ML17264A412

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Forwards SE Concerning Pressurized Thermal Shock Evaluation for Plant.Plant Reactor Vessel Projected to Be Below PTS Screening Criteria at Expiration of License
ML17264A412
Person / Time
Site: Ginna Constellation icon.png
Issue date: 03/22/1996
From: Andrea Johnson
NRC (Affiliation Not Assigned)
To: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
Shared Package
ML17264A413 List:
References
TAC-M93827, NUDOCS 9603250330
Download: ML17264A412 (5)


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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001

~rch 22, 1996 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas 8 Electric Corporation 89 East Avenue Rochester, NY 14649

SUBJECT:

R.E.

GINNA NUCLEAR POMER PLANT PRESSURIZED THERMAL SHOCK EVALUATION (TAC NO. M93827)

Dear Dr. Mecredy:

By letter dated October 11,

1995, you submitted an updated pressurized thermal shock (PTS) evaluation for the R.E. Ginna Nuclear Power Plant (Ginna).

The NRC staff has completed its review of your submittal.

In the enclosed safety evaluation (SE), the staff concludes that the Ginna reactor vessel is projected to be below the PTS screening criteria at the expiration of its license.

Since this conclusion is dependent upon the available chemistry and surveillance data, it is subject to change when new data become available.

Additionally, the Ginna reactor coolant system pressure and temperature limits report, as referenced in Ginna Technical Specification 5.6.6, should be updated to include the material properties discussed in the enclosed SE.

The update should cover the use of the ratioing procedure in Regulatory Guide 1.99, Revision 2.

Also with regard to your specific methodology for determining low-temperature overpressure protection setpoints and its application of American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code)

Case N-514, you should request an exemption from 10 CFR 50.55a to use the ASME Code Addenda that incorporates Code Case N-514,Section XI, Division 1, "Low Temperature Overpressure Protection,"

approved February 12, 1992.

Sincerely, Docket No. 50-244

Enclosure:

As stated cc:

See next page Alle R. Johns

, Project Manager Proje

'rate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation 9603250330 960322 PDR ADQCK 05000244'I P

PDR

Dr. Robert C. Mecredy R.E.

Ginna Nuclear Power Plant CC:

Peter D. Drysdale, Senior 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 2 Rockefeller Plaza
Albany, NY 12223-1253 Charlie Donaldson, Esq.

Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Nicholas S.

Reynolds Winston

& Strawn 1400 L St.

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 Fall
Road, Room 11 Rochester, NY 14620

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