ML060270088

Facsimile Transmission Draft Request for Additional Information to Be Discussed in an Upcoming Conference Call (Tac No. MC8327)

ML060270088
Person / Time
Site:	Millstone
Issue date:	01/31/2006
From:	Nerses V Plant Licensing Branch III-2
To:	Darrell Roberts Plant Licensing Branch III-2
Nerses V, NRR//DLPM, 415-1484
References
TAC MC8327
Download: ML060270088 (3)

Text

January 31, 2006 MEMORANDUM TO: Darrell J. Roberts, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Victor Nerses, Senior Project Manager /RA by E. Miller for/

Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

MILLSTONE POWER STATION, UNIT NO. 3 - FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MC8327)

The attached draft request for additional information (RAI) was transmitted by facsimile on January 31, 2006, to Mr. Paul Willoughby, at Dominion Nuclear Connecticut, Inc. (DNC).

This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call with DNC in order to clarify certain items in the licensees submittal. The draft RAI is related to DNCs submittal dated September 13, 2005, regarding a Technical Specification change in the recirculation spray system timing. Review of the draft RAI would allow DNC 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. 50-423

Enclosure:

RAI

January 31, 2006 MEMORANDUM TO: Darrell J. Roberts, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Victor Nerses, Senior Project Manager /RA by E. Miller for/

Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

MILLSTONE POWER STATION, UNIT NO. 3 - FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MC8327)

The attached draft request for additional information (RAI) was transmitted by facsimile on January 31, 2006, to Mr. Paul Willoughby, at Dominion Nuclear Connecticut, Inc. (DNC).

This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call with DNC in order to clarify certain items in the licensees submittal. The draft RAI is related to DNCs submittal dated September 13, 2005, regarding a Technical Specification change in the recirculation spray system timing. Review of the draft RAI would allow DNC 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. 50-423

Enclosure:

RAI DISTRIBUTION:

Public APal RidsNrrDraAadb LPL1-2 RidsNrrPMVNerses Accession No.: ML060270088 OFFICE LPL1-2/PM LPL1-2/LA EEEB/C LPL1-2/BC NAME VNerses: cm CRaynor RJenkins DRoberts (GEMiller for)

DATE 1/31/06 1/31/06 1/13/06 1/31/06 OFFICIAL RECORD COPY

REQUEST FOR ADDITIONAL INFORMATION MILLSTONE POWER STATION, UNIT NO. 3 (TAC NO. MC8327)

By letter dated September 13, 2005, Dominion Nuclear Connecticut, Inc. submitted a license amendment request for a change to the recirculation spray system timing in the Millstone Power Station, Unit No. 3, Technical Specifications. The Nuclear Regulatory Commission staff requests the following additional information to complete its review.

1. In Section 1.3 of Attachment 1 (Page 6 of 13), you have stated that there is no adverse impact on the emergency diesel generator capability as a result of a design change to start the recirculation spray system pump through actuation by the refueling water storage tank low-low level signal instead of actuation by a timer. Please provide affected calculations in support of above statement. Also provide revised final safety analysis report pages for this design change.