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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARRA-23-0230, Refuel 27 (C1 R27) Inservice Inspection (ISI) Report2023-09-25025 September 2023 Refuel 27 (C1 R27) Inservice Inspection (ISI) Report RA-22-0608, Refuel 25 (C2R25) Inservice Inspection (ISI) Report2023-01-25025 January 2023 Refuel 25 (C2R25) Inservice Inspection (ISI) Report RA-22-0021, Refuel 26 (C1 R26) Inservice Inspection (ISI) Report2022-01-26026 January 2022 Refuel 26 (C1 R26) Inservice Inspection (ISI) Report RA-21-0223, Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report2021-08-0202 August 2021 Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report RA-19-0391, Refuel 23 (C2R23) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report2019-12-19019 December 2019 Refuel 23 (C2R23) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report RA-19-0092, Refuel 24 (C1R24) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report2019-03-11011 March 2019 Refuel 24 (C1R24) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report CNS-18-032, Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report2018-07-12012 July 2018 Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report CNS-17-061, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information2017-12-21021 December 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information CNS-17-002, End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report2017-01-0606 January 2017 End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report CNS-16-067, ASME OM Code In-Service Testing Program Document2016-08-31031 August 2016 ASME OM Code In-Service Testing Program Document CNS-16-042, Snubber Program Plan for the Fourth Ten-Year Inservice Testing Interval2016-06-13013 June 2016 Snubber Program Plan for the Fourth Ten-Year Inservice Testing Interval CNS-16-020, Inservice Inspection Report for End of Cycle 22 Refueling Outage2016-03-18018 March 2016 Inservice Inspection Report for End of Cycle 22 Refueling Outage ML15280A3422015-10-0505 October 2015 Fourth Inservice Inspection Interval Steam Generator Tube Plan ML15238A8832015-08-19019 August 2015 Fourth Inservice Inspection Interval Plan and Inservice Inspection Interval Pressure Test Plan CNS-15-074, CISI-1462.10.0040, Revision 0, Fourth Interval Inservice Inspection Outage Schedule, Quality Assurance Program Related2015-08-13013 August 2015 CISI-1462.10.0040, Revision 0, Fourth Interval Inservice Inspection Outage Schedule, Quality Assurance Program Related ML15238A9002015-08-12012 August 2015 CISI-1462.10.0040, Revision 0, Fourth Interval Inservice Inspection Outage Schedule, Quality Assurance Program Related ML15238A8982015-08-12012 August 2015 CISI-1462.10.0040-ISI, Revision 1, Fourth Interval Inservice Inspection Plan CNS-15-061, Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 20 Refueling Outage2015-07-0606 July 2015 Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 20 Refueling Outage ML15238A8962015-06-23023 June 2015 Fourth Inspection Interval Inservice Inspection Pressure Test Plan CNS-15-047, Steam Generator Inservice Inspection Summary Report for End of Cycle 21 Refueling Outage, Response to NRC Requests for Additional Information (Rais)2015-05-15015 May 2015 Steam Generator Inservice Inspection Summary Report for End of Cycle 21 Refueling Outage, Response to NRC Requests for Additional Information (Rais) CNS-15-022, Request to Use a Portion of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section Xl, for Inservice Inspection Activities2015-03-16016 March 2015 Request to Use a Portion of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section Xl, for Inservice Inspection Activities CNS-14-105, Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 21 Refueling Outage2014-09-25025 September 2014 Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 21 Refueling Outage CNS-14-001, Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 19 Refueling Outage2014-01-13013 January 2014 Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 19 Refueling Outage ML13085A0252013-03-21021 March 2013 Inservice Inspection Report for End of Cycle 20 Refueling Outage ML12195A3462012-07-10010 July 2012 Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 18 Refueling Outage ML12125A2972012-05-0303 May 2012 Proposed Alternative Request Number 11-CN-001 for the Third Ten-Year Inservice Inspection Interval Response to NRC Request for Additional Information ML1109806012011-04-0505 April 2011 Steam Generator (SG) Tube Inspection Report for End of Cycle 17 Refueling Outage Pursuant to Technical Specification (TS) 5.6.8 ML1102003222011-01-19019 January 2011 Inservice Inspection Report and Steam Generator In-Service Inspection Summary Report for End of Cycle 17 Refueling Outage ML0920104982009-07-14014 July 2009 Inservice Inspection Report and Steam Generator In-Service Inspection Summary Report for End of Cycle 16 Refueling Outage ML0927500082008-09-11011 September 2008 Inservice Inspection Report and Steam Generator In-service Inspection Summary Report for End of Cycle 17 Refueling Outage ML0805001792008-02-11011 February 2008 Inservice Inspection Report and Steam Generator In-service Inspection Summary Report for End of Cycle 15 Refueling Outage ML0732001122007-11-0808 November 2007 Request for Relief Number 07-GO-001 Alloy 600 Pressurizer Weld Overlays - Submittal of Committed Information ML0721202212007-07-30030 July 2007 Notification of Inspection and Request for Information ML0713503782007-05-0707 May 2007 Submittal of Steam Generator Inservice Inspection Documentation for Third Ten-Year Interval ML0709502752007-03-28028 March 2007 Inservice Inspection Report for End of Cycle 16 Refueling Outage ML0623403632006-08-15015 August 2006 Inservice Testing (IST) Program for Pumps and Valves - Third Ten-Year Interval Plan ML0620603112006-07-18018 July 2006 Inservice Inspection Reports for End of Cycle 14 Refueling Outage ML0607403192006-03-0606 March 2006 Submittal of Third Ten-Year Interval Inservice Inspection Plan and Inservice Inspection Pressure Test Plan ML0603901542006-02-0606 February 2006 Notification of Inspection and Request for Information ML0525905642005-09-0808 September 2005 Request for Relief Number 05-CN-004 Limited Weld Examinations During End-of-Cycle 15 Refueling Outage ML0525004942005-08-30030 August 2005 Inservice Inspection Report and Steam Generator Outage Summary Report for End-of-Cycle 15 Refueling Outage ML0518601322005-06-16016 June 2005 Submittal of Third Ten-Year Interval Inservice Inspection Plan and Inservice Inspection Pressure Test Plan ML0514002732005-05-11011 May 2005 Request for Relief Number 05-CN-003, Limited Volumetric Inspection Coverages During End-of-Cycle 12 and End-of-Cycle 13 Refueling Outages ML0508105992005-03-11011 March 2005 Duke Requests NRC Approval of an Alternative to the Requirements of the 1998 Edition Through the 2000 Addenda of the Pressure Vessel Code, Section XI for the Listed Inservice Inspection Intervals ML0502604532005-01-17017 January 2005 Inservice Inspection Report for End of Cycle 13 Refueling Outage ML0430103872004-10-19019 October 2004 Second Ten Year Inservice Inspection Interval Steam Generator C Hot Leg Nozzle Welds ML0414901162004-05-18018 May 2004 Request for Relief from Pressure Requirement at Certain Class 1 Inservice Inspection Pressure Test Boundaries ML0408502452004-03-17017 March 2004 Inservice Inspection Report for End-of- Cycle 14 Refueling Outage ML0317605962003-06-18018 June 2003 Inservice Inspection Report & Steam Generator Outage Summary Report for End of Cycle 12 Refueling Outage ML0313405102003-05-0707 May 2003 Relief, Request for Relief Number 02-002, Revision 1 Re Limited Weld Examinations for End of Cycle 13 Refueling Outage 2023-09-25
[Table view] Category:Letter type:CNS
MONTHYEARCNS-18-008, License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing2018-07-19019 July 2018 License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing CNS-18-032, Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report2018-07-12012 July 2018 Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report CNS-18-031, Notice of Enforcement Discretion (NOED) Request2018-06-18018 June 2018 Notice of Enforcement Discretion (NOED) Request CNS-18-028, 2017 Annual Radiological Environmental Operating Report2018-05-14014 May 2018 2017 Annual Radiological Environmental Operating Report CNS-18-026, Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report2018-05-10010 May 2018 Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report CNS-18-023, (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System2018-05-0808 May 2018 (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System CNS-18-025, Submittal of 2017 Annual Radioactive Effluent Release Report2018-04-30030 April 2018 Submittal of 2017 Annual Radioactive Effluent Release Report CNS-18-022, Submittal of Emergency Plan Implementing Procedure2018-04-12012 April 2018 Submittal of Emergency Plan Implementing Procedure CNS-18-017, Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-22018-03-24024 March 2018 Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-2 CNS-18-015, Commitment Change Evaluation Report for 20172018-03-22022 March 2018 Commitment Change Evaluation Report for 2017 CNS-18-005, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-02-0808 February 2018 Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes CNS-18-006, Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days2018-01-23023 January 2018 Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days CNS-17-058, Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to 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 Fukus2017-12-28028 December 2017 Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to 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 Fukushi CNS-17-061, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information2017-12-21021 December 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information CNS-17-056, Catawba Nuclear Station Units 1 and 2, Resubmittal of Emergency Plan, Revision 17-22017-11-0101 November 2017 Catawba Nuclear Station Units 1 and 2, Resubmittal of Emergency Plan, Revision 17-2 CNS-17-056, Catawba Nuclear Station Units 1 and 2, Submittal of Emergency Plan, Revision 17-22017-10-23023 October 2017 Catawba Nuclear Station Units 1 and 2, Submittal of Emergency Plan, Revision 17-2 CNS-17-053, Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement2017-10-12012 October 2017 Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement CNS-17-048, Supplemental Response to Preliminary White Finding, Apparent Violations, and NRC Inspection Report 05000414/2017012; Enforcement Action 17-1222017-09-29029 September 2017 Supplemental Response to Preliminary White Finding, Apparent Violations, and NRC Inspection Report 05000414/2017012; Enforcement Action 17-122 CNS-17-049, Submittal of Ufsar/Selected Licensee Commitment Changes Manual2017-09-28028 September 2017 Submittal of Ufsar/Selected Licensee Commitment Changes Manual CNS-17-051, Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask2017-09-28028 September 2017 Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask CNS-17-014, License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time2017-09-14014 September 2017 License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time CNS-17-050, ISFSI - Registration of Spent Fuel Storage Cask2017-09-12012 September 2017 ISFSI - Registration of Spent Fuel Storage Cask CNS-17-047, Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding2017-08-29029 August 2017 Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding CNS-17-041, ISFSI - Registration of Spent Fuel Storage Cask2017-08-15015 August 2017 ISFSI - Registration of Spent Fuel Storage Cask CNS-17-040, Withdrawal of Inservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for Testing Chemical and Volume Control Pump2017-08-14014 August 2017 Withdrawal of Inservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for Testing Chemical and Volume Control Pump CNS-17-039, Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump2017-07-27027 July 2017 Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump CNS-17-036, Mid-Cycle Power Uprate Ascension Startup Report2017-06-29029 June 2017 Mid-Cycle Power Uprate Ascension Startup Report CNS-17-033, Technical Specification Bases Changes2017-06-27027 June 2017 Technical Specification Bases Changes CNS-17-029, Flood Hazard Mitigating Strategies Assessment Report Submittal2017-06-20020 June 2017 Flood Hazard Mitigating Strategies Assessment Report Submittal CNS-17-030, Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core2017-06-20020 June 2017 Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core CNS-17-024, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations2017-05-25025 May 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations CNS-17-031, Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report2017-05-24024 May 2017 Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report CNS-17-027, Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report2017-05-10010 May 2017 Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report CNS-17-015, Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report2017-04-27027 April 2017 Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report CNS-17-021, Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days2017-04-20020 April 2017 Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days CNS-17-020, Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing2017-04-11011 April 2017 Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing CNS-17-008, Commitment Change Evaluation Report for 20162017-03-16016 March 2017 Commitment Change Evaluation Report for 2016 CNS-17-004, Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants.2017-01-26026 January 2017 Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants. CNS-17-002, End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report2017-01-0606 January 2017 End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report CNS-16-080, Submittal of Emergency Plan Implementing Procedure2016-12-20020 December 2016 Submittal of Emergency Plan Implementing Procedure CNS-16-077, Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-12-0808 December 2016 Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident CNS-16-066, Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task..2016-10-20020 October 2016 Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task.. CNS-16-069, Submittal of Emergency Plan, Revision 16-22016-10-10010 October 2016 Submittal of Emergency Plan, Revision 16-2 CNS-16-068, Submittal of Emergency Plan Implementing Procedure Revisions2016-10-10010 October 2016 Submittal of Emergency Plan Implementing Procedure Revisions CNS-16-064, License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 242016-09-0707 September 2016 License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 24 CNS-16-061, Submittal of Design Basis Specification for the Plant Fire Protection Revision 252016-08-12012 August 2016 Submittal of Design Basis Specification for the Plant Fire Protection Revision 25 CNS-16-051, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) an2016-08-0202 August 2016 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) and CNS-16-049, ISFSI Registration of Spent Fuel Storage Cask2016-07-14014 July 2016 ISFSI Registration of Spent Fuel Storage Cask CNS-16-056, Transmittal of Emergency Plan Implementing Procedures, Including Revision 034 to RP/0/A/5000/006A and Revision 038 to RP/0/A/5000/00682016-07-13013 July 2016 Transmittal of Emergency Plan Implementing Procedures, Including Revision 034 to RP/0/A/5000/006A and Revision 038 to RP/0/A/5000/0068 CNS-16-050, Unit 2 - Ufsar/Selected Licensee Commitment Changes2016-07-12012 July 2016 Unit 2 - Ufsar/Selected Licensee Commitment Changes 2018-07-19
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--t1f~DUKE Tom Simril Vice President
~JENERGY(i Catawba Nuclear Station Duke Energy CN01 VP I 4800 Concord Road York, SC 29745 o: 803.701.3340 f: 803.701.3221 tom.simril@duke-energy.com CNS-18-032 July 12, 2018 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001
Subject:
Duke Energy Carolinas, LLC (Duke Energy)
Catawba Nuclear Station, Unit 2 Docket Number 50-414 Catawba Unit 2 Refueling Outage 22 (C2R22) lnservice Inspection Report Summary Report In accordance with Section XI of the ASME Code, please find enclosed the subject 90-day Owner's Activity Report, Form OAR-1, which provide the results of Catawba's C2R22 lnservice Inspection.
There are no regulatory commitments contained in this letter or its enclosure.
If you have any questions concerning this, please call Dustin Yang at (803) 701-3084.
Sincerely, Tom Simril Vice President, Catawba Nuclear Station
Enclosure:
Owner's Activity Report for Refueling Outage C2R22 www.duke-energy.com
Document Control Desk Page 2 July 12, 2018 xc (with attachments):
C. Haney Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, GA 30303-1257 J. D. Austin Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station M. Mahoney (addressee only)
Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mailstop 0-8H4A Rockville, MD 20852
CASE N-532-5 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number Owner's Activity Report for Refueling Outage C2R22 Plant _______ C_a_ta_w_b_a_N_uc_lear Station, 4800 Concord Road~,Y_or_k~,_s_c__2_9_7_4_5_ _ _ _ _ __
Unit No. 2 Commercial service date 08/19/1986 Refueling outage no. C2R22 (if applicable) _---:....c.;_'-'-'--'-"-"---
Current inspection interval Fourth Inspection Interval (18_!1_Third lns~ction Interval (Containment ISi)
(1st, 2nd, 3rd, 4th, other)
Current inspection period First Inspection Period (ISi and Containment ISi)
(1st, 2nd, 3rd)
Edition and Addenda of Section XI applicable to the inspection plans ASME Section XI 2007 Edition through 2008 Addenda Date and revision of inspection plans See Attachment - Page 2 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Same as above The following Code Cases are permitted by the ISi and Pressure Test Plan:
4th Interval: N-513-3, N-532-5, N-586-1, N-600, N-613-1, N-639, N-643-2, N-648-1, N-651, N-705, N-706-1, N-712, N-716-1, N-722-1, N-729-4, N-731, Code Cases used for inspection N-735, N-747, N-751, N-765, N-770-2, N-771, N-776, N-786-1, N-798, and evaluation: - - ~ - -N-805, N-800, ~--~ N-823,
-~- - - - -&-N-845 N-825, ------------*****-***------
(if applicable)
CERTIFICATE OF CONFORMANCE l certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of C2R22 conform to the requirements of Section XI.
(refueling outage number)
Signed Austin Keller, ISi Program Owner Date G, / 13 / \ f!,
I 1 CERTIFICATE OF ll"ISERVICE 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 South Carolina and employed by Hartford Steam Boiler Inspection and Insurance Company of Connecticut have inspected the items described in this Owner's Activity Report, 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 repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
---~-~-~~---l)~c,s~r_,p,J~M---'<11...,_,//.'""",_I-_ _ _ _ _ Commissions __,/.,....,'.5i"--'-7-=-'/.-=~--rZ='4_..__/l!.--"""-A-'='fI=----
1nspector's Signature National Board, State, Province, and Endorsements Date !, .J .a.§ j 201 g 1 of 4
CASE N-532-5 ATTACHMENT CATAWBA UNIT 2 END OF CYCLE 22 INSERVICE INSPECTION REPORT Date and Revision of lnservice Inspection Plans:
I. Fourth Interval lnservice Inspection Plans
- 1. The following documents comprise the Catawba Nuclear Station 4th Interval lnservice Inspection Plan for Unit 2 (Class 1, 2, and 3 Components):
- a. Catawba Nuclear Station Unit 1 and Unit 2 - Fourth Interval lnservice Inspection Plan, Document #CISl-1462.10-0040-ISI PLAN, Rev. 3, dated 06/13/2018.
- b. Fourth Interval lnservice Inspection Outage Schedule Catawba Nuclear Station Unit 2, Document #CISl-1462.10-0040-UNIT 2, Rev. 0, dated 08/13/2015 including the following addenda:
- i. CISl-1462.10-0040-4CNS2-001 through CISl-1462.10-0040-4CNS2-006
- 2. The following document comprises the Catawba Nuclear Station 4th Interval lnservice Inspection Pressure Test Plan for Unit 2:
- a. Catawba Nuclear Station Units 1 and 2 Fourth Inspection Interval lnservice Inspection Pressure Test Plan, Document #CISl-1462.20.0040-PTPlan, Rev. 1, dated 07/13/2017.
II. Containment lnservice Inspection Plan
- 1. The following document comprises the Catawba Nuclear Station 3rd Interval Containment lnservice Inspection Plan for Unit 2 (Class MC):
- a. Catawba Nuclear Station Units 1 and 2 - Third Interval Containment lnservice Inspection Plan, Document #CN-ISIC3-1042-0001, Rev. 6, dated 05/08/2018.
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CASE N-532-5 TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Description Evaluation Description Item Number During C2R22, thermal sleeve upper flange wear measurement data collected by Framatome via WO# 20170073. Of the 57 thermal sleeve wear measurements, 1 (penetration #18) initially exceeded separation criteria. However, an Augmented Inspection to address wear phenomena evaluation was performed by Westinghouse in associated with RVCH thermal sleeves on Westinghouse AUG/ G20.1 letter LTR-RIDA-18-100 that relaxed the yield Units per Technical Bulletin TB-07-2, Rev. 3 and separation criteria provided in industry guidance document PWROG-16003-P Rev. 1 by reducing industry-enveloping conservatisms based upon site-specific details such as measurement accuracy and site-specific wear rates. Reference NCR #02193730.
VT-2 examination revealed boric acid residue on the 2C Steam Generator Hot and Cold Leg B-P / B15.10 ISi Class A Bolted Connection - IWA-5241(f) Primary Manway Covers. Engineering Evaluation found to be acceptable. Reference NCR
- 02192806.
VT-2 examination revealed boric acid residue on seal table mechanical fittings, 2C Reactor Coolant Pump Main Flange Bolting, and lncore B-P / B15.10 ISi Pressure Test Zone 2NC-001 L-A Instrumentation Tubing. Engineering Evaluation found to be acceptable. Reference NCRs
- 02197471 and #02197466.
VT-2 examination revealed boric acid residue on C-H/C7.10 ISi Pressure Test Zone 2FW-001 L-B valve 2NS-20A. Engineering Evaluation found to be acceptable. Reference NCR #02140492.
VT-2 examination revealed boric acid residue on C-H / C7.10 ISi Pressure Test Zone 2ND-001 L-B valve 2ND-3. Engineering Evaluation found to be acceptable. Reference NCR #02192166.
VT-2 examination revealed boric acid residue on NI piping upstream of valve 2Nl-18. Engineering C-H / C7.10 ISi Pressure Test Zone 2Nl-010L-B Evaluation found to be acceptable. Reference NCR #02195381.
VT-2 examination revealed boric acid residue C-H / C7.10 ISi Pressure Test Zone 2NV-005L-B valve 2NV-333. Engineering Evaluation found to be acceptable. Reference NCR #02187670.
VT-2 examination revealed boric acid residue on valve 2KF-6 and flow element 2KF-FE-5100.
D-B / 02.10 ISi Pressure Test Zone 2KF-001 L-C Engineering Evaluation found to be acceptable.
Reference NCR #02186336.
VT-2 examination revealed boric acid residue on D-B / 02.10 ISi Pressure Test Zone 2KF-002L-C valve 2KF-20. Engineering Evaluation found to be acceptable. Reference NCR #02175038.
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CASE N-532-5 TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Repair/ Replacement Code Class
\ Item Description I Description of Work I Date Completed I Plan Number None 4 of 4