ML14314A723
| ML14314A723 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 10/27/1998 |
| From: | Subbaratnam R NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9810300210 | |
| Download: ML14314A723 (47) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 27, 1998 LICENSEE:
Carolina Power & Light Company FACILITY:
H. B. Robinson Steam Electric Plant, Unit No. 2
SUBJECT:
SUMMARY
OF OCTOBER 20, 1998, MEETING REGARDING REALISTIC BEST ESTIMATE LARGE BREAK LOSS-OF-COOLANT ACCIDENT (LOCA)
METHODOLOGY AT H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT 2 This summary refers to the meeting with Carolina Power & Light Company (CP&L) conducted on October 20, 1998, at the U.S. Nuclear Regulatory Commission (NRC) office in Rockville, Maryland. The purpose of the meeting was for the licensee to update the staff on its position regarding the subject matter. Enclosure 1 is a list of meeting attendees. Enclosure 2 is a copy of the handout (Non-Proprietary) provided at the meeting. The CP&L presentation included background information, a discussion of licensing activities, and the project schedule.
Background and Project Schedule The meeting was held at the request of CP&L to discuss its submittal of Realistic Best Estimate Large Break Loss-of-Coolant Accident (LOCA) methodology at H. B. Robinson Steam Electric Plant (HBRSEP). The meeting objective was to describe the proposed submittal by CP&L on the realistic large break LOCA methodology documentation in support of emergency core cooling system model simulation for H. B. Robinson and obtain feedback comments from the agency on the coverage. The presenters included team of CP&L staff and engineers from Siemens, a CP&L vendor. CP&L described the uncertainty approach used in the development of realistic large break LOCA uncertainties. The presentation also included a current project schedule and milestones on the proposed revision to the documentation, introduction of additional benchmarks, and finally, a plant-specific analysis. CP&L indicated an approximate completion date for the project to be December 1999. The submittal and approval process will include replacement of the old Appendix K methodology, staff approval, and a submission to ACRS for final approval by the first week of March 1999. The plant-specific submittal will follow thereafter with a projected completion date of December 1999.
Licensing Action:
The following milestones were discussed during the meeting:
Milestones Target Date CP&L Submittal to Staff for Review January 1999 Staff Acceptance Review & Submittal to ACRS February 1999 ACRS Kickoff Meeting Mid-March 1999 9810300210 981027 PDR ADOCK 05000261 P
October 27, 1998
-2 These dates are subject to change. A total of 15 copies will be submitted by CP&L to the NRC to cover both the requirements of the NRC staff and the ACRS.
Original signed by:
Ram Subbaratnam, Project Manager Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-261
Enclosures:
- 1. List of attendees
- 2. Handout cc w/encls: See next page Distribution (w/enclosures)
LDocket-File,
R. Subbaratnam PUBLIC R. Caruso PDII-3 R/F J. Staudenmeier E. Wang F. Orr R. Landry B. Desai, SRI, Robinson OGC M. Shuaibi ACRS J. Zwolinski S. Collins/F. Miraglia F. Hebdon R. Zimmerman M. Tschiltz B. Boger L. Plisco, RII FILENAME - G:\\ROBINSON\\MTG\\MET10209.NOT OFFICE PM:P AA:PDII-2 D:PDII-3 NAME RSubbaratnam EDunnington FHebdon6 DATE 1 O/98 1 001/98 10/98 COPY Yes/No e INo No OFFICIAL RE ORD COPY
October 27, 1998
-2 These dates are subject to change. A total of 15 copies will be submitted by CP&L to the NRC to cover both the requirements of the NRC staff and the ACRS.
Original signed by:
Ram Subbaratnam, Project Manager Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-261
Enclosures:
- 1. List of attendees
- 2. Handout cc w/encls: See next page Distribution (w/enclosures)
Docket File R. Subbaratnam PUBLIC R. Caruso PDII-3 R/F J. Staudenmeier E. Wang F. Orr R. Landry B. Desai, SRI, Robinson OGC M. Shuaibi ACRS J. Zwolinski S. Collins/F. Miraglia F. Hebdon R. Zimmerman M. Tschiltz B. Boger L. Plisco, RII FILENAME - G:\\ROBINSON\\MTG\\MET10209.NOT OFFICE PM:P
-4..A:PDIl-2 D:PDII-3 NAME RSubbaratnam EDunningt FHebdon DATE 10 /tf98 1007/98 1017/98 COPY Yes/No No No OFFICIAL RE ORD COPY
These dates are subject to change. A total of 15 copies will be submitted by CP&L to the NRC to cover both the requirements of the NRC staff and the ACRS.
Ram Subbaratnam, Project Manager Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-261
Enclosures:
- 1. List of attendees
- 2. Handout cc w/encls: See next page
H. B. Robinson Steam Electric Plant, Unit No. 2 cc:
Mr. William D. Johnson Mr. Mel Fry, Director Vice President and Senior Counsel N.C. Department of Environment Carolina Power & Light Company and Natural Resources Post Office Box 1551 Division of Radiation Protection Raleigh, North Carolina 27602 3825 Barrett Dr.
Raleigh, North Carolina 27609-7721 Ms. Karen E. Long Assistant Attorney General Mr. Robert P. Gruber State of North Carolina Executive Director Post Office Box 629 Public Staff-NCUC Raleigh, North Carolina 27602 Post Office Box 29520 Raleigh, North Carolina 27626-0520 U.S. Nuclear Regulatory Commission Resident Inspector's Office Mr. Virgil R. Autry, Director H. B. Robinson Steam Electric Plant South Carolina Dept. of Health 2112 Old Camden Road Division of Radioactive Waste Management Hartsville, South Carolina 29550 Bureau of Land & Waste Management 2600 Bull Street Regional Administrator, Region 11 Columbia, South Carolina 29201 U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Ms. D. B. Alexander, Manager Atlanta, Georgia 30303 Performance Evaluation and Regulatory Affairs CPB 9 Mr. J. W. Moyer Carolina Power & Light Company Director of Site Operations Post Office Box 1551 Carolina Power & Light Company Raleigh, North Carolina 27602-1551 H. B. Robinson Steam Electric Plant Unit No. 2 3581 West Entrance Road Mr. D. E. Young, Site Vice President Hartsville, South Carolina 29550 Carolina Power & Light Company H. B. Robinson Steam Electric Plant Public Service Commission Unit No. 2 State of South Carolina Post Office Box 790 Post Office Drawer 11649 Hartsville, South Carolina 29550 Columbia, South Carolina 29211 Mr. H. K. Chernoff Mr. T. M. Wilkerson Supervisor, Licensing/Regulatory Programs Manager - Regulatory Affairs Carolina Power & Light Company Carolina Power & Light Company H. B. Robinson Steam Electric Plant, H. B. Robinson Steam Electric Plant Unit No.R2 Unit No. 2 3581 West Entrance Road 3581 West Entrance Road Hartsville, South Carolina 29550 Hartsville, South Carolina 29550-0790
ATTENDEE LIST FOR THE MEETING OF OCTOBER 20, 1998 NAME ORGANIZATION S.E. "Gene" Jensen SPC Albert A. Garrou CP&L/LIC/RP Lewis E. Wells CP&L, NFMESA Leo Martin CP&L Robin L. Feuerbacher Siemens Jerald S. Holm Siemens James F. Mallay Siemens Larry O'Dell Siemens Egan Wang NRC Frank Orr NRC/SRXB Ralph Caruso NRC/SRXB Joseph Staudenmeier NRC/SRXB Ralph Landry NRC/SRXB Ram Subbaratnam DRPE/NRR
United States Nuclear Regtatory Commission Attachment III to Serial: RNP-RA/98-0186 41 Pages H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 SLIDES - REALISTIC LARGE BREAK LOSS OF COOLANT ACCIDENT (LOCA)
METHODOLOGY (NON-PROPRIETARY)
Realistic Large Break Loss of Coolant Accident (LOCA)
Methodology SIEMENS
Realistic Large Break LOCA Methodology
- Agenda
- Introduction A. Garrou
- Perspective J. S. Holm
- Methodology Documentation L. D. O'Dell
- Supporting Documentation L. D. O'Dell
- Uncertainties Methodology S. E. Jensen
- Summary A. Garrou CP&LSIEMENS2
Introduction A. Garrou SIEMENS 3
Realistic Large Break LOCA Methodology
- Introduction
+ Meeting objective
" Describe planned Realistic Large Break LOCA documentation and obtain NRC feedback on coverage a Describe uncertainty approach used in the development of Realistic Large Break LOCA uncertainties and obtain NRC feedback on approach SIEMENS 4
Current Project Description - Schedule 1
1 2
2 9
9 0
0 9
9 0
0 8
9 0
1 Revise Documentation 9/9 1/9 Additional Benchmarks 9/9 1/9 Plant-Specific Analysis 1/9 1/1 RNP 5/90 9/10 HNP NRC Submittals (RNP/HNP) 199 910 SIEMENS
Perspective J. S. Holm, Manager Product Licensing SIEMENS 6
History of PWR Realistic LBLOCA Methodology Development Revised W Best NRC Approval Appendix Estimate W Best SEC-83-472 K Rule Submittal Estimate 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 I
I I
I I
I SPC Best SPC SPC SPC NRC SPC Submittal Estimate Realistic RODEX3 Realistic Approval of Revised Program Program Submittal Submittal RODEX3 Realistic Documentation SIEMENS 7
Benefits
- Replace "old" Appendix K Methodology
- Focus V&V effort on new technology
- Competitive methodology SIEMENS 8
Meeting Expectations
- Obtain feedback from NRC on the differences between the SPC Realistic Methodology and the CSAU Methodology example in NUREGICR-5249 SIEMENS 9
Methodology and Supporting Documentation L. D. O'Dell, Manager U.S. & Far East Research &
Technology SIEMENS 10
Realistic Large Break LOCA Methodology
- Methodology Documentation
+ EMF-92-139, Revision 1, "Realistic Evaluation of 0
Large Break LOCA Phenomena in Pressurized' Water Reactors" a Realistic chosen instead of best estimate to indicate that methodology is not fully deterministic nor fully best estimate but a combination of both approaches a Describes compliance with NUREG/CR-5249 "Application of Code Scaling, Applicability, and Uncertainty (CSAU) Evaluation Methodology to a Large Break Loss of Coolant Accident" SIEMENS 11
Realistic Large Break LOCA Methodology
- Methodology Documentation
.Table of Contents (Main Sections)
" Methodology Description (Roadmap)
" Requirements and Code Capabilities (CSAU Element 1)
" Assessment and Ranging of Parameters (CSAU Element 2)
- Sensitivity and Uncertainty Analysis (CSAU Element 3)
- Demonstration Cases SIEMENS 12
Realistic Large Break LOCA Methodology
- Methodology Description (Roadmap)
+ Subsections m Requirements and Code Capabilities
- CSAU Element 1 m Assessment and Ranging of Parameters
- CSAU Element 2 m Sensitivity and Uncertainty Analysis
- CSAU Element 3 m Demonstration Cases
- Describes application of CSAU methodology
- Demonstrates compliance with Regulatory Guide 1.157, Rev. 0, "Best-Estimate Calculations of Emergency Core Cooling System Performance" SIEMENS 13
Realistic Large Break LOCA Methodology
- Requirements and Code Capabilities
- Subsections a Event Specific Requirements
- Specify Scenario (CSAU Step 1)
- Specified the large break LOCA scenario
- Select Plant (CSAU Step 2)
- Selected W 3-and 4-loop plants and CE plants
- Performed demonstration calculations for W 3-and 4-loop plant types
- Identify and Rank Phenomena (CSAU Step 3)
- Developed Process Identification and Ranking Table (PIRT)
SIEMENS 14
Realistic Large Break LOCA Methodology
- Requirements and Code Capabilities
- Subsections
" Methodology Specific Capabilities
- Select Frozen Codes (CSAU Step 4)
- Selected frozen versions of RODEX3, S-RELAP5, and ICECON
- Provide Complete Documentation (CSAU Step 5)
- Developed code theory manuals, programmers guide, user manuals, verification report, and validation report
- Determine Code Applicability (CSAU Step 6)
- Developed code verification and applicability documents SIEMENS 15
Realistic Large Break LOCA Methodology
- Assessment and Ranging of Parameters
.Subsections
" Assessment Matrix (CSAU Step 7)
- Separate and integral effect tests (SET/IET) selected to support important phenomena identified in PIRT
" Nodalization (CSAU Step 8)
- Common nodalization selected and used in SET, IET, and plant analyses SIEMENS 16
Realistic Large Break LOCA Methodology
- Assessment and Ranging of Parameters
- Subsections m Code and Experiment Accuracy (CSAU Step 9)
- CSAU approach determines uncertainty based on individual parameters determined from the PIRT
- SPC approach determines principle uncertainty based on comparisons between code and integral tests
- Integral approach provides most direct indication of code performance and directly addresses uncertainty propagation
- Integral approach consistent with SECY 83-472
- CSAU used integral approach to verify individual parameter approach SIEMENS 17
Realistic Large Break LOCA Methodology
- Assessment and Ranging of Parameters
- Subsections
- Effects of Scale (CSAU Step 10)
- CSAU process has a detailed 10-step approach
- SPC approached scale effects by simulating tests in facilities at different scales and showing that the code simulates different scale facilities equally well
- LOFT power to volume scaling of 1:50
- CCTF volumetric scaling of 1:25
- UPTF scaling 1:1
- FLECHT-SEASET bundle scaling of 1:1 SIEMENS 18
Realistic Large Break LOCA Methodology
- Sensitivity and Uncertainty Analysis
- Subsections a Reactor Input Parameters and State (CSAU Step 11)
- Response surface developed for various power parameters using the Nuclear Power Plant (NPP) model m Plant Sensitivity Calculations (CSAU Step 12)
- Plant specific biases determined from sensitivity studies using the NPP model SIEMENS 19
Realistic Large Break LOCA Methodology
- Sensitivity and Uncertainty Analysis
- Subsections
" Biases and Uncertainties (CSAU Step 13)
- Generic Statistical Uncertainty Analysis Methodology (GSUAM) used to perform Monte Carlo sampling
" Total Uncertainty (CSAU Step 14)
- Statement of total uncertainty for the code is given for the limiting value of the primary safety criteria SIEMENS 20
Realistic Large Break LOCA Methodology
- Demonstration Cases
.Subsections a Westinghouse 3-Loop Plant
- H. B. Robinson Steam Electric Plant Unit #2 analysis
- Submitted on CP&L docket 50-261 m Westinghouse 4-Loop Plant
- Demonstration/sample problem analysis
_ji SIEMENS 21
Realistic Large Break LOCA Methodology
- Supporting Documentation
- Developed to meet requirements of Regulatory Guide 1.157
+ Developed to meet requirements of NUREG/CR-5249
" Developed to meet requirements of industry standards a NUREG/BR-0167, "Software Quality Assurance Program and Guidelines" February 1993 m ASME NQA-2a-1990, Addenda to ASME NQA-2-1989 Edition, "Quality Assurance Requirements for Nuclear Facility Applications" April 1990 F
-U&
7 A
NaSIEMENS 22
Realistic Large Break LOCA Methodology
- Supporting Documentation
" Analysis guidelines
- Documentation of computer codes a RODEX3 code a S-RELAP5 code "ICECON code
+ GSUAM methodology documentation m ANYOLS code m MOCARS code
" H. B. Robinson Steam Electric Plant Unit #2 analysis
- Westinghouse 4-loop sample problem analysis SIEMENS 23
Realistic Large Break LOCA Methodology
- Analysis Guidelines
- EMF-2054(P), Revision 0, "S-RELAP5 Input Deck Development Guidelines for Realistic Large Break LOCA Analysis of Pressurized Water Reactor"
+ EMF-2053(P), Revision 0, "Guideline for Performance of Realistic Large Break LOCA Analysis of a Pressurized Water Reactor" 7SIEMENS 24
Realistic Large Break LOCA Methodology
- Documentation of Computer Codes
- RODEX3 code
- ANF-90-145(P)(A), "RODEX3 Fuel Rod Thermal Mechanical Response Evaluation Model"
- Volume I, Theoretical Manual
- Volume II, Thermal and Gas Release Assessments
- Supplement 1, Correspondence
" EMF-1 557, "RODEX3A: Users Code Description and Input Manual"
" EMF-2099, "RODEX3A: Code Verification and Applicability Review" SIEMENS 25
Realistic Large Break LOCA Methodology
- Documentation of Computer Codes
- S-RELAP5 Code
" EMF-2100, Revision 0, "S-RELAP5: Model and Correlations Code Manual"
- EMF-21 01, Revision 0, "S-RELAP5: Programmers Guide"
- EMF-CC-097(P), Revision 2, "S-RELAP5 Input Data Requirements" SIEMENS 26
Realistic Large Break LOCA Methodology
- Documentation of Computer Codes
- S-RELAP5 Code (Continued) m EMF-2058, Revision 0, "S-RELAP5:
Code Verification and Applicability Review" a EMF-2102, Revision 0, "S-RELAP5:
Code Validation" SIEMENS 27
Realistic Large Break LOCA Methodology
- Documentation of Computer Codes
- ICECON Code 0
" XN-CC-39, Revision 2, "ICECON: A Computer Program Used to Calculate Containment Back Pressure for LOCA Analysis (Including Ice Condenser Plants)"
- XN-CC-39, Revision 2, Supplement 1, "ICECON Code User's Manual"
" EMF-2103, Revision 0, "ICECON Code Verification and Applicability Review" SIEMENS 28
Realistic Large Break LOCA Methodology
- Documentation of Computer Codes
- GSUAM Methodology Documentation m XN-NF-81-22(P)(A), "Generic Statistical Uncertainty Analysis Methodology" m EMF-2104, Revision 0, "ANYOLS: A Flexible Stepwise Regression Program" m EMF-2105, Revision 0, "MOCARS: A Monte Carlo Code for Determining Distribution and Simulation Limits and Ranking System Components by Importance" SIEMENS 29
Uncertainties Methodology S. E. Jensen, Team Leader ECCS Methods SIEMENS 30
Realistic Large Break LOCA Methodology
- Uncertainties Methodology
+ CSAU Approach
" Perform full scale NPP analyses based on PIRT identified phenomena/parameters and associated uncertainties
" Develop response surface from NPP analysis matrix
- Perform Monte Carlo sampling on response surface to develop a probability distribution of Peak Clad Temperature (PCT)
" From probability distribution of PCT determine 95%
probability PCT
" Address other PCT uncertainty contributors, generally with biases a Combine all uncertainty contributors to determine total PCT uncertainty
- Confirm by comparison to integral experimental data SIEMENS 31
Realistic Large Break LOCA Methodology
- Uncertainties Methodology
+ SPC Approach SIEMENS 32
Realistic Large Break LOCA Methodology
- Uncertainties Methodology
+ Application of PIRT for RLBLOCA m Used to establish controlling phenomena
- Used in development of assessment matrix
- Experiments which model controlling phenomena
- Experiments which address effects of scale SIEMENS 33
Realistic Large Break LOCA Methodology
- Uncertainties Methodology
+ Parameters treated deterministically SIEMENS 34
Realistic Large Break LOCA Methodology
- Uncertainties Methodology SIEMENS 35
Realistic Large Break LOCA Methodology
- Uncertainties Methodology SIEMENS 36
Realistic Large Break LOCA Methodology
- Uncertainties Methodology SIEMENS 37
Realistic Large Break LOCA Methodology Uncertainties Combined Using GSUAM (50,000 Trials)
Monte Carlo PCT Calculation Results 3-Loop Westinghouse PWR SIEMENS 38
Realistic Large Break LOCA Methodology Uncertainties Combined Using GSUAM (50,000 Trials)
Monte Carlo PCT Calculation Results 4-Loop Westinghouse PWR tfSIEMENS 39
Summary
- CP&L is committed to ensuring a quality submittal for HBRSEP, Unit No. 2
- Sees Realistic LOCA as a means to increasing margin and reducing regulatory burden
+ Postures HBRSEP, Unit No. 2 for License Renewal
- Agrees with SPC uncertainty approach which reflects lessons learned from previous submittal
- Will closely monitor SPC submittal development and post-submittal support SIEMENS 40