ML060620015
| ML060620015 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 03/03/2006 |
| From: | Miller G E Plant Licensing Branch III-2 |
| To: | Roberts D J Plant Licensing Branch III-2 |
| Miller G, NRR/DLPM, 415-2481 | |
| References | |
| TAC MC8873 | |
| Download: ML060620015 (3) | |
Text
March 3, 2006MEMORANDUM TO: Darrell J. Roberts, Chief Plant 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 - 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, toMr. Mike O'Keefe, 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 withFPLE in order to clarify certain items in the licensee's submittal. The draft RAI is related to FPLE's 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, 2006MEMORANDUM TO: Darrell J. Roberts, Chief Plant 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 - 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, toMr. Mike O'Keefe, 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 withFPLE in order to clarify certain items in the licensee's submittal. The draft RAI is related to FPLE's 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 RAIDISTRIBUTION
- Public SMirandaRidsNrrDssSpwb LPL1-2 R/FRidsNrrPMGMillerRidsNrrDorlLplbAccession No.: ML060620015OFFICELPL1-2/PMLPL1-2/LANRR/DSS/SPWB/BCLPL1-2/BCNAMEGEMiller:em CRaynorJNakoskiDRobertsDATE3/3/063/3/063/03/063/3/06OFFICIAL RECORD COPY Enclosure DRAFTREQUEST FOR ADDITIONAL INFORMATIONSEABROOK STATION, UNIT NO. 1(TAC NO. MC8873)By letter dated November 7, 2005, FPL Energy Seabrook, LLC submitted a report for NuclearRegulatory 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 completeits review.1.The Seabrook final safety analysis report (FSAR) Section 10.2.3.4 lists the atmosphericrelief 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 cooli ng system actuation analysis that takes into account the valuelisted in the Seabrook FSAR for ARV stroke time. 2.Technical Specification (TS) 3.7.1.6 governs the operability of the ARVs, and itsassociated Surveillance Requirement 4.7.1.6 requires verification of the operability atcertain intervals based on nitrogen accumulator tank pressure and the ability to openand 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 Codeof Federal Regulations (10 CFR) Part 50.36(c)(2)(ii) or 10 CFR 50.36(c)(3) for inclusionin 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 (FSARSection 10.2.3.4 identifies that operation of the ADVs is possible in bothautomatic and manual modes). c.The ARVs are assumed to regulate steam generator outlet header pressure tothe analyzed value (approximately 1135 psia).