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.1 1 t I
U.S.NRCUNITED STATES NUCLEAR REGULATORY COMMISSION
Protecting People and the Environment
PUBLIC MEETING - DISCUSS ISSUES IDENTIFIED INTHE REVIEW OF U.S EPR LBLOCA AND FUEL
MECHANICAL TOPICAL REPORTS
July 9, 2009
N RC/N RO/DSRA/SRSB
1
I I
UNTDSTATES NUCLEAR REGULATORY COMMISSION
Ptcting People and the Environment
Purpose of the meeting:
For both topical report reviews, staff will informAREVA of concerns and positions regarding theremaining issues, provide technical bases anddiscuss the path forward
LBLOCA TR: ANP-10278P Rev.0 "U.S. EPR Realistic
Large Break Loss of Coolant Accident"
Fuel TR: ANP-10285P Rev.0 " U.S. EPR Fuel AssemblyMechanical Design Topical Report
2
U.S.NRCUNITED STATES NUCLEAR REGULATORY COMMISSION
Protecting People and the EnvironmentEPR SRSB Review Scope
Current Schedule: 9/30/09Review Results
1. Set Point TRSER Issued
2. RIA TR SERto be issued
shortly
1. Phase One Reviewcompleted
2. Phase Two Reviewon going with RAIsoutstanding
1. Phase One Reviewcompleted
2. Phase Two Reviewon going
3
Protn PLBLOCA TR Major Issues #1
Deficient Fuel Pellet Thermal Conductivity Model
RODEX3A based fuel pellet thermal conductivity
model does not take into account the exposure
dependent thermal conductivity degradation
Impact: 1. Hot rod and average rod initial stored
energy calculation
2. Rod heat transfer transient behavior
Staff Position: PCT penalty should be applied, if the
method is used without modification
4
U.S.NRCUNITED STATES NUCLEAR REGULATORY COMMISSION
Protecting People and the Enzironment LBLOCA TR Major Issues #2
Critical Flow Model Deficiency
S-RELAP5 code does not appropriately predict the
critical flow with the presence of non-condensablegases under certain conditions
Impact: Non-physical RCS pressurization prediction
for certain cases
Staff Position: Compensatory measure required, if the
method is used without modification
5
USNC LBLOCA TR Major Issues #3UNITED STATES NUCL.EAR REGULATORY COMMUSSION
Protecting People and the Environment
Lower Plenum Refill And Core Flow Oscillation
Staff is concerned that S-RELAP5 code predicts
significant core inlet liquid mass flux prior to the
lower plenum refill and significant large amplitude
core flow oscillation
Impact: Core quenching time and heat transfer above
the quench front
Staff Position: PCT penalty should be applied, if the
method is used without modification6
POther LBLOCA TR TechnicalIssues
Technical issues that have been discussed in the
course of the review:
Group 1 Issues - those which the staff and AREVAhave reached common understanding
Group 2 issues - those which the staff has takenpositions without reaching common understandingwith AREVA
7
'zU.S.NRC LB LOCA TR Other TechnicalUNITED STATES NUCLEAR REGULATORY. COMMISSION
Protecting People and the Environment
Issues
Group 1:Initial power (Sampled -> rated+ uncertainty)Decay heat (Sampled -> nominal+uncertainty)Number of computer runs (59 -> 124)Loss of Offsite Power Analysis (not needed due toRCP automatic trip)Downcomer Boiling (Present treatment isacceptable)Lower bound of break spectrum (Present Treatmentis acceptable)Fuel Rod Quench (No quench unless both T<TminAND void<0.95)
8.
SU.S.NRTR
UNTDSTATES NUCLEAR REGULATORY COMMISSION I .~ ~ I ~I J~~Protecting Pe:opl adheEnionmen LBLOCA TR Other Technical
Issues
Group 2:Rod-to-Rod Radiation and core heat transfer
- Consistent with NRR staff position- Present treatment is still acceptable to EPR
because of low PCTForslund=Rohsenow Correlation
- Restriction appliesAccumulator Liquid temperature
- Insufficient justification of a temperature
distribution for hot full power operation, thetech. spec. maximum temperature should be
used 9
U.S.NRCUNITED STATES NUCLEAR REGULATORY COMMISSION
Protecting People and the Environment LBLOCA TR Path Forward
Current Approach:
Support current EPR DCD schedule, allow the method
to be used with limitations
Alternate Approach:
Issue SER with open items. AREVA proposes new
schedule to submit the revised topical report to
address issues
10
U.S.NRC Fuel Mechanical Design TRUNITED STATES NUCLEAR REGULATORY COMMISSON
Proftecing Peopk anad th Environment I s e #Issue #1
Significant M5 assembly growth has been observed
Staff is concerned that the newly revised EPR fuelassembly growth model has not been validatedwith sufficient data and the stress history.uncertainty has not been defined
Impact: Fuel assembly burn-up limit
Path Forward:
AREVA has agreed to respond to new RAIs regarding
stress history uncertainty, data base size and growth
trend. A new review schedule has been established.
11
'US.NRCUNITED STATES NUCLEAR REGULATORY COMMISSION
Protecting People and the Environment
Fuel Mechanical Design TRIssue #2
COPERNIC Code Cladding Strain Model
Staff is concerned that COPERNIC code has notbeen validated against the latest cladding strain
test data
Impact: Fuel rod maximum linear heat generation rate
for AQOs
Path Forward:
AREVA has agreed to respond to new RAIs regarding
the comparison of COPERNIC results with new-test
data12
U.S.NRCUNITED STATES NUCLEAR REGULATORY COMMISSION
Protecting People and the Environment Fuel TR Path Forward
New Schedule has been established with AREVA
Latest round of RAI responses due in August, 2009
Current SER delivery date 10/31/09
Assuming satisfactory RAI response from AREVA
13
Status of Review of U.S. EPRTM Realistic Large BreakLOCA Topical Report and Fuel Assembly Mechanical
Design Topical Report
AREVA NP and Me NRCJu~y 9, 2009
TM EPR is a trademark of the AREVA Group EPR> NRC Meetina. RLBLOCA and FAM TR - July 9, 2009 1AREVA NP INC.
m .. ..... • J s
Introduction
Sandra M. SloanRegulatory Affairs Manager
New Plants
EPR2AREVA NP INC. > NRC Meeting, RLBLOCA and FAM TR - July 9, 2009
AREVA NP Meeting Objectives
> Obtain a complete list of open issues for the U.S.EPR Realistic Large Break LOCA Topical Reportand Fuel Assembly Mechanical Design TopicalReport
> Gain an understanding of the technical basis forNRC positions, particularly regarding proposed"compensatory measures"
> Provide AREVA NP perspective on NRC positions
Information provided will form the basis for an informeddecision regarding the path forward for the two reports.
EPRL > NRC Meeting, RLBLOCA and FAM TR - July 9, 2009 3
i AREVA NP INC. a
Background: RLBLOCA Topical Report
ANP-10278P submitted March 26, 2007
ANP-10278P accepted for review May 9, 2007
1st round RAIs issued July 20, 2007
Response to 1st round RAIs Aug.17, 2007
First scheduled DSER date (by letter dated May 9, Dec. 31,20072007)
2nd round RAIs issued May 15, 2008
Response to 2nd round RAIs June 13, 2008
Phone call: NRC states DSER being prepared, but July 10, 2008open issues remain with 2nd round RAIs; Optionsgiven: 1) DSER with statement that certain parts ofmethodology are unacceptable; 2) PCT penalty > 500'F; 3) 3rd round RAIs
EPRi AREVA NP INC. L > NRC Meeting, RLBLOCA and FAM TR - July 9, 2009 4
Background: RLBLOCA Topical Report
Second scheduled DSER date (by letter dated March July 15, 200826, 2008)
Meeting to identify all open items and discuss path July 25, 2008forward
NRC-AREVA NP face-to-face management Aug. 6, 2008discussion: AREVA NP accepts 3rd round RAIs aspath forward. No new issues; apply "transitionapproach ."
3rd round RAls issued Sept. 5, 2008
Meeting to describe AREVA NP strategy to address Sept. 10, 20083rd round RAIs
NRC Audit.- RODEX2 and RODEX3A Dec. 3-4, 2008
First set of responses to 3rd round RAIs Dec. 19, 2008
4th round RAIs issued Jan. 28, 200•.
L EPRAREVA NP INC. / > NRC Meeting, RLBLOCA and FAM TR - July 9, 2009 5
Background: RLBLOCA Topical Report
5th round RAIs issued March 11, 2009
Second set of responses to 3rd round RAIs March 31, 2009
Response to 4th round RAts April 2, 2009
Response to 5th round RAIs April 9 2009
NRC audit April 22-23, 2009
Draft 6th round RAIs received May 21, 2009
Status meeting July 9, 2009
Third scheduled DSER date (by letter dated March Sept. 16, 200919, 2009)
Fourth scheduled DSER date (by letter dated June Sept. 30, 200925, 2009)
EPRAREVA NP INC.. > NRC Meeting, RLBLOCA and FAM TR - July 9, 2009 6
Cumulative PCT Impact of ProposedChanges and Compensatory Measures
> U.S. EPR FSAR Rev. 0 LBLOCA PCT, 1512 OF
Item APCT
Fuel rod model (RODEX). 200 OF
Flow and lower plenum 100 OFrefill
Decay heat 200 OF
124 cases (was 59) 100 OF
TOTAL --600 OF
EPRAREVA NP INC. > NRC Meeting, RLBLOCA and FAM TR - July 9, 2009 7
Background: Fuel AssemblyMechanical Design Topical Report
ANP-10285P submitted October 2, 2007
ANP-10285P accepted for review Dec. 7, 2007
First round RAI issued April 30, 2008
First set of responses to round 1 RAI May 29, 2008
Second set of response to round 1 RAI June 13, 2008
Second round RAI issued June 24, 2008
Response to second round RAI July 24, 2008
First scheduled DSER date (by letter dated August 21, 2008December 7, 2007)
Audit (2 days) Dec. 3-4, 2008
EPRAREVA NP INC > NRC Meeting, RLBLOCA and FAM TR - July 9, 2009 8
Background: Fuel AssemblyMechanical Design Topical Report
Third round RAI issued Jan. 15, 2009
First set of responses round 3 RAI April 2, 2009
Audit (2 days) April 23-24, 2009
Revision to round 3 RAI 38 April 30, 2009
Fourth round RAI issued June 26, 2009
Planned response to fourth round RAI August 14, 2009
Current DSER schedule Oct. 31,2009
EPRmRV PIC> NRC Meeting, RLBLOCA and FAM TR - July 9, 2009 9
AREVA NP Next Steps
> Evaluate information received regardingremaining open issues and technical basis forcompensatory measures
Consider in a broad context, including- effect ofpreviously-identified methodology changes and impacton overall DC review schedule
> Notify NRC of response to stated positions,especially regarding proposed compensatorymeasures
EPR_> NRC Meeting, RLBLOCA and FAM TR - July 9, 2009 10AREVA NP INC.