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Category:Letter
MONTHYEARIR 05000482/20244202024-10-31031 October 2024 Security Baseline Inspection Report 05000482/2024420 ML24296B1902024-10-22022 October 2024 10 CFR 50.55a Requests for the Fifth Ten-Year Interval Inservice Testing Program 05000482/LER-2024-001-01, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-10-22022 October 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing 05000482/LER-2024-002, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve2024-10-21021 October 2024 Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve ML24284A2842024-10-10010 October 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24283A0752024-10-0909 October 2024 Notification of Commercial Grade Dedication Inspection (05000482/2025012) and Request for Information ML24199A1712024-09-17017 September 2024 Issuance of Amendment No. 241 Revise Ventilation Filter Testing Program Criteria and Administrative Correction of Absorber in Technical Specification 5.5.11 ML24260A0712024-09-12012 September 2024 License Amendment Request for a Risk-Informed Resolution to GSI-191 IR 05000482/20240102024-09-10010 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000482/2024010 (Public) ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24248A0762024-09-0404 September 2024 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 26 Owner’S Activity Report ML24248A2492024-09-0404 September 2024 Inservice Inspection Program Fourth Interval, Third Period, Refueling Outage 26 Owner’S Activity Report ML24241A2212024-08-29029 August 2024 Notice of Enforcement Discretion for Wolf Creek Generating Station ML24240A2642024-08-27027 August 2024 Corporation - Request for Notice of Enforcement Discretion Regarding Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000482/20240052024-08-14014 August 2024 Updated Inspection Plan for Wolf Creek Generating Station (Report 05000482/2024005) ML24227A5562024-08-14014 August 2024 Application to Revise Technical Specifications to Adopt TSTF-569-A, Revision 2, Revision of Response Time Testing Definitions ML24213A3352024-07-31031 July 2024 License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1. ML24206A1252024-07-24024 July 2024 Revision of Three Procedures and Two Forms That Implement the Radiological Emergency Response Plan (RERP) IR 05000482/20240022024-07-18018 July 2024 Integrated Inspection Report 05000482/2024002 05000482/LER-2024-001, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-07-0202 July 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing IR 05000482/20244012024-07-0202 July 2024 Security Baseline Inspection Report 05000482/2024401 ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24162A1632024-06-11011 June 2024 Operating Corporation – Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000482/2024010) ML24150A0562024-05-29029 May 2024 Foreign Ownership, Control or Influence (FOCI) Information – Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML23345A1602024-05-0909 May 2024 Revision of Safety Evaluation for Amendment No. 237 Request for Deviation from Fire Protection Requirements ML24089A2622024-04-29029 April 2024 Financial Protection Levels ML24118A0022024-04-27027 April 2024 Wolf Generating Nuclear Station - 2023 Annual Radiological Environmental Operating Report ML24118A0032024-04-27027 April 2024 2023 Annual Radioactive Effluent Release Report - Report 47 ML24113A1882024-04-19019 April 2024 Foreign Ownership, Control or Influence Information - Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML24109A1842024-04-18018 April 2024 Cycle 27 Core Operating Limits Report ML24109A1212024-04-18018 April 2024 (WCGS) Form 5 Exposure Report for Calendar Year 2023 IR 05000482/20240012024-04-17017 April 2024 Integrated Inspection Report 05000482/2024001 ML24114A1442024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37 ML24106A1482024-04-15015 April 2024 Notification of Inspection (NRC Inspection Report 05000482/2024003) and Request for Information ML24098A0052024-04-0707 April 2024 2023 Annual Environmental Operating Report ML24089A0972024-03-29029 March 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24089A1352024-03-29029 March 2024 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes ML24074A3312024-03-14014 March 2024 Missed Quarterly Inspection Per 40 CFR 266 Subpart N IR 05000482/20240122024-03-11011 March 2024 Fire Protection Team Inspection Report 05000482/2024012 ML24080A3452024-03-11011 March 2024 7 of the Wolf Creek Generating Station Updated Safety Analysis Report ML24016A0702024-03-0808 March 2024 Issuance of Amendment No. 240 Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ML24068A1992024-03-0707 March 2024 Changes to Technical Specification Bases - Revisions 93 and 94 ML24066A0672024-03-0505 March 2024 4-2022-024 Letter - OI Closure to Licensee ML24061A2642024-03-0101 March 2024 Revision of Two Procedures That Implement the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) Commissioners IR 05000482/20230062024-02-28028 February 2024 Annual Assessment Letter for Wolf Creek Generating Station Report 05000482/2023006 ML24059A1702024-02-28028 February 2024 Annual Fitness for Duty Program Performance Report, and Annual Fatigue Report for 2023 ML24026A0212024-02-27027 February 2024 Issuance of Amendment No. 239 Modified Implementation Date of License Amendment No. 238 ML24050A0012024-02-19019 February 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) 2024-09-06
[Table view] Category:Report
MONTHYEARML24248A0762024-09-0404 September 2024 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 26 Owner’S Activity Report ML23334A2502023-11-30030 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 2024-09-04
[Table view] Category:Miscellaneous
MONTHYEARML24248A0762024-09-0404 September 2024 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 26 Owner’S Activity Report ML23334A2502023-11-30030 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 ML23068A1962023-03-0909 March 2023 Biennial 50.59 Evaluation Report 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 ML20182A4292020-06-30030 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, ML18023A1572018-01-18018 January 2018 Submittal of Blind Sample Error Investigation Report 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 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 ML15314A6572015-11-0404 November 2015 Submittal of 10 CFR 50.46 Thirty Day Report of Emergency Core Cooling System (ECCS) Model Changes 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 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 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 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 ML14189A5312014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 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 ML14189A5372014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 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 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, 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 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, 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 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 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 52014-06-19019 June 2014 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 ML14136A1712014-05-30030 May 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14077A2812014-02-10010 February 2014 Operating Corporation Flood Hazard Reevaluation Report,Revision 0 ML1307206802013-03-0404 March 2013 Cycle 20 Core Operating Limits Report ET 12-0032, WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix B, Area Walk-by Checklists (Awcs), Page B-1 Through Page B-502012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix B, Area Walk-by Checklists (Awcs), Page B-1 Through Page B-50 ML12342A2502012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix B, Area Walk-by Checklists (Awcs), Page B-51 Through Page B-100 ML12342A2512012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix B, Area Walk-by Checklists (Awcs), Page B-101 Through Page B-150 ML12342A2532012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Cover Through Appendix a, Seismic Walkdown Checklists (Swcs) Page A-112 ML12342A2542012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix B, Area Walk-by Checklists (Awcs), Page B-151 Through Page B-184 ML12342A2552012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix B, Area Walk-by Checklists (Awcs), Page B-185 Through Page B-228 ML12342A2572012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix C, Licensing Basis Evaluations Summary, Page C-1 Through End ML12342A2592012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix a, Seismic Walkdown Checklists (Swcs) Page A-113 Through Page A-222 ML12342A2602012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix a, Seismic Walkdown Checklists (Swcs) Page A-223 Through Page A-320 ML12342A2612012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix a, Seismic Walkdown Checklists (Swcs) Page A-321 Through Page A-350 ML12342A2622012-11-30030 November 2012 WCAP-17678-NP, Rev. 0, Wolf Creek Generating Station Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report. Appendix a, Seismic Walkdown Checklists (Swcs) Page A-348 Through Page A-440 ML12100A0762012-03-26026 March 2012 Foreign Ownership, Control or Influence Information - Updated Lists of Owners, Officers, Directors and Executive Personnel ML11133A3482011-05-0808 May 2011 Great Plains Energy, Inc. and Kansas Electric Power Cooperative, Inc. - Item 8. Financial Statemnts and Supplemental Data ML11279A0052011-03-31031 March 2011 John Redmond Reservoir Diversion and Impacts to Downstream Conditions: System Simulation Modeling ML1107500302011-03-10010 March 2011 Biennial 50.59 Evaluation Report ML1023501702010-09-15015 September 2010 Review of the Results of 16th Steam Generator Tube Inservice Inspections Performed During Refueling Outage 17 ML0917607642009-06-24024 June 2009 Phase 3 Potential Loss of RHR Due to Inadequate Cooling of Suction Line During Mode 4 to Mode 3 Transition at Wolf Creek ET 09-0010, Pressure and Temperature Limits Report, Revision 12009-03-0606 March 2009 Pressure and Temperature Limits Report, Revision 1 ET 09-0005, Submittal of Requested Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification2009-01-29029 January 2009 Submittal of Requested Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification 2024-09-04
[Table view] |
Text
W4f&LF CREEK'NUCLEAR OPERATING CORPORATION Kevin J. Mo'es Manager Regulatory Affairs January 12, 2006 RA 06-0001 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
References:
- 1) Letter ET 95-0112, dated October 31, 1995, from R. C. Hagan, WCNOC, to USNRC 2) Letter WO 95-0189, dated December 27, 1995, from 0. L.Maynard, WCNOC, to USNRC 3) NRC Letter dated February 9, 1996, from USNRC to Neil S.Cams, WCNOC
Subject:
Docket 50-482: Containment Inservice Inspection Program First Interval, Second Period Owner's Activity Reports Gentlemen:
This submittal provides the Owner's Activity Reports for the second period of the first interval of the WCNOC Containment Inservice Inspection Program. Code Case N-532, "Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000," requires that an Owner's Activity Report (Form OAR-1) be prepared and certified upon completion of each refueling outage. Each Form OAR-1 prepared during an inspection period shall be submitted following the end of the inspection period.In References 1 and 2, Wolf Creek Nuclear Operating Corporation (WCNOC) requested use of ASME Code Case N-532 in lieu of current ASME Section Xl reporting requirements.
In Reference 3, the USNRC concluded that the proposed alternative to use Code Case N-532 and the clarifications contained within References 1 and 2 provide an acceptable level of quality and safety and approved the use of Code Case N-532 for use at Wolf Creek Generating Station.The enclosures provide the Owner's Activity Reports for the period of September 3, 2001 through May 19, 2005. This timeframe constitutes the second period of the first interval of the WCNOC Containment Inservice Inspection Program. Within this period, Refueling Outages 12 (RF12), 13 (RF13) and 14 (RF14) occurred.
The enclosed Forms OAR-1 (Reports WCRE-I1, 11-P2-RF12; WCRE-11, 11-P2-RF13; and WCRE-11, 11-P2-RF14) correspond to these outages.PO. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 4 An Equal Opportunity Employer M/F/HCNVET RA 016-0001 Page 2 of 2 The required 5-year frequency for conducting IWL examinations occurs within periods 1 and 3 of the WCNOC Containment Inservice Inspection Program. Therefore, no IWL examinations were performed during this period (period 2).There are no commitments contained within this letter.If you have any questions concerning this matter, please contact me at (620) 364-4126 or Ms. Diane Hooper at (620) 364-4041.Very truly yours, Kevin J. es KJM/rIt Enclosures cc: J. N. Donohew (NRC), w/e W. B. Jones (NRC), wfe B. S. Mallett (NRC), w/e Senior Resident Inspector (NRC), w/e FORM OAR-I OWNER'S ACTIVITY REPORT Report Number WCRE-I 1. II-P2-RF-12 Owner Wolf Creek Nuclear ODeratine Corporation (Name and Address of Owner)Plant WolfCreek Generatinz Station. 1550 Oxen Lane Northeast.
Burlington.
Kansas 66839 (Name and Address of Plant)Unit No. I (If applicable)
Commercial service date 9-3-85 Refueling outage no.12 Current inspection interval I" Interval for the Containment Inservice Inspection Program (Ist. 2nd. 3rd. 4th. other)2.id period for the Containment Inservice Inspection Proeram Current inspection period (I st. 2nd. 3rd)1 tM edition with no addenda Edition and Addenda of Section Xi applicable to the inspection plan Date and revision of inspection plan%VCRE-l I Rev. (). dated 10-24-2000 Edition and Addenda of Section Xi applicable to repairs and replacements.
if different than the inspection plan 1992 edition with 1992 addenda CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report arc correct. and that the examinations, tests, repairs. replacements, evaluations.
and corrective measures represented by this report conform to the requirements of Section Xl.Certificate of Authorization No.N/A Expiration Date N/A Dennis E Tougaw iZ, 4.1 O.,4f (If aoolicablc)
Signed Date Z/ i=-TIylllsx:r O ner or Owner's DesignW, Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned.
holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Kansas and employed by Factory Mutual Insurance Company Johnston.
Rhode Island described in this Owner's Activity Report, during the period September 3.2001 to April 27. 2002 to the best of my knowledge and belief. the Owner has performed all activities represented by this report in accordance with the requirements of Section Xi.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied. concerning the examinations.
tests. repairs. replacements.
evaluations and corrective measures described in this report. Furthermore.
neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or con inspection.
Commissions KS#299 of have inspected the items , and state that I/ Inspector'd Signature Date <L _ 6 __National Board, State, Province, and Endorsements This formn (E00127) may be obtained from the Order Dept.. ASME. 22 Law Drive. Box 2300. Fairfield.
NJ 07007-2300
(,MR-i II-P2-Rr-12 I'alze I ol'J TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Completion of RF-12 (I-1, P-2)Total Total Total Total Examinations Examinations Examinations Examinations Credited (%) to Examination Required For Credited for This Credited (%) for Date for the Category
- The Interval Period** The Period Interval Remarks E-A 826 1. 0.1 33 Note* No examinations pertaining to Subsection 1W!. it-ere peribrmed d1uring this time.** Tlhis column is interpreted to represent ithe cunulahte num'ber of exams perfbrmed to date in this period.Note: 100% of the Accessible Surface Areas of Category E-A are required to be inspected each Inspection Period per Table IWE-2500-1 OAR-I II-P2-RF-12 I'Pae 2 ot!
TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Flaw Flaw or Relevant Condition Found Examination Item Item Description Characterization (IWA- During Scheduled Section XI Category Number 3300) Examination or Test (Yes or No)E-A E1.12 Incore Tunnel Sump Liner Localized pitting in the liner Yes floor. The pits were of various sizes, 3/4 inch to 2 inches in diameter, 1/32 inch to 5/32 inch in depth.Attachment I provides further information as required by the Containment Inseqvice Inspection Program.OAR-1 II-P2-RF-12 Page 3 of 5 I&b TABLE 3 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Flaw or Relevant Condition Found Repair, During Scheduled Repair/Replacement, .Section XI Replacement Code or Corrective Item Description Examination or Date Plan Class Measure Description of Work Test (Yes/No) Complete Number There were no repairs, replacements, or corrective measures performed on any Class MC or CC items during the period of this report, which were required due to an item containing a flaw or relevant condition that exceeded acceptance criteria.OAR-I II-P2-RF-12 Page 4 of 5 Attachment I RF-12 IWE Examination Revealing Flaw or Area Of Degradation Exceeding Acceptance Standards 1) Description of flaw or area, including the extent of degradation, and the conditions that led to the degradation.
Localized pitting was found in the liner floor of the Incore tunnel sump. The pits were of various sizes, % to 2 inches in diameter, 1/32 to 5/32 inch in depth. Holes in the coating on the liner floor had permitted this pitting to initiate.
The holes in the coating were caused by inadequate protection of the coating during a welding operation on nearby piping and components.
The inadequate protection allowed sparks and slag from the welding to burn holes in the coating, which allowed the pitting to initiate.2) The acceptability of each flaw or area.The areas were acceptable for continued service as sufficient thickness of the liner exists at the bottom of the pits to maintain the liner plate function.3) A description of necessary corrective actions.The coating on the sump liner was repaired to prevent further pitting or loss of material.Reference WO 02-235562-000 and CCP 10183 OAR-I II-P2-RF-12 Page 5 of 5 FORM OAR-I OWNER'S ACTIVITY REPORT Report Number WCRE-I I, II-P2-RF-13 Owner Wolf Creek Nuclear Operating Corporation, 1550 Oxen Lane Northeast, Burlington, Kansas 66839 (Name and Address of Owner)Plant Wolf Creek Generating Station, 1550 Oxen Lane Northeast, Burlington, Kansas 66839 (Name and Address of Plantl 9-3-85 Refueling outage no.Unit No. I Commercial service date 13 (If applicable)
Current inspection interval 1' Interval for the Containment Inservice Inspection Program (Ist. 2nd. 3rd. 4th. other)2nd period for the Containment Inservice Inspection Program Current inspection period (Ist. 2nd. 3rd)1998 edition with no addenda Edition and Addenda of Section Xl applicable to the inspection plan Date and revision of inspection plan WCRE-I I Rev. 0, dated 10-24-2000 Edition and Addenda of Section XI applicable to repairs and replacements, if different than the inspection plan 1992 edition with 1992 addenda CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct, and that the examinations, tests, repairs, replacements, evaluations, and corrective measures represented by this report conform to the requirements of Section XI.Certificate of Authorization No.Signed Dennis E. Tougaw NIA Expiration Date N/A (If atolicable)
Date __ -I_ -______o..S.,.v9.
^ ., .Of Owner4'r (C5wner's Designee, Titl/'CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Kansas and employed by The Hartford Steam Boiler Inspection and Insurance Company of Connecticut of Hartford, Connecticut have inspected the items described in this Owner's Activity Report, during the period April 28, 2002 to December 2,2003 , and state that to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, repairs, replacements, evaluations and corrective measures described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arisium ectedtth i pection.Commissions KS#tS86 A, B, N, I J Inspector's Signature National Board, State, Province, and Endorsements Date // C This form (EO0127) may be obtained from the Order Dept., ASME, 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300 OAR-I JI-P2-RF-13 Page I of 5 TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Completion of RF-13 (I-1, P-2)Total Total' Total -Total Examinations Examinations
.Examinations Examinations Credited (%)to Examination Required For Credited for This Credited (%) for -Date for the Category
The Period Interval -. Remarks E-A 826 222 27 60 Note* No examinations pertaining to Subsection IWL were performed during this time.*
- This column is interpreted to represent the cumulative number of exams performed to date in this period.Note: I 00% of the Accessible Surface Areas of Category E-A are required to be inspected each Inspection Period per Table IWE-2500-1 CAR-I II-P2-RF-13 Page 2 of 5 TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Flaw Flaw or Relevant Condition Found Examination Item Item Description Characterization (IWA- During Scheduled Section XI Category Number 3300) Examination or Test (Yes or No)E-A E 1.12 Liner of the Sump at 270 Localized pitting in the liner Yes Degrees floor. The pit sizes ranged 1/16 inch diameter to clustered pitting with a single pit major dimension of 3/8 inch in width, and from 3/32 inch to 7/64 inch in depth.E-A E- .1 I Penetration P-1 6 Pitting at the 11:00 position.
Yes The largest pit was measured at 1/16 inch in depth and 1/8 inch in diameter.Attachment I provides further information as required by the Containment Inservice Inspection Program.OAR-I 11-P2-RF-13 Page 3 of 5 TABLE 3 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Flaw or Relevant Condition Found Repair, During Scheduled Repair/Replacement, Section Xl Replacement Code or Corrective Item Description Examination or Date Plan Class Measure Description of Work Test (Yes/No) Complete Number C-C Corrective Concrete surface on the East side Repair of concrete surface area where Yes 11126102 2002-052 Measure of the reactor building, at the top small pieces of grout from an earlier of the construction opening construction repair have started to separate and come off the face of the I reactor building._
OAR-I II-P2-RF-13 rPage 4 of 5 Attachment 1 RF-1 3 IWE Examination Revealing Flaw or Area Of Degradation Exceeding Acceptance Standards Flaws in the Liner of the Sump at 270 Degrees 1) Description of flaw or area, including the extent of degradation, and the conditions that led to the degradation.
Localized pitting was found in the liner of the sump at 270 degrees. The pits were of various sizes, ranging from isolated 1/16 inch diameter to clustered pitting with a major diameter of 3/8 inch in width, and from 3/32 to 7/64 inch in depth. Degradation of the surface coating by aging and perhaps localized damage, combined with being normally wet, has led to this corrosion.
- 2) The acceptability of each flaw or area.The areas were acceptable for continued service as sufficient thickness of the liner exists at the bottom of the pits to maintain the liner plate function.3) A description of necessary corrective actions.The coating on the sump liner was repaired to prevent further pitting or loss of material.Reference WO 03-257157-000 and CCP 11255 Flaws located on Containment Penetration P-16 4) Description of flaw or area, including the extent of degradation, and the conditions that led to the degradation.
Pitting was noted at the 11:00 position (looking DS). The largest pits measured were 1/16 inch in depth and 1/8 inch in diameter.
Degradation of the surface coating by aging and perhaps localized damage led to this corrosion.
- 5) The acceptability of each flaw or area.The areas were acceptable for continued service as sufficient thickness of the liner exists at the bottom of the pits to maintain the liner plate function.6) A description of necessary corrective actions.The coating on the penetration was repaired to prevent further pitting or loss of material.Reference WO 03-2571757-000 and CCP 11267 OAR-I JJ-P2-RF-13 Page S of S FORM OAR-] OWNER'S ACTIVITY REPORT W-CRE-II, II-P2-RF-14 Report Number Owner Wolf Creek Nuclear Operating Corporation, 1550 Oxen Lane Northeast, Burlington, Kansas 66839 (Name and Address of Owner)Plant Wolf Creek Generating Station, 1550 Oxen Lane Northeast, Burlington, Kansas 66839 (Name and Address of Plant)9-3-85 Refueling outage no.Unit No. I (If applicable)
Current inspection interval Commercial service date 14_" Interval for the Containment Inservice Inspection Program (st. 2nd. 3rd. 4th. other)2" period for the Containment Inservice Inspection Program (Ist. 2nd. 3rd)Current inspection period Edition and Addenda of Section XI applicable to the inspection plan 1998 edition with no addenda Date and revision of inspection plan WCRE-I I Rev. 2, dated 6-1-2004 Edition and Addenda of Section Xl applicable to repairs and replacements, if different than the inspection plan 1992 edition with 1992 addenda CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct, and that the examinations, tests, repairs, replacements, evaluations, and corrective measures represented by this report conform to the requirements of Section XM.Certificate of Authorization No.N/A (If aoolicable)
Expiration Date N/A Dlennis E. Thiiaaw ; _%Z'4d Signed Fngineer Date l/ 20Co5 Owfier or Owner's Designed; Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Kansas and employed by The Hartford Steam Boiler Inspection and Insurance Company of Connecticut of Hartford, Connecticut have inspected the items described in this Owner's Activity Report, during the period December 3, 2003 to May 19,2005 , and state that to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section Xl.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, repairs, replacements, evaluations and corrective measures described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arisin m o"Anectdlwith thjs inspection.
Commissions KS#586 A, B, N, I National Board, State, Province, and Endorsements Signature Date _ III I_/ I This form (EO0127) may be obtained from the Order Dept., ASME, 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300 OAR-I I1-P2-RF-14 Page I of S TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Completion of RF-14 (I-1, P-2)Total Total .Total Total Examinations Examinations .Examinations Examinations
-Credited (%) to Examination Required For Credited for This Credited (%) for Date forthe Category,'
The Interval Period** The Period Interval Remarks E-A 823 274 33 67 Notel E-C 8 4 50 50 Note 2* No examinations pertaining to Subsection JWL were performed during this time.** This column is interpreted to represent the cumulative number of exams performed to date in this period.Note 1: 100% of the Accessible Surface Areas of Category E-A are required to be inspected each Inspection Period per Table IWE-2500-1 Note 2: In accordance with IWE-1241, 4 components were reclassified as Category E-C in Period 2 resulting in 8 examinations in this Category being required for the Interval.
Three of these components had previously been examined as Category E-A components.
OAR-I II-P2-RF-14 Page 2 of 5 TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Flaw Flaw or Relevant Condition Found Examination Item Item Description Characterization (IWA- During Scheduled Section XI Category Number 3300) Examination or Test (Yes or No)E-C E4.1 1 Liner of the Sump at 90 Pitting in the liner. The pit Yes Degrees sizes on the bottom were clusters up to 3/4 inch long by 5/8 inch wide, and from 1/32 inch to 3/32 inch in depth. One pit was on the side of the liner measuring I inch long by 1/2 inch wide by_ _ 3/32 inch deep.E-A E-1.1 I Containment Dome Liner Indentations in the dome Yes liner. The indentations noted in a coated area were characterized as"deformation" and "other signs of distress".
Those noted in a non-coated area were characterized as"deformation".
The size of the indentations are 1/8 inch in diameter and 1/32 inch in_ _ depth.Attachment I provides further information as required by the Containment Inservice Inspection Program.OAR-I I)-P2-RF-14 Page 3 of 5 TABLE 3 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Flaw or Relevant Condition Found Repair, During Scheduled Repair/Replacement,Section XI Replacement Code or Corrective Item Description Examination or Date Plan Class Measure Description of Work Test (Yes/No) Complete Number There were no repairs, replacements, or corrective measures performed on any Class MC or CC items during the period of this report, which were required due to an item containing a flaw or relevant condition that exceeded acceptance criteria.OAR-I II-P2-RF-14 Page 4 of 5 Attachment I RF-14 IWE Examination Revealing Flaw or Area Of Degradation Exceeding Acceptance Standards Flaws in the Liner of the Sump at 90 Degrees 1) Description of flaw or area, including the extent of degradation, and the conditions that led to the degradation.
Pitting was found in the liner of the sump at 90 degrees. The pit sizes on the bottom of the liner were clusters ranging from 1/2 inch long by 1/2 inch wide to a maximum of 3/4 inch long by 5/8 inch wide, and from 1/32 to 3/32 inch in depth. One pit was noted on the south wall of the liner approximately 9 inches up from the bottom, it measured 1 inch long by 1/2 inch wide by 3/32 inch deep. Degradation of the surface coating by aging and perhaps localized damage, combined with being normally wet, has led to this corrosion.
- 2) The acceptability of each flaw or area.The areas were acceptable for continued service, as sufficient thickness of the liner exists at the bottom of the pits to maintain the liner plate function.3) A description of necessary corrective actions.The coating on the sump liner was repaired to prevent further pitting or loss of material.Reference WO 05-271950-001 and CCP 11753 Flaws located on Containment Dome Liner 4) Descri~otion of flaw or area, including the extent of degradation, and the conditions that led to the degradation.
Indentations were noted on the dome liner at 2201 ft. elevation and 358° azimuth. There were 10 indentations identified, 4 in a coated area that were characterized as "deformation' and "other signs of distress", and the other 6 in a non-coated area that were characterized as udeformation".
The size of the indentations were 1/8 inch in diameter by 1/32 inch in depth. The indentations have the appearance of a mark left by a chipping hammer and have an old appearance.
Based on this information, the indentations most likely occurred during fabrication of the liner plate or construction and erection.5) The acceptability of each flaw or area.The areas were acceptable for continued service as sufficient thickness of the liner exists at the bottom of the deformation to maintain the liner plate function.6) A description of necessary corrective actions.No corrective actions were necessary.
Reference WO 05-272686-001 and CCP 11797 OAR-I II-P2-RF-14 Page 5 of 5