Provision 3, offsite communications improvements identified by this evaluation
that are applicable to CPNPP Units 3 and 4 will be implemented prior to full
participation exercise milestone (see Table 1B-202 item 8).
1B.9.3.1.2
NTTF 9.3.1.2 - Emergency preparedness regulatory actions
(staffing) (Tier 1)
The Section on Staffing in Enclosure 7 to SECY-12-025 (Reference 1B-5)
requested the following information from licensees:
1. Provide an assessment of the on-site and augmented staff needed to respond
to a large scale natural event meeting the conditions described above. This
assessment should include a discussion of the on-site and augmented staff
available to implement the strategies as discussed in the emergency plan
and/or described in plant operating procedures. The following functions are
requested to be assessed:
•
How on-site staff will move back-up equipment (e.g., pumps, generators)
from alternate on-site storage facilities to repair locations at each reactor
as described in the order regarding the NTTF Recommendation 4.2. It is
requested that consideration be given to the major functional areas of
NUREG-0654, Table B-1 such as plant operations and assessment of
operational aspects, emergency direction and control, notification/
communication, radiological accident assessment, and support of
operational accident assessment, as appropriate.
•
New staff or functions identified as a result of the assessment.
•
Collateral duties (personnel not being prevented from timely performance
of their assigned functions).
2. Provide an implementation schedule of the time needed to conduct the onsite
and augmented staffing assessment. If any modifications are determined to be
appropriate, please include in the schedule the time to implement the
changes.
3. Identify how the augmented staff would be notified given degraded
communications capabilities.
1B-18
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
4. Identify the methods of access (e.g., roadways, navigable bodies of water and CTS-01532
dockage, airlift, etc.) to the site that are expected to be available after a
widespread large scale natural event.
5. Identify any interim actions that have been taken or are planned prior to the
completion of the staffing assessment.
6. Identify changes that have been made or will be made to your emergency plan
regarding the on-shift or augmented staffing changes necessary to respond to
a loss of all ac power, multi-unit event, including any new or revised
agreements with offsite resource providers (e.g., staffing, equipment,
transportation, etc.).
CPNPP Units 3 and 4 Response
CP COL 1.9(7)
With respect to provisions 1, 2, 3, 4 and 6 of SECY-12-0025 (Reference 1B-5)
Enclosure 7 Recommendation 9.3 (Staffing section), CPNPP Units 3 and 4 FSAR
Section 13.3 states that the staffing evaluation will be completed in accordance
with the NEI 12-01 and its findings implemented including any needed
modifications, and the evaluation results submitted to the NRC before the full
participation exercise (see Table 1B-202 item 3).
The request for interim actions described in provision 5 is not applicable to
CPNPP Units 3 and 4 because the actions associated with this recommendation
will be completed prior to initial fuel load.
1B.9.3.2
NTTF 9.3.2 - Emergency preparedness regulatory actions (Tier
2) (the remaining portions of Recommendation 9.3, with the
exception of Emergency Response Data System (ERDS)
capability addressed in Tier 3)
The NTTF Report made the following Recommendation:
9.3
Order licensees to do the following until rulemaking is complete:
•
Add guidance to the emergency plan that documents how to perform a
multiunit dose assessment (including releases from spent fuel pools)
using the licensee’s site-specific dose assessment software and
approach.
•
Conduct periodic training and exercises for multiunit and prolonged
SBO scenarios. Practice (simulate) the identification and acquisition of
offsite resources, to the extent possible.
•
Ensure that EP equipment and facilities are sufficient for dealing with
multiunit and prolonged SBO scenarios.
CPNPP Units 3 and 4 Response
1B-19
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CPNPP Units 3 and 4 have addressed this recommendation in NTTF 4.2 in
response to EA-12-049, provision (5).
1B.9.3.3
NTTF 9.3.3 - ERDS capability (related to long-term evaluation
Recommendation 10) (Tier 3)
The NTTF Report made the following Recommendation:
•
Maintain ERDS capability throughout the accident.
CPNPP Units 3 and 4 Response
CPNPP Units 3 and 4 comply with the recommendation by enhancing power
supply capability throughout the accident to plant communication systems,
including ERDS, as described in the US-APWR DCD Subsections 9.5.2.1.1 and
9.5.2.6, which are incorporated by reference.
1B.9.4
NTTF 9.4 - ERDS Modernization
The NTTF Report made the following Recommendation:
9.4
Order licensees to complete the ERDS modernization initiative by June
2012 to ensure multiunit site monitoring capability.
In SECY-11-0124 (Reference 1B-3), the NRC staff concluded that additional
regulatory action is not necessary at this time to ensure implementation of the
ERDS modernization.
CPNPP Units 3 and 4 Response
As the NRC staff concluded in SECY-11-0124 (Reference 1B-3), that additional
regulatory action is not necessary at this time, CPNPP Units 3 and 4 will not take
any action.
1B.10.0
NTTF 10.0 - Additional EP topics for prolonged SBO and multiunit
events (long-term evaluation) (Tier 3)
The NTTF Report made the following Recommendation:
The Task Force recommends, as part of the longer term review, that the NRC
should pursue additional EP topics related to multiunit events and prolonged SBO.
CPNPP Units 3 and 4 Response
See recommendations 10.1, 10.2 and 10.3 below.
1B-20
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
1B.10.1
NTTF 10.1 - Protective Equipment
CTS-01532
The NTTF Report made the following Recommendation:
10.1
Analyze current protective equipment requirements for emergency
responders and guidance based upon insights from the accident at
Fukushima.
CPNPP Units 3 and 4 Response
CPNPP Units 3 and 4 will comply with the new requirements, as necessary, once
they are issued.
1B.10.2
NTTF 10.2 - Command and Control
The NTTF Report made the following Recommendation:
10.2
Evaluate the command and control structure and the qualifications of
decisionmakers to ensure that the proper level of authority and oversight
exists in the correct facility for a long-term SBO or multiunit accident or
both.
CPNPP Units 3 and 4 Response
CPNPP Units 3 and 4 will comply with new requirements, as necessary, once they
are issued.
1B.10.3
NTTF 10.3 - Evaluate ERDS
The NTTF Report made the following Recommendation:
10.3
Evaluate ERDS to do the following:
•
Determine an alternate method (e.g., via satellite) to transmit ERDS
data that does not rely on hardwired infrastructure that could be
unavailable during a severe natural disaster.
•
Determine whether the data set currently being received from each site
is sufficient for modern assessment needs.
•
Determine whether ERDS should be required to transmit continuously
so that no operator action is needed during an emergency.
CPNPP Units 3 and 4 Response
CPNPP Units 3 and 4 will comply with new requirements, as necessary, once they
are issued.
1B-21
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
1B.11.0
NTTF 11.0 - EP topics for decision-making, radiation monitoring,
and public education (long-term evaluation) (Tier 3)
The NTTF Report made the following Recommendation:
The Task Force recommends, as part of the longer term review, that the NRC
should pursue EP topics related to decisionmaking, radiation monitoring, and
public education.
CPNPP Units 3 and 4 Response
See recommendations 11.1, 11.2, 11.3 and 11.4 below.
1B.11.1
NTTF 11.1 - Enhanced Onsite Resources
The NTTF Report made the following Recommendation:
11.1
Study whether enhanced onsite emergency response resources are
necessary to support the effective implementation of the licensees’
emergency plans, including the ability to deliver the equipment to the site
under conditions involving significant natural events where degradation of
offsite infrastructure or competing priorities for response resources could
delay or prevent the arrival of offsite aid.
CPNPP Units 3 and 4 Response
CPNPP Units 3 and 4 will comply with new requirements, as necessary, once they
are issued.
1B.11.2
NTTF 11.2 - Decisionmaking Framework
The NTTF Report made the following Recommendation:
11.2
Work with FEMA, States, and other external stakeholders to evaluate
insights from the implementation of EP at Fukushima to identify potential
enhancements to the U.S. decisionmaking framework, including the
concepts of recovery and reentry.
CPNPP Units 3 and 4 Response
CPNPP Units 3 and 4 will comply with new requirements, as necessary, once they
are issued.
1B.11.3
NTTF 11.3 - Real-time Radiation Monitoring
The NTTF Report made the following Recommendation:
1B-22
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
11.3
Study the efficacy of real-time radiation monitoring onsite and within the
EPZs (including consideration of ac independence and real-time
availability on the Internet).
CPNPP Units 3 and 4 Response
CPNPP Units 3 and 4 will comply with new requirements, as necessary, once they
are issued.
1B.11.4
NTTF 11.4 - Training
The NTTF Report made the following Recommendation:
11.4
Conduct training, in coordination with the appropriate Federal partners, on
radiation, radiation safety, and the appropriate use of KI in the local
community around each nuclear power plant.
CPNPP Units 3 and 4 Response
CPNPP Units 3 and 4 will comply with new requirements, as necessary, once they
are issued.
1B.12.0
NTTF 12.0 - NRC Reactor Oversight Process and Staff Training
The NTTF Report made the following Recommendation:
The Task Force recommends that the NRC strengthen regulatory oversight of
licensee safety performance (i.e., the ROP) by focusing more attention on
defense-in-depth requirements consistent with the recommended
defense-in-depth framework.
CPNPP Units 3 and 4 Response
See recommendations 12.1 and 12.2 below.
1B.12.1
NTTF 12.1 - Reactor Oversight Process modifications to reflect
the recommended defense-in-depth framework (dependent on
Recommendation 1) (Tier 3)
The NTTF Report made the following Recommendation:
12.1
Expand the scope of the annual ROP self assessment and biennial ROP
realignment to more fully include defense-in-depth considerations.
The NRC staff proposed in SECY-12-0095 (Reference 1B-6) that the staff would
defer action on Recommendation 12.1 until the Commission has provided staff
guidance regarding Recommendation 1.
1B-23
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CPNPP Units 3 and 4 Response
CTS-01532
As the NRC staff proposed in SECY-12-0095 that the staff would defer action on
Recommendation 12.1 until the Commission has provided staff guidance
regarding Recommendation 1, CPNPP Units 3 and 4 takes no action.
1B.12.2
NTTF 12.2 - Staff training on severe accidents, resident inspector
training on SAMGs (dependent on Recommendation 8) (Tier 3)
The NTTF Report made the following Recommendation:
12.2
Enhance NRC staff training on severe accidents, including training
resident inspectors on SAMGs.
CPNPP Units 3 and 4 Response
As this recommendation is applicable only to the NRC, CPNPP Units 3 and 4
takes no action.
1B.13
Additional Recommendations
1B.13.1
Additional Recommendation 3 Basis of Emergency Planning
Zone Size
In SECY-12-0095, NRC staff proposed the following plan:
The staff plans a longer-term action that is already being evaluated by existing
activities. The staff will use insights from the current Level 3 PRA study as well as
information obtained from the United Nations Scientific Committee on the Effects
of Atomic Radiation (UNSCEAR) assessment to inform the evaluation of the
potential impacts that a multiunit event may have on the EPZ. Such insights would
be primarily related to understanding the sensitivity of the calculated offsite health
consequences to various modeling assumptions.
The staff will use the results of the Level 3 PRA and the UNSCEAR assessment to
inform the process of evaluating the EPZ basis.
CPNPP Units 3 and 4 Response
As this recommendation is applicable only to the NRC, CPNPP Units 3 and 4
takes no action.
1B.13.2
Additional Recommendation 4 Prestaging of Potassium Iodide
beyond 10 miles
In SECY-12-0095, NRC staff proposed the following plan:
1B-24
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
The issue of whether KI should be distributed beyond the 10-mile EPZ will be
CTS-01532
evaluated within ongoing efforts to address issues surrounding the use of KI. The
staff plans to review information obtained from studies proposed by the Japanese
Government and will propose any changes to policy regarding KI.
Using existing resources, the staff will continue to monitor and evaluate the
population health studies proposed by the Japanese Government.
CPNPP Units 3 and 4 Response
As this recommendation is applicable only to the NRC, CPNPP Units 3 and 4
takes no action.
1B.13.3
Additional Recommendation 5 Transfer of Spent Fuel to Dry Cask
Storage
In SECY-12-0095, NRC staff proposed the following plan:
The staff plans to undertake the following activities:
•
Complete research including the SFPSS (Spent Fuel Pool Scoping Study),
human reliability analysis for mitigation, and effects associated with
increased fuel handling activities associated with loading and movement of
casks to enhance its understanding of spent fuel safety.
•
Evaluate the research stated above and other lessons learned from Tier 1
and 2 items on the staff’s current understanding of spent fuel safety in
accordance with the Commission Safety Goals and existing NRC studies
and analyses.
•
Gather stakeholder input, including from both the ACRS and public, on the
results of its research and any potential regulatory actions.
-
Develop a regulatory analysis for any potential new or revised
regulatory action.
-
Provide a recommendation on the need for any regulatory action to the
Commission.
The staff does not currently have sufficient information regarding the scope of all
of the additional research needed to develop a detailed schedule with milestones.
CPNPP Units 3 and 4 Response
As this recommendation is applicable only to the NRC, CPNPP Units 3 and 4
takes no action.
1B-25
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
1B.14
References
1B-1
SECY-11-0032, Consideration of Cumulative Effects of Regulation in
the Rulemaking Process, March 2, 2011.
1B-2
SECY-11-0093, Near-Term Report and Recommendation for Agency
Actions Following the Events in Japan, July 12, 2011.
1B-3
SECY-11-0124, Recommended Actions to be Taken Without Delay
from the Near-term Task Force Report, September 9, 2011.
1B-4
SECY-11-0137, Prioritization of Recommended Actions to Be Taken in
Response to Fukushima Lessons Learned, October 3, 2011.
1B-5
SECY-12-0025, Proposed Orders and Requests for Information in
Response to Lessons Learned from Japan’s March 11, 2011, Great
Tohoku Earthquake and Tsunami, February 17, 2012.
1B-6
SECY-12-0095, Tier 3 Program Plans and 6-Month Status Update in
Response to Lessons Learned from Japan’s March 11, 2011, Great
Tohoku Earthquake and Subsequent Tsunami, July 13, 2012.
1B-7
Order EA-12-049, Issuance of Order to Modify Licenses with Regard to
Requirements for Mitigation Strategies for Beyond-Design-Basis
External Events, March 12, 2012.
1B-8
Order EA-12-051, Order Modifying Licenses With Regard to Reliable
Spent Fuel Pool Instrumentation, March 12, 2012.
1B-9
NRC Request for Information Pursuant to 50.54(f) Recommendations
2.1, 2.3, and 9.3, March 12, 2012.
1B-10
Request for Additional Information No. 6527, COLA, Revision 2, RAI
Letter Number 261, June 25, 2012.
1B-11
Request for Additional Information No. 6929, COLA, Revision 2, RAI
Letter Number 269, December 13, 2012.
1B-12
MUAP-13002, US-APWR Evaluation and Design Enhancement to
Incorporate Lessons Learned from TEPCO's Fukushima Dai-ichi
Nuclear Power Station Accident, Rev.0, March 2013.
CTS-01532
1B-26
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CTS-01532
Table 1B-201 (Sheet 1 of 7)
Cross Reference to Standard Plant
NTTF
No.
Description
FSAR Section
DCD Section
MUAP-13002
Section
1.0
Clarify the Regulatory Framework
1B.1.0
----
----
1.1
Draft a Commission policy statement that
articulates a risk-informed defense-in-depth
framework that includes extended design-basis
requirements in the NRC’s regulations as
essential elements for ensuring adequate
protection.
1B.1.1
----
----
1.2
Initiate rulemaking to implement a risk-informed,
defense-in-depth framework consistent with the
above recommended Commission policy
statement.
1B.1.2
----
----
1.3
Modify the Regulatory Analysis Guidelines to
more effectively implement the defense-in-depth
philosophy in balance with the current emphasis
on risk-based guidelines.
1B.1.3
----
----
1.4
Evaluate the insights from the IPE and IPEEE
efforts as summarized in NUREG-1560,
“Individual Plant Examination Program:
Perspectives on Reactor Safety and Plant
Performance,” issued December 1997, and
NUREG-1742, “Perspectives Gained from the
Individual Plant Examination of External Events
(IPEEE) Program,” issued April 2002, to identify
potential generic regulations or plant-specific
regulatory requirements.
1B.1.4
----
----
1B-27
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 1B-201 (Sheet 2 of 7)
Cross Reference to Standard Plant
NTTF
No.
Description
FSAR Section
CTS-01532
DCD Section
MUAP-13002
Section
2.0
Seismic and Flooding Protection
1B.2.0
----
----
2.1
Seismic and flood hazard reevaluations
1.9.5.2
1B.2.1
Table 2.0-1R
2.3.1.2
2.4.2
2.4.3
2.5.2
3.4.1.2
3.4.1.4
1.9.5.2
1.9.6
Table 1.9.5-8
5.1.1
5.3.1
5.3.2
2.2
Ten-year confirmation of seismic and flooding
hazards
1.9.5.2
1B.2.2
1.9.5.2
Table 1.9.5-8
5.3.3
2.3
Seismic and Flooding Walkdowns
1B.2.3
----
5.3.4
2.3.1
Seismic Walkdowns
1B.2.3.1
----
5.3.4
2.3.2
Flooding Walkdowns
1B.2.3.2
----
5.3.4
3.0
Potential enhancements to the capability to
prevent or mitigate seismically induced fires and
floods (long-term evaluation)
1B.3.0
----
5.3.5
4.0
Station Blackout Mitigation
1B.4.0
----
----
4.1
Station blackout regulatory actions
1.9.5.2
1B.4.1
1.9.5.2
Table 1.9.5-8
5.1.2
1B-28
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 1B-201 (Sheet 3 of 7)
Cross Reference to Standard Plant
NTTF
No.
Description
FSAR Section
CTS-01532
DCD Section
MUAP-13002
Section
4.2
Equipment covered under Title 10 of the Code of
Federal Regulations (10CFR) 50.54(hh)(2) Mitigation Strategies for Beyond-Design-Basis
External Events
1.9.5.2
1B.4.2
3.4.1.2
3.4.1.4
13.2.1.1.4
13.5.2.1
13.5.2.2
1.9.5.2
Table 1.9.5-5
Table 1.9.5-8
1.9.6
5.1.2
6.1
6.3
6.4
6.5
6.6
6.7.3
6.8
6.9.2
5.0
Containment Hardened Vents
1B.5.0
----
----
5.1
Reliable hardened vents for Mark I and Mark II
containments
1.9.5.2
1B.5.1
1.9.5.2
Table 1.9.5-8
5.3.6
5.2
Reliable hardened vents for other containment
designs (long-term evaluation)
1B.5.2
----
5.3.7
6.0
Hydrogen control and mitigation inside
containment or in other buildings (long-term
evaluation)
1B.6.0
----
5.3.8
7.0
Spent fuel pool makeup capability and
instrumentation
1B.7.0
----
----
7.1
Spent Fuel Pool Instrumentation
1.9.5.2
1B.7.1
13.2.1.1.4
13.5.2.2
Table 13.4-201
1.9.5.2
Table 1.9.5-6
Table 1.9.5-8
1.9.6
5.1.3
6.7.1
6.7.2
1B-29
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 1B-201 (Sheet 4 of 7)
Cross Reference to Standard Plant
NTTF
No.
Description
FSAR Section
CTS-01532
DCD Section
MUAP-13002
Section
7.2
Order licensees to provide safety-related ac
electrical power for the spent fuel pool makeup
system.
1.9.5.2
1B.7.2
1.9.5.2
Table 1.9.5-8
5.2.1
7.3
Order licensees to revise their technical
specifications to address requirements to have
one train of onsite emergency electrical power
operable for spent fuel pool makeup and spent
fuel pool instrumentation when there is irradiated
fuel in the spent fuel pool, regardless of the
operational mode of the reactor.
1.9.5.2
1B.7.3
1.9.5.2
Table 1.9.5-8
5.2.1
7.4
Order licensees to have an installed seismically
1.9.5.2
qualified means to spray water into the spent fuel 1B.7.4
pools, including an easily accessible connection
to supply the water (e.g., using a portable pump or
pumper truck) at grade outside the building.
1.9.5.2
Table 1.9.5-8
5.2.1
7.5
Initiate rulemaking or licensing activities or both to 1.9.5.2
require the actions related to the spent fuel pool
1B.7.5
described in detailed recommendations 7.1–7.4.
1.9.5.2
Table 1.9.5-8
5.2.1
8.0
Strengthening and integration of emergency
operating procedures, severe accident
management guidelines (SAMGs), and extensive
damage mitigation guidelines
1.9.5.2
1B.8.0
13.5.2.1
13.5.2.2
1.9.5.2
Table 1.9.5-8
1.9.6
5.1.4
6.9.1
8.1
Orders to Integrate Programs and Guidance
1B.8.1
----
----
8.2
Standard Technical Specification Administrative
Controls
1B.8.2
----
----
1B-30
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 1B-201 (Sheet 5 of 7)
Cross Reference to Standard Plant
NTTF
No.
Description
FSAR Section
CTS-01532
DCD Section
MUAP-13002
Section
8.3
Licensee Technical Specifications
1B.8.3
----
----
8.4
Realistic Training and Exercises
1B.8.4
----
----
9.0
Emergency Plans for Prolonged SBO and
Multiunit Events
1B.9.0
----
----
9.1
Emergency preparedness (EP) enhancements for 1B.9.1
prolonged station blackout (SBO) and multiunit
events (dependent on availability of critical skill
sets)
----
5.3.9
9.2
Emergency preparedness (EP) enhancements for 1B.9.2
prolonged station blackout (SBO) and multiunit
events (dependent on availability of critical skill
sets)
----
5.3.10
9.3
Emergency preparedness regulatory actions
1B.9.3
----
5.2.2
9.3.1
Emergency preparedness regulatory actions
(communication and staffing)
1.9.5.2
1B.9.3.1
----
5.1.5
9.3.1.1 Emergency preparedness regulatory actions
(communication)
1.9.5.2
1B.9.3.1.1
9.5.2.2.2.2
9.5.2.2.5.1
1.9.5.2
Table 1.9.5-7
Table 1.9.5-8
1.9.6
5.1.5.1
6.10.1
9.3.1.2 Emergency preparedness regulatory actions
(staffing)
1.9.5.2
1B.9.3.1.2
13.3.2
13.3.5
1.9.5.2
Table 1.9.5-7
Table 1.9.5-8
1.9.6
5.1.5.2
6.10.2
9.3.2
1B.9.3.2
----
5.2.2
Emergency preparedness regulatory actions
1B-31
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 1B-201 (Sheet 6 of 7)
Cross Reference to Standard Plant
NTTF
No.
Description
FSAR Section
CTS-01532
DCD Section
MUAP-13002
Section
9.3.3
ERDS capability (related to long-term evaluation
Recommendation 10)
1B.9.3.3
9.5.2.1.1
9.5.2.6
5.3.11
9.4
ERDS Modernization
1B.9.4
----
----
10.0
Additional EP topics for prolonged SBO and
multiunit events (long-term evaluation)
1B.10.0
----
5.3.12
10.1
Protective Equipment
1B.10.1
----
----
10.2
Command and Control
1B.10.2
----
----
10.3
Evaluate ERDS
1B.10.3
----
----
11.0
EP topics for decision-making, radiation
monitoring, and public education (long-term
evaluation)
1B.11.0
----
5.3.13
11.1
Enhanced Onsite Resources
1B.11.1
----
----
11.2
Decisionmaking Framework
1B.11.2
----
----
11.3
Real-time Radiation Monitoring
1B.11.3
----
----
11.4
Training
1B.11.4
----
----
12.0
NRC Reactor Oversight Process and Staff
Training
1B.12.0
----
----
12.1
Reactor Oversight Process modifications to reflect 1B.12.1
the recommended defense-in-depth framework
(dependent on Recommendation 1)
----
5.3.14
1B-32
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 1B-201 (Sheet 7 of 7)
Cross Reference to Standard Plant
NTTF
No.
Description
FSAR Section
CTS-01532
DCD Section
MUAP-13002
Section
12.2
Staff training on severe accidents, resident
inspector training on SAMGs (dependent on
Recommendation 8)
1B.12.2
----
5.3.15
AR 3
Basis of Emergency Planning Zone Size
1B.13.1
----
5.3.16
AR 4
Prestaging of Potassium Iodide beyond 10 miles
1B.13.2
----
5.3.17
AR 5
Transfer of Spent Fuel to Dry Cask Storage
1B.13.3
----
5.3.18
Notes:
1. The cross-referenced sections of the DCD and MUAP-13002 frequently reference additional sections of the DCD or
MUAP. This table does not capture these additional cross-references.
2. The COL Items related to Fukushima responses are provided in DCD Subsection 1.9.6.
3. DCD references are Tier 2 unless noted otherwise.
1B-33
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CTS-01532
Table 1B-202 (Sheet 1 of 3)
Summary of Post-COL Commitment and Programs for NTTF Recommendations
Item
Description
Source
FSAR Section
Implementation
Milestone
Implementation
Requirement
1
Site-specific strategies NTTF 4.0, 4.1, 4.2
to mitigate beyond
EA-12-049
design basis external
NEI 12-06
events including:
- Protection of
portable equipment
- Acquisition, staging,
or installing of
equipment
- Maintenance and
testing of portable
equipment
- Procedures and
guidance and
training on
mitigation of BDB
external events
1B.4.0
1B.4.1
1B.4.2
1B 9.3.2
13.2.1.1.4
13.5.2.1
13.5.2.2
Prior to initial fuel License
load
Condition
RAI 6929
(CP RAI #269)
2
SFP level
instrumentation
maintenance
procedure
development and
perform training.
1B.7.1
13.2.1.1.4
13.5.2.2
Table 13.4-201
18 months prior
to initial fuel load
NTTF 7.1
EA-12-051
NEI 12-02
Commitment for
procedures
RAI 6527
(CP RAI #261)
Question 01.05-2
See Table 13.4201, item 12, for
training (License
Condition)
1B-34
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 1B-202 (Sheet 2 of 3)
Summary of Post-COL Commitment and Programs for NTTF Recommendations
Item
Description
Source
FSAR Section
CTS-01532
Implementation
Milestone
Implementation
Requirement
3
Staffing assessment
NTTF 9.3 Item 1
regarding onsite and
SECY-12-0025
augmented staffing to
NEI 12-01
address a BDB
external event.
Complete assessment,
implement results and
submit report to NRC.
1B.9.3.1.2
13.3.2
13.3.5
Prior to first full
participation
exercise
License
Condition
RAI 6527
(CP RAI #261)
Question 01.05-3
4
Procedures and
guidance and training
on mitigation of
beyond-design-basis
external events.
NTTF 4.2
EA-12-049 Item 5
13.2.1.1.4
13.5.2.2
Prior to first full
participation
exercise
Commitment
5
Develop EOPs,
SAMGs and EDMGs
which incorporate
lessons learned from
TEPCO’s
Fukushima-Daiichi
Nuclear Power Plant
Accident.
NTTF 8
13.5.2.1
13.5.2.2
Prior to first full
participation
exercise
Commitment
1B-35
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 1B-202 (Sheet 3 of 3)
Summary of Post-COL Commitment and Programs for NTTF Recommendations
Item
Description
Source
FSAR Section
CTS-01532
Implementation
Milestone
Implementation
Requirement
Commitment
6
Submit a Flex
Integrated Plan to the
NRC that will be
consistent with the
design of the
US-APWR, the
US-APWR Fukushima
technical document,
and the guidance
provided by
JLD-ISG-2012-01 and
NEI 12-06.
Item 5 of Attachment
2 to EA-12-049
NA
At least six
months prior to
the first full
participation
exercise
7
Submit a final report to
the NRC confirming full
compliance with Item 5
of Attachment 2 to
Order EA-12-049.
Letter TXNB-13001
[ML13022A107],
dated January 17,
2013
NA
Prior to initial fuel Commitment
load
8
Conduct and
implement the results
of a communications
assessment.
NTTF 9.3
Item 1
9.5.2.2.2.2
9.5.2.2.5.1
Prior to first full
participation
exercise
1B-36
Commitment
Revision 3
Chapter 2
Chapter 2 Tracking Report Revision List
Change ID No.
Section
FSAR
Rev. 3
Page
RCOL2_03.03.02-9
Table 2.0-1R
(Sheet[s] 1, [2]
of 13)
2.0-2
[2.0-2,
2.0-3]
2.3.1.2.2
2.3-13
2.3.2.3
2.3-37
CTS-01514
Table 2.0-1R
(Sheets 3,
4,5,6 of 13)
CTS-01514
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
-
Response to
RAI No. 250
Luminant Letter
no.TXNB-12032
Date
09/14/2012
Revised to
incorporate RG
1.221.
2.0-4
2.0-5
2.0-6
2.0-7
Consistency
with DCD as
described in
Letter. TXNB12033
(ML12268A413)
Updated to reflect
revised X/Q values.
0
Table 2.3-338
(Sheets 1,3 of
3)
2.3-244
2.3-246
Consistency
with DCD as
described in
Letter. TXNB12033
(ML12268A413)
Updated to reflect
revised source and
receptor locations.
0
CTS-01514
Table 2.3-339
(Sheet 1 of 2)
2.3-247
Consistency
with DCD as
described in
Letter. TXNB12033
(ML12268A413)
Updated to reflect
revised X/Q values.
0
CTS-01513
Figure
2.1-201
2.3-380
Consistency
with DCD as
described in
Letter. TXNB12033
(ML12268A413)
Updated to reflect
standard plant and
site-specific layout.
0
4th
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
Section was revised
to reflect new
acronyms and
abbreviations used
in the groundwater
elevation and
pathways analysis
description.
-
RCOL2_02.04.12-9
S04
Acronyms and
Abbreviations
-
2-lxi
2-lxv
2-lxvi
2_1
Change ID No.
Section
RCOL2_02.04.12-9
S04
Table 2.0-1R
(Sheet 8 of 13)
RCOL2_02.04.12-9
S04
Reason for
change
Change Summary
2.0-9
4th
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
Table updated to
describe sitespecific groundwater
levels.
2.4.12.3
2.4-78
2.4-79
2.4-79
through
2.4-82
Section was revised
to reflect updates to
the maximum
groundwater
elevation and
pathways.
-
2.4.12.3.1
2.4.12.3.1.1
2.4-82
through
2.4-85
4th
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
2.4.12.3.1.1.1
(New
Subsection)
2.4.12.3.1.1.2
(New
Subsection)
2.4.12.3.1.1.3
(New
Subsection)
FSAR
Rev. 3
Page
Rev.
of
FSAR
T/R
-
2.4-85
2.4.12.5
2.4-86
through
2.4-88
RCOL2_02.04.12-9
S04
Table 2.4.12208 (Sheets 1,
2 of 2)
2.4-230
2.4-231
4th
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
Table was revised to
reflect updates to
the groundwater
monitoring wells
installation details.
-
RCOL2_02.04.12-9
S04
Table 2.4.12211
2.4-239
4th
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
Table was revised to
reflect
updatedresults of
the groundwater
pathways analysis.
-
2_2
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
-
RCOL2_02.04.12-9
S04
Figure 2.4.12212
-
4th
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
Figure was revised
to reflect updated
results of the
groundwater
pathways analysis.
RCOL2_02.04.12-9
S04
Figure 2.4.12213
-
4th
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
Figure was revised
to reflect updated
results of the
groundwater
pathways analysis.
-
RCOL2_02.04.12-9
S04
Figure 2.4.12214
-
4th
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
Figure was revised
to reflect updated
vertical release
pathway.
-
RCOL2_02.04.12-9
S04
Figure 2.4.12215
-
4th
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
Figure was updated
to show
comparisonbetween
pre and post
construction surface
topography.
-
RCOL2_02.04.12-9
S04
Figure 2.4.12216
-
4th
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
Figure was added to
show cut and
engineered fill
buildup areas.
-
RCOL2_02.04.12-9
S04
Figure 2.4.12217
-
4th
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
Figure was updated
to reflect the
updated postconstruction
groundwater
conceptual model.
-
2_3
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
-
RCOL2_02.04.12-9
S04
Figure 2.4.12218
-
4th
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
Figure was added
showing postconstruction surface
topography.
RCOL2_02.04.12-9
S04
Figure 2.4.12219 (Sheets 1,
2 of 2)
-
4th
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
Figure was added to
show MODFLOW
model grid.
-
RCOL2_02.04.12-9
S04
Figure 2.4.12220
-
4th
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
Figure was added to
reflect results of the
groundwater
pathways analysis.
-
RCOL2_02.04.1212 S01
Acronyms and
Abbreviations
2-lxvi
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
-
RCOL2_02.04.1212 S01
2.4.12.2.4
2.4-73
through
2.4-76
2.4.12.5
2.4-86
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
Section was revised
to reflect new
acronyms and
abbreviations used
in the groundwater
elevation and
pathways analysis
description.
Sections were
updated to reflect
updated
groundwater well
monitoring results.
Table 2.4.12209 (Sheets 1
through 3 of 3)
2.4-232
through
2.4-234
Table was revised to
reflect
updatedgroundwater
monitoring results.
-
RCOL2_02.04.1212 S01
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
2_4
-
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
-
RCOL2_02.04.1212 S01
Table 2.4.12213 (New
Table)
2.4-240
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
Table was added to
show average rate
of rise in nonequilibrium
groundwater
monitoring wells.
RCOL2_02.04.1212 S01
Figure 2.4.12208
-
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
Figure was update
to reflect new site
layout and plot plan.
-
RCOL2_02.04.1212 S01
Figure 2.4.12209 (Sheets 1
through 20 of
20)
-
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
Figure was updated
to reflect latest
groundwater
monitoring results
(adding 40 more
sheets)
-
RCOL2_02.04.1212 S01
Figure 2.4.12210 (Sheets 1
through 4 of 4)
-
Supplemental
Response to
RAI No. 147
Luminant Letter
no.TXNB-13013
Date 4/29/2013
-
CTS-01521
Table 2.0-1R
(Sheet 9 of 13
[10 of 13])
2.0-10
[2.0-11]
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
Figure was updated
to reflect new site
layout and plot plan
and updated
groundwater
monitoring results
(adding 2 more
sheets)
Updated table entry
to reflect revisions to
Section 2.5
2_5
1
Change ID No.
Section
FSAR
Rev. 3
Page
CTS-01521
2.5.1
2.5-2
CTS-01521
2.5.1.1.4
2.5-16
CTS-01521
2.5.1.1.4.2
2.5-20
[2.5-21]
Reason for
change
Change Summary
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
Section was revised
due to CEUS and
CPNPP layout
update.
2_6
Rev.
of
FSAR
T/R
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
CTS-01521
2.5.1.1.4.2.3
2.5-23
CTS-01521
2.5.1.1.4.3
2.5-23
[2.5-24]
CTS-01521
2.5.1.1.4.3.4.2
2.5-28
through
2.5-29
Reason for
change
Change Summary
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
Section was revised
due to CEUS and
CPNPP layout
update.
2_7
Rev.
of
FSAR
T/R
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
CTS-01521
2.5.1.1.4.3.6
2.5-30
CTS-01521
2.5.1.1.4.3.6.1
2.5-30
[2.5-31]
CTS-01521
2.5.1.1.4.3.6.1.
1
through
2.5.1.1.4.3.6.1.
2
2.5-31
through
2.5-40
Reason for
change
Change Summary
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
Section was revised
due to CEUS and
CPNPP layout
update.
2_8
Rev.
of
FSAR
T/R
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
CTS-01521
2.5.1.1.4.3.6.2
2.5-40
through
2.5-41
Section was revised
due to CEUS and
CPNPP layout
update.
CTS-01521
2.5.1.1.4.3.7
2.5-41
CTS-01521
2.5.1.1.4.3.7.1
2.5-41
through
2.5-42
[2.5-43]
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
2_9
Rev.
of
FSAR
T/R
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
CTS-01521
2.5.1.1.4.3.7.2
2.5-43
CTS-01521
2.5.1.1.4.3.7.3
2.5-43
through
2.5-44
[2.5-45]
CTS-01521
2.5.1.2.5.1
2.5-55
[2.5-56]
Reason for
change
Change Summary
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
Section was revised
due to CEUS and
CPNPP layout
update.
2_10
Rev.
of
FSAR
T/R
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
CTS-01521
2.5.1.2.5.2
2.5-56
CTS-01521
2.5.1.2.5.6
2.5-58
[2.5-59]
CTS-01521
2.5.1.2.5.10.1
2.5-60
[2.5-61]
Reason for
change
Change Summary
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
Section was revised
due to CEUS and
CPNPP layout
update.
2_11
Rev.
of
FSAR
T/R
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
CTS-01521
2.5.1.2.5.10.2.3
2.5-64
[2.5-65]
Section was revised
due to CEUS and
CPNPP layout
update.
CTS-01521
2.5.1.2.5.10.3
2.5-64
[2.5-65]
CTS-01521
Figure 2.5.1213
-
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
2_12
Rev.
of
FSAR
T/R
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Figure was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
CTS-01521
Figure 2.5.1215
-
CTS-01521
Figure 2.5.1230
-
CTS-01521
2.5.2
2.5-66
Reason for
change
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
2_13
Change Summary
Figure was revised
due to CEUS and
CPNPP layout
update.
Rev.
of
FSAR
T/R
1
Figure was revised
due to CEUS and
CPNPP layout
update.
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
Section was revised
due to CEUS and
CPNPP layout
update.
CTS-01521
2.5.2
2.5-67
[2.5-68]
CTS-01521
2.5.2.1
2.5-68
CTS-01521
2.5.2.1.1
2.5-68
2.5-69
2_14
Rev.
of
FSAR
T/R
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
Section was revised
due to CEUS and
CPNPP layout
update.
CTS-01521
2.5.2.1.2
2.5-69
through
2.5-71
[2.5-72
through
2.5-74]
CTS-01521
2.5.2.1.3
2.5-71
[2.5-74]
CTS-01521
2.5.2.1.3.1
2.5-72
2.5-73
[2.5-74
through
2.5-77]
2_15
Rev.
of
FSAR
T/R
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
Section was revised
due to CEUS and
CPNPP layout
update.
CTS-01521
2.5.2.1.3.2
2.5-73
through
2.5-75
[2.5-77
through
2.5-80]
CTS-01521
2.5.2.2
2.5-75
through
2.5-77
[2.5-80
through
2.5-82]
CTS-01521
2.5.2.2.1
2.5-77,
2.5-78
[2.5-82
through
2.5-84]
2_16
Rev.
of
FSAR
T/R
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
Section was revised
due to CEUS and
CPNPP layout
update.
CTS-01521
2.5.2.2.1.1
2.5-78,
2.5-79
[2.5-84
through
2.5-85]
CTS-01521
2.5.2.2.1.2
2.5-79,
2.5-80
[2.5-85
through
2.5-87]
CTS-01521
2.5.2.2.1.3
2.5-80
2.5-81
[2.5-87
2.5-88]
2_17
Rev.
of
FSAR
T/R
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
Section was revised
due to CEUS and
CPNPP layout
update.
CTS-01521
2.5.2.2.1.4
through
2.5.2.2.2.6
2.5-81
through
2.5-84
[2.5-88
through
2.5-99]
CTS-01521
2.5.2.3
2.5-93
2.5-94
[2.5-99
through
2.5-101]
CTS-01521
2.5.2.4
2.5-94
[2.5101]
2_18
Rev.
of
FSAR
T/R
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
Section was revised
due to CEUS and
CPNPP layout
update.
CTS-01521
2.5.2.4.1
2.5-94,
2.5-95
[2.5-101
through
2.5-102]
CTS-01521
2.5.2.4.2
2.5-95,
2.5-96
[2.5-102
2.5-103]
CTS-01521
2.5.2.4.2.1
2.5-96,
2.5-97
[2.5-103
through
2.5-104]
2_19
Rev.
of
FSAR
T/R
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
Section was revised
due to CEUS and
CPNPP layout
update.
CTS-01521
2.5.2.4.2.2
2.5-97
[2.5105 2.5105]
CTS-01521
2.5.2.4.2.2.1
through
2.5.2.4.2.3.4
2.5-97
through
2.5-113
[2.5-106
through
2.5-121]
CTS-01521
2.5.2.4.3
2.5-113,
2.5-114
[2.5-122
2.5-123]
2_20
Rev.
of
FSAR
T/R
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
Section was revised
due to CEUS and
CPNPP layout
update.
CTS-01521
2.5.2.4.4
2.5-114
through
2.5-117
[2.5-123
through
2.5-127]
CTS-01521
2.5.2.5
2.5-117,
2.5-118
[2.5127,
2.5-128]
CTS-01521
2.5.2.5.1
2.5-118,
2.5-119
[2.5-128
and 2.5129]
2_21
Rev.
of
FSAR
T/R
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
Section was revised
due to CEUS and
CPNPP layout
update.
CTS-01521
2.5.2.5.2.1
2.5-119,
2.5-120
[2.5-129
through
2.5-131]
CTS-01521
2.5.2.5.2.2
2.5-121
[2.5131]
CTS-01521
2.5.2.5.2.3
2.5-121
through
2.5-123
[2.5-132
through
2.5-134]
2_22
Rev.
of
FSAR
T/R
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
Section was revised
due to CEUS and
CPNPP layout
update.
CTS-01521
2.5.2.6.1
2.5-123
2.5-124
[2.5134,
2.5-135]
CTS-01521
2.5.2.6.1.1
2.5-124
Through
2.5-126
[2.5-135
through
2.5-137]
CTS-01521
2.5.2.6.1.2
2.5-126
[2.5138]
2_23
Rev.
of
FSAR
T/R
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
Section was revised
due to CEUS and
CPNPP layout
update.
CTS-01521
2.5.2.6.2
2.5-127
through
2.5-129
[2.5-139
through
2.5-142]
CTS-01521
2.5.2.6.2
(New
Subsection
2.5.2.6.3)
2.5-129
[2.5-143
through
2.5-144]
CTS-01521
2.5.3.1
2.5-130
2.5-131
[2.5145]
2.5-146]
2_24
Rev.
of
FSAR
T/R
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
Section was revised
due to CEUS and
CPNPP layout
update.
CTS-01521
2.5.3.2
2.5-131
Through
2.5-131
[2.5-146
2.5-147]
CTS-01521
2.5.3.3
2.5-134
[2.5149]
CTS-01521
2.5.7
2.4-242
2.5-246
2.5-249
Through
2.5-252
2.5-255
2.5-256
2.5-259
[2.5-257
2.5-261,
2.5-264
through
2.5-267,
2.5-270
2.5-271,
2.5-274,
2.5-275]
2_25
Rev.
of
FSAR
T/R
1
Section was revised
due to CEUS and
CPNPP layout
update.
1
Section was revised
to remove unused
references and due
to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
CTS-01521
Table 2.5.2201
2.5-299
through
2.5-304
[2.5-315
through
2.5-324]
CTS-01521
Table 2.5.2202
2.5-305
2.5-306
[2.5-325
through
2.5-328]
CTS-01521
Table 2.5.2203
2.5-307
2.5-308
[2.5-329
through
2.5-332]
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
2_26
Change Summary
Table was revised
due to CEUS and
CPNPP layout
update.
Rev.
of
FSAR
T/R
1
Table was revised
due to CEUS and
CPNPP layout
update.
1
Table was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
CTS-01521
Table 2.5.2204
2.5-309
[2.5-333
through
2.5-334]
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
Table was revised
due to CEUS and
CPNPP layout
update.
CTS-01521
Table 2.5.2205
2.5-310
[2.5-335
through
2.5-336]
Table was revised
due to CEUS and
CPNPP layout
update.
1
CTS-01521
Table 2.5.2206
2.5-311
[2.5-337
through
2.5-338]
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
Table was revised
due to CEUS and
CPNPP layout
update.
1
2_27
Change Summary
Rev.
of
FSAR
T/R
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
CTS-01521
Table 2.5.2207
2.5-312
2.5-313
[2.5-339
through
2.5-341]
CTS-01521
Table 2.5.2208
2.5-314
[2.5-342
through
2.5-343]
CTS-01521
Table 2.5.2209
2.5-315
[2.5-344
through
2.5-345]
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
2_28
Change Summary
Table was revised
due to CEUS and
CPNPP layout
update.
Rev.
of
FSAR
T/R
1
Table was revised
due to CEUS and
CPNPP layout
update.
1
Table was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
CTS-01521
Table 2.5.2210
2.5-316
[2.5-346
through
2.5-347]
CTS-01521
Table 2.5.2211
2.5-317
[2.5348]
CTS-01521
Table 2.5.2212
2.5-318
[2.5-349
through
2.5-355]
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
2_29
Change Summary
Table was revised
due to CEUS and
CPNPP layout
update.
Rev.
of
FSAR
T/R
1
Table was revised
due to CEUS and
CPNPP layout
update.
1
Table was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
CTS-01521
Table 2.5.2213
2.5-319
[2.5-356
through
2.5-357]
CTS-01521
Table 2.5.2214
2.5-320
2.5-321
[2.5-358
through
2.5-361]
CTS-01521
Table 2.5.2215
2.5-322
2.5-323
[2.5-362
through
2.5-365]
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
2_30
Change Summary
Table was revised
due to CEUS and
CPNPP layout
update.
Rev.
of
FSAR
T/R
1
Table was revised
due to CEUS and
CPNPP layout
update.
1
Table was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
CTS-01521
Table 2.5.2216
2.5-324
[2.5-366
through
2.5-368]
CTS-01521
Table 2.5.2217
2.5-325
[2.5-369
through
2.5-371]
CTS-01521
Table 2.5.2218
2.5-326
[2.5-372
through
2.5-374]
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
2_31
Change Summary
Table was revised
due to CEUS and
CPNPP layout
update.
Rev.
of
FSAR
T/R
1
Table was revised
due to CEUS and
CPNPP layout
update.
1
Table was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
CTS-01521
Table 2.5.2219
2.5-327
[2.5-375
through
2.5-377]
CTS-01521
Table 2.5.2220
2.5-328
[2.5378]
CTS-01521
Table 2.5.2221
2.5-329
[2.5-379
through
2.5-381]
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
2_32
Change Summary
Table was revised
due to CEUS and
CPNPP layout
update.
Rev.
of
FSAR
T/R
1
Table was revised
due to CEUS and
CPNPP layout
update.
1
Table was revised
due to CEUS and
CPNPP layout
update.
1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
CTS-01521
Table 2.5.2222
2.5-330
[2.5382]
CTS-01521
Table 2.5.2223
2.5-331
[2.5-383
through
2.5-385]
CTS-01521
Tables 2.5.2224 through
2.5.2-237
2.5-332
through
2.5-351
[2.5-386
through
2.5-405]
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
2_33
Change Summary
Table was revised
due to CEUS and
CPNPP layout
update.
Rev.
of
FSAR
T/R
1
Table was revised
due to CEUS and
CPNPP layout
update.
1
Tables were deleted
due to CEUS and
CPNPP layout
update.
1
Change ID No.
CTS-01521
Section
Figures 2.5.2201 through
259
FSAR
Rev. 3
Page
-
To reflect plant
layout changes
and inclusion of
EPRI-CEUS
Seismic
Catalog, as
described in
both the
Luminant ISCP
Letter
ML12268A41
and Fukushima
RAI 261
response
ML12207A599.
3rd
Supplemental
Response to
RAI No. 139
Luminant Letter
no.TXNB-13016
Date 5/13/2013
New Figures
2.5.2-260
through 277
Figures are
located in
UTR files 2,
3, and 4 of 4.
RCOL2_02.04.02-2
S03
Table 2.0-1R
(Sheet 8 of 13)
2.0-9
RCOL2_02.04.02-2
S03
2.4.2.1
2.4-18
2.4.2.2
2.4-18
through
2.4-20
2.4.2.3
2.4-21
through
2.4-25
2.4-26
RCOL2_02.04.02-2
S03
2.4.3
Reason for
change
2.4.3.1
2.4-27
2.4-28
2.4.3.3
2.4-29
through
2.4-31
2.4.3.4
2.4-31
2.4-32
2.4.3.5
2.4-32
2.4.3.6
2.4-33
3rd
Supplemental
Response to
RAI No. 139
Luminant Letter
no.TXNB-13016
Date 5/13/2013
3rd
Supplemental
Response to
RAI No. 139
Luminant Letter
no.TXNB-13016
Date 5/13/2013
2_34
Change Summary
Figures were
revised due to
CEUS and CPNPP
layout update.
Rev.
of
FSAR
T/R
1
Table revised to
update maximum
flood level.
-
Section revised to
update probable
maximum
precipitation (PMP),
probable maximum
flood (PMF), and
two year coincident
wind wave elevation
and its effects.
Section revised to
update water
elevation values and
regulation guidelines
referenced.
-
-
Change ID No.
RCOL2_02.04.02-2
S03
RCOL2_02.04.02-2
S03
RCOL2_02.04.02-2
S03
RCOL2_02.04.02-2
S03
Section
FSAR
Rev. 3
Page
Reason for
change
2.4.4.1
2.4-44
through
2.4-50
2.4.4.3
2.4-51
2.4-52
3rd
Supplemental
Response to
RAI No. 139
Luminant Letter
no.TXNB-13016
Date 5/13/2013
Section revised to
update breach flow
values and
overtopping
elevation
2.4.5
2.4-53
2.4-57
2.4.10
2.4-61
Section revised to
update PMF,
maximum flood
level, and elevation
reference.
-
2.4.7
2.4.14
2.4-122
3rd
Supplemental
Response to
RAI No. 139
Luminant Letter
no.TXNB-13016
Date 5/13/2013
2.4.16
2.4-127
2.4-132
2.4-157
3rd
Supplemental
Response to
RAI No. 139
Luminant Letter
no.TXNB-13016
Date 5/13/2013
Tables have been
revised to update
PMP values, runoff
values, surface
water elevations,
supercritical
velocities.
-
3rd
Supplemental
Response to
RAI No. 139
Luminant Letter
no.TXNB-13016
Date 5/13/2013
Tables have been
revised to update
watershed PMP
values, watershed
subbasin
characteristics, and
Snyder’s unit
hydrograph
characteristics.
-
Table 2.4.2205
Table 2.4.2206
2.4-158
Table 2.4.2207 (Sheets 1,
2 of 2)
2.4-159
2.4-160
Table 2.4.2208
2.4-161
Table 2.4.2209
Table 2.4.3201
2.4-162
Table 2.4.3202
2.4-164
Table 2.4.3203 (Sheets 1
through 3 of 3)
2.4-165
through
2.4-167
Table 2.4.3204
2.4-168
Table 2.4.3205 (Sheets 1
through 3 of 3)
2.4-169
through
2.4-163
2_35
Change Summary
Tables 2.4.3-203,
2.4.3-204, 2.4.3205, 2.4.3-208,
2.4.3-209, have
been deleted.
Rev.
of
FSAR
T/R
-
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
2.4-171
Table 2.4.3207
2.4-173
Table 2.4.3208
2.4-174
Table 2.4.3209
2.4-175
Table 2.4.3210
2.4-176
RCOL2_02.04.02-2
S03
(New tables)
2.4-176
3rd
Supplemental
Response to
RAI No. 139
Luminant Letter
no.TXNB-13016
Date 5/13/2013
Tables have been
added providing:
watershed hourly
PMP estimates for
the four basins and
SCR watershed
hourly PMP
estimates.
-
-
3rd
Supplemental
Response to
RAI No. 139
Luminant Letter
no.TXNB-13016
Date 5/13/2013
Figures revised to
reflect: latest site
grading and
drainage plan,
update supercritical
flow locations, and
update PMP depth
curves.
-
Table 2.4.3211
Table 2.4.3212
Table 2.4.3213
Table 2.4.3214
RCOL2_02.04.02-2
S03
Table 2.4.3215
Figure 2.4.2202
Figure 2.4.2203
Figure 2.4.2204
Figure 2.4.2205
Figures 2.4.2-205
has been deleted.
Figure 2.4.2206
Figure 2.4.2207
2_36
Change ID No.
RCOL2_02.04.02-2
S03
Section
Figure 2.4.3202
FSAR
Rev. 3
Page
-
Figure 2.4.3203
Figure 2.4.3204
Reason for
change
3rd
Supplemental
Response to
RAI No. 139
Luminant Letter
no.TXNB-13016
Date 5/13/2013
Figure 2.4.3205
Change Summary
Figures were
revised to include
storm centers,
update the subbasin schematic,
update PMF flow
and elevation
hydrographs, and
critical fetch length.
Rev.
of
FSAR
T/R
-
Figures 2.4.3-203
and 2.4.3-204 were
deleted.
Figure 2.4.3207
Figure 2.4.3208
RCOL2_02.04.02-2
S03
Figure 2.4.3209
Figure 2.4.3211
-
Figure 2.4.3212
Figure 2.4.3213
3rd
Supplemental
Response to
RAI No. 139
Luminant Letter
no.TXNB-13016
Date 5/13/2013
Figures have been
revised to update
Snyder’s unit
hydrographs for
basins 1-4.
-
Figures 2.4.3-211
and 2.4.3-212 have
been deleted.
Figure 2.4.3214
Figure 2.4.3215
Figure 2.4.3216
Figure 2.4.3217
RCOL2_02.04.02-2
S03
Figure 2.4.3219
Figure 2.4.3220
Figure 2.4.3221
-
3rd
Supplemental
Response to
RAI No. 139
Luminant Letter
no.TXNB-13016
Date 5/13/2013
2_37
Figures have been
added showing
overall watershed
two-thirds temporal
distribution for
Basins 1-4.
-
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
Figure 2.4.3222
Figure 2.4.3223
RCOL2_02.04.02-2
S03
Figure 2.4.4203
-
3rd
Supplemental
Response to
RAI No. 139
Luminant Letter
no.TXNB-13016
Date 5/13/2013
Figure revised to
update water
surface elevation at
Brazos River.
-
RCOL2_02.04.13-5
S02
Acronyms and
Abbreviations
2-lx
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Revised to add the
Acronyms:
contaminated zone
(CZ) and Effluent
Concentration Limits
(ECL)
-
RCOL2_02.04.13-5
S02
2.4.13
2.4-89
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Section revised to
include conceptual
vertical movement
of groundwater to
the nearest
surfacewater body
and aquifer.
-
RCOL2_02.04.13-5
S02
2.4.13.1
2.4-89
2.4-90
2.4-91
2.4-92
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Section revised to
correct editorial
errors and remove
unnecessary
acronyms.
-
CTS-01535
2.4.13.1
2.4-91
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Removed
unnecessary
abbreviation “(NE)”
from second
sentence of first
paragraph.
-
2_38
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
-
CTS-01536
2.4.13.1
2.4-91
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Revised text to
reflect change in
Figure number from
2.4.12-207 to
2.4.12-208 in third
paragraph.
RCOL2_02.04.13-5
S02
2.4.13.2
2.4-92
through
2.4-94
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Section revised to
describe the two
pathways (vertical &
horizontal) that were
considered in the
postulated tank
failure evalued using
RESRAD-OFFSITE.
-
RCOL2_02.04.13-5
S02
2.4.13.3
2.4-94
2.4-95
2.4-95
2.4-96
Subsections were
deleted and topics
included in these
sections were
incorporated into
2.4.13.2
-
2.4.13.4
2.4.13.4.1
2.4-96
2.4-97
2.4-97
through
2.4-103
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Subsections were
deleted and topics
included in these
sections were
incorporated into
2.4.13.2
-
RCOL2_02.04.13-5
S02
2.4.13.4.2
2.4-103
through
2.4-107
RCOL2_02.04.13-5
S02
2.4.13.2.1
2.4.13.2.1.1
2.4.13.2.1.2
2.4.13.2.2
(New sections)
2.4-103
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Section added to
describe the
shortest and fastest
horizontal flow paths
and the vertical flow
path.
-
RCOL2_02.04.13-5
S02
2.4.13.5
2.4-107
through
2.4-111
2.4-111
2.4-112
Subsections were
deleted and topics
included in these
sections were
incorporated into
2.4.13.2
-
2.4.13.5.1
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
2.4.13.5.2
2.4-112
2_39
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Subsection included
to provide a
summary of the
limiting and
bounding pathways
chosen for releases.
-
through
2.4-114
2.4.13.5.3
2.4-114
through
2.4-116
2.4.13.5.4
2.4-116
2.4-117
2.4.13.5.5
2.4-117
2.4.13.5.6
2.4-117
through
2.4-119
2.4.13.5.7
2.4-119
through
2.4-121
2.4-121
RCOL2_02.04.13-5
S02
2.4.13.3 (New
section)
RCOL2_02.04.13-7
S02
2.4.16
2.4-131
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Subsection was
revised to remove
reference 2.4-297.
-
RCOL2_02.04.13-5
S02
Table 2.4.13202 (Sheets 1,
2 of 2)
2.4-242
2.4-243
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Table was revised to
show the
Radionuclide
Concentrations and
Unity Values for the
Shortest Horizontal
Flow Path Scenario.
-
2_40
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
-
RCOL2_02.04.13-5
S02
Table 2.4.13203
2.4-244
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Table was revised to
show the
Radionuclide
Concentration and
Unity Values for the
Fastest Horizontal
flow Path Scenario.
RCOL2_02.04.13-5
S02
Table 2.4.13204 (Sheets 1,
2 of 2)
2.4-245
2.4-246
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Table was revised to
show the
Radionuclide
Concentrations and
Unity Values for the
Vertical Flow Path
Scenario.
-
RCOL2_02.04.13-5
S02
Table 2.4.13205 (Sheets 1,
2 of 2)
2.4-247
2.4-248
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Table was revised to
show a summary of
the sensitivity
analyses performed.
-
RCOL2_02.04.13-5
S02
Table 2.4.13206 (Sheets 1,
2 of 2)
2.4-249
2.4-250
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Table was deleted.
-
RCOL2_02.04.13-5
S02
Table 2.4.13207 (Sheets 1,
2 of 2)
2.4-251
2.4-252
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Table was deleted.
-
RCOL2_02.04.13-5
S02
Table 2.4.13208 (Sheets 1,
2 of 2)
2.4-253
2.4-254
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Table was deleted.
-
2_41
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
RCOL2_02.04.13-5
S02
Table 2.4.13209 (Sheets 1,
2 of 2)
2.4-255
2.4-256
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Table was deleted.
Rev.
of
FSAR
T/R
-
RCOL2_02.04.13-5
S02
Table 2.4.13210
2.4-257
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Table was deleted.
-
RCOL2_02.04.13-5
S02
Table 2.4.13211
2.4-258
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Table was deleted.
-
RCOL2_02.04.13-5
S02
Table 2.4.13212
2.4-259
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Table was deleted.
-
RCOL2_02.04.13-5
S02
Figure 2.4.13201 through
Figure 2.4.13207
-
2nd
Supplemental
Response to
RAI No. 145
Luminant Letter
no.TXNB-13018
Date 5/28/2013
Figure 2.4.13-201
was revised to
update the release
locations for the
BAT and Horizontal
Flow Paths (Fastest
& Shortest).
-
Figures 2.4.13-202
through 2.4.13-207
were deleted.
2_42
Change ID No.
CTS-01532
Section
Table 2.0-1R
(Sheet 1, 2,
8,9,10 of 13)
2.3.1.2
2.4.2
2.4.2.2
2.4.3
2.5.2
CTS-01542
2.4.3
FSAR
Rev. 3
Page
Reason for
change
Change Summary
2.0-2
2.0-3
2.0-9
2.0-10
[2.0-11]
To address sitespecific
strategies to
mitigate beyond
design basis
external events
per guidance in
NRC Order EA12-049, the
DCD added a
new COL item
(COL 1.9(2)-1)
which resulted
in an impact to
FSAR Ch. 2.
The applicable
portions of FSAR
Ch. 2 were updated
to incorporate COL
1.9(2)-1 and
address beyond
design basis
external events per
guidance in NRC
Order EA 12-049.
Editorial
correction
Corrected 749.09ft
to 794.09ft.
2.3-9
2.4-17
2.4-20
2.4-26
[2.4-27]
2.5-66
2.4-26
[2.4-27]
Rev.
of
FSAR
T/R
2
2
*Page numbers for the attached marked-up pages may differ from the revision 3 page numbers due to text additions
and deletions. When the page numbers for the attached pages do differ, the page number for the attached page is
shown in brackets.
2_43
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 2.0-1R (Sheet 1 of 13)
Key Site Parameters
Meteorology
Parameter Value
Parameter Description
CP COL 2.3(1)
Normal winter precipitation roof load
DCD
(11)
Extreme winter precipitation roof load(12)
50 lb/ft
2
11.7 lb/ft
75 lb/ft2
37.8 lb/ft2
48-hr probable maximum winter precipitation 36 in
(PMWP)
CP COL 1.9(2)-1
CP COL 1.9(2)-1
CPNPP 3 and 4
2
31 in
CTS01532
230 mph
230 mph
184 mph maximum rotational
184 mph maximum rotational
46 mph maximum translational
46 mph maximum translational
Radius of maximum rotational speed
150 ft
150 ft
Rate of Pressure drop
0.5 psi/s
0.5 psi/s
Tornado maximum pressure drop
1.2 psi
1.2 psi
Tornado-generated missile spectrum and
associated velocities
15 ft long schedule 40 steel pipe moving
horizontally at 135 ft/s(1)
15 ft long schedule 40 steel pipe moving
horizontally at 135 ft/s(1)
Tornado maximum wind speed
CTS01532
4000 lb automobile moving horizontally at 135 4000 lb automobile moving horizontally at
ft/s(1)
135 ft/s(1)
1 in diameter steel sphere moving horizontally 1 in diameter steel sphere moving
at 26 ft/s(1)
horizontally at 26 ft/s(1)
CP COL 1.9(2)-1
Extreme wind speed (other than in tornado
and hurricane)
155 mph for 3-second gusts at 33 ft
aboveground level based on 100-year return
period, with importance factor of 1.15 for
seismic category I and II structures
2.0-2
96 mph for-3-second gust wind speed at
33-ft aboveground based on 100-year
return period
Revision 3
RCOL2_0
3.03.02-9
CTS01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 2.0-1R (Sheet 2 of 13)
Key Site Parameters
CP COL 1.9(2)-1
CP COL 1.9(2)-1
Design-basis hurricane wind
Hurricane-generated missile spectrum and
associated velocities
Ambient design air temperature
CP COL 2.3(1)
160 mph for 3-second gusts at 33 ft. above
ground level which corresponds to the
exceedance frequency of 10-7 per year
145 mph for 3-second gusts at 33 ft. above
ground level which corresponds to the
exceedance frequency of 10-7 per year
15 ft. long Schedule 40 pipe moving
horizontally at 102 ft/s or vertically at 85 ft/s
15 ft. long Schedule 40 pipe moving
horizontally at 85 ft/s or vertically at
85 ft/s
RCOL2_0
3.03.02-9
CTS-01532
RCOL2_0
3.03.02-9
CTS-01532
4000 lb automobile moving horizontally at 135 4000 lb automobile moving horizontally at
114 ft/s or vertically at 85 ft/s
ft/s or vertically at 85 ft/s
RCOL2_0
3.03.02-9
1 in. diameter steel sphere moving horizontally 1 in. diameter steel sphere moving
horizontally at 73 ft/s or vertically at
at 89 ft/s or vertically at 85 ft/s
85 ft/s
RCOL2_0
3.03.02-9
1% annual exceedance maximum:
100°F dry bulb,
77°F coincident wet bulb,
81°F non-coincident wet bulb
1% annual exceedance maximum:
99°F dry bulb,
75°F coincident wet bulb,
78°F non-coincident wet bulb
0% exceedance maximum:
115°F dry bulb,
80°F coincident wet bulb,
86°F non-coincident wet bulb,
historical limit excluding peaks <2 hr
0% exceedance maximum:
112°F dry bulb,
78°F coincident wet bulb,
83°F non-coincident wet bulb,
historical limit excluding peaks <2 hr
100-year return period maximum:
115°F dry bulb,
78°F coincident wet bulb
86°F non-coincident wet bulb
2.0-3
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 2.0-1R (Sheet 8 of 13)
Key Site Parameters
CP COL 2.3(2)
Steam line break releases(8)
-2
See steam line break releases to Main Control Room
intake (above)(13)
3
0-8 hrs
8-24 hrs
1-4 days
4-30 days
1.9×10 s/m
1.1×10-2 s/m3
7.1×10-3 s/m3
4.7×10-3 s/m3
Fuel handling area releases(7)
0-8 hrs
8-24 hrs
1-4 days
4-30 days
1.1×10-3 s/m3
6.7×10-4 s/m3
4.3×10-4 s/m3
2.8×10-4 s/m3
See fuel handling area releases to Main Control
Room intake (above)(13)
Hydrologic Engineering
CP COL 2.4(1)
Parameter Description
Parameter Value
DCD
CP COL 1.9(2)-1
Maximum flood (or tsunami) level
1 ft below plant grade
2.0-9
CPNPP 3 and 4
793.66 ft msl for SCR
820.98 ft msl for a Local Intense Precipitation at units
3 and 4 site.CPNPP Units 3 and 4 plant grade - 822 ft
NAVD 88
Local Intense Precipitation - 820.93 ft NAVD 88
PMF with coincident wind waves - 811.09 ft NAVD 88
PMF - 794.09 ft NAVD 88
PMF with coincident wind waves - 811.09 ft NAVD 88
Local Intense Precipitation - 820.93 ft NAVD 88
PMF with coincident domino-type dam failure 768.69 ft NAVD88
Revision 3
RCOL2_02.
04.02-2 S03
CTS01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 2.0-1R (Sheet 9 of 13)
Key Site Parameters
CP COL 1.9(2)-1
Maximum rainfall rate (hourly)
19.4 in/hr for seismic category I and 19.01 in/hr
II structures
CTS01532
CP COL 1.9(2)-1
Maximum rainfall rate (short-term)
6.3 in/5 min for seismic category I
and II structures
6.23 in/5 min
CTS01532
CP COL 1.9(2)-1
Maximum groundwater level
1 ft below plant grade
1 ft below plant grade804 ft msl between the internal
ESWPT walls and R/B Complex
795 ft msl for portions adjacent to ESWPC
795 ft msl for areas external to ESWPT, including
external ESWPT walls, Turbine Building, PSFSV,
and UHSRS
RCOL2_02.
04.12-9 S04
Geology, Seismology, and Geotechnical Engineering
CP COL 2.5(1)
Parameter Description
Parameter Value
DCD
CPNPP 3 and 4
Maximum slope for foundation-bearing
stratum
20° from horizontal in untruncated
strata
Layer C slopes at less than 10 degree across the
footprint and the site area.
Safe-shutdown earthquake (SSE) ground
motion
0.3 g peak ground acceleration
The SSE is the envelope of the GMRS and the
minimum earthquake requirement of 10 CFR 50
Appendix S, based on the shape of the Certified Site
Design Response Spectra (CSDRS) scaled down to
a PGA of 0.1 g. The CSDRS is itself a modified RG
1.60 shape formed by shifting the control points at 9
Hz and 33 Hz to 12 Hz and 50 Hz, respectively.
2.0-10
Revision 3
CTS01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 2.0-1R (Sheet 10 of 13)
Key Site Parameters
CP COL 1.9(2)-1
CP COL 1.9(2)-1
CP COL 2.5(1)
SSE (certified seismic design) horizontal
ground response spectra
Regulatory Guide (RG) 1.60,
The minimum DCD spectrum envelops all four FIRS,
enhanced spectra in high frequency down to frequencies of 0.5 Hz. Values of the
horizontal
range (see Figure 3.7.1-1)
10-5 UHRS and FIRS are shown in Table 2.5.2-229
for the seven spectral frequencies.The DCD
spectrum envelopes all FIRS down to frequencies of
0.5 Hz. Values of the horizontal 10-4 mean UHRS,
10-5 mean UHRS (both at GMRS/FIRS1/FIRS2
control elevations), and GMRS/FIRS1/FIRS2 are in
Table 2.5.2-220 for seven spectral frequencies.
Values for remaining FIRS are in Table 2.5.2-222.
SSE (certified seismic design) vertical
ground response spectra
RG 1.60, enhanced spectra in high For vertical FIRS motions, the same considerations
frequency range (see Figure 3.7.1-2) used for the GMRS were used for the FIRS. That is,
as a conservative assumption the V/H ratio for the
FIRS spectra is assumed to be equal to the V/H ratio
from RG 1.60.
Potential for surface tectonic deformation at
site
None within the exclusion area
boundary
No potential tectonic surface deformation has been
identified at the site.
Subsurface stability – minimum allowable
static bearing capacity
15,000 lb/ft2
The minimum allowable bearing capacity of the
foundation bearing stratum meets or exceeds the
DCD requirement
Subsurface stability – minimum allowable
60,000 lb/ft2
dynamic bearing capacity, normal conditions
plus SSE
The minimum allowable dynamic bearing capacity of
the foundation bearing stratum meets or exceeds the
DCD requirement
Subsurface stability – minimum shear wave
velocity at SSE input at ground surface
The site stratigraphy has a measured velocity in
excess of 1000 ft/sec
1000 ft/s
2.0-11
Revision 3
CTS-01521
CTS-01532
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
and Caribbean Sea. Hurricanes strike the Texas coast an average of one every
three yr. Inland, hurricanes cause damage due to high winds, including tornadoes,
and flooding from excessive rainfall. Persons along the coast must also contend
with storm tides (Reference 2.3-202).
Although tornadoes can occur anytime, most of them materialize during April,
May, and June. In a normal year, about 130 tornadoes are sighted in Texas, 30
percent of which occur in May. On average, about 200 people are hurt and a
dozen are killed annually by the tornadoes. Tornadoes are most likely to occur
along and south of the Red River between Lubbock and Dallas; they are least
likely in the Trans-Pecos. Thunderstorms occur in every month of the year, though
least in winter. With an average of sixty thunderstorm days a year, East Texas is
most susceptible to the severe localized phenomena fostered by the storm (hail,
high winds, flash flooding). The mean annual number of thunderstorm days
diminishes from east to west across Texas; the Trans-Pecos has only about forty
such days each year. The lower Valley has fewer still (thirty). The peak hail
frequency statewide is in May. Most hailstorms are short-lived, however, because
the macroscale weather systems (such as squall lines) that generate hail move
rapidly. Hailstones are usually largest in the High Plains, where hail the size of
tennis balls-even baseballs-is not uncommon in the summer. Sunshine is most
abundant in the extreme west, where El Paso receives an average of 80 percent
of the total possible sunshine annually. Cloud cover is most prevalent along the
coast, especially in the Upper Coast, where the mean annual sunshine amounts
to only about 60 percent of possible sunshine hours (Reference 2.3-202).
Weather stations in the region surrounding the CPNPP site are shown on Figure
2.3-207. The closest weather stations to the CPNPP site are: Dublin, Glen Rose,
Cleburne, Benbrook, Dallas Fort Worth Airport, Dallas Love Field Airport, Mineral
Wells Airport, Weatherford, and Stephenville. Based on data for the period 1971 –
2000 for Dallas Fort Worth Airport, Dallas Love Field Airport, Mineral Wells
Airport, and Glen Rose the mean daily maximum temperature is 77.6°F and the
mean daily minimum temperature is 54°F. The lowest daily minimum is -15°F and
the highest daily maximum temperature is 115°F. The annual average
precipitation is 34.6 in. Monthly data from these stations are given in Tables
2.3-202 through 2.3-205. From data collected at the Dallas Fort Worth Airport, the
Mineral Wells Airport, and the CPNPP site the typical wind direction for the region
is from 147 degrees (Figures 2.3-208 through 2.3-210), the average wind speed is
10.5 mph. The frequency of snowfall in this region is so low that the average
annual snowfall is near zero. The frequency of sleet and freezing rain is discussed
in the following sections along with the regional dewpoint/relative humidity.
CP COL 1.9(2)-1
2.3.1.2
Regional Meteorological Conditions for Design and Operating CTS-01532
Bases
2.3.1.2.1
General
Meteorological data are presented in this subsection for severe weather
phenomena such as hurricanes, tornadoes, thunderstorms, lightning, hail, high air
2.3-9
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 1.9(2)-1
CP COL 2.4(1)
2.4.2
Floods
CTS-01532
Add the following at the end of DCD Subsection 2.4.2.
2.4.2.1
Flood History
Floods in Texas typically are associated with thunderstorms during the summer
and hurricanes and tropical storms in the late summer through early fall.
(Reference 2.4-228) Historical flooding in the Brazos River watershed above the
site has been a result of precipitation runoff. There are no known historical floods
due to dam failures, surges, seiches, tsunamis, ice jams, or landslides. Dam
failures are discussed in Subsection 2.4.4. Surge and seiches are discussed in
Subsection 2.4.5. Tsunamis are discussed in Subsection 2.4.6. Ice effects are
discussed in Subsection 2.4.7. Landslides are discussed in Subsection 2.4.9. The
maximum recorded water surface elevation associated with floods of record for all
rivers and streams in the vicinity are significantly lower than the Comanche Peak
Nuclear Power Plant (CPNPP) Units 3 and 4 site grade as discussed below.
The greatest known flood of the Brazos River occurred in 1876 prior to any
monitoring. Therefore, quantitative data for this event do not exist (Reference 2.4214). The USGS gage (08091000) on the Brazos River nearest to the site is
located near Glen Rose, Texas just upstream of the confluence with the Paluxy
River. Although there are no flood control dams upstream of the gage on the
Brazos River, the gage is subject to regulation by Morris Sheppard Dam,
completed in 1941 and impounding Possum Kingdom Lake, and De Cordova
Bend Dam, completed in 1969 and impounding Lake Granbury. (Reference 2.4222) The gage drainage area is 25,818 sq mi. The contributing drainage area of
the gage is 16,252 sq mi (Reference 2.4-224) and the gage location is shown in
Figure 2.4.2-201.
The peak flow measurement period of record for the gage 08091000 is from 1923
to the present. The maximum recorded water surface elevation of 603.58 ft msl
occurred on April 28, 1990 and corresponded to a discharge of 79,800 cfs. The
discharge was exceeded in 1991, 1981, 1957, and 1935. However, the recorded
water surface elevations were less than the flood elevation occurring in 1990. The
maximum recorded discharge of 97,600 cfs occurred on May 18, 1935 (Reference
2.4-224). The annual peak stage and discharge measurements for the period of
record are provided in Table 2.4.2-201. The datum for USGS gage (08091000) is
reported in North American Datum 1927 (NAD27) and National Geodetic Vertical
Datum of 1929 (NGVD29).
The Paluxy River is a tributary of the Brazos River. A USGS gage (08091500) is
located upstream of the confluence with the Squaw Creek tributary near Glen
Rose, Texas. The gage drainage area is 410 sq mi (Reference 2.4-225) and the
gage location is shown in Figure 2.4.2-201. The peak flow measurement period of
record for the gage contains periodic measurements in 1908, 1918, and 1922 and
is continuous from 1948 to the present. (Reference 2.4-220) The maximum
recorded water surface elevation of 636.86 ft msl occurred on April 17, 1908 and
2.4-17
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
the analysis. Runup is evaluated for slopes from 10:1 to vertical. Datum
conversion is accounted for in the comparison to the site grade.
The summary results of the events evaluated to determine the worst potential
flood are provided as follows:
•
Probable maximum precipitation (PMP) on the total watershed and critical
sub-watersheds, including seasonal variations and potential consequent
RCOL2_02.0
dam failures, with a corresponding water surface elevation of 793.66 ft
4.02-2 S03
msl794.09 ft NAVD 88 (discussed in Subsection 2.4.3).
•
Dam failures, including a postulated domino-type failures of three
upstream dams coincident with the Probable Maximum Flood (PMF), with
RCOL2_02.0
a corresponding water surface level of 760.68 ft msl768.69 ft NAVD 88
4.02-2 S03
(discussed in Subsection 2.4.4).
•
Two year coincident wind waves with a corresponding water surface level
of 810.64 ft msl811.09 ft NAVD 88 (discussed in Subsection 2.4.3).
RCOL2_02.0
4.02-2 S03
Specific analysis of Brazos River flood levels resulting from ocean front surges,
seiches, and tsunamis is not required because of the inland location and elevation
characteristics of the CPNPP site. Additional details are provided in Subsections
2.4.5 and 2.4.6. Snowmelt and ice effect considerations are unnecessary because
of the temperate zone location of CPNPP. Additional details are provided in
Subsection 2.4.3 and Subsection 2.4.7. Flood waves from landslides into
reservoirs required no specific analysis, in part because of the absence of major
elevation relief. In addition, elevation characteristics of the vicinity relative to the
associated water features, combined with limited slide volumes prohibit significant
landslide induced flood waves. Additional details are provided in Subsection 2.4.9.
The maximum flood levelwater surface elevation at CPNPP Units 3 and 4 due to
PMF is elevation 793.66 ft msl794.09 ft NAVD 88. This elevation would result from
a PMP at CPNPP Units 3 and 4 on the Squaw Creek watershed, as described in
Subsection 2.4.3. Coincident wind waves would create maximum waves of
16.9817 ft resulting in a design basis flood elevation of 810.64 ft msl811.09 ft
NAVD 88 due to PMF. CPNPP Units 3 and 4 safety-related plant elevation is 822 ft
mslNAVD 88, providing more than 101 ft of freeboard under the worst potential
flood considerations.
RCOL2_02.0
4.02-2 S03
RCOL2_02.0
4.02-2 S03
The maximum water surface elevation at CPNPP Units 3 and 4 due to local
intense precipitation is 820.93 ft NAVD 88. This elevation would result from a local
intense PMP, as described in Subsection 2.4.2.3, The design basis flood elevation
due to local intense precipitation is 820.93 ft NAVD 88, providing more than 1 ft of
CTS-01532
freeboard relative to the grade elevation of 822 ft NAVD 88. The identification of
critical flooding events in Subsection 2.4.2 and the detailed discussions in
Subsection 2.4.3 include considerable conservatism. As a result, the design basis
flood elevation of 821 ft NAVD 88 also meets the intent for the maximum water
surface elevation for the beyond-design-basis flood level.
2.4-20
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 1.9(2)-1
CP COL 2.4(1)
2.4.3
Probable Maximum Flood (PMF) on Streams and Rivers
CTS-01532
Add the following at the end of DCD Subsection 2.4.3.
The guidance in Appendix A of the U.S. Nuclear Regulatory Commission (NRC)
Regulatory Guide 1.59 and in NUREG/CR-7046 was followed in determining the
probable maximum flood (PMF) by applying the guidance of ANSI/ANS-2.8-1992
(Reference 2.4-229). ANSI/ANS-2.8-1992 was issued to supersede ANSI N1701976, which is referred to by Regulatory Guide 1.59 and NUREG/CR-7046. ANSI/
ANS-2.8-1992 is the latest available standard.
The PMF was determined for the Squaw Creek watershed and routed through the
SCR to determine a water surface elevation of 793.66 ft msl74994.09 ft NAVD 88.
The PMF for the Paluxy River watershed at the confluence with the Brazos River
was also examined. The PMF for the Paluxy River and the Squaw Creek
watersheds was combined with the Brazos River dam failure flood flow to
determine any backwater effects that may affect the site. The Brazos River dam
failure flood flow is described in Subsection 2.4.4 and includes the PMF for the
Brazos River. The resulting water surface elevation downstream of the Squaw
Creek Dam is 761.11 ft msl769.11 ft NAVD 88.
The CPNPP Units 3 and 4 safety-related facilities are located at elevation 822 ft
mslNAVD 88. Therefore, PMF on rivers and streams does not present any
potential hazards for CPNPP Units 3 and 4 safety-related facilities.
2.4.3.1
Probable Maximum Precipitation
The PMP is defined by HMR 51 (Reference 2.4-218) and HMR 52 (Reference 2.4219). HMR 53 (Reference 2.4-230) may be used to derive seasonal estimates of
the PMP. The PMP was determined for the Squaw Creek watershed and the
combined Squaw Creek and Paluxy River watersheds to maximize the effects of
flooding downstream of the SCR. Using the location of the watersheds, HMR 51
PMP charts are used to determine generalized estimates of the all-season PMP
for drainage areas from 10 to 20,000 sq mi for durations from 6 to 72 hr. The
resulting depth-area-duration (DAD) values are shown in Table 2.4.3-201.
HMR 52 is used to determine the aerial distribution of PMP estimates derived from
HMR 51. The recommended elliptical isohyetal pattern from HMR 52, shown in
Figure 2.4.3-201, is used for the watersheds. The watershed model, combining
both watersheds, contains 4 subbasins and is shown in Figure 2.4.3-202. The
watershed model is discussed in detail in Subsection 2.4.3.3.
HMR 52 computer software (Reference 2.4-231), developed by USACE, is used
to determine the optimum storm size and orientation to produce the greatest PMP
over the watersheds using the HMR 51 derived DAD table. Several storm centers
were examined for each watershed to determine the critical storm center.
2.4-27
Revision 3
RCOL2_02.0
4.02-2 S03
RCOL2_02.0
4.02-2 S03
RCOL2_02.0
4.02-2 S03
CTS-01542
RCOL2_02.0
4.02-2 S03
RCOL2_02.0
4.02-2 S03
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 1.9(2)-1
CP SUP2.5(2)
2.5.2
Vibratory Ground Motion
CTS-01532
Add the following after the content of DCD Section 2.5.2.
This subsection provides a detailed description of vibratory ground motion
assessments, specifically the criteria and methodology for establishing the
Ground Motion Response Spectra (GMRS) and Foundation Input Response
Spectra (FIRS) for the Comanche Peak Nuclear Power Plant Units 3 and 4
(CPNPP Units 3 and 4). It includes the information needed to address DCD COL CTS-01521
Item 2.5(1), which is incorporated by reference with the following variances and
supplements. The development of the GMRS for CPNPP Units 3 and 4 follows a
methodology consistent with the approach recommended in Regulatory Guide
(RG) 1.208 and, therefore, satisfies the requirements set forth in Section 100.23,
"Geologic and Seismic Siting Criteria," of Title 10, Part 100, of the Code of Federal
Regulations (10 CFR 100), "Reactor Site Criteria." This subsection begins with a
review of the approach outlined in RG 1.208 and is followed by these subsections:
•
Seismicity (Subsection 2.5.2.1)
•
Geologic and Tectonic Characteristics of the Site and Region (Subsection
2.5.2.2)
•
Correlation of Earthquake Activity with Seismic Sources (Subsection
2.5.2.3)
•
PSHA and Controlling Earthquake (Subsection 2.5.2.4)
•
Seismic Wave Transmission Characteristics of the Site (Subsection
2.5.2.5)
•
Ground Motion and Site Response Analysis (Subsection 2.5.2.6).
RG 1.208 provides guidance on methods acceptable by the Nuclear Regulatory
Commission (Reference 2.5-369) for satisfying the requirements of developing the
site-specific GMRS, which in turn represents the first step in developing the Safe
Shutdown Earthquake (SSE) ground motion levels as a characterization of the
seismic hazard at CPNPP Units 3 and 4. The process outlined in RG 1.208 for
determining the GMRS includes:
•
The geological, geophysical, seismological, and geotechnical
investigations of the site and site region, including the identification of
seismic sources significant to seismic hazard at the site.
•
The procedures for performing a Probabilistic Seismic Hazard Analysis
(PSHA) and deaggregating mean hazard.
•
Characterization of the seismic wave transmission characteristics of the
site.
2.5-66
Revision 3
Chapter 3
Chapter 3 Tracking Report Revision List
Change ID No.
RCOL2_03.0
9.06-22 S01
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Supplemental
Response to RAI
No. 244
Luminant Letter
no.TXNB-12021
Date 6/13/2012
Deleted references
to NUREG-1482
Rev. 2.
Rev.
of
FSAR
T/R
-
3.9.6
3.9-2
[3.9-2,
3.9-3]
3.9.10
3.9-6
RCOL2_14.03.0738
3.8.4.1.3.2
3.8-6
Response to RAI
No. 254
Luminant Letter
no.TXNB-12022
Date 6/21/2012
Clarified design
criteria.
-
RCOL2_09.02.0525 S01
3.6.1.3
3.6-1
3.6-2
Table 3.6-201
3.6-3
Added Table for
site-specific high
and moderate
energy fluid
systems.
-
3.6.4
Supplemental
01 Response to
RAI No. 252
Luminant Letter
no.TXNB-12031
Date 09/10/2012
3.3
3.3-1
3.3-2,
3.3-3
Revised to
incorporate RG
1.221.
-
3.3.2.1 (New
Subsection)
3.3.2.2.1 (New
Subsection)
3.3.2.2.4
3.3.2.3
Response to RAI
No. 250
Luminant Letter
no.TXNB-12032
Date 09/14/2012
RCOL2_03.03.02-9
3.3.3
3.5.1.4 (New
Subsection)
3.3-3
[3.3-4]
3.5-3
3.5.1.5
3.5.2
3.5.4
3.5-3
[3.5-4]
3.7.3.9
3.5-5
[3.5-6]
3.8.4.1.3.1
3.7-11
3.8.4.1.3.2
3.8-4
3_1
Change ID No.
Section
3.8.4.4.3.2
Table 3.8-203
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
3.8-5
3.8-6
[3.8-5
through
3.8-7]
3.8-11
[3.8-11,
3.8-12]
3.12.5.3.6
3.8-21
3.12.7
3LL.2
3.12-1
3.12-2
3LL-1
RCOL2_14.0
3.07-38 S01
Table 3.2-201
(Sheets 2, 3 of 3)
3.2-4
3.2-5
Supplemental
Response to RAI
No. 254
Luminant Letter
no.TXNB-12034
Date 09/24/2012
Following SSCs for
freeze protection
are added to the
table:
- Drain lines from
ESWS piping
- ESW piping room
unit heaters
- UHS transfer
piping room unit
heaters
-
RCOL2_14.0
3.07-38 S01
Table 3D-201
(Sheets 4 through
11 of 11)
3D-5
through
3D-12
Supplemental
Response to RAI
No. 254
Luminant Letter
no.TXNB-12034
Date 09/24/2012
Following SSCs for
freeze protection
are added to the
table.
- ESW piping room
unit heaters
- UHS transfer
piping room unit
heaters
-
RCOL2_03.06.01-1
3.6.1.3
3.6-1
[3.6-1
through
3.6-2]
Response to RAI
No. 262
Luminant Letter
no.TXNB-12035
Date 9/26/2012
Revised COL
3.6(1).
-
3_2
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
RCOL2_03.06.01-1
3.6.2.1
3.6-2
[3.6-3]
Response to RAI
No. 262
Luminant Letter
no.TXNB-12035
Date 9/26/2012
Revised COL
3.6(4).
RCOL2_09.05.04-1
3.8.4.1.3.1
3.8-5
Response to RAI
No. 265
Luminant Letter
no.TXNB-12043
Date 12/18/2012
CTS-01515
3.5.1.6
3.5-4
[3.5-5]
CTS-01512
Figure 3K-201
[Sheet 1, 2 of 2]
3K-2
[3K-3]
RCOL2_03.04.01-1
3.4.1.2
3.4-1
Consistency with
DCD and sitespecific changes
as described in
Letter. TXNB12033
(ML12268A413)
Consistency with
DCD and sitespecific
changes
as described in
Letter. TXNB12033
(ML12268A413)
Response to RAI
No. 275
Luminant Letter
no.TXNB-13019
Date 6/18/2013
Description for
environmental
conditions of
ESWPT and a
temporary
ventilation system
are added.
Updated aircraft
hazards evaluation
to reflect changes
in plant layout.
CTS-01532
ACRONYMS
AND
ABBREVIATIONS
3-ix
CTS-01532
3.4.1.2
3.4-1
3_3
Rev.
of
FSAR
T/R
-
-
0
Overall General
Arrangement plan
replaced with the
updated version;
and minor editorial
correction.
0
Revised 3.4.1.2 to
address the failure
of the outside
tanks.
-
Design change
as described in
Luminant ISCP
Letter
ML12268A413
The acronym for
essential service
water pipe chase
was added.
2
Fukushimarelated COL item
COL 1.9(3)
Description for the
BDB external flood
evaluation was
added.
2
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
2
CTS-01539
3.4.1.3
3.4-2
Design change
as described in
Luminant ISCP
Letter
ML12268A413
Description for the
flooding evaluation
for the site-specific
structures and
ESWPC was
added.
CTS-01532
3.4.1.4
3.4-2
[3.4-3]
Fukushimarelated COL item
COL 1.9(3)
Description for the
BDB external flood
evaluation was
added.
2
CTS-01532
3.4.4
3.4-3
[3.4-4]
The reference is
not used any
more.
Reference 3.4-201
was deleted.
2
CTS-01532
3.4.4
3.4-3
[3.4-4]
Reference 3.4-202
was added.
2
CTS-01541
3.5.1.6
3.5-4
[3.5-5]
Reference by the
addition of
Fukushimarelated
description to
Subsection
3.4.1.2.
Correction
Clarified definition
of A, effective area
of the plant, and
corrected the
calculated value of
N, estimated
annual number of
aircraft operation
2
*Page numbers for the attached marked-up pages may differ from the revision 3 page numbers due to text additions
and deletions. When the page numbers for the attached pages do differ, the page number for the attached page is
shown in brackets.
3_4
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
ACRONYMS AND ABBREVIATIONS
A/B
AC/B
ACI
ARS
ASCE
ASME
BE
CAV
CCWS
CFR
COL
COLA
CPNPP
CSDRS
DBFL
DCD
EQ
EQSDS
ESF
ESW
ESWPC
ESWPT
ESWS
FE
FIRS
FW
GMRS
IEEE
ILRT
ISI
ISRS
IST
LB
LBB
MCR
MOV
MS
N/A
NRC
auxiliary building
access building
American Concrete Institute
acceleration response spectra
American Society of Civil Engineers
American Society of Mechanical Engineers
best estimate
cumulative absolute velocity
component cooling water system
Code of Federal Regulations
Combined License
Combined License Application
Comanche Peak Nuclear Power Plant
certified seismic design response spectra
design-basis flooding level
Design Control Document
environmental qualification
equipment qualification summary data sheet
engineered safety features
essential service water
essential service water pipe chase
essential service water pipe tunnel
essential service water system
finite element
foundation input response spectra
feedwater
ground motion response spectra
Institute of Electrical and Electronic Engineers
integrated leak rate test
inservice inspection
in-structure response spectra
inservice testing
lower bound
leak before break
main control room
motor operated valve
main steam
not applicable
U.S. Nuclear Regulatory Commission
3-ix
CTS01539
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
3.4
WATER LEVEL (FLOOD) DESIGN
This section of the referenced DCD is incorporated by reference with the following
departures and/or supplements.
3.4.1.2
STDCP COL
3.4(1)
CP COL 3.4(5)
Flood Protection from External Sources
Replace the first sentence of the third paragraph in DCD Subsection 3.4.1.2 with
the following.
RCOL2_03.0
4.01-1
Entrances to all safety-related structures are above the design-basis flooding level
(DBFL) listedflood elevations described in Section 2.4, and adequate sloped site
grading and drainage prevents flooding caused by probable maximum
precipitation (PMP). or postulated failure of non safety-related, non seismic
storage tanks located on siteEntrances to all safety-related structures are also
protected from flooding due to the failure of the outside tanks (such as the
condensate storage tanks, refueling water storage auxiliary tank, demineralized
water storage tanks, and fire water storage tanks) by the site's grading and
drainage or installed curbs.
RCOL2_03.0
4.01-1
RCOL2_03.0
4.01-1
Replace the fourth paragraph in DCD Subsection 3.4.1.2 with the following.
No site-specific flood protection measures such as levees, seawalls, floodwalls,
site bulkheads, revetments, or breakwaters are applicable at CPNPP Units 3 and
CTS-01532
4, since the plant is built above the DBFLdesign-basis flood elevations and has
adequate site grading.
CP COL 1.9(3)
CTS-01532
The beyond-design-basis (BDB) flood elevation applied to the design of the
site-specific structures of CPNPP Units 3 and 4 is described in Section 2.4.2.
Since the design-basis flood elevations and the BDB flood elevation are
equivalent, no further flood protection measure is applied to the site-specific
structures for implementation of the baseline coping strategies as specified in NEI
12-06 (Reference 3.4-202).
CP COL 3.4(4)
Replace the seventh paragraph in DCD Subsection 3.4.1.2 with the following.
All seismic Category 1 buildings and structures below-grade are protected against
the effects of flooding, including ground water. This protection is achieved by
providing a water barrier on all exterior below-grade concrete members. The
water barrier consists of providing waterstops at all below-grade construction
3.4-1
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
joints in the exterior wall and base mats subjected to ground water seepage, and
membrane waterproofing material at all below-grade exterior wall surfaces. The
foundation slab water barrier system consists of crystalline waterproofing
compound applied between the base mat and fill concrete/bedrock. The
compound will either be spray applied or dry-shake to the fill concrete/bedrock. A
cementitious membrane coating made out of a crystalline waterproofing
compound is provided on the inside face of the UHS basin outermost walls and
foundation slab, including the UHS sump pit, to prevent water migration from the
UHS basin into the subgrade.
STD COL 3.4(3)
Replace the last sentence in the ninth paragraph in DCD Subsection 3.4.1.2 with
the following.
Site-specific potential sources of external flooding such as the cooling tower,
service water piping, or circulating water piping are not located near structures
containing safety-related SSCs, with the exception of piping entering plant
structures. The CWS enters only within the T/B, and any postulated pipe break is
prevented from back-flowing into the safety-related R/B by watertight separation.
Postulated pipe breaks near structures are prevented from entering the structures
by adequate sloped site grading and drainage.
3.4.1.3
STD COL 3.4(7)
Flood Protection from Internal Sources
Replace the last sentence in the last paragraph of DCD Subsection 3.4.1.3 with
the following.
Three site-specific safety-related structures (the UHSRS, the PSFSV, the
ESWPT) and the essential service water pipe chase (ESWPC) have been
evaluated for internal flooding concerns: the UHSRS, the ESWPT, and the
PSFSV. Other site-specific buildings and structures in the plant yard are
designated as non safety-related. By definition, their postulated failure due to
internal flooding or other postulated events do not adversely affect safety-related
SSCs or required safety functions.
CTS-01539
Each of these three structures is configured with independent compartments,
divisionally separated. Internal flooding of any one compartment and
corresponding division will not prevent the system from performing required
safety-related functions. Postulated flooding events such as those caused by
moderate energy line break (MELB) or fire suppression system activation within
one division will affect that respective division only. Flooding affecting one
compartment will not affect adjacent areas.
CTS-01539
3.4-2
Revision 3
CTS-01539
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
3.4.1.4
STD COL 3.4(2)
Evaluation of External Flooding
Replace the last sentence in the last paragraph of DCD Subsection 3.4.1.4 with
the following.
As discussed in Section 2.4, the site-specific DBFL doesdesigned-basis flood
elevations do not exceed the maximum flood level for the standard plant design.
Therefore, there are no static and/or dynamic flooding forces beyond those
considered in the standard plant design.
CP COL 1.9(3)
CTS-01532
As per subsection 3.4.1.2 discussion on BDB external flooding, no further
evaluation of external flooding is required for determination of appropriate actions
to protect the site-specific structures from a BDB external flooding.
3.4.2
STD COL 3.4(6)
Analysis Procedures
Replace the last paragraph of DCD Subsection 3.4.2 with the following.
No site-specific physical models are used to predict prototype performance of
hydraulic structures and systems, since there are no unusual design or
configuration or design or operating bases involving thermal and erosion
problems.
3.4.3
Combined License Information
Replace the content of DCD Subsection 3.4.3 with the following.
STD COL 3.4(1)
3.4(1) Site-specific design of plant grading and drainage
This COL item is addressed in Subsection 3.4.1.2.
STD COL 3.4(2)
3.4(2) DBFL applicability to site
This COL item is addressed in Subsection 3.4.1.4.
STD COL 3.4(3)
3.4(3) Site-specific flooding hazards from engineered features
This COL item is addressed in Subsection 3.4.1.2.
CP COL 3.4(4)
3.4(4) Additional ground water protection
This COL item is addressed in Subsection 3.4.1.2.
CP COL 3.4(5)
CTS-01532
3.4(5) DBFL and site-specific conditions
This COL item is addressed in Subsection 3.4.1.2.
3.4-3
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
STD COL 3.4(6)
3.4(6) Physical models for performance of hydraulic structures and systems
This COL item is addressed in Subsection 3.4.2.
STD COL 3.4(7)
CP COL 3.4(7)
3.4(7) Protection from internal flooding
This COL item is addressed in Subsection 3.4.1.3 and 3K.1.
3.4.4
References
Add the following reference after the last reference in DCD Subsection 3.4.4.
3.4-201
A Guide to the Use of Waterproofing, Dampproofing, Protective,
and Decorative Barrier Systems for Concrete, ACI 515.1R-79,
American Concrete Institute, Revised 1985Not used.
3.4-202
Diverse and Flexible Coping Strategies (FLEX) implementation
Guide, NEI 12-06 Revision 0, August 2012.
3.4-4
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
A = Effective area of plant in square miles (combined effective area of Units 3 CTS-01541
and 4)
In order to maintain PFA less than the order of 10-7 for both Units 3 and 4, the
above equation is rearranged to solve for N using values of C, A and w
determined below:
CTS-01515
CTS-01541
N = PFA /(C x A/w) = 19,30035,30017,600 operations per year
NUREG-0800, SRP 3.5.1.6 provides a value of C = 4x10-10 for commercial
aircraft. A table within SRP 3.5.1.6 also provides values for C for various
distances up to 10 statute miles from the end of the runway, and notes data are
not available for military aircraft greater than 5 statute miles from the end of
runway. Since the probability of military crashes is otherwise similar or less than
the probability of commercial air carriers within 5 statute miles of the end of
runway, the value of C = 4x10-10 provides a conservative approach for
determining the probability of in-route crashes on military airways. This
methodology is also consistent with the determination for the probability of in-flight
military aircraft crash in “The Annual Probability of an Aircraft Crash on the U.S.
Department of Energy Reservation in Oak Ridge, Tennessee” (Reference
3.5-201), Subsection 3.3.1.
CTS-01541
The effective area of each unit in the plant is conservatively determined as
CTS-01515
0.090790 square miles (0.1980 square miles for the plant) from the sum of the
aircraft shadow area (AS), skid area (AK), and footprint area (AB), calculated using
CTS-01515
a bounding power block volume by enveloping the outer boundaries of the R/B
complex, UHSRS, ESWPT and PSFSVs, access building (AC/B), A/B, power
source buildings (PS/Bs), and T/B of 490600 ft wide by 650690 ft long by 230 ft
high.
CTS-01515
AS = 230 ft x 650690 ft = 149,500158,700 ft2, where the shadow length is
conservatively determined using a 45 degree angle from the tallest point of the
power block, and the shadow width is equal to the widest dimension of the
power block.
AK = 0.6 miles (skid length) x 650690 ft = 2,059,2002,185,920 ft2, where the
skid length for military aircraft is determined from Reference 3.5-201, and the
width of skid is equal to the widest dimension of the power block.
CTS-01515
AB = 490600 ft x 650690 ft = 318,500414,000 ft2 as the total land occupied by CTS-01515
the power block.
The annual number of aircraft operations on military training route VR-158 noted
in Subsection 2.2.2.7.2 confirms operations are less than 19,30035,30017,600
operations per year. Therefore, neither an air crash nor an air transportation
accident is required to be considered as part of the design basis.
3.5-5
Revision 3
CTS-01515
CTS-01541
Chapter 4
Chapter 4 Tracking Report Revision List
Change ID
No.
Section
FSAR
Rev. 3
Page
Reason for change
Change Summary
Rev.
of
FSAR
T/R
*Page numbers for the attached marked-up pages may differ from the revision 3 page numbers due to text additions
and deletions. When the page numbers for the attached pages do differ, the page number for the attached page is
shown in brackets.
4_1
Chapter 5
Chapter 5 Tracking Report Revision List
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for change
Change Summary
Rev.
of
FSAR
T/R
*Page numbers for the attached marked-up pages may differ from the revision 3 page numbers due to text additions
and deletions. When the page numbers for the attached pages do differ, the page number for the attached page is
shown in brackets.
5_1
Chapter 6
Chapter 6 Tracking Report Revision List
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for change
Change Summary
Rev.
of
FSAR
T/R
-
RCOL2_06.0
4-15
6.4.4.2
6.4-2
6.4-3
Supplemental 01
Response to RAI
No. 240
Luminant Letter
no.TXNB-12021
Date 6/13/2012
Figure 1 was added to
the response due to
inadvertently omitted in
the original response.
No changed in FSAR
due to Supplemental
Response to RAI No.
240.
RCOL2_06.02.025
6.2.2.3.2
6.2-2
6.2-2
[6.2-3]
RCOL2_06.02.026
Table
6.2.2-2R
(Sheet 7
of 22)
6.2-4
Added discussion of
administrative programs
to maintain RMI, fiber
insulation, and aluminum
within design-basis
limits.
COL Item 6.2(5) location
made more specific
(Section 6.2.2.3 to
Section 6.2.2.3.2)
-
6.2.8
Response to RAI
No. 271
Luminant Letter
no.TXNB-13001
Date 01/17/2013
RCOL2_06.02.027
6.2.2.3.2
6.2-1
-
CTS-01522
6.4.4.2
6.4-2
Changes are made to
CP 3/4 latent debris
sampling program.
Sampling in accordance
with NEI 04-07 with
exceptions noted.
Exceptions are based on
CP 1/2 operating
experience.
The MCR intake
elevation is updated.
Response to RAI
No. 272
Luminant Letter
no.TXNB-13005
Date 03/04/2013
Response to RAI
No. 272
Luminant Letter
no.TXNB-13005
Date 03/04/2013
To reflect the new
seismic layout design
change.
-
1
*Page numbers for the attached marked-up pages may differ from the revision 3 page numbers due to text additions
and deletions. When the page numbers for the attached pages do differ, the page number for the attached page is
shown in brackets.
6_1
Chapter 7
Chapter 7 Tracking Report Revision List
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for change
Change Summary
Rev.
of
FSAR
T/R
*Page numbers for the attached marked-up pages may differ from the revision 3 page numbers due to text additions
and deletions. When the page numbers for the attached pages do differ, the page number for the attached page is
shown in brackets.
7_1
Chapter 8
Chapter 8 Tracking Report Revision List
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
-
RCOL2_08.01-3
8.1.2.1
8.1-1
Response to RAI
No. 249
Luminant Letter
no.TXNB-12013
Date 05/16/2012
Subsection 8.1.2.1 was
revised to state that the
switching station
equipment shared
between Units 3 and 4
includes the circuit
breakers, and that no
important to safety SSCs
are shared between
Units 3 and 4, under any
operating scenario
(normal or emergency).
RCOL2_03.03.02-9
8.2.1.2.1.1
8.2-4
Response to RAI
No. 250
Luminant Letter
no.TXNB-12032
Date 9/14/2012
Revised to incorporate
RG 1.221.
-
RCOL2_08.01-2
S03
8.1.2.1
8.1-1
[8.1-1
throug
h 8.12]
3rd Supplemental
Response to RAI
No. 9
Luminant Letter
No.TXNB-13007
Date 03/04/2013
Sentences of switching
station moved to section
8.2.2.1 Applicable
Criteria.
-
RCOL2_08.01-2
S03
8.2.2.1
(new
section)
8.2-10
[8.2-10
throug
h 8.211]
3rd Supplemental
Response to RAI
No. 9
Luminant Letter
No.TXNB-13007
Date 03/04/2013
Compliance to GDC 5 of
Switching Station added
to 8.2.2.1 Applicable
Criteria.
-
CTS-01508
Figure
8.3.1-201
8.3-21
Revised to reflect
common
foundation and the
new plant layout
Figure was updated to
reflect standard plant
and site-specific layout
changes.
0
CTS-01508
Figure
8.2-207
8.2-31
Turbine Building
and Electrical
Building layout
change.
The road surrounding
the Unit 3 and Unit 4
switchyard are changed.
Other non-technical
editorial changes are
made such as removal of
dimension line of the
building.
1
Figure was
updated to reflect
standard plant and
8_1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
The road surrounding
the Unit 3 and Unit 4
switchyard are changed.
Other non-technical
editorial changes are
made such as removal of
dimension line of the
building.
1
- AAC selector circuit
“Disconnecting Switch”
replaced with “Circuit
Breaker”
- Enhanced PSMS Power
Supply Configuration
- Modification to the P1/P2
Non-Class 1E 6.9kV
Bus Configuration
- Removal of primary
system power supply
panel
-Other related changes
2
site-specific layout
changes
CTS-01508
CTS-01532
Figure
8.2-208
Figure 8.11R
Table
8.3.1-4R
(Sheet 1
through 4
of 4)
Figure
8.3.1-1R
(Sheet 1,
5, 6 of
7[8])
8.2-32
8.1-2
[8.1-3]
8.3-6
throug
h
8.3-9
8.3-10
throug
h
8.3-12
Turbine Building
and Electrical
Building layout
change.
Figure was
updated to reflect
standard plant and
site-specific layout
changes
Reflection of
Fukushima-related
electrical changes
submitted by the
US-APWR DCD
update tracking
report, MUAP11021, Rev. 4
(ML13154A292)
8.3-13
Figure
8.3.1-2R
(Sheet 2 of
24)
*Page numbers for the attached marked-up pages may differ from the revision 3 page numbers due to text additions
and deletions. When the page numbers for the attached pages do differ, the page number for the attached page is
shown in brackets.
8_2
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CTS-01532
Comanche Peak 3&4
Switching Station
Comanche Peak 3&4
Switching Station
Reserve Auxiliary
Transformer
Circuit Breakers 1
Main Transformer
Circuit Breaker
Unit Switchyard
Plant
Reserve Auxiliary
Transformer
Circuit Breakers 2
Unit Switchyard
Plant
Main Transformer
3 Single Phase
Reserve Auxiliary
Transformer
Generator Load
Break Switch
UAT1
UAT2
UAT3
UAT4
RAT1
RAT2
RAT3
RAT4
Unit Auxiliary
Transformer
Main Turbine
Generator
1
A Class 1E
6.9kV Bus
2
5
1
A Class 1E GTG
2
B Class 1E GTG
A Selector
Circuit
6.9kV-480V
A Class 1E
Station Service
Transformer
3
C Class 1E
GTG
6.9kV-480V
C Class 1E
Station Service
Transformer
6.9kV-480V
B Class 1E
Station Service
Transformer
A AAC GTG
B Class 1E
480V Load Center
A Class 1E
480V Load Center
A1 Class 1E
480V
Load Center
A Class 1E
480V MCC
3
C Class 1E
6.9kV Bus
B Class 1E
6.9kV Bus
6
D Class 1E
6.9kV Bus
B Selector
Circuit
B AAC GTG
D1 Class 1E
480V
Load Center
C Class 1E
480V MCC
B Class 1E
480V MCC
N1 Non-Class 1E
13.8kV Bus
N2 Non-Class 1E
13.8kV Bus
N1 Non Class 1E
480V Load Center
6.9kV-480V
P11 Non-Class 1E
Station Service
Transformer
N2 Non Class 1E
480V Load Center
N4 Non-Class 1E
6.9kV Bus
N5 Non-Class 1E
6.9kV Bus
N6 Non-Class 1E
6.9kV Bus
6
5
13.8kV-480V
N2 Non-Class 1E
Station Service
Transformer
13.8kV-480V
N1 Non-Class 1E
Station Service
Transformer
N3 Non-Class 1E
6.9kV Bus
P2 Non-Class 1E 6.9kV Bus
P1 Non-Class 1E 6.9kV Bus
4
D Class 1E
GTG
6.9kV-480V
D Class 1E
Station Service
Transformer
D Class 1E
480V Load Center
C Class 1E
480V Load Center
K
A1 Class 1E
480V MCC
4
6.9kV-480V
P12 Non-Class 1E
Station Service
Transformer
P12 Non Class 1E
480V Load Center
P11 Non Class 1E
480V Load Center
6.9kV-480V
P21 Non-Class 1E
Station Service
Transformer
6.9kV-480V
N3 Non-Class 1E
Station Service
Transformer
6.9kV-480V
P22 Non-Class 1E
Station Service
Transformer
P21 Non Class 1E
480V Load Center
P22 Non Class 1E
480V Load Center
6.9kV-480V
N5 Non-Class 1E
Station Service
Transformer
6.9kV-480V
N4 Non-Class 1E
Station Service
Transformer
N3 Non Class 1E
480V Load Center
N4 Non Class 1E
480V Load Center
N5 Non Class 1E
480V Load Center
6.9kV-480V
N6 Non-Class 1E
Station Service
Transformer
N6 Non Class 1E
480V Load Center
K
P11 Non-Class 1E
480V MCC
D Class 1E
480V MCC
D1 Class 1E
480V MCC
P12 Non-Class 1E
480V MCC
P21 Non-Class 1E
480V MCC
P22Non-Class 1E N3 1Non-Class 1E
480V MCC
480V MCC
N42 Non-Class 1E
480V MCC
a
P11-MCC P22-MCC
P21-MCC P12-MCC
LEGEND
M
M
A DC
Switchboard
M
B DC
Switchboard
M
C DC
Switchboard
D DC
Switchboard
a
M
N1 DC
Switchboar
P21-MCC
P12 MCC
A1 DC
Switchboard
D1 DC
Switchboard
A MOV
Inverter 1
C UPS Unit
Bypass
Tr
B UPS Unit
Bypass
Tr
A UPS Unit
Bypass
Tr
A MOV
Inverter 2
B MOV
Inverter
D UPS Unit
Bypass
Tr
N12
UPS Unit
D MOV
Inverter 2
N12 I&C
Panelboard
B MOV
480V MCC
C MOV
480V MCC
N3 DC
Switchboard
P12-MCC
P21 MCC
P22-MCC
N4 DC
N3 DC
Switchboard P11 MCC
Switchboard
N21
UPS Unit
N21 I&C
Panelboard
P12-MCC
P21 MCC
A MOV
A MOV
480V MCC 1 480V MCC2
M
N2 DC
Switchboard
N22
UPS Unit
M
HIGH VOLTAGE
CIRCUIT BREAKER
N4 DC
Switchboard
DRAWOUT TYPE
CIRCUIT BREAKER
P11-MCC
P22 MCC
P21-MCC
N2 DC
N1 DC
Switchboard P12 MCC
Switchboard
N31
UPS Unit
CIRCUIT
BREAKER
LOAD BREAK
SWITCH
N32
UPS Unit
GENERATOR
N11 I&C
Panelboard
D MOV
Inverter 1
C MOV
Inverter
N11
UPS Unit
N1 DC
Switchboard
M
D MOV
D MOV
480V MCC1 480V MCC2
N2 DC
Switchboard
N41
UPS Unit
N22 I&C
Panelboard
P22-MCC
P11 MCC
P11-MCC
N1 DC
Switchboard P22 MCC
N42
UPS Unit
N31 I&C
Panelboard
N2 DC
Switchboard
N5
UPS Unit
N32 I&C
Panelboard
TRANSFORMER
M
MECHANICAL
INTERLOCK
K
MECHANICAL KEY
INTERLOCK
RECTIFER
BATTERY
A I&C
Panelboard
CP COL 8.2(3)
A1 I&C
Panelboard
A2 I&C
Panelboard
B I&C
Panelboard
B1 I&C
Panelboard
B2 I&C
Panelboard
C I&C
Panelboard
C2 I&C
C1 I&C
Panelboard Panelboard
N41 I&C
Panelboard
D1 I&C
D2 I&C
D I&C
Panelboard Panelboard Panelboard
N42 I&C
Panelboard
N5 I&C
Panelboard
Figure 8.1-1R Simplified One Line Diagram Electric Power System
8.1-3
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 8.3.1-4R (Sheet 1 of 4)
Electrical Load Distribution - Class 1E GTG Loading
A Class 1E GTG
Quantity
Installed
Load
STD COL 9.2(6)
STD COL 9.2(20)
STD COL 9.2(20)
Rated
Output
Load
Input
[kW]
[kW]
Efficiency
[%]
Power
Factor
Load
Factor
[%]
[%]
LOOP
LOCA Concurrent with a LOOP
Hot Shutdown
Quantity
[kW]
[kVAR]
[kVA]
Quantity
[kW]
Cold Shutdown
[kVAR]
[kVA]
Quantity
[kW]
[kVAR]
[kVA]
A Safety Injection Pump
1
900
9500
905
85
95
1
9500
58958
1118059
0
-
-
-
0
-
-
-
A Component Cooling Water Pump
1
610
64410
905
85
95
1
64410
400378
75818
1
64410
400378
7518
1
64410
400378
7518
A Essential Service Water Pump
1
650
68650
905
85
95
1
68650
42703
808765
1
68650
42703
808765
1
68650
42703
808765
A Containment Spray/Residual Heat Removal Pump
1
400
42200
905
85
95
1
42200
26348
49771
0
-
-
-
1
42200
26348
49771
A Charging Pump
1
820
86620
905
85
95
0
-
-
-
1
86620
53708
1019965
1
86620
53708
1019965
A Class 1E Electrical Room Air Handling Unit Fan
1
80
89
85
80
95
1
89
68
112
1
89
68
112
1
89
68
112
A Essential Chiller Unit
1
2960
324260
895
805
95
1
324260
243161
405306
1
324260
243161
405306
1
324260
243161
405306
A Spent Fuel Pit Pump
1
230
25743
8905
80
95
0
-
-
-
1
(25743)
(19382)
(32203)
1
(25743)
(19382)
(32203)
A Class 1E Electrical Room Air Handling Unit Electrical Heater
1
250
250
100
100
100
0
-
-
-
0
-
-
-
0
-
-
-
A Pressurizer Heater (Back-up)
1
562
562
100
100
100
0
-
-
-
1
562
0
562
0
-
-
-
A Essential Service Water Pump Cooling Tower Fan
2
150
1658
8590
80
95
2
33617
25238
420396
2
33617
25238
420396
2
33617
25238
420396
Motor Control Centers (A&A1)
2
2
320328
650
19964
377385
670
2
270278
620
16834
318326
634
2
270278
620
16834
318326
634
37713779
3787
2441150
44954503
4355
37773785
3839
2095
1822
44024410
4249
36373645
3677
2358070
43374345
4220
Total
(
8.3-6
):This load is started by manually if GTG has necessary margin after completing automatic load sequence.
Revision 3
CTS-01532
CTS-01532
RCOL2_14.0
3.07-38 S03
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 8.3.1-4R (Sheet 2 of 4)
Electrical Load Distribution - Class 1E GTG Loading
B Class 1E GTG
Quantity
Installed
Load
Rated
Output
[kW]
Load
Input
[kW]
Efficiency
[%]
Power
Factor
Load
Factor
[%]
[%]
LOOP
LOCA Concurrent with a LOOP
Hot Shutdown
Quantity
[kW]
[kVAR]
[kVA]
Quantity
[kW]
Cold Shutdown
[kVAR]
[kVA]
Quantity
[kW]
[kVAR]
[kVA]
CTS-01532
B Safety Injection Pump
1
900
9500
905
85
95
1
9500
58958
11181059
0
-
-
-
0
-
-
-
B Component Cooling Water Pump
1
610
64410
905
85
95
1
64410
400378
7518
1
64410
400378
7518
1
64410
400378
7518
B Essential Service Water Pump
1
650
68650
905
85
95
1
68650
42703
808765
1
68650
42703
808765
1
68650
42703
808765
B Containment Spray/Residual Heat Removal Pump
1
400
42200
905
85
95
1
42200
26348
49771
0
-
-
-
1
42200
263248
49771
B Emergency Feed Water Pump
1
590
47553
905
85
73
1
47553
29581
55933
1
47553
29581
55933
0
-
-
-
B Class 1E Electrical Room Air Handling Unit Fan
1
80
89
85
80
95
1
89
68
112
1
89
68
112
1
89
68
112
B Essential Chiller Unit
1
2960
324260
895
805
95
1
324260
243161
405306
1
324260
243161
405306
1
324260
243161
405306
A Spent Fuel Pit Pump
1
230
25743
8590
80
95
0
-
-
-
1
(25743)
(19382)
(32203)
1
(25743)
(19382)
(32203)
B Class 1E Electrical Room Air Handling Unit Electrical Heater
1
250
250
100
100
100
0
-
-
-
0
-
-
-
0
-
-
-
B Pressurizer Heater (Back-up)
1
562
562
100
100
100
0
-
-
-
1
562
0
562
0
-
-
-
STD COL 9.2(20)
B Essential Service Water Pump Cooling Tower Fan
2
150
1658
8590
80
95
2
33617
25238
420396
2
33617
25238
420396
2
33617
25238
420396
CTS-01532
STD COL 9.2(20)
Motor Control Centers (B&A1)
2
2
320323
640
1959
377380
660
2
270273
610
16829
318321
624
2
270273
610
16829
318321
624
RCOL2_14.0
3.07-38 S03
42464249
4230
2736
2426
50545057
4876
33863389
3462
1853
1590
39423945
3810
27712774
2847
1821
1557
33183321
3245
STD COL 9.2(6)
Total
(
8.3-7
): This load is started by manually if GTG has necessary margin after completing automatic load sequence.
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 8.3.1-4R (Sheet 3 of 4)
Electrical Load Distribution - Class 1E GTG Loading
C Class 1E GTG
Quantity
Installed
Load
Rated
Output
[kW]
Load
Input
[kW]
Efficiency
[%]
Power
Factor
Load
Factor
[%]
[%]
LOOP
LOCA Concurrent with a LOOP
Hot Shutdown
Quantity
[kW]
[kVAR]
[kVA]
Quantity
[kW]
Cold Shutdown
[kVAR]
[kVA]
Quantity
[kW]
[kVAR]
[kVA]
CTS-01532
C Safety Injection Pump
1
900
9500
905
85
95
1
9500
58958
1118059
0
-
-
-
0
-
-
-
C Component Cooling Water Pump
1
610
64410
905
85
95
1
64410
400378
7518
1
64410
400378
7518
1
64410
400378
7518
C Essential Service Water Pump
1
650
68650
905
85
95
1
68650
42703
808765
1
68650
42703
808765
1
68650
42703
808765
C Containment Spray/Residual Heat Removal Pump
1
400
42200
905
85
95
1
42200
26348
49771
0
-
-
-
1
42200
26348
49771
C Emergency Feed Water Pump
1
590
47553
905
85
73
1
47553
29581
55933
1
47553
29581
55933
0
-
-
-
C Class 1E Electrical Room Air Handling Unit Fan
1
80110
89116
8590
80
95
1
89116
6887
112145
1
89116
6887
11245
1
89116
6887
11245
C Essential Chiller Unit
1
2960
324260
895
805
95
1
324260
243161
405306
1
324260
243161
405306
1
324260
243161
405306
B Spent Fuel Pit Pump
1
230
25743
8590
80
95
0
-
-
-
1
(25743)
(19382)
(32203)
1
(25743)
(193)82
(32203)
C Class 1E Electrical Room Air Handling Unit Electrical Heater
1
250
250
100
100
100
0
-
-
-
0
-
-
-
0
-
-
-
C Pressurizer Heater (Back-up)
1
562
562
100
100
100
0
-
-
-
1
562
0
562
0
-
-
-
STD COL 9.2(20)
C Essential Service Water Pump Cooling Tower Fan
2
150
1658
8590
80
95
2
33617
25238
420396
2
33617
25238
420396
2
33617
25238
420396
CTS-01532
STD COL 9.2(20)
Motor Control Centers (C&D1)
2
2
320323
560
19987
377380
567
2
270273
520
16806
318321
531
2
270273
520
168106
318321
531
RCOL2_14.0
3.07-38 S03
42464249
4266
2736
2441
50545057
4915
33863389
3488
1853
1654
39423945
3860
27712774
2873
18621
33183321
3299
STD COL 9.2(6)
Total
(
8.3-8
):This load is started by manually if GTG has necessary margin after completing automatic load sequence.
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 8.3.1-4R (Sheet 4 of 4)
Electrical Load Distribution - Class 1E GTG Loading
D Class 1E GTG
Quantity
Installed
Load
Rated
Output
[kW]
Load
Input
[kW]
Efficiency
[%]
Power
Factor
Load
Factor
[%]
[%]
LOOP
LOCA Concurrent with a LOOP
Hot Shutdown
Quantity
[kW]
[kVAR]
[kVA]
Quantity
[kW]
Cold Shutdown
[kVAR]
[kVA]
Quantity
[kW]
[kVAR]
[kVA]
CTS-01532
D Safety Injection Pump
1
900
9500
905
85
95
1
9500
58958
1118059
0
-
-
-
0
-
-
-
D Component Cooling Water Pump
1
610
64410
905
85
95
1
64410
400378
7518
1
64410
400378
7518
1
64410
400378
7518
D Essential Service Water Pump
1
650
68650
905
85
95
1
68650
42703
808765
1
68650
42703
808765
1
68650
42703
808765
D Containment Spray/Residual Heat Removal Pump
1
400
42200
905
85
95
1
42200
26348
49771
0
-
-
-
1
42200
26348
49771
DB Charging Pump
1
820
86620
905
85
95
0
-
-
-
1
86620
53708
1019965
1
86620
53708
1019965
D Class 1E Electrical Room Air Handling Unit Fan
1
80110
89116
8590
80
95
1
89116
6887
11245
1
89116
6887
11245
1
89116
6887
11245
D Essential Chiller Unit
1
2960
324260
895
805
95
1
324260
243161
405306
1
324260
243161
405306
1
324260
243161
405306
B Spent Fuel Pit Pump
1
230
25743
8590
80
95
0
-
-
-
1
(257)43)
(19382)
(32203)
1
(257)43)
(19382)
(32203)
D Class 1E Electrical Room Air Handling Unit Electrical Heater
1
250
250
100
100
100
0
-
-
-
0
-
-
-
0
-
-
-
D Pressurizer Heater (Back-up)
1
562
562
100
100
100
0
-
-
-
1
562
0
562
0
-
-
-
STD COL 9.2(20)
D Essential Service Water Pump Cooling Tower Fan
2
150
1658
8590
80
95
2
33617
252238
420396
2
33617
25238
420396
2
33617
25238
420396
CTS-01532
STD COL 9.2(20)
Motor Control Centers (D&D1)
2
2
320328
570
19995
377385
578
2
270278
540
16845
318326
542
2
270278
540
16845
318326
542
RCOL2_14.0
3.07-38 S03
37713779
3823
2441
2168
44954503
4395
37773785
3875
2095
1820
44024410
4281
36373645
3713
2358
2068
43374345
4250
STD COL 9.2(6)
Total
(
8.3-9
): This load is started by manually if GTG has necessary margin after completing automatic load sequence.
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CTS-01532
CP COL 8.2(3)
Figure 8.3.1-1R Onsite AC Electrical Distribution System (Sheet 1 of 78)
Main One Line Diagram
8.3-10
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CTS-01532
STD COL 9.2(20)
Figure 8.3.1-1R Onsite AC Electrical Distribution System (Sheet 5 of 78)
Class 1E 480V Buses A and B One Line Diagram
8.3-11
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CTS-01532
STD COL 9.2(20)
Figure 8.3.1-1R Onsite AC Electrical Distribution System (Sheet 6 of 78)
Class 1E 480V Buses C and D One Line Diagram
8.3-12
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CTS-01532
CP COL 8.2(3)
Figure 8.3.1-2R Logic Diagrams (Sheet 2 of 24)
One Line Diagram
8.3-13
Revision 3
Chapter 9
Chapter 9 Tracking Report Revision List
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
-
RCOL2_09.02.01-7
9.2.1.3
9.2-5
[9.2-6]
Response to
RAI No. 251
Luminant Letter
no.TXNB-12016
Date 05/31/2012
Added discussion
regarding CCW heat
exchanger backflush
procedure including
valve alignment and
identification as a
maintenance outage
train.
RCOL2_09.02.01-8
9.2.1.2.2.5
9.2-4
Response to
RAI No. 251
Luminant Letter
no.TXNB-12016
Date 05/31/2012
Revised to discuss the
ESWS piping material
and inspection.
RCOL2_09.02.01-9
9.2.5.5
9.2-21
[9.2-22
9.2-23]
Response to
RAI No. 251
Luminant Letter
no.TXNB-12016
Date 05/31/2012
Revised to clarify that
level switches are
utilized to prevent
water hammer and are
non safety-related.
RCOL2_09.0
1.05-1 S01
9.1.5.3 9.1.5
(New
Section)
9.1.5.1(New
Subsection)
9.1.5.3 (New
Subsection)
9.1.5.4 (New
Subsection)
9.1.5.6 (New
Subsection)
9.1-1
[9.1-1
through
9.1-5]
Supplemental
01 Response to
RAI No. 52
Luminant Letter
no.TXNB-12021
Date 6/13/2012
The heavy load
handling program
description is
enhanced to satisfy the
requirements of COL
item 9.1 (6).
-
9.1.6
9.1-2
[9.1-5]
9.2.5.2.1
9.2-12
[9.2-13]
9.2-18
[9.2-20]
Added design criteria
for cooling tower spray
nozzle sizing.
Clarified design
criteria.
-
9.2.5.3
Response to
RAI No. 254
Luminant Letter
no.TXNB-12022
Date 6/21/2012
9.2.5.2.1
9.2-12
[9.2-13]
Added discussion
about UHS fan speed
and direction.
-
9.2.5.2.2
9.2-15
Response to
RAI No. 257
Luminant Letter
no.TXNB-12022
Date 6/21/2012
RCOL2_14.03.07-38
RCOL2_14.02-21
9_1
Added discussion
-
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
[9.2-16]
Change Summary
Rev.
of
FSAR
T/R
about level switches.
RCOL2_09.0
4.05-23 S01
9.4.5.3.6
9.4-6
Supplemental 01
RAI No. 243
Luminant Letter
no.TXNB-12030
Date 08/29/2012
Added the design
information about the
wall separating the
ESW pump room from
the transfer pump
room.
-
RCOL2_09.0
4.05-23 S01
Table 9.4202
9.4-11
Supplemental 01
Response to
RAI No. 243
Luminant Letter
no.TXNB-12030
Date 08/29/2012
Changed the capacity
of UHS ESW Pump
House Ventilation
System Equipment.
-
RCOL2_09.0
4.05-23 S01
9A.3.101
9A-2
9A-3
9A.3.104
9A-5
Changed or added fire
protection design
features for UHS
basins, ESW pump
rooms and transfer
pump rooms.
-
9A.3.102
Supplemental 01
Response to
RAI No. 243
Luminant Letter
no.TXNB-12030
Date 08/29/2012
9A.3.105
9A-6
9A.3.107
9A-8
9A-9
9A.3.108
9A-10
9A.3.110
9A-12
9A.3.111
9A-13
9.2.1.2.3.1
9.2-4
9.2-15
[9.2-17]
Removed description
of level switches
located in the UHS
cooling tower riser
piping.
-
9.2.5.2.2
9.2.5.5
9.2-22
[9.2-25]
Supplemental 01
Response to
RAI No. 251
Luminant Letter
no.TXNB-12031
Date 9/10/2012
RCOL2_09.02.01-9
S01
9_2
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
-
RCOL2_09.02.05-18
S01
9.2.5.2.1
9.2-12
Supplemental 01
Response to
RAI No. 252
Luminant Letter
no.TXNB-12031
Date 09/10/2012
Added description to
discuss UHS cooling
tower plume discharge.
RCOL2_03.03.02-9
9.2.5.2.1
9.2-12
[9.2-13]
Revised to incorporate
RG 1.221.
-
9.2.5.2.2
9.2-15
[9.2-17]
Response to
RAI No. 250
Luminant Letter
no.TXNB-12032
Date 9/14/2012
9.4.5.3.6
9.4.5.4.6
9.4-7
9.2.1.3
9.2-5
9.2-15
Description is added
regarding freeze
protection of the UHS
and ESWS.
-
9.2.5.2.2
9.2.10
9.2-24
Supplemental
Response to
RAI No. 254
Luminant Letter
no.TXNB-12034
Date 09/24/2012
RCOL2_14.0
3.07-38 S01
Table 9.2.5-201 is
added for address of
CP COL 9.2(19).
RCOL2_14.0
3.07-38 S01
Table 9.2.5201 (New
Table)
9.2-35
Supplemental
Response to
RAI No. 254
Luminant Letter
no.TXNB-12034
Date 09/24/2012
New table is
introduced to describe
electric power division
for clarification.
-
RCOL2_14.0
3.07-38 S01
Figure 9.2.51R (Sheets
1, 2 of 2)
9.2-38
9.2-39
Supplemental
Response to
RAI No. 254
Luminant Letter
no.TXNB-12034
Date 09/24/2012
The figure is revised to
show the newly
introduced drain lines
for freeze protection.
-
9_3
Change ID No.
RCOL2_14.0
3.07-38 S01
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Supplemental
Response to
RAI No. 254
Luminant Letter
no.TXNB-12034
Date 09/24/2012
Supply areas are
added to the UHS
ESW Pump House
Ventilation System and
to for freeze protection
of the UHSS and
ESWS.
Rev.
of
FSAR
T/R
-
9.4.5.1.1.6
9.4-3
9.4.5.2.6
9.4-4
through
9.4-6
RCOL2_14.0
3.07-38 S01
Table 9.4202
9.4-11
Supplemental
Response to
RAI No. 254
Luminant Letter
no.TXNB-12034
Date 09/24/2012
ESW piping room unit
heaters and UHS
transfer piping room
unit heaters are added
to the table.
-
RCOL2_14.0
3.07-38 S01
Table 9.4203 (Sheet 3
of 6)
9.4-14
Supplemental
Response to
RAI No. 254
Luminant Letter
no.TXNB-12034
Date 09/24/2012
ESW piping room unit
heaters and UHS
transfer piping room
unit heaters are added
to the table.
-
RCOL2_14.0
3.07-38 S01
Figure 9.4201
9.4-18
Supplemental
Response to
RAI No. 254
Luminant Letter
no.TXNB-12034
Date 09/24/2012
The figure is revised to
add newly introduced
dampers to inlets and
exhausts of the
ventilation system.
-
RCOL2_09.02.05-18
S02
9.2.5.2.1
9.2-12
Supplemental 02
Response to
RAI No. 252
Luminant Letter
no.TXNB-12036
Date 11/12/2012
Corrected vertical
distance value for
distance between UHS
CT discharge and
other intakes; Revised
description to indicate
pump house intakes on
the south side take
advantage of the
prevailing wind
direction.
-
9_4
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
-
RCOL2_09.02.05-20
S02
9.2.5.2.2
9.2-15
Supplemental 02
Response to
RAI No. 252
Luminant Letter
no.TXNB-12036
Date 11/12/2012
Revised description to
indicate that vortex is
not a concern during
simultaneous pump
operation of ESWP
and UHS Transfer
Pump.
RCOL2_14.03.07-38
S02
9.2.1.3
9.2-5
[9.2-6]
Supplemental 02
Response to
RAI No. 254
Luminant Letter
no.TXNB-12036
Date 11/12/2012
Revised to include
description that
ESWPT is below grade
and therefore freezing
is not a concern.
-
RCOL2_09.02.01-9
S02
9.2.1.2.3.1
9.2-4
[9.2-4,
9.2-5]
Supplemental 02
Response to
RAI No. 251
Luminant Letter
no.TXNB-12041
Date 12/03/2012
Revise the location of
the DCD reference
location and add the
evaluation of why void
detection is not
required.
-
9.2.5.5
9.2-21
[9.2-24]
Change LMN from
“STD COL 9.2(24) to
STD COL 9.2(32)”.
9.2.10
9.2-25
[9.2-29]
Delete “9.2.5.5” from
9.2(32) Void dection
system.
9.2.6.2 (New
section)
9.2-22
RCOL2_12.0312.04-11 S04
Supplemental
04
Response to
RAI No. 135
Luminant Letter
no.TXNB-12042
Date 12/6/2012
9_5
Revised to state that
the CST for CPNPP
Unit 3 is located on
west side of Unit 3 as
depicted on Figure
12.3-201, while the
CPNPP Unit 4 CST is
located on the east
side of Unit 4, as
depicted on Figure
12.3-202.
-
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
RCOL2_09.0
4.05-26
Table 9.4201 (Sheet 1
of 2)
9.4-9
[9.4-10]
Response to
RAI No. 266
Luminant Letter
no.TXNB-12043
Date 12/18/2012
RCOL2_09.0
4.05-27
9.4.3.2.2
9.4-2
Response to
RAI No. 266
Luminant Letter
no.TXNB-12043
Date 12/18/2012
The LMN “CP COL
9.4(4)” and description
of supplemental
heating is added.
-
RCOL2_09.05.04-1
9.5.4.2.2.1
9.5-21
Response to
RAI No. 265
Luminant Letter
no.TXNB-12043
Date 12/18/2012
Temperature condition
of PSFSV is added.
-
RCOL2_09.04.05-23
S02
9.3.3.2.3
(new
section)
9.3-2
[9.3-2
through
9.3-3]
Supplemental
S02 Response
to RAI No. 243
Luminant Letter
no.TXNB-13006
Date 03/04/2013
Design description of
floor drain system and
liquid detection system
were added.
-
9_6
Change Summary
Rev.
of
FSAR
T/R
-
MCR/Class 1E
Electrical HVAC
Equipment Room Induct Heater Capacity
“Non-heating” is added
for Train A and D.
Change ID No.
RCOL2_09.04.05-23
S02
Section
FSAR
Rev. 3
Page
9.4.5.1.1.6
9.4-3
9.4.5.2.6
9.4-4
[9.4-5]
9.4.5.3.6
9.4-7
9.4.7
9.4-8
[9.4-9]
Table 9.4202
(replaced
table)
9.4-11
[9.4-12]
Table 9.4203[204]
(Sheets 1,
5[7] of 6[8])
9.4-12,
9.4-16
[9.4-14,
9.4-20]
CTS-01509
Table
9.4-201
CTS-01517
Figure 9.5.1202
RCOL2_09.04.05-23
S02
Reason for
change
Supplemental
S02 Response
to RAI No. 243
Luminant Letter
no.TXNB-13006
Date 03/04/2013
Change Summary
Temperature range
was deleted.
Rev.
of
FSAR
T/R
-
A sentence describing
the Table 9.4-202 was
added.
Table numbers were
revised
correspondence with a
new table.
Supplemental
S02 Response
to RAI No. 243
Luminant Letter
no.TXNB-13006
Date 03/04/2013
New table was added
as Table 9.4-202 and
table numbers were
revised
correspondence with
this new table.
-
9.4-9
9.4-10
[9.4-11]
To reflect
impacts on
heating and
cooling capacity
due to layout
changes.
Heating and cooling
capacity and in-duct
heater capacity in
Table 9.4-201 have
been changed.
0
9.5-148
Design change
as described in
Luminant ISCP
Letter
ML12268A413
Reflected new site
plan.
0
9_7
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
0
CTS-01516
9A.3
9A-1
Correction
Changed “Pumping
Station” to “Pump
House” in first bullet.
CTS-01518
9A.3
9A-1
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Added bullets ESWPiping Room and
UHS-Transfer Piping
Room.
0
CTS-01518
9A.3
9A-2
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Changed the DCD
Subsection to
9A.3.153.
0
CTS-01518
9A.3.101
[9A.3.201]
9A-2
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Changed Section
9A.3.101 to 9A.3.201
and changed title to
FA7-201-01.
0
9_8
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
0
CTS-01516
9A.3.101
[9A.3.201]
9A-2
Correction
Changed “exceed” to
“exceeding”
CTS-01516
9A.3.101
[9A.3.201]
9A-2
Correction
Added 3.2.1.j.
0
CTS-01518
9A.3.101
[9A.3.201]
9A-2
[9A-3]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Deleted “The electrical
circuits from other
safety trains in this
area will be protected
by a one-hour fire
rated wrap.”
0
CTS-01518
9A.3.202
[New]
9A-3
and
[9A-4]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Added new subsection
9A.3.202, FA7-201-02
A-ESW Piping Room
0
9_9
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
CTS-01518
9A.3.102
[9A.3.203]
9A-3
[9A-5]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Changed Section
9A.3.102 to 9A.3.203
and changed fire area
to FA7-202 to fire zone
FA7-202-01.
CTS-01516
9A.3.102
[9A.3.203]
9A-3
[9A-5]
Correction
Changed “D” to “C or
D.”
0
CTS-01516
9A.3.102
[9A.3.203]
9A-3
[9A-5]
Correction
Changed “exceed” to
“exceeding”
0
CTS-01516
9A.3.102
[9A.3.203]
9A-3
[9A-5]
Correction
Added 3.2.1.j.
0
9_10
Rev.
of
FSAR
T/R
0
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
0
CTS-01518
9A.3.204
[New]
9A-4
[9A-6,
9A-7]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Added new Subsection
9A.3.204, FA7-202-02
A-UHS Transfer Piping
Room.
CTS-01518
9A.3.103
[9A.3.205]
9A-4
[9A-7]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Changed section from
9A.3.103 to 9A.3.205
and changed fire area
from FA7-203 to fire
zone FA7-203-01.
0
CTS-01518
9A.3.104
[9A.3.206]
9A-5
[9A-8]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Changed section from
9A.3.104 to 9A.3.206
and changed fire area
from FA7-204 to fire
zone FA7-204-01.
0
CTS-01516
9A.3.104
[9A.3.206]
9A-5
[9A-8]
Correction
Changed “exceed” to
“exceeding”
0
9_11
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
CTS-01516
9A.3.104
[9A.3.206]
9A-5
[9A-9]
Correction
Added 3.2.1.j.
CTS-01518
9A.3.104
[9A.3.206]
9A-6
[9A-9]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Deleted “The electrical
circuits from other
safety trains in this
area will be protected
by a one-hour fire
rated wrap.”
0
CTS-01518
9A.3.207
[New]
9A-6
[9A-10,
9A-11]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Added new Subsection
9A.3.207, FA7-204-02
B-ESW Piping Room.
0
CTS-01518
9A.3.105
[9A.3.208]
9A-6
[9A-11]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Changed section from
9A.3.105 to 9A.3.208
and changed fire area
from FA7-205 to fire
zone FA7-205-01.
0
9_12
Change Summary
Rev.
of
FSAR
T/R
0
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
CTS-01516
9A.3.105
[9A.3.208]
9A-6
[9A-11]
Correction
Changed “D” to “C or
D.”
CTS-01516
9A.3.105
[9A.3.208]
9A-6
[9A-11]
Correction
Changed “exceed” to
“exceeding”
0
CTS-01516
9A.3.105
[9A.3.208]
9A-6
[9A-12]
Correction
Added 3.2.1.j.
0
CTS-01518
9A.3.209
[New]
9A-7
[9A-13,
9A-14]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Added new Subsection
9A.3.209, FA7-205-02
B-UHS Transfer Piping
Room.
0
9_13
Change Summary
Rev.
of
FSAR
T/R
0
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
CTS-01518
9A.3.106
[9A.3.210]
9A-7
[9A-14]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Changed section from
9A.3.106 to 9A.3.210
and changed fire area
from FA7-206 to fire
zone FA7-206-01.
CTS-01518
9A.3.107
[9A.3.211]
9A-8
[9A-15]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Changed section from
9A.3.107 to 9A.3.211
and changed fire area
from FA7-207 to fire
zone FA7-207-01.
0
CTS-01516
9A.3.107
[9A.3.211]
9A-8
[9A-15]
Correction
Changed “exceed” to
“exceeding”
0
CTS-01516
9A.3.107
[9A.3.211]
9A-9
[9A-15]
Correction
Added 3.2.1.j.
0
9_14
Rev.
of
FSAR
T/R
0
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
CTS-01518
9A.3.107
[9A.3.211]
9A-9
[9A-16]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Deleted “The electrical
circuits from other
safety trains in this
area will be protected
by a one-hour fire
rated wrap.”
CTS-01518
9A.3.212
[New]
9A-9
[9A-16,
9A-17,
9A-18]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Added new Subsection
9A.3.212, FA7-207-02
C-ESW Piping Room.
0
CTS-01518
9A.3.108
[9A.3.213]
9A-10
[9A-18]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Changed section from
9A.3.108 to 9A.3.213
and changed fire area
from FA7-208 to fire
zone FA7-208-01.
0
CTS-01516
9A.3.108
[9A.3.213]
9A-10
[9A-18]
Correction
Changed “A” to “A or
B.”
0
9_15
Rev.
of
FSAR
T/R
0
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
CTS-01516
9A.3.108
[9A.3.213]
9A-10
[9A-18]
Correction
Changed “exceed” to
“exceeding”
CTS-01516
9A.3.108
[9A.3.213]
9A-10
[9A-18]
Correction
Added 3.2.1.j.
0
CTS-01518
9A.3.214
[New]
9A-11
[9A-19,
9A-20]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Added new Subsection
9A.3.214, FA7-208-02
C-UHS Transfer Piping
Room.
0
CTS-01518
9A.3.109
[9A.3.215]
9A-11
[9A-20]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Changed section from
9A.3.109 to 9A.3.215
and changed fire area
from FA7-209 to fire
zone FA7-209-01.
0
9_16
Change Summary
Rev.
of
FSAR
T/R
0
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
CTS-01518
9A.3.110
[9A.3.216]
9A-12
[9A-21]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Changed section from
9A.3.110 to 9A.3.216
and changed fire area
from FA7-210 to fire
zone FA7-210-01.
CTS-01516
9A.3.110
[9A.3.216]
9A-12
[9A-21]
Correction
Changed “exceed” to
“exceeding”
0
CTS-01516
9A.3.110
[9A.3.216]
9A-12
[9A-22]
Correction
Added 3.2.1.j.
0
CTS-01518
9A.3.110
[9A.3.216]
9A-13
[9A-23]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Deleted “The electrical
circuits from other
safety trains in this
area will be protected
by a one-hour fire
rated wrap.”
0
9_17
Rev.
of
FSAR
T/R
0
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
0
CTS-01518
9A.3.217
[New]
9A-13
[9A-23,
9A-24]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Added new Subsection
9A.3.217, FA7-210-02
D-ESW Piping Room.
CTS-01516
9A.3.111
[9A.3.218]
9A-13
[9A-24]
Correction
Changed section from
9A.3.111 to 9A.3.218
and changed fire area
from FA7-211 to fire
zone FA7-211-01.
0
CTS-01516
9A.3.111
[9A.3.218]
9A-13
[9A-24]
Correction
Changed “A” to “A or
B.”
0
CTS-01516
9A.3.111
[9A.3.218]
9A-13
[9A-24]
Correction
Changed “exceed” to
“exceeding”
0
9_18
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
CTS-01516
9A.3.111
[9A.3.218]
9A-13
[9A-25]
Correction
Added 3.2.1.j.
CTS-01518
9A.3.219
[New]
9A-14
[9A-26,
9A-27]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Added new Subsection
9A.3.219, FA7-211-02
D-UHS Transfer Piping
Room.
0
CTS-01518
9A.3.112
[9A.3.220]
9A-14
[9A-27]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Changed section from
9A.3.112 to 9A.3.220
and changed fire area
from FA7-212 to fire
zone FA7-212-01.
0
CTS-01518
9A.3.113
[9A.3.221]
9A-15
[9A-28]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Changed subsection
9A.3.113 to 9A.3.221
0
9_19
Change Summary
Rev.
of
FSAR
T/R
0
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
CTS-01518
9A.3.114
[9A.3.222]
9A-17
[9A-29]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Changed subsection
9A.3.114 to 9A.3.222
CTS-01518
Table 9A201
[Sheet 1,2 of
2]
9A-19
[9A-31,
9A-32]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Revised table to
include new fire zones.
0
CTS-01518
Table 9A202
(Sheet 1
through 25
of 25 [Sheet
1 through 33
of 33])
9A-20 –
9A-44
[9A-33
through
9A-65]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
Revised summary
sheets associated with
Fire Areas FA7-201
through 212 to reflect
new fire zone
information
0
CTS-01518
Table 9A203
[Sheet 1,2 of
2]
9A-45
[9A-66,
9A-67]
Design change
as described in
Supplemental
Response to
RAI No. 254
(ML12334A026)
and the ISCP
(ML
12268A413).
9_20
Change Summary
Revised summary
sheets for Fire Zones
FA7-301-01 through 13
to reflect revised FHA
section.
Revised table to
include new fire zones.
Rev.
of
FSAR
T/R
0
0
Change ID No.
CTS-01519
Section
FSAR
Rev. 3
Page
Reason for
change
Figure 9A201
9A-46
[9A-68]
Design change
as described in
Luminant ISCP
Letter
ML12268A413
and
Supplemental
Responses to
RAIs No. 243
(ML12243A456)
and No. 254
(ML12334A026)
Change Summary
Figure is revised to
reflect:
Rev.
of
FSAR
T/R
0
Integration of the north
portions of the ESWPT
into the south side of
the UHSRS.
Integration of adjacent
UHSRS (C and D) and
(A and B) on a single
foundation.
ESW Pump House
layout changes
described in responses
to RAIs 243 S01 and
254 S03.
New fire areas for
ESW Piping Room and
UHS Transfer Piping
Room
CTS-01519
Figure 9A202
9A-47
[9A-69]
Design change
as described in
Luminant ISCP
Letter
ML12268A413
and
Supplemental
Responses to
RAIs No. 243
(ML12243A456)
and No. 254
(ML12334A026)
9_21
Revised roadway north
of Transformer Yard.
0
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
1
MIC-03-09-00013
9.2.5.2.3
9.2-17
9.2-18
[9.2-20
9.2-21]
Consistency with
DCD change
Updated heat loads to
be consistent with
associated DCD
changes.
CTS-01529
9.2.5.3
9.2-18
[9.2-21]
Editorial
correction
Replaced “type” with
“types” in section
9.2.5.3.
1
CTS-01532
9.5.2.2.2.2
9.5.2.2.5.1
9.5-19
9.5-20
Address COL
item, COL 1.9(6)
2
RCOL2_01.05-3 S01
9.5.2.2.2.2
9.5.2.2.5.1
9.5-19
9.5-20
Supplemental
Response to
RAI No. 261
Luminant Letter
no.TXNB-13026
Date 8/1/2013
Description was added
to address BDBEE
design enhancement,
including satellite
telephone system,
ENS transfer to
satellite telephone
system and external
communication links
list to satellite
telephone links.
Description was added
to address BDBEE
design enhancement,
including satellite
telephone system,
ENS transfer to
satellite telephone
system and external
communication links
list to satellite
telephone links.
2
*Page numbers for the attached marked-up pages may differ from the revision 3 page numbers due to text additions
and deletions. When the page numbers for the attached pages do differ, the page number for the attached page is
shown in brackets.
9_22
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
include telephone, radio frequency system, privately-owned microwave and fiber
optic systems, broadband (internet), and personal cell phone.
9.5.2.2.2
STD COL 9.5(4)
STD COL 9.5(5)
Private Automatic Branch Telephone Exchange (PABX)
Replace the third sentence in DCD Subsection 9.5.2.2.2 with the following.
Access to commercial facilities such as central office trunk, utility’s private
network, and other offsite connections are provided though redundant and diverse
routes as discussed in Subsection 9.5.2.2.2.2 and 9.5.2.2.5.1.
9.5.2.2.2.2
STD COL 9.5(4)
STD COL 9.5(5)
Emergency Telephones
Add the following paragraphs to the end of the DCD Subsection 9.5.2.2.2.2.
Direct communications links (direct telephone) are provided to the NRC
Operations Center, the State Emergency Operations Center, and the Central
Emergency Operations Center. A crisis management radio system is provided
which meets the intent of NUREG 0654 is discussed in Subsection 9.5.2.2.5.2.
The Emergency Notification System (ENS) capability is part of the Federal
Telecommunication System (FTS) independent phone link, with extensions in the
Main Control Room (MCR), Technical Support Center (TSC) and Emergency
Operations Facility (EOF). The FTS extensions in the MCR, TSC and EOF are all
part of the emergency communications capability of the Private Automatic Branch
Telephone Exchange (PABX).
CP COL 1.9(6)
The ENS is connected through a local telephone company system through a
switch that is located and maintained at the site. Power is provided from a
non-safety related uninterruptible power supply (UPS) system capable of
operating in the event of a LOOP. The design provides for the ENS to remain
functional from the site to the NRC Operations Center in the event of a LOOP at
the site and complies with the requirements of IE Bulletin 80-15. Upon failure of a CTS-01532
local telephone company system, the ENS will transfer to the satellite telephone RCOL2_01.0
5-3 S01
system described in Subsection 9.5.2.2.2.4.
9.5-19
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
9.5.2.2.5.1
CP COL 9.5(4)
General
Replace the first and second sentence of the first paragraph in DCD Subsection
9.5.2.2.5.1 with the following.
Plant specific redundant external communication links include.
CP COL 1.9(6)
•
Copper and fiber optic telephone circuits
•
Microwave telephone links
•
Fiber optic data links
•
Emergency radio communication links
•
Direct telephone links to utility operations centers, the NRC, and State and
Local Emergency Operations facilities
•
Satellite telephone links
•
Personal cell phone links (no credit is taken but these links provide
alternate links which allow for additional communication paths)
9.5.2.2.5.2
STD COL 9.5(6)
STD COL 9.5(8)
Emergency Communications
Replace the second and third sentence of the second paragraph in DCD
Subsection 9.5.2.2.5.2 with the following.
The effectiveness of the overall emergency response plan is in conformance with
the requirements of 10 CFR 50.47 (b)(8). Adequate communications equipment
are provided and maintained to allow the control room to communicate with offsite
personnel and organizations. Pursuant to the emergency response plan, the
following equipment is tested.
•
An inspection and test is performed of the TSC voice communication
equipment.
•
An inspection and test is performed of the operation support center voice
communication equipment.
•
An inspection and test is performed of the EOF voice communication
equipment.
•
A test is performed of the means for warning or advising onsite individuals
of an emergency.
The offsite communications systems within the onsite Technical Support Center
provide for emergency response following a design basis accident. During
emergencies, the TSC is the primary onsite communication center for the
communications to the control room, the operations support center and the NRC.
9.5-20
Revision 3
CTS-01532
RCOL2_01.0
5-3 S01
Chapter 10
Chapter 10 Tracking Report Revision List
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
RCOL2_12.0312.04-11 S04
10.4.8.2.1
10.4-7
through
10.4-8
Supplemental
04 Response
to RAI No.
135
Luminant
Letter no.
TXNB-12042
Date
12/6/2012
Revised to refer to
Figures 12.3-201 and
12.3-202
Rev.
of
FSAR
T/R
-
*Page numbers for the attached marked-up pages may differ from the revision 3 page numbers due to text additions
and deletions. When the page numbers for the attached pages do differ, the page number for the attached page is
shown in brackets.
10_1
Chapter 11
Chapter 11 Tracking Report Revision List
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for change
Change Summary
RCOL2_03.03.029
11.4.2.3
11.4-3
Response to RAI
No. 250
Luminant Letter
no.TXNB-12032
Date 9/14/2012
Revised to incorporate
RG 1.221.
RCOL2_12.0312.04-11 S04
11.2.3.4
11.2-8
Supplemental 04
Response to RAI
No. 135
Luminant Letter
no.TXNB-12042
Date 12/6/2012
Clarified the description
of the piping run for
Unit 3 and Unit 4.
Rev.
of
FSAR
T/R
-
-
*Page numbers for the attached marked-up pages may differ from the revision 3 page numbers due to text additions
and deletions. When the page numbers for the attached pages do differ, the page number for the attached page is
shown in brackets.
11_1
Chapter 12
Chapter 12 Tracking Report Revision List
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
-
RCOL2_12.0312.04-11 S04
12.3.6
12.3-4
Supplemental 04
Response to RAI
No. 135
Luminant Letter
no.TXNB-12042
Date 12/6/2012
Added Figure 12.3-202.
RCOL2_12.0312.04-11 S04
Table 12.3201 (Sheets
1, 4 of 5)
12.3-6,
12.3-9
Supplemental 04
Response to RAI
No. 135
Luminant Letter
no.TXNB-12042
Date 12/6/2012
Clarified the description
of the piping run for Unit
3 and Unit 4.
-
RCOL2_12.0312.04-11 S04
Figure 12.3201
12.3-12
Supplemental 04
Response to RAI
No. 135
Luminant Letter
no.TXNB-12042
Date 12/6/2012
Clarified the description
of the piping run from the
T/B to the yard.
-
RCOL2_12.0312.04-11 S04
Figure 12.3202 (New
Figure)
[12.313]
Supplemental 04
Response to RAI
No. 135
Luminant Letter
no.TXNB-12042
Date 12/6/2012
-
CTS-01510
Figure
12.3-1R
(Sheet 1 of
34)
12.3-11
Consistency with
DCD as described
in Letter.
TXNB-12033
(ML12268A413)
Revised figure to show
that it is now only
applicable to CPNPP Unit
3 and added new figure
for CPNPP Unit 4 yard
piping routing and
building penetration
schematic.
Figure was updated to
reflect standard plant and
site-specific layout
changes.
0
*Page numbers for the attached marked-up pages may differ from the revision 3 page numbers due to text additions
and deletions. When the page numbers for the attached pages do differ, the page number for the attached page is
shown in brackets.
12_1
Chapter 13
Chapter 13 Tracking Report Revision List
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
-
RCOL2_13.04-6
Table 13.4201 (Sheet 6
of 11)
13.4-7
Response to RAI
No. 255
Luminant Letter
no.TXNB-12013
Date 05/31/2012
Deleted 10 CFR 52.78
has as a Program
Source for Item 11,
Program Title, “Non
licensed Plant Staff
Training Program” in
FSAR Table 13.4-201.
RCOL2_01.05-3
13.3.2
13.3-1
Response to RAI
No. 261
Luminant Letter
no.TXNB-12027
Date 7/24/2012
Added evaluation of
emergency staffing in
accordance with NEI
12-01
13.3.5 (new
section)
13.3-2
RCOL2_13.06.0160
13.6
13.6-1
Response to RAI
No. 270
Luminant Letter
no.TXNB-13017
Date 5/28/2013
Added a new
paragraph to the end
of Section 13.6
-
CTS-01532
13.2.1.1.2
13.2-2
Editorial
correction
“Subsection” was
changed to
“Subsections”.
2
CTS-01532
13.2.1.1.3
(New
13.2.1.1.4)
13.2-2
EA-12-049,
Resolution of
new COL items
1.9(2)-4, 1.9(2)-5
and 1.9(4)
Added a new section
on training on
mitigation of BDB
external events
2
-
Added reference to the
NEI 12-01
13_1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
2
RCOL2_01.05-2
S01
13.2.1.1.3
(New
13.2.1.1.4)
13.2-2
Supplemental
Response to RAI
No. 261
Luminant Letter
no.TXNB-13026
Date 8/1/2013
Added a new section
on training on
mitigation of BDB
external events
RCOL2_01.05-3
13.3.2
13.3-1
[13.3-2]
Supplemental
Response to RAI
No. 261
Luminant Letter
no.TXNB-13026
Date 8/1/2013
A paragraph was
added on action
regarding staffing
reevaluation for BDB
event.
2
CTS-01532
13.3.2
13.3-1
[13.3-2]
NTTF
recommendation
9.3.1.2,
Resolution of
new COL item
COL 1.9(7)
A paragraph was
added on action
regarding staffing
reevaluation for BDB
event.
2
R0COL2_01.05-3
13.3.4
(New 13.3.5)
13.3-2
[13.3-3]
Supplemental
Response to RAI
No. 261
Luminant Letter
no.TXNB-13026
Date 8/1/2013
A section was added
for reference.
2
CTS-01532
13.3.4
(New 13.3.5)
13.3-2
[13.3-3]
Associated
change with
resolution of new
COL item COL
1.9(7)
A section was added
for reference.
2
CTS-01532
Table 13.4201 (Sheet 7
of 11)
13.4-8
Resolution of
new COL item
COL 1.9(4)
LMN STD COL 1.9(4)
was added to Item 12.
2
13_2
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
2
CTS-01532
13.5.2.1
13.5-4
NTTF
recommendation
8,
Resolution of
new COL item
COL 1.9(5)
A paragraph was
added on action
regarding EOP for
BDB external events.
RCOL2_01.05-2
S01
13.5.2.2
13.5-5
[13.5-6]
Supplemental
Response to RAI
No. 261
Luminant Letter
no.TXNB-13026
Date 8/1/2013
Paragraphs were
added on action
regarding development
of procedures for
maintenance, testing
and calibration of SFP
instruments.
2
CTS-01532
13.5.2.2
13.5-5
[13.5-6]
EA-12-049,
EA-12-051,
NTTF
recommendation
8,
Resolution of
new COL items
1.9(2)-4, 1.9(2)5, 1.9(4) and
1.9(5)
Paragraphs were
added on action
regarding development
of procedures for
maintenance, testing
and calibration for SFP
instruments,
equipment for BDB
events and emergency
procedures.
2
*Page numbers for the attached marked-up pages may differ from the revision 3 page numbers due to text additions
and deletions. When the page numbers for the attached pages do differ, the page number for the attached page is
shown in brackets.
13_3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
senior management using the guidance provided by ACAD 08-001 (Ref.
13.2-202), “The Process for Initial Accreditation of Training in the Nuclear Power
Industry.” FSAR Figure 13.1-205 depicts anticipated milestone dates to support
initial fuel load.
13.2.1.1.1
Licensed Plant Staff Training Program
Replace the content of DCD Subsection 13.2.1.1.1 with the following.
The content of this subsection is discussed above.
13.2.1.1.2
Non-Licensed Plant Staff Training Program (to be verified
during construction)
Replace the content of DCD Subsection 13.2.1.1.2 with the following.
The content of this subsection is discussed above.
CTS-01532
Add the following Subsections after DCD Subsection 13.2.1.1.2.
13.2.1.1.3
Hazards Awareness Training
Workers and operators will receive initial and annual refresher training for
protection from chemical hazards and confined space entry in accordance with 29
CFR 1910. As part of this training, operators receive training for response to toxic
gas release events.
13.2.1.1.4
Training on Mitigation of Beyond-Design-Basis External Event CTS-01532
Workers and operators will receive initial and refresher training for responding to
CP COL 1.9(2)-5 beyond-design-basis (BDB) external events and multiunit events based on the
criteria established for Emergency Planning. Training requirements are
established that are necessary to maintain, calibrate, and test equipment and
support the effective implementation of the EP exercise objectives.
CP COL 1.9(2)-4
CP COL 1.9(4)
Licensed and non-licensed staff are trained in the use of the primary and backup RCOL2_01.0
5-2 S01
SFP level instrument channels including the provision for alternate power. A
training program is developed and implemented to maintain available and reliable
the SFP level instrumentation.
13.2.1.2
Coordination with Preoperational Tests and Fuel Loading
Replace the content of DCD Subsection 13.2.1.2 with the following.
The content of this subsection is discussed above.
13.2.2
Applicable Nuclear Regulatory Commission Documents
Replace the content of DCD Subsection 13.2.2 with the following.
The content of this subsection is discussed above.
13.2-2
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
13.3
EMERGENCY PLANNING
This section of the referenced DCD is incorporated by reference with the following
departures and/or supplements.
STD COL 13.3(1)
Replace the fourth sentence of the first paragraph in the DCD Subsection 13.3
with the following.
Interfaces of design features with site specific designs and site parameters are
addressed in Combined License Application Part 5 “Emergency Plan”.
STD COL 13.3(7)
Add the following paragraph to the end of DCD Section 13.3.
The description of the operation support center is provided in Combined License
Application Part 5 “Emergency Plan”.
13.3.1
CP COL 13.3(2)
Combined License Application and Emergency Plan Content
Replace the first and second sentence of the first paragraph in the DCD
Subsection 13.3.1 with the following.
The Emergency Plan for the CPNPP Units 3 and 4 is provided in Combined
License Application Part 5 “Emergency Plan”. The Emergency Plan is developed
in accordance with 10 CFR 50.47 Appendix E and 10 CFR 52.
STD COL 13.3(3)
STD COL 13.3(4)
Replace the second paragraph in the DCD Subsection 13.3.1 with the following.
Emergency classifications and action levels, and the security-related aspects of
emergency planning are addressed in Combined License Application Part 5
“Emergency Plan”.
13.3.2
CP COL 13.3(5)
Emergency Plan Considerations for Multi-Unit Site
Replace the sentence in the DCD Subsection 13.3.2 with the following.
The interface between the Emergency Plan for CPNPP Units 3 and 4 and the
Emergency Plan for CPNPP Units 1 and 2 is addressed in the CPNPP Units 3 and
4 Combined License Application Part 5 “Emergency Plan”.
CP COL 1.9(7)
Prior to the full participation exercise milestone in Table 13.4-201, an evaluation
(including staffing) will be completed and implemented in accordance with NEI
13.3-1
Revision 3
RCOL2_01.0
5-3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 13.3(6)
12-01 (Ref. 13.3-201), including changes to the Emergency Plan and FSAR, as
necessary.
RCOL2_01.0
5-3
13.3.3
CTS-01532
Emergency Planning Inspections, Tests, Analyses, and
Acceptance Criteria
Replace the sentence in the DCD Subsection 13.3.3 with the following.
Emergency planning inspections, tests, analyses, and acceptance criteria are
addressed in the CPNPP Units 3 and 4 Combined License Application Part 5
“Emergency Plan” and are provided in the CPNPP Units 3 and 4 Combined
License Application Part 10 “ITAAC and ITAAC Closure”.
13.3.4
Combined License Information
Replace the content of DCD Subsection 13.3.4 with the following.
STD COL 13.3(1)
13.3(1) Interfaces of design features with site specific designs and site
parameters
This COL item is addressed in Section 13.3.
CP COL 13.3(2)
13.3(2) Comprehensive emergency plan
This COL item is addressed in Subsection 13.3.1.
STD COL 13.3(3)
13.3(3) Emergency classification and action level scheme
This COL item is addressed in Subsection 13.3.1.
STD COL 13.3(4)
13.3(4) Security-related aspects of emergency planning
This COL item is addressed in Subsection 13.3.1.
CP COL 13.3(5)
13.3(5) Multi-unit site interface plan depending on the location of the new reactor
on, or near, an operating reactor site with an existing emergency plan
This COL item is addressed in Subsection 13.3.2.
CP COL 13.3(6)
13.3(6) Emergency planning inspections, tests, analyses, and acceptance criteria
This COL item is addressed in Subsection 13.3.3.
STD COL 13.3(7)
13.3(7) Operation support center
This COL item is addressed in Section 13.3.
13.3.5
RCOL2_01.0
5-3
References
Add the following reference after the last reference in DCD Subsection 13.3.5.
13.3-2
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 1.9(7)
13.3-201
Guideline for Assessing Beyond Design Basis Accident Response RCOL2_01.0
Staffing and Communications Capabilities, NEI 12-01, Revision 0, 5-3
CTS-01532
Nuclear Energy Institute, May 2012.
13.3-3
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 13.4-201 (Sheet 7 of 11)
CP COL 13.4(1)
Operational Programs Required by NRC Regulation and Program Implementation
Item
STD COL 13.6(1)
STD COL 1.9(4)
12.
Program Title
For elements of Fire
Protection Program, Security
Program and Radiation
Protection Program prior to
full program implementation.
Reactor Operator Training
Program
Program Source
(Required By)
10 CFR 70.22
10 CFR 55.13
FSAR (SRP)
Section
Implementation
Milestone
Prior to implementation of the
program elements
Requirement
10 CFR 70.22 (a)
13.2.1
18 months prior to scheduled
fuel load
License Condition
13.2.1
Within 3 months after
issuance of an operating
license or the date the
Commission makes the
finding under 10 CFR
52.103(g)
10 CFR 50.54 (i-1)
Full participation exercise
conducted within 2 years of
scheduled date for initial
loading of fuel.
10 CFR 50, Appendix
E.IV.F.2a(ii)
Onsite exercise conducted
within 1 year before the
schedule date for initial
loading of fuel.
10 CFR 50, Appendix
E.IV.F.2a(ii)
10 CFR 55.31
10 CFR 55.41
10 CFR 55.43
10 CFR 55.45
13.
Reactor Operator
Requalification Program
10 CFR 50.34(b)
10 CFR 50.54(i)
10 CFR 55.59
14.
Emergency Planning
10 CFR 50.47
13.3
10 CFR 50, Appendix E
13.4-8
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
maintenance, and other instructions appropriate for operation of systems
important to safety.
•
General Plant Procedures - These procedures provide instructions for the
integrated operation of the plant (e.g., startup, shutdown, power operation
and load changing, process monitoring, fuel handling, maintenance,
surveillance, and periodic testing).
•
Abnormal Condition Procedures - These procedures specify operator
actions for restoring an operating variable to its normal controlled value
when it departs from its normal range, or restoring normal operating
conditions following a transient. Such actions are invoked following an
operator observation or an annunciator alarm indicating a condition that, if
not corrected, could degenerate into a condition requiring action under an
Emergency Operating Procedure.
•
Emergency Operating Procedures (EOPs) – These procedures direct
actions necessary for the operators to mitigate the consequences of
transients and accidents that cause plant parameters to exceed reactor
protection system or engineering safety feature actuation setpoints.
The Procedure Generation Package (PGP) will be developed and
provided to the NRC at least three months prior to commencing formal
operator training on the EOPs. The PGP will include a detailed description
of the process for developing the Plant-Specific Technical Guidelines
(P-STGs) from the US-APWR generic technical guidelines, a plant-specific
writer’s guide that details the specific methods for preparing the EOPs
based on the P-STGs, a description of the program for verfication and
validation (V&V) of the EOPs and a brief description of the operator
training program for the EOPs (See NUREG-0737, Supplement 1). The
PGP development process also includes the identification of safety
significant deviations from the generic technical guidelines (including the
identification of additional equipment beyond that identified in the generic
technical guidelines) and engineering evaluations or analyses as
necessary to support the adequacy of each deviation. In accordance with
the human factors program summarized in DCD Section 18.8, the PGP
describes the process used to identify operator information and control
requirements.
The EOPs are symptom-based with clearly specified entry and exit
conditions. Transitions between and within the normal operating, alarm
response, and abnormal operating procedures and the EOPs are
appropriately laid out, well defined, and easy to follow (See Section 18.8).
The use of human factored, functionally oriented, EOPs will improve
human reliability and the ability to mitigate the consequence of a broad
range of initiating events and subsequent multiple failures or operator
errors, without the need to diagnose specific events.
CP COL 1.9(5)
The EOPs are developed with consideration given to mitigative features
for beyond-design-basis (BDB) external events and multiunit events.
13.5-4
Revision 3
CTS-01532
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
The general objectives of the EOP V&V process are to ensure the EOPs:
•
-
correctly reflect the generic technical guidelines
-
reflect the procedure writer’s guide
-
are useable
-
correctly refer to controls, equipment and indications
-
provide language and level of information consistent with minimum
staff qualifications and composition
-
provide a high level of assurance they will effectively guide the
operator in mitigating transients and accidents.
Alarm Response Procedures – These procedures guide operator actions
for responding to plant alarms.
13.5.2.2
STD COL 13.5(7)
Maintenance and Other Operating Procedures
Replace the content of DCD Subsection 13.5.2.2 with the following.
The following maintenance and other operating procedures are classified as
General Plant Procedures:
•
Plant Radiation Protection Procedures - Detailed written and approved
procedures and instructions are used to ensure that occupational
radiation exposure is maintained ALARA. It is the responsibility of the
Radiation and Industrial Safety Manager to prepare and maintain the
plant radiation protection procedures and instructions. Careful
administrative control of the use of these procedures and instructions
ensures that a sound health physics philosophy becomes an integral part
of station operation and maintenance.
•
Emergency Preparedness Procedures - The Emergency Planning
Manager is responsible for preparing and maintaining procedures that
implement the protective measures outlined in the Emergency Plan.
RCOL2_01.0
Procedures are established and maintained for the use of the primary and 5-2 S01
backup spent fuel pool instrument channels and for the equipment needed CTS-01532
to mitigate BDB external events, including portable equipment. Emergency
procedures including EOPs, SAMGs and EDMGs address BDB external
events.
•
Instrument Calibration and Test Procedures - The Director, Maintenance is
responsible for preparing procedures and instructions for proper control
and periodic calibration of plant measuring and test equipment to maintain
accuracy within necessary limits and to confirm adequacy of calibration
frequency. Specific procedures are prepared for surveillance tests
performed on safety-related equipment and instrumentation. These
CP COL 1.9(2)-4
CP COL 1.9(2)-5
CP COL 1.9(4)
CP COL 1.9(5)
13.5-5
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
procedures have provisions for assuring measurement accuracies are
adequate to keep safety parameters within operational and safety limits.
CTS-01532
Processes and procedures are established and maintained for scheduling
RCOL2_01.0
and implementing necessary testing, maintenance and calibration of the
primary and backup spent fuel pool level instrument channels to maintain 5-2 S01
the instrument channels at the design accuracy and for equipment needed
to mitigate BDB external events including portable equipment.A master
surveillance schedule reflecting the status of all planned in-plant
surveillance testing is maintained. Control measures exist to assure
appropriate documentation, reporting, and evaluation of test results.
CP COL 1.9(2)-4
CP COL 1.9(4)
•
Chemical/Radiochemical Control Procedures - The preparation of
detailed, written, and approved chemical and radiochemical procedures
and instructions are the responsibility of the Chemistry Manager. These
procedures and instructions ensure primary and secondary side
chemical/radiochemical quality, protection of component integrity, and
promotion of efficient plant operation.
•
Radioactive Waste Management Procedures - It is the responsibility of the
Radiation and Industrial Safety Manager to prepare procedures and
instructions for the operation of radioactive liquid, solid, and gaseous
waste systems and provide guidance for collection, storage, processing,
and discharge of these materials. Radioactive waste management is
incorporated into these procedures to support the effort to minimize
radiation exposure and precisely control the release of radioactive material
to the environment.
•
Maintenance and Modification Procedures - Maintenance or modification
that may affect the functioning of safety-related SSCs are performed in
accordance with applicable codes, bases, standards, design
requirements, material specifications, and inspection requirements.
Maintenance of safety-related equipment is pre-planned and performed in
accordance with written procedures, written instructions, or drawings
appropriate to the circumstances. Skills normally possessed by qualified
maintenance personnel may not require detailed step-by-step delineation
in a written procedure. It is the responsibility of the Director, Maintenance,
to implement a maintenance program for safety-related mechanical and
electrical equipment and instruments and controls.
•
Material Control Procedures - The Director, Oversight, and Nuclear
Overview, is responsible for preparing procedures and instructions for the
proper procurement, documentation, and control of safety-related
materials and components necessary for plant maintenance and
modification. The procedures will be sufficiently detailed to ensure that
purchased materials and components associated with safety-related
structures or systems are as follows:
-
Purchased to specifications and codes that ensure performance at
least equivalent to the original equipment.
-
Produced or fabricated under quality control that ensures
performance at least equivalent to that of the original equipment.
13.5-6
Revision 3
Chapter 14
Chapter 14 Tracking Report Revision List
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
RCOL2_09.02.01-6
14.2.12.1.113
14.2-5
Response to RAI
No. 251
Luminant Letter
no.TXNB-12016
Date 05/31/2012
Revised item A.2 to
clarify that ESW
pumps and UHS
transfer pumps are
demonstrated to have
adequate NPSH and
no vortex formation at
minimum basin water
level.
RCOL2_14.02-21
14.2.12.1.113 14.2-5
Response to RAI
No. 257
Luminant Letter
no.TXNB-12022
Date 6/21/2012
Clarified preoperational
test objectives,
methods, and
acceptance criteria.
14.2-6
[14.2-7]
RCOL2_14.02-20
14.2.12.1.113
14.2-5
through
14.2-6
[14.2-5
through
14.2-7]
Response to RAI
No. 256
Luminant Letter
no.TXNB-12026
Date 7/20/2012
RCOL2_09.02.01-9
S01
14.2.12.1. 113
14.2-5
through
14.2-6
[14.2-5
through
14.2-7]
Supplemental 01
Response to RAI
No. 251
Luminant Letter
no.TXNB-12031
Date 9/10/2012
RCOL2_14.02-21
S01
14.2.12.1.113
14.2-6
Supplemental
Response to RAI
No. 257
Luminant Letter
no.TXNB-12034
Date 9/24/2012
14_1
Change Summary
Added preoperational
test acceptance criteria
for water hammer
prevention.
An item is added to the
UHSS preoperational
test (14.2.12.1.113) to
verify the ability of the
UHS, in conjunction
with the ESWS,
CCWS, and RHRS, to
cool down the RCS.
Removed description
of level switches
located in the UHS
cooling tower riser
piping.
An items is added to
the UHSS
preoperational test
(14.2.12.1.113) to
verify the function of
the newly added drain
valves for freeze
protection.
Rev.
of
FSAR
T/R
-
-
-
-
-
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
-
RCOL2_09.02.0520 S02
14.2.12.1.113
14.2-5
14.2-6
Supplemental 02
Response to RAI
No. 252
Luminant Letter
no.TXNB-12036
Date 11/12/2012
Revised UHS
Preoperational Test to
include simultaneous
operation of ESWP
and UHS Transfer
Pump with no
interfering vortices.
RCOL2_14.02-21
S02
14.2.12.1.113
14.2-6
[14.2-7]
Supplemental 02
Response to RAI
No. 257
Luminant Letter
no.TXNB-12036
Date 11/12/2012
Corrected to remove
reference to electrical
heat tracing.
-
RCOL2_09.02.01-9
S02
14.2.12.1.113
14.2-5,
14.2-6
[14.2-5
through
14.2-7]
Supplemental 02
Response to RAI
No. 251
Luminant Letter
no.TXNB-12041
Date 12/03/2012
Revise the description
about water hammer/
voids in the spray
header or nozzles.
-
*Page numbers for the attached marked-up pages may differ from the revision 3 page numbers due to text additions
and deletions. When the page numbers for the attached pages do differ, the page number for the attached page is
shown in brackets.
14_2
Chapter 15
Chapter 15 Tracking Report Revision List
Change ID
No.
Section
FSAR
Rev. 3
Page
Reason for change
Change Summary
Rev.
of
FSAR
T/R
*Page numbers for the attached marked-up pages may differ from the revision 3 page numbers due to text additions
and deletions. When the page numbers for the attached pages do differ, the page number for the attached page is
shown in brackets.
15_1
Chapter 16
Chapter 16 Tracking Report Revision List
Change ID
No.
Section
FSAR
Rev. 3
Page
Reason for change
Change Summary
Rev.
of
FSAR
T/R
*Page numbers for the attached marked-up pages may differ from the revision 3 page numbers due to text additions
and deletions. When the page numbers for the attached pages do differ, the page number for the attached page is
shown in brackets.
16_1
Chapter 17
Chapter 17 Tracking Report Revision List
Change ID
No.
Section
FSAR
Rev. 3
Page
Reason for change
Change Summary
Rev.
of
FSAR
T/R
*Page numbers for the attached marked-up pages may differ from the revision 3 page numbers due to text additions
and deletions. When the page numbers for the attached pages do differ, the page number for the attached page is
shown in brackets.
17_1
Chapter 18
Chapter 18 Tracking Report Revision List
Change ID
No.
Section
FSAR
Rev. 3
Page
Reason for change
Change Summary
Rev.
of
FSAR
T/R
*Page numbers for the attached marked-up pages may differ from the revision 3 page numbers due to text additions
and deletions. When the page numbers for the attached pages do differ, the page number for the attached page is
shown in brackets.
18_1
Chapter 19
Chapter 19 Tracking Report Revision List
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
Rev.
of
FSAR
T/R
-
RCOL2_19-19
19.1.5
19.1-9
Response to RAI
No. 248
Luminant Letter
no.TXNB-12016
Date 05/31/2012
Information for extreme
wind bounding
assessment added for
LPSD and at power
operation.
RCOL2_19-19
Table 19.1205
(Sheets 24
through 25
of 35)
19.1-74
through
19.1-75
Response to RAI
No. 248
Luminant Letter
no.TXNB-12016
Date 05/31/2012
Information added to
address risk from
extreme winds.
-
RCOL2_03.03.02-9
19.1.5
19.1-6
Revised to incorporate
RG 1.221.
-
Table 19.1205 (Sheet
12, 16, 24
of 35)
19.1-62
19.1-66
19.1-74
Response to RAI
No. 250
Luminant Letter
no.TXNB-12032
Date 9/14/2012
19.2-4
Response to RAI
No. 267
Luminant Letter
no.TXNB-12043
Date 12/18/2012
Updated values from
using more recent dollar
values in calculation.
-
19.1-9,
19.1-10
Response to RAI
No. 264
Luminant Letter
no.TXNB-12043
Date 12/18/2012
Clarified screening
criteria used for external
events and results of
screening.
-
19.1-87
RCOL2_19-23
RCOL2_19-21
Table 19.1206 (Sheet
2 of 2)
19.2.6.4
19.2.6.6
19.1.5
19_1
Change ID No.
Section
FSAR
Rev. 3
Page
Reason for
change
Change Summary
RCOL2_19-21
Table 19.1205
(Sheets 24
through 25
of 35)
19.1-74
through
19.1-75
Response to RAI
No. 264
Luminant Letter
no.TXNB-12043
Date 12/18/2012
Updated wording on
extreme wind screening
discussion.
RCOL2_19-22
19.1.5
19.1-5
through
19.1-6,
19.1-10
Response to RAI
No. 264
Luminant Letter
no.TXNB-12043
Date 12/18/2012
Clarified results of
external flooding
screening.
-
RCOL2_19-22
Table 19.1205
(Sheets 27
through 31
of 35)
19.1-77
through
19.1-81
Response to RAI
No. 264
Luminant Letter
no.TXNB-12043
Date 12/18/2012
Updated wording on
external flooding
screening discussion.
-
RCOL2_19-24
19.1.2.3
(New
Subsection)
19.1-2
[19.1-3]
Response to RAI
No. 268
Luminant Letter
no.TXNB-12043
Date 12/18/2012
Clarified expectations on
requirements to
demonstrate technical
adequacy.
19.1.4.1.2
19.1-4
[19.1-5,
19.1-6]
Response to RAI
No. 268
Luminant Letter
no.TXNB-12043
Date 12/18/2012
Capture requirements to
update PRA following
construction to capture
changes.
RCOL2_19-24
19_2
Rev.
of
FSAR
T/R
-
-
-
Change ID No.
RCOL2_19-24
RCOL2_19-25
RCOL2_19-25
RCOL2_19-25
Section
19.3.3
19.1
FSAR
Rev. 3
Page
Reason for
change
Change Summary
19.3-1
[19.3-1,
19.3-2]
Response to RAI
No. 268
Luminant Letter
no.TXNB-12043
Date 12/18/2012
19.1-1
Response to RAI
No. 268
Luminant Letter
no.TXNB-12043
Date 12/18/2012
Updated and expanded
FSAR section crossreferences for risk
informed applications.
Update FSAR location
references for PRA
update requirements.
-
19.1.1.2.1
19.1-1
19.1.1.3.1
(New
Subsection)
19.1-1
[19.1-2]
19.1.1.3.2
(New
Subsection)
19.1.7
(New
Subsection)
19.1-1
[19.1-2]
19.1-13
[19.114,
19.115]
Response to RAI
No. 268
Luminant Letter
no.TXNB-12043
Date 12/18/2012
Updated and expanded
FSAR section crossreferences for risk
informed applications.
Table 19.1207
(Sheets 1,
2 of 2)
(New
Table)
19.1-89
[19.191,
19.192]
Response to RAI
No. 268
Luminant Letter
no.TXNB-12043
Date 12/18/2012
Updated and expanded
FSAR section crossreferences for risk
informed applications.
19_3
Rev.
of
FSAR
T/R
-
-
-
Change ID No.
RCOL2_19-25
Section
19.3.3
FSAR
Rev. 3
Page
19.3-1
Reason for
change
Response to RAI
No. 268
Luminant Letter
no.TXNB-12043
Date 12/18/2012
DCD_16-117
Table 19.1119R
(Sheets 19,
34)
19.1-21
19.1-36
Response to RAI
No. 161
MHI Letter No.
UAP-HF-12022
Date 02/08/2012
DCD_19-494
Table 19.1119R
(Sheet 34)
19.1-36
CTS-01528
19.2.6.6
Table 19.29R
19.2-4
19.2-6
Change Summary
Rev.
of
FSAR
T/R
-
Updated and expanded
FSAR section crossreferences for risk
informed applications.
-
Response to RAI
No. 669
MHI Letter No.
UAP-HF-12023
Date 02/08/2012
Incorporated new key
insights regarding
administrative controls
for AAC and
demineralized water
storage tank during
atpower operation and
SIS during LPSD
operation
Incorporated a new key
insight regarding
administrative controls
for SIS during LPSD
operation
Consistency with
RAI 267
Luminant Letter
no.TXNB-12043
Date 12/18/2012
Maximum averted cost
and SAMA benefit
values at the
corresponding discount
rates were updated.
1
-
*Page numbers for the attached marked-up pages may differ from the revision 3 page numbers due to text additions
and deletions. When the page numbers for the attached pages do differ, the page number for the attached page is
shown in brackets.
19_4
Fly UP