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| | number = ML060340097 | | | number = ML060340097 |
| | issue date = 02/16/2006 | | | issue date = 02/16/2006 |
| | title = R.E. Ginna Nuclear Power Plant - Review of Pressure and Temperature Limits Report (TAC No. MC7574) | | | title = R.E. Ginna Nuclear Power Plant - Review of Pressure and Temperature Limits Report |
| | author name = Milano P D | | | author name = Milano P D |
| | author affiliation = NRC/NRR/ADRO/DORL | | | author affiliation = NRC/NRR/ADRO/DORL |
Revision as of 22:55, 10 February 2019
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Text
February 16, 2006Mrs. Mary G. KorsnickVice 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 ANDTEMPERATURE LIMITS REPORT (TAC NO. MC7574)
Dear Mrs. Korsnick:
On July 1, 2005, R.E. Ginna Nuclear Power Plant, LLC (the licensee) submitted its revisedreactor coolant system (RCS) pressure and temperature limits report (PTLR) for the R.E. GinnaNuclear 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 periodand 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 staffreviewed 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 becauseit remains in compliance with the NRC-approved methodology of Westinghouse Topical ReportWCAP-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 generalprovisions 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 isacceptable for the continued operation of the Ginna RCS. Sincerely,/RA/Patrick D. Milano, Senior Project ManagerPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-244 cc: See next page February 16, 2006Mrs. Mary G. KorsnickVice 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 ANDTEMPERATURE LIMITS REPORT (TAC NO. MC7574)
Dear Mrs. Korsnick:
On July 1, 2005, R.E. Ginna Nuclear Power Plant, LLC (the licensee) submitted its revisedreactor coolant system (RCS) pressure and temperature limits report (PTLR) for the R.E. GinnaNuclear 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 periodand 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 staffreviewed 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 becauseit remains in compliance with the NRC-approved methodology of Westinghouse Topical ReportWCAP-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 generalprovisions 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 isacceptable for the continued operation of the Ginna RCS. Sincerely,/RA/Patrick D. Milano, Senior Project ManagerPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-244 cc: See next page Accession Number: ML060340097OFFICELPLI-1\PMLPLI-1\LACVIB\BCLPLI-1\BCNAMEPMilano:tswSLittleMMitchellRLauferDATE02/15/0602/15/0602/01/0602/16/06Official Record Copy DISTRIBUTION: for letter to M. Korsnick datedPUBLIC LPLI-1 Reading File R. LauferRidsNrrDorlLplI-1 M. MitchellRidsNrrDciCvib P. MilanoRidsNrrPMPMilano S. LittleRidsNrrLASLittle C. Sydnor J. Trapp, R-IRidsRgn1MailCenterOGCRidsOgcRp ACRSRidsAcrsAcnwMailCenter B. Singal, DORL DPR R.E. Ginna Nuclear Power Plant cc:
Mr. Michael J. WallacePresident R.E. Ginna Nuclear Power Plant, LLC c/o Constellation Energy 750 East Pratt Street Baltimore, MD 21202Mr. John M. HeffleySenior Vice President and Chief Nuclear Officer Constellation Generation Group 1997 Annapolis Exchange Parkway Suite 500 Annapolis, MD 21401Kenneth Kolaczyk, Sr. Resident InspectorR.E. Ginna Nuclear Power Plant U.S. Nuclear Regulatory Commission 1503 Lake Road Ontario, NY 14519Regional Administrator, Region IU.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406Mr. Peter R. Smith, PresidentNew York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399Mr. Carey W. Fleming, EsquireSenior Counsel - Nuclear Generation Constellation Generation Group, LLC 750 East Pratt Street, 17th Floor Baltimore, MD 21202Mr. Charles Donaldson, EsquireAssistant Attorney General New York Department of Law 120 Broadway New York, NY 10271Ms. Thelma Wideman, DirectorWayne County Emergency Management Office Wayne County Emergency Operations Center 7336 Route 31 Lyons, NY 14489Ms. Mary Louise MeisenzahlAdministrator, Monroe County Office of Emergency Preparedness 1190 Scottsville Road, Suite 200Rochester, NY 14624Mr. Paul EddyNew York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223