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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARRA-24-0004, End of Cycle 29 (M1R29) Inservice Inspection Summary Report2024-02-21021 February 2024 End of Cycle 29 (M1R29) Inservice Inspection Summary Report RA-22-0303, End of Cycle 28 (M1 R28) Steam Generator Tube Inspection Report2022-10-25025 October 2022 End of Cycle 28 (M1 R28) Steam Generator Tube Inspection Report RA-22-0178, End of Cycle 28 (M1R28) Inservice Inspection Summary Report2022-08-0808 August 2022 End of Cycle 28 (M1R28) Inservice Inspection Summary Report RA-19-0400, End of Cycle 27 (M1R27) Inservice Inspection Summary Report2021-01-19019 January 2021 End of Cycle 27 (M1R27) Inservice Inspection Summary Report RA-20-0031, Revision to Request for Alternative in Accordance with 10 CFR 50.55a (z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period2020-01-23023 January 2020 Revision to Request for Alternative in Accordance with 10 CFR 50.55a (z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period RA-19-0341, Request for Alternative in Accordance with 10 CFR 50.55a (z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period2019-12-19019 December 2019 Request for Alternative in Accordance with 10 CFR 50.55a (z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period RA-19-0268, End of Cycle 26 (M1 R26) Inservice Inspection Summary Report2019-07-10010 July 2019 End of Cycle 26 (M1 R26) Inservice Inspection Summary Report MNS-18-003, End of Cycle 25 In-service and Steam Generator In-service Inspection Summary Reports2018-01-11011 January 2018 End of Cycle 25 In-service and Steam Generator In-service Inspection Summary Reports MNS-17-033, Snubber Program Plan for the Fourth Ten-Year Lnservice Testing (IST) Interval2017-08-0202 August 2017 Snubber Program Plan for the Fourth Ten-Year Lnservice Testing (IST) Interval ML16208A0582016-07-14014 July 2016 End of Cycle 24 Inservice Inspection Report MNS-15-010, Inservice Inspection Report, End of Cycle 23 Refueling Outage2015-02-12012 February 2015 Inservice Inspection Report, End of Cycle 23 Refueling Outage ML14197A2872014-06-26026 June 2014 MISI-1462.10-0040, Revision 0, Fourth Inspection Interval Inservice Inspection Plan, Enclosure 1 MNS-14-053, MISI-1462.20-0040, Revision 0, Fourth Inspection Interval Inservice Inspection Pressure Test Plan2014-06-24024 June 2014 MISI-1462.20-0040, Revision 0, Fourth Inspection Interval Inservice Inspection Pressure Test Plan MNS-14-026, Risk-Informed Inservice Inspection Program Response to Request for Additional Information2014-03-0303 March 2014 Risk-Informed Inservice Inspection Program Response to Request for Additional Information ML13234A0692013-08-13013 August 2013 Relief Request Serial #13-MN-002, Risk-Informed Inservice Inspection Program Fourth Inservice Inspection Interval ML13212A0672013-07-22022 July 2013 Inservice Inspection Report End of Cycle 22 Refueling Outage ML13205A1692013-07-11011 July 2013 Steam Generator In-Service Inspection Summary Report Unit 1, End of Cycle (EOC)22 ML13078A0092013-02-27027 February 2013 Fourth Ten-Year Inservice Testing Interval Inservice Testing Program, Revision 28 ML12321A0502012-11-0101 November 2012 Steam Generator Inservice Inspection Report ML12025A1392012-01-12012 January 2012 Inservice Inspection Report End of Cycle 21 Refueling Outage ML11362A0792011-12-15015 December 2011 Fourth Inspection Interval Inservice Inspection Pressure Test Plan ML1025101862010-08-30030 August 2010 Relief Request Serial #10-MN-001 ML1020405152010-07-15015 July 2010 Inservice Inspection Report Unit 1, End of Cycle 20 Refueling Outage ML0918804232009-06-29029 June 2009 Relief Request Serial #09-MN-003 ML0918804242009-06-29029 June 2009 Relief Request Serial #09-MN-004 ML0905106612009-02-0909 February 2009 In-Service Inspection Report, Unit 1, End of Cycle (EOC) 19 ML0904908362009-02-0202 February 2009 Steam Generator In-Service Inspection Report, End of Cycle (EOC) 19 ML0805805772008-03-26026 March 2008 Relief, Third 10-Year Interval Inservice Inspection Program Plan Repair of Chemical Volume and Control System Valve 1NV-240, MD6274 ML0726204622007-08-23023 August 2007 Inservice Inspection Report, End of Cycle 18 Refueling Outage ML0704500202007-02-0808 February 2007 Notification of Inspection and Request for Information ML0617801652006-06-0909 June 2006 Inservice Testing Program, Request for Additional Information, Relief Request Nos. MC-GRP-01 ML0513003642005-05-0303 May 2005 Units 1 & 2, Inservice Testing Program Relief Request MC-SRP-NS-01 Supplement 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 ML0423305882004-08-12012 August 2004 Third Ten-Year Inservice Testing Interval Inservice Testing Program, Revision 27 ML0421602882004-07-26026 July 2004 Relief Request (RR) 03-001 ML0419401702004-06-30030 June 2004 Inservice Inspection Report End of Cycle 16 Refueling Outage ML0407607472004-03-0808 March 2004 Inservice Inspection Plan Relief Requests ML0401505112004-01-0505 January 2004 Inservice Inspection (ISI) Pressure Test Plan, Third Ten-Year Interval Plan ML0400200412003-12-0909 December 2003 to Third Interval Inservice Inspection Plan, McGuire Nuclear Station, Units 1 and 2, Unit 1, Section 1 Through Unit 2, Section 2 ML0400200402003-12-0909 December 2003 to Third Interval Inservice Inspection Plan, McGuire Nuclear Station, Units 1 and 2, General Requirements Through Unit 1, Section 2 2024-02-21
[Table view] Category:Letter
MONTHYEARIR 05000369/20240032024-11-0404 November 2024 Integrated Inspection Report 05000369/2024003 and 05000370/2024003 ML24303A4212024-10-30030 October 2024 Mcguire Nuclear Station, Units 1 & 2, Notification of an NRC Fire Protection Team Inspection FPTI NRC 05000369/2025010, 05000370/2025010 and Request for Information RFI IR 05000369/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000369/2024402 05000370/2024402 IR 05000369/20240052024-08-26026 August 2024 Updated Inspection Plan for McGuire Nuclear Station, Units 1 and 2, (Report 05000369-2024005 and 05000370-2024005) IR 05000369/20244042024-08-0101 August 2024 Cover Letter Security Baseline Inspection Report 05000369/2024404 and 05000370/2024404 IR 05000369/20253012024-07-29029 July 2024 Notification of Licensed Operator Initial Examination 05000369/2025301 and 05000370/2025301 IR 05000369/20244032024-07-25025 July 2024 – Cyber Security Inspection Report 05000369/2024403 and 05000370/2024403 Rev IR 05000369/20240022024-07-24024 July 2024 Integrated Inspection Report 05000369/2024002 and 05000370/2024002 ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000369/20244012024-07-0303 July 2024 – Security Baseline Inspection Report 05000369/2024401 and 05000370/2024401 ML24176A2802024-06-26026 June 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000369-2024404 and 05000370-2024404) IR 05000369/20240112024-06-0404 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000369/2024011 and 05000370/2024011 ML24149A1772024-05-28028 May 2024 NRC Response to Duke Energy 2025 FOF Schedule Change Request (Catawba and McGuire) IR 05000369/20240012024-05-0808 May 2024 Integrated Inspection Report 05000369-2024001 and 05000370-2024001 and 07200038-2024001 ML24110A0382024-04-30030 April 2024 – Correction to Issuance of Amendment Nos. 330 and 309, Regarding Implementation of Technical Specifications Task Force (TSTF) Traveler TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf ML24100A8742024-04-10010 April 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000369/2024403; and 05000370/2024403 ML24052A3062024-04-0808 April 2024 Issuance of Amendment Nos. 331 & 310, Regarding Adoption of Title 10 of Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML24031A5402024-03-26026 March 2024 Issuance of Amendment Nos. 330 and 309 Regarding Implementation of TSTF 505,Rev. 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML24085A2402024-03-21021 March 2024 Requalification Program Inspection - McGuire Nuclear Station IR 05000369/20230062024-02-28028 February 2024 Annual Assessment Letter for McGuire Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000369/2023006 and 05000370/2023006 ML24024A2182024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000369/20230042024-01-31031 January 2024 Integrated Inspection Report 05000369/2023004 and 05000370/2023004 ML24019A1392024-01-25025 January 2024 TSTF 505 and 50.69 Audit Summary ML24019A2002024-01-24024 January 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000369/20234022023-12-14014 December 2023 – Material Control and Accounting Program Inspection Report 05000369/2023402 and 05000370/2023402 05000369/LER-1923-001, Automatic Actuation of the 1A Motor Driven Auxiliary Feedwater Pump Due to Human Error2023-12-13013 December 2023 Automatic Actuation of the 1A Motor Driven Auxiliary Feedwater Pump Due to Human Error ML23317A2272023-11-17017 November 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Transmittal of Dam Inspection Report - Non-Proprietary ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230032023-10-24024 October 2023 Integrated Inspection Report 05000369/2023003 and 05000370/2023003; and Inspection Report 07200038/2023001 IR 05000369/20230102023-10-13013 October 2023 Age Related Degradation Inspection Report 05000369/2023010 and 05000370/2023010 IR 05000369/20240102023-10-13013 October 2023 Notification of McGuire Nuclear Station Comprehensive Engineering Team Inspection – U.S. Nuclear Regulatory Commission Inspection Report 05000369, 370/2024010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds IR 05000369/20233012023-09-20020 September 2023 William B. McGuire Nuclear Station - NRC Examination Report 05000369/2023301 and 05000370/2023301 ML23230A0652023-08-31031 August 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Relief Request Use of Later Edition of ASME Code ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230052023-08-25025 August 2023 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 (Report 05000369/2023005 and 05000370/2023005) IR 05000369/20234012023-08-0404 August 2023 – Security Baseline Inspection Report 05000369/2023401 and 05000370/2023401 (OUO-SRI) Cover IR 05000369/20230022023-07-28028 July 2023 Integrated Inspection Report 05000369/2023002 and 05000370/2023002 ML23206A0092023-07-24024 July 2023 William B. McGuire Nuclear Station – Operator Licensing Written Examination Approval 05000369/2023301 and 05000370/2023301 IR 05000369/20234202023-07-24024 July 2023 – Security Baseline Inspection Report 050003692023420 and 050003702023420 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23159A2712023-06-20020 June 2023 William B. McGuire Nuclear Station, Unit 1 - Relief Request Impractical Reactor System Welds ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined ML23124A0862023-05-0303 May 2023 Cycle 29, Revision 1, Core Operating Limits Report (COLR) IR 05000369/20230012023-05-0101 May 2023 Integrated Inspection Report 05000369/2023001 and 05000370/2023001 ML23115A2122023-05-0101 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23094A1832023-04-18018 April 2023 Audit Plan TSTF-505, Rev. 2, RITSTF Initiative 4B & 10 CFR 50.69, Risk-Informed Categorization & Treatment of Structures, Systems & Components for Nuclear Power Reactors (EPIDs L-2023-LLA-0021 & L-2023-LLA-0022) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility 2024-08-26
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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