ML060340097
| ML060340097 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/16/2006 |
| From: | Milano P Plant Licensing Branch III-2 |
| To: | Korsnick M Ginna |
| tsw1 | |
| References | |
| TAC MC7574 | |
| Download: ML060340097 (4) | |
Text
February 16, 2006 Mrs. Mary G. Korsnick Vice President R.E. Ginna Nuclear Power Plant R.E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519
SUBJECT:
R.E. GINNA NUCLEAR POWER PLANT - REVIEW OF PRESSURE AND TEMPERATURE LIMITS REPORT (TAC NO. MC7574)
Dear Mrs. Korsnick:
On July 1, 2005, R.E. Ginna Nuclear Power Plant, LLC (the licensee) submitted its revised reactor coolant system (RCS) pressure and temperature limits report (PTLR) for the R.E. Ginna Nuclear Power Plant (Ginna). The revised PTLR was submitted in accordance with the requirements of Ginna Technical Specification (TS) Section 5.6.6, Reactor Coolant System (RCS) Pressure-Temperature Limits Report, which specifies that the PTLR be provided to the Nuclear regulatory Commission (NRC) upon issuance for each reactor vessel fluence period and for revisions thereto. Since the RCS pressure and temperature limits for Ginna are documented in the licensee-controlled PTLR, the revised PTLR was submitted to the NRC for information only and does not require approval in a formal safety evaluation. The NRC staff reviewed the PTLR to ensure that the approved methodology was used to modify the PTLR.
The NRC staff finds that the revised PTLR meets the requirements of Ginna TS 5.6.6 because it remains in compliance with the NRC-approved methodology of Westinghouse Topical Report WCAP-14040-NP-A, Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Curves, and associated documents for developing PTLRs, as specified in TS 5.6.6. Furthermore, the revised PTLR is consistent with the general provisions of Generic Letter (GL) 96-03, Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits, and the associated technical criteria for PTLRs specified in Attachment 1 to GL 96-03.
Based on the above considerations, the NRC staff concludes that the revised PTLR is acceptable for the continued operation of the Ginna RCS.
Sincerely,
/RA/
Patrick D. Milano, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244 cc: See next page
February 16, 2006 Mrs. Mary G. Korsnick Vice President R.E. Ginna Nuclear Power Plant R.E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519
SUBJECT:
R.E. GINNA NUCLEAR POWER PLANT - REVIEW OF PRESSURE AND TEMPERATURE LIMITS REPORT (TAC NO. MC7574)
Dear Mrs. Korsnick:
On July 1, 2005, R.E. Ginna Nuclear Power Plant, LLC (the licensee) submitted its revised reactor coolant system (RCS) pressure and temperature limits report (PTLR) for the R.E. Ginna Nuclear Power Plant (Ginna). The revised PTLR was submitted in accordance with the requirements of Ginna Technical Specification (TS) Section 5.6.6, Reactor Coolant System (RCS) Pressure-Temperature Limits Report, which specifies that the PTLR be provided to the Nuclear regulatory Commission (NRC) upon issuance for each reactor vessel fluence period and for revisions thereto. Since the RCS pressure and temperature limits for Ginna are documented in the licensee-controlled PTLR, the revised PTLR was submitted to the NRC for information only and does not require approval in a formal safety evaluation. The NRC staff reviewed the PTLR to ensure that the approved methodology was used to modify the PTLR.
The NRC staff finds that the revised PTLR meets the requirements of Ginna TS 5.6.6 because it remains in compliance with the NRC-approved methodology of Westinghouse Topical Report WCAP-14040-NP-A, Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Curves, and associated documents for developing PTLRs, as specified in TS 5.6.6. Furthermore, the revised PTLR is consistent with the general provisions of Generic Letter (GL) 96-03, Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits, and the associated technical criteria for PTLRs specified in Attachment 1 to GL 96-03.
Based on the above considerations, the NRC staff concludes that the revised PTLR is acceptable for the continued operation of the Ginna RCS.
Sincerely,
/RA/
Patrick D. Milano, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244 cc: See next page Accession Number: ML060340097 OFFICE LPLI-1\\PM LPLI-1\\LA CVIB\\BC LPLI-1\\BC NAME PMilano:tsw SLittle MMitchell RLaufer DATE 02/15/06 02/15/06 02/01/06 02/16/06 Official Record Copy
DISTRIBUTION: for letter to M. Korsnick dated PUBLIC LPLI-1 Reading File R. Laufer RidsNrrDorlLplI-1 M. Mitchell RidsNrrDciCvib P. Milano RidsNrrPMPMilano S. Little RidsNrrLASLittle C. Sydnor J. Trapp, R-I RidsRgn1MailCenter OGC RidsOgcRp ACRS RidsAcrsAcnwMailCenter B. Singal, DORL DPR
R.E. Ginna Nuclear Power Plant cc:
Mr. Michael J. Wallace President R.E. Ginna Nuclear Power Plant, LLC c/o Constellation Energy 750 East Pratt Street Baltimore, MD 21202 Mr. John M. Heffley Senior Vice President and Chief Nuclear Officer Constellation Generation Group 1997 Annapolis Exchange Parkway Suite 500 Annapolis, MD 21401 Kenneth Kolaczyk, Sr. Resident Inspector R.E. Ginna Nuclear Power 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. Peter R. Smith, President New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Carey W. Fleming, Esquire Senior Counsel - Nuclear Generation Constellation Generation Group, LLC 750 East Pratt Street, 17th Floor Baltimore, MD 21202 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 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 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223