ML070800176

Requests for Additional Information for the Review of the Wolf Creek Generating Station, Unit 1, License Renewal Application

ML070800176
Person / Time
Site:	Wolf Creek
Issue date:	04/11/2007
From:	Veronica Rodriguez NRC/NRR/ADRO/DLR/REBB
To:	Garrett T Wolf Creek
rodriguez v m, ADRO/DLR/RLRB, 415-3703
References
Download: ML070800176 (6)

Text

April 11, 2007Mr. Terry J. GarrettVice President Engineering Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839

SUBJECT:

REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THEWOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATION

Dear Mr. Garrett:

By letter dated September 27, 2006, Wolf Creek Nuclear Operating Corporation submitted anapplication pursuant to 10 CFR Part 54, to renew the operating license for Wolf Creek Generating Station, Unit 1, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.These requests for additional information were discussed with Lorrie Bell, and a mutuallyagreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3703 or e-mail VMR1@nrc.gov

.Sincerely,/RA/Verónica M. Rodríguez, Project Manager License Renewal Branch B Division of License Renewal Office of Nuclear Reactor RegulationDocket No. 50-482

Enclosure:

Requests for Additional Informationcc w/encl: See next page

ML070800176OFFICELA:DLRPM:RLRB:DLRBC:RLRB:DLRNAMEIKingVRodríguezRAuluck DATE04/09/0704/10/0704/11/07 WOLF CREEK GENERATING STATION (WCGS), UNIT 1LICENSE RENEWAL APPLICATION (LRA)REQUESTS FOR ADDITIONAL INFORMATION (RAI)Electrical and Instrumentation and Control SystemsRAI 2.5-1LRA Section 2.5 does not explicitly describe the offsite recovery paths (from the switchyard tothe onsite distribution system) for a station blackout (SBO). The General Design Criterion 17 described in Title 10 Code of Federal Regulations Part 50 (10 CFR Part 50), Appendix A, requires that electric power from the transmission network to the onsite electric distribution system be supplied by two physically independent circuits to minimizethe likelihood of their simultaneous failure. In addition, the guidance provided by letter dated April 1, 2002, "Staff Guidance on Scoping ofEquipment Relied on to Meet the Requirements of the Station Blackout Rule (10 CFR 50.63) for License Renewal (10 CFR 54.4(a)(3))," states: For purposes of the license renewal rule, the staff has determined that the plant systemportion of the offsite power system that is used to connect the plant to the offsite power source should be included within the scope of the rule. This path typically includes switchyard circuit breakers that connect to the offsite system power transformers (startup transformers), the transformers themselves, the intervening overhead or underground circuits between circuit breaker and transformer and transformer and onsite electrical system, and the associated control circuits and structures. Ensuring that the appropriate offsite power system long-lived passive structures and components that are part of this circuit path are subject to an aging management review will assure that the bases underlying the SBO requirements are maintained over the period of extended license. According to the above, both paths that are used to control the offsite circuits to the plantshould be age managed. According to LRA drawing LR-WCGS-ELEC-KD-7496, the high voltage switchyard circuit breakers, underground cables, and its associated components and structures are not presently included within the scope of license renewal. The staff requests that the applicant justify why these components are not within the scope of license renewal. In addition the staff requests that the applicant explain in detail which high voltage breakers and other components in the switchyard will be connected from the startup transformer XMR01 and ESF No. 1 transformer XNB01 up to the offsite power system for the purpose of SBO recovery.RAI 2.5-2Regulatory Guide 1.188, "Standard Format and Content for Application to Renew NuclearPower Plant Operating Licenses," endorses Nuclear Energy Institute (NEI) 95-10, revision 6, "Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule," issued in June 2005. NEI 95-10, Appendix B, indicates that elements,resistance temperature detectors, sensors, thermocouples and transducers should be included in the list of components and/or commodity groups subject to an aging management review if a pressure boundary is applicable. The staff requests that the applicant explain why these components are not included in LRA Section 2.5 as components within the scope of license renewal.RAI 2.5-3 There has been operating experience regarding the failure of cable tie-wraps caused by thebrittleness of the plastic material. The cable tie-wraps are long-lived passive components. Its intended functions include to maintain spacing for power cable ampacity, maintain stiffness in unsupported lengths of wire bundles to ensure minimum bending radius, and maintain cables within vertical raceways, among others. Most recently, at Point Beach, the regional inspectors identified an unresolved item after noticing that the current configuration of the plant may not be consistent with plant design documents due to the age related breakage of a large number of plastic tie-wraps used to fasten wires and cables. At Point Beach, cable tie-wraps are part of the cable design in order to maintain cable ampacity or are credited in the licensee's Seismic Qualifications Utility Group to seismically qualify the cable tray system. The staff requests that the applicant explain how WCGS manages the aging of cable tie-wraps. In addition, the staff requests that the applicant justify why the cable tie-wraps are not included within the scope of license renewal in accordance with the requirements of 10 CFR 54.4.

Letter to T. Garrett, from V. Rodriguez, dated April 11, 2007DISTRIBUTION:

SUBJECT:

REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THEWOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATIONHARD COPY DLR RF E-MAIL:PUBLICRWeisman GGalletti DShum SSmith (srs3)

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SRay VGoel Wolf Creek Generating Station cc:Jay Silberg, Esq.Pillsbury Winthrop Shaw Pittman, LLP 2300 N Street, NW Washington, DC 20037Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-7005Senior Resident InspectorU.S. Nuclear Regulatory Commission P.O. Box 311 Burlington, KS 66839Chief Engineer, Utilities DivisionKansas Corporation Commission 1500 SW Arrowhead Road Topeka, KS 66604-4027Office of the GovernorState of Kansas Topeka, KS 66612Attorney General120 S.W. 10 th Avenue, 2 nd FloorTopeka, KS 66612-1597County ClerkCoffey County Courthouse 110 South 6 th StreetBurlington, KS 66839Thomas A. Conley, Section ChiefRadiation and Asbestos Control Kansas Department of Health and Environment Bureau of Air and Radiation 1000 SW Jackson, Suite 310 Topeka, KS 66612-1366Vice President Operations/Plant ManagerWolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839Supervisor LicensingWolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839U.S. Nuclear Regulatory CommissionResident Inspectors Office/Callaway Plant

8201 NRC Road Steedman, MO 65077-1032Kevin J. Moles, ManagerRegulatory Affairs Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839Lorrie I. Bell, Project ManagerWolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839Mr. James RossNuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708