ML17264A306
| ML17264A306 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/26/1995 |
| From: | Marsh L NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TAC-M92320, NUDOCS 9512290222 | |
| Download: ML17264A306 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205554001 December 26, 1995 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric. Corporation 89 East Avenue Rochester, NY 14649
Dear Dr. Mecredy:
SUBJECT:
REFERENCES:
R.
E.
GINNA - ACCEPTANCE FOR REFERENCING OF PRESSURE TEMPERATURE LIMITS REPORT (TAC ¹ H92320) l.
Amendment No. 48 to Facility Operating License No.
DPR-18, R.
E. Ginna Nuclear Power Plant, March 6, 1992.
2.
Letter from C. I. Grimes, NRC, to R. A. Newton, Westinghouse Electric Corporation, "Acceptance for Referencing of Topical Report WCAP-14040, Revision 1,
'Methodology Used to Develop Cold Overpressure Mitigating.
System Setpoints and RCS Heatup and Cooldown Limit Curves,.'"
October 16, 1995.
3.
Letter from R.
C. Hect edy, Rochester Gas and Electric Corporation (RG&E), to Document Control Desk, NRC, Attention A. R. Johnson, "Technical Specifications Improvement
- Program, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)," December 8, 1995.
As part of their application to convert the Ginna technical specifications to the improved standard technical specifications, Rochester Gas and Electric Corporation (RG&E) proposed to reference WCAP-14040 as the methodology they would use to calculate the reactor coolant system pressure and temperature (P/T) and the low-temperature overpressure protection (LTOP) system limits.
These limits would then be documented in a pressure temperature limits report (PTLR).
- However, RG&E determined that they need to operate in accordance with the existing limits, previously approved by the staff (Reference 1).
For this
- reason, they. have not generated plant-specific P/T and LTOP limits using the WCAP-14040 methodology.
Therefore, the staff cannot complete its review of the application of the methodology for Ginna.
As a result, the curves, setpoints,
- values, and parameters in the improved technical specifications proposed PTLR are those the staff had previously reviewed and approved.
The staff acceptance of the proposed PTLR, Reference 3,
applies only to the format of the report.
Contacts:
Haggalean W. Weston, (301) 415-3151 John C.,Tsao, (301) 415-2702 95i2290222 9'5i226 PDR ADOCK 05000244 P
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Dr. Robert C. Hecredy December 26, f995 The methodology in WCAP-14040 along with supplements provided by RG&E would be used to calculate, future changes to the P/T and LTOP limits.
When RG&E generates new P/T and LTOP system limits in accordance with this methodology and submits them to the staff, the staff will review and approve the new limits to ensure that these limits are acceptable based on the approved methodology.
At that time, RG&E will be required to revise the technical specifications Administrative Controls section to reference the staff approved methodology.
Sincerely, ORIGINAL SIGNED BY G.
EDISON FOR:
Docket No. 50-244 Ledyard B. Harsh, Director Project Directorate, I-1 Division of Reactor Projects Office of Nuclear Reactor Regulation DISTRIBUTION:
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Dr. Robert C. Mecredy The methodology in WCAP-14040 along with supplements provided by RG&E would be used to calculate future changes to the P/T and LTOP system limits.
When RGSE generates new P/T and LTOP system limits in accordance with this methodology and submits them to the staff, the staff will review and approve the new limits to ensure that these limits are acceptable based on the approved methodology.
At that time, RG8E will be required to revise the technical specifications Administrative Controls section to reference the staff approved methodology.
Docket No. 50-244 Ledyard B. Marsh, Director Project Directorate I-1 Division of Reactor Projects Office of Nuclear Reactor Regulation