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Category:Letter type:ET
MONTHYEARET 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 ET 23-0005, 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peen2023-03-16016 March 2023 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened ET 23-0003, License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications2023-03-0101 March 2023 License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ET 23-0002, Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2023-02-0707 February 2023 Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 23-0004, Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2023-01-26026 January 2023 Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ET 22-0006, Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2022-12-0101 December 2022 Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 22-0010, License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2022-08-0202 August 2022 License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ET 22-0012, Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-07-12012 July 2022 Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0011, Withdrawal of 10 CFR 50.55a Request I4R-08, Relief for Extension of Follow-up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surface2022-05-31031 May 2022 Withdrawal of 10 CFR 50.55a Request I4R-08, Relief for Extension of Follow-up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surface ET 22-0005, Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-04-13013 April 2022 Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0003, CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads2022-04-0606 April 2022 CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads ET 22-0002, Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head .2022-04-0404 April 2022 Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head . ET 22-0004, Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report2022-03-15015 March 2022 Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report ET 22-0001, Removal of the Table of Contents from the Technical Specifications2022-01-12012 January 2022 Removal of the Table of Contents from the Technical Specifications ET 21-0017, Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-12-22022 December 2021 Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0009, Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage2021-11-0101 November 2021 Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage ET 21-0015, Withdrawal of License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-20020 October 2021 Withdrawal of License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 21-0012, Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-11011 October 2021 Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 21-0004, License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2021-09-29029 September 2021 License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 21-0010, License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-09-29029 September 2021 License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0005, Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-1912021-08-12012 August 2021 Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 20-0013, Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415)2020-10-26026 October 2020 Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415) ET 20-0011, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2020-10-0101 October 2020 Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ET 20-0007, License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers2020-06-0808 June 2020 License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers ET 20-0008, Operating Corporation Update for Full Implementation of Open Phase Detection System2020-05-20020 May 2020 Operating Corporation Update for Full Implementation of Open Phase Detection System ET 20-0004, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2020-04-27027 April 2020 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) ET 20-0002, Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 12020-01-29029 January 2020 Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 ET 19-0021, Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-12-0909 December 2019 Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0020, Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-11-13013 November 2019 Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0019, Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-09-10010 September 2019 Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0018, Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-08-22022 August 2019 Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0014, lnserv1ce Inspection (ISI) Program Relief Request Number 14R-07, to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, D1v1s1on 12019-08-15015 August 2019 lnserv1ce Inspection (ISI) Program Relief Request Number 14R-07, to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, D1v1s1on 1 ET 19-0002, License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-03-18018 March 2019 License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0008, Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption.2019-03-0505 March 2019 Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption. ET 19-0003, License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange2019-02-25025 February 2019 License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange ET 19-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 42019-01-23023 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4 ET 18-0032, Operating Corporation Change of Date for Full Implementation of Open Phase Detection System2018-12-0707 December 2018 Operating Corporation Change of Date for Full Implementation of Open Phase Detection System ET 18-0035, Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-12-0606 December 2018 Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0029, (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection2018-10-31031 October 2018 (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection ET 18-0018, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-06-19019 June 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0016, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information2018-05-29029 May 2018 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information ET 18-0014, Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-05-29029 May 2018 Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ET 18-0013, Relief Request Number I4R-06, Request for Relief from ASME Code Case N-729-4 for Reactor Vessel Head Penetration Nozzle Weld2018-05-0202 May 2018 Relief Request Number I4R-06, Request for Relief from ASME Code Case N-729-4 for Reactor Vessel Head Penetration Nozzle Weld ET 18-0011, (WCGS) - Guarantee of Payment of Deferred Premiums2018-04-30030 April 2018 (WCGS) - Guarantee of Payment of Deferred Premiums ET 18-0012, Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-04-19019 April 2018 Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0010, Financial Protection Levels2018-03-29029 March 2018 Financial Protection Levels ET 18-0007, Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-02-15015 February 2018 Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ET 18-0005, Withdrawal of License Amendment Request for Revision to the Emergency Plan2018-02-0505 February 2018 Withdrawal of License Amendment Request for Revision to the Emergency Plan ET 18-0004, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-01-29029 January 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 17-0025, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term2017-11-14014 November 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term 2023-05-17
[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:Administrative
MONTHYEARML19178A3392019-07-0909 July 2019 Staff Assessment of Aging Management Program and Inspection Plan of Reactor Vessel Internals ML17241A2512017-11-0808 November 2017 Staff Assessment of Flooding Focused Evaluation ML17072A0512017-03-0202 March 2017 Biennial 50.59 Evaluation Report for 01/01/2015 - 12/31/2016 ET 06-0044, Operating Corporation'S Revised Commitment Regarding 10 CFR 50.55a Request I3R-052006-10-0202 October 2006 Operating Corporation'S Revised Commitment Regarding 10 CFR 50.55a Request I3R-05 ML0429500902004-09-29029 September 2004 Attachment I, Administrative Procedure AP 07B-003, Revision 5, Offsite Dose Calculation Manual. ML0429500942003-05-22022 May 2003 Attachment II, Administrative Procedure AP 07B-004, Revision 5, Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program). ML0429500972002-03-0101 March 2002 Attachment III, Administrative Procedure AP 31A-100, Revision 4, Solid Radwaste Process Control Program. 2019-07-09
[Table view] |
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W*1LF CREEK 'NUCLEAR OPERATING CORPORATION Terry J. Garrett Vice President Engineering October 2, 2006 ET 06-0044 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Reference:
- 1) Letter ET 06-0042, dated September 27, 2006, from T. J. Garrett, WCNOC, to USNRC
- 2) Letter ET 06-0031, dated August 4, 2006, from T. J. Garrett, WCNOC, to USNRC
- 3) Letter ET 06-0021, dated May 19, 2006, from T. J. Garrett, WCNOC, to USNRC
Subject:
Docket 50-482: Wolf Creek Nuclear Operating Corporation's Revised Commitment Regarding 10 CFR 50.55a Request 13R-05 Gentlemen:
Reference 3 provided Wolf Creek Nuclear Operating Corporation (WCNOC) 10 CFR 50.55a Request 13R-05, which requested alternatives to the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV),Code,Section XI for the installation and examination of full structural weld overlays for repairing/mitigating Pressurizer nozzle-to-safe end dissimilar metal (DM) and safe end-to-piping stainless steel (SS) butt welds.
Reference 2 provided WCNOC's responses to a July 6, 2006 Nuclear Regulatory Commission (NRC) request for additional information (RAI) regarding the WCNOC 10 CFR 50.55a Request 13R-05 and provided Revision 1 to 13R-05 to address two WCNOC responses to the RAI.
Reference 1 provided WCNOC's responses to RAIs provided electronically on September 20, 2006.
/ Phone: (620) 364-8831 P.O. Box 411 / Burlington, KS 66839 An Equal Opportunity Employer M/F/HCNET
ET 06-0044 Page 2 of 2 During subsequent discussions between the NRC and WCNOC staff on September 28, 2006 and October 2, 2006, it was determined that additional information was needed related to the commitments made in Reference 1. It was also noted in these discussions that minor clarifications were needed in Table 5, Weld Overlay Examination Requirements, which was provided by Reference 2. Therefore, WCNOC has revised the commitment page to include information relevant to subsequent inservice examinations and to include two footnotes that reiterate information found in the Performance Demonstration Initiative qualified ultrasonic examination procedures discussed in Request 13R-05, Revision 1, in Reference 2. WCNOC has also made the requested changes to Table 5 originally submitted by Reference 2. to this letter provides WCNOC's revised list of commitments regarding 10 CFR 50.55a Request 13R-05. Enclosure 1 to this letter provides changes to Table 5. If you have any questions, please contact me at (620) 364-4084 or Mr. Kevin Moles at (620) 364-4126.
Sincerely Terry J. Garrett TJG/rlt : Revised List of Commitments : Revised Table 5 from ET 06-0031 cc: J. N. Donohew (NRC), w/a, w/e G. E. Werner (NRC), w/a. w/e B. S. Mallett (NRC), w/a, w/e Senior Resident Inspector (NRC), w/a, w/e
Attachment 1 to ET 06-0044 Page 1 of 1 REVISED LIST OF COMMITMENTS The following table identifies revised commitments by Wolf Creek Nuclear Operating Corporation (WCNOC) provided in letter ET 06-0042. Any other statements in this submittal are provided for information purposes and are not considered to be commitments. Please direct questions regarding these commitments to Mr. Kevin Moles at (620) 364-4126.
COMMITMENT Due DatelEvent WCNOC will notify the NRC Project Manager for Wolf Creek When the final UT Generating Station (WCGS) when the ultrasonic (UT) examination of the examination of the final full structural weld overlay is complete. weld overlays during WCNOC's Fall 2006 Refueling Outage is completed.
WCNOC will provide the results of the UT examinations of the Within 14 days of full structural weld overlays of the WCGS Pressurizer safety, completion of the relief, spray and surge line nozzle welds to the NRC. final UT examination of the weld overlays The results will include: during WCNOC's Fall 2006 Refueling A listing of indications detected1; Outage.
- The type and nature of the indications2 Also included in the results will be a discussion of any repairs to the overlay material and/or base metal and the reason for the repair.
Subsequent inservice examination of full structural repair weld overlays on the Pressurizer nozzle welds will be in accordance with the 2004 Edition with 2005 Addenda of ASME Section XI, Appendix Q, Q-4300 as prescribed in WCNOC Request 13R-05, Rev. 1, Table 5, page 27 of 28, attached to WCNOC letter ET 06-0044 dated October 2, 2006. Subsequent inservice examinations of preemptive full structural weld overlays on the Pressurizer nozzle welds will be as prescribed in WCNOC Request 13R-05, Rev. 1, Table 5, page 28 of 28, attached to WCNOC letter ET 06-0044 dated October 2, 2006.
1 The recording criteria of the ultrasonic examination procedure to be used for the examination of the WCGS Pressurizer weld overlays (PDI-UT-8, Revision F) requires that all indications, regardless of amplitude, be investigated to the extent necessary to provide accurate characterization, identity, and location. Additionally, the procedure requires that all indications, regardless of amplitude, that cannot be clearly attributed to the geometry of the overlay configuration be considered flaw indications.
2 Ultrasonic examination procedure PDI-UT-8, Revision F, requires that all suspected flaw indications are to be plotted on a cross sectional drawing of the weld and that the plots should accurately identify the specific origin of the reflector.
Enclosure 1 to ET 06-0044 Changes to Table 5: Weld Overly Examination Requirements (Pages 26-28 of Request 13R-05, Rev. 1, submitted in letter ET 06-0031)
10 CFR 50.55a Request Number 13R-05, Revision I I Table 5: Weld Overlay Examination Requirements IN-PROCESS EXAMINATIONS Examination Description* Method Technique Reference Acceptance Standards Safe end, welds, nozzle, and pipe pre-overlay Surface Liquid Penetrant N-504-3 and Q-2000 N-504-3, Paragraph (c), Q-surface preparation. 2000 (b)
Corrective layers of weld metal, if required, Surface Liquid Penetrant N-504-3 and Q-2000 N-504-3, Paragraph (d), Q-not associated with the structural weld 2000(c) overlay.
Thickness measurements for verifying final Volumetric UT-0 0L N-504-3 and Q-3000 Per weld overlay design deposited weld reinforcement, I I I requirements and Q-3000 COMPLETED WELD OVERLAY EXAMINATION and PRESERVICE EXAMINATION REQUIREMENTS Examination Description* Method Technique Reference Acceptance Standards Examination of the completed weld overlay Surface Liquid Penetrant N-504-3, N-638-1, and Q-4 100 (b) and examination of a band around the entire Q-4100 circumference of the nozzle and pipe at least 1.5 times the nozzle end thickness outward from the toe of the weld overlay on the nozzle side and at least 0.50 inches outward from the toe of the weld overlay on the pipe side. For the portion of the weld overlay installed per Code Case N-638-1 and the band area on the nozzle side, this examination will occur at least 48 hrs. after the completed weld overlay has returned to ambient temperature.
Completed weld overlay for complete Volumetric UT-0%L; N-504-3, N-638-1, Q- Thickness per weld bonding and minimum thickness and for UT angle beam per 4100, and Appendix overlay design detection of welding flaws. Examination for PDI-qualified VIII requirements in Q-3000 bonding and welding flaws in the portion of procedures and bonding and welding the weld overlay installed per Case N-638-1 flaws per Q-4100(c) will occur at least 48 hrs. after the completed weld overlay has returned to ambient temperature.
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10 CFR 50.55a Request Number 13R-05, Revision I Table 5: Weld Overlay Examination Requirements Completed weld overlay and the outer 25 Volumetric UT angle beam per N-504-3, N-638-1, Q- N-504-3, Paragraph (i) and percent of the original DM weld thickness at PDI-qualified 4200, and Appendix Q-4200 least 0.5-inches beyond the toes of the procedure VIII original DM weld and butter and at least 0.5 inches beyond any as-found flaw. For N-638-1 welding, this examination will occur at least 48 hrs. after the completed weld overlay has returned to ambient temperature.
Completed weld overlay and the outer 25 Volumetric UT angle beam per N-504-3, Q-4200, and N-504-3, Paragraph (i) and percent of the original SS pipe weld PDI-qualified Appendix VIII Q-4200 thickness at least 0.5-inches beyond the toes procedure of the original SS weld and at least 0.5 inches beyond any as-found flaw.
INSERVICE EXAMINATION REQUIREMENTS Examination Description* Method Technique Reference Acceptance Standards Full Structural Repair WOL: Weld overlay Volumetric UT angle beam per ASME Section XI Q-4300 and outer 25 percent of the original DM weld PDI procedure Appendix VIII and Q-thickness at least 0.5-inches beyond the toes 4300 of the original DM weld and butter, and at least 0.5 inches beyond any as-found flaw, will be examined within the next two refueling outages. Re-examination will be on a sampling basis in accordance with Q-4300(b) through (f) and Q-4310. These examinations will be added to the IS1 Program Plan in accordance with IWB-2412(b)(1).
Full Structural Repair WOL: Weld overlay Volumetric UT angle beam per ASME Section XI Q-4300 and outer 25 percent of the original SS pipe PDI procedure Appendix VIII and Q-weld thickness at least 0.5-inches beyond the 4300 toes of the original SS weld, and at least 0.5 inches beyond any as-found flaw, will be examined within the next two refueling outages. Re-examination will be on a 27 of 28 I
I, 10 CFR 50.55a Request Number 13R-05, Revision I I
Table 5: Weld Overlay Examination Requirements sampling basis in accordance with Q-4300(b) through (f) and Q-43 10. These examinations will be added to the IST Program Plan in accordance with IWB-2412(b)(1).
Preemptive Full Structural WOL: If greater Volumetric UT angle beam per ASME Section XI Q-4300(b) and (c) than or equal to 90% coverage of the original PDI procedure Appendix VIII and Q-DM weld is achieved with PDI qualified 4300 para. (b) through procedures and no service related indications (f) and Q-4310 are identified, the weld overlay and outer 25 percent of the original DM weld thickness at least 0.5-inches beyond the toes of the original DM weld and butter will be examined on a sampling basis in accordance with Q-4300(b) through (f) and Q-4310.
These examinations and frequency of performance will be added to the ISI Program Plan in accordance with IWB-2412(b)(1).
Preemptive Full Structural WOL: If greater Volumetric UT angle beam per ASME Section XI Q-4300(b) and (c) than or equal to 90% coverage of the original PDI procedure Appendix VIII and Q-SS weld is achieved with PDI qualified 4300 para. (b) through procedures and no service related indications (f) and Q-4310 are identified, the weld overlay and outer 25 percent of the original SS weld thickness at least 0.5-inches beyond the toes of the original SS weld will be examined on a sampling basis in accordance with Q-4300(b) through (0 and Q-4310. These examinations and frequency of performance will be added to the ISI Program Plan in accordance with IWB-2412(b)(1).
- This is a general examination description of the examinations to be performed; it does not identify all requirements for performing the examinations. As noted on page 6 of 28 of 10 CFR 50.55a Request 13R-05, Revision 1, submitted by letter ET 06-003 1, the examination requirements comply with non-mandatory Appendix Q except as noted.
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