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==Subject:==
==Subject:==
Duke Energy Carolinas, LLC (Duke Energy) McGuire Nuclear Station, Unit 1 Docket No. 50-369 End of Cycle 24 lnservice Inspection Report Steven D. Capps Vice President McGuire Nuclear Station Duke Energy MGOl VP I 12700 Hagers Ferry Road Huntersville, NC 28078 O: 980.875.4805 f: 980.875.4809 Steven. Ca pps@duke-energy.com Pursuant to the reporting requirements of American Society of Mechanical Engineers (ASME) Section XI, as amended by ASME Code Case N-532-5, attached is the subject report. Should you have any questions or require additional information, please contact P.T. Vu of Regulatory Affairs at (980) 875-4302. Sincerely, JMJt,,I Steven D. Capps Attachment www.duke-energy.com U.S. Nuclear Regulatory Commission July 14, 2016 Page 2 xc: C. Haney, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 G.E. Miller, Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8G9A Rockville, MD 20852-2738 V. Sreenivas, Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8G9A Rockville, MD 20852-2738 J. Zeiler NRC Senior Resident Inspector McGuire Nuclear Station A. Hutto NRC Senior Resident Inspector McGuire Nuclear Station   
Duke Energy Carolinas, LLC (Duke Energy) McGuire Nuclear Station, Unit 1 Docket No. 50-369 End of Cycle 24 lnservice Inspection Report Steven D. Capps Vice President McGuire Nuclear Station Duke Energy MGOl VP I 12700 Hagers Ferry Road Huntersville, NC 28078 O: 980.875.4805 f: 980.875.4809 Steven. Ca pps@duke-energy.com Pursuant to the reporting requirements of American Society of Mechanical Engineers (ASME) Section XI, as amended by ASME Code Case N-532-5, attached is the subject report. Should you have any questions or require additional information, please contact P.T. Vu of Regulatory Affairs at (980) 875-4302. Sincerely, JMJt,,I Steven D. Capps Attachment www.duke-energy.com U.S. Nuclear Regulatory Commission July 14, 2016 Page 2 xc: C. Haney, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 G.E. Miller, Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8G9A Rockville, MD 20852-2738 V. Sreenivas, Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8G9A Rockville, MD 20852-2738 J. Zeiler NRC Senior Resident Inspector McGuire Nuclear Station A. Hutto NRC Senior Resident Inspector McGuire Nuclear Station   
... CASE N-532-5 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number ________ _______ _ Plant McGuire Nuclear Station, 12700 Hagers Ferry Rd, Huntersville, NC 28078-9340 Unit No. Commercial service date --------Refueling outage no. 1 EOC24 12/01/1981 (if applicable) Current inspection interval (1s1. 2nd, 3rd, 41h. olher) Current inspection period ISi-2nd, Containment-1st (1st, 2nd, 3rd) Edition and Addenda of Section XI applicable to the inspection plans 2007 with 2008 addenda Date and revision of inspection plans See attachment ----------------------------Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Same Code Cases used: The following Code Cases are permitted by the ISi Plans: N-513-3, N-526, N-532-5, N-566-2, N-586-1, N-613-1, N-639, N-643-2, N-648-1, N-663, N-706-1, N-716, N-722-1, N-729-1, N-731, N-735, N-770-1 (if applicable) CERTIFICATE OF CONFORMANCE I 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 1 EOC24 conform to the requirements of Section XI. (refueling outage number) Date Signed ----------------------------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 North Carolina and employed by HSB Global Standards of CT 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 perfonned 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 c nnected with this inspectio -CommissionsN;2. i / t 1.S.AC!./S Ol: National Board, State, and Endorsements 7-7-/0 ,v.Jr,,tJS Page 1 of4 I' _) CASE N-532-5 Attachment McGuire Unit 1 End of Cycle 24 lnservice Inspection Report The McGuire Nuclear Station Unit 1 Fourth Ten Year lnservice Inspection (ISi) Plan complies with 1 OCFR50.55a(g), which implements, by reference, the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, 2007 Edition with 2008 Addenda. This summary report is being submitted pursuant to the reporting requirements of ASME Section XI as amended by ASME Code Case N-532-5, "Repair/Replacement Activity Documentation Requirements and lnservice Inspection Summary Report Preparation and Submission Section XI, Division 1". Contained within this summary report are the form OAR-1 (Owner's Activity Report) and Tables 1 and 2 of Code Case N-532-5 for McGuire Nuclear Station during cycle 24 and Refueling Outage 24 (1EOC24). 1 EOC24 is the first outage of the second ISi period in the fourth inspection interval. 1 EOC24 is the second outage of the first Containment period in the third inspection interval. This report includes all Repair/Replacement activities from November 17, 2014 through April 16, 2016, cycle 24. Pressure testing performed on-line prior to 9/1 /2015 are in the 1st period. Date and Revision of lnservice Inspection Plans: Fourth Interval lnservice Inspection Plans The following document comprises the McGuire Nuclear Station 4th Interval lnservice Inspection Plan for Unit 1 (Class 1, 2, and 3 Components): "Fourth Interval lnservice Inspection Plan, McGuire Nuclear Station Unit 1 and Unit 2, General Requirements" -Document "MISl-1462.10-0040-GEN REQ UNIT 1 SECOND AND THIRD PERIODS AND UNIT 2", Rev 1, dated 05/28/2015. The following document comprises the McGuire Nuclear Station 4th Interval lnservice Inspection Pressure Test Plan for Unit 1: "McGuire Nuclear Station -Fourth Interval lnservice Inspection Plan -Pressure Test Plan", Document MISl-1462.20-0040-PTPLAN, Rev 1, dated 06/18/2015. Containment lnservice Inspection Plan The following document comprises the McGuire Nuclear Station 3rd Interval Containment lnservice Inspection Plan for Unit 1 (Class MC): "McGuire Nuclear Station -Third Interval Containment lnservice Inspection Plan -Containment -Units 1 & 2", Document #MC-ISIC3-1042-0001, Rev. 3, dated 10/21/2015. Page Z of4 CASE N-532-5 McGuire Nuclear Unit 1 Form OAR-1 Owner's Activity Report Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service Examination Category and Item Description Evaluation Description Item Number Westinghouse performed an analytical evaluation of the flaws and documented the justification for continued operation under Report B-8 I B2.11 Flaws in excess of the ASME XI code allowable were (Reference NCR 01596672). discovered in the Pressurizer lower head to shell weld Dunng 1 EOC24 the Pressurizer lower head to during 1EOC17 and 1EOC24. shell weld was inspected again. There was no change in the size/number of flaws so the current Westinghouse analysis justification for continued operations, for the life of the plant, remains valid. Reference NCR 02015606. C-H I C7.10 Boric acid residue found on bolted connection for valve Item was evaluated by Engineering in NCR 1ND-18, during 1 EOC24 02012421and found to be acceptable. This is NOT considered an analytical evaluation. C-H I C7.10 Dry Boric acid was found on bolted connection for valves Item was evaluated by Engineering in NCR 1 ND35 and 1 FW-27A (on-line, 1st period inspection) 01699924 and found to be acceptable. This is NOT considered an analvticai evaluation. C-H I C7.10 Inactive boron leak found on bolted connection for valve Item was evaluated by Engineering in NCR 1 NV-290 (on-line, 1st period inspection) 01906973 and found to be acceptable. This is NOT considered an analvtical evaluation. D-B I 02.10 inactive boron leak found on bolted connection for valve item was evaluated by Engineering in NCR 1KF-24 (on-line, 1st period inspection) 01906844 and found to be acceptable. This is NOT considered an analytical evaluation. Thickness readings below 87.5% of nominal wall were Item was evaluated by Service Water Corrosion R-A I R.17 observed during Inspection of wall thickness grid at weld program manager in NCR 02015846 and found 1RN233*6 and 1RN245-8 during 1 EOC24 to be acceptable. This is NOT considered an analvtical evaluation. Thickness readings below 87.5% of nominal wall were Item was evaluated by Service Water Corrosion R-A I R.17 observed during inspection of wall thickness grid at weld program manager in NCR 02014622 and found 1 RN264-1, during 1 EOC24 to be acceptable. This is NOT considered an analvtical evaluation. Thickness readings below 87.5% of nominal wall were Item was evaluated by Service Water Corrosion R-A/ R.17 observed during inspection of wall thickness grid at weld program manager in NCR 02014621 and found 1RN1F300, during 1EOC24 to be acceptable. This is NOT considered an analvtical evaluation. Thickness readings below 87.5% of nominal wall were Item was evaluated by Service Water Corrosion R-A I R.17 observed during inspection of wall thickness grid at weld program manager in NCR 02014605 and found 1 RN1 F279, during 1 EOC24 to be acceptable. This is NOT considered an analvtical evaluation. Page 3 of4 l ' CASE N-532-5 McGuire Nuclear Unit 1 Form OAR-1 Owner's Activity Report Table 2 Abstract of Repair/Replacement Activities Required For Continued Service Code Item Description Description of Work Date Completed Repair I Replacement Class Plan Number Replaced bolting for the 1 PZR Manway, Bolting pressurizer manway (original 02/12/2015 2190092-05, 14 bolt damaged due to leaking diaphraQm, on-line discovery) Repaired indication on weld 1NC1F-1374 and its associated 1 Weld 1NC1F-1374 welds (original weld rejected; 4/16/2016 2184066-29 AUG program, summary M1 .G14.1.0004 inspected durinQ 1EOC24) Replaced Valve 1Nl-126 1 Valve 1Nl-126, Bolting (Bolting rejected on old valve; 4/16/2016 2178270-04 Category B-G-2, Item 87.70 inspected durinQ 1EOC24) Replaced the section of vendor B VCfYC chiller condenser, supplied piping on the inlet side 3 vendor supplied Inlet piping of the B VCfYC chiller 01/14/2015 2097603-12 condenser (original piping had leak, on-line discovery) Replaced 1VA-AH-0022 / 1A 3 NS Pump AHU Coil NS Pump AHU Cooling Coil 4/9/2016 20049140-65 (original coil had leak, on-line discovervl Page 4 of 4
... CASE N-532-5 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number ________ _______ _ Plant McGuire Nuclear Station, 12700 Hagers Ferry Rd, Huntersville, NC 28078-9340 Unit No. Commercial service date --------Refueling outage no. 1 EOC24 12/01/1981 (if applicable) Current inspection interval (1s1. 2nd, 3rd, 41h. olher) Current inspection period ISi-2nd, Containment-1st (1st, 2nd, 3rd) Edition and Addenda of Section XI applicable to the inspection plans 2007 with 2008 addenda Date and revision of inspection plans See attachment ----------------------------Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Same Code Cases used: The following Code Cases are permitted by the ISi Plans: N-513-3, N-526, N-532-5, N-566-2, N-586-1, N-613-1, N-639, N-643-2, N-648-1, N-663, N-706-1, N-716, N-722-1, N-729-1, N-731, N-735, N-770-1 (if applicable) CERTIFICATE OF CONFORMANCE I 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 1 EOC24 conform to the requirements of Section XI. (refueling outage number) Date Signed ----------------------------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 North Carolina and employed by HSB Global Standards of CT 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 perfonned 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 c nnected with this inspectio -CommissionsN;2. i / t 1.S.AC!./S Ol: National Board, State, and Endorsements 7-7-/0 ,v.Jr,,tJS Page 1 of4 I' _) CASE N-532-5 Attachment McGuire Unit 1 End of Cycle 24 lnservice Inspection Report The McGuire Nuclear Station Unit 1 Fourth Ten Year lnservice Inspection (ISi) Plan complies with 1 OCFR50.55a(g), which implements, by reference, the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, 2007 Edition with 2008 Addenda. This summary report is being submitted pursuant to the reporting requirements of ASME Section XI as amended by ASME Code Case N-532-5, "Repair/Replacement Activity Documentation Requirements and lnservice Inspection Summary Report Preparation and Submission Section XI, Division 1". Contained within this summary report are the form OAR-1 (Owner's Activity Report) and Tables 1 and 2 of Code Case N-532-5 for McGuire Nuclear Station during cycle 24 and Refueling Outage 24 (1EOC24). 1 EOC24 is the first outage of the second ISi period in the fourth inspection interval. 1 EOC24 is the second outage of the first Containment period in the third inspection interval. This report includes all Repair/Replacement activities from November 17, 2014 through April 16, 2016, cycle 24. Pressure testing performed on-line prior to 9/1 /2015 are in the 1st period. Date and Revision of lnservice Inspection Plans: Fourth Interval lnservice Inspection Plans The following document comprises the McGuire Nuclear Station 4th Interval lnservice Inspection Plan for Unit 1 (Class 1, 2, and 3 Components): "Fourth Interval lnservice Inspection Plan, McGuire Nuclear Station Unit 1 and Unit 2, General Requirements" -Document "MISl-1462.10-0040-GEN REQ UNIT 1 SECOND AND THIRD PERIODS AND UNIT 2", Rev 1, dated 05/28/2015. The following document comprises the McGuire Nuclear Station 4th Interval lnservice Inspection Pressure Test Plan for Unit 1: "McGuire Nuclear Station -Fourth Interval lnservice Inspection Plan -Pressure Test Plan", Document MISl-1462.20-0040-PTPLAN, Rev 1, dated 06/18/2015. Containment lnservice Inspection Plan The following document comprises the McGuire Nuclear Station 3rd Interval Containment lnservice Inspection Plan for Unit 1 (Class MC): "McGuire Nuclear Station -Third Interval Containment lnservice Inspection Plan -Containment -Units 1 & 2", Document #MC-ISIC3-1042-0001, Rev. 3, dated 10/21/2015. Page Z of4 CASE N-532-5 McGuire Nuclear Unit 1 Form OAR-1 Owner's Activity Report Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service Examination Category and Item Description Evaluation Description Item Number Westinghouse performed an analytical evaluation of the flaws and documented the justification for continued operation under Report B-8 I B2.11 Flaws in excess of the ASME XI code allowable were (Reference NCR 01596672). discovered in the Pressurizer lower head to shell weld Dunng 1 EOC24 the Pressurizer lower head to during 1EOC17 and 1EOC24. shell weld was inspected again. There was no change in the size/number of flaws so the current Westinghouse analysis justification for continued operations, for the life of the plant, remains valid. Reference NCR 02015606. C-H I C7.10 Boric acid residue found on bolted connection for valve Item was evaluated by Engineering in NCR 1ND-18, during 1 EOC24 02012421and found to be acceptable. This is NOT considered an analytical evaluation. C-H I C7.10 Dry Boric acid was found on bolted connection for valves Item was evaluated by Engineering in NCR 1 ND35 and 1 FW-27A (on-line, 1st period inspection) 01699924 and found to be acceptable. This is NOT considered an analvticai evaluation. C-H I C7.10 Inactive boron leak found on bolted connection for valve Item was evaluated by Engineering in NCR 1 NV-290 (on-line, 1st period inspection) 01906973 and found to be acceptable. This is NOT considered an analvtical evaluation. D-B I 02.10 inactive boron leak found on bolted connection for valve item was evaluated by Engineering in NCR 1KF-24 (on-line, 1st period inspection) 01906844 and found to be acceptable. This is NOT considered an analytical evaluation. Thickness readings below 87.5% of nominal wall were Item was evaluated by Service Water Corrosion R-A I R.17 observed during Inspection of wall thickness grid at weld program manager in NCR 02015846 and found 1RN233*6 and 1RN245-8 during 1 EOC24 to be acceptable. This is NOT considered an analvtical evaluation. Thickness readings below 87.5% of nominal wall were Item was evaluated by Service Water Corrosion R-A I R.17 observed during inspection of wall thickness grid at weld program manager in NCR 02014622 and found 1 RN264-1, during 1 EOC24 to be acceptable. This is NOT considered an analvtical evaluation. Thickness readings below 87.5% of nominal wall were Item was evaluated by Service Water Corrosion R-A/ R.17 observed during inspection of wall thickness grid at weld program manager in NCR 02014621 and found 1RN1F300, during 1EOC24 to be acceptable. This is NOT considered an analvtical evaluation. Thickness readings below 87.5% of nominal wall were Item was evaluated by Service Water Corrosion R-A I R.17 observed during inspection of wall thickness grid at weld program manager in NCR 02014605 and found 1 RN1 F279, during 1 EOC24 to be acceptable. This is NOT considered an analvtical evaluation. Page 3 of4 l ' CASE N-532-5 McGuire Nuclear Unit 1 Form OAR-1 Owner's Activity Report Table 2 Abstract of Repair/Replacement Activities Required For Continued Service Code Item Description Description of Work Date Completed Repair I Replacement Class Plan Number Replaced bolting for the 1 PZR Manway, Bolting pressurizer manway (original 02/12/2015 2190092-05, 14 bolt damaged due to leaking diaphraQm, on-line discovery) Repaired indication on weld 1NC1F-1374 and its associated 1 Weld 1NC1F-1374 welds (original weld rejected; 4/16/2016 2184066-29 AUG program, summary M1 .G14.1.0004 inspected durinQ 1EOC24) Replaced Valve 1Nl-126 1 Valve 1Nl-126, Bolting (Bolting rejected on old valve; 4/16/2016 2178270-04 Category B-G-2, Item 87.70 inspected durinQ 1EOC24) Replaced the section of vendor B VCfYC chiller condenser, supplied piping on the inlet side 3 vendor supplied Inlet piping of the B VCfYC chiller 01/14/2015 2097603-12 condenser (original piping had leak, on-line discovery) Replaced 1VA-AH-0022 / 1A 3 NS Pump AHU Coil NS Pump AHU Cooling Coil 4/9/2016 20049140-65 (original coil had leak, on-line discovervl Page 4 of 4}}
}}

Revision as of 06:15, 19 May 2018

McGuire Nuclear Station, Unit 1 - End of Cycle 24 Inservice Inspection Report
ML16208A058
Person / Time
Site: McGuire Duke Energy icon.png
Issue date: 07/14/2016
From: Capps S D
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
N-532-5
Download: ML16208A058 (6)
v • d • e


Text

, \* . Serial No: MNS-16-058 July 14, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk

Subject:

Duke Energy Carolinas, LLC (Duke Energy) McGuire Nuclear Station, Unit 1 Docket No. 50-369 End of Cycle 24 lnservice Inspection Report Steven D. Capps Vice President McGuire Nuclear Station Duke Energy MGOl VP I 12700 Hagers Ferry Road Huntersville, NC 28078 O: 980.875.4805 f: 980.875.4809 Steven. Ca pps@duke-energy.com Pursuant to the reporting requirements of American Society of Mechanical Engineers (ASME)Section XI, as amended by ASME Code Case N-532-5, attached is the subject report. Should you have any questions or require additional information, please contact P.T. Vu of Regulatory Affairs at (980) 875-4302. Sincerely, JMJt,,I Steven D. Capps Attachment www.duke-energy.com U.S. Nuclear Regulatory Commission July 14, 2016 Page 2 xc: C. Haney, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 G.E. Miller, Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8G9A Rockville, MD 20852-2738 V. Sreenivas, Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8G9A Rockville, MD 20852-2738 J. Zeiler NRC Senior Resident Inspector McGuire Nuclear Station A. Hutto NRC Senior Resident Inspector McGuire Nuclear Station

... CASE N-532-5 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number ________ _______ _ Plant McGuire Nuclear Station, 12700 Hagers Ferry Rd, Huntersville, NC 28078-9340 Unit No. Commercial service date --------Refueling outage no. 1 EOC24 12/01/1981 (if applicable) Current inspection interval (1s1. 2nd, 3rd, 41h. olher) Current inspection period ISi-2nd, Containment-1st (1st, 2nd, 3rd) Edition and Addenda of Section XI applicable to the inspection plans 2007 with 2008 addenda Date and revision of inspection plans See attachment ----------------------------Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Same Code Cases used: The following Code Cases are permitted by the ISi Plans: N-513-3, N-526, N-532-5, N-566-2, N-586-1, N-613-1, N-639, N-643-2, N-648-1, N-663, N-706-1, N-716, N-722-1, N-729-1, N-731, N-735, N-770-1 (if applicable) CERTIFICATE OF CONFORMANCE I 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 1 EOC24 conform to the requirements of Section XI. (refueling outage number) Date Signed ----------------------------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 North Carolina and employed by HSB Global Standards of CT 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 perfonned 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 c nnected with this inspectio -CommissionsN;2. i / t 1.S.AC!./S Ol: National Board, State, and Endorsements 7-7-/0 ,v.Jr,,tJS Page 1 of4 I' _) CASE N-532-5 Attachment McGuire Unit 1 End of Cycle 24 lnservice Inspection Report The McGuire Nuclear Station Unit 1 Fourth Ten Year lnservice Inspection (ISi) Plan complies with 1 OCFR50.55a(g), which implements, by reference, the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, 2007 Edition with 2008 Addenda. This summary report is being submitted pursuant to the reporting requirements of ASME Section XI as amended by ASME Code Case N-532-5, "Repair/Replacement Activity Documentation Requirements and lnservice Inspection Summary Report Preparation and Submission Section XI, Division 1". Contained within this summary report are the form OAR-1 (Owner's Activity Report) and Tables 1 and 2 of Code Case N-532-5 for McGuire Nuclear Station during cycle 24 and Refueling Outage 24 (1EOC24). 1 EOC24 is the first outage of the second ISi period in the fourth inspection interval. 1 EOC24 is the second outage of the first Containment period in the third inspection interval. This report includes all Repair/Replacement activities from November 17, 2014 through April 16, 2016, cycle 24. Pressure testing performed on-line prior to 9/1 /2015 are in the 1st period. Date and Revision of lnservice Inspection Plans: Fourth Interval lnservice Inspection Plans The following document comprises the McGuire Nuclear Station 4th Interval lnservice Inspection Plan for Unit 1 (Class 1, 2, and 3 Components): "Fourth Interval lnservice Inspection Plan, McGuire Nuclear Station Unit 1 and Unit 2, General Requirements" -Document "MISl-1462.10-0040-GEN REQ UNIT 1 SECOND AND THIRD PERIODS AND UNIT 2", Rev 1, dated 05/28/2015. The following document comprises the McGuire Nuclear Station 4th Interval lnservice Inspection Pressure Test Plan for Unit 1: "McGuire Nuclear Station -Fourth Interval lnservice Inspection Plan -Pressure Test Plan", Document MISl-1462.20-0040-PTPLAN, Rev 1, dated 06/18/2015. Containment lnservice Inspection Plan The following document comprises the McGuire Nuclear Station 3rd Interval Containment lnservice Inspection Plan for Unit 1 (Class MC): "McGuire Nuclear Station -Third Interval Containment lnservice Inspection Plan -Containment -Units 1 & 2", Document #MC-ISIC3-1042-0001, Rev. 3, dated 10/21/2015. Page Z of4 CASE N-532-5 McGuire Nuclear Unit 1 Form OAR-1 Owner's Activity Report Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service Examination Category and Item Description Evaluation Description Item Number Westinghouse performed an analytical evaluation of the flaws and documented the justification for continued operation under Report B-8 I B2.11 Flaws in excess of the ASME XI code allowable were (Reference NCR 01596672). discovered in the Pressurizer lower head to shell weld Dunng 1 EOC24 the Pressurizer lower head to during 1EOC17 and 1EOC24. shell weld was inspected again. There was no change in the size/number of flaws so the current Westinghouse analysis justification for continued operations, for the life of the plant, remains valid. Reference NCR 02015606. C-H I C7.10 Boric acid residue found on bolted connection for valve Item was evaluated by Engineering in NCR 1ND-18, during 1 EOC24 02012421and found to be acceptable. This is NOT considered an analytical evaluation. C-H I C7.10 Dry Boric acid was found on bolted connection for valves Item was evaluated by Engineering in NCR 1 ND35 and 1 FW-27A (on-line, 1st period inspection) 01699924 and found to be acceptable. This is NOT considered an analvticai evaluation. C-H I C7.10 Inactive boron leak found on bolted connection for valve Item was evaluated by Engineering in NCR 1 NV-290 (on-line, 1st period inspection) 01906973 and found to be acceptable. This is NOT considered an analvtical evaluation. D-B I 02.10 inactive boron leak found on bolted connection for valve item was evaluated by Engineering in NCR 1KF-24 (on-line, 1st period inspection) 01906844 and found to be acceptable. This is NOT considered an analytical evaluation. Thickness readings below 87.5% of nominal wall were Item was evaluated by Service Water Corrosion R-A I R.17 observed during Inspection of wall thickness grid at weld program manager in NCR 02015846 and found 1RN233*6 and 1RN245-8 during 1 EOC24 to be acceptable. This is NOT considered an analvtical evaluation. Thickness readings below 87.5% of nominal wall were Item was evaluated by Service Water Corrosion R-A I R.17 observed during inspection of wall thickness grid at weld program manager in NCR 02014622 and found 1 RN264-1, during 1 EOC24 to be acceptable. This is NOT considered an analvtical evaluation. Thickness readings below 87.5% of nominal wall were Item was evaluated by Service Water Corrosion R-A/ R.17 observed during inspection of wall thickness grid at weld program manager in NCR 02014621 and found 1RN1F300, during 1EOC24 to be acceptable. This is NOT considered an analvtical evaluation. Thickness readings below 87.5% of nominal wall were Item was evaluated by Service Water Corrosion R-A I R.17 observed during inspection of wall thickness grid at weld program manager in NCR 02014605 and found 1 RN1 F279, during 1 EOC24 to be acceptable. This is NOT considered an analvtical evaluation. Page 3 of4 l ' CASE N-532-5 McGuire Nuclear Unit 1 Form OAR-1 Owner's Activity Report Table 2 Abstract of Repair/Replacement Activities Required For Continued Service Code Item Description Description of Work Date Completed Repair I Replacement Class Plan Number Replaced bolting for the 1 PZR Manway, Bolting pressurizer manway (original 02/12/2015 2190092-05, 14 bolt damaged due to leaking diaphraQm, on-line discovery) Repaired indication on weld 1NC1F-1374 and its associated 1 Weld 1NC1F-1374 welds (original weld rejected; 4/16/2016 2184066-29 AUG program, summary M1 .G14.1.0004 inspected durinQ 1EOC24) Replaced Valve 1Nl-126 1 Valve 1Nl-126, Bolting (Bolting rejected on old valve; 4/16/2016 2178270-04 Category B-G-2, Item 87.70 inspected durinQ 1EOC24) Replaced the section of vendor B VCfYC chiller condenser, supplied piping on the inlet side 3 vendor supplied Inlet piping of the B VCfYC chiller 01/14/2015 2097603-12 condenser (original piping had leak, on-line discovery) Replaced 1VA-AH-0022 / 1A 3 NS Pump AHU Coil NS Pump AHU Cooling Coil 4/9/2016 20049140-65 (original coil had leak, on-line discovervl Page 4 of 4

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