ML090830485

Request for Additional Information Regarding Temporary Non-Code Repair of the Class 3 Service Water System Emergency Diesel Generator Jacket Water Heat Exchanger and Air Coller Heat Exchanger

ML090830485
Person / Time
Site:	Millstone
Issue date:	04/06/2009
From:	Sanders C Plant Licensing Branch 1
To:	Christian D Dominion Nuclear Connecticut
Sandeers, Carleen, NRR/DORL, 415-1603
References
TAC ME0040, TAC ME0441, FOIA/PA-2011-0115
Download: ML090830485 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 6, 2009 Mr. David A. Christian President and Chief Nulcear Officer Dominion Nuclear Connecticut, Inc.

Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

MILLSTONE POWER STATION, UNIT NO.2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING TEMPORARY NON-CODE REPAIR OF THE CLASS 3 SERVICE WATER SYSTEM EMERGENCY DIESEL GENERATOR JACKET WATER HEAT EXCHANGER AND AIR COOLER HEAT EXCHANGER (TAC NOS. ME0040 AND ME0441)

Dear Mr. Christian:

By letter dated January 20, 2009, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090210296), Dominion Nuclear Connecticut, Inc. (DNC) submitted relief requests for Millstone Power Station, Unit NO.2 (MPS2). The relief requests are for the temporary non-code repair of class 3 service water system 'A' emergency diesel generator jacket water heat exchanger and class 3 service water system 'B' emergency diesel generator air cooler heat exchanger.

The Nuclear Regulatory Commission (NRC) staff has reviewed the information DNC provided and determined that additional information is required in order to complete the evaluation as set forth in the Enclosure.

The draft questions were sent to Mr. Bill Bartron, of your staff, to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. On March 30, 2009, Mr. Bartron agreed that you would provide a response by May 5,2009.

If you have any questions regarding this matter, I may be reached at 301-415-1603.

Sincerely,

~Carleen J. Sa rs, Project Manager Plant Licensin ranch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-336

Enclosure:

Request for Additional Information cc w/encls: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 MILLSTONE POWER STATION, UNIT NO.2 REQUEST FOR ADDITIONAL INFORMATION TEMPORARY NON-CODE REPAIR CLASS 3 SERVICE WATER SYSTEM EMERGENCY DIESEL GENERATOR JACKET WATER HEAT EXCHANGER X-45A AND AIR COOLER HEAT EXCHANGER X-83B DOCKET NO. 50-336 By letter dated January 20, 2009, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090210296), Dominion Nuclear Connecticut, Inc. (DNC) submitted relief requests for Millstone Power Station, Unit NO.2 (MPS2). The relief requests are for the temporary non-code repair of class 3 service water system 'A' emergency diesel generator (EDG) jacket water heat exchanger and class 3 service water system 'B' EDG air cooler heat exchanger. In order for the U.S. Nuclear Regulatory Commission staff to complete its review of the document listed above, the staff needs the following additional information:

1. In Attachment 2, Section 6.6, "Extent of Condition," of the original application, it appears that the "B" EDG Air Cooler Heat Exchanger was referenced where the "A" EDG Jacket Water Heat Exchanger should be. Please clarify or correct.

2. What is the trend in the leak rate of the "A" EDG Jacket Water Heat Exchanger and the "B" EDG Air Cooler Heat Exchanger?

3. In section 2.0(e) of Code Case N-513-2, "Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Divition 1," a frequent periodic inspection of no more then 30 day intervals shall be used to determine if flaws are growing. Alternatively, a flaw growth evaluation may be performed to predict the time at which the detected flaw will grow to the allowable size. When a flaw growth analysis is used to establish the allowable time, periodic examinations of no more than 90 day intervals shall be conducted to verify the flaw growth analysis predictions. Was a flaw growth analysis done for either EDG? If a flaw growth analysis was done, please justify why periodic examinations of no more than 90 day intervals do not need to be performed?

Enclosure

April 6, 2009 Mr. David A. Christian President and Chief Nulcear Officer Dominion Nuclear Connecticut, Inc.

Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

MILLSTONE POWER STATION, UNIT NO.2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING TEMPORARY NON-CODE REPAIR OF THE CLASS 3 SERVICE WATER SYSTEM EMERGENCY DIESEL GENERATOR JACKET WATER HEAT EXCHANGER AND AIR COOLER HEAT EXCHANGER (TAC NOS. ME0040 AND ME0441)

Dear Mr. Christian:

By letter dated January 20, 2009, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090210296), Dominion Nuclear Connecticut, Inc. (DNC) submitted relief requests for Millstone Power Station, Unit NO.2 (MPS2). The relief requests are for the temporary non-code repair of class 3 service water system 'A' emergency diesel generator jacket water heat exchanger and class 3 service water system 'B' emergency diesel generator air cooler heat exchanger.

The Nuclear Regulatory Commission (NRC) staff has reviewed the information DNC provided and determined that additional information is required in order to complete the evaluation as set forth in the Enclosure.

The draft questions were sent to Mr. Bill Bartron, of your staff, to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. On March 30, 2009, Mr. Bartron agreed that you would provide a response by May 5, 2009.

If you have any questions regarding this matter, I may be reached at 301-415-1603.

Sincerely, Ira!

Carleen J. Sanders, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-336

Enclosure:

Request for Additional Information cc w/encls: Distribution via Listserv DISTRIBUTION:

PUBLIC LPU-2 Reading RidsAcrsAcnw_MailCTR Resource PPatnaik, DCI/CSGB RidsNrrDorlLpl1-2 Resource RidsNrrDciCpnb Resource RidsNrrPMCSanders Resource RidsNrrLAABaxter Resource RidsOgcRp Resource RidsRgn1 MailCenter Resource Accession No ... ML090830485 OFFICE NRR/LPLI-2/PM NRR/LPLI-2/LA DCI/CPNB NRR/LPLI-2/BC NAME CSanders ABaxter TChan HChernoff DATE 03/2612009 03/26/2009 03/26/2009 416/09 Official Record Copy