ML20135E628
| ML20135E628 | |
| Person / Time | |
|---|---|
| Issue date: | 12/05/1996 |
| From: | Birmingham J NRC (Affiliation Not Assigned) |
| To: | Matthews D NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9612110373 | |
| Download: ML20135E628 (16) | |
Text
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December 5, 1996 6 MEMORANDUM T0: David B. Matthews, Chief i
t Generic Issues and Environmental l Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM: Joseph L. Birmingham, Project Manager Original Signed By:
Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclekr Reactor Regulation
SUBJECT:
SUMARY OF NOVEMBER 26, 1996, PUBLIC MEETING WITH SIEMENS POWER CORPORATION SENIOR MANAGEMENT TO DISCUSS ~LARGE-BREAK l
LOCA CODE ISSUES l
- On November 26, 1996, members of Siemens Power Corporation (Siemens) senior l management met with Nuclear Regulatory Commission staff and management to i l
discuss large-break loss-of-coolant accident code issues. The primary concern l is the potential for excessive peak clad temperatures to occur as a result of nonconservative estimates of _ post-LOCA reflood heat transfer rates. Siemens senior management presented an overview of the history and current status of the issue and also the preliminary findings of a Siemens Augmented Assessment Team formed to evaluate the issue. Siemens senior management discussed the preliminary Augmented Assessment Team recommendations and the proposed !
schedule for implementation of the recommendations. Siemens also discussed planned initiatives to improve communications with the NRC and licensees by developing and implementing written guidance.
i The NRC staff asked questions on the scope of the Augmented Assessment Team, the methods used by the assessment team, and the preliminary findings. NRC
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l management indicated that staff resources would be dedicated to inspect and )
evaluate the resolution of this issue and also the generic implications. i l
Meeting attendees are listed in Attachment I and the slides presented by l Siemens are in Attachment 2. !
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- ,o December 5, 1996 j MEMORANDUM T0: David B. Matthews, Chief Generic Issues and Environmental Projects Branch l Division of Reactor Program Management 1
Office of Nuclear Reactor Regulation
, FROM: Joseph L. Birmingham, Project Manager Generic Issues and Environmental /]
Projects Branch y i Division of Reactor Program Management l Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF NOVEMBER 26, 1996, PUBLIC MEETING WITH SIEMENS POWER CORPORATION SENIOR MANAGEMENT TO DISCUSS LARGE-BREAK LOCA CODE ISSUES On November 26, 1996, members of Siemens Power Corporation (Siemens) senior management met with Nuclear Regulatory Commission staff and management to discuss large-break loss-of-coolant accident code issues. The primary concern is the potential for excessive peak clad temperatures to occur as a result of nonconservative estimates of post-LOCA reflood heat transfer rates. Siemens senior management presented an overview of the history and current status of the issue and also the preliminary findings of a Siemens Augmented Assessment Team formed to evaluate the issue. Siemens senior management discussed the
' preliminary Augmented Assessment Team recommendations and the proposed schedule for implementation of the recommendations. Siemens also discussed planned initiatives to improve communications with the NRC and licensees by developing and implementing written guidance.
The NRC staff asked questions on the scope of the Augmented Assessment Team, 1 the methods used by the assessment team, and the preliminary findings. NRC 4
management indicated that staff resources would be dedicated to inspect and l evaluate the resolution of this issue and also the generic implications.
Meeting attendees are listed in Attachment I and the slides presented by Siemens are in Attachment 2.
Attachments: As stated l cc w/atts: See next page i
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i Distribu'; my Mtg. Summary w/Siemens; dated November 26. 1996:
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EWang 01/ Dan Murphy E-Mail (w/att 1)
A Thadani F. Miraglia R. Zimmerman T. Martin B. Sheron D. Matthews R.' Jones
! A. Levin J. Staudenmeier S. KoenicP.
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H. D. Curet, Manager Product Licensing Siemens Power Corporation 2101 Horn Rapids Road P.O. Box 130 Richland, WA .99352-0130 David G. McAlees Senior Vice President Siemens Power Corporation 155 108th Avenue NE P.O. Box 90777 Bellevue, WA 98009-0777 l
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SIEMENS SENIOR MANAGEMENT MEETING ATTENDEES NOVEM8ER 26, 1996 NAME ORGANIZATION DAN MURPHY NRC\01 ASHOK THADANI NRC\NRR :
ROBERT JONES NRC\NRR\DSSA\SPSB l FRANK ORR NRC\NRR\DSSA\SRXB l LARRY PHILLIPS NRC\NRR\DSSA\SRXB GEORGE THOMAS NRC\NRR\DSSA\SRXB l ED GOODWIN NRC\NRR\DRPM\PECB JOSEPH BIRMINGHAM NRC\NRR\DRPM\PGEB J0E STAUDENNEIER NRC\NRR\DSSA\SASG ALAN LEVIN NRC\NRR\DSSA\SRXB STEVE K0ENICK NRC\NRR\DSSA\PECB
, TOMMY LE NRC\NRR\DRPE\PDII-l ALBERT L GARROU CP&L\H.B. ROBINSON MIKE SCH0PPMAN FLORIDA POWER & LIGHT DANIEL POTERALSKI CAROLINA POWER & LIGHT DAN FADEL CONSUMERS POWER \ PALISADES
, DAVID MCALEES SIEMENS POWER CORPORATION 1 CHRIS M POWERS SIEMENS POWER CORPORATION i JIM NORDAHL SIEMENS POWER CORPORATION ROGER REYNOLDS SIEMENS POWER CORPORATION '
. DON CURET SIEMENS POWER CORPORATION E
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ATTACHMENT 1 i
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SIEMENS NRC Management Meeting
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Siemens Power Corporation - Nuclear Division Senior Vice President &
General Manager D. G. McAlees Finance Strategec Planning Sales & Projects Human Resources Director Director Director Vece President J. H. Nordahl Engmeeting & Research & Technology Quality i
Manufacturing Director Director Vice Presedent W. D. Krebs C. M. Powers B. N. Femreite ;
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Siemens Power Corporation - Nuclear Division t
Enethode & Codes Managee ,
R. S. Reynolds Enynoering Autornetson Safety Analyses Neutrorwc Analysis Codes & Techneca: Mecherwcel Analysis US & Far East Q Code Maintenance Methods Methods Support. Europe Methods Product IA'555'"9 +
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Anoroach:
Establish cross functional team comprised of persennel from Quality, Methods & Codes and Nuclear Engineering. Augment this core team with independent consultant support with specialized LOCA methodology and licensing skills. If possible, team with SPC customer technical resources provided through the Siemens Fuels Users Group.
l l Core team members: 1 l
Doug Adkisson (Leader) Sales & Projects Dick Collingham Methods & Codes j Jerry L Holm Quality Larry Nielsen {
i PWR Neutronics '
! Don Curet Reload Licensing i
Marvin Thurgood Consultant, LOCA Methodology / Licensing Expertise The team will conduct interviews, perform reference searches, review calculation notebooks, seek customer feedback and NRC reviewer input, as appropriate. The team will also enlist additional resources as necessary to complete this assessment in an expeditious manner. -
I Schedule: Comolation Date Form Team 11/01/96 Conclude Assessment 11/30/96 issue Draft Conclusions 12/06/96 ,
Finalize Conclusions 12/13/96 Management Review 12/20/96 Communicate Results 12/30/96 l
SIEMENS SPC PWR LBLOCA Augmented Assessment Team
- i. Objectives:
Evaluate SPC's PWR LBLOCA methodology development process Confirm compliance with relevant SERs including an assessment of the licensing basis Evaluate the interface between " Development" and " Application"
- 11. Approach:
Cross functional team from Quality, M&C, Nuc. Eng. and Reload Licensing
. Augmented w/outside consultant '
Perform Events and Causal Factors analysis Conduct interviews, reference searches, calculation notebook reviews Identify corrective actions for identified genene issues Ill. Schedule:
Team Formation 11/01/96
. Complete Assessment 11/30/96 !
Finalize Conclusions 12/13/96
- Management Review 12/20/96 !
Communicate P.esults 12/30/96 y 11122196
_ _ _ _ _ _ _ . _ _ _ _ _ ~ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .______._____ ____ _ ._ _ __ _ ____ _ _ ___ _
SIEMENS SPC PWR LBLOCA Augmented Assessment Team Evolution of the LBLOCA Model Concern - TOODEE2 Updates t Four Distinct Phases:
t
. Phase 1 -
FCTF Testing and Correlation pre-1987 Development
. Phase 2 -
Early Application Experience; 1987-1991 l Non-Physical Behavior Concern Defined
. Phase 3 -
Resolution to Non-Physical 1991-1995 Trend Developed to improve Sensitivity Analysis Capability !
. Phase 4 -
Resolution Approach Deemed 6/95-Present Inappropriate 3 I t #2296
SIEMENS l SPC PWR LBLOCA Augmented Assessment Team Preliminary Assessment Findings Regarding TOODEE2 Updates
. Phase 1: Less Than Adequate Test Planning and Design Less Than Adequate Correlation Verification and Validation
. Phase 2: Less Than Adequate Problem Tracking and Closure Less Than Adequate Technical Review
. Phase 3: Less Than Adequate Code Change Control Less Than Adequate Licensing Compliance Review
. Phase 4: Less Than Adequate Licensing Submittals Less Than Adequate Management interface w/NRC 4 19122196
___________________._._.___m___ _ _ _ _ _ .- _- . _ _ - - ___ _ __, _
SIEMENS SPC PWR LBLOCA Augmented Assessment Team Preliminary Assessment Team Recommendations
- New provisions for error identification, resolution, and closure are well-founded; application to Engineering / Methods & Codes should proceed judiciously
. Our current code revision control process should be reviewed ,
and revised, as appropriate, in light of identified weaknesses in previous work
- Create Engineering Quality Teams (EQTs) to improve licensing application and analytical work
. Create an Engineering Assessment Program to improve performance
SIEMENS SPC Communication Initiatives i
t Ilblective:
i Improved recognition of NRC issues and requests.
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SPC Communication Initiatives Implement written guidance to define requirements for
- evaluation and reporting to licensees for submittal of i
code and model changes.
- . Implement written guidance for effective communication with the NRC and licensees.
Initiate benchmarking with utility customers to learn effective NRC submittal and reporting processes.
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