ML030420264

R. E. Ginna Nuclear Power Plant, Relief, Inservice Testing Program Relief Request PR-2, MB7232

ML030420264
Person / Time
Site:	Ginna
Issue date:	02/10/2003
From:	Richard Laufer NRC/NRR/DLPM/LPD1
To:	Mecredy R Rochester Gas & Electric Corp
Clark R, NRR/DLPM, 415-2297
References
TAC MB7232
Download: ML030420264 (4)

Text

February 10, 2003 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649

SUBJECT:

R. E. GINNA NUCLEAR POWER PLANT - INSERVICE TESTING PROGRAM RELIEF REQUEST PR-2 (TAC NO. MB7232)

Dear Dr. Mecredy:

By letter dated January 9, 2003, Rochester Gas and Electric (RG&E) requested the Nuclear Regulatory Commissions (NRCs) approval to use a more recent edition and addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code). The revised Code with addenda allows for pump analysis and the establishment of new reference values as a part of the corrective actions to be taken when pump test acceptance criteria are not met. The current Code of record for the Ginna Inservice Test (IST) program is the 1987 Edition and 1988 Addenda of the ASME OM Part 6 Standard (OM-6). RG&E requested approval to use paragraph ISTB 6200(c) of the 1998 Edition up to and including the 2000 Addenda of the ASME OM Code related to inservice testing of pumps for the remainder of its fourth ten-year IST interval. The analysis required by ISTB 6200(c) includes both pump and system level evaluations to determine operational readiness, the cause of the change in pump performance, and an evaluation of all trends indicated by available data. The results of the analysis are to be documented in the Record of Tests as specified in paragraph 7.3 of OMa-1988, Part 6.

Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(f)(4)(iv) states that inservice testing of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a(b), subject to NRC approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions and addenda are met. The 1998 Edition up to and including the 2000 Addenda of the ASME OM Code were incorporated by reference in 10 CFR 50.55a(b) on September 26, 2002 (67 FR 60520), with no modifications or limitations placed on ISTB requirements. Therefore, the request to use the portions of a later Code and Addenda associated with the inservice testing of pumps at Ginna submitted by RG&E in its letter dated January 9, 2003, is approved pursuant to 10 CFR 50.55a(f)(4)(iv).

Sincerely,

/RA/

Richard J. Laufer, Chief, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-244 cc: See next page

February 10, 2003 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649

SUBJECT:

R. E. GINNA NUCLEAR POWER PLANT - INSERVICE TESTING PROGRAM RELIEF REQUEST PR-2 (TAC NO. MB7232)

Dear Dr. Mecredy:

By letter dated January 9, 2003, Rochester Gas and Electric (RG&E) requested the Nuclear Regulatory Commissions (NRCs) approval to use a more recent edition and addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code). The revised Code with addenda allows for pump analysis and the establishment of new reference values as a part of the corrective actions to be taken when pump test acceptance criteria are not met. The current Code of record for the Ginna Inservice Test (IST) program is the 1987 Edition and 1988 Addenda of the ASME OM Part 6 Standard (OM-6). RG&E requested approval to use paragraph ISTB 6200(c) of the 1998 Edition up to and including the 2000 Addenda of the ASME OM Code related to inservice testing of pumps for the remainder of its fourth ten-year IST interval. The analysis required by ISTB 6200(c) includes both pump and system level evaluations to determine operational readiness, the cause of the change in pump performance, and an evaluation of all trends indicated by available data. The results of the analysis are to be documented in the Record of Tests as specified in paragraph 7.3 of OMa-1988, Part 6.

Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(f)(4)(iv) states that inservice testing of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a(b), subject to NRC approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions and addenda are met. The 1998 Edition up to and including the 2000 Addenda of the ASME OM Code were incorporated by reference in 10 CFR 50.55a(b) on September 26, 2002 (67 FR 60520), with no modifications or limitations placed on ISTB requirements. Therefore, the request to use the portions of a later Code and addenda associated with the inservice testing of pumps at Ginna submitted by RG&E in its letter dated January 9, 2003, is approved pursuant to 10 CFR 50.55a(f)(4)(iv).

Sincerely,

/RA/

Richard J. , Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-244 cc: See next page DISTRIBUTION:

PUBLIC PDI-1 R/F SRichards RLaufer DTerao RClark GKlein SLittle GHill (2) OGC HNeih, EDO ACRS BPlatchek, R-I Accession Number: ML030420264 *See previous concurrence OFFICE PDI-1:PM PDI-1:LA EMEB:SC* OGC* PDI-1:SC NAME RClark SLittle DTerao DHoefling RLaufer DATE 2/6/03 2/6/03 01/31/03 02/05/03 2/7/03 OFFICIAL RECORD COPY

R.E. Ginna Nuclear Power Plant cc:

Kenneth Kolaczyk, Sr. Resident Inspector Mr. Paul Eddy R.E. Ginna Plant New York State Department of U.S. Nuclear Regulatory Commission Public Service 1503 Lake Road 3 Empire State Plaza, 10th Floor Ontario, NY 14519 Albany, NY 12223 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. William M. Flynn, President New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Daniel F. Stenger Ballard Spahr Andrews & Ingersoll, LLP 601 13th Street, N.W., Suite 1000 South Washington, DC 20005 Ms. Thelma Wideman, Director Wayne County Emergency Management Office Wayne County Emergency Operations Center 7336 Route 31 Lyons, NY 14489 Ms. Mary Louise Meisenzahl Administrator, Monroe County Office of Emergency Preparedness 1190 Scottsville Road, Suite 200 Rochester, NY 14624