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Category:Licensee 30-Day Written Event Report
MONTHYEARWO 17-0023, Submittal of Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report2017-03-27027 March 2017 Submittal of Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report WO 14-0092, Submittal of Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report2014-12-15015 December 2014 Submittal of Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report ML0712402692007-05-22022 May 2007 Summary of Telephone Conference Call Held on March 20, 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, Uni ML0712402862007-05-20020 May 2007 Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Wolf Creek Nuclear Operating Corporation, Concerning Draft Requests for Additional Information Pertaining to the Wolf Creek, Unit 1, LRA WO 04-0056, Special Report 2004-001 Re Inoperability of the a Train of Reactor Vessel Level Indicating System for Greater than 30 Days2005-01-0404 January 2005 Special Report 2004-001 Re Inoperability of the a Train of Reactor Vessel Level Indicating System for Greater than 30 Days 2017-03-27
[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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May 20, 2007LICENSEE:Wolf Creek Nuclear Operating CorporationFACILITY:Wolf Creek Generating Station, Unit 1
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON MAY 2, 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 May 2, 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
Enclosures:
- 1. List of Participants
- 2. List of Draft Requests for Additional Informationcc w/encls: See next page
ML071240286OFFICEPM:RLRB:DLRLA:DLRBC:RLRB:DLRNAMEVRodríguezYEdmondsRAuluck DATE05/16/0705/16/0705/20/07 TELEPHONE CONFERENCE CALLWOLF CREEK GENERATING STATION, UNIT 1LICENSE RENEWAL APPLICATIONLIST OF PARTICIPANTSMAY 2, 2007PARTICIPANTSAFFILIATIONSVerónica M. RodríguezU.S. Nuclear Regulatory Commission (NRC)Samuel MirandaNRC Lorrie BellWolf Creek Nuclear Operating Corporation (WCNOC)
Bill SelbeWCNOC Eric BlocherStrategic Teaming and Resource Sharing Alliance (STARS)Paul CrawleySTARSRichard Geiger STARS Gordon ChenSTARS DRAFT REQUESTS FOR ADDITIONAL INFORMATIONWOLF CREEK GENERATING STATION, UNIT 1LICENSE RENEWAL APPLICATIONMAY 2, 2007The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf CreekNuclear Operating Corporation (WCNOC) held a telephone conference call on May 2, 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 (LRA). Reactor Vessel and InternalsD-RAI 2.3.1.1-1 LRA Table 2.3.1-1 indicates that the reactor vessel head vent pipe is within the scope of licenserenewal and that it has a pressure boundary intended function. The staff requests that the applicant clarify which portions of the reactor head vent system, shown in Updated Safety Analysis Report (USAR) Figure 18.2-1, are within the scope of license renewal. The staff requests that the applicant identify which license renewal criteria these components meet and their intended functions. Discussion: The applicant indicated that the question is clear. The applicant clarified thatalthough not specifically indicated in LRA Section 2.3.1.1, both, D-RAIs 2.3.1.1-1 and 2.3.1.1-2,reference the same license renewal drawing LR-WCGS-BB-M-12BB04. Based on the discussion with the applicant, the staff agreed to combine these D-RAIs and revise this question as follows. The revised question will be sent as a formal RAI. USAR Figures 18.2-1 and 18.2-13 shows the reactor head vent system and the reactorvessel level instrumentation system, respectively. The staff requests that the applicant indicate which portions of the reactor head vent system are within the scope of license renewal. In addition, the applicant should clarify if the spare head penetration of the level instrumentation system is within the scope of license renewal. The staff requests that the applicant identify which license renewal criteria these components meet and their intended functions. D-RAI 2.3.1.1-2 USAR Figure 18.2-13 shows the reactor vessel level instrumentation system. The staffrequests that the applicant clarify if the spare head penetration of this system is within the scope of license renewal. If the penetration is not within the scope of license renewal, the staff requests that the applicant justify its response. Discussion: This question has been combined with D-RAI 2.3.1.1-1. Therefore, this questionis withdrawn and will not be sent as a formal RAI. Reactor Makeup Water SystemD-RAI 2.3.2.6-1LRA Section 2.3.2.6-1 states that the reactor makeup water system provides containmentisolation for penetration P-25. The staff requests that the applicant specifically identify the components (and their functions) affected by the containment isolation. In addition, the staff requests that the applicant clarify if these components are within the scope of license renewal.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. High Pressure Coolant Injection SystemD-RAI 2.3.2.10-1License renewal drawing LR-WCGS-EM-M-12EM01 shows the refueling water storage tankwithin the scope of license renewal. However, the piping and components EBN01A, EBN01B and EBN01C, which are entirely enclosed by this tank, are not. The staff requests that the applicant justify why these components are not within the scope of license renewal in accordance with Title 10 Code of Federal Regulations Part 54.4(a)(2) (10 CFR 54.4(a)(2). Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. Chemical and Volume Control SystemD-RAI 2.3.3.7-1License renewal drawing LR-WCGS-BG-M-12BG03 shows the volume control tank (TBG05)within the scope of license renewal. The staff requests that the applicant explain why the piping and spray nozzles are not included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. D-RAI 2.3.3.7-2LRA Table 2.3.3-7 does not lists component type of pumps and tanks supports. The staffrequests that the applicant clarify if the pumps and tanks supports are within the scope of license renewal. If the supports are not within the scope of license renewal the staff requests that the applicant justify its response; if they are, the applicant should indicate where these components are discussed. Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. D-RAI 2.3.3.7-3 License renewal drawing LR-WCGS-BG-M-12BG04 shows the spent resin storage tanksoutside the scope of license renewal; however, all their connecting lines were included within the scope. The staff requests that the applicant explain and justify this inconsistency. Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.
Letter to Wolf Creek Nuclear Operating Corporation, from V. Rodriguez, dated May 20, 2007
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON MAY 2, 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 APPLICATIONDISTRIBUTION
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CJacobs JDonohew GPick, RIV SCochrum, RIV CLong, RIV SMiranda Wolf Creek Generating Station cc:Jay Silberg, Esq.Pillsbury Winthrop Shaw Pittman, LLP 2300 N Street, NW Washington, DC 20037Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-7005Senior Resident InspectorU.S. Nuclear Regulatory Commission P.O. Box 311 Burlington, KS 66839Chief Engineer, Utilities DivisionKansas Corporation Commission 1500 SW Arrowhead Road Topeka, KS 66604-4027Office of the GovernorState of Kansas Topeka, KS 66612Attorney General120 S.W. 10 th Avenue, 2 nd FloorTopeka, KS 66612-1597County ClerkCoffey County Courthouse 110 South 6 th StreetBurlington, KS 66839Thomas A. Conley, Section ChiefRadiation and Asbestos Control Kansas Department of Health and Environment Bureau of Air and Radiation 1000 SW Jackson, Suite 310 Topeka, KS 66612-1366Vice President Operations/Plant ManagerWolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839Supervisor LicensingWolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839U.S. Nuclear Regulatory CommissionResident Inspectors Office/Callaway Plant
8201 NRC Road Steedman, MO 65077-1032Kevin J. Moles, ManagerRegulatory Affairs Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839Lorrie I. Bell, Project ManagerWolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839Mr. James RossNuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708