ML20206U221
| ML20206U221 | |
| Person / Time | |
|---|---|
| Issue date: | 05/14/1999 |
| From: | Wen P NRC (Affiliation Not Assigned) |
| To: | Carpenter C NRC (Affiliation Not Assigned) |
| References | |
| PROJECT-694 NUDOCS 9905250114 | |
| Download: ML20206U221 (34) | |
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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066 0001
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M1y 14,1999 MEMORANDUM TO: Cynthia A. Carpenter, Chief Generic issues, Environmental, Financial and Rulemaking Branch Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation FROM:
Peter C. Wen, Project Manager heAvC. W Generic issues, Environmental, Financial and Rulemaking Branch Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF APRIL 29,1999, SEMIANNUAL NRR/ WESTINGHOUSE OWNERS GROUP SENIOR MANAGEMENT MEETING The subject meeting was held at the NRC offices in Rockville, Maryland, on April 29,1999, between representatives of the Westinghouse Owners Group (WOG) and the Office of Nuclear Reactor Regulation (NRR) staff. The purpose of the semiannual senior management meeting (SMM) is to encourage communication between NRR management and the WOG, discuss emerging issues and concerns, and give the status of the important activities of NRR and the WOG. Attachment 1 is a list of attendees, and Attachment 2 contains the WOG presentation material.
- l. INTRODUCTION Samuel Collins, Director of NRR, gave the opening remarks, stressing the importance of the SMM between the WOG and NRC. He highlighted several current issues being worked on by the staff, including the Millstone 2 restart, the Clinton restart, the D.C. Cook restart, the Watts Bar Operational Safeguard Response Evaluation activHy, the Callaway electro-sleeving, the new oversight process, decommissioning activities, the NRR licensing backlog, the risk-informed scope of assessment for the maintenance rule,10 CFR 2.206 on the disposition of fuelleaks,10 CFR 50.72 and 50.73 rulemaking, and the status of the final rule for 10 CFR 50.59. He also briefly discussed the recent NRR reorganization.
II. WOG PRESENTATIONS i
Although the WOG works on a large number of issues at any one time, the WOG specifically addressed nine topics at the SMM: the top nozzle spring clamp screw issue, the redefinition of the large-break loss-of-coolant accident (LB LOCA) licensing basis, the status of the baffle pl' r('
9905250114 990514 77 Q.
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C. Carpenter M3y 14,1999 barrel bolting (BBB) program, the risk-informed anticipated transient without scram (ATWS) model, containment sump issues, core damage assessment guidance (CDAG) and post-accident sampling system (PASS) elimination, risk-informed technical specifications (RI-TS),
the motor-operated valve (MOV) program, and probabilistic safety assessment (PSA) certification. These issues are discussed briefly herein.
Too Nozzle Sorina Clamo Screw issue: At the V.C. Summer plant on April 13,1999, while removing fuel assemblies from the reactor core, the licensee noted that a fuel assembly was not properly latched. A video camera inspection revealed an approximate 1/8-inch gap between the hoiddown spring block assembly and the top nozzle. The problem assembly was frcm a batch of fuel t1at had completed two operating cycles. The WOG presented a chronological status of this event and will supply a more detailed briefing at a later Westinghouse fuel performance meeting with the staff. At the present time, the WOG believes that no operational safety issues resulted from this event.
Redefinition of LB LOCA Licensina Basis: The WOG has undertaken a program in response to Commissioner Diaz' request to redefine the LB LOCA licensing basis by eliminating it as a consideration on the basis of risk perspectNes from probabilistic risk assessments / individual plant examinations (PRAs/IPEs) that show the LB LOCA is not a significant risk contributor.
The WOG believes significant cost savings can be obtained without compromising safety by revising the plant licensing bases. The WOG effort began recently and will continue into 1999, and interactions with the staff will begin sometime in October 1999.
The staff commented that this effort should be performed with a risk-informed perspective, and that the WOG should persuade the industry through the Nuclear Energy institute (NEI) to support this effort.
Status of the Baffle Barrel Boltina Prooram: The WOG discussed the inspections and
)
replacement activities at the Farley, Point Beach, and Ginna facilities. WOG activities have become integrated as one aspect of a broader industry effort, the PWR Materials Reliability Project. The baffle bolt activities include hot cell evaluations of baffle bolts removed from the plants. The WOG concluded that the inspection results to date confirm its previous conclusion that baffle bolt cracking is an aging management issue and not an immediate safety concern.
The staff acknowledged the adequacy of WOG activity on this issue. The staff requested the WOG to share the hot cell result when it becomes availabit Risk-Informed ATWS Model: The WOG wants requirements for reload designs to be based less on the moderator temperature coefficient and more on risk models. A meeting between the staff and the WOG was held on December 17,1998, to discuss this issue. In response to that meeting, the WOG is evaluating the need to enhance certain areas of the program, especially (1) consequence assessment if the reactor coolant system (RCS) pressure exceeds 3,200 psi and (2) detailed assessment of large early release frequency (LERF). The WOG questioned the need to perform detailed LERF assessments for events with very small changes in core damage frequency (CDF).
I
y C. Carpenter Ity 14,1999 The staff commented that guidance has been provided in Regulatory Guide 1.174 and that if the 6CDF is sufficiently below the ALERF criterion, an explicit assessment of conditional LERF need not be performed.
Containment Sumo issues: The concern here is the generation of debris after the LOCA, which has a potential of clogging the containment sump screen. The WOG discussed the position of the PWR Owners Groups (PWR OGs) on the use of leak before break (LBB) on this issue. The WOG believes that by using LBB, the General Design Criterion (GDC) 4 would allow it to exclude dynamic effects associated with postulated pipe ruptures in evaluating the debris generation. In a previous meeting held on December 15,1998, the ctaff did not endorse this interpretation by the PWR OGs, and stated that the issue will be explored further as part of GS!-191.
The WOG is actively participating with NRC to address this issue. It has supported phenomena identification and ranking table (PIRT) panels on both the sump blockage and the coatings issues by providing people to serve on the panels. The WOG also attended NRC public meetings on the sump blockage and coatings issues.
The staff acknowledged the WOG's involvement in this issue and would further like to see a volunteer for the WOG Reference Plants in support of NRC research on this topic.
Core Damaae Assessment Guidance and PASS Elimination: The requirement for a PASS in operating reactors was introduced after the TMI accident. The purpose of the PASS was to provide tho operators with information on the degree of core degradation, radioactivity release, and the general condition of the plant. The PASS was designed by various manufacturers for different licensees, but all designs had to meet the NRC requirements specified in NUREG-0737, " Clarification of TMl Action Plan Requirements." In a letter to NRC dated October 27,1998, the WOG submitted WCAP-14986, Revision 1, "WOG Post-Accident Sampling System Requirements: A Technical Basis," for the staff's review. The WOG is hoping that some of PASS requirements can be eliminated on the basis of the analyses presented in the WCAP.
The current (1984 vintage) WOG CDAG guidance relies heavily on PASS capabilities for core damage assessment. The WOG believes that since insight has been gained in the CDA technology over the years since the development of the 1984 vantage guidance, it is time to revise the CDA methodology. The new guidance will rely on two primary indicators for assessing the type and degree of core damage: the core exit thermocouples and the containment high-range radiation monitor. Thus, CDA will not need PASS input.
Both topical reports were being reviewed by the staff at the time of this meeting.
Risk-Informed Technical Specifications: A joint NRC/ industry effort to develop a set of fully RI-TS is continuing. The WOG is supporting the industry and NRC RI-TS initiatives and will be submitting several RI-TS-related topical reports for the staffs review. The staff indicated that it preferred that submittals be sent in one at a time because this practice will more evenly distribute the staffs workload.
A
1 1
C. Carpenter 4-fty 14,1999 MOV Proaram: The Joint Owners Group (JOG) program was established by industry in response to Generic Letter 96-05, " Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves." The WOG is one of active members of the JOG. The JOG holds a semiannual meeting with the staff to appraise the status of JOG activities. The most recent meeting was held on April 14,1999.
The staff commented that the approach taken by the JOG /WOG on the MOV issue serves as a good example of industry and the staff working together to resolve a safety issue of interest to
)
both.
PSA Certification: The WOG has begun a PSA certification program to perform peer review of l
licensees' PRAs so that they can be used in risk-informed regulation. The intent of this certification is to reduce, as much as possible, the need for staff review of PRAs. The WOG effort is very similar to the Boiling Water Reactor Owners Group (BWROG) effort, which the staff has previously examined.
- The staff commented that there is a disconnect between the BWROG, ASME and the PWR OGs on this issue. NEl has recently been involved in modifying the ASME standard to ensure one process.
Ill. REVIEW of WOG SUBMITTALS to NRC The current and future planned lists of WOG submittals to NRC were reviewed. The NRR staff has made significant progress in eliminating the backlog. Since the previous SMM meeting on October 27,1998, the staff has issued six (6) SERs. A brief discussion was held on the break opening time topical report, as follows:
Break Openino Time: The WOG requested the NRC 's approval of WCAP-14748, " Justification for increasing Break Opening Times in Westinghouse PWRs," in January 1997 for generic application. The staff's approval of the WCAP was limited to the BBB program only. The staff stated in its October 1998 safety evaluation that future applications to other issues outside the BBB program will have to be reviewed on a case-by-case basis, in a letter to NRC dated December 10,1998, the WOG requested that the review of WCAP-14748 be continued for generic application (so that it can be applied to other items in addition to the Baffle Barrel Bolting program). The staff will further discuss the schedule and the review scope with the WOG in a conference call.
IV. NRC ITEMS The staff gave a brief update on the status of the reactor coolant pump sealissue (Generic Safety issue [GSl]-23). The Office of Nuclear Regulatory Research (RES) is responsible for the GSI process. There are issues associated with obtaining proprietary seal models and the corresponding costs. The staff appealed to the WOG to help resolve GSI-23. The Reactor Systems Branch is the NRR contact for this topic, and a meeting will be set up with PWR OGs to further discuss these issues.
e C. Carpenter
-5 May 14,1999 V. CLOSING COMMENTS In the closing comments, Brian Sheron, Associate Director of NRR, described some of the issues that need to be worked on together by the industry groups. He gave the following examples:
Expect the staff to ask risk-related questions even if the licensee's submittalis non-risk e
informed. This happened when Callaway submitted a deterministic steam generator tube sleeving TS change request for the staff's review. Because of the severe accident concern related to the steam generator, the staff asked risk-related questions. The staff is drafting a paper to present its position on this issue to the Commission.
l The staff would like to engage the industry through DSI 13, " Voluntary Industry initiatives," in e
lieu of the generic letter process. A process for determining the threshold for these activities and an approach for confirming licensing actions are needed.
The staff encourages utilities to reach out to their communities and make them aware of the e
Y2K readiness of the utilities.
Finally, a senior WOG representative commented that the WOG has seen very positive changes in NRC staff practices in recent months. He observed that the responses from the staff are more prompt and the staff reviews of the WOG WCAPs is in a more timely manner.
Project No. 694 Attachments: As stated j
l cc w/attsi See next page l
C. Carpenter 5-Ity 14,1999 V. CLOSING COMMENTS in the closing comments, Brian Sheron, Associate Director of NRR, described some of the issues that need to be worked on together by the industry groups. He gave the following examples:
Expect the staff to ask risk-related questions even if the licensee's submittalis non-risk informed. This happened when Callaway submitted a deterministic steam generator tube sleeving TS change request for the staff's review. Because of the severe accident concern related to the steam generator, the staff asked risk-related questions. The staff is drafting a paper to present its position on this issue to the Commission.
The staff would like to engage the industry through DSI 13, " Voluntary industry Initiatives."
in lieu of the generic letter process. A process for determining the threshold for these activities and an approach for confirming licensing actions are needed.
The staff encourages utilities to reach out to their communities and make them aware of the Y2K readiness of the utilities.
Finally, a senior WOG representative commented that the WOG has seen very positive changes in NRC staff practices in recent months. He observed that the responses from the staff are more prompt and the staff reviews of the WOG WCAPs is in a more timely manner.
Project No. 694 Attachments: As stated 1
cc w/atts: See next page j
I DISTRIBUTION: See attached page DOCUMENT NAME: G:pxw\\msum0429.wog OFFICE RGEB (A)SC:RGEB NAME PWen:sw PCW TBergmhh DATE 05/ / 3 /99 05 / jY /99 OFYlCIAL RECORD COPY
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WOG/NRR SENIOR MANAGEMENT MEETING LIST OF ATTENDEES APRIL 29,1999 Name Oraanization Sam Collins NRR Brian Sheron NRR Dave Matthews NRR/ DRIP Frank Gillespie NRR/DIPM Dick Wessman NRR/DE Tim Collins NRR/DSSA Rich Barrett NRR/DSSA/SPSB Jerry Wermiel NRR/DSSA/SRXB Ralph Caruso NRR/DSSA/SRXB l
George Hubbard NRR/DSSA/SPLB Richard Lobel NRR/DSSA/SPLB Jim O'Brien NRR/DIPM/HOLB Peter Wen NRR/ DRIP /RGEB Brew Barron Duke Energy Lou Liberatori Consolidated Edison Larry Walsh Northeast Utilities Roger Newton WEPCo Bob Bryan WA Wayne Harrison South Texas Project Karl Jacobs New York Power Authority
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Tim Herrmann AmerenUE David Lounsbury PSE&G Hank Sepp Westinghouse Jack Bastin Westinghouse Andrew Drake Westinghouse /WOG Project Office Sam Binger Westinghouse /WOG Project Office Leslie Collins ABB-CE
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e Westinghouse Owners Group cc:
Mr. Nicholas Liparulo Westinghouse Electric Corporation Mail Stop ECE 4-15 P.O. Box 355 Pittsburgh, Pennsylvania 15320-0355 Jack Bastin, Director Wectinghouse Electric Corporation 11921 Rockville Pike, Suite 107 Rockville, MD 20852 Mr. Hank Sepp Westinghouse Electric Corporation Mail Stop ECE 4-07A P.O. Box 355 Pittsburgh, Pennsylvania 15320-0355 Mr. Andrew Drake Westinghouse Owners Group Westinghouse Electric Corporation Mail Stop ECE 5-16 P.O. Box 355 Pittsburgh, Pennsylvania 15320-0355
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l DISTRIBUTION: w/atts: Summary of April 29,1999, meeting with WOG dated May 14. 1999 Hard Copy Central Files PUBLIC Project File RGEB R/F PWen E-Mail:
SCollins/RZimmerman BSheron W Kane DMatthews/SNewberry C Carpenter FAkstulewicz T. Bergman B Boger/FGillespie GHolahan/TCollins JStrosnider/R Wessman R Barrett JWermiel RCaruso G Hubbard RLobel JO'Brien GTracy, EDO