ML111661914

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Closeout of Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems
ML111661914
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 06/27/2011
From: Billoch-Colon A
Plant Licensing Branch III
To: Pacilio M
Exelon Nuclear
Billoch-Colon A, NRR/DORL, 301-415-3302
References
TAC MD7839, TAC MD7840, GL-08-001
Download: ML111661914 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 27, 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

LASALLE COUNTY STATION, UNITS 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. MD7839 AND MD7840)

Dear Mr. Pacilio:

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)

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 April 11,2008, October 14, 2008, November 3,2009, and May 6,2010 (ADAMS Accession Nos. ML081020758, ML082880706, ML093160345, and ML101300311, respectively), Exelon Generation Company, LLC (Exelon, the licensee), provided information in

M.Pacilio

- 2 response to GL 2008-01 for the LaSalle County Station, Units 1 and 2 (LSCS). The NRC staff has concluded that the licensee for LSCS has acceptably demonstrated that for LSCS 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, Exelon's GL 2008-01 response for LSCS is considered closed and no further information or action is requested with the exception of any commitments Exelon has made with respect to the GL 2008-01 responses for LSCS. 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 contact me at (301 )-415-3302 or araceli.billoch@nrc.gov.

Sincerely, Araceli T. Billoch Colon, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374 cc: Distribution via Listserv

M. Pacilio

-2 response to GL 2008-01 for the LaSalle County Station, Units 1 and 2 (LSCS). The NRC staff has concluded that the licensee for LSCS has acceptably demonstrated that for LSCS 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, Exelon's GL 2008-01 response for LSCS is considered closed and no further information or action is requested with the exception of any commitments Exelon has made with respect to the GL 2008-01 responses for LSCS. 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 contact me at (301 )-415-3302 or araceILbilloch@nrc.gov.

Sincerely, IRA!

Araceli T. Billoch Colon, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374 cc: Distribution via Listserv DISTRIBUTION:

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06/27111 OFFICIAL RECORD COpy