ML17250B281
| ML17250B281 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/29/1993 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17250B282 | List: |
| References | |
| TAC-M84004, NUDOCS 9307010133 | |
| Download: ML17250B281 (5) | |
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Docket No. 50-244 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-000I June 29, 1993 Dr. Robert C. Mecredy Vice President, Nuclear Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649
Dear Dr. Mecredy:
SUBJECT:
RELIEF REQUESTS 23 AND 24 TO FORGO THE 'HYDROSTATIC PRESSURE TEST REQUIRED FOR REPAIRS TO THE SERVICE WATER AND AUXILIARY FEEDWATER SYSTEM, R.E.
GINNA NUCLEAR POWER PLANT (TAC NO. M84004)
I am writing to confirm the verbal authorization we gave during our telephone conference with your staff on Apri] 20, 1993, to implement the subject relief requests.
The NRC staff has reviewed the Rochester Gas and Electric Corporation's (RG&E) submittal of January 12,
- 1993, as supplemented on April 5 and April 19, and two letters on April 20 and May 7, in which RG8IE requested a
"one-time" relief from the required hydrostatic testing, following replacement
. activities, of the service water system (SWS) and the turbine-driven auxiliary feedwater system (TDAFWS) at the R.
E. Ginna Nuclear Power Plant.
The licensee proposed alternative tests to establish the structural integrity and safety of the systems.
The staff concludes that the licensee has demonstrated that the proposed alternatives would provide an acceptable level of quality and safety.
I have enclosed the staff's safety evaluation (SE) to document the bases for the staff's conclusion.
These reliefs are acceptable for a single usage during the 1993 maintenance and refueling outage (Cycle 23), which reaffirms our finding during the telephone conference on April 20,
- 1993, between the NRC staff and RGEE.
The Plant Technical Specifications required both the SWS and TDAFWS to be operational during plant startup on April 21, 1993.
In relief request (RR) 23, the licensee proposed to perform alternate American Society of Mechanical Engineers (ASME)Section III nondestructive examination (NDE) and satisfy alternative pressure test requirements for the replacement of valves V-4611, V-4613, V-4626, V-4669, V-4738, V-4739, and V-4760 in a Class 3
- SWS, and for the replacement of check valve V-4023 in a Class 3
TDAFWS.
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Dr. Robert C. Mecredy June 29, 1993 In RR 24, the licensee proposes to perform alternate ASME Section III NDE and satisfy alternative pressure test requirements for replacement of isolation valves V-4663, V-4013, V-4027, and V-4028 in the Class 3
SWS.
The staff finds the licensee's relief requests 23 and 24 to be acceptable, and, therefore, authorizes the alternative tests as detailed in the enclosed SE pursuant to 10 CFR 50.55a(a)(3)(i).
Sincerely, /s/
Walter R. Butler, Director Project Directorate I-3 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/enclosure:
See next page DISTRIBUTION:
"-Docket File, NRC 8 Local PDRs PDI-3 Reading T. Hurley/F. Miraglia J. Partlow E. Rossi J.
Lieberman S.
Varga J.
Calvo W. Butler T. Clark A. Johnson OGC E. Jordan G. Hill (2)
ACRS (10)
OPA OC/LFDCB V. McCree, EDO J. Linville, RI J. Strosnider G. Johnson D. Naujock OFFICE IIAHE LA:
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)0 93 06 01 93 93 OFFICIAL RECORD COPY FILENAME: A:iGIN84004. REL
Dr. Robert C. Mecredy dune 29, 1993 In RR 24, the licensee proposes to perform alternate ASME Section III NDE and satisfy alternative pressure test requirements for replacement of isolation valves V-4663, V-4013, V-4027, and V-4028 in the Class 3
SWS.
The staff finds the licensee's relief requests 23 and 24 to be acceptable, and, therefore, authorizes the alternative tests as detailed in the enclosed SE pursuant to 10 CFR 50.55a(a)(3)(i).
Sincerely, EJ Walter R. Butler, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/enclosure:
See next page
Dr. Robert C. Mecredy R.E.
Ginna Nuclear Power Plant CC:
Thomas A. Hoslak, Senior Resident Inspector R.E.
Ginna Plant U.S. Nuclear Regulatory Commission 1503 Lake Road
- Ontario, New York 14519 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Ms.
Donna Ross Division of Policy Analysis 5 Plannin9 New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Charlie Donaldson, Esq.
Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Nicholas S.
Reynolds Winston 5 Strawn 1400 L St.
N.W.
Washington, DC 20005-3502 Hs.
Thelma Wideman
- Director, Wayne County Emergency Management Office Wayne County Emergency Operations Center 7370 Route 31
- Lyons, New York 14489 Hs.
Mary Louise Heisenzahl Administrator, Monroe County Office of Emergency Preparedness ill West Fall
- Road, Room 11 Rochester, New York 14620