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| {{#Wiki_filter:August 28, 2007LICENSEE:Wolf Creek Nuclear Operating CorporationFACILITY:Wolf Creek Generating Station, Unit 1 | | {{#Wiki_filter:August 28, 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 ONAUGUST 17, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING 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 August 17, 2007, to discuss and clarify the staff's requests for additional information (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 RAIs.Enclosure 1 provides a listing of the participants and Enclosure 2 contains a listing of the RAIsdiscussed with the applicant, including a brief description on the status of the items.The applicant had an opportunity to comment on this summary. A mutually agreeable date forthe 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 | | OF TELEPHONE CONFERENCE CALL HELD ON AUGUST 17, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING 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 August 17, 2007, to discuss and clarify the staffs requests for additional information (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 RAIs. provides a listing of the participants and Enclosure 2 contains a listing of the RAIs discussed with the applicant, including a brief description on the status of the items. |
| ./RA/Verónica M. Rodríguez, Project Manager License Renewal Branch B Division of License Renewal Office of Nuclear Reactor RegulationDocket No. 50-482
| | The applicant had an opportunity to comment on this summary. A mutually agreeable 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. |
| | /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 Requests for Additional Informationcc w/encls: See next page | | : 2. List of Requests for Additional Information cc w/encls: See next page |
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| ML072320452OFFICELA:DLRPM:RLRB:DLRBC:RLRB:DLRNAMEYEdmondsVRodríguezRAuluck DATE08/24/0708/27/0708/28/07 Letter to Wolf Creek Nuclear Operating Corp From V. Rodriguez Dated August 28, 2007
| | ML072320452 OFFICE LA:DLR PM:RLRB:DLR BC:RLRB:DLR NAME YEdmonds VRodríguez RAuluck DATE 08/24/07 08/27/07 08/28/07 |
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| | Letter to Wolf Creek Nuclear Operating Corp From V. Rodriguez Dated August 28, 2007 |
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| ==SUBJECT:== | | ==SUBJECT:== |
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| ==SUMMARY== | | ==SUMMARY== |
| OF TELEPHONE CONFERENCE CALL HELD ONAUGUST 17, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATIONDISTRIBUTION | | OF TELEPHONE CONFERENCE CALL HELD ON AUGUST 17, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATION DISTRIBUTION: |
| :HARD COPY: DLR RFE-MAIL:PUBLICSSmith (srs3)
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| RidsNrrDci RidsNrrDra RidsNrrDe RidsNrrDeEemb RidsNrrDeEeeb | | SDuraiswamy RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsNrrDlrReba RidsNrrDlrRebb RidsNrrDci RidsNrrDra RidsNrrDe RidsNrrDeEemb RidsNrrDeEeeb RidsNrrDss RidsOgcMailCenter RidsNrrAdes |
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| | VRodriguez CJacobs JDonohew GPick, RIV SCochrum, RIV CLong, RIV |
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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 Ms. Julie Keys 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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| | TELEPHONE CONFERENCE CALL WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS AUGUST 17, 2007 PARTICIPANTS AFFILIATIONS Verónica M. Rodríguez U.S. Nuclear Regulatory Commission (NRC) |
| VRodriguez
| | William Koo NRC Charles Medenciy Wolf Creek Nuclear Operating Corporation (WCNOC) |
| | Donald Naylor WCNOC Eric Blocher Strategic Teaming and Resource Sharing Alliance (STARS) |
| | Paul Crawley STARS Enclosure 1 |
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| CJacobs JDonohew GPick, RIV SCochrum, RIV CLong, RIV 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
| | REQUESTS FOR ADDITIONAL INFORMATION WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION AUGUST 17, 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 August 17, 2007, as a followup discussion and request for clarification to the applicants response to the following requests for additional information (RAIs) concerning the Wolf Creek Generating Station (WCGS), Unit 1, license renewal application (LRA). The applicants response to these RAIs was submitted by letter dated July 26, 2007. |
| | 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 on a timely manner. |
| | In addition, the staff requests that the applicant update the AMP Updated Safety Analysis Report (USAR) supplement to reflect all changes made to the program. |
| | Discussion: Based on the discussion with the applicant, the staff indicated that the response to this RAI requires clarification. The staff requested that the applicant address the following: |
| | (1) The staff indicated that the applicants response did not address the steam generator primary nozzle and safe ends. The staff requested that the applicant address this Aging Management Review (AMR) line item. |
| | The applicant indicated that the steam generator primary nozzle and safe ends AMR line items will be modified to provide a clarification. |
| | (2) The staff requested that the applicant clarify if WCGS has Alloy 600 components in the instrumentation nozzles. |
| | The applicant indicated that WCGS only has Alloy 600 in the control rod drive mechanism. The applicant indicated that a footnote will be added to the RAI response to provide a clarification. |
| | Enclosure 2 |
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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 66839Ms. Julie KeysNuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 Enclosure 1TELEPHONE CONFERENCE CALLWOLF CREEK GENERATING STATION, UNIT 1LICENSE RENEWAL APPLICATIONLIST OF PARTICIPANTSAUGUST 17, 2007PARTICIPANTSAFFILIATIONSVerónica M. RodríguezU.S. Nuclear Regulatory Commission (NRC)William KooNRC Charles MedenciyWolf Creek Nuclear Operating Corporation (WCNOC)Donald NaylorWCNOC Eric BlocherStrategic Teaming and Resource Sharing Alliance (STARS)Paul CrawleySTARS REQUESTS FOR ADDITIONAL INFORMATIONWOLF CREEK GENERATING STATION, UNIT 1LICENSE RENEWAL APPLICATIONAUGUST 17, 2007The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf CreekNuclear Operating Corporation held a telephone conference call on August 17, 2007, as a followup discussion and request for clarification to the applicant's response to the following requests for additional information (RAIs) concerning the Wolf Creek Generating Station (WCGS), Unit 1, license renewal application (LRA). The applicant's response to these RAIswas submitted by letter dated July 26, 2007. 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 on a timely manner.In addition, the staff requests that the applicant update the AMP Updated Safety AnalysisReport (USAR) supplement to reflect all changes made to the program. Discussion: Based on the discussion with the applicant, the staff indicated that the responseto this RAI requires clarification. The staff requested that the applicant address the following: (1) The staff indicated that the applicant's response did not address the steam generatorprimary nozzle and safe ends. The staff requested that the applicant address this Aging Management Review (AMR) line item. The applicant indicated that the steam generator primary nozzle and safe ends AMR lineitems will be modified to provide a clarification.(2) The staff requested that the applicant clarify if WCGS has Alloy 600 components in theinstrumentation nozzles. The applicant indicated that WCGS only has Alloy 600 in the control rod drivemechanism. The applicant indicated that a footnote will be added to the RAI response to provide a clarification. (3) The staff requested that the applicant clarify the term "generator maintenance" providedin the table for this RAI response. The applicant indicated that WCGS performs generator maintenance every refuelingoutage. The applicant indicated that a footnote will be added to the RAI response to provide a clarification and details about the generator maintenance frequency.(4)The staff indicated that the applicant's response did not include the USAR supplementfor the Nickel Alloy AMP as requested in the RAI. The staff clarified that the USAR supplement should make reference to the AMP commitment (Commitment No. 30). In addition, the staff indicated that Commitment No. 30 should be supplemented to reflect the same language established in the commitment for pressure boundary nickel alloy components (Commitment No. 19).}}
| | (3) The staff requested that the applicant clarify the term generator maintenance provided in the table for this RAI response. |
| | The applicant indicated that WCGS performs generator maintenance every refueling outage. The applicant indicated that a footnote will be added to the RAI response to provide a clarification and details about the generator maintenance frequency. |
| | (4) The staff indicated that the applicants response did not include the USAR supplement for the Nickel Alloy AMP as requested in the RAI. The staff clarified that the USAR supplement should make reference to the AMP commitment (Commitment No. 30). In addition, the staff indicated that Commitment No. 30 should be supplemented to reflect the same language established in the commitment for pressure boundary nickel alloy components (Commitment No. 19). |
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Category:Meeting Summary
MONTHYEARML23303A2182023-11-0606 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 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 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 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 ML0812803052008-05-0808 May 2008 Summary of Conference Call with Wolf Creek Nuclear Operating Corporation Spring 2008 Steam Generator Tube Inspections During Refueling Outage 16 at Wolf Creek Generating Station 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 2023-11-06
[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
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August 28, 2007 LICENSEE: Wolf Creek Nuclear Operating Corporation FACILITY: Wolf Creek Generating Station, Unit 1
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON AUGUST 17, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING 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 August 17, 2007, to discuss and clarify the staffs requests for additional information (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 RAIs. provides a listing of the participants and Enclosure 2 contains a listing of the 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. A mutually agreeable 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.
/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 Requests for Additional Information cc w/encls: See next page
ML072320452 OFFICE LA:DLR PM:RLRB:DLR BC:RLRB:DLR NAME YEdmonds VRodríguez RAuluck DATE 08/24/07 08/27/07 08/28/07
Letter to Wolf Creek Nuclear Operating Corp From V. Rodriguez Dated August 28, 2007
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON AUGUST 17, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATION DISTRIBUTION:
HARD COPY:
DLR RF E-MAIL:
PUBLIC SSmith (srs3)
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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 Ms. Julie Keys 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
TELEPHONE CONFERENCE CALL WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS AUGUST 17, 2007 PARTICIPANTS AFFILIATIONS Verónica M. Rodríguez U.S. Nuclear Regulatory Commission (NRC)
William Koo NRC Charles Medenciy Wolf Creek Nuclear Operating Corporation (WCNOC)
Donald Naylor WCNOC Eric Blocher Strategic Teaming and Resource Sharing Alliance (STARS)
Paul Crawley STARS Enclosure 1
REQUESTS FOR ADDITIONAL INFORMATION WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION AUGUST 17, 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 August 17, 2007, as a followup discussion and request for clarification to the applicants response to the following requests for additional information (RAIs) concerning the Wolf Creek Generating Station (WCGS), Unit 1, license renewal application (LRA). The applicants response to these RAIs was submitted by letter dated July 26, 2007.
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 on a timely manner.
In addition, the staff requests that the applicant update the AMP Updated Safety Analysis Report (USAR) supplement to reflect all changes made to the program.
Discussion: Based on the discussion with the applicant, the staff indicated that the response to this RAI requires clarification. The staff requested that the applicant address the following:
(1) The staff indicated that the applicants response did not address the steam generator primary nozzle and safe ends. The staff requested that the applicant address this Aging Management Review (AMR) line item.
The applicant indicated that the steam generator primary nozzle and safe ends AMR line items will be modified to provide a clarification.
(2) The staff requested that the applicant clarify if WCGS has Alloy 600 components in the instrumentation nozzles.
The applicant indicated that WCGS only has Alloy 600 in the control rod drive mechanism. The applicant indicated that a footnote will be added to the RAI response to provide a clarification.
Enclosure 2
(3) The staff requested that the applicant clarify the term generator maintenance provided in the table for this RAI response.
The applicant indicated that WCGS performs generator maintenance every refueling outage. The applicant indicated that a footnote will be added to the RAI response to provide a clarification and details about the generator maintenance frequency.
(4) The staff indicated that the applicants response did not include the USAR supplement for the Nickel Alloy AMP as requested in the RAI. The staff clarified that the USAR supplement should make reference to the AMP commitment (Commitment No. 30). In addition, the staff indicated that Commitment No. 30 should be supplemented to reflect the same language established in the commitment for pressure boundary nickel alloy components (Commitment No. 19).