ML111250165

Closeout of Generic Letter 2008-01 Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems

ML111250165
Person / Time
Site:	Davis Besse
Issue date:	06/27/2011
From:	Michael Mahoney Plant Licensing Branch III
To:	Allen B S FirstEnergy Nuclear Operating Co
mahoney, m NRR/DORL/LPLIII-2 415-3867
References
TAC MD7819
Download: ML111250165 (3)

Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 June 27, 2011 Mr. Barry S. Allen Site Vice President FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station Mail Stop A-DB-3080 5501 North State Route 2 Oak Harbor, OH 43449-9760 DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 -CLOSEOUT OF GENERIC LETTER 2008-01 "MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS" (TAC NO. MD7819)

Dear Mr. Allen:

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 was requested that licensees provide the following information within 9 months of the date of the GL: 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 Part 50 of Title 10 of the Code of Federal Regulations and the licensing basis and operating license as those requirements apply to the subject systems; 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, 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 and October 26,2009 (ADAMS Accession Nos. ML082900577 and ML093020224, respectively), FirstEnergy Nuclear Operating Company (FENOC, the licensee) provided information in response to GL 2008-01 for the Davis-Besse B Allen Nuclear Power Station, Unit 1 (DBNPS). The NRC staff has reviewed the submitted information and has concluded that the licensee for DBNPS has acceptably demonstrated that for DBNPS, 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 DBNPS 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 DBNPS. 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) 25151177, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems (NRC Generic Letter 2008-01)" (ADAMS Accession No. ML082950666).

TI2515/177 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 to contact me at (301) 415-3867 or michael.mahoney@nrc.gov. WlJ Michael Mahoney, Pr ect Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346 cc: Distribution via Listserv B.Allen Nuclear Power Station, Unit 1 (DBNPS). The NRC staff has reviewed the submitted information and has concluded that the licensee for DBNPS has acceptably demonstrated that for DBNPS, 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 DBNPS 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 DBNPS. 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).

TI2515/177 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 to 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. 50-346 cc: Distribution via Listserv DISTRIBUTION:

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