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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 ML24092A0752024-03-28028 March 2024 3R22 Refueling Outage Inservice Inspection (ISI) Owners Activity Report Extension ML23068A1072023-03-0808 March 2023 End of Cycle 21 Steam Generator Tube Inspection Report Supplement ML22300A1002022-10-27027 October 2022 End of Cycle 21 Steam Generator Tube Inspection Report ML22213A1202022-08-19019 August 2022 Inservice Inspection Program - Owners Activity Report, Refueling Outage 21 ML21336A6252021-12-0101 December 2021 Inservice Inspection Program, Owners Activity Report, Refueling Outage 27 ML21014A2262020-12-21021 December 2020 Inservice Inspection Program Owner'S Activity Report, Refueling Outage 20 ML20268A2252020-09-23023 September 2020 ASME Section XI Inservice Inspection Program Relief Requests for Limited Coverage Examinations Performed in the Third Period of the Fourth 10-Year Inspection Interval ML20198M6822020-07-15015 July 2020 Alternate Request RR-05-06 - Inspection Interval Extension for Steam Generator Pressure Retaining Welds and Full-Penetration Welded Nozzles ML20076A5492020-03-14014 March 2020 Alternative Request IR-4-03 for Use of an Alternative Non-Code Methodology to Demonstrate Structural Integrity of Class 3 Moderate-Energy Piping ML20049A0882020-02-17017 February 2020 ASME Section XI Inservice Inspection Program Relief Requests for Limited Coverage Examinations Performed in the Second Period of the Third 10-Year Inspection Interval ML20048A0062020-02-11011 February 2020 ASME Section XI Inservice Inspection Program: Relief Request for Limited Coverage Examinations Performed in the Second Period of the Fourth 10-Year Inspection Interval ML19275D2542019-09-19019 September 2019 End of Cycle 19 Steam Generator Tube Inspection Report ML19211B1672019-07-23023 July 2019 Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 19 ML19100A1262019-03-19019 March 2019 Inservice Inspection Program Interval Change ML19023A0242019-01-11011 January 2019 Submittal of Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 25 ML18114A1052018-04-19019 April 2018 End of Cycle 18 Steam Generator Tube Inspection Report ML18066A0782018-03-0101 March 2018 In-service Testing Program for Pumps, Valves, & Snubbers Fifth & Fourth 10-Year Interval Updates for Units 2 & 3 ML18031A0932018-01-24024 January 2018 Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 18 ML17269A0302017-09-18018 September 2017 End of Cycle 24 Steam Generator Tube Inspection Report ML17187A1362017-06-27027 June 2017 Inservice Inspection Program, Owner'S Activity Report, Refueling Outage 24 ML16222A3512016-08-0202 August 2016 Submittal of End of Cycle 17 Steam Generator Tube Inspection Report ML16214A2432016-07-25025 July 2016 Inservice Inspection Program, Owner'S Activity Report, Refueling Outage 17 ML16033A4712016-01-22022 January 2016 Inservice Inspection Program, Owner'S Activity Report, Refueling Outage 23 ML15356A3752015-12-14014 December 2015 End-of-Cycle 23 Steam Generator Tube Inspection Report ML15050A0412015-02-0909 February 2015 End of Cycle 16 Steam Generator Tube Inspection Report ML15049A2932015-02-0909 February 2015 Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 16 ML15033A3732015-01-26026 January 2015 Response to Second Request for Addition Information Regarding Aging Management Program Description: Inservice Inspection - Reactor Vessel Internals, License Renewals Commitment #13 ML14220A0162014-08-0101 August 2014 Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 22 ML14206A8372014-07-21021 July 2014 Response to Request for Additional Information Regarding Aging Management Program Description: Inservice Inspection - Reactor Vessel Internals, License Renewal Commitment #13 (MF3402) ML14188B1902014-06-26026 June 2014 End of Cycle 22 Steam Generator Tube Inspection Report ML14143A4082014-05-20020 May 2014 Examination Summary and Coverage Results ASME Section XI Inservice Inspection Program Alternative Request RR-04-15, Limited One-Sided Ultrasonic Examination Technique ML14051A1092014-02-0707 February 2014 Response to Request for Additional Information Regarding ASME Section XI Inservice Inspection Program Alternative Request RR-04-15, Limited One-Sided Ultrasonic Examination Technique ML13284A0652013-10-0202 October 2013 End of Cycle 15 Steam Generator Tube Inspection Report ML13218A2642013-07-31031 July 2013 Information in Support of License Renewal Commitment #13 Program Description for Reactor Vessel Internals Inspections ML13045A4862013-02-0505 February 2013 Inservice Inspection Program-Owner's Activity Report, Refueling Outage 21 ML12151A3592012-06-0707 June 2012 End of Cycle 20 Steam Generator Tube Inservice Inspection Report Review ML12109A0442012-04-0606 April 2012 End of Cycle 14 Steam Generator Tube Inspection Report ML11207A4642011-07-18018 July 2011 Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 20 ML1102502592011-01-20020 January 2011 Request for Additional Information Regarding Relief Requests for Limited Coverage Examinations Performed in the Second 10-Year Inspection Interval ML1022205272010-08-0505 August 2010 Fourth 10-Year Interval Inservice Inspection Program ML1025802042010-07-29029 July 2010 Fourth 10-Year Interval Inservice Inspection Program and Associated Proposed Alternatives and Relief Request ML1021500712010-07-25025 July 2010 Inservice Inspection Program - Owner'S Activity Report ML1006404562010-03-0505 March 2010 CFR50.55a Relief Request IR-3-14, Update to the Risk-Informed Inservice Inspection Program for the Third 10-Year Inspection Interval ML1005011632010-02-0404 February 2010 Inservice Inspection Program - Owner'S Activity Report for Refueling Outage 19 ML0913106662009-04-28028 April 2009 Third 10-year Interval Inservice Inspection Program and Associated Proposed Alternatives and Relief Requests ML0908503442009-03-13013 March 2009 Submittal of End of Cycle 12 Steam Generator Tube Inspection Report ML0905700482009-02-13013 February 2009 Submittal of Inservice Inspection Program - Owner'S Activity Report for 05/20/07 Through Refueling Outage 12, 11/24/08 ML0824104152008-08-0707 August 2008 Submittal of Inservice Inspection Program - Owner'S Activity Report ML0811401382008-04-11011 April 2008 Submittal of 2007 Steam Generator Tube Inspection Report 2024-04-30
[Table view] Category:Letter
MONTHYEARIR 05000336/20240032024-11-0707 November 2024 Integrated Inspection Report 05000336/2024003 and 05000423/2024003 and Apparent Violation and Independent Spent Fuel Storage Installation Inspection Report 07200008/2024001 ML24289A0152024-10-21021 October 2024 Review of the Fall 2023 Steam Generator Tube Inspection Report 05000423/LER-2024-001, Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary2024-10-14014 October 2024 Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary IR 05000336/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000336/2024402 and 05000423/2024402 (Cover Letter Only) ML24281A1102024-10-0707 October 2024 Requalification Program Inspection 05000423/LER-2023-006-02, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-09-26026 September 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A2192024-09-16016 September 2024 Decommissioning Trust Fund Disbursement - Revision to Previous Thirty-Day Written Notification ML24260A1952024-09-16016 September 2024 Response to Request for Additional Information Regarding Proposed Amendment to Support Implementation of Framatome Gaia Fuel ML24248A2272024-09-0404 September 2024 Operator Licensing Examination Approval ML24240A1532024-09-0303 September 2024 Summary of Regulatory Audit Supporting the Review of License Amendment Request for Implementation of Framatome Gaia Fuel IR 05000336/20240052024-08-29029 August 2024 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005 IR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 ML24221A2872024-08-0808 August 2024 Independent Spent Fuel Storage Installation (ISFSI) - Submittal of Cask Registration for Spent Fuel Storage IR 05000336/20244412024-08-0606 August 2024 Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only) ML24212A0742024-08-0505 August 2024 Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification ML24211A1712024-07-25025 July 2024 Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change IR 05000336/20244032024-07-22022 July 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403 IR 05000336/20245012024-07-0101 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501 ML24180A0932024-06-28028 June 2024 Readiness for Additional Inspection: EA-23-144 IR 05000336/20240102024-06-26026 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010 ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 IR 05000336/20244402024-06-24024 June 2024 Final Significance Determination for Security-Related Greater than Green Finding(S) with Assessment Follow-up; IR 05000336/2024440 and 05000423/2024440 and Notice of Violation(S), NRC Investigation Rpt 1-2024-001 (Cvr Ltr Only) ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24280A0012024-06-20020 June 2024 Update to the Final Safety Analysis Report (Redacted Version) ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) 05000336/LER-2024-001, Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications2024-06-10010 June 2024 Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24165A1292024-06-0505 June 2024 ISFSI, 10 CFR 50.59 Annual Change Report for 2023 Annual Regulatory Commitment Change Report for 2023 ML24128A2772024-06-0404 June 2024 Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary) ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24110A0562024-05-21021 May 2024 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2023-LLE-0013) (Letter) ML24109A0032024-05-21021 May 2024 Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary) ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report 05000423/LER-2023-006-01, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24141A2432024-05-20020 May 2024 Response to Request for Additional Information Regarding Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment No. 15 IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation ML24123A2042024-05-0202 May 2024 Pre-Decisional Replay to EA-23-144 05000423/LER-2023-006, Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-0202 May 2024 Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 ML24116A0452024-04-25025 April 2024 Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only) ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating Report ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report ML24103A0202024-04-22022 April 2024 Summary of Regulatory Audit in Support of License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits ML24106A2032024-04-15015 April 2024 2023 Annual Environmental Operating Report ML24088A3302024-04-0404 April 2024 Regulatory Audit Plan in Support of License Amendment Request to Implement Framatome Gaia Fuel ML24093A2162024-04-0101 April 2024 Response to Request for Additional Information Regarding License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits 2024-09-04
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Dominion Nuclear Connecticut, Inc.
Millstone Power Station ii~ @mini@w Rope Ferry Road Waterford, CT 06385 JUL 18 2011 U.S. Nuclear Regulatory Commission Serial No.11-396 Attention: Document Control Desk NSS&L/MLC RO Washington, DC 20555 Docket No. 50-336 License No. DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 2 INSERVICE INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT, REFUELING OUTAGE 20 Dominion Nuclear Connecticut, Inc. hereby submits the American Society of Mechanical Engineers (ASME),Section XI, Form OAR-i, Owner's Activity Report for the period from November 19, 2009 through Refueling Outage 20, completed on May 3,2011, for Millstone Power Station Unit 2. The enclosure is in accordance with the requirements of ASME Code Case N-532-4.
If you have any questions or require additional information, please contact Mr. William D. Bartron at (860) 444-4301.
Very truly yours, R. K. MacManus Director, Nuclear Station Safety and Licensing
Enclosure:
- 1. Millstone Power Station Unit 2, Owner's Activity Report - Refueling Outage 20 Commitments made in this letter: None.
43(0(47
Serial No.11-396 Owner's Activity Report, 2R20 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 C. J. Sanders Project Manager U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08B3 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
Serial No.11-396 Docket No. 50-336 ENCLOSURE1 INSERVICE INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT REFUELING OUTAGE 20 MILLSTONE POWER STATION UNIT 2 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT NO. 2 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 20 Revision 0 Contents:
OAR- 1 Report Number: MP2-2R20 Table 1: Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service.
Table 2: Abstract of Repairs/Replacement Activities Required for Continued Service Prepared By: Date:
ISfProgram OW9%f Reviewed By: Date: "7tS*2.oII Independent Review Reviewed By: Date: vZ'//gQr-Auth zed-Nucl&r Inservice inSpetor
10 ., t , ý . ,
InIkk Form OAR-1 Owner's Activity Report WDOMiniW IAttcmn 1, E-AA-S-0 Page 1 of D rf. KI' knHa KAD'I 9WN1 DIoII Mill~tnnA NIu'~lA~ar Pnw~r ~t~tinn Rnn~ FAin, Rn~rI W~tArfArd flnnnA~tk'It flR~RF~
Rnnp Ferrv Road Waterford Connecticut 06385 I
Millstone Nuclear Power Station Unit No. 2 Commercial service date 12/26/1975 Refueling outage no. 20 (if applicable)
Current inspection interval 4th
( 1 $',2fno 3,T 4 m, other)
Current inspection period 1st (I st 2 no, 3rd)
Edition and Addenda of Section Xl applicable to the inspection plans 2004 Edition, No Addenda Date and revision of inspection plans 06/10/10 Revision 3.
Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans N/A Code Cases used: N-460. N-532-4. N-566-2. N-586-1, N-722 (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 Xl; and (c) the repair/replacement activities and evaluations supporting the completion of 2R20 conform to the requirements of Section Xl.
(refueling outage number)
Signed ISI Program Owner Date 07/05/2011 Owner orOwners De~ heeTit e 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 Connecticut and employed by HSB CT of Hartford, 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.
.,--r Commissions ,,9/'9ý Y" 7-/A7, ,*-."-
Inspep.trs Sigpatfure Naf'ona( Board, State, Provin ce and Endorsements Date
IC'77 Form OAR-1 Owner's Activity Report Atahmn 1,t-A-S1 00 Pag 2. f Table I Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number F-A / F1.30 Pipe Support 329020 Support member corrosion evaluated by Engineering as acceptable for continued service.
F-A / F1.30 Pipe Support 329020A Support member corrosion evaluated by
.Engineering as acceptable for continued service.
F-A / F1.30 Pipe Support 329048 Support member corrosion evaluated by Engineering as acceptable for continued service.
F-A / F1.20 Pipe Support 304029 Bolting thread engagement evaluated by Engineering as acceptable for continued service.
F-A / F1.30 Pipe Support 427110 Separation gap between support wall plate and wall evaluated by Engineering as acceptable for continued service.
F-A / F1.20 Pipe Support 301126 Spring can setting evaluated by Engineering as acceptable for continued service.
F-A / F1.10 Pipe Support 408014 Spring can setting evaluated by Engineering as acceptable for continued service.
F-A/ F1.10 Pipe Support 408017D Spring can setting and bolting thread engagement evaluated by Engineering as acceptable for continued service.
B-G-2 / B7.70 Valve 2-SI-245 Bolting Minor bolting thread damage evaluated by Engineering as acceptable for continued service.
F-A/ F1.20 Pipe Support 312012 Spring can setting evaluated by Engineering as acceptable for continued service.
C-H / C7.10 Valve 2-CH-192 Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.
C-H / C7.10 Valve 2-CS-091 Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.
B-P I B15.10 Valve 2-RC-35A Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.
C-H / C7.10 Valve 2-SI-073 Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.
Form OAR-1 Owner's Activity Report Attachent 1,ER-AA.I[S 0 3 of 0* 4 Examination Item Description Evaluation Description Category and Item Number C-H /C7.10 Valve 2-SI-411 Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.
C-H /C7.10 Valve 2-SI-432 Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for~continued service.
C-H I C7.10 Valve 2-SI-434 Evidence of leakage at bolted connection
,evaluated in accordance with Code Case N-566-2 as acceptable for continued service.
C-H / C7.10 Valve 2-SI-435 Evidence of leakage at bolted connection
.evaluated in accordance with Code-Case N-566-2 as acceptable for continued service.
C-H I C7.10 Valve 2-SI-645 Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.
C-H I C7.10 SDC heat exchanger X23A Evidence of leakage at bolted connection channel head cover evaluated in accordance with Code Case N-566-2 as acceptable for continued service.
Form OAR-1 Owner's Activity Report Attc 1 I Pe 4 Table 2 Abstract of Repair/Replacement Activities Required forContinued Service Code Class Item Description Description of Work Date Repair/Replacement Completed Plan Number Replace section of line 3 PipeSpool Y3"-HUD-130 between 2- 0811/2010 '53M20808003 Pipe Spool SW-1 78A and,2-SW-179A.
Replace a section of inlet 3Pipe Spool piping M2X183 due to erosion at elbow, 2"- 07/29/2010 53102186593 HUD-113.
Weld repair the 3 Pipe Flange degraded outlet flange 10/28/2009 53102292843 on spool SK-4256A.
3 Pipe Spool Replace portion of line 04/08/2011 53102358019 4"-EBD (B)-25.
Fabricate and install 3 Pipe Spool ;cooling piping for P40CM 04/26/2011 53M208051335 replacement motor.
"Fabricate replacement pipe spool SK-3650 for 3 Pipe Spool line 8-inch JGD-7 lAW 01/05/2011 53102403014 DCN MP2-10-01196-000.
Valves 1 Replace drain valves 2- 04/13/2011 53102288546 SI-024A and 2-SI-024B.
Rework corroded areas 3 Pipe Spool on spools for line 6-inch 04/15/2011 53102187069 JGD-4 per attachment 8 of CM-AA-NWP-101.
Pipe support M2HGR-2 Support 412016 -found indications Remove by an 04/23/2011 53102429523 ISI examination.
Replace 2 X 3/4-inch 3 reducing bushing on 04/24/2011 53102432023 Pipe Fitting X18A upstream of valve 2-SW-92A.
Replace section of line 3 PipeSpool 3"-HUD-130 between 2- 08/11/2010 53M20808003 Pipe Spool SW-1 78A and 2-SW-179A.
Replace a section of inlet 3 Pipe Spool piping M2X183 due to erosion at elbow, 2"- 07/29/2010 -53102186593 HUD-113.
Weld repair the 3 Pipe Flange degraded outlet flange 10/28/2009 53102292843
_ on spool SK-4256A. I