ML17265A620
| ML17265A620 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/08/1999 |
| From: | Bajwa S NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17265A621 | List: |
| References | |
| TAC-MA3286, TAC-MA4706, NUDOCS 9904140159 | |
| Download: ML17265A620 (6) | |
Text
Dr. Robert C. Mecredy
'Vice President, Nuclear rations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649 April 8, 1
SUBJECT:
REQUEST FOR RELIEF NO. 33 FROM THE AMERICANSOCIETY OF MECHANICALENGINEERS (ASME) CODE SECTION XI REQUIREMENTS FOR THE R. E. GINNA NUCLEAR POWER PLANTTHIRD 10-YEAR INSERVICE INSPECTION INTERVAL(TAC NOS. MA3286 AND MA4706)
Dear Dr. Mecredy:
By letter dated August 6, 1998, as supplemented by letter dated February 9, 1999, you requested relief (RR-33) from the examination requirement of the ASME Code,Section XI, for the circumferential shell welds of the reactor pressure vessel, pursuant to the provisions of 10 CFR 50.55a(g)(5)(iii) for the third 10-year inspection interval of the unit. The NRC staff concludes that the proposed alternative methodology meets or exceeds the Section XI requirements, provides for better qualified examiners and higher quality examinations and relief is granted.
The alternative inspection is approved pursuant to 10 CFR 50.55a(a)(3)(i).
The relief granted is authorized by law and will not endanger life or property, or the common defense and security and is.otherwise in the public interest giving due consideration to the burden upon the licensee ifthe requirements were imposed on the facility. The proposed alternative provides an acceptable level of quality and safety. The staff's evaluation and conclusion are contained in the enclosed safety evaluation with attached Technical Letter
'eport.
Therefore, the subject request for relief from the Code requirement is granted for the third 10-year inspection interval.
Sincerely, ORIGINAL SIGNED RY:
S. Singh Bajwa, Chief, Section 1
Project Directorate I
Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
Safety Evaluation w/attached Technical Letter Report ccw/encl: See next page piG DOCUMENT NAME: G:EGINNA)RELA4706.WPD DISTRIBUTION:
See attached Mg FN CMEEE MPV DOCUMENT NAME: G:)GINNA)RELA4706.WPD To receive a copy of this doctmtent, indicate in the box:
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Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 April 8, 1999
SUBJECT:
REQUEST FOR RELIEF NO. 33 FROM THE AMERICANSOCIETY OF MECHANICALENGINEERS (ASME) CODE SECTION XI REQUIREMENTS FOR THE R. E. GINNA NUCLEAR POWER PLANTTHIRD 10-YEAR INSERVICE INSPECTION INTERVAL(TAC NOS. MA3286 AND MA4706)
Dear Dr. Mecredy:
Therefore, the subject request fo'r relief from the Code requirement is granted for the third 10-year inspection interval.
Sincerely, By letter dated August 6, 1998, as supplemented by letter dated February 9, 1999, you requested relief (RR-33) from the examination requirement of the ASME Code,Section XI, for the circumferential shell welds of the reactor pressure vessel, pursuant to the provisions of 10 CFR 50.55a(g)(5)(iii) for the third 10-year inspection interval of the unit. The NRC staff concludes that the proposed alternative methodology meets or exceeds the Section XI requirements, provides for better qualified examiners and higher quality examinations and relief is granted.
The alternative inspection is approved pursuant to 10 CFR 50.55a(a)(3)(i).
The relief granted is authorized by law and will not endanger life or property, or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee ifthe requirements were imposed on the facility. The proposed alternative provides an acceptable level of quality and safety. The staff's evaluation and conclusion are contained in the enclosed safety evaluation with attached Technical Letter Report.
Docket No. 50-244 S. Singh Bajwa, Chief, Section 1
Project Directorate I
Division of Licensing Project Management Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation w/attached Technical Letter Report ccw/encl: See next page
~
4 4
Dr. Robert C. Mecredy Rochester Gas and Electric Company R.E. Ginna Nuclear Power Plant CC:
Peter D. Drysdale, Sr. Resident Inspector R.E. Ginna Plant
,U.S. Nuclear Regulatory Commission 1503 Lake Road Ontario, NY 14519 Regional Administrator, Region I
U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. F. William Valentino, President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399 Charles Donaldson, Esquire Assistant Attorney General New York Department of L'alw 120 Broadway New York, NY 10271 Nicholas S. Reynolds
, Winston 8 Strawn 1400 S Street N.W.
Washington, DC 20005-3502 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 111 West Falls Road, Room 11 Rochester, NY 14620 Mr..Paul Eddy New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223
DATE:
April 8, 1999 DISTRIBUTION:
PUBLIC PDI R/F
'I J. Zwolinski/S. Black S. Bajwa S. Little G. Vissing R. Norsworthy (e-mail SE only, RCN)
OGC G. Hill (2 copies)
ACRS T. McLellan B. McCabe R. Blougb, RGN I S. Barber, RGN I cc w/encl: Plant Service list
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