ML20196J657

Discusses Closure to TAC MA0543 & MA0544 Re GL 92-01 Rev 1, Suppl 1,RV Structural Integrity.Nrc Has Revised Rvid & Releasing It as Rvid,Version 2 as Result of Review of Responses

ML20196J657
Person / Time
Site:	Farley
Issue date:	07/02/1999
From:	Padovan L NRC (Affiliation Not Assigned)
To:	Dennis Morey SOUTHERN NUCLEAR OPERATING CO.
References
GL-92-01, GL-92-1, TAC-MA0543, TAC-MA0544, TAC-MA543, TAC-MA544, NUDOCS 9907070380
Download: ML20196J657 (4)

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j UNITED STATES NUCLEAR REGULATORY COMMISSION k 2 WASHINGTON, D.C. M66-0001 July 2,1999 Mr. D. N. Morey Vice President - Farley Project Southern Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabama 35201-1295

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 RE: GENERIC LETTER 92-01 CLOSEOUT (TAC NOS. MA0543 AND MA0544)

Dear Mr. Morey:

On May 19,1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter 92-01, Revision 1, Supplement 1 (GL 92-01, Rev.1, Supp.1), " Reactor Vessel Structural Integrity," to holders of nuclear operating licenses. In issuing the GL the staff required addressees of the GL to:

(1) identify, collect and repor1 any new data pertinent to the analysis of structural integrity of the reactor pressure vessels (RPVs) at their nuclear plants, and (2) to assess the impact of that data on their RPV integrity analyses relative to the requirements of Sections 50.60 and 50.61 to Part 50 of Title 10 of the Code of Federal Reaulations (10 CFR 50.60 and 10 CFR 50.61), and to the requirements of Appendices G and H to Part 50 of Title 10 of the Code of Federal Reaulations (Appendices G and H to 10 CFR Part 50).

On August 9,1995, you submitted your initial response to GL 92-01, Rev.1, Supp.1. and provided the requested information relative the structural integrity assessments for the Joseph M. Farley Nuclear Plant, Units 1 and 2. We evaluated your response and issued our evaluation of your response on August 13,1996. However, since tne time of our closure letter, the Combustion Engineering (CE) Owners Group and the Babcock and Wilcox (B&W) Owners Group have each submitted additional data regarding the alloying chemistries of beltline welds O

in CE and B&W fabricated vessels. The Owners Groups submitted additional alloying data in Topical Reports CE NPSD-1039, Revision 2, CE NPSD-1119, Revision 1, for CE fabricated j RPV welds, and BAW-2325, Revision 1, for B&W fabricated RPV welds, in addition, Chicago Bridge and Iron (CB&l) BWR data were submitted in Topical Report BWRVIP-46. The staff d

y determined that additional information was necessary on the structural integrity assessments for your plants as a result of the CE and B&W efforts. On April 3,1998, we issued a request for additionalinformation (RAl) to you in regard to the alloying chemistries of beltline welds, your assessment of surveillance data for your facility, pressure-temperature (P-T) limits, and pressurized thermal shock (PTS) assessments In general, with respect to the RAI contents, we requested that you reassess the alloying chemistries for the beltline welds and RPV surveillance welds relative to the chemistries provided in the applicable topical report. We also requested that you provide the impact of any changes to the best-estimate chemistries for your beltline RPV welds on the structural integrity assessments for your facility relative to the requirements of 10 CFR 50.60,10 CFR 50.61, and Appendices G and H to 10 CFR Part 50, as applicable to the licensing bases for Farley.

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. s D. N. Idorey_ You responded to our April 3,1998, RAI on June 19,1998. We have revised the Reactor Vessel Integrity Database (RVID) and are releasing it as RVID, Version 2, as a result of our review of your responses to GL 92-01, Revision 1, GL 92-01, Rev.1, Supp.1, and the Supp.1 RAl. We posted the new database diskettes on the world-wide-web at a location whicn is linked to the NRC home page (http 1/www.nrc. gov /NRR/RVID/index.html). We recommend that you review this information. If the staff does not receive comments by September 1,1999, we will assume that the data entered into the RVID are acceptable for your plant. No additional .

Information is necessary with regard to the structural integrity assessments. Future submittals on P-T limits, PTS (only applicable to PWRs), or upper shelf energy (USE) should reference the most current information.

This closes our efforts in regard to TAC No(s). MA0543 and MA0544, We appreciate your efforts in regard to this matter. Please call me at (301) 415-1423 if you have any questions.

Sincerely,

1. ^ ' 'A L. Mark Padovan, Project Manager, Section 1 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos.' 50-348 and 50-364 cc: See next page -

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Jos*eph MI Farley Nuclear Plant cc:

Mr. L M. Stinson Rebecca V. Badham General Manager . SAER Supervisor Southern Nuclear Operating Company Southern Nuclear Operating Company

. Post Office Box 470 P. O. Box 470 Ashford, Alabama 36312 Ashford, Alabama 36312 Mr. Mark Ajluni, Licensing Manager Southem Nuclear Operating Company Post Office Box 1295 i Birmingham, Alabama 35201-1295 Mr. M. Stanford Blanton 3 Balch and Bingham Law Firm Post Office Box 306 1710 Sixth Avenue North Birmingham, Alabama 35201 Mr. J. D. Woodard Executive Vice President Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201 State Health Officer Alabama Department of Public Health 434 Monroe Street Montgomery, Alabama 36130-1701 l

Chairman Houston County Commission Post Office Box 6406 Dothan, Alabama 36302 Resident inspector U.S. Nuclear Regulatory Commission 7388 N. State Highway 95 Columbia, Alabama 35319 l

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. D' N. Morey July 2,1999 You responded to our April 3,1998, RAI on June 19,1998. We have revised the Reactor Vessel Integrity Database (RVID) and are releasing it as RVID, Version 2, as a result of our review of your responses to GL 92-01, Revision 1, GL 92-01, Rev.1, Supp.1, and the Supp.1' .

RAl. We posted the new database diskettes on the world-wide-web at a location which is linked I to the NRC home page (http://www.nrc. gov /NRR/RVID/index.html). We recommend that you review this information, if the staff does not receive comments by September 1,1999, we will assume that the data entered into the RVID are acceptable for your plant. No additional information is necessary with regard to the structural integrity assessments. Future submittals on P-T limits, PTS (only applicable to PWRs), or upper shelf energy (USE) should reference the most current information.

'This closes our efforte in regard to TAC No(s). MA0543 and MA0544. We appreciate your efforts in regard to this matter. Please call me at (301) 415-1423 if you have any questions.

Sincerely, Original signed by:

L. Mark Padovan, Project Manager, Section 1 Project Directorate ll Division of Licensing Project Management Office of Nucleer Reactor Regulation Docket Nos. 50-348 and 50-364 cc: See next page DISTRIBUTION:

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