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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML23277A2772023-10-11011 October 2023 Regulatory Audit Summary Concerning Review of Request Number CI3R-01 for Proposed Alternative Inspection Frequency for Containment Unbonded Post Tensioning System Components ML23075A0742023-03-16016 March 2023 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 25 Owners Activity Report ML23075A1632023-03-16016 March 2023 Inservice Inspection Program Fourth Interval, Third Period, Refueling Outage 25 Owners Activity Report ML22124A0062022-05-0505 May 2022 Review of the Spring 2021 Refueling Outage 24 Steam Generator Tube Inservice Inspection Report 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 ML21217A3342021-08-0505 August 2021 Inservice Inspection Program Fourth Interval, Second Period, Refueling Outage 24 Owner'S Activity Report ML21217A3352021-08-0505 August 2021 Containment Inservice Inspection Program Third Interval, First Period, Refueling Outage 24 Owner'S Activity Report ML20042C8922020-02-0404 February 2020 Containment Inservice Inspection Program Third Interval, First Period, Refueling Outage 23 Owner'S Activity Report ML20042C8962020-02-0404 February 2020 Lnservice Inspection Program Fourth Interval, Second Period, Refueling Outage 23 Owner'S Activity Report 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 ML18234A1322018-08-14014 August 2018 Submittal of Containment Inservice Inspection Program Second Interval, Third Period, Refueling Outage 22 Owner'S Activity Report ML18234A1312018-08-14014 August 2018 Lnservice Inspection Program Fourth Interval, First Period, Refueling Outage 22 Owner'S Activity Report ET 17-0008, Results of the Twentieth Steam Generator Tube Lnservice Inspection2017-05-0202 May 2017 Results of the Twentieth Steam Generator Tube Lnservice Inspection ET 17-0007, CFR 50.55a Request 14R-05 for the Fourth Inservice Inspection Program Interval2017-04-13013 April 2017 CFR 50.55a Request 14R-05 for the Fourth Inservice Inspection Program Interval ET 16-0005, Inservice Inspection Plan and 10 CFR 50.55a Requests 14R-01 and 14R-02 for the Fourth Inservice Inspection Program Interval2016-02-23023 February 2016 Inservice Inspection Plan and 10 CFR 50.55a Requests 14R-01 and 14R-02 for the Fourth Inservice Inspection Program Interval ET 15-0024, Results of the Nineteenth Steam Generator Tube Inservice Inspection2015-10-20020 October 2015 Results of the Nineteenth Steam Generator Tube Inservice Inspection ET 15-0022, Fourth Ten-Year Interval Submittal Snubber Program Plan and Inservice Testing Program Plan, WCOP-29, Revision 02015-09-0202 September 2015 Fourth Ten-Year Interval Submittal Snubber Program Plan and Inservice Testing Program Plan, WCOP-29, Revision 0 ML15217A0222015-07-28028 July 2015 Containment Inservice Inspection Program Second Interval, Second Period, Refueling Outage 20 Owner'S Activity Report ML15222A2512015-07-28028 July 2015 Inservice Inspection Program Third Interval, Third Period, Refueling Outage 20 Owner'S Activity Report ET 14-0018, 10CFR50.55a Request I3R-10 for Third Inservice Inspection Program Interval2014-06-26026 June 2014 10CFR50.55a Request I3R-10 for Third Inservice Inspection Program Interval ML14174B1232014-06-25025 June 2014 Review of 18th Steam Generator Tube Inspection Report ET 13-0030, Results of the Eighteenth Steam Generator Tube Inservice Inspection2013-09-30030 September 2013 Results of the Eighteenth Steam Generator Tube Inservice Inspection ML13199A2362013-07-11011 July 2013 Submittal of Containment Inservice Inspection Program Second Interval, Second Period, Refueling Outage 19 Owner'S Activity Report ET 11-0008, (WCGS) - Results of the Seventeenth Steam Generator Tube Inservice Inspection2011-10-19019 October 2011 (WCGS) - Results of the Seventeenth Steam Generator Tube Inservice Inspection ML11263A1492011-09-13013 September 2011 Containment Inservice Inspection Program Second Interval, First Period, Refueling Outage 18 Owner'S Activity Report ML11263A1482011-09-13013 September 2011 Inservice Inspection Program Third Interval, Second Period, Refueling Outage 18 Owner'S Activity Report ET 10-0012, Results of the Sixteenth Steam Generator Tube Inservice Inspection2010-04-0808 April 2010 Results of the Sixteenth Steam Generator Tube Inservice Inspection ML1004907522010-02-0909 February 2010 Submittal of Inservice Inspection Program Third Interval, Second Period, Refueling Outage 17 Owner'S Activity Report ML0822603672008-08-0606 August 2008 Containment Inservice Inspection Program First Interval, Third Period, Owner'S Activity Reports ML0822603412008-08-0606 August 2008 Inservice Inspection Program Third Interval, First Period, Refueling Outage 16 Owner'S Activity Report ML0704304622007-01-31031 January 2007 Containment Inservice Inspection Program First Interval, Third Period, Refueling Outage 15 Owner'S Activity Report RA-07-0012, Inservice Inspection Program Third Interval, First Period, Refueling Outage 15 Owner'S Activity Report2007-01-31031 January 2007 Inservice Inspection Program Third Interval, First Period, Refueling Outage 15 Owner'S Activity Report ML0614503192006-05-19019 May 2006 10 CFR 50.55a Request I3R-05, Installation and Examination of Full Structural Weld Overlays for Repairing/Mitigating Pressurizer Nozzle-to-Safe End Dissimilar Metal Welds and Adjacent Safe End-to Piping Stainless Steel Welds ET 06-0011, CFR 50.55a Requests I2R-34, I2R-35, I2R-36, I2R-37, and I2R-38 for the Second Inservice Inspection Program Interval2006-03-0202 March 2006 CFR 50.55a Requests I2R-34, I2R-35, I2R-36, I2R-37, and I2R-38 for the Second Inservice Inspection Program Interval ET 06-0010, Inservice Inspection Program Plan for the Third Ten-Year Interval and 10 CFR 50.55a Requests I3R-01, I3R-02, and I3R-042006-03-0202 March 2006 Inservice Inspection Program Plan for the Third Ten-Year Interval and 10 CFR 50.55a Requests I3R-01, I3R-02, and I3R-04 ET 06-0001, Revision to Technical Specification 5.5.8, Inservice Testing Program to Adopt Technical Specification Task Force Standard Technical Specification Change Traveler, TSTF-479, Revision 02006-02-0101 February 2006 Revision to Technical Specification 5.5.8, Inservice Testing Program to Adopt Technical Specification Task Force Standard Technical Specification Change Traveler, TSTF-479, Revision 0 ET 05-0004, Steam Generator Tube Plugging Report2005-05-0404 May 2005 Steam Generator Tube Plugging Report WM 04-0046, Results of the Twelfth Steam Generator Tube Inservice Inspection2004-10-27027 October 2004 Results of the Twelfth Steam Generator Tube Inservice Inspection WM 04-0008, Request to Extend the Second 10-year Inservice Inspection (ISI) Interval for Reactor Pressure Vessel Examinations, 10 CFR 50.55a Request 12R-282004-04-15015 April 2004 Request to Extend the Second 10-year Inservice Inspection (ISI) Interval for Reactor Pressure Vessel Examinations, 10 CFR 50.55a Request 12R-28 ET 03-0006, Implementation of the ASME Code for Operation and Maintenance of Nuclear Power Plants, Regarding the Check Valve Monitoring Program2003-08-26026 August 2003 Implementation of the ASME Code for Operation and Maintenance of Nuclear Power Plants, Regarding the Check Valve Monitoring Program ML0319704482003-07-0808 July 2003 Inservice Inspection Program Second Interval, Second Period Owner'S Activity Reports ET 02-0046, Results of Eleventh Steam Generator Tube Inservice Inspection2002-12-11011 December 2002 Results of Eleventh Steam Generator Tube Inservice Inspection ET 02-0049, Containment Inservice Inspection Program First Interval, First Period Owner'S Activity Reports2002-11-0404 November 2002 Containment Inservice Inspection Program First Interval, First Period Owner'S Activity Reports 2023-03-16
[Table view] 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
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W6..F.CREEK 'NUCLEAR OPERATING CORPORATION Gary B. Fader Vice President Technical Services NOV- 4-2002
-ET_ 02-0049 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington,- DC- 20555
References:
- 1) Letter ET 95-0112, dated October 31, 1995, from Robert C.
Hagan, WCNOC, to USNRC
- 2) Letter WO 95-0189, dated December 27, 1995, from Otto L.
Maynard, WCNOC, to USNRC
- 3) Letter dated February 9, 1996, from USNRC to Neil S. Cams, WCNOC
Subject:
'Docket 50-482: Containment Inservice Inspection Program First
- §- Interval, First Period Owner's Activity Reports Gentlemen:
In References land 2,-Wolf Creek Nuclear Operating Corporation (WCNOC) requested use of American Society of Mechanical Engineers -(ASME)- 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," in lieu of current ASME Section Xl reporting requirements.
In Reference 3,-the Nuclear Regulatory Commission (NRC) 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. Code Case N-532 requires that an Owner's Activity Report (Form OAR-1) be prepared and certified upon completion-of each refueling outage.
Each Form OAR-I prepared during an inspection period shall be submitted following the end of the inspection period. The enclosure provides the Owner's Activity Reports for the first period of the first interval of the WCNOC Containment -Inservice Inspection Program. Refueling Outage 11 occurred within this period. -The enclosed OAR-1 forms correspond to Refueling Outage 11 and the operational cycle since the completion-of Refueling Outage 10. The initial inspections of the Containment Inservice inspection Program commenced during this time.
Although Refueling Outage 10 occurred during the first period of the program, no containment inspections were scheduled or performed during Refueling Outage 10 and no Form OAR- was completed. A-separate Form OAR-l was prepared for subsections IWE and IWL of -the Containment Inservice Inspection Program.
RO Box 411 / Burlington, KS 66839 I Phone. (620) 364-8831 An Equal Opportunity Employer MiF/HCIVET - -
ET 02-0049 Page 2 of 2 No commitments are contained in this correspondence.---
If you have-any questions concerning this matter, please contact me-at (620) 364-4034, or Karl A. (Tony) Harris, Manager Regulatory Affairs, at (620) 364-4038.
Very truly yours, Gary B. Fader GBF/rIg Enclosure cc: J. N. Donohew (NRC), we D. N. Graves (NRC), wle E. W. Merschoff (NRC), wle Senior Resident Inspector (NRC), w/e --
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number WCRE-11. Il-PI-RF-1l Owner WolfCreek Nuclear Operating Corporation (Name and Address of Owner)
Plant Wolf Creek Generatine Station, 1550 Oxen Lane Northeast, Burlinton, Kansas 66839 (Name and Address of Plant)
Unit No 1 Commercial service date 9-3-85 Refueling outage no 11 (If applicable)
Current inspection interval Ist (Ist. 2nd. 3rd. 4th. other)
Current inspection period 1st N1st. 2nd. 3rd)
Edition and Addenda of Section XI applicable to the inspection plan 1998 edition with no addenda Date and revision of inspection plan WCRE-l 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 Xl.
Certificate of Authorization No N/A Expiration Date N/A (If antlicable)
Signed Dennis F Tougaw 'V," ./4'T/ Enmneer Date 5 J0 Z02-Os(ier or Owner's Designee, 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 of Johnston, Rhode Island have inspected the items described in this Owner's Activity Report, during the period September 9, 1998 to September 9, 2001 , 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, concerming 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 ansing from or connected with this inspection.
I i21 -
L . /Commissions KS#299 U
V *L*.-nspector's Signature t National Board, State, Province, and Endorsements Date 30 Tsr 02 7f (This form (E00127) may be obtained from the Order Dept , ASME, 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300 OAR-I I-PI-RF-II Page 1 of4
TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Completion of RF-11 (I-1, P-i)
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** AInterval Remarks E-A 826 275 33 33 Note
- This column is interpretedto representthe cumulative number of exams performedto date in this period.
- This column is interpretedto representthe cumulative percentage ofscheduled exams for the interval which have completed in thisperiodto date; thus,for thefirst period, the columns showing %forthe period and %16forthe interval will display the same values.
Note: 100% of the Accessible Surface Areas of Category E-A are required to be inspected each Inspection Penod per Table IWE-2500-1 OAR-I I1-PI-RF-I I Page 2 of 4
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 During Scheduled Section XI Category Number (IWA-3300) Examination or Test (Yes or No)
There were no components containing flaws or relevant conditions that required an evaluation to determine acceptability for continued service.
OAR-I II-PI-RF-l I Page3 of 4
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 Class MC components which required Repairs, Replacements, or Corrective Measures for Continued Service.
OAR-I II-PI-RF-II Page 4 of 4
FORM OAR-I OWNER'S ACTIVITY REPORT Report Number WCRE-1I. Il-Pl-RFI I t Owner WOLF CREEK NUCLEAR OPERATING CORPORATION / Post Office Box 411 - Burlington, KS 66839 (Name and Address of Owner)
Plant WOLF CREEK GENERATING STATION / Post Office Box 411 - Burli*gton. KS 66839 (Name and Address of Plant)
Unit No 1 Commercial service date 9/3/1985 Refueling outage no. 11 (If applicable)
Current inspection interval I`t interval for the Containment Inservice Inspection Program (Ist. 2nd. 3rd. 4th. other)
Current inspection period I"tperiod for the Containment Inservice Inspection Program (Ist. 2nd. 3rd)
Edition and Addenda of Section XI applicable to the inspection plan 1998 edition with no addenda Date and revision of inspection plan WCRE-11 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 N/A Expiration Date N/A (If annlicable)
Signed Dennis E. Tougaw YL44**l i/%40 Z~' Engineer Date 10/16/02 Own& or Owner's Desinee, 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 Factory Mutual Insurance Company of Johnston, Rhode Island have inspe acted the items described in this Owner's Activity Report, during the period September 3, 1998 to September 3, 2001 , 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 ansing from or connected this insption.
Commissions KS#299
- -1 I/ Inspector's ýignature National Board, State, Province, and Endorsements Date i-szTh This form (EOO 127) may be obtained from the Order Dept, ASME, 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300 OAR-I H-PI-RFI1 Page I of 4
TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Completion of RF-11 (I-1, P-1)
... TTotal Total Examinations .
Exaiination* . Examinations TEExaminaxions Exanations -Credited (%) to .
Ea -RequiredFor CeditedtforThis , .,Credited (%) "foio ----Date for the ,,_
_-ýCate'gory6 ',,-The 1nteir;4.'a Period -'- The Period, IneilRenrk L-A 12 650 50 Note I L-1B Note 2 Note 1: 100% of the Accessible Surface Areas of Category L-A are required to be inspected each Inspection Period. WCRE-1 1 divides these into six examination areas.
Note 2: In accordance with IOCFR50.55a, the expedited containment tendon inspections may be satisfied by the existing WCNOC Program for tendon inspections. Accordingly, containment tendon inspections were performed in accordance with the existing WCNOC Program for tendon inspections, as defined and implemented by Technical Specifications sections 3.6.1 and 5.5.6 rather than in accordance with Section XI Subsection IWL. The 10CFR50.55a(b)(2)(viii) limitations and modifications regarding documentation of tendon inspections results do not apply to the expedited containment tendon inspections satisfied by the existing WCNOC Program. However, no conditions were identified applicable to examination category L-B that would have required documentation in this report if the inspections were being performed in accordance with Subsection IWL.
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.g , i TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT RIPQUIRED EVALUATION FOR CONTINUED SERVICE Flaw Flaw or Relevant Examinat Item Item Description Characterization (IWA-3300) Condition Found ion Number During Scheduled Category Section XI Examination or Test (Yes or No)
L-A L1.1 1 1) Concrete surface on the East side of Small pieces of grout have from an earlier construction repair No the reactor building, at the top of the have started to separate and come off. No damage to the construction opening. rebar was noted. The separated pieces of grout/concrete are shallow, thickness of less than I Y2 inches. (WO 98-204041 001)
L-A L1.11 2) Concrete surface on Buttress B @ Concrete damage was noted on Buttress B @ horizontal Yes horizontal tendon 5BA. tendon 5BA. The damaged area is 2" deep x 1' wide x 2' long. (WO 00-219373-000)
L-A L1.11 3) Concrete surface on Buttress A at the Concrete damage was noted on Buttress A at the lightening Yes lightening rod anchor. rod anchor. The damaged area is 2" deep x 6" wide x 6"
_...........long. (WO 00-218264-000)
L-A L1.11 4) Concrete surface on Buttress B @ Concrete damage was noted on Buttress B @ horizontal Yes horizontal tendon 54CB. tendon 54CB. The damaged area is 2 1/2A" deep x 1' wide x 2' 6" long. (WO 00-219378-000)
L-A Lt.11 5) The grease caps of the vertical The vertical tendons grease caps in the Tendon Gallery were Yes tendons in the Tendon Gallery noted as having very small leaks. Numerous drops of grease (appx. 30) was noted on the caps and also evidence of minor leakage on floor. This leakage appears to have been there for a long period of time. (WO 00-219379-000)
L-A L1.11 6) Concrete surface at the construction Exposed rebar and missing concrete at the construction joint, Yes joint, elevation 2043'-10 1/2" @ AZ 118 elevation 2043'-10 1/2" @ AZ 118 Degrees, below the bottom Degrees, below the bottom of the of the Equipment Hatch. The rebar appears to be #7 and part Equipment Hatch. of the shear ties/stirrups provided in the concrete wall (C 0R2901). No cracks has been developed or observed in the area around the subject rebar. The missing concrete cover above the rebar is less than /2" thick. (WO 00-219372-000)
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TABLE 3 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES r 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 Class CC components which required repair, replacements, or corrective measures during the period of this OAR-1 OAR-I 1I-PI-RFII Page 4 of4