ML20199G890
| ML20199G890 | |
| Person / Time | |
|---|---|
| Issue date: | 11/17/1997 |
| From: | Craig C NRC (Affiliation Not Assigned) |
| To: | Essig T NRC (Affiliation Not Assigned) |
| Shared Package | |
| ML20199G894 | List: |
| References | |
| FRN-63FR50465, PROJECT-694 AF41-2-3, GL-96-05, GL-96-5, NUDOCS 9711250329 | |
| Download: ML20199G890 (6) | |
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November 17, 1997 MEMORANDUM FOR: Thomas H. Essig, Acting Chief Generic issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation Claudia M. Craig, Senior Project Manag O d.IC ALL I
FROM:
Generic issues and Environmental Projects bran)ch i
Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF MEETING WITH THE WESTINGHOUSE OWNERS GROUP (WOG) TO DISCUSS THE WOG REPORT ON MOTOR-OPERATED VALVES (MOV) RISK RANKING The subject meeting was held at the NRC offices in Rockville, Maryland on October 30,1997, between representatives of the WOG, Westinghouse, and the NRC staff. The purpose of the meetir.g was to c'iscuss the WOG Enginee:ing Report V EC-1658," Risk Ranking Approach for Motor-Operated Valves in Response to Generic Letter 96-05." Attachment 1 is a list of meeting participants. On August 25,1997, the NRC staff held a conference call with representatives of the WOG in prepareion for the public meeting on WOG Engineering Report V-EC-1658. The NRC providad a number of questions / comments te.he WOG The WOG provided, by fax, responses to those comments by letters dated August 29,1997, and September 26,1997. The letters are provided as Attachments 2 and 3, respectively. Attachment 4 is a copy of the non-proprietary presentation material discussed at the meeting.
On September 18,1996, the NRC issued Generic Letter (GL) 96-05, " Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves," to request that licensees establish a program, or ensure the effectiveness of the current program, to verify on a periodic basis that safety-related MOVs continue to be capable of performing their safety functions within the current licensing bases of the facility. By letter dated June 2,1997, the WOG submitted Revision 0 to WOG Engineering Report V EC-1658, for NRC staff review. The WOG prepared Engineering Report V-EC-1658 to pr. iide assistance to individual licensees in ranking MOVs according to their risk significance in support of the development of GL 96-05
. programs.
The WOG intends that Westinghouse licensees will be able to apply the MOV risk ranking approach in implementing an industry-wide Joint Owners Grcup (JOG) Program on MOV Periodic Verification. The NRC staff recently completed a safety evaluation on the topical report describing the JOG program. In the JOG program, test iritervals for MOVs will be established based on the MOV's risk significance and functional margin. In a safety evaluation
, g, g dated February 27,1996, the NRC staff accepted, with certain conditions and limitations, a s
method developed by the Boiling Water Reactor (BWR) Owners Group to risk rank MOVs in p f,05 llflli<.
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-2 November 17 1997 During the October 30,1997, meeting, the WOG representatives outlined the planned changes to WOG Engineering Report V EC 1658 described in Attachments 2 and 3 to these meeting mir utes, in addition, the WOG representatives discussed further planned changes to the engineering report listed in Attachment 4 to these meeting' minutes. The NRC staff and WOG
. representatives discussed the planned revision to WOG Engineering Report V-EC-1658, and the WOG representatives agreed to address the NRC staff comments provided during the meeting. Among the planned changes to the engineering report, the WOG stated that risk -
schievement worth will be addressed for each MOV risk category. The WOG will state in the engineering report that potential common cause failures will need to be addressed as part of.
any request to exceed the 10-year test interval limitation. The WOG discussed its development of a list of safety significant MOVs. Attachment 5 is a facsimile transmittal from the WOG following the meeting that provides additionalinformation on safety significant MOVs. The WOG stated that the engir.eering report will specify that safety-related MOVs must be capable of performing their safety function over the 6ntire duration between tests regardless of their risk -
significance, in response to NRC staff comments and discussions during the public meeting, the WOG representatives stated that a revision to WOG Engineering Report V-EC-1658 would be 4
submitted for NRC staff review in early December 1997. The NRC staff plans to complete its review of WOG Engineering Report V-EC-1658 and to prepare a safety evaluation on the i
results of the staff review in early 1998. Based on the discussions at the public meeting on October 30,1997, and actions planned by the WOG, the NRC staff expects to be able to conclude that, with certain conditions and limitations, the WOG program described in WOG Engineering Report V-EC-1658 provides an acceptable method for risk ranking MOVs for Westinghouse-designed plants.
Preject No. 694 Attachments: As steted
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-a DISTRIBUTION: w/ attachments: Summary of October 30,1997, meeting with WOG dated 7 ovember 17,J97 N
Hard Copy Centrol Files PUBLIC Project File PGEB R/F-MCass CCraig E-Mail:
SCollins/FMiraglia RZimmerman BSheron JRoe GHolahan GLainas/JStrosnider RWessman -
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November 17, 1997 MEMORANDUM TO: Thom:s H. Essig, Chief i
Generic Issues and Environmental Proje::ts Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:
_Claudia M. Craig, Senior Project Manager Original Signed By:
Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF MEETING WITH WESTINGHOL'"E TO DISCUSS AXIAL OFFSET ANOMALY (AOA) ANU SEABROOK FUEL FAILURES The subject meeting was held at the Nuclear Reguletory Commission (NRC) offices in Rockville, Maryland on October 23,1997, between representatives of Westinghouse and the NRC staff. The meeting was held to provide additionalinformation regarding the AOA and the Seabrool< fuel failures. By letter dated November 6,1997, Westinghouse provided both p oprietary and non-proprietary versions of the presentation material. Attachment 1 is a copy of the non-proprietary presentation material. %ttachment 2 is a list of meeting participants.
Westinghouse provided a summary of the Calloway AOA event and described the various actions taken in responte to the event, including the plant being held at b% power for the remainder of the fuel cycle. Westinghouse described a meeting that was held to solicit input from utilities, Westinghouse, and EPRI on possible solutions to the AOA issue. Westinghouse provided details on what actions they have taken to determine how to maintain shutdown margin. Westinghouse concluded that higher boiling rates increase AOA susceptability, however, other contributors may include crud source, coolant chemistry, and boron and lithium concentration. Westinghouse described several EPRI and Westinghouse programs that are evaluating the AOA issue.
Westinghouse also provided additional informa'. ion about the fuct failures at Seebrook and the msults of the evaluation to date. Westinghouse performed fuelinspections, a power history evaluation, visual and eddy current examinations on the fuel, oxide measurement, profilometry, and crud scraping. Westinghouse described the mechanisms that have been ruled out and discussed the two possible causes: internal contamination possibly exacerbated by high sustained rod power and crud-induced corrosion. Westinghouse cautioned the root cause may be a combination of the two. Westinghouse described what other actions are being considered and described the corrective actions being taken for Seabrook. Westinghouse expects a decision on whether further examinations are needed by the first quarter of 1998.
Attachmerts: As stated cc w/atts: See next page Distribution: See next page DOCUMENT NAME: 10_23_97. MIN DISTRIBUTION: See next page OFFICE PGEB (A)SC:PGEB BC: SRXB NAME CCraig:M MCasef TCollins %
DATE O/L3/97 h / 0 /97
){ / R/97 OFFICIAL RECORD COPY $3
l T. Essig 2
November 17, 1997 During the October 30,1997, meeting, the WOG representatives outlined the planned changes to WOG Engineering Report V-EC-1658 described in Attachments 2 and 3 to these meeting m!nutes, in addition, the WOG representatives discussed further planned changes to the engineering report listed in Attachment 4 to these meeting minutes. The NRC staff and WOG representatives discussed the planned revision to WOG Engineering Report V-EC-1658, and the WOG representatives agreed to address the NRC staff comments provided during the meeting. Among the planned changes to the engineering report, the WOG stated that risk achievement worth will be addressed for each MOV risk category. The WOG will state in the engineering report that potential common cause failures will need to be addressed as part of any request to exceed the 10 year test interval limitation. The WOG discussed its development of a list of safety significant MOVs. Attachment 5 is a facsimile transmittal from the WOG following the meeting that provides additionalinformation on safety significant MOVs. The WOG stated that the engineering report will specify that safety-related MOVs must be capable of performing their safety function over the entire duration between tests regardless of their risk significance, in response to NRC staff comments and discussions during tbc public meeting, the WOG representatives stated that a revision to WOG Engineering Report V-EC-1658 would be submitted for NRC staff review in early December 1997. The NRC staff plans to complete its review of WOG Engineering Report V EC 1658 and to prepare a safety evaluation on the results of the staff review in early 1998. Based on the discussions at the public meeting on October 30,1997, and actions planned by the WOG, the NRC staff expects to be able to conclude that, with certain cond:tions and limitations, the WOG program described in WOG Engineering Report V-EC-1658 provides an acceptable method for risk ranking MOVs for Westinghouse-designed plants.
Project No. 694 Attachments: As stated cc w/atts: See next page DISTRIBUT1QN:
See attached page DOCUMENT NAME: 10_30_97. MIN OFFICE PGEB SC:PGEp BC:EMEB NAME CCraikb MCh RWessh DATE O / N /97 g / M /97 lti l1 /97 DFFICIAL RECORD COPY
3 WOG/NRC MEETING OCTOBER 30,1997 MEETING PARTICIPANTS Name Organization Claudia Craig NRC/NRR/PGEB Dick Wessman NRC/NRR/EMEB Steve DiTommaso WOG Project Office Steve Reckford BGE - Calvert Cliffs Bonnie Wdliamson Nucleonics Week John Koelbel BGE - Calvert Cliffs Dave Termo NRC/NRR/EMEB Karl Jacobs New York Power Authority /WOG Ike Ezekoye Westinghouse Tech Lead GL 96-05 Jerry Andre Westinghouse /PRA Steve Loehlein DOE - Beaver Valley /WOG Steve Long NRC/NRR/SPSB Thomas Scarbrough NRC/NRR/EMEB Chad Smith Duke Power /MEE-MOV Program Lead ATTACHMENT 1
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