ML093511024

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Closeout of GL 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems,
ML093511024
Person / Time
Site: Nine Mile Point  Constellation icon.png
Issue date: 01/11/2010
From: Richard Guzman
Plant Licensing Branch 1
To: Belcher S
Nine Mile Point
Guzman R, NRR/DORL, 415-1030
References
GL-08-001, TAC MD7848, TAC MD7849
Download: ML093511024 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 11, 2010 Mr. Samuel L. Belcher Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093 SUB~IECT: NINE MILE POINT NUCLEAR STATION, UNIT NOS. 1 AND 2 - CLOSEOUT OF GENERIC LETrER 2008-01, "MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS" (TAC NOS. MD7848 AND MD7849)

Dear Mr. Belcher:

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, July 6,2009, September 29, 2009, and December 14, 2009 (ADAMS Accession Nos. ML082900036, ML091950416, ML092790558, and ML093631558, respectively), you provided information in response to the GL. The NRC staff has reviewed the submitted information and has concluded that for Nine Mile Point Nuclear Station, Unit Nos. 1 and 2, your response to the GL is acceptable. Consequently, your GL response is considered closed and no further information or action is requested of you.

S. Belcher -2 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 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 matter, I may be reached at 301-415-1030.

Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-220 and 50-410 cc: Distribution via Listserv

ML082950666). The 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 matter, I may be reached at 301-415-1030.

Sincerely, IRA!

Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-220 and 50-410 cc: Distribution via Listserv DISTRIBUTION:

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