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, 2007 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: 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 FOR ADDITIONAL INFORMATION (TAC NO. MD2791)

The attached draft request for information (RAI) was transmitted on May 3, 2007, to Mr. Michael OKeefe of FPL Energy Seabrook, LLC (FPLE). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensees 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 letter relates 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, 2007 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: 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 FOR ADDITIONAL INFORMATION (TAC NO. MD2791)

The attached draft request for information (RAI) was transmitted on May 3, 2007, to Mr. Michael OKeefe of FPL Energy Seabrook, LLC (FPLE). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensees 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 letter relates 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 DISTRIBUTION PUBLIC RidsNrrDorlLpl1-2(HChernoff RDennig PDI-2 Reading RidsNrrPMREnnis DNold RidsNrrDorlDpr ACCESSION NO.: ML071240449 OFFICE PDI-2/PM NAME GEMiller DATE 5/3/07 OFFICIAL RECORD COPY

DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT SEABROOK STATION, UNIT NO. 1 DOCKET NO. 50-443 By letter dated August 7, 2006, FPL Energy Seabrook, LLC submitted license amendment request (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 the changes 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 proposed amendment 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 1991 to 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.

Enclosure