ML071240449

Draft Request for Additional Information

ML071240449
Person / Time
Site:	Seabrook
Issue date:	05/03/2007
From:	Geoffrey Miller NRC/NRR/ADRO/DORL/LPLI-2
To:	Chernoff H NRC/NRR/ADRO/DORL/LPLI-2
Miller G, NRR/DORL, 415-2481
References
TAC MD2791
Download: ML071240449 (3)

Text

May 3, 2007MEMORANDUM TO:Harold K. Chernoff, ChiefPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationFROM:G. Edward Miller, Project Manager /ra/Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

SEABROOK STATION, UNIT NO. 1, DRAFT REQUEST FORADDITIONAL INFORMATION (TAC NO. MD2791)The attached draft request for information (RAI) was transmitted on May 3, 2007, to Mr. MichaelO'Keefe of FPL Energy Seabrook, LLC (FPLE). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee's amendment request for Seabrook Station, Unit No. 1, dated August 7, 2006. The proposed amendment requested to revise various sections of the Seabrook Station, Unit No. 1 Technical Specifications (TSs). This letterrelates specifically to the changes proposed for TS 3.3.9, "Remote Shutdown System," and TS 3.7.4, "Service Water System/Ultimate Heat Sink." Review of the draft RAI will allow FPLE to determine and agree upon a schedule for a response to the RAI. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request.Docket No. 50-443

Enclosure:

Draft RAI May 3, 2007MEMORANDUM TO:Harold K. Chernoff, ChiefPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationFROM:G. Edward Miller, Project Manager /ra/Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

SEABROOK STATION, UNIT NO. 1, DRAFT REQUEST FORADDITIONAL INFORMATION (TAC NO. MD2791)The attached draft request for information (RAI) was transmitted on May 3, 2007, to Mr. MichaelO'Keefe of FPL Energy Seabrook, LLC (FPLE). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee's amendment request for Seabrook Station, Unit No. 1, dated August 7, 2006. The proposed amendment requested to revise various sections of the Seabrook Station, Unit No. 1 Technical Specifications (TSs). This letterrelates specifically to the changes proposed for TS 3.3.9, "Remote Shutdown System," and TS 3.7.4, "Service Water System/Ultimate Heat Sink." Review of the draft RAI will allow FPLE to determine and agree upon a schedule for a response to the RAI. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request.Docket No. 50-443

Enclosure:

Draft RAIDISTRIBUTIONPUBLICRidsNrrDorlLpl1-2(HChernoffRDennigPDI-2 ReadingRidsNrrPMREnnisDNold RidsNrrDorlDprACCESSION NO.: ML071240449OFFICEPDI-2/PMNAMEGEMiller DATE5/3/07OFFICIAL RECORD COPY EnclosureDRAFT REQUEST FOR ADDITIONAL INFORMATIONREGARDING PROPOSED LICENSE AMENDMENTSEABROOK STATION, UNIT NO. 1DOCKET NO. 50-443By letter dated August 7, 2006, FPL Energy Seabrook, LLC submitted license amendmentrequest (LAR) 06-03. The LAR requested to revise various sections of the Seabrook Station, Unit No. 1 (Seabrook) Technical Specifications (TSs). This letter relates specifically to thechanges proposed for TS 3.3.9, "Remote Shutdown System," and TS 3.7.4, "Service Water System/Ultimate Heat Sink." The Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that the following additional information is needed to complete its review with respect to the aforementioned TS sections: The NRC staff has reviewed the information the licensee provided that supports the proposedamendment and would like to discuss the following issues to clarify the submittal.1)In your submittal, you stated that -"To enhance plant reliability, a design change (DCR 90-032) was implemented in 1991to replace the pneumatic actuator installed on these valves with a gear operated manual actuator. Additionally, the design change upgraded the downstream branch header remote/manual isolation valves MS-V-393 and MS-V-394 for use as the GDC 57 containment isolation valves. MS-V-393 and MS-V-394 replaced MS-V-127 and MS-V-128 as the GDC 57 containment isolation valves." (Excerpt from letter dated August 7, 2006) -. "The containment isolation boundary was relocated to the downstream valves,encompassing approximately 23 feet of piping, which was upgraded from ANS Safety Class 3 to ANS Safety Class 2 as part of the design change." (Excerpt from letter dated January 22, 2007)The NRC staff requests additional information about valves MS-V-393 and MS-V-394. Specifically, do these air operated valves satisfy the minimum design requirements of ANSI N271-1976 "Containment Isolation Provisions for Fluid Systems" as endorsed by NRC Regulatory Guide 1.141? If the valves do not satisfy the minimum design requirements, provide a description of the deviation from the guidelines and a justification for the deviation.