Letter Sequence Other |
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MONTHYEARML0701601892006-12-19019 December 2006 12/19/2006, Viewgraphs from Meeting with Wolf Creek Generating Station to Discuss License Renewal Process and Environmental Scoping Project stage: Meeting ML0701201212006-12-19019 December 2006 Transcript of Wolf Creek Nuclear Generating Station Environmental Scoping Meeting, 12/19/2006, Page 1-22 Project stage: Request ML0701201142006-12-19019 December 2006 Environmental Scoping Public Meeting Evening Session Transcripts Project stage: Request ML0701803672007-01-11011 January 2007 Operating Corporation - Response to Request for Additional Information Regarding the Review of the License Renewal Application Project stage: Response to RAI ML0701704732007-01-19019 January 2007 12/19/2006 Summary of Public Meetings Related to the Review of the Wolf Creek Generating Station License Renewal Application Project stage: Meeting ML0702405542007-02-0707 February 2007 Request for Additional Information Regarding Severe Accident Mitigation Alternatives for Wolf Creek Generating Station Project stage: RAI ML0702305462007-02-21021 February 2007 Environmental Site Audit Regarding Wolf Creek Generating Station License Renewal Application Project stage: Other ML0722505722007-03-14014 March 2007 Meeting Minute Notes Captured by Bob Dover (Earth Tech) on March 13-14, 2007 During Wolf Creek Environmental Site Audit Project stage: Request ML0708511882007-04-0909 April 2007 Request for Additional Information Regarding the Environmental Site Audit Conducted at Wolf Creek Generating Station During the Week of March 16, 2007 Project stage: RAI ML0710802612007-04-18018 April 2007 E-mail Dated 4/18/07 - Lorrie Bell (Wolf Creek Nuclear Operating Corporation) to Christian Jacobs (NRC) Regarding Response to Questions Posed by NRC During March 20, 2007 Telecon Project stage: Request ML0712700402007-04-27027 April 2007 Administrative Procedure AP 07B-003, Revision 6, Offsite Dose Calculation Manual. Project stage: Request ML0710300772007-04-27027 April 2007 Summary of Site Audit Related to the Review of the License Renewal Application for Wolf Creek Generating Station, Unit 1 Project stage: Approval ML0708505382007-05-0101 May 2007 Issuance of Environmental Scoping Summary Report Associated with the Staff'S Review of the Application by Wolf Creek Nuclear Operating License for Wolf Creek Generating Station Project stage: Approval ML0724202502007-06-21021 June 2007 Summary of Phone Conversation Conducted Between John Szeligowski (Earth Tech) and Larry Holloway (Kansas Corporation Commission) on June 21, 2007 Regarding Alternatives Analysis for WCGS EIS Project stage: Request ML0718401902007-06-26026 June 2007 Response to NRC Request for Follow-up Information Regarding Severe Accident Mitigation Alternatives, Related to License Renewal Application Project stage: Request ML0718401882007-06-26026 June 2007 Response to NRC Requests for Follow-up Information Regarding Severe Accident Mitigation Alternatives for Wolf Creek Generating Station License Renewal Application Project stage: Other ML0720003122007-07-13013 July 2007 Summary of Impact to Wolf Creek License Renewal Application Severe Accident Mitigation Alternatives Analysis Due to Computer Program Error Project stage: Other ML0723404432007-08-15015 August 2007 Summary of the Impact to Wolf Creek Generating Station License Renewal Application Severe Accident Mitigation Alternatives Analysis Due to Computer Program Errors Project stage: Other ML0722204792007-09-18018 September 2007 Notice of Availability of the Draft Plant-Specific Supplement 32 to the GEIS Regarding Wolf Creek Generating Station, Unit 1 (FRN) Project stage: Draft Other ML0722204492007-09-18018 September 2007 Letter from NRC to Wolf Creek Nuclear Operating Corporation Project stage: Other Press Release-IV-07-036, - NRC to Hold Public Meetings on Draft Environmental Impact Statement for Wolf Creek License Renewal Application2007-09-19019 September 2007 Press Release-IV-07-036 - NRC to Hold Public Meetings on Draft Environmental Impact Statement for Wolf Creek License Renewal Application Project stage: Request ML0724201492007-09-20020 September 2007 Letter from NRC to Us Fish & Wildlife Service Biological Assessment for License Renewal of Wolf Creek Generating Station Project stage: Other ML0728202872007-09-24024 September 2007 Comment (1) of Jim Hays, on Behalf of Kansas Dept. of Wildlife & Parks Regarding Supplement 32 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Wolf Creek, Unit 1 Project stage: Supplement ML0725400262007-09-30030 September 2007 NUREG-1437, Suppl 32, Dfc, Generic Environmental Impact Statement for the License Renewal of Nuclear Plants: Regarding Wolf Creek Generating Station, Draft for Comment. Project stage: Draft Other ML0732403112007-11-0808 November 2007 Draft EIS Wolf Creek Public Meeting: Afternoon Project stage: Request ML0732402882007-11-0808 November 2007 Official Transcript of Draft EIS Wolf Creek Generating Station Public Meeting: Evening Session on November 8, 2007 in Burlington, Kansas. Pages 1 - 15 Project stage: Request ML0809501772008-05-0808 May 2008 Notice of Availability of the Final Plant-Specific Supplement 32 to the Generic Environmental Impact Statement for Licence Renewal of Nuclear Plants Regarding Wolf Creek Generating Station Project stage: Other ML0812807492008-05-0808 May 2008 Notice of Availability of the Final Plant-Specific Supplement 32 to the Generic Environmental Impact Statement for Licence Renewal of Nuclear Plants Regarding Wolf Creek Generating Station (TAC MD3182) - FRN Project stage: Other ML0812606082008-05-31031 May 2008 NUREG-1437, Supp No. 32, Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Final Report Project stage: Acceptance Review ML0810602772008-06-0606 June 2008 Final Supplement 32 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Wolf Creek Generating Station Nuclear Power Plant Project stage: Other 2007-06-21
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Category:Letter
MONTHYEARML24025A0992024-01-25025 January 2024 Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML24018A0792024-01-22022 January 2024 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed Nshcd and Opportunity for a Hearing (EPID L-2024-LLA-0007) (Letter) ML24018A1382024-01-18018 January 2024 Inservice Inspection Request for Information ML24018A2482024-01-18018 January 2024 License Amendment Request to Modify the Implementation Date of License Amendment No. 238 IR 05000482/20230042024-01-11011 January 2024 Integrated Inspection Report 05000482/2023004 ML23356A0722024-01-0404 January 2024 Supplemental Information Needed for Acceptance of Requested Licensing Actions Exemption from Specific 10 CFR Part 73N Requirements (EPID L-2023-LLE-0048) (Redacted Version) WO 23-0002, Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-0082023-12-26026 December 2023 Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-008 ML23348A3662023-12-18018 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000482 2024012) and Request for Information ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23299A2662023-11-29029 November 2023 Issuance of Amendment No. 238 Modified Implementation Date of License Amendment No. 237 ML23331A4972023-11-27027 November 2023 Supplement to License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23325A2112023-11-20020 November 2023 Submittal of Request for Exemption from Specific Provisions in 10 CFR 73.55 ML23320A2772023-11-16016 November 2023 License Amendment Request to Revise Ventilation Filter Testing Program Criteria in Technical Specification 5.5.11.b and Administrative Correction of Absorber in Technical Specification 5.5.11 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23305A3472023-11-0101 November 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML23292A3592023-10-19019 October 2023 License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23292A3572023-10-19019 October 2023 Operating Corporation, Request for Correction in Response to Issuance of Amendment No. 237 and Corresponding Safety Evaluation ML23277A2772023-10-11011 October 2023 Regulatory Audit Summary Concerning Review of Request Number CI3R-01 for Proposed Alternative Inspection Frequency for Containment Unbonded Post Tensioning System Components ML23284A2392023-10-11011 October 2023 NRC Initial Operator Licensing Examination Approval 05000482/2023301 ML23276B4552023-10-0303 October 2023 Technical Specification 5.6.8 Post Accident Monitoring (PAM) Report ML23264A8682023-09-21021 September 2023 Independent Spent Fuel Storage Installation Registration of Dry Storage Canister WC-EOS-37PTH-008-B4L, WC-EOS-37PTH-007-B4L, and WC-EOS-37PTH-002-B4L ML23256A2062023-09-14014 September 2023 Withdrawal of Requested Licensing Action Exemption from Specific 10 CFR Part 73 Requirements ML23165A2502023-08-31031 August 2023 Issuance of Amendment No. 237 Request for Deviation from Fire Protection Requirements ML23243A0002023-08-31031 August 2023 Wolf Generating Station - Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements IR 05000482/20230052023-08-23023 August 2023 Updated Inspection Plan for Wolf Creek Nuclear Operating Corporation, Unit 1 (Report 05000482/2023005) - Mid-Cycle Letter 2023 ML23232A0012023-08-19019 August 2023 Revision of One Procedure That Implements the Radiological Emergency Response Plan (Rerp). Includes EPP 06-009, Rev. 13 ML23221A3932023-08-0909 August 2023 Submittal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML23220A4222023-08-0808 August 2023 Supplement to License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ML23201A1212023-08-0707 August 2023 Issuance of Amendment No. 236 Revision to Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML23130A2902023-07-26026 July 2023 Issuance of Amendment No. 235 Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections IR 05000482/20230022023-07-11011 July 2023 Integrated Inspection Report 05000482/2023002 ML23167A0042023-06-26026 June 2023 Audit Plan to Support Review of Request for Alternative Containment Inservice Inspection Frequency IR 05000482/20234012023-06-21021 June 2023 Security Baseline Inspection Report 05000482/2023401 ML23171B1312023-06-20020 June 2023 Additional Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML23151A4162023-05-31031 May 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) ET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components2023-05-17017 May 2023 CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components WO 23-0014, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23132A1532023-05-12012 May 2023 Transmittal of 2022 Annual Financial Reports WM 23-0009, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1)2023-05-10010 May 2023 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1) ML23135A1172023-05-0808 May 2023 Redacted Version of Revision 36 to Updated Safety Analysis Report ML23117A2112023-04-27027 April 2023 Annual Exposure Report (2022) ML23117A1342023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report Report 46 2024-01-04
[Table view] Category:Report
MONTHYEARML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23292A3572023-10-19019 October 2023 Operating Corporation, Request for Correction in Response to Issuance of Amendment No. 237 and Corresponding Safety Evaluation ML23244A2142023-09-0101 September 2023 IAEA Osart Report ML23068A1962023-03-0909 March 2023 Biennial 50.59 Evaluation Report ML23135A2012022-12-0606 December 2022 EQSD-I, Rev 18, Equipment Qualification Design Basis Document ML23135A1932022-09-0101 September 2022 EQSD-II, Rev 34, Equipment Qualification Summary Document WO 22-0021, Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report2022-08-29029 August 2022 Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report ML22152A2042022-05-18018 May 2022 EQSD-I, Revision 16, Equipment Qualification Design Basis Document ML22152A1992022-05-18018 May 2022 EQSD-II, Revision 33, EQ Program Master List (Table 1) Plus Mild Environment SR Electrical Equipment List (Table 2) ML22152A1942022-05-18018 May 2022 EQSD-I, Revision 15, Equipment Qualification Design Basis Document ML23135A2072022-04-0606 April 2022 EQSD-I, Rev 17, Equipment Qualification Design Basis Document ML20290A6192020-07-23023 July 2020 Corrected Redacted Version of Rev. 33 to Updated Safety Analysis Report, EQSD-I, Rev. 14, Equipment Qualification Design Basis Document ML20182A4292020-06-30030 June 2020 Request for Notice of Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating WO 20-0048, Request for Notice of Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating2020-06-30030 June 2020 Request for Notice of Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating WO 20-0041, Rev. 32 to Equipment Qualification Summary Document-II (EQSD-II)2020-01-15015 January 2020 Rev. 32 to Equipment Qualification Summary Document-II (EQSD-II) ML19330F8632019-12-0606 December 2019 Regulatory Audit Summary Regarding License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation, ML19178A3392019-07-0909 July 2019 Staff Assessment of Aging Management Program and Inspection Plan of Reactor Vessel Internals ML19092A1562018-09-18018 September 2018 EQSD-I, Rev 14 ML18093B0112018-03-0808 March 2018 Revision 31 to Updated Safety Analysis Report, Equipment Classification Design Basis Document, EQSD-I Rev 13 ML18093B0132018-03-0808 March 2018 Revision 31 to Updated Safety Analysis Report, Equipment Qualification Summary Document, EQSD-II, Rev 30, Redacted WO 19-0010, EQSD-II, Rev 312018-02-19019 February 2018 EQSD-II, Rev 31 ML18023A1572018-01-18018 January 2018 Submittal of Blind Sample Error Investigation Report ML17241A2512017-11-0808 November 2017 Staff Assessment of Flooding Focused Evaluation ML17234A4002017-08-17017 August 2017 Summary of Changes to Three Forms That Implement Radiological Emergency Response Plan (RERP) ML17093A6652017-03-27027 March 2017 Report on Financial Protection Levels ML17151B0452017-03-0909 March 2017 Equipment Qualification Summary Document, Master List Section II, EQSD-II, Rev 28, Part 2 - Redacted ML17151B0442017-03-0202 March 2017 Equipment Qualification Summary Document, Master List Section II, EQSD-II, Rev 28, Part 1 ML17072A0512017-03-0202 March 2017 Biennial 50.59 Evaluation Report for 01/01/2015 - 12/31/2016 ML17151B0432017-01-26026 January 2017 Equipment Qualification Design Basis Document, EQSD-I, Rev 11 ML17054C2302017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - A-3788, Technical Report, Appendix a, Fission Product Removal Effectiveness of Chemical Additives in PWR Containment Sprays ET 17-0005, 16C4405-RPT-002, Revision 0, Seismic High Frequency Confirmation for WCGS2016-12-15015 December 2016 16C4405-RPT-002, Revision 0, Seismic High Frequency Confirmation for WCGS WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-I, Revision 9, Equipment Qualification Design Basis Document.2016-05-31031 May 2016 Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-I, Revision 9, Equipment Qualification Design Basis Document. ML16204A1802016-05-31031 May 2016 Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-I, Revision 9, Equipment Qualification Design Basis Document. WM 16-0008, Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-II, Revision 27 Redacted2016-05-31031 May 2016 Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-II, Revision 27 Redacted ML15314A6572015-11-0404 November 2015 Submittal of 10 CFR 50.46 Thirty Day Report of Emergency Core Cooling System (ECCS) Model Changes ML17151B0392015-10-26026 October 2015 E-1F9915, Rev 8, Design Basis Document for Ofn RP-017, Control Room Evaluation ET 16-0003, Flood Hazard Reevaluation Report, Revision 12015-10-21021 October 2015 Flood Hazard Reevaluation Report, Revision 1 ML15216A3202015-08-12012 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights ML15075A0282015-03-0404 March 2015 Biennial 50.59 Evaluation Report ML15062A2752015-02-24024 February 2015 Pressure and Temperature Limits Report, Revision 2 ET 15-0002, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, for Large Break Loss-of-Coolant (LOCA) Analysis Methodology2015-01-21021 January 2015 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, for Large Break Loss-of-Coolant (LOCA) Analysis Methodology WO 14-0095, Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-12-23023 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14189A5372014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5 ML14189A5432014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A5332014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5 ML14189A5312014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5 ML14189A5002014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5 ML14189A4982014-06-19019 June 2014 Stars Response to Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program - Vendor Information Request RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 2023-09-01
[Table view] Category:Technical
MONTHYEARML23244A2142023-09-0101 September 2023 IAEA Osart Report ML23135A2012022-12-0606 December 2022 EQSD-I, Rev 18, Equipment Qualification Design Basis Document ML23135A1932022-09-0101 September 2022 EQSD-II, Rev 34, Equipment Qualification Summary Document WO 22-0021, Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report2022-08-29029 August 2022 Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report ML22152A2042022-05-18018 May 2022 EQSD-I, Revision 16, Equipment Qualification Design Basis Document ML22152A1992022-05-18018 May 2022 EQSD-II, Revision 33, EQ Program Master List (Table 1) Plus Mild Environment SR Electrical Equipment List (Table 2) ML22152A1942022-05-18018 May 2022 EQSD-I, Revision 15, Equipment Qualification Design Basis Document ML23135A2072022-04-0606 April 2022 EQSD-I, Rev 17, Equipment Qualification Design Basis Document ML20290A6192020-07-23023 July 2020 Corrected Redacted Version of Rev. 33 to Updated Safety Analysis Report, EQSD-I, Rev. 14, Equipment Qualification Design Basis Document ML19092A1562018-09-18018 September 2018 EQSD-I, Rev 14 ML18093B0112018-03-0808 March 2018 Revision 31 to Updated Safety Analysis Report, Equipment Classification Design Basis Document, EQSD-I Rev 13 ML18093B0132018-03-0808 March 2018 Revision 31 to Updated Safety Analysis Report, Equipment Qualification Summary Document, EQSD-II, Rev 30, Redacted WO 19-0010, EQSD-II, Rev 312018-02-19019 February 2018 EQSD-II, Rev 31 ML17151B0452017-03-0909 March 2017 Equipment Qualification Summary Document, Master List Section II, EQSD-II, Rev 28, Part 2 - Redacted ML17151B0442017-03-0202 March 2017 Equipment Qualification Summary Document, Master List Section II, EQSD-II, Rev 28, Part 1 ML17151B0432017-01-26026 January 2017 Equipment Qualification Design Basis Document, EQSD-I, Rev 11 ML17054C2302017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - A-3788, Technical Report, Appendix a, Fission Product Removal Effectiveness of Chemical Additives in PWR Containment Sprays WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-I, Revision 9, Equipment Qualification Design Basis Document.2016-05-31031 May 2016 Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-I, Revision 9, Equipment Qualification Design Basis Document. ML16204A1802016-05-31031 May 2016 Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-I, Revision 9, Equipment Qualification Design Basis Document. WM 16-0008, Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-II, Revision 27 Redacted2016-05-31031 May 2016 Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-II, Revision 27 Redacted ML17151B0392015-10-26026 October 2015 E-1F9915, Rev 8, Design Basis Document for Ofn RP-017, Control Room Evaluation ML15062A2752015-02-24024 February 2015 Pressure and Temperature Limits Report, Revision 2 ML14189A4982014-06-19019 June 2014 Stars Response to Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program - Vendor Information Request ML14064A3292014-02-26026 February 2014 NP-Attachment to LTR-LIS-13-557, Rev 0, Application of Westinghouse Best-Estimate Large Break LOCA Methodology to the Wolf Creek Generating Station ET 14-0009, Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2014-02-25025 February 2014 Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis ML14034A0542014-02-12012 February 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident ML14023A6142014-02-0303 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Wolf Creek Generating Station, TAC No.: MF0788 ML13247A0772013-08-31031 August 2013 WCAP-17658-NP, Rev. 0, Wolf Creek Generating Station Transition of Methods for Core Design and Safety Analyses - Licensing Report ML13247A0782013-08-31031 August 2013 WCAP-17746-NP, Rev. 0 Westinghouse Setpoint Methodology as Applied to the Wolf Creek Generating Station ML13247A0792013-08-31031 August 2013 WCAP-17602-NP, Rev. 0, Westinghouse Setpoint Calculations for the Wolf Creek Generating Station Control, Protection, and Indication Systems ML13247A0802013-08-13013 August 2013 Full Scope Implementation of the Alternative Source Term ML13177A2852013-06-30030 June 2013 WCAP-17678-NP, Supplement 1, Revision 1, Wolf Creek Generating Station Supplemental Information for Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report, Part 3 of 3 ML12340A3982012-11-30030 November 2012 PEUS-WR-12-5, Revision 1, Wolf Creek Nuclear Operating Corporation Post Fukushima Flooding Walkdown Report ML1222602142012-08-16016 August 2012 Iolb Evaluation of Ifr 2012-04 Relating to Wolf Creek Loss of Offsite Power and Notification of Unusual Event ML12129A3872011-08-30030 August 2011 Enclosure III, Wolf Creek Nuclear Operating Corporation Administrative Procedure AP 31A-100, Revision 8, Solid Radwaste Process Control Program. ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0822702982008-07-30030 July 2008 CS Innovations Report 6002-00002, Rev. 2, Als Configuration Management Plan, Non-Proprietary, Enclosure II ML0822703012008-07-29029 July 2008 CS Innovations Report 6002-00026, Rev. 1, Als Platform Overview, Non-Proprietary, Enclosure Viii ML0822703002008-07-29029 July 2008 CS Innovations Report 6101-00200, Rev. 3, Msfis V & V Report, Non-Proprietary, Enclosure VI ML0822702992008-07-29029 July 2008 CS Innovations Report 6002-00001, Rev. 2, Als Quality Assurance Plan, Non-proprietary, Enclosure IV ET 08-0032, Submittal of Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification2008-05-14014 May 2008 Submittal of Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification ML0804401002008-01-31031 January 2008 Westinghouse Electric Company LLC LTR-CDME-08-11 NP-Attachment, Interim Alternate Repair Criterion (ARC) for Cracks in the Lower Region of the Tubesheet Expansion Zone ML0727506142007-09-24024 September 2007 LTR-CDME-07-198 NP-Attachment, Response to NRC RAI Relating to LTR-CDME-07-72 P-Attachment and LTR-CDME-05-209-P of the Wolf Creek Generating Station (WCGS) Permanent B* License Amendment Request. ML0724703942007-08-31031 August 2007 Final Report on Implication of Wolf Creek Indications. ML0719700832007-07-14014 July 2007 Draft a EPRI Report: Advanced Fea Industry Corres Presentation Studies ML0720003122007-07-13013 July 2007 Summary of Impact to Wolf Creek License Renewal Application Severe Accident Mitigation Alternatives Analysis Due to Computer Program Error ML0715603982007-04-30030 April 2007 Evaluation of Circumferential Indications in Pressurizer Nozzle Dissimilar Metal Welds at the Wolf Creek Power Plant - Non-Proprietary Report ET 07-0008, Supplemental Information on Main Steam and Feedwater Isolation System Controls Modification2007-04-18018 April 2007 Supplemental Information on Main Steam and Feedwater Isolation System Controls Modification ML0708001982007-03-13013 March 2007 9100-00003-NP, Rev. 1, Wolf Creek Generating Station Main Steam and Feedwater Isolation System (Msfis) Controls Summary. ML0702401592007-01-22022 January 2007 MRP 2007-003 Attachment 1, Implications of Wolf Creek Pressurizer Butt Weld Indications Relative to Safety Assessment and Inspection Requirements. 2023-09-01
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F CREEK NUCLEAR OPERATING CORPORATION Terry. J. Garrett Vice President, Engineering July 13, 2007 ET 07-0029 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Reference:
Letter ET 06-0038, dated September 27, 2006, from T.J. Garrett, WCNOC, to USNRC
Subject:
Docket No. 50-482: Summary of the Impact to Wolf Creek Generating Station License Renewal Application Severe Accident Mitigation Alternatives Analysis due to Computer.
Program: Error Gentlemen:
The reference provided Wolf Creek Nuclear Operating Corporation's (WCNOC) License Renewal Application (LRA) for the Wolf Creek Generating Station (WCGS). A problem with a computer program used to generate some portions of the Severe Accident Mitigation Alternatives (SAMA) analysis has been discovered that has impact on the WCGS SAMA analysis report. The WCGS SAMA analysis is Attachment F, "Severe Accident Mitigation Alternatives Analysis," to LRA Appendix E, "Applicant's Environmental Report Operating License Stage." The Total Economic Costs and Total Long-Term Pathway Doses following
'an' accident at WCGS were calculated using MELCOR ACCIDENT CONSEQUENCE CODE SYSTEM (MACCS2).
MACCS2 simulates the impact of severe'accidents at nuclear power plants on the -surrounding environment and is used for the quantification of Level 3 probabilistic risk assessments (PRA).One of the input files needed to run MACCS2 is "site data". The site data input file is generated using Sector Population, Land Fraction, and Economic Estimation Program (SECPOP2000).
A difference in the format of the site data input deck generated by SECPOP2000.
and the expected format of the input deck by the MACCS2 code:was recently discovered that impacted the Total Economic Costs calculated by MACCS2.The WCGS SAMA analysis was reanalyzed using-,the corrected SECPOP .input. The attachment to this letter provides an analysis and summary of the impact of the re-analysis to conclusions reached in Attachment F of LRA Appendix E.No commitments are identified in this submittal.
If you have-any questions concerning this matter, please contact me at (620) 364-4084,.or Mr. Kevin Moles at (620) 364-4126.P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET.,-
ET 07-0029 Page 2 of 3 Terry J. Garrett TJG/rlt Attachment
-Summary of Impact to SAMA Analysis cc: J. N. Donohew (NRC), w/a V. G. Gaddy (NRC), w/a C. Jacobs (NRC), w/a B. S. Mallett (NRC), w/a Senior Resident Inspector (NRC), w/a ET 07-0029 Page 3 of 3 STATE OF KANSAS COUNTY OF COFFEY))Terry J. Garrett, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he, has executed the same for and on behalf of said Corporation with full power and authority to'do so; and that the facts therein stated are.true and correct to the best of his knowledge, information and belief.Terry J/4arrett Vice r esident Engineering SUBSCRIBED and sworn to before me this d3!iay ofILI tL, 2007.~ HONDA L. TIEMEYERNoayPbi.OFFICIAL:
Notary Public~SEAL:, My COMMISSION EXPIRES January 11, 2010 Expiration Date 4LfA , .144 )I)D Q (,- I Attachment to ET 07-0029 Page 1 of 3 Attachment Summary of the Impact to Wolf Creek Generating Station License Renewal Application Severe Accident Mitigation Alternative Analysis due to Computer Program Error Attachment to ET 07-0029 Page 2 of 3 An error in the output of the Sector Population, Land Fraction, and Economic Estimation (SECPOP2000) program (when used to produce a MELCOR ACCIDENT CONSEQUENCE CODE SYSTEM (MACCS2) input file) was discovered that caused the Wolf Creek severe accidents analysis to be reworked.
The re-analysis produced an insignificant change to dose-risk and a small change to cost-risk.
These changed values were then used to recalculate a monetary screening value (Maximum Averted Cost Risk or MACR) for determining the cost-effectiveness of potential Severe Accident Mitigation Alternatives (SAMA)s.The modified MACR (accounts for external events) based on the mean probabilistic risk assessment (PRA) results increased from $1,852,000 to $1,876,000 (1.3 percent increase).
The 9 5 th percentile PRA results sensitivity case was also recalculated and it was determined that the modified MACR increased from $3,518,800 to $3,564,400 (also a 1.3 percent increase).
The changes to the modified MACR estimates did not impact the analysis.In addition to the impact on the modified MACR, the SECPOP error also impacted the averted cost-risks that were calculated for each of the SAMAs. The following table provides a summary of the impact of using the corrected results. in conjunction with the mean PRA results in the detailed cost-benefit calculations that were performed.
Results Summary for SECPOP Error Correction (Mean PRA Results)SAMA ID Cost of Averted Net Value Averted Net Value Change Implement Cost- (Base) Cost- Risk (Post in Cost-ation Risk (Post SECPOP Effective-(Base) SECPOP Correction) ness?Correction)
SAMA 1 $800,000 $799,882 -$118 $800,784 $784 Yes SAMA 2 $400,000 $655,712 $255,712 $656,254 $256,254 No SAMA 3 $328,000 $293,252 -$34,748 $292,442 -$35,558 No SAMA 4 -$600,000 $243,368 -$356,632
$259,672 -$340,328 No Case 1 SAMA4- $50,000 $173,050 $123,050 $184,812 $134,812 No Case 2 SAMA 5 $50,000 $54,576 $4,576 $54,698 $4,698 No SAMA 8 $565,000 $43,492 -$521,508
$43,522 -$521,478 No SAMA 13 $150,000 $111,168 -$38,832 $110,716 -$39,284 No SAMA 14 $1,200,000
$882,152 -$317,848
$883,116 -$316,884 No-ase 15 $3,250,000
$404,219 $28571 $409,458 -$2,840,542 No SAMA 15-Case 2 $1,000,000
$404,219 -$595,781
$409,458 -$590,542 No SAMA 16 $565,000 $22,648 -$542,352
$22,800 -$542,200 No SAMA 17 $550,000 $65,328 -$484,672
$65,388 -$484,612 No Attachment to ET 07-0029 Page 3 of 3 As demonstrated in the table, the corrections to the SECPOP input had a minimal impact on the averted cost-risk estimates and only one SAMA (SAMA 1) that was originally classified as "not cost beneficial" was re-classified as "cost beneficial" based on the use of the corrected input.Given that SAMA 1 was identified as potentially cost Vbeneficial in the 95th percentile PRA results sensitivity analysis that was performed-inmthe Environmental Report (ER) submittal, this change did not result in the identification of any newpotentially cost beneficial SAMAs.In addition to the review of the mean PRA results quantifications, it was necessary to examine how the 95th percentile PRA results quantifications were impacted given that they were also used to identify potentially cost beneficial SAMAs. The following table provides a summary of the cost benefit calculations using the corrected SECPOP input in conjunction with the 95th percentile PRA results. In this case, no SAMAs were identified as potentially cost beneficial that were not already identified in the ER submittal.
Results Summary for SECPOP Error Correction (95th Percentile PRA Results)SAMA ID Cost of Averted Net Value Averted Net Value Change Implement Cost- (Base) Cost- Risk (Post in Cost-ation Risk (Post SECPOP Effective-(Base) SECPOP Correction) ness?Correction)
$1,519,77 SAMA 1 $800,000 6 $719,776 $1,521,490
$721,490 No SAMA 2 $400,000 $1,245,853
$845,853 $1,246,883
$846,883 No SAMA 3 $328,000 $557,179 $229,179 $555,640 $227,640 No SAMA4 -$600,000 $462,399 -$137,601
$493,377 -$106,623 No Case 1 SAMA4- $50,000 $328,795 $2781795 $351,143 $301,143 No Case 2 SAMA 5 $50,000 $103,694 $53,694. $103,926 $53,926 No SAMA 8 $565,000 $82,635 -$482,365
$82,692 -$482,308 No SAMA 13 $150,000 $211,219 $61,219 $210,360 $60,360 No SAMA 14 $1,200,000
$1,676,089
$476,089 $1,677,920
$477,920 No SAMA 15-Case 1 $3,250,000
$768,017 -$2,481,983
$777,969 -$2,472,031 No SAMA 15 $1,000,000
$768,017 -$231,983
$777,969 -$222,031 No-Case 2 SAMA 16 $565,000 $43,031 -$521,969
$43,320 -$521,680 No SAMA 17 $550,000 $124,123 -$425,877
$124,237 -$425,763 No