ML11125A010

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Closeout of Generic Letter 2008-01 Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems
ML11125A010
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 06/28/2011
From: Orf T
Plant Licensing Branch II
To: Nazar M
Florida Power & Light Co
Orf T
References
GL-08-001, TAC MD7872, TAC MD7873
Download: ML11125A010 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D,C. 20555-0001 June 28, 2011 Mr. Mano Nazar Executive Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420

SUBJECT:

ST. LUCIE, UNIT NOS. 1 AND 2 - CLOSEOUT OF GENERIC LETTER 2008-01 "MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS" (TAC NOS. MD7872 AND MD 7873)

Dear Mr. Nazar:

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 [Title 10 of the Code of Federal Regulations] 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 letters dated May 12,2008 (ADAMS Accession No. ML081370603), October 14, 2008 (ADAMS Accession No. ML082900487), February 9,2009 (ADAMS Accession No. ML090430192), June 17, 2009 (ADAMS Accession No. ML091750097), and September 11, 2009 (ADAMS Accession No. ML092580089), Florida Power & Light Company (the licensee)

M. Nazar

-2 provided information in response to the GL The licensee's "L-2008-070, Three Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and [[system" contains a listed "[" character as part of the property label and has therefore been classified as invalid. Systems.|May 12, 2008, letter]] stated that much of the evaluations would be completed within the 9;'month response time period. Because some of the evaluations required system walkdowns, portions of the subject piping that is inaccessible during normal operations was to be reviewed and a response submitted within 90 days following the end of the fall 2008 refueling outage for Unit 1 and within 90 days of the end of the spring 2009 refueling outage for Unit 2.

The licensee's "L-2008-221, Nine-Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and [[system" contains a listed "[" character as part of the property label and has therefore been classified as invalid. Systems.|October 14, 2008, letter]] provided, as requested by the GL, the results of evaluations performed to date to demonstrate compliance with 10 CFR Part 50, Appendix B.

Also provided, were the licensee's description of corrective actions determined necessary to assure compliance. Finally, this letter provided the schedule to complete corrective actions and the schedule to complete remaining evaluations. In the remainder of the responses, the licensee provided the results of the remaining evaluations. The NRC staff has reviewed the submitted information and has concluded that the licensee has acceptably addressed each request.

Consequently, the licensee's GL response is considered closed and no further information or action is requested from the licensee-the remaining commitments associated with the GL responses will be reviewed as a separate activity. The NRC's Region II staff performed 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) and found no plant-specific issues. 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 the subject systems' operability is reasonably ensured.

If you have any questions regarding this letter, please feel free to contact Tracy Orf at (301) 415-2788 or at tracy.orf@nrc.gov.

Tracy J Orf, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389 cc: Distribution via Listserv

ML082950666) and found no plant-specifiq issues.

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 feel free to contact Tracy Orf at (301) 415-2788 or at tracy.orf@nrc.gov.

Sincerely, IRA!

Tracy J Orf, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389 cc: Distribution via Listserv Distribution:

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