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| {{#Wiki_filter:May 8, 2007LICENSEE:Wolf Creek Nuclear Operating CorporationFACILITY:Wolf Creek Generating Station, Unit 1 | | {{#Wiki_filter:May 8, 2007 LICENSEE: Wolf Creek Nuclear Operating Corporation FACILITY: Wolf Creek Generating Station, Unit 1 |
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| ==SUBJECT:== | | ==SUBJECT:== |
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| ==SUMMARY== | | ==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 APPLICATIONThe U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf CreekNuclear Operating Corporation held a telephone conference call on April 10, 2007, to discuss and clarify the staff's 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 staff's D-RAIs.Enclosure 1 provides a listing of the participants and Enclosure 2 contains a listing of theD-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 RegulationDocket No. 50-482 | | 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 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. List of Participants | | : 1. List of Participants |
| : 2. List of Draft Requests for Additional Informationcc w/encls: See next page | | : 2. List of Draft Requests for Additional Information cc w/encls: See next page |
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| ML071220365OFFICEPM:RLRB:DLRLA:DLRBC:RLRB:DLRNAMEVRodríguezSFigueroaRAuluck DATE05/4/0705/4/0705/8/07 TELEPHONE CONFERENCE CALLWOLF CREEK GENERATING STATION, UNIT 1LICENSE RENEWAL APPLICATIONLIST OF PARTICIPANTSAPRIL 10, 2007PARTICIPANTSAFFILIATIONSVeronica RodriguezU.S. Nuclear Regulatory Commission (NRC)William KooNRC Lorrie BellWolf Creek Nuclear Operating Corporation Eric BlocherStrategic Teaming and Resource Sharing Alliance (STARS)
| | ML071220365 OFFICE PM:RLRB:DLR LA:DLR BC:RLRB:DLR NAME VRodríguez SFigueroa RAuluck DATE 05/4/07 05/4/07 05/8/07 |
| Paul CrawleySTARS Donald StevensSTARS DRAFT REQUESTS FOR ADDITIONAL INFORMATIONWOLF CREEK GENERATING STATION, UNIT 1LICENSE RENEWAL APPLICATIONAPRIL 10, 2007The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf CreekNuclear 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 ProgramD-RAI B.2.1.34-1 The Nickel Alloy Aging Management Program (AMP) was submitted prior to the performance ofpre-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 UpdatedSafety 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 aformal RAI.D-RAI B.2.1.34-2 PWSCC of components made of Alloy 600/82/182 in pressurized power reactors (PWR) is anemerging 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 staff's 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 Electric Power Research Institute MRP). The program inspection requirements of Alloy600/82/182 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 applicant's Reactor Vessel Coolant SystemSupplement commitment incorporates some of these items. However, the applicant wasinformed 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.2.1.34-3By letter dated October 12, 2005, the NRC staff provided comments and recommendations tothe 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 NRC's 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 aformal RAI.D-RAI B.2.1.34-4By letter dated July 27, 2004, WCNOC responded to NRC Bulletin 2004-01, "Inspection of Alloy82/182/600 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 aformal RAI.D-RAI B.2.1.34-5NRC Bulletin 2003-02, "Leakage from Reactor Pressure Vessel Lower Head Penetrations andReactor 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 discussthe 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 aformal RAI.D-RAI B.2.1.34-6The LRA states that the reactor coolant system (RCS) pressure boundary, RCS non-pressureboundary, 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 aformal RAI.D-RAI B.2.1.34-7The 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 aformal RAI.D-RAI B.2.1.34-8The monitoring and trending program element states that relative risk rankings for Alloy 600locations 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 aformal RAI. D-RAI B.2.1.34-9The corrective actions program element states that "Corrective actions may be used as trackingand 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.
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| Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.
| | 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) |
| Memo to Wolf Creek Nuclear Operating Corp from V. Rodriguez dated May 08, 2007DISTRIBUTION:
| | 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 |
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| ==SUBJECT:==
| | 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. |
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| ==SUMMARY==
| | 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. |
| 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 APPLICATIONHARD COPY DLR RF E-MAIL:PUBLICRWeisman SSmith (srs3)
| | Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI. |
| SDuraiswamy RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsNrrDlrReba RidsNrrDlrRebb
| | 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. |
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| RidsNrrDci RidsNrrDra RidsNrrDe RidsNrrDeEemb RidsNrrDeEeeb
| | 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. |
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| RidsNrrDss RidsOgcMailCenter RidsNrrAdes
| | Memo to Wolf Creek Nuclear Operating Corp from V. Rodriguez dated May 08, 2007 DISTRIBUTION: |
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| | ==SUBJECT:== |
| | |
| | ==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: |
| | PUBLIC RWeisman SSmith (srs3) |
| | SDuraiswamy RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsNrrDlrReba RidsNrrDlrRebb RidsNrrDci RidsNrrDra RidsNrrDe RidsNrrDeEemb RidsNrrDeEeeb RidsNrrDss RidsOgcMailCenter RidsNrrAdes |
| ------------- | | ------------- |
| VRodriguez | | VRodriguez CJacobs JDonohew GPick, RIV SCochrum, RIV CLong, RIV WKoo |
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| CJacobs JDonohew GPick, RIV SCochrum, RIV CLong, RIV WKoo 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 | |
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| 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}} | | 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}} |
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Category:Meeting Summary
MONTHYEARML24212A0372024-08-0707 August 2024
Summary of July 23, 2024, Teleconference with Wolf Creek Nuclear Operating Corporation Regarding Wolf Creek Generating Station, Unit 1, Amendment No. 237, Allowing the Use of Portable Lighting
ML24088A3122024-04-0101 April 2024
Summary of March 25, 2024, Teleconference with Wolf Creek Nuclear Operating Corporation Regarding Revised Safety Evaluation for Wolf Creek Generating Station Unit 1, Amendment No. 237, Allowing the Use of Portable Lighting
ML23303A2182023-11-0606 November 2023
Summary of October 16, 2023, Pre-Submittal Teleconference with Wolf Creek Nuclear Operating Corporation Regarding a License Amendment Request to Adopt TSTF-505 for Wolf Creek Generating Station, Unit 1
ML22147A0932022-06-0606 June 2022
2021 Annual Assessment Public Meeting Summary
ML22011A0862022-01-11011 January 2022
Summary of January 10, 2022, Pre-Submittal Teleconference with Wolf Creek Nuclear Operating Corporation Regarding a License Amendment Request to Use Portable Lighting for Wolf Creek Generating Station, Unit 1
ML21333A1312021-12-0707 December 2021
Summary of Meeting with Wolf Creek Nuclear Operating Corporation Diesel Generator Completion Time License Amendment Request for Wolf Creek Generating Station
ML21200A1102021-07-21021 July 2021
Summary of July 13, 2021, Pre-Submittal Teleconference with Wolf Creek Nuclear Operating Corporation Regarding a Temporary Emergency Preparedness Exercise Exemption Request
ML21140A3892021-05-24024 May 2021
Riv Column 1 EOC 2020 Public Meeting Summary
ML21127A1322021-05-11011 May 2021
Summary of April 16, 2021, Conference Call with Representatives of Wolf Creek Generating Station Regarding the Spring 2021 Steam Generator Tube Inspections
ML20332A0422020-12-0101 December 2020
Summary of November 19, 2020, Pre-Submittal Teleconference with Wolf Creek Nuclear Operating Corporation an Emergency Response Organization Staffing License Amendment Request
ML20332A0462020-11-30030 November 2020
Summary of November 18, 2020, Pre-Submittal Teleconference with Wolf Creek Nuclear Operating Corporation a Risk-Informed Generic Safety Issue (GSI)-191 License Amendment Request
ML20189A2832020-07-0707 July 2020
Summary of Region IV Annual Assessment Public Meeting
ML19143A4182019-05-21021 May 2019
Summary of Public Meeting with Wolf Creek Nuclear Operation Corporation
ML19140A4742019-05-20020 May 2019
Closed Meeting with Wolf Creek Nuclear Operating Corporation to Conduct a Mediation Session Regarding Falsification of Documentation Associated with Licensee Maintenance Activities
ML18313A2542018-11-16016 November 2018
Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation Regarding License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses for Wolf Creek Generating Station
ML17276B4892017-10-23023 October 2017
9/25/17 Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation Regarding the Proposed LAR for Change in Emergency Plan Staff Augmentation Response Times for Wolf Creek Generating Station (CAC No. MG0174; EPID L-2017-LRM-001
ML16271A4822016-09-27027 September 2016
Summary of Regulatory Conference to Discuss Safety Significance of Wolf Creek Generating Station Emergency Generator Excitation Diode Apparent Violation
ML16250A1652016-09-0909 September 2016
8/25/16 Summary of Preapplication Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Amendment Request to Transition to Westinghouse Analyses Methodologies and Alternate Source Term at Wolf Creek Generating Station
ML16243A5132016-09-0101 September 2016
Summary of August 25, 2016, Public Meeting with Wolf Creek Nuclear Operating Corporation and Amerenue Regarding a Proposed Application for a New Technical Specification for the Class 1E Electrical Equipment Air Conditioning System (MF8118 a
ML16106A1742016-04-22022 April 2016
Summary of Meeting with Wolf Creek Nuclear Operating Company to Discuss the Generic Safety Issue (GSI)-191 Testing Plan/Fiber Penetration and Head Loss Testing Approach for Wolf Creek Generating Station
ML15182A0952015-06-30030 June 2015
Summary of Annual Assessment Meeting with Wolf Creek Nuclear Operating Corporation (WCNOC) Regarding Wolf Creek Generating Station 2014 Performance
ML14188C4812014-07-0707 July 2014
Summary of Annual Assessment Meeting with Wolf Creek Generating Station
ML14134A1842014-05-14014 May 2014
Summary of Public Meeting to Discuss an Apparent Violation Identified at Wolf Creek Generating Station
ML14038A3852014-02-0606 February 2014
1/22/2014 - Summary of Public Meeting to Discuss Corrective Actions Implemented to Address the Chilling Effect Letter
ML13221A2152013-08-12012 August 2013
7/30/2013 - Summary of Preapplication Meeting with Wolf Creek Nuclear Operating Company to Discuss Proposed Transition to Westinghouse Methodologies for Core Design and Non-LOCA Safety Analyses at Wolf Creek Generating Station
ML13221A2132013-08-12012 August 2013
8/7/2013 - Summary of Preapplication Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Long-Term Corrective Actions for Water Hammer Events in the Essential Service Water System at Wolf Creek
ML13121A4892013-05-0101 May 2013
End of Cycle Meeting Summary 4-18-13
ML13077A0732013-04-0101 April 2013
Summary of 2/28/13 and 3/11/13 Conference Calls with Licensee and Its Contractors Ongoing Steam Generator Tube Inspection Activities During Refueling Outage 19
ML12355A6922012-12-20020 December 2012
Summary of Public Meeting with Wolf Creek Nuclear Operating Corp Re Improved Station Performance
ML12276A2652012-11-0101 November 2012
Meeting Summary with Wolf Creek Nuclear Operating Corporation to Discuss Transition from Current to NRC-Approved Westinghouse Methodologies for Performing the Core Design and Non-LOCA Safety Analysis at Wolf Creek
ML12191A1742012-07-0909 July 2012
6/25/2012 Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation
ML12191A1462012-07-0606 July 2012
6/26/2012 - Summary of Public Meeting to Discuss Performance of Wolf Creek Nuclear Operating Corporation
ML13246A3802012-05-0808 May 2012
Email from M. King, NRR on Ioeb Clearinghouse Screening Summary for Tuesday, May 8, 2012
ML1207601012012-03-16016 March 2012
Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation
ML13246A3782012-02-16016 February 2012
Email from M. King, NRR on Ioeb Clearinghouse Screening Summary for Thursday, February 16, 2012
ML13246A3772012-01-31031 January 2012
Email from M. King, NRR on Ioeb Clearinghouse Screening Summary for Tuesday, January 31, 2012
ML13246A3762012-01-23023 January 2012
Email from M. King, NRR on Ioeb Clearinghouse Screening Summary for Monday, January 23, 2012
ML12011A1012012-01-19019 January 2012
Summary of Meeting with NEI and to Address Di&C Issues
ML13246A3742012-01-17017 January 2012
Email from M. King, NRR on Ioeb Clearinghouse Screening Summary for Tuesday, January 17, 2012
ML1110104292011-04-11011 April 2011
Summary of Annual Performance Assessment Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Wolf Creek Generating Station Performance for the NRC Inspection Period Ending December 31, 2010
ML1024506282010-09-0202 September 2010
Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation
ML1013404892010-05-14014 May 2010
Summary of Annual Performance Assessment Meeting with Wolf Creek Nuclear Operating Corporation to Discuss the Wolf Creek Generating Station Performance for the NRC Inspection Period from January 1 Through December 31, 2009
ML0933805662009-12-17017 December 2009
Summary of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02 Sent 7/31/2009 and 8/27/2009, Respectively
ML0933702032009-12-0303 December 2009
Summary of Public Meeting for Wolf Creek Generating Station
ML0924607142009-09-28028 September 2009
Summary of Meeting with Union Electric Co., and Wolf Creek, to Discuss Draft Requests for Additional Information on GL 2004-02 for Callaway, Unit 1, and Wolf Creek
ML0911205282009-04-21021 April 2009
Summary of Annual Performance Assessment Meeting for Wolf Creek Generating Station
ML0902102062009-01-23023 January 2009
Summary of Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Changes to Post Fire Shutdown Unresolved Items Analysis Methods Pre-Application for Wolf Creek Generating Station
ML0829607972008-10-22022 October 2008
Summary of Meeting with Wolf Creek, Discussing Several Initiatives Being Implemented to Improve Plant Performance
ML0817706682008-06-25025 June 2008
Summary of Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Several Initiatives That Were Being Implemented to Improve Plant Performance at Wolf Creek
ML0813606472008-06-10010 June 2008
05/01/2008-Summary of Public Meeting on Safety Evaluation Report with Open Items Regarding the Wolf Creek Generating Station License Renewal Review
2024-08-07
[Table view]
Category:Memoranda
MONTHYEARML23179A2132023-07-0505 July 2023
Approval for Credit for the Wolf Creek Generating Station Operational Safety Review Team to the Baseline Inspection Samples/Hours
ML22165A0882022-06-14014 June 2022
Information Request, Security IR 2022403
ML22147A0932022-06-0606 June 2022
2021 Annual Assessment Public Meeting Summary
ML22034A3932022-02-16016 February 2022
Calendar Year 2021 Security Baseline Completion Memo
ML21309A5482021-11-15015 November 2021
NSIR Staff Review of the Wolf Creek Generating Stations Security Plan Training & Qualification Plan & Safeguards Contingency Plan for the Verification of ASM EA 20 091 Incorporation
ML21243A4492021-09-0202 September 2021
ISFSI Technical Assistance Request - Review of Physical Security Plan
ML21140A3892021-05-24024 May 2021
Riv Column 1 EOC 2020 Public Meeting Summary
ML18173A0082018-06-20020 June 2018
Cancelling Numerous Inspection Report Numbers
ML17019A2912017-01-19019 January 2017
Notice of Closed Regulatory Conference with Wolf Creek Generating Station
ML17019A2932017-01-19019 January 2017
Notice of Closed Regulatory Conference with Wolf Creek Generating Station
ML16064A1872016-03-0404 March 2016
Closed Pre-Decisional Enforcement Conference with Wolf Creek Nuclear Operating Corporation
ML15251A0092015-09-11011 September 2015
Review of Revision 28 to the Updated Safety Analysis Report
ML15015A1712015-01-0808 January 2015
Focused Baseline Inspection at the Wolf Creek Site for a Major Essential Service Water Modification
ML14197A3442014-07-25025 July 2014
Review of Revision 27 to the Updated Safety Analysis Report
ML13204A2432013-07-24024 July 2013
Notice of Preapplication Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Long-Term Corrective Actions for Water Hammer Events in the Essential Service Water System at Wolf Creek
ML13109A2342013-07-12012 July 2013
Safety Evaluation Regarding Wolf Creek Generating Station - Loss of Offsite Power and Augmented Inspection, Issue for Resolution 2012-004
ML13179A1012013-07-0909 July 2013
7/30/13 Notice of Forthcoming Preapplication Meeting with Wolf Creek Nuclear Operating Company to Discuss Proposed Transition to Westinghouse Methodologies for Core Design and Non-LOCA Safety Analyses at Wolf Creek Generating Station
ML13093A0592013-04-0202 April 2013
Public Meeting with Wolf Creek Nuclear Operating Corporation to Discuss the Performance Assessment Results for Wolf Creek Generating Station for 2012
ML13078A1552013-03-20020 March 2013
License Amendment Request to Change Diesel Generator Surveillance Requirements
ML12249A0292012-09-0606 September 2012
9/20/12 Notice of Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Transition from Current to NRC-Approved Westinghouse Methodologies for Performing the Core Design and Non-LOCA Safety Wolf Creek Station
ML1222602142012-08-16016 August 2012
Iolb Evaluation of Ifr 2012-04 Relating to Wolf Creek Loss of Offsite Power and Notification of Unusual Event
ML12011A1012012-01-19019 January 2012
Summary of Meeting with NEI and to Address Di&C Issues
ML1101106702011-02-0707 February 2011
Fire Protection Safety Evaluation Input for Wolf Creek Generating Station Regarding License Amendment Request for Deviation from the Fire Protection Program Requirements
ML1006010322010-03-0101 March 2010
Cy 2009 Baseline Inspection Completion
ML0929300152009-10-20020 October 2009
Revised Notice of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02
ML0928003162009-10-16016 October 2009
Notice of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02 Sent 7/31/0209 and 8/27/2009, Respectively
ML0925404602009-09-10010 September 2009
Summary of Phone Call with Industry to Issues Related to Eccentricity of the Steam Generator Tube-to-Tubesheet Joints in the Finite Element Model Used for the Technical Basis of the Permanent Alternate Repair Criteria License Amendment Requ
ML0920306202009-07-31031 July 2009
Notice of Forthcoming Conference Call with Union Electric Company and Wolf Creek Nuclear Operating Company Re Draft Requests for Additional Information on Generic Letter 2004-02 for Callaway Plant and Wolf Creek Creek Generating Station
ML0917002962009-07-30030 July 2009
Issuance of Amendment 183, Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, to Extend the Surveillance Frequency on ESFAS Slave Relays from 92 Days to 18 Months
ML0835705252008-12-24024 December 2008
Meeting Notice, Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Pre-Application of Post-fire Safe Shutdown Issues at Wolf Creek
ML0829405182008-11-10010 November 2008
Renewal of Full-Power Operating License for the Wolf Creek Generating Station, Unit 1
ML0813006882008-05-0909 May 2008
03/05/2008 Meeting Minutes of Subcommittee on Plant License Renewal Regarding Wolf Creek Generating Station
ML0812001002008-04-29029 April 2008
End of Cycle Meeting with Wolf Creek Nuclear Operation Corporation
IR 05000482/20080072008-04-24024 April 2008
IR 05000482-08-007, on 01/15/2008 - 03/13/2008, Wolf Creek Generating Station, NRC Special Inspection
ML0810805452008-04-18018 April 2008
05/01/2008-Notice of Forthcoming Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Safety Evaluation Report Open Items Related to Metal Fatigue Analyses for License Renewal
ML0807904692008-04-10010 April 2008
Summary of Teleconference with Wolf Creek Nuclear Operating Corporation, Ameren Union Electric Company for Callaway Plant, and Performance Contracting, Inc. Containment Sump Head Loss Testing
ML0802500852008-03-26026 March 2008
Summary of Second Conference Call Held on January 16, 2008, with PWR Licensees on New Temporary License Amendment Needed for Steam Generator Tube Inspections in Spring 2008 Refueling Outages
ML0807404192008-03-14014 March 2008
Assessment of Inspections of Dissimilar Metal Butt Welds in a Retired Pressurizer
ML0807400842008-03-14014 March 2008
Draft Regulatory Guide for Comment
ML0807304562008-03-13013 March 2008
Cy 2007 Baseline Inspection Completion
ML0804503232008-03-0303 March 2008
Summary of Third Conference Call Held with Pressurized-Water Reactor Licensees on Status of NRC Review of License Amendment Requests for Steam Generator Tube Inspections
ML0807300242008-02-22022 February 2008
Status Report and Proposed Agenda for the ACRS Subcommittee on March 5, 2008 Related to the License Renewal Application of Wolf Creek Generating Stations Unit 1
ML0804504682008-02-19019 February 2008
Federal Register Notice Regarding the Meeting of the ACRS Subcommittee on Wolf Creek Plant License Renewal Application, March 5, 2008
ML0803603712008-02-0707 February 2008
Advisory Sub-Committee on Reactor Safeguards Review of the Wolf Creek Generating Station, License Renewal Application - Safety Evaluation Report with Open Items
ML0800901542008-01-22022 January 2008
Summary of Conference Call Held with PWR Licensees on the Temporary License Amendment Needed for Steam Generator Tube Inspections in Spring 2008 Refueling Outages
ML0733103642007-11-27027 November 2007
Revised Notice of Meeting with Wolf Creek Nuclear Operating Corp, to Discuss NRC Staff'S Request for Information on Licensee'S Supplemental Letter Dated September 27, 2007, to the Application Dated February 21, 2006, to Revise TS 5.5.9
ML0733101982007-11-27027 November 2007
Notice of Meeting with Wolf Creek Nuclear Operating Corporation, to Discuss NRC Staff'S Request for Additional Information on Licensee'S Proposed Main Steam and Feedwater Isolation System Modification in Its Application Dated March 14, 2007
ML0732500032007-11-21021 November 2007
Memo to Thomas G. Hiltz Key Issues for Discussion for November 28, 2007 Meeting on Steam Generator Tube Inspection License Amendment (Tac MD0197)
ML0730901272007-11-0808 November 2007
Notice of Meeting with Wolf Creek Nuclear Operating Corporation to Discuss NRC Staff'S Request for Additional Information on Licensee'S Supplemental Letter to Letter Dated September 27, 2007, to Application Dated February 21, 2006
ML0727000542007-10-0202 October 2007
Summary of Telephone Conference Call Held on 9/26/07, Between the U.S. NRC and Wolf Creek Nuclear Operating Corporation, Concerning Draft Requests for Additional Information Pertaining to the Wolf Creek Generating Station, Unit 1, LRA
2023-07-05
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML22361A0052022-12-27027 December 2022
NRR E-mail Capture - Request for Additional Information Wolf Creek Request for Deviation from Fire Protection Program Requirements
ML22321A2662022-11-16016 November 2022
January 2023 Emergency Preparedness Program Inspection - Request for Information
ML22307A1372022-11-0202 November 2022
August 2022 Emergency Preparedness Exercise Inspection Unresolved Item - Request for Information
ML22249A2552022-06-29029 June 2022
Request for Information for an NRC Post-Approval Site Inspection for License Renewal 05000482/2022012
ML22165A0882022-06-14014 June 2022
Information Request, Security IR 2022403
ML22166A3222022-06-14014 June 2022
August 2022 Emergency Preparedness Exercise Inspection - Request for Information
ML22055A1142022-02-23023 February 2022
NRR E-mail Capture - Request for Additional Information - Wolf Creek Request to Revise Diesel Generator Completion Time
ML22045A4512022-02-14014 February 2022
NRR E-mail Capture - Request for Additional Information - Wolf Creek Steam Generator Inspection Report 24th Refueling
ML22025A3612022-01-21021 January 2022
PI&R RFI Final
ML21327A2602021-11-23023 November 2021
NRR E-mail Capture - Request for Additional Information - Wolf Creek Revision of Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
ML21271A1952021-09-28028 September 2021
E-mail 9-28-21 RFI for Wc EP Inspection Nov 2021
ML21253A0902021-09-23023 September 2021
Supplemental Information Needed for Acceptance of Requested Licensing Actions License Amendment and Regulatory Exemption for a Risk-Informed Approach to Address GSI-191 (EPIDs L-2021-LLA- 0152 and L-2021-LLE-0039)
ML21221A1282021-08-0505 August 2021
NRR E-mail Capture - Urgent: Draft Request for Additional Information - Wolf Creek one-time Request for Exemption from the Biennial Emergency Preparedness Exercise
ML21132A1032021-05-12012 May 2021
Document Request List, Paperwork Reduction Act Statement
ML20302A4782020-10-28028 October 2020
OPC R1 Request for Information
ML20262A7512020-09-17017 September 2020
NRR E-mail Capture - Requests for Additional Information: Wolf Creek Amendment Request to Modify Technical Specification Surveillance Frequency Consistent with TSTF-425
ML20195A2712020-07-13013 July 2020
Generation Station - Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000482/2020012) and Request for Information
ML20133J8972020-05-12012 May 2020
12 May 2020 E-mail - RFI for NRC In-Office Inspection of Recent Wcngs Eplan_Eal Changes
ML20009E4802020-01-0909 January 2020
Relief Request to Utilize Code Case N-666-1 for Wolf Creek Generating Station - Request for Additional Information
ML19346E6052019-11-0404 November 2019
Target Set Request for Information for Week of November 4, 2019
ML19224A5242019-08-12012 August 2019
NRR E-mail Capture - Request for Additional Information - License Amendment Request to Revise Wolf Creek Generating Station Technical Specification 3.3.5
ML18304A1052018-11-0505 November 2018
Request for Additional Information License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses and Alternative Source Term (CAC No. MF9307; EPID L-2017-LLA-0211)
ML18282A6402018-10-0909 October 2018
NRR E-mail Capture - Request for Additional Information - Wolf Creek Generating Station License Amendment Request for Revision to the Emergency Plan
ML18270A0942018-10-0404 October 2018
Request for Additional Information License Amendment Request for Transition to Westinghouse Methodology for Selected Accident and Transient Analyses
ML18207A4332018-07-24024 July 2018
NRR E-mail Capture - (External_Sender) Draft Request for Additional Information Relief Request from ASME Code N-666-1 Alternate Repair of Essential Service Water Piping Wolf Creek Generating Station, Unit 1 EPID No.:L-2018-LLR-0101
ML18116A6132018-04-25025 April 2018
Operating Corporation - Notification of Inspection (NRC Inspection Report 05000482/2018002) and Request for Information
ML17331A1782017-12-0404 December 2017
Request for Additional Information License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternate Source Term (CAC No. MF9307; EPID L-2017-LLA-0211)
ML17291A7102017-10-17017 October 2017
NRR E-mail Capture - Request for Additional Information - License Amendment Request (LAR) for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term
ML17265A0142017-09-21021 September 2017
NRR E-mail Capture - Request for Additional Information - License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses
ML17170A3152017-06-19019 June 2017
Notification of an NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000482/2017008) and Request for Information
ML17166A0382017-06-14014 June 2017
NRR E-mail Capture - Request for Additional Information - License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term
ML17052A0282017-02-15015 February 2017
NRR E-mail Capture - Wolf Creek Generating Station - Official EAL RAIs
ML16319A4282016-11-14014 November 2016
NRR E-mail Capture - Request for Additional Information (RAI) - Relief Requests 13R-14 and 13R-15
ML16300A2662016-10-21021 October 2016
Request for Additional Information - Relief Request I3R-13 Regarding Weld Examination Coverage
IR 05000482/20160022016-08-0303 August 2016
NRC Integrated Inspection Report 05000482/2016002
ML16110A3722016-04-25025 April 2016
Request for Additional Information, License Amendment Request to Revise Technical Specification (TS) 4.2.1 and TS 5.6.5 to Allow Use of Optimized Zirlo as Approved Fuel Rod Cladding
ML16020A1392016-01-15015 January 2016
Notification of NRC Component Design Bases Inspection (05000482/2016007) and Initial Request for Information
ML15135A4862015-05-14014 May 2015
Wc 2015007 17T RFI
ML15082A0052015-03-27027 March 2015
Request for Additional Information, Round 2, Request to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
ML15079A0762015-03-23023 March 2015
Request for Additional Information, Round 2, Flood Hazard Reevaluation Report for Recommendation 2.1 of the Near-Term Task Force Review of the Insights from the Fukushima Dai-Ichi Accident
ML15040A6252015-02-10010 February 2015
Request for Additional Information, License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
ML14323A5742014-12-0404 December 2014
Request for Additional Information, License Amendment Request to Revise Fire Protection Program Related to Alternative Shutdown Capability as Described in USAR
ML14230A7572014-08-21021 August 2014
Request for Additional Information, Relief Request I3R-10, Alternative from Pressure Test Requirements of ASME Code Section XI, IWC-5220, Third 10-Year Inservice Inspection Interval
ML14206A0122014-08-0101 August 2014
Request for Additional Information, Relief Requests I3R-08, RPV Interior Attachments and I3R-09, RPV Pressure-Retaining Welds, Exam Interval Extensions, Third 10-year Inservice Inspection Interval
ML14197A3362014-07-25025 July 2014
Request for Additional Information, Relief Request I3R-11, Alternative from Pressure Test Requirements of ASME Code Section XI IWC-5220, Third 10-Year Inservice Inspection Interval
ML14148A3872014-06-0202 June 2014
Request for Additional Information Related to Flood Hazard Reevaluation Report for Recommendation 2.1 of the Near-Term Task Force Review of the Insights from the Fukushima Dai-Ichi Accident
ML14111A1002014-04-30030 April 2014
Request for Additional Information, Nrr/Dss/Srxb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term
ML14083A4002014-04-0303 April 2014
Request for Additional Information, Nrr/Dra/Arcb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term
ML14058A0882014-03-0505 March 2014
Request for Additional Information, Nrr/De/Eeeb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term
ML14027A1622014-01-28028 January 2014
Redacted, Request for Additional Information, Round 2, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term
2022-06-29
[Table view] |
Text
May 8, 2007 LICENSEE: Wolf Creek Nuclear Operating Corporation FACILITY: Wolf Creek Generating Station, Unit 1
SUBJECT:
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:
SUBJECT:
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:
PUBLIC RWeisman SSmith (srs3)
SDuraiswamy RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsNrrDlrReba RidsNrrDlrRebb RidsNrrDci RidsNrrDra RidsNrrDe RidsNrrDeEemb RidsNrrDeEeeb RidsNrrDss RidsOgcMailCenter RidsNrrAdes
VRodriguez CJacobs JDonohew GPick, RIV SCochrum, RIV CLong, RIV WKoo
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
