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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:License-Operator
MONTHYEARIR 05000482/20233012023-12-19019 December 2023 NRC Examination Report 05000482/2023301 ML23284A2392023-10-11011 October 2023 NRC Initial Operator Licensing Examination Approval 05000482/2023301 ML23097A0162023-04-0707 April 2023 Notification of NRC Initial Operator Licensing Examination 05000482/2023301 ML22020A1332021-12-0707 December 2021 11 Public Forms WO 20-0020, Response to NRC Regulatory Issue Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations2020-03-18018 March 2020 Response to NRC Regulatory Issue Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations ML20015A5192019-12-14014 December 2019 11-WC-2019-12 Public Forms ML20007E4422019-12-14014 December 2019 10-WC-2019-12 Post-Exam Comments ML19326A7722019-11-22022 November 2019 NRC Initial Operator Licensing Examination Approval 05000482/2019301 ML19011A3712019-01-10010 January 2019 Announcement of Generic Fundamentals Examination Section of the Written Operator Licensing Examination for 2019 WO 18-0014, Response to NRC Regulatory Issue Summary 2018-02, Preparation and Scheduling of Operator Licensing Examinations2018-04-16016 April 2018 Response to NRC Regulatory Issue Summary 2018-02, Preparation and Scheduling of Operator Licensing Examinations ML18086B0842018-02-16016 February 2018 Facility Cover Letter - Riv - March 2018 - GFE ML18009A9852018-01-0808 January 2018 Announcement of Generic Fundamentals Examination Section of the Written Operator Licensing Examination for 2018 ML17355A6512017-12-0404 December 2017 11 Post-Examination Comments ML17355A6452017-11-15015 November 2017 11 Draft Written Exam Comments ML18012A7472017-11-15015 November 2017 11 Public Forms ML17355A6412017-11-15015 November 2017 11 Draft Operating Test ML17355A6432017-11-15015 November 2017 11 Draft Outline Comments ML17355A6442017-11-15015 November 2017 11 Draft Outlines ML17355A6402017-11-15015 November 2017 11 Draft Operating Test Comments ML17355A6462017-11-15015 November 2017 11 Draft Written Exam ML17355A6482017-11-15015 November 2017 11 Final Operating Test ML17355A6492017-11-15015 November 2017 11 Final Outlines ML17355A6502017-11-15015 November 2017 11 Final Written Exam ML17013A5482017-01-13013 January 2017 Generic Fundamentals Section of the Written Operator Licensing Examination Scheduled for 2017 ML16336A7892016-12-0101 December 2016 Operating Company - Notification of NRC Initial Operator Licensing Examination 05000482/2017301 WO 16-0039, Form 536 Operator Licensing Examination and Scheduling Data in Response to RIS 2106-092016-07-19019 July 2016 Form 536 Operator Licensing Examination and Scheduling Data in Response to RIS 2106-09 ML16182A2852016-06-30030 June 2016 Arkansas, Units 1 and 2,South Texas Project, Units 1 and 2, Wolf Creek, Generic Fundamentals Examination Results for June 8, 2016 ML16027A3002015-12-29029 December 2015 2015-11-POST Exam Analysis ML15351A0282015-12-17017 December 2015 Generic Fundamentals Section of the Written Operator Licensing Examination Scheduled for 2016 ML16036A3882015-11-13013 November 2015 2015-11-PUBLIC Forms ML16036A3872015-11-13013 November 2015 2015-11-PROPOSED Written Exam Comments ML16036A3862015-11-13013 November 2015 2015-11-PROPOSED Outlines ML16036A3852015-11-13013 November 2015 2015-11 - Proposed Operating Test ML16036A3842015-11-13013 November 2015 2015-11-PROPOSED Operating Test Comments ML16036A3832015-11-13013 November 2015 2015-11-Final Outlines ML16036A3822015-11-13013 November 2015 2015-11-PROPOSED Outline Comments ML16036A3812015-11-13013 November 2015 2015-11-Proposed Written Exam ML16027A3192015-11-13013 November 2015 WC-2015-11 - Final Written Exams ML16027A3122015-11-13013 November 2015 2015-11 - Final Operating Test ML15317A1672015-11-12012 November 2015 2015-11-Examination Approval ML15181A2152015-06-30030 June 2015 Notification of NRC Initial Operator Licensing Examination 05000482/2015301 ML14345A3302014-12-11011 December 2014 Announcement of the Generic Fundamentals Section of the Written Operator Licensing Examinations for 2015 ML14181A3842014-06-30030 June 2014 Generic Fundamentals Examination Results June 2014 ML13248A5962013-07-26026 July 2013 WC-2013-07 Draft Operating Test ML13252A0302013-07-26026 July 2013 WC-2013-07 Public Forms ML13252A0292013-07-26026 July 2013 WC-2013-07 Draft Written Examination Comments ML13248A6002013-07-26026 July 2013 WC-2013-07 Draft Operating Test Comments ML13248A5982013-07-26026 July 2013 Wc 2013-07 Draft Outline Comments ML13248A5932013-07-26026 July 2013 WC-2013-07 Draft Outlines.Pdf ML13248A5942013-07-26026 July 2013 WC-2013-07 Final Outlines 2023-04-07
[Table view] Category:Part 55 Examination Related Material
MONTHYEARIR 05000482/20233012023-12-19019 December 2023 NRC Examination Report 05000482/2023301 ML23284A2392023-10-11011 October 2023 NRC Initial Operator Licensing Examination Approval 05000482/2023301 ML23097A0162023-04-0707 April 2023 Notification of NRC Initial Operator Licensing Examination 05000482/2023301 ML22020A1332021-12-0707 December 2021 11 Public Forms WO 20-0020, Response to NRC Regulatory Issue Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations2020-03-18018 March 2020 Response to NRC Regulatory Issue Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations ML20007E4422019-12-14014 December 2019 10-WC-2019-12 Post-Exam Comments ML20015A5192019-12-14014 December 2019 11-WC-2019-12 Public Forms ML19326A7722019-11-22022 November 2019 NRC Initial Operator Licensing Examination Approval 05000482/2019301 WO 18-0014, Response to NRC Regulatory Issue Summary 2018-02, Preparation and Scheduling of Operator Licensing Examinations2018-04-16016 April 2018 Response to NRC Regulatory Issue Summary 2018-02, Preparation and Scheduling of Operator Licensing Examinations ML18009A9852018-01-0808 January 2018 Announcement of Generic Fundamentals Examination Section of the Written Operator Licensing Examination for 2018 ML17355A6512017-12-0404 December 2017 11 Post-Examination Comments ML17355A6482017-11-15015 November 2017 11 Final Operating Test ML17355A6412017-11-15015 November 2017 11 Draft Operating Test ML17355A6402017-11-15015 November 2017 11 Draft Operating Test Comments ML17355A6432017-11-15015 November 2017 11 Draft Outline Comments ML17355A6502017-11-15015 November 2017 11 Final Written Exam ML17355A6462017-11-15015 November 2017 11 Draft Written Exam ML17355A6442017-11-15015 November 2017 11 Draft Outlines ML17355A6452017-11-15015 November 2017 11 Draft Written Exam Comments ML17355A6492017-11-15015 November 2017 11 Final Outlines ML18012A7472017-11-15015 November 2017 11 Public Forms ML16336A7892016-12-0101 December 2016 Operating Company - Notification of NRC Initial Operator Licensing Examination 05000482/2017301 WO 16-0039, Form 536 Operator Licensing Examination and Scheduling Data in Response to RIS 2106-092016-07-19019 July 2016 Form 536 Operator Licensing Examination and Scheduling Data in Response to RIS 2106-09 ML16182A2852016-06-30030 June 2016 Arkansas, Units 1 and 2,South Texas Project, Units 1 and 2, Wolf Creek, Generic Fundamentals Examination Results for June 8, 2016 ML16027A3002015-12-29029 December 2015 2015-11-POST Exam Analysis ML15351A0282015-12-17017 December 2015 Generic Fundamentals Section of the Written Operator Licensing Examination Scheduled for 2016 ML16036A3832015-11-13013 November 2015 2015-11-Final Outlines ML16027A3122015-11-13013 November 2015 2015-11 - Final Operating Test ML16027A3192015-11-13013 November 2015 WC-2015-11 - Final Written Exams ML16036A3812015-11-13013 November 2015 2015-11-Proposed Written Exam ML16036A3822015-11-13013 November 2015 2015-11-PROPOSED Outline Comments ML16036A3842015-11-13013 November 2015 2015-11-PROPOSED Operating Test Comments ML16036A3852015-11-13013 November 2015 2015-11 - Proposed Operating Test ML16036A3862015-11-13013 November 2015 2015-11-PROPOSED Outlines ML16036A3872015-11-13013 November 2015 2015-11-PROPOSED Written Exam Comments ML16036A3882015-11-13013 November 2015 2015-11-PUBLIC Forms ML15317A1672015-11-12012 November 2015 2015-11-Examination Approval ML15181A2152015-06-30030 June 2015 Notification of NRC Initial Operator Licensing Examination 05000482/2015301 ML14345A3302014-12-11011 December 2014 Announcement of the Generic Fundamentals Section of the Written Operator Licensing Examinations for 2015 ML14181A3842014-06-30030 June 2014 Generic Fundamentals Examination Results June 2014 ML13248A5982013-07-26026 July 2013 Wc 2013-07 Draft Outline Comments ML13252A0302013-07-26026 July 2013 WC-2013-07 Public Forms ML13252A0292013-07-26026 July 2013 WC-2013-07 Draft Written Examination Comments ML13248A6002013-07-26026 July 2013 WC-2013-07 Draft Operating Test Comments ML13248A5932013-07-26026 July 2013 WC-2013-07 Draft Outlines.Pdf ML13248A5942013-07-26026 July 2013 WC-2013-07 Final Outlines ML13248A5962013-07-26026 July 2013 WC-2013-07 Draft Operating Test ML13198A0112013-07-17017 July 2013 Operating Company - NRC Initial Operator Licensing Examination Approval ML1204704362012-01-18018 January 2012 WC-2012-01-Final OP Test ML1204704452012-01-18018 January 2012 2012-01-Final Outlines 2023-04-07
[Table view] |
Text
W0LF CREEK NUCLEAR OPERATING CORPORATION September 16, 2008 Terry J. Garrett Vice President Engineering ET 08-0044 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Docket No. 50-482: 10 CFR 50.55a Request 13R-06, Alternative to the Examination Requirements of ASME Section Xl for Class 1 Piping Welds Examined from the Inside of the Reactor Vessel Gentlemen:
Pursuant to 10 CFR 50.55a(a)(3)(i), Wolf Creek Nuclear Operating Corporation (WCNOC) hereby requests Nuclear Regulatory Commission (NRC) approval of the attached 10 CFR 50.55a Request for the Third Ten-Year Interval of WCNOC's Inservice Inspection (ISI) Program.
The attached 10 CFR 50.55a Request (13R-06) requests alternatives to the requirements of ASME Section Xl for Class 1 Piping Welds Examined from the Inside of the Reactor Vessel.
The proposed alternatives provide an acceptable level of quality and safety as required by 10 CFR 50.55a(a)(3)(i).
WCNOC requests approval of the attached 10 CFR 50.55a Request by July 31, 2009, to support task planning and establishing contracts and resources for Refueling Outage 17 (RF1 7).
RF17 is scheduled to begin on October 10, 2009.
Phone: (620) 364-8831 P.O. Box 411 / Burlington, KS 66839 /
An Equal Opportunity Employer M/F/HCNET
ET 08-0044 Page 2 of 2 There are no commitments contained within this letter. If you have any questions, please contact me at (620) 364-4084 or Mr. Richard Flannigan at (620) 364-4117.
Sincerely, Terry J. Garrett TJG/rlt
Attachment:
10 CFR 50.55a Request 13R-06 cc: E. E. Collins (NRC), w/a V. G. Gaddy (NRC), w/a B. K. Singal (NRC), w/a Senior Resident Inspector (NRC), w/a
Attachment to ET 08-0044 Wolf Creek Nuclear Operating Corporation 10 CFR 50.55a Request 13R-06, Alternative to the Examination Requirements of ASME Section XI for Class 1 Piping Welds Examined from the Inside of the Reactor Vessel
Attachment to ET 08-0044 Page 1 of 5 10 CFR 50.55a Request Number 13R-06 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)
Alternative Provides Acceptable Level of Quality and Safety
- 1. ASME Code Components Affected Class 1 Risk-Informed Inservice Inspection (RI-ISI) pressure retaining piping welds examined from the inside surface of the reactor pressure vessel (RPV) using procedures, personnel, and equipment qualified to ASME Section Xl, Appendix VIII, Supplement 2 or 10 criteria.
SAFE-END DISSIMILAR METAL WELDS CODE CATEGORY R-A (Formerly CODE CATEGORY B-F)
Code Item Description Weld No.
(Note 1 R1.20 Safe-end to Loop A RPV Outlet Nozzle RV-301-121-A R1.20 Safe-end to Loop A RPV Inlet Nozzle RV-302-121-A, Note 3 R1.20 Safe-end to Loop B RPV Outlet Nozzle RV-301-121I-B R1.20 Safe-end to Loop B RPV Inlet Nozzle RV-302-121-B, Note 3 R1.20 Safe-end to Loop C RPV Outlet Nozzle RV-301-121-C R1.20 Safe-end to Loop C RPV Inlet Nozzle RV-302-121-C, Note 3 R1.20 Safe-end to Loop D RPV Outlet Nozzle RV-301-121 -D R1.20 Safe-end to Loop D RPV Inlet Nozzle RV-302-121-D, Note 3 SAFE-END PIPING WELDS CODE CATEGORY R-A (Formerly CODE CATEGORY B-J)
Code Item Description Weld No.
(Note 2) (Note 3)
R1.20 Elbow to Loop A RPV Inlet Safe-End Weld BB-01-F102 R1.20 Pipe to Loop A RPV Outlet Safe-End Weld BB-01-F103 R1 .20 Elbow to Loop B RPV Inlet Safe-End Weld BB-01-F202 R1.20 Pipe to Loop B RPV Outlet Safe-End Weld BB-01-F203 R1.20 Elbow to Loop C RPV Inlet Safe-End Weld BB-01-F302 R1.20 Pipe to Loop C RPV Outlet Safe-End Weld BB-01-F303 R1.20 Elbow to Loop D RPV Inlet Safe-End Weld BB-01-F402 R1.20 Pipe to Loop D RPV Outlet Safe-End Weld BB-01-F403 Note 1: These welds were formerly Item B5.10.
Note 2: These welds were formerly Item B9.11.
Note 3: During the Second Ten-Year Interval of Wolf Creek Nuclear Operating Corporation's (WCNOC) ISI Program, these locations had surface conditions that limited the detection of axial flaws by Ultrasonic Testing (UT).
Page 1 of 5
Attachment to ET 08-0044 Page 2 of 5
- 2. Applicable Code Edition and Addenda ASME Boiler and Pressure Vessel Code, Section Xl 1998 Edition through 2000 Addenda.
- 3. Applicable Code Requirement Examination Category R-A, items R1.20 (formerly Code Categories B-F, B5.10 and B-J, B9.11 in the 1998 Edition through 2000 Addenda) specifies volumetric examination.
This volumetric examination is conducted in accordance with Appendix VIII, Supplements 10 and 2, with the alternative requirements of approved Code Cases N-695 and N-696.
- 4. Reason for Request Two alternatives are requested:
Requested Alternative A:
Alternative to the 0.125 inch root mean square error (RMSE) depth sizing requirement of Appendix VIII, Supplements 10 and 2, with the alternative requirements of Code Cases N-695 and N-696.
To date, although examination vendors have qualified for detection and length sizing on these welds, the examination vendors have not met the established RMSE of 0.125 inch for depth sizing.
Wolf Creek Nuclear Operating Corporation (WCNOC) proposes to use a contracted examination vendor that has demonstrated the ability to meet a depth sizing qualification requirement with an RMSE of 0.189 inch instead of the 0.125 inch required for Supplement 10 and Code Case N-695, and an RMSE of 0.245 inch instead of the 0.125 inch for Supplements 10 and 2 combined, as per Code Case N-696.
Requested Alternative B:
Alternative to supplement the ultrasonic test (UT) method with eddy current examinations when performing examinations of the Code specified pipe weld volumes from the inside diameter (ID) surface due to existing ID configurations.
The examination vendor for the Wolf Creek Generating Station (WCGS) reactor vessel nozzle examinations has been qualified for detection of circumferential flaws in accordance with Appendix VIII, Supplements 10 and 2 with the alternative requirements of Code Cases N-695 and N-696, as demonstrated through the Electric Power Research Institute (EPRI) Performance Demonstration Initiative (PDI)
Program, for nozzle-to-safe end and safe end-to-pipe welds examined from the ID surface. The vendor is similarly qualified for the detection of axial flaws provided the Page 2 of 5
Attachment to ET 08-0044 Page 3 of 5 surface is machined or ground smooth with no exposed root reinforcement or counter-bore. Surface roughness is present that will call into question the ultrasonic qualifications demonstrated for detection of axial flaws.
The examination vendor has developed an eddy current technique to augment the ultrasonic examination method and provide increased sensitivity at the ID surface.
The eddy current technique was first used in the VC Summer reactor vessel primary nozzle examinations of 2000. The procedure was refined after its first use in 2000 by applying it to the VC Summer hot leg dissimilar metal weld section removed from service. The removed section had a number of primary water stress corrosion cracking flaws along with non-relevant indications resulting from metallurgical interface and surface geometry. Using these actual flaws and geometric conditions in the removed section to refine the technique, the vendor developed a reliable flaw-screening criteria which allowed for the successful use of the procedure in the VC Summer 2002 and 2003 examinations.
Since that time, the technique has been successfully blind tested for the Swedish authority SQC Kvaleficeringscentrum AB (SQC NDT Qualification Center) under the program, "Qualification of Equipment, Procedure and Personnel for Detection, Characterization and Sizing of Defects in Areas in Nozzle to Safe End Welds at Ringhals Unit 3 and 4," Hakan Soderstrand 7-10-03. The important qualification parameters for Eddy Current in the SQC blind tests were as follows:
-Defect types: fatigue and stress corrosion cracks, surface initiated
-Tilt: +/-10 degrees; Skew: +/-10 degrees
-Detection target size: IDSCC 6mm(0.25 inch) long
-Flaw Location: within 10mm (113/32 inch)
-Length of the planer flaw within a 70% confidence interval:+/-9mm (3/8 inch)
-False call rate: less than or equal to 20% for the personnel qualification tests (Ref. SQC Qualification Report No. 019A/03)
This technique has also been used to supplement examination of portions of the relevant near-surface volumes during the last 15 domestic pressurized water reactor nozzle-to-pipe examinations conducted by the vendor.
- 5. Proposed Alternative and Basis for Use Requested Alternative A:
WCNOC proposes to use approved Code Cases N-695 and N-696 with a combined RMSE of 0.245 inch instead of the 0.125 inch specified for depth sizing in the Code Cases. In the event an indication is detected that requires depth sizing, the 0.120 inch difference between the required RMSE and the demonstrated RMSE (0.245 inch - 0.125 inch = 0.120 inch) will be added to the measured through-wall extent for comparison with applicable acceptance criteria. If the examination vendor demonstrates an improved depth sizing RMSE prior to the examination, the excess of that improved RMSE over the 0.125 inch RMSE requirement, if any, will be added to the measured value for comparison with applicable acceptance criteria.
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Attachment to ET 08-0044 Page 4 of55, '
The proposed alternative assures that the nozzle-to-safe end welds and the subject reactor coolant piping circumferential welds will be fully examined by procedures, personnel and equipment qualified by demonstration in all aspects except depth sizing. For depth sizing, the proposed addition of the difference between the qualified and demonstrated sizing tolerance to any flaw required to be sized compensates for the potential variation and provides an acceptable level of quality and safety in accordance with 10 CFR 50.55a(a)(3)(i).
Use of the combined qualification requirements for Supplements 2 and 10 prior to availability of Code Case N-696, and the :concept of adding the difference between the required RMSE value and the demonstrated RMSE value to the indication depth, were separately approved for the V.C. Summer Station by NRC letter dated February 3, 2004 (ML040340450).
Requested Alternative B:
In refueling outage RF14 of ISI Interval 2, WCNOC found that 12 of the 16 components identified above had inside surface conditions that did not allow coverage to be claimed for detection of axial flaws. Use of the below alternative was approved for the second ISI Interval by the NRC in a letter dated December 27, 2006 (ML063470082). WCNOC proposes to continue the use of this alternative in the third ISI Interval.
WCNOC proposes using surface geometry profiling software (profilometry) in conjunction with a focused immersion ultrasonic transducer positioned to permit accurate profile data across the examination volume to help the examiner confirm locations where the raw data indicates lack of transducer contact due to problematic surface geometry. Eddy current examination will be used to supplement ultrasonic examination for all nozzle-to-safe end and safe end-to-pipe welds. Profilometry will be used to determine the surface areas, and confirm those previously identified, where roughness may limit the ability of ultrasonic methods to be used effectively as qualified through performance demonstration.
The eddy current method will be used to assure any axial flaws at the ID surface volume that could be missed by ultrasonic examination due to potential surface roughness are detected. As a compliment to ultrasonic examinations for rough surface detection coverage, the following eddy current techniques will be utilized:
-Up to two plus point probes applied circumferentially on the pipe inside surface in scan increments of 0.080 inch circumferentially (for axial flaws) and 0.25 inch axially.
-Automated systems for data collection and analysis The target flaw size for the eddy current procedure is 0.28 inch long, well within the ASME Code linear flaw acceptance standards of 0.45 inches for austenitic material, and 0.625 inch for ferritic material (defined for the outside surface in the Code Tables). All eight nozzle-to-safe end welds and all eight safe end-to-pipe welds will be examined.
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Attachment to ET 08-0044 Page 5 of 5 The ultrasonic examinations supplemented by eddy current examinations and profilometry will be conducted to the maximum extent practical and are subject to third party review by the Authorized Nuclear Inservice Inspector.
Use of ultrasonic profilometry and eddy current examination with procedures and personnel qualified through the SQC blind tests to supplement Appendix VIII qualified ultrasonic procedures and personnel for the nozzle-to-safe end and safe end-to-pipe welds provides additional assurance that surface-breaking flaws that may be present would be detected in the presence of potential surface roughness, resulting in an equivalent or better level of quality and safety than that currently qualified to meet ASME Code requirements in accordance with 10 CFR 50.55a(a)(3)(i). The proposed alternative was approved for the Surry Power Station by NRC letter dated October 16, 2004 (ML042950444). The proposed alternative was also approved for the second ISI Interval of the Wolf Creek Generating Station by NRC letter dated December 27,2006 (ML063470082).
- 6. Duration of Proposed Alternative The proposed alternative is for the third inspection interval that begins on September 3, 2005 and ends on September 2, 2015.
- 7. Precedents Requested Alternative A:
The proposed alternative for the use of the combined qualification requirements for Supplements 10 and 2 prior to the availability of Code Case N-696, and the concept of adding the difference between the required RMSE value and the demonstrated value to the measured indication depth, were separately approved for the V.C.
Summer Station by NRC letter dated February 3, 2004, (ML040340450).
Requested Alternative B:
The proposed alternative was approved for profilometry and eddy current for the Surry Power Station by NRC letter dated October 16, 2004 (ML042950444). The proposed alternative was also approved for the second ISI Interval of the Wolf Creek Generating Station by NRC letter dated December 27,2006 (ML063470082).
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