ML20216C033
| ML20216C033 | |
| Person / Time | |
|---|---|
| Issue date: | 05/08/1998 |
| From: | Craig C NRC (Affiliation Not Assigned) |
| To: | Essig T NRC (Affiliation Not Assigned) |
| References | |
| PROJECT-694 NUDOCS 9805190069 | |
| Download: ML20216C033 (37) | |
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UNITED STATES l
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NUCLEAR REGULATORY COMMISSION l
o WASHINGTON, D.C. 20555-0001 l
'>w May 8, 1998 l
MEMORANDUM FOR: Thomas H. Essig, Acting Chief l
Generic issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation x
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FROM:
Claudia M. Craig, Senior Project Manage Generic issues and Environmental Projects Branch Division of Reactor Program Management b
Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF WESTINGHOUSE OWNERS GROUP (WOG)
MEETING ON BAFFLE BARREL BOLTING (B') PROGRAM The subject meeting was held at the NRC offices in Rockville, Maryland on April 23,1998, between members of the WOG, Westinghouse, and NRR staff. The purpose of the meeting was to continue discussions on the WOG B' program, specifically to provide an update of the program analyses and site inspection / replacement preparation activities, to address items from the April 9,1998, NRC letter to the WOG, to present an alternative licensing strategy, to provide a summary of the risk informed safety significance assessment, and to present the results of the application of the B methodology to two loop plants. Attachment 1 is a list of participants. is a copy of the non-proprietary presentation material.
The WOG summarized the proposed licensing schedule which identified a number of topical reports that the WOG requested be reviewed and approved by the NRC by late summer 1998 to support the lead plant outages scheduled for fall 1998. In March 1998, the staff advised the WOG that the proposed licensing schedule could not be met and provided the WOG a letter dated April 9,1998, requesting a discussion of the B' program's safety significance, alternate approaches, and plant-specific submittal schedules.
During the meeting, the WOG provided a summary of the work performed to develop a risk assessment. The WOG performed the risk assessment to evaluate the risk associated with the possibility of degraded bolts in the baffle barrel region, to conform to the draft NRC risk-informed guidance, and provide insights such that baffle barrel bolt degradation can be treated as an aging management issue. Based on this and previous presentations, the staff did not identify significant concems with the risk assessment, however, a formal review was not performed by the staff.
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i The WOG and staff discussed the status of the review of the topical report on break opening j
times. The staff provided a Request for Additional Information (RAI) to which the WOG responded. The staff had several additional comments and committed to provide those to the
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WOG in the near future. The WOG needs approval of the topical report in June 1998.
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T. Essig
-2 May 8, 1998
/s an alternative to the previous WOG request for an expedited staff approval of a number of topical reports (WCAPs) by September 15,1998, WOG is only requesting approval of the WCAP-14748/9," Justification for increasing Break Opening Times" by June 1998. WOG's plan for the lead plants (Point Beach 2 and Farley 1)is to preemptively replace the number of bolts necessary to maintain the design requirements by using the 10 CFR 50.59 process. For non-lead plants, WOG proposes the use of data from the U.S. lead plant (s) and foreign plants as input to evaluate potentially nonconforming and degraded conditions and apply the process of Generic Letter 91-18, Revision 1, should degraded bolts be identified. WOG presented an overview of a generic 10 CFR 50.59 evaluation for baffle bolting repair and replacement activities, and concluded that; 1) no unreviewed safety questions exist; 2) no technical specification changes are required; 3) the 10 CFR 50.59 process is acceptable for replacement of baffle bolts using the Westinghouse methodology; and 4) NRC approval is not required prior to this activity. The WOG queried the staff regarding use of a 10 CFR 50.59 process. The staff indicated that such an approach appeared reasonable; however, each individual licensee would have to make their own determination.
One of the primary issues raised by the staff regarding the baffle bolt assessments is the proposed use of ASME and SRP stress allowables intended for non-irradiated materials to evaluate irradiated bolts in existing internals. The WOG is expected to provide additional data in support of the proposed allowable bolt stresses. The staff also expressed interest in the l
Cetails of WOG and licensee programs for replacement bolt manufacture, details of the onsite ceptacement activity (tooling, personnel qualification, etc.) and diagnostic actions on removed i
bolts.
The WOG discussed upcoming submittals, outage schedules, plant specific submittals and ensured that the questions identified in the April 9, W98, NRC letter had been addressed during the meeting. The WOG plans on documenting its response to the NRC in a letter to be issued I
in the near future. The staff distributed a draft schedule (Attachment 3) that listed the topical reports submitted to date and the topicals to be submitted in the future and identified the level of effort and schedule to complete the review based on existing workloads.
The WOG, in a proprietary portion of the meeting, discussed the application of the methodology to the two loop plants to determine the number and location of the bolts to be replaced.
I Project No. 694 l
Attachments: As stated l
cc w/atts: See next page l
l t
l l
T. Essig May 8, 1998 As an alternative to the previous WOG request for an expedited staff approval of a number of topical reports (WCAPs) by September 15,1998, WOG is only requesting approval of the WCAP-14748/9, " Justification for increasing Break Opening Times" by June 1998. WOG's plan for the lead plants (Point Beach 2 and Farley 1) is to preemptively replace the number of bolts necessary to maintain the design requirements by using the 10 CFR 50.59 process. For non-lead plants, WOG proposes the use of data from the U.S. lead plant (s) and foreign plants as input to evaluate potentially nonconforming and degraded conditions and apply the process of Generic Letter 91-18. Revision 1, should degraded bolts be identified. WOG presented an i
overview of a generic 10 CFR 50.59 evaluation for baffle bolting repair and replacement activities, and concluded that; 1) no unrevie'.ved safety questions exist; 2) no technical specification changes are required; 3) the 10 CFR 50.59 process is acceptable for replacement of baffle bolts using the Westinghouse methodology; and 4) NRC approval is not required prior j
to this activity. The WOG queried the staff regarding use of a 10 CFR 50.59 process. The staff indicated that such an approach appeared reasonable; however, each individuallicensee would have to make their own determination.
One of the primary issues raised by the staff regarding the baffle bolt assessments is the
)
proposed use of ASME and SRP stress allowables intended for non-irradiated materials to evaluate irradiated bolts in existing internals. The WOG is expected to provide additional data in support of the proposed allowable bolt stresses. The staff also expressed interest in the details of WOG and licensee programs for replacement bolt manufacture, details of the onsite replacement activity (tooling, personnel qualification, etc.) and diagnostic actions on removed I
bolts.
The WOG discussed upcoming submittals, outage schedules, plant specific submittals and ensured that the questions identified in the April 9,1998, NRC letter had been addressed during the meeting. The WOG plans on documenting its response to the NRC in a letter to be issued in the near future. The staff distributed a draft schedule (Attachment 3) that listed the topical reports submitted to date and the topicals to be submitted in the future and identified the level of effort and schedule to complete the review based on existing workloads.
The WOG, in a proprietary portion of the meeting, discussed the application of the methodology to the two loop plants to determine the number and location of the bolts to be replaced.
l Project No. 694 Attachments: As stated cc w/atts: See next page DISTRIBUTION-See attached page i
DOCUMENT NAME: 4_23_98. MIN
- See previous concurrence OFFICE PGEB (A)SC:PGEB BC:EMEB NAME CCraig:sw*
MMalloy*
RWessman*
I DATE 04 /29 /98 05 / 04 /98 05/08 /98 OFFICIAL RECORD COPY
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l DISTRIBUTION: w/ attachments: Summary of April 23,1998, meeting with WOG dated May 8, 1998 Hard_ Copy Central Files l
PUBLIC l
Project File PGEB R/F MMalloy CCraig E-Mail:
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JRoe/DMatthews TEssig GHolahan/SNewberry Glainas/JStrosnider MMcNeil, RES CGrimes l
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KWichman FGrubelich JRajan AEl-Bassioni LLund, RES CECarpenter j
l KManoly Slee,SPSB i
RWessman LLois RCaruso TCollins JZimmerman Llois LGundrum WLiu MShuaibi l
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WOG/NRC MEETING BAFFLE BARREL BOLTING PROGRAM APRIL 23,1998 MEETING PARTICIPANTS Name Organization Michael McNeil NRC/RES/DET Wan C. Liu NRC/NRR/PDLR Allen Hiser NRC/NRR/EMCB Charles Tomes Wisconsin Public Service Corp.
Lee Rochino Rochester Gas & Electric Francis Grubelich NRC/NRR/EMEB Dick Wessman NRC/NRR/EMEB J. Rajan NRC/NRR/EMEB Richard Schwirian Westinghouse Albert Jones Southern Nuclear-Farley
' Adel El-Bassioni NRC/NRR/SPSB Ken Balkey Westinghouse
' David Forsyth Westinghouse Bob Borsum B&WOG Karl Jacobs NYPA George Wrobel RG&E Kamal Manoly NRC/NRR/EMEB Charles Boyd Westinghouse Mark Ajiuni SNC Farley J.S. Galembush Westinghouse Roger Newton WEPCo Claudia Craig NRC/NRR/PGEB Patrick Wdliams FTl Frank Gregory FTl Jim Barsic Westinghouse Steve DiTommaso WOG Project Office Ralph Caruso NRC/NRR/SRXB Mike Schoppman Florida Power & Light Ian Wilson Westinghouse Lynn Connor DSA Charlie Griffin Carolina Power & Light Dan Trombola Westinghouse Robert L. Phillips Tennessee Valley Authority Linda L. Gundrum NRC/NRR/PD3-1 Mohammed Shuaibi NRC/NRR/SRXB Gus Lainas NRC/NRR/DE ATTACHMENT 1
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Mr. Hank Sepp Westinghouse Electric Corporation Mail Stop ECE 4-07A P.O. Box 355 Pittsburgh, Pennsylvania 15320-0355 Mr. Jack Bastin, Director Regulatory Affairs Westinghouse Electric Corporation 11921 Rockville Pike Suite 107 Rockville, MD 20852 Mr. Andrew Drake Westinghouso Owners Group Westinghouse Electric Corporation Mail Stop ECE 5-16 I
P.O. Box 355 Pittsburgh, Pennsylvania 15320-0355
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