ML062760445

Extension of Relief Requests 2 & 3 for Fourth 10-Year Inservice Testing Program Interval

ML062760445
Person / Time
Site:	Prairie Island
Issue date:	10/20/2006
From:	Murphy M NRC/NRR/ADRO/DORL/LPLIII-1
To:	Thomas J. Palmisano Nuclear Management Co
M. Chawla LPL3-1
References
TAC MD3123, TAC MD3124
Download: ML062760445 (4)

Text

October 20, 2006 Mr. Thomas J. Palmisano Site Vice President Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089

SUBJECT:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -

EXTENSION OF RELIEF REQUESTS 2 AND 3 FOR THE FOURTH 10-YEAR INSERVICE TESTING PROGRAM INTERVAL (TAC NOS. MD3123 AND MD3124)

Dear Mr. Palmisano:

By letter dated July 25, 2005, the Nuclear Regulatory Commission granted interim relief until September 30, 2006 to Prairie Island Nuclear Generating Plant, Units 1 and 2, for Relief Requests 2 and 3 associated with the fourth 10-year inservice testing interval.

In a letter dated June 28, 2004, NMC requested relief for Diesel-driven cooling water pumps 12 and 22, and motor-driven cooling water pump 121. Relief was requested from ISTB-3550, which requires that a rate or quantity meter be installed in each of the pump test circuits. If a meter does not indicate the flow directly, the record shall include the method used to reduce the data. The Licensee proposed alternative pump testing using non-instrumented bypass lines that feed a jacket cooler and a gear oil cooler. Additional unmetered flow feeds the chemical treatment, and filtered water system.

In a letter dated July 25, 2005, the staff evaluated these alternate methods and concluded that the bypass lines are not fixed resistance systems and fouling of the associated equipment could change the resistance of the bypass lines and potentially mask pump degradation. Long-term relief could not be granted due to the lack of information in the relief request explaining how the testing will account for potential masking of degrading flow rates.

However, interim relief was granted pursuant to 10 CFR 50.55a(f)(6)(i) based on the impracticality of the design and the burden that would result if the Code requirements were immediately imposed, such as a plant shutdown because testing in accordance with the Code could not be performed. The staff also concluded that the current test method will identify significant degrading trends for an interim period, providing an adequate level of assurance of the operational readiness of the pumps.

The staff further concluded that granting relief would not endanger life or property or the common defense and security and was otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. The licensee was requested to respond prior to September 30, 2006, to inform the staff

T. Palmisano of actions taken to achieve compliance with the code requirements. The licensee responded in a letter dated September 19, 2006, and requested an extension of the interim relief for Relief Requests 2 and 3 until May 30, 2007.

The licensee determined that a modification to the system piping was necessary to comply with the Code requirements. Implementation of the modification was originally planned so that the requirements of the Code could be met prior to the expiration of the interim relief period.

However, it was recently identified that some components received for the modification do not reflect parameters assumed in the modification design and therefore, portions of the modification require reanalysis and will delay installation of the modification. Additionally, the onset of colder weather will decrease plant cooling water loads, thus making it difficult to achieve adequate flows for the required pump tests.

The licensee requested an extension of interim Relief Requests 2 and 3 until May 30, 2007, to allow completion of the modification and to allow testing during a period of higher cooling water loads. The staff has determined that the proposed extension to May 30, 2007, of interim Relief Requests 2 and 3 is acceptable based on the time frame required to complete installation of the modification package and to allow testing of the pumps during a period of higher cooling water loads. The current test method will continue to identify any significant degrading trends during the extension period, which will provide an adequate level of assurance of the operational readiness of the pumps. Verbal relief was granted to Prairie Island Unit 1 and 2, during a telephone conference held on September 21, 2006 (ML062900037).

If you have further questions, please contact Mahesh Chawla at (301) 415-8371.

Sincerely,

/RA/

Martin C. Murphy, Acting Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306 cc: See next page

T. Palmisano The licensee determined that a modification to the system piping was necessary to comply with the Code requirements. Implementation of the modification was originally planned so that the requirements of the Code could be met prior to the expiration of the interim relief period.

However, it was recently identified that some components received for the modification do not reflect parameters assumed in the modification design and therefore, portions of the modification require reanalysis and will delay installation of the modification. Additionally, the onset of colder weather will decrease plant cooling water loads, thus making it difficult to achieve adequate flows for the required pump tests.

The licensee requested an extension of interim Relief Requests 2 and 3 until May 30, 2007, to allow completion of the modification and to allow testing during a period of higher cooling water loads. The staff has determined that the proposed extension to May 30, 2007, of interim Relief Requests 2 and 3 is acceptable based on the time frame required to complete installation of the modification package and to allow testing of the pumps during a period of higher cooling water loads. The current test method will continue to identify any significant degrading trends during the extension period, which will provide an adequate level of assurance of the operational readiness of the pumps. Verbal relief was granted to Prairie Island Unit 1 and 2, during a telephone conference held on September 21, 2006 (ML062900037).

If you have further questions, please contact Mahesh Chawla at (301) 415-8371.

Sincerely,

/RA/

Martin C. Murphy, Acting Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306 cc: See next page DISTRIBUTION PUBLIC LPLIII-1 R/F RidsNrrPMMChawla RidsNrrLATHarris RidsNrrDorlLple RidsOgcRp TLiu WPoertner RidsAcrsAcnwMailCenter RidsRgn3MailCenter TBloomer, EDO RIII ADAMS Accession Number: ML062760445 OFFICE LPL3-1/PM LPL3-1/LA CPTB:BC OGC LPL3-1/BC(A)

NAME MChawla THarris JHuang for TCampbell MMurphy TLiu DATE 10/ /06 10/17/06 10/17/06 10/19/06 10/20/06 OFFICIAL RECORD COPY

Prairie Island Nuclear Generating Plant, Units 1 and 2 cc:

Jonathan Rogoff, Esquire Tribal Council Vice President, Counsel & Secretary Prairie Island Indian Community Nuclear Management Company, LLC ATTN: Environmental Department 700 First Street 5636 Sturgeon Lake Road Hudson, WI 54016 Welch, MN 55089 Manager, Regulatory Affairs Nuclear Asset Manager Prairie Island Nuclear Generating Plant Xcel Energy, Inc.

Nuclear Management Company, LLC 414 Nicollet Mall, R.S. 8 1717 Wakonade Drive East Minneapolis, MN 55401 Welch, MN 55089 Michael B. Sellman Manager - Environmental Protection Division President and Chief Executive Officer Minnesota Attorney Generals Office Nuclear Management Company, LLC 445 Minnesota St., Suite 900 700 First Street St. Paul, MN 55101-2127 Hudson, MI 54016 U.S. Nuclear Regulatory Commission Craig G. Anderson Resident Inspector's Office Senior Vice President, Group Operations 1719 Wakonade Drive East Nuclear Management Company, LLC Welch, MN 55089-9642 700 First Street Hudson, WI 54016 Regional Administrator, Region III U.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351 Administrator Goodhue County Courthouse Box 408 Red Wing, MN 55066-0408 Commissioner Minnesota Department of Commerce 85 7th Place East, Suite 500 St. Paul, MN 55101-2198