ML071220365

Summary of Telephone Conference Call Held on April 10, 2007, Between the U.S. Nuclear Regulatory Commission and Wolf Creek Nuclear Operating Corporation, Concerning Draft RAIs Pertaining to the Wolf Creek Generating Station, Unit 1, LRA

ML071220365
Person / Time
Site:	Wolf Creek
Issue date:	05/08/2007
From:	Veronica Rodriguez NRC/NRR/ADRO/DLR/RLRB
To:	Wolf Creek
Rodriguez V
References
Download: ML071220365 (10)

Text

May 8, 2007 LICENSEE: Wolf Creek Nuclear Operating Corporation FACILITY: Wolf Creek Generating Station, Unit 1

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON APRIL 10, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf Creek Nuclear Operating Corporation held a telephone conference call on April 10, 2007, to discuss and clarify the staffs draft requests for additional information (D-RAIs) concerning the Wolf Creek Generating Station, Unit 1, license renewal application. The telephone conference call was useful in clarifying the intent of the staffs D-RAIs. provides a listing of the participants and Enclosure 2 contains a listing of the D-RAIs discussed with the applicant, including a brief description on the status of the items.

The applicant had an opportunity to comment on this summary.

/RA/

Verónica M. Rodríguez, Project Manager License Renewal Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-482

Enclosures:

1. List of Participants

2. List of Draft Requests for Additional Information cc w/encls: See next page

ML071220365 OFFICE PM:RLRB:DLR LA:DLR BC:RLRB:DLR NAME VRodríguez SFigueroa RAuluck DATE 05/4/07 05/4/07 05/8/07 TELEPHONE CONFERENCE CALL WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS APRIL 10, 2007 PARTICIPANTS AFFILIATIONS Veronica Rodriguez U.S. Nuclear Regulatory Commission (NRC)

William Koo NRC Lorrie Bell Wolf Creek Nuclear Operating Corporation Eric Blocher Strategic Teaming and Resource Sharing Alliance (STARS)

Paul Crawley STARS Donald Stevens STARS Enclosure 1

DRAFT REQUESTS FOR ADDITIONAL INFORMATION WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION APRIL 10, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf Creek Nuclear Operating Corporation held a telephone conference call on April 10, 2007, to discuss and clarify the following draft requests for additional information (D-RAIs) concerning the Wolf Creek Generating Station (WCGS), Unit 1, license renewal application.

Nickel Alloy Aging Management Program D-RAI B.2.1.34-1 The Nickel Alloy Aging Management Program (AMP) was submitted prior to the performance of pre-mitigation weld inspections for the application of weld overlays on pressurizer connections with dissimilar metal butt welds at WCGS. The pre-mitigation inspection performed in 2006 identified extensive circumferential cracking at three dissimilar metals welds associated with surge, relief, and safety nozzles. The staff requests that the applicant revise this AMP to incorporate information pertaining to the dissimilar metals butt weld inspection activities and findings. The revised AMP should: (1) discuss program enhancements incorporated as a result of the inspections, (2) provide information regarding the mitigation and preventive actions, taken or planned, to reduce the susceptibility of Alloy 600/82/182 components to primary water stress corrosion cracking (PWSCC), (3) discuss the inspection frequency and method of inspection of components susceptible to PWSCC covered under the scope of this program, and (4) provide justification that the AMP will provide reasonable assurance that PWSCC will be detected in a timely manner.

In addition, the staff requests that the applicant update the AMP summary in the Updated Safety Analysis Report (USAR) supplement to reflect all changes made to the program.

Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI B.2.1.34-2 PWSCC of components made of Alloy 600/82/182 in pressurized power reactors (PWR) is an emerging material degradation issue. The industry has initiated augmented inspections and mitigation of susceptible components to ensure safe operation of the affected plants. Recent inspection findings of extensive circumferential cracking of Alloy 82/182 dissimilar metal welds at WCGS has raised concerns regarding the adequacy of the inspection scope and schedule based on industry initiatives. In addition, discussions with the industry to resolve the staffs comments and recommendations to the inspection program delineated in the Materials Reliability Program (MRP)-139, Primary System Butt Weld Inspection and Evaluation Guideline, is continuing. Therefore, to ensure that the program is acceptable for implementation during the period of extended operation and that it will manage the effects of aging in accordance with 10 CFR 54.21(a)(3), the staff requests that the applicant commit to continue to participate in industry initiatives (such as the Westinghouse Owners Group and the Enclosure 2

Electric Power Research Institute MRP). The program inspection requirements of Alloy 600/82/182 components must be consistent with the latest version of the NRC accepted industry guidance, generic communications, orders, and applicable regulatory requirements delineated in 10 CFR 50.55a. In addition, the staff requests that the applicant submit the AMP inspection plan for NRC review and approval at least 24 months prior to entering the period of extended operation.

Discussion: The staff recognized that the applicants Reactor Vessel Coolant System Supplement commitment incorporates some of these items. However, the applicant was informed that the Nickel Alloy Aging Management Program commitment needs to be supplemented and kept separate from the items related to the Reactor Vessel Internals. The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI B.2.1.34-3 By letter dated October 12, 2005, the NRC staff provided comments and recommendations to the Nuclear Energy Institute (NEI) pertaining to the guidance provided in MRP-139 for the inspection and evaluation of Alloy 82/182 butt welds. This initiative is continuing and a resolution has not been reached. The staff requests that the applicant identify any exceptions that WCGS plans to take to the NRCs comments and recommendations provided to the NEI. If WCGS plans to take exceptions, the staff requests that the applicant provide its technical justification.

Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI B.2.1.34-4 By letter dated July 27, 2004, WCNOC responded to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized Water Reactors. The staff requests that the applicant confirm that WCGS is not taking any exception to the guidance provided in this bulletin. If exceptions are identified, the applicant should address and justify them, especially those in the following areas: (1) percentage of inspection coverage to be achieved at each location, and (2) performance of an extent-of-condition evaluation, sample expansion, and non-destructive examinations if circumferential cracking is found. In addition, in view of the extensive PWSCC found at WCGS, the staff requests that the applicant discuss any enhancements made to the WCGS inspection plan for those components addressed in Bulletin 2004-01.

Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI B.2.1.34-5 NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity, requested information from PWR licensees regarding the reactor coolant pressure boundary integrity associated with the reactor pressure vessel lower head penetrations. WCNOC did not discuss augmented inspection plans for these components in its response to this bulletin nor in its description of the AMP.

In view of the extensive PWSCC found at WCGS, the staff requests that the applicant discuss the inspection plan for the components addressed in Bulletin 2003-02, and provide justification for its adequacy.

Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI B.2.1.34-6 The LRA states that the reactor coolant system (RCS) pressure boundary, RCS non-pressure boundary, and ESF locations are included within the scope of this AMP. The staff requests that the applicant identify the components associated with these locations and its corresponding inspection plan. In addition, the staff requests that the applicant identify any Alloy 600/82/182 components not covered within the scope of this program and the reasons for their exclusion.

Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI B.2.1.34-7 The detection of aging effects program element states that this AMP utilizes various visual, surface and volumetric inspections and examination techniques for early detection of PWSCC in Alloy 600 components. However, it does not specify whether the equipment, method and personnel used for these inspections meet the ASME Code Section XI requirements. The staff requests that the applicant revise the LRA to clarify this statement.

Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI B.2.1.34-8 The monitoring and trending program element states that relative risk rankings for Alloy 600 locations are included as part of this AMP. The staff requests that the applicant address how the relative risk rankings will be used in the inspection of Alloy 600/82/182 components and whether this ranking methodology was approved by the NRC.

Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI B.2.1.34-9 The corrective actions program element states that Corrective actions may be used as tracking and documentation records for changes in plant thought processes and to identify potential improvement in programs from benchmarking activities. The staff requests that the applicant provide details and examples to clarify this statement.

Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

Memo to Wolf Creek Nuclear Operating Corp from V. Rodriguez dated May 08, 2007 DISTRIBUTION:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON APRIL 10, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATION HARD COPY DLR RF E-MAIL:

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Wolf Creek Generating Station cc:

Jay Silberg, Esq. Supervisor Licensing Pillsbury Winthrop Shaw Pittman, LLP Wolf Creek Nuclear Operating Corporation 2300 N Street, NW P.O. Box 411 Washington, DC 20037 Burlington, KS 66839 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Resident Inspectors Office/Callaway Plant 611 Ryan Plaza Drive, Suite 400 8201 NRC Road Arlington, TX 76011-7005 Steedman, MO 65077-1032 Senior Resident Inspector Kevin J. Moles, Manager U.S. Nuclear Regulatory Commission Regulatory Affairs P.O. Box 311 Wolf Creek Nuclear Operating Corporation Burlington, KS 66839 P.O. Box 411 Burlington, KS 66839 Chief Engineer, Utilities Division Kansas Corporation Commission Lorrie I. Bell, Project Manager 1500 SW Arrowhead Road Wolf Creek Nuclear Operating Corporation Topeka, KS 66604-4027 P.O. Box 411 Burlington, KS 66839 Office of the Governor State of Kansas Mr. James Ross Topeka, KS 66612 Nuclear Energy Institute 1776 I Street, NW, Suite 400 Attorney General Washington, DC 20006-3708 120 S.W. 10th Avenue, 2nd Floor Topeka, KS 66612-1597 County Clerk Coffey County Courthouse 110 South 6th Street Burlington, KS 66839 Thomas A. Conley, Section Chief Radiation and Asbestos Control Kansas Department of Health and Environment Bureau of Air and Radiation 1000 SW Jackson, Suite 310 Topeka, KS 66612-1366 Vice President Operations/Plant Manager Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839