SBK-L-06006, Completion of License Condition 2.K Supplemental Information

Completion of License Condition 2.K Supplemental Information

ML060190542
Person / Time
Site:	Seabrook
Issue date:	01/11/2006
From:	St.Pierre G Florida Power & Light Energy Seabrook
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
SBK-L-06006, TAC MC8873
Download: ML060190542 (3)

Text

v FPL Energy Seabrook Station FPL Energy P.O. Box 300 Seabrook, NH 03874 Seabrook Station (603) 773-7000 JAN 1 1 MMQ Docket No. 50-443 SBK-L-06006 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Seabrook Station Facility Operating License NPF-86 Completion of License Condition 2.K Supplemental Information

References:

1. FPL Energy Seabrook, LLC letter (SBK-L-05226) to USNRC Document Control Desk, "Facility Operating License NPF-86, Completion of License Condition 2.K," dated November 7, 2005.

2. Memorandum from G. E. Miller, Project Manager to D. J. Roberts, Chief Plant Licensing Branch 1-2, "Seabrook Station Unit No. 1 Conference Call, Documentation of Discussion (TAC No MC8 873), dated December 22, 2005.

By letter dated November 7, 2005 (Reference 1), FPL Energy Seabrook, LLC (FPL Energy Seabrook) provided a revised safety analysis for the inadvertent actuation of the Emergency Core Cooling System at power event. The letter provided the information required by facility operating license NFP-86, license condition 2.K.

The following supplemental information was requested by the NRC during a telephone conference on December 21, 2005 and included in the documentation of discussion (Reference 2). The information supports the revised safety analysis for the inadvertent actuation of the Emergency Core Cooling System at power event.

• The revised analysis relies upon the Main Steam System atmospheric steam dump valves for maintaining Reactor Coolant System temperature (Tavg).

• As described in Seabrook Station Updated Final Safety Analysis Report (UFSAR), Sections 7.4.5, 7.4.6, and 10.3. the atmospheric steam dump valves are safety related and comply with the requirements for safety related systems, structures, and components.

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r U. S. Nuclear Regulatory Commission SBK-L-06006/Page 2

• A single failure of one atmospheric dump valve in RCS Loop 4 is assumed, thus, the revised analysis credits only three of the four atmospheric steam dump valves.

• The atmospheric dump valves will be available for mitigation of an inadvertent Emergency Core Cooling System actuation at power event.

Should you have any questions concerning this submittal, please contact Mr. Stephen T. Hale, Power Uprate Project Manager, at (603) 773-7561.

Very truly yours, FPL Energy Seabrook, LLC Gene St. Pierre Site Vice President cc: S. J. Collins, NRC Region I Administrator G. E. Miller, NRC Project Manager G. T. Dentel, NRC Resident Inspector Mr. Bruce Cheney, ENP, Director, Division of Emergency Services NH Department of Safety, Division of Emergency Services, Communications and Management Bureau of Emergency Management 33 Hazen Drive Concord, NH 03305

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U. S. Nuclear Regulatory Commission SBK-L-06006/Page 3 Oath and Affirmation 1, Gene St. Pierre, Site Vice President of FPL Energy Seabrook, LLC hereby affirm that the information and statements contained within this correspondence including the enclosure are based on facts and circumstances which are true and accurate to the best of my knowledge and belief.

Sworn and Subscribed Before me this_

(1 day of T4 , 2006 Gene St. Pierre Notary Public Site Vice President

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