ML060340097: Difference between revisions
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| number = ML060340097 | | number = ML060340097 | ||
| issue date = 02/16/2006 | | issue date = 02/16/2006 | ||
| title = | | title = Review of Pressure and Temperature Limits Report | ||
| author name = Milano P | | author name = Milano P | ||
| author affiliation = NRC/NRR/ADRO/DORL | | author affiliation = NRC/NRR/ADRO/DORL | ||
| addressee name = Korsnick M | | addressee name = Korsnick M | ||
| addressee affiliation = R. E. Ginna Nuclear Power Plant, LLC | | addressee affiliation = R. E. Ginna Nuclear Power Plant, LLC | ||
| docket = 05000244 | | docket = 05000244 | ||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:February 16, | {{#Wiki_filter: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:== | ==SUBJECT:== | ||
R.E. GINNA NUCLEAR POWER PLANT - REVIEW OF PRESSURE | R.E. GINNA NUCLEAR POWER PLANT - REVIEW OF PRESSURE AND TEMPERATURE LIMITS REPORT (TAC NO. MC7574) | ||
==Dear Mrs. Korsnick:== | ==Dear Mrs. Korsnick:== | ||
On July 1, 2005, R.E. Ginna Nuclear Power Plant, LLC (the licensee) submitted its | 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:== | ==SUBJECT:== | ||
R.E. GINNA NUCLEAR POWER PLANT - REVIEW OF PRESSURE | R.E. GINNA NUCLEAR POWER PLANT - REVIEW OF PRESSURE AND TEMPERATURE LIMITS REPORT (TAC NO. MC7574) | ||
==Dear Mrs. Korsnick:== | ==Dear Mrs. Korsnick:== | ||
On July 1, 2005, R.E. Ginna Nuclear Power Plant, LLC (the licensee) submitted its | 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. | ||
Mr. Michael J. | 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 Ms. Thelma Wideman, Director President Wayne County Emergency Management R.E. Ginna Nuclear Power Plant, LLC Office c/o Constellation Energy Wayne County Emergency Operations 750 East Pratt Street Center Baltimore, MD 21202 7336 Route 31 Lyons, NY 14489 Mr. John M. Heffley Senior Vice President and Ms. Mary Louise Meisenzahl Chief Nuclear Officer Administrator, Monroe County Constellation Generation Group Office of Emergency Preparedness 1997 Annapolis Exchange Parkway 1190 Scottsville Road, Suite 200 Suite 500 Rochester, NY 14624 Annapolis, MD 21401 Mr. Paul Eddy Kenneth Kolaczyk, Sr. Resident Inspector New York State Department of R.E. Ginna Nuclear Power Plant Public Service U.S. Nuclear Regulatory Commission 3 Empire State Plaza, 10th Floor 1503 Lake Road Albany, NY 12223 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}} | |||
Latest revision as of 22:39, 23 November 2019
| 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 Ms. Thelma Wideman, Director President Wayne County Emergency Management R.E. Ginna Nuclear Power Plant, LLC Office c/o Constellation Energy Wayne County Emergency Operations 750 East Pratt Street Center Baltimore, MD 21202 7336 Route 31 Lyons, NY 14489 Mr. John M. Heffley Senior Vice President and Ms. Mary Louise Meisenzahl Chief Nuclear Officer Administrator, Monroe County Constellation Generation Group Office of Emergency Preparedness 1997 Annapolis Exchange Parkway 1190 Scottsville Road, Suite 200 Suite 500 Rochester, NY 14624 Annapolis, MD 21401 Mr. Paul Eddy Kenneth Kolaczyk, Sr. Resident Inspector New York State Department of R.E. Ginna Nuclear Power Plant Public Service U.S. Nuclear Regulatory Commission 3 Empire State Plaza, 10th Floor 1503 Lake Road Albany, NY 12223 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