ML20134J357
| ML20134J357 | |
| Person / Time | |
|---|---|
| Issue date: | 11/06/1996 |
| From: | Wang E NRC (Affiliation Not Assigned) |
| To: | Matthews D NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9611150171 | |
| Download: ML20134J357 (23) | |
Text
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November 6, 1996 MEMORANDUM TO:
David B. Matthews, Chief Generic Issues and Environmental i
Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:
Egan Y. Wang, Reactor System Engineer Original Signed By:
Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
MEETING SUNiARY OF NOVEMBER 4, 1996, REGARDING THE
" REALISTIC LOCA ECCS EVALUATION MODEL FOR PWR LARGE BREAK LOCA ANALYSIS" On November 4, 1996, representatives of Siemens Power Corporation (SPC) met with representatives of the Nuclear Regulatory Commission (NRC). The purpose of this meeting was to provide an opportunity for SPC representatives to review and discuss the " Realistic LOCA ECCS Evaluation Model For PWR Large Break L0ct. Analysis" code issues.
SPC representatives provided an introduction and a brief description on current activities with regard to the codes. Most o? the meeting involved presentation of proprietary information.
Attachment I provides a list of meeting attendees. Attachment 2 is the non-proprietary version of the presentation material.
Attachments: As stated cc w/att: See next page DISTRIBUTION:
See attached page
")cument name: 9611044T. SUM
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1 l-f.11Jf_1BUTION: Mtg. Sunnary of November 4 Meeting with Siemens Power Corporation Dated November 6.1995 i
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E. Merschoff, RII i
W. Alexion, RIII J..lyer, RIV E. Wang OGC ACRS 1
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F. Miraglia A. Thadani i
R. Zimmerman j
T. Martin 1
E. Jordan D. Matthews F. Akstulewicz T. Collins K. Kavanagh l1. Richines a
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i November 6, 1996 i
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MEMORANDUM TO:
David B. Matthews, Chief Generic Issues and Environmental j
Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation i
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FROM:
Egan Y. Wang, Reactor System Engineer Generic Issues and Environmental CL,-7r
'^- ~ g Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation 4
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SUBJECT:
MEETING SUPMARY OF NOVEM8ER 4,1996, REGARDING THE
" REALISTIC LOCA ECCS EVALUATION MODEL FOR PWR LARGE BREAK LOCA ANALYSIS" On November 4, 1996, representatives of Siemens Power Corporation (SPC) met with representatives of the Nuclear Regulatory Commission (NRC). The purpose of this meeting was to provide an opportunity for SPC representatives to review and discuss the " Realistic LOCA ECCS Evaluation Model For PWR Large Break LOCA Analysis" code issues. SPC representatives provided an introduction and a brief description on current activities with regard to the codes. Most of the meeting involved presentation of proprietary information.
Attachment I provides a list of meeting attendees. Attachment 2 is the non-proprietary version of the presentation material.
Attachments: As stated cc w/att:
see next page ar m
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CC*
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Mr. H. D. Curet, Manager Product Licensing Siemens Power Corporation 2101 Horn Rapids Road P. O. Box 130 Richland, WA 99352-0130 3
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j NRC/SIEMENS POWER CORPORATION NEETING ON MIXED OXIDE FUEL i
LIST OF ATTEISEES i
Oct 23, 1996 H&ME ORGANIZATION j
Burns, J. P.
WPPSS Heiks, R. L.
Siemens i
Garner, N. L.
Siemens i
Garber, D. E.
Siemens i
Copeland, R.
Siemens Collins, T. E.
NRC/NRR i
Kavanagh, K.
NRC/NRR 4
Richines, H.
NRC/NRR Wang, Egan NRC/NRR 5
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l ATTACHMENT I
SIEMENS Overview of Realistic PWR Large Break LOCA Methodology and NRC Review Statu 3
Presented by:
H. D. Curet and S. E. Jensen 9
l Siemens Power Corporation - Nuclear Division
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Introduction 1
. Purpose - Overview of submitted methodology and supporting documentation t
. Objective - Demonstrate sufficient methodology documentation to justify reinitiating the review t
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SIEMENS Key Events RODEX3, April 1991 submittal approved in February 1996 Realistic PWR LBLOCA Code and Methodology submitted October 1992 and i
December 1992, respectively
. Westinghouse "BE Model" submitted August 1992 SPC Uncertainties Analyses submitted July 1993 ITS discontinued review of SPC Methodology in September 1994 SPC anticipated NRR and contractor to reinitiate review in June 1996
. Westinghouse "BE Model" approved June 1996
. Received copy of ITS close out report September 1996 l
Lessons learned from Westinghouse review August 1992 to June 1996 to be applied to future "BE Model" reviews
. Meeting with NRR on November 1996 to discuss lessons learned to be applied to SPC Realistic Model l
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SIEMENS l
Background
System Rule to allow realistic LOCA evaluation models in place of prescribed conservative models i
. Uncertainties in realistic evaluation models to be quantified i
. High probability that 10 CFR 50.46 criteria are not exceeded including uncertainties
- Basis for rule change is extensive research performed after 1975 rule as documented in " Compendium of ECCS Research" I
- NRC issued Regulatory Guide 1.157 providing guidance for best estimate LOCA analysis l
- NRC developed code scaling, applicability, and unc~ertdinty (CSAU) i evaluation methodology f
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Status of Realistic LOCA Submittal Realistic LOCA submittal consists of 14 topical reports which have been l
submitted for NRC review as follows-
. ANF-90-145(P), Vols.1&2, RODEX3 Fuel Rod Model, submitted April 1991 l
. EMF-92-139(P), Vol. 3, Assessments, submitted September 1992
. EMF-92-139(P), Vol. 2, S-RELAP5 Code, submitted October 1992 I
. EMF-92-139(P), Vol.1, Methodology Description, submitted December 1992 t
. EMF-92-139(P), Vol. 3, Supplements 1-7, Assessment Calculation, submitted July 1993
. EMF-92-139(P), Vol. 4, Uncertainties, submitted July 1993
. EMF-92-139(P), Vol. 5,4-Loop PWR Uncertainties, Submitted September 1995 Final planned methodology report submitted July 1993 l
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SIEMENS 1
i General Methodology i
Select codes based on capabilities Specify LBLOCA scenario, identify, and rank phenomena (PIRT)
Establish assessment matrix Define system and experiment nodalization i
Perform assessments, determine accuracy and bias, and effects of sca!e Perform NPP calculation t
Determine uncertainty and biases l
t Total uncertainty to calculate LBLOCA scenario in specific NPP i
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SIEMENS Codes for Realistic LOCA
- RODEX3 - Fuel rod thermal mechanical response
- S-RELAP5 - System thermal hydraulic response (steady & transient) l
- ICECON - Containment backpressure I
- GSUAM - Generic statistical uncertainties analysis methodology it es
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SIEMENS i
Benchmarks Demonstrates Realistic LOCA analysis capability of S-RELAP5 against experiments of varying scale 1
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SIEMENS Benchmarks (cont'd)
. SPC assessments of S-RELAPS against integral test experiments:
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. Assessments selected to encompass entire range of LBLOCA blowdown, refill, and reflood phenomena from facilities of varying scale
. Example calculations of Westinghouse 3-loop and 4-loop PWRs are provided llM EMDCSEA
SIEMENS Uncertainties Methodology Methodology:
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SIEMENS Uncertainties Methodology Parameters treated deterministically
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SIEMENS Uncertainties Methodology t
Parameters included in experimental design
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Uncertainties Methodology
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SIEMENS Uncertainties Methodology Additional uncertainties Plant uncertainties I
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SIEMENS Uncertainties Methodology Uncertainties combined using GSUAM ([
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Monte Carlo PCT Calculation Results 3-Loop Westinghouse PWR
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Uncertainties Methodology P
Uncertainties combined using GSUAM ([
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l Summary and Conclusions SPC developed Realistic PWR LBLOCA evaluation model following CSAU stepwise approach I
1 Code applicability and scaling effects evaluated by numerous assessments against experimental data Methodology uncertainties were identified, quantified, and combined using l
GSUAM l
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i Methodology submitted to NRC.for review l
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l Summary SPC submitted PWR Realistic LBLOCA Methodology to update technology
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