...

Outline Background on SOARCA State-of-the-Art Reactor Consequence Analyses (SOARCA)

by user

on
Category: Documents
3

views

Report

Comments

Transcript

Outline Background on SOARCA State-of-the-Art Reactor Consequence Analyses (SOARCA)
State-of-the-Art Reactor Consequence
Analyses (SOARCA)
Surry Uncertainty Analysis (UA)
Regulatory Information Conference
March 9, 2016
Tina Ghosh, PhD, Accident Analysis Branch
U.S. NRC Office of Nuclear Regulatory Research
Outline
•
•
•
•
•
•
Background
Objectives
Scope and approach
Parameters
Sample of results
Overall conclusions
2
Background on SOARCA
• SOARCA was initiated to develop a body of
knowledge on the realistic outcomes of severe
reactor accidents; two pilot plants.
Peach Bottom
Surry
• SECY-12-0092, “State-of-the-Art Reactor
Consequence Analyses – Recommendation for
Limited Additional Analysis”
– Staff recommended “UA for a severe accident scenario at
Surry”.
3
1
Objectives of the Surry
Uncertainty Analysis
• Develop insight into overall sensitivity of results and
conclusions to uncertainty in inputs.
• Identify the most influential input parameters contributing to
variations in accident progression, source term, and offsite
consequences.
• “Complement and support” the NRC’s Site Level 3 PRA
project and post-Fukushima activities including Tier 3
items. (SRM SECY-12-0092)
4
Scope and Approach
• SOARCA Surry unmitigated short term station blackout
(STSBO) scenario chosen.
• Epistemic (state-of-knowledge) uncertainty in key input
parameter values described with probability distributions.
• Uncertainty in these parameters propagated in a two-step
Monte Carlo process using MELCOR and MACCS.
• Figures of merit investigated: cesium and iodine release,
hydrogen production, early and latent cancer fatality risk.
• Results analyzed with statistical regression based methods,
scatter plots, and phenomenological investigation of
selected individual realizations.
5
MELCOR Uncertain Parameters
Sequence
In-Vessel Accident Progression
•
•
•
•
•
•
•
•
•
•
Primary SV stochastic failure to
close (FTC)
Primary SV stochastic failure to
open (FTO)
Primary SV FTC due to passing
water
Secondary SV stochastic FTC
SV open area fraction (SVOFRAC)
Primary SV FTC due to overheating
Reactor coolant pump seal leakage
(RCPSL)
Normalized temperature of hottest
SG tube (TUBETEMP)
SG tube thickness (mm)
(TUBTHICK)
•
•
•
•
•
•
Zircaloy melt breakout temperature**
(SC1131(2))
Molten clad drainage rate**
(SC1141(2))
Radial molten debris relocation time
constant (RDMTC)
Radial solid debris relocation time
constant (RDSTC)
Time in the fuel cycle of the accident
(BOC, MOC, or EOC) (CYCLE)
Decay Heat (DEV_DEC_HEAT)
Melting temperature of the eutectic
formed between UO2 and ZrO2
(SC1132)
** indicates parameter was uncertain in the Peach Bottom UA
6
2
MELCOR Uncertain Parameters
(continued)
Ex-vessel Accident Progression
Chemical Forms of Iodine and Cesium
•
•
•
•
Hydrogen ignition criteria (H2 LFL)
Steam Generator Tube Rupture
(SGTR) location (for
decontamination factor per
ARTIST) (SGTRLOC)
Aerosol Transport and Deposition
•
Containment Behavior
•
•
•
CHEMFORM iodine** (CHEMFORMI2)
CHEMFORM cesium**
(CHEMORMCS)
Dynamic Shape Factor (PARTSHAPE)
Containment design leakage rate
(DLEAK)
Containment fragility curve (CFC)
Containment convection heat
transfer coefficient (XHTFCL)
** indicates parameter was uncertain in the Peach Bottom UA
7
MACCS Uncertain Parameter
Groups
Deposition
Latent Health Effects
Wet Deposition (CWASH1)
Dry Deposition Velocities (VDEPOS, • Dose and dose rate effectiveness factor
(DDREFA)
m/s)
• Lifetime Cancer Fatality Risk Factors
Dispersion
(CFRISK)
• Crosswind Dispersion Linear
• Long Term Inhalation Dose Coefficients
Coefficient (CYSIGA)
Early Health Effects
•
•
•
•
Vertical Dispersion Linear
Coefficient (CZSIGA)
•
Shielding factors
•
Groundshine Shielding Factors
(GSHFAC)
Inhalation Protection Factors
(PROTIN)
•
•
Early Health Effects LD50 Parameter
(EFFACA)
Early Health Effects Exponential
Parameter (EFFACB)
Early Health Effects Threshold Dose
(EFFTHR)
All of these parameters were uncertain in the SOARCA Peach Bottom UA too
8
MACCS Uncertain Parameters
(continued)
Emergency Response
•
Evacuation Delay (DLTEVA)
•
Evacuation Speed (ESPEED)
•
Hotspot Relocation Time (TIMHOT)
•
Normal Relocation Time (TIMNRM)
•
Hotspot Relocation Dose (DOSHOT)
•
Normal Relocation Dose (DOSNRM)
Aleatory Uncertainty
•
Weather trials
All of these parameters were uncertain in the SOARCA Peach Bottom UA too
9
3
Cesium Release Fraction to
Environment
•
•
There is a clear bifurcation
in the results, with the
higher release fractions
representing SGTR
realizations, and the
remainder of the
realizations having much
lower releases.
The release fractions for
non-SGTR realizations are
almost all below 0.001 at
48 hours, while the SGTR
realizations are in the 0.01
range.
Cesium release fractions over 48 hours with
mean, median, 5th and 95th percentiles
10
Mean, individual, LCF risk (based on
LNT) regression results within a 10mile circular area for all realizations
11
Mean, individual, LCF risk (based on
LNT) regression results within a 10mile circular area for realizations
that do not involve SGTR.
Rank Regression
Quadratic
Recursive
Partitioning
Final R2
0.73
0.83
0.84
R2 contr.
Si
Ti
Si
Ti
Input
SRRC
CYCLE
0.27
0.52
0.14
0.23
0.18
0.55
GSHFAC.2
0.19
0.44
0.22
0.38
0.18
0.54
DLEAK
0.12
-0.33
0.06
0.20
0.03
0.16
CFRISK.8
0.03
0.16
0.04
0.07
0.02
0.14
CYSIGA.1
0.03
-0.18
0.02
0.02
0.01
0.04
VDEPOS.1
0.02
0.12
0.02
0.06
0.01
0.24
PARTSHAPE
0.01
0.09
0.01
0.03
0.00
0.04
CFRISK.7
0.01
0.12
0.02
0.03
0.00
0.02
CFC
0.02
-0.13
0.02
0.03
0.00
0.02
DEV_DEC_HEAT
0.01
-0.08
0.02
0.04
0.00
0.04
CFRISK.6
0.01
0.09
0.02
0.07
0.00
0.04
DDREFA.8
0.01
-0.11
0.01
0.03
0.01
0.03
CHEMFORMCS
0.01
-0.09
--------GSHFAC.3
----0.02
0.07
----CFRISK.4
0.01
0.09
--------CFRISK.3
------------SV_NBCYC
----0.00
0.02
----SGTRLOC
0.00
0.04
0.00
0.03
----CFRISK.1
--------0.00
0.12
DLTEVA_5.12
--------0.00
0.04
ZR.95_ICH.9
--------0.00
0.03
* highlighted if main contribution larger than 0.02 or conjoint contribution larger than 0.1
MARS
0.59
Si
Ti
0.30
0.25
0.09
0.07
0.04
0.03
0.05
0.03
0.02
0.02
0.01
--0.02
----0.01
0.00
0.00
-------
0.30
0.27
0.09
0.07
0.05
0.07
0.06
0.03
0.02
0.04
0.01
--0.03
----0.02
0.00
0.00
-------
Main
Contr.*
Conjoint
Contr. *
0.179
0.166
0.062
0.030
0.019
0.017
0.012
0.012
0.010
0.010
0.009
0.006
0.005
0.005
0.002
0.001
0.001
0.000
0.000
0.000
0.000
0.128
0.152
0.077
0.040
0.012
0.081
0.018
0.007
0.009
0.021
0.023
0.014
0.001
0.014
0.000
0.003
0.005
0.009
0.033
0.011
0.008
12
4
Overall Conclusions
• Surry UA corroborates SOARCA study
conclusions:
– Public health consequences from severe nuclear
accident scenarios modeled are smaller than previously
calculated, and very small in absolute terms.
– Delayed releases calculated provide time for
emergency response actions such as evacuating or
sheltering; long-term phase dominates health effect
risks because emergency response is faster than
progression to release.
– “Essentially zero” early fatality risk projected.
13
Overall Conclusions (2)
• A major determinant of source term magnitude and health
consequences is whether or not an SGTR occurs.
• Mean, individual, LCF risks assuming LNT dose
response, conditional on an the occurrence of an
accident, estimated in this uncertainty analysis of the
Surry STSBO are very low, approximately 3×10-5 within
10 miles and lower at longer distances.
• Use of multiple techniques to post-process Monte Carlo
results provided better explanatory power with regard to
which input parameters are most important to uncertainty
in results.
14
Core Team Members and
Advisors
• MELCOR and severe accident progression: Randy
Gauntt, Kyle Ross, Scott Weber, Jeff Cardoni (SNL); KC
Wagner (dycoda); Ed Fuller, Hossein Esmaili, Don
Helton (NRC)
• MELMACCS: Nate Bixler, Doug Osborn (SNL)
• MACCS, consequence analysis and emergency
response: Nate Bixler, Joe Jones, Doug Osborn (SNL)
• Uncertainty Analysis (UA) methodology and glossary:
Cedric Sallaberry, Aubrey Eckert, Dusty Brooks, Jon
Helton, Matthew Denman (SNL); Tina Ghosh, Trey
Hathaway (NRC)
15
5
SOARCA References
•
•
•
•
•
•
•
•
NUREG-1935, State-of-the-Art Reactor Consequence Analyses (SOARCA)
Report (November 2012)
NUREG/BR-0359, Modeling Potential Reactor Accident Consequences,
Rev. 1 (December 2012)
NUREG/CR-7110, Vol. 1, SOARCA Project Peach Bottom Integrated
Analysis, Rev. 1, (May 2013)
NUREG/CR-7110, Vol. 2, SOARCA Project Surry Integrated Analysis, Rev.
1 (August 2013)
NUREG/CR-7008, MELCOR Best Practices as Applied in the SOARCA
Project (August 2014)
NUREG/CR-7009, MACCS Best Practices as Applied in the SOARCA
Project (August 2014)
NUREG/CR-7155, SOARCA Project Uncertainty Analysis of the Unmitigated
Long-Term Station Blackout of the Peach Bottom Atomic Power Station
Draft report on SOARCA Uncertainty Analysis of the Unmitigated Short-Term
Station Blackout of the Surry Power Station available in ADAMS, accession
number ML15224A002
16
Acronyms
CCDF
LCF
LNT
MACCS
SGTR
SNL
SOARCA
SRM
STSBO
UA
Complementary cumulative distribution function
Latent cancer fatality
Linear no threshold
MELCOR Accident Consequence Code System
Steam generator tube rupture
Sandia National Laboratories
State-of-the-Art Reactor Consequence Analyses
Staff Requirements Memorandum
Short term station blackout
Uncertainty Analysis
17
6
Fly UP