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MONTHYEARL-08-133, Three Month Response to NRC GL-08-001, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.2008-04-11011 April 2008 Three Month Response to NRC GL-08-001, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems. Project stage: Request ML0815105142008-09-16016 September 2008 Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems, Proposed Alternative Course of Action Project stage: Other L-08-315, Nine Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems2008-10-14014 October 2008 Nine Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems Project stage: Other L-08-383, Supplemental Information Regarding NRC Generic Letter 2008-012008-12-19019 December 2008 Supplemental Information Regarding NRC Generic Letter 2008-01 Project stage: Supplement L-09-158, Ninety Day Post-Outage Supplemental Response to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.2009-08-10010 August 2009 Ninety Day Post-Outage Supplemental Response to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems. Project stage: Supplement ML0933403892009-12-0404 December 2009 Request for Additional Information Related to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems Project stage: RAI L-10-011, Response to NRC Request for Additional Information Regarding Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.:2010-01-27027 January 2010 Response to NRC Request for Additional Information Regarding Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.: Project stage: Response to RAI ML1116104342011-06-27027 June 2011 Closeout of Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems. Project stage: Other 2008-09-16
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 Jtme 27, 2011 Mr. Mark B. Bezilla Site Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant Mail Stop A-PY -A290 P.O. Box 97,10 Center Road Perry,OH 44081-0097
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT 1 - CLOSEOUT OF GENERIC LETTER 2008-01 "MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS" (TAC NO. MD7862)
Dear Mr. Bezilla:
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.
In GL 2008-01 it 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. 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.
By letters dated October 14,2008, December 19, 2008, August 10, 2009, and January 27,2010 (ADAMS Accession Nos. ML082980365, ML090430426, ML092320128, and ML100340587, respectively), FirstEnergy Nuclear Operating Company (FENOC, the licensee) provided information in response to GL 2008-01 for the Perry Nuclear Power Plant, Unit 1 (PNPP). The
M.8ezilla - 2 NRC staff has reviewed the submitted information and has concluded that the licensee for PNPP has acceptably demonstrated that for PNPP, the "subject systems are in compliance with the current licensing and design bases and applicable regulatory requirements; and that suitable design, operation, and testing measures are in place for maintaining this compliance,>> as stated in GL 2008-01.
Consequently, FENOC's GL 2008-01 response for PNPP is considered closed and no further information or action is requested with the exception of any commitments FENOC has made with respect to GL 2008-01 responses for PNPP. The NRC staff expects that the associated commitments will be entered into the licensee's tracking system, and controlled consistent with the Nuclear Energy Institute (NEI) document NEI 99-04, "Guidelines for Managing NRC Commitment Changes."
In addition, the NRC's Region III 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). TI 2515/177 is confirmatory in nature in that it directs NRC inspectors 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 the plant-specific information supports a conclusion that subject systems operability is reasonably ensured.
If you have any questions regarding this letter, please contact me at (301 )-415-3867 or michael. mahoney@nrc.gov.
ichael Ma ney, Project Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440 cc: Distribution via Listserv
M. Bezilla - 2 NRC staff has reviewed the submitted information and has concluded that the licensee for PNPP has acceptably demonstrated that for PNPP, the "subject systems are in compliance with the current licensing and design bases and applicable regulatory requirements; and that suitable design, operation, and testing measures are in place for maintaining this compliance," as stated in GL 2008-01.
Consequently, FENOC's GL 2008-01 response for PNPP is considered closed and no further information or action is requested with the exception of any commitments FENOC has made with respect to GL 2008-01 responses for PNPP. The NRC staff expects that the associated commitments will be entered into the licensee's tracking system, and controlled consistent with the Nuclear Energy Institute (NEI) document NEI 99-04, "Guidelines for Managing NRC Commitment Changes."
In addition, the NRC's Region III 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). T12515/177 is confirmatory in nature in that it directs NRC inspectors 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 the plant-specific information supports a conclusion that subject systems operability is reasonably ensured.
If you have any questions regarding this letter, please contact me at (301 )-415-3867 or michael,mahoney@nrc.gov.
Sincerely, IRA!
Michael Mahoney, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440 cc: Distribution via Listserv DISTRIBUTION:
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