ML18107A470

Discusses Closure of Listed TACs in Response to Requests for Addl Info Re GL 92-01

ML18107A470
Person / Time
Site:	Salem
Issue date:	07/30/1999
From:	Milano P NRC (Affiliation Not Assigned)
To:	Keiser H Public Service Enterprise Group
References
GL-92-01, TAC-MA0567, TAC-MA0568, NUDOCS 9908040207
Download: ML18107A470 (4)

Text

UNITED STATE'3 NUCLE,.\\R REGULATORY O:OMMISSIOtJ Mr. Harold W. Keiser Chief Nuclear Officer & President -

Nuclear Business Unit Public Service Electric & Gas Company Post Office Box 236

• Hancocks Bridge, NJ 08038 WASHINGTON, O.C. 20555--0001

. July 30, 1999

SUBJECT:

CLOSURE OF TAC NOS. MA0567 AND MA0568 - RESPONSE TO THE REQUESTS FOR ADDITIONAL INFORMATION (RAI) TO GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, "REACTOR VESSEL STRUCTURAL INTEGRITY," FOR THE SALEM NUCLEAR GENERATING STATION, UNIT NOS.1AND2

Dear Mr. Keiser:

On May 19, 1995, the U.S. Nuclear Regulatory Commission (NRG) 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 report 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 1 O of the Code of Federal Regulations (10 CFR 50.60 and 1 O CFR 50.61 ), and to the requirements of Appendices G and H to Part 50 of Title 1 O of the Code of Federal Regulations (Appendices G and H to 10 CFR Part 50).

On August 14, 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 Salem Nucl~ar Generating Station, Unit Nos. 1 and 2. The NRG staff evaluated your response to GL 92-01, Rev. 1, Supp. 1, and provided its conclusion relative to your response on July 31,.

1996. However, since the time of the staff's 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 in CE and B&W fabricated vessels. The additional alloying data were submitted in Topical Reports CE NPSD-1039,

/i Revision 2, CE NPSD-1119, Revision 1, for CE fabricated RPV welds, and BAW-2325, Revision\\\\ rro\\

.1, for B&W fabricated RPV welds. In addition, Chicago Bridge and Iron (CB&I) BWR data were.'1 submitted in Topical Report BWRVIP-46. As a result of the efforts by CE and B&W, the staff

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determined that additional information was necessary relative to the structural integrity assessments for your plants. On June 11, 1998, the staff issued a request for additional information (RAI)_ in regard to the alloying chemistries of beltline welds, y<;>ur assessment of surveillance data for your facility, pressure-temperature (P-T} limits, and pressurized thermal shock (PTS} assessments for the Salem units. In.general, with respect to the contents of the r

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.. v RAI, the staff 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, and 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 1 O CFR 50.60, 1 O CFR 50.61, and Appendices G and H to 1 O CFR Part 50, as applicable to the licensing bases tor your plants.

You provided your response to the staff's RAI tor Salem on August 4, 1998. As a result of the staff's review of your responses to GL 92-01, Revision 1; GL 92-01, Rev. 1, Supp. 1; and the Supp. 1 RAI, the staff has revised the information in the Reactor Vessel Integrity Database *

(RVID) and is releasing it as RVID Version 2.

The new database diskettes are posted on the world-wide-web at a location which is linked 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.AVID are acceptable for your plant. No additional

.information is necessary with* regard to the structural integrity.assessments. Future submittals onP:..Tlimits, PTS (only*applicableto PWRs), or upper shelf energy (USE) should reference the most current information.

This closes the staff's efforts in regard to TAC Nos. MA0567 and MA0568. The staff appreciates your efforts in regard to this matter.

If you have any questions regarding this matter, please contact me at (301) 415-1457.

Docket Nos. 50-272 and 50-311

• cc: See next page Sincerely, c-IB~

Patrick D. Milano, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation

1....

Public Service Electric & Gas Company cc:

Jeffrie J. Keenan, Esquire Nuclear Business Unit - N21 P.O. Box236 Hancocks Bridge, NJ 08038 General Manager - Salem Operations Salem Nuclear Generating Station P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Louis Storz Sr. Vice President - Nuclear Operations Nuclear Department P.O. Box236 Hancocks Bridge, NJ 08038 Senior Resident Inspector Salem Nuclear Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 Dr. Jill Lipoti, Asst. Director Radiation Protection Programs NJ Department of Environm.ental Protection and Energy CN 415 Trenton, NJ 08625-0415 Maryland Office of People's Counsel 6 St. Paul Street, 21st Floor Suite 2102 Baltimore, MD 21202 Ms. R..A. Kankus Joint Owner Affairs PECO Energy Company 965 Chesterbrook Blvd., 63C-5 Wayne, PA 19087 Mr. Elbert Simpson Senior Vice President-Nuclear Engineering Nuclear Department P.O. Box236 Hancocks Bridge, NJ 08038 Salem Nuclear Generating Station, Units 1 and 2 Richard Hartung Electric Service Evaluation Board of Regulatory Commissioners 2 Gateway Center, Tenth Floor Newark, NJ 07102 Regional Administrator, Region I

• U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Lower Alloways Creek Township c/o Mary 0. Henderson, Clerk Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Director - Licensing Regulation & Fuels Nuclear Busienss Unit - N21 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. David Wersan Assistant Consumer Advocate Office of Consumer Advocate 1425 Strawberry Square Harrisburg, PA 17120 Manager - Joint Gen-eration Atlantic Energy 6801 Black Horse Pike Egg Harbor Twp., NJ 08234-4130 Carl D. Schaefer External Operations - Nuclear.

Delmarva Power & Light Company P.O. Box231 Wilmington, DE 19899 Public Service Commission of Maryland Engineering Division Chief Engineer 6 St. Paul Centre Bal~imore, MD 21202-6806 Mr. Harold W. Keiser Chief Nuclear Officer & President Nuclear Business Unit Public Service Electric and Gas Company

RAI, the staff 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, and 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 1 O CFR 50.60, 1 O CFR 50.61, and Appendices G and H to 1 O CFR Part 50, as applicable to the licensing bases for your plants.

You provided your response to the staff's RAI for Salem on August 4, 1998. As*a result of the staff's review of your responses to GL 92-01, Revision 1; GL 92-01, Rev. 1, Supp. 1; and the Supp. 1 RAI, the staff has revised the information in the Re.actor Vessel Integrity Database (RVID) and is releasing it as RVID Version 2.

The new database diskettes are posted on the world-wide-web at a location which is linked to the NRG 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 the staff's efforts in regard to TAC Nos. MA0567 and MA0568. The staff appreciates your efforts in regard to this matter.

If you have any questions regarding this matter, please contact me at (301) 415-1457.

Docket Nos. 50-272 and 50-311 cc: See next page DISTRIBUTION:

. Pocket File

• PUBLIC PD 1-2 R/F JClifford KWichman Sincerely, ORIGINAL SIGNED BY: R, *. -Eimis. for Patrick D. Milano, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation TClark OGG ACRS AHeiser Alee PMilano GVissing MOprendek, RGN-1 DOCUMENT NAME: LTRa0567.wpd OFFICE PDl-2/PM PDl-2/LA

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