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Category:Letter
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 29, 2011 Vice President, Operations Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 10393
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - CLOSEOUT OF GENERIC LETTER 2008-01 "MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS" (TAC NO. MD7828)
Dear Sir or Madam:
On January 11,2008, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML072910759). The stated purpose of GL 2008-01 was (a) to request addressees to submit information to demonstrate that the subject systems are in compliance with the current licensing and design bases and applicable regulatory requirements, and that suitable design, operational, and testing control measures are in place for maintaining this compliance; and, (b) to collect the requested information to determine if additional regulatory action is required.
GL 2008-01 requested that licensees provide the following information within 9 months of the date of the GL:
(a) A description of the results of evaluations that were performed pursuant to requested actions specified in the GL. This description should provide sufficient information to demonstrate that you are or will be in compliance with the quality assurance criteria in Sections III, V, XI, XVI, and XVII of Appendix B to 10 CFR Part 50 and the licensing basis and operating license as those requirements apply to the subject systems; (b) A description of all corrective actions, including plant, programmatic, procedure, and licensing basis modifications that you determined were necessary to assure compliance with these regUlations; and, (c) A statement regarding which corrective actions were completed, the schedule for completing the remaining corrective actions, and the basis for that schedule.
In your letters dated October 14, 2008, March 31,2009, and January 18, 2010 (ADAMS Accession Nos. ML082900037, ML090960469, and ML100220458, respectively), you provided information in response to the GL. Specifically, in the letter dated January 18, 2010, your responses provided the following additional information:
- RAI 1 addressed corrective actions that have been completed and corrective actions that are planned. The licensee changed operating procedures to include additional fill and
V. P. Operations -2 vent guidance for the Residual Heat Removal (RHR) and Containment Spray (CS) systems. Some surveillance tests were modified to require venting of the keep-full level switches and to require a condition report in the event that air is observed while venting.
The NRC staff finds that this acceptably addresses the question.
- RAI 2 addressed surveillance intervals. The licensee confirmed that surveillances are done on a monthly basis. The NRC staff finds that this acceptably addresses the question.
The NRC staff has reviewed the submitted information and finds that for James A. FitzPatrick Nuclear Power Plant, the licensee has acceptably demonstrated "that gas accumulation is maintained less than the amount that challenges operability of these systems, and that appropriate action is taken when conditions adverse to quality are identified" as stated in GL 2008-01. Consequently, your GL response is considered closed and no further information or action is requested of you with the exception of any commitments you have made with respect to the GL responses. Notwithstanding, the NRC's Region I staff may decide to perform (and would contact you to schedule) an inspection using Temporary Instruction (TI) 2515/177, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems (NRC Generic Letter 2008-01)" (ADAMS Accession No. ML082950666). The TI 2515/177 is confirmatory in nature in that it directs NRC inspectors to assess applicable information that is available at the plant, to selectively verify that the licensee has implemented or is in the process of acceptably implementing the commitments, modifications, and programmatically controlled actions described in the licensee's response to GL 2008-01, and to confirm the NRC staff conclusion on the basis of the plant-specific information that subject systems operability is reasonably ensured or, conversely, to identify items where additional follow-up is necessary to confirm the NRC staff conclusion.
If you have any questions regarding this letter, please feel free to contact me at (301) 415-3308.
Sincerely, Bhalchandra K. Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-333 cc: Distribution via Listserv
ML082950666). The TI 2515/177 is confirmatory in nature in that it directs NRC inspectors to assess applicable information that is available at the plant, to selectively verify that the licensee has implemented or is in the process of acceptably implementing the commitments, modifications, and programmatically controlled actions described in the licensee's response to GL 2008-01, and to confirm the NRC staff conclusion on the basis of the plant-specific information that subject systems operability is reasonably ensured or, conversely, to identify items where additional follow-up is necessary to confirm the NRC staff conclusion.
If you have any questions regarding this letter, please feel free to contact me at (301) 415-3308.
Sincerely,
/raJ Bhalchandra K. Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-333 cc: Distribution via Ustserv DISTRIBUTION:
PUBLIC RidsNrrDorlLPL1-1 RidsNrrPMFitzPatrick RidsOGCMailCenter LPL1-1 Reading File RidsNrrDssSrxb RidsNrrDprPgcb RidsNrrLASLittle RidsAcrsAcnwMailCenter DORL DPR MGray, RI S.Miranda, NRRISRXB J.Gall, NRRISRXB T. Nakanishi, NRRISRXB W. Lyon, NRRISRXB D Beaulieu, NRR/PGCB ADAMS ACCESSION NUMBER: ML100740336 (* No SUbstantial chan e in SE Input Memo FICE LPL1-1/PM LPL1-1/LA RXB/BC
- LPL1-1/BC LPL 1-1/PM ME BVaidya SUttle BVaidya TE 3/28/11 128111 3/29/11