ML20059A782

Summarizes 930929 Meeting W/Numarc to Discuss Current Status of GL 92-01, Reactor Vessel Structural Integrity

ML20059A782
Person / Time
Issue date:	10/21/1993
From:	Mcdonald D Office of Nuclear Reactor Regulation
To:	Wiggins J Office of Nuclear Reactor Regulation
References
GL-88-11, GL-92-01, GL-92-1, NUDOCS 9310270118
Download: ML20059A782 (5)

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October 21, 1993 1

MEMORANDUM FOR: James T. Wiggins, Acting Director Division of Engineering Office of Nuclear Reactor Regulation FROM:

Daniel G. Mcdonald, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

SUMMARY

OF MEETING HELD ON SEPTEMBER 29, 1993, WITH NUCLEAR MANAGEMENT AND RESOURCES COUNCIL (NUMARC) TO DISCUSS THE CURRENT STATUS OF GENERIC LETTER (GL) 92-01, " REACTOR VESSEL STRUCTURAL INTEGRITY" 4

4 BACKGROUND I

I Generic Letter (GL) 92-01, " Reactor Vessel Structural Integrity," Revision 1, was issued on March 6, 1992. The GL is part of the Nuclear Regulatory f

Commission (NRC) staff's continuing program to evaluate reactor vessel integrity. The informatien provided is being used to confirm that all licensees are complying with the requirements of 10 CFR 50.60,10 CFR 50.61, Appendices G and H to 10 CFR Part 50, and are fulfilling the comitments made in response to GL 88-11. "NRC Position On Radiation Embrittlement of Reactor i

Vessel Materials and Its Impact On Plant Operation."

5 NUMARC has classified reactor vessel issues as a priority item. NUMARC informed the Commission that it is responsible for the coordination of the utilities' generic activities associated with reactor vessel issues including the regulatory changes discussed in SECY 91-333, " Additional Requirements for Yankee Rowe Pressure Vessel Issues," and the responses to GL 92-01.

l PURPOSE The subject meeting was held on September 29, 1993, at the NRC Headquarters located at One White Flint North in Rockville, Maryland. The purpose of the meeting was for the NRC staff to present the current status of its efforts related.to GL 92-01 and identify those areas of concern y ke PSRC could assist in focusing the utilities efforts.

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A list of attendees is enclosed.

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l Mr. James:T. Wiggins October 21, 1993

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SUMMARY

The NRC staff indicated all of the remaining requests for additional C i information (RAls) would be issued in early October. The responses to the i

I RAIs which have been received are currently being reviewed and this portion of the review effort is currently scheduled to be completed by the end of December.

It was noted that, in some cases, there is incomplete data or some of the data provided is inconsistent with that provided in previous submittals and will require resolution with individual licensees. These problems impact both the upper shelf energy (USE) and pressurized thermal shock issues.

The next item discussed was the status of the bounding equivalent margins analysis being provided by the owners groups. The Boiling Water Reactor Owners Group and the Babcock and Wilcox Reactor Veuel Owners Group submittals',.

are currently under review and the staff is waitirn for the Westinghouse % 6 &

Owners Group (WOG) and the Combustion Engineering Owners Group (CEOG)

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submittal s.

Mr. Cozens, who was representing NUMARC, indicated that the:WOG 4, _ R report would be submitted within a couple of days and he would check on thef F

'r status of the CEOG report.

Both reports have now been submitted. The staff. :P

.q noted that some licensees are still in the process of gathering and submitti data on vessel materials in lieu of referencing the applicable owners group

QQ1, bounding equivalent margins analysis. The staff is concerned that it may'taki

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significant time and resources to assure the validity and accuracy of the data provided.

It was noted that the equivalent margins analysis addresses near term concerns related to reactor vessel material issues and that the utilities and staff would continue to pursue other materials concerns (e.g., chemistries and material properties) that may impact issues such as low temperature overpressurization set points, reference temperature-pressurized thermal shock (RTg ) values, and vessel pressure-temperature limits, i

The staff described the Reactor Vessel Integrity Data base (RVID) it is developing using all of the available material data including that provided in response to the GL and RAls.

It was further indicated that the RVID should be completed in,the.May 1994 time frame.

w Mr. Cozens sNed;that,the industry has a similar initiative in this area and suggested that:thejstaffennd industry work together to assure a ceglete data base., The staffi tedtseted it will continue development of the RVID on its projected schedule?!t'was agreed to set up a meeting in late November or early December 1993 to discuss efforts currently underway for developing detailed material data bases.

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i Mr. James T. Wiggins October 21, 1993

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The staff indicated that it intended to summarize the status of issues and concerns:related to the structural integrity of reactor pressure vessels in a hn

~;i9 NUREG' report. The NUREG report is currently expected to be provided to the f

Commission by June 1994.

'. k Daniel G. Mcdonald, Senior Project Manager Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosure:

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ENCLOSURE

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• September 29. 1993 Generic letter (GL) 92-01

" Reactor Vessel Structural Intecrity" List of Attendees PARTICIPANTS ORGANIZATION Daniel Mcdonald NRC/NRR/PDI-1 Robert A. Capra NRC/NRR/PDI-1 ED Hackett NRC/NRR/EMCB i

Simon Sheng NRC/NRR/EMCB Barry J. Elliot NRC/NRR/EMCB Jack Strosnider NRC/NRR/EMCB i

Kurt Cozens NUMARC t

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Mr. James T. Wiggins October 21, 1993 f

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The staff indicated that it intended to summarize the status of issues and concerns related to the structural integrity of reactor pressure vessels in a j

NUREG report. The NUREG report is currently expected to be provided to the Commission by June 1994.

i Original signed by-i Daniel G. Mcdonald, Senior Project Manager Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosure:

List of Attendees DISTRIBUTION:

Central File CVogan ACRS (10)

NRC & Local PDRs DMcDonald VMcCree, 17/G/21 PDI-1 Reading OGC CCowgill, RGN-I TMurley/FMiraglia,12/G/18 EJordan, MNBB 3701 JWiggins, 7/D/26 l

JPartlow JStrosnider, 7/D/4 SVarga EHackett, 7/D/4 JCalvo SSheng, 7/0/4 RACapra BElliot, 7/D/4

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