ML060620015

Facsimile Transmission, Draft Request for Additional Information (RAI) to Be Discussed in an Upcoming Conference Call

ML060620015
Person / Time
Site:	Seabrook
Issue date:	03/03/2006
From:	Geoffrey Miller Plant Licensing Branch III-2
To:	Darrell Roberts Plant Licensing Branch III-2
Miller G, NRR/DLPM, 415-2481
References
TAC MC8873
Download: ML060620015 (3)

Text

March 3, 2006 MEMORANDUM TO: Darrell J. Roberts, 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 - FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (RAI) TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MC8873)

The enclosed draft RAI was transmitted by facsimile on March 3, 2006, to Mr. Mike OKeefe, FPL Energy Seabrook, LLC (FPLE). This draft RAI was transmitted to facilitate the technical review being conducted by the staff and to support a conference call with FPLE in order to clarify certain items in the licensees submittal. The draft RAI is related to FPLEs submittal dated November 7, 2005, regarding a report submitted for Nuclear Regulatory Commission (NRC) review to resolve license condition 2.K for the Seabrook Station, Unit No. 1.

Review of the draft RAI would allow FPLE to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.

Docket No. 50-443

Enclosure:

Draft RAI

March 3, 2006 MEMORANDUM TO: Darrell J. Roberts, 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 - FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (RAI) TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MC8873)

The enclosed draft RAI was transmitted by facsimile on March 3, 2006, to Mr. Mike OKeefe, FPL Energy Seabrook, LLC (FPLE). This draft RAI was transmitted to facilitate the technical review being conducted by the staff and to support a conference call with FPLE in order to clarify certain items in the licensees submittal. The draft RAI is related to FPLEs submittal dated November 7, 2005, regarding a report submitted for Nuclear Regulatory Commission (NRC) review to resolve license condition 2.K for the Seabrook Station, Unit No. 1.

Review of the draft RAI would allow FPLE to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.

Docket No. 50-443

Enclosure:

Draft RAI DISTRIBUTION:

Public SMiranda RidsNrrDssSpwb LPL1-2 R/F RidsNrrPMGMiller RidsNrrDorlLplb Accession No.: ML060620015 OFFICE LPL1-2/PM LPL1-2/LA NRR/DSS/SPWB/BC LPL1-2/BC NAME GEMiller:em CRaynor JNakoski DRoberts DATE 3/3/06 3/3/06 3/03/06 3/3/06 OFFICIAL RECORD COPY

DRAFT REQUEST FOR ADDITIONAL INFORMATION SEABROOK STATION, UNIT NO. 1 (TAC NO. MC8873)

By letter dated November 7, 2005, FPL Energy Seabrook, LLC submitted a report for Nuclear Regulatory Commission (NRC) review to resolve license condition 2.K for the Seabrook Station, Unit No. 1 (Seabrook). The NRC staff requests the following additional information to complete its review.

1. The Seabrook final safety analysis report (FSAR) Section 10.2.3.4 lists the atmospheric relief valves (ARVs) stroke time to be less than, or equal to, 70 seconds, which appears to be different than the stroke time modeled in the analysis provided in the November 7, 2005, letter. Please clarify this discrepancy or provide an inadvertent emergency core cooling system actuation analysis that takes into account the value listed in the Seabrook FSAR for ARV stroke time.

2. Technical Specification (TS) 3.7.1.6 governs the operability of the ARVs, and its associated Surveillance Requirement 4.7.1.6 requires verification of the operability at certain intervals based on nitrogen accumulator tank pressure and the ability to open and close fully. Provide a justification for why the following assumptions found in the analysis submitted and the FSAR do not meet any of the criterion of Title 10 of the Code of Federal Regulations (10 CFR) Part 50.36(c)(2)(ii) or 10 CFR 50.36(c)(3) for inclusion in the Seabrook TSs:

a. The assumption that the valve stroke time is less than, or equal to, 70 seconds.

b. The ARVs are assumed to be in automatic mode during power operation (FSAR Section 10.2.3.4 identifies that operation of the ADVs is possible in both automatic and manual modes).

c. The ARVs are assumed to regulate steam generator outlet header pressure to the analyzed value (approximately 1135 psia).

Enclosure