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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARWBL-23-038, American Society of Mechanical Engineers, Section XI, Third 10-Year Inservice Inspection Interval, Inservice Inspection Owners Activity Report for Cycle 18 Operation2023-08-0707 August 2023 American Society of Mechanical Engineers, Section XI, Third 10-Year Inservice Inspection Interval, Inservice Inspection Owners Activity Report for Cycle 18 Operation CNL-22-109, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements2022-12-22022 December 2022 Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements WBL-22-057, American Society of Mechanical Engineers, Section XI, First 10-Year Inservice Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 4 Operation2022-09-26026 September 2022 American Society of Mechanical Engineers, Section XI, First 10-Year Inservice Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 4 Operation WBL-22-018, Cycle F214 Steam Generator Tube Inspection Report2022-03-28028 March 2022 Cycle F214 Steam Generator Tube Inspection Report WBL-22-006, American Society of Mechanical Engineers, Section XI, Third 10-Year Inservice Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 17 Operation2022-03-0404 March 2022 American Society of Mechanical Engineers, Section XI, Third 10-Year Inservice Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 17 Operation WBL-21-036, Supplement to the American Society of Mechanical Engineers, Section XI, First 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 3 Operation2021-08-0505 August 2021 Supplement to the American Society of Mechanical Engineers, Section XI, First 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 3 Operation WBL-21-028, Cycle 3 Steam Generator Tube Inspection Report2021-05-10010 May 2021 Cycle 3 Steam Generator Tube Inspection Report WBL-21-008, American Society of Mechanical Engineers, Section XI, First 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 3 Operation2021-02-11011 February 2021 American Society of Mechanical Engineers, Section XI, First 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 3 Operation WBL-20-049, Augmented Inservice Test Program, Revision 22020-10-21021 October 2020 Augmented Inservice Test Program, Revision 2 WBL-20-042, American Society of Mechanical Engineers, Section XI, Third 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 16 Operation2020-09-0303 September 2020 American Society of Mechanical Engineers, Section XI, Third 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 16 Operation L-19-041, Cycle 2 Steam Generator Tube Inspection Report2019-08-27027 August 2019 Cycle 2 Steam Generator Tube Inspection Report L-19-045, American Society of Mechanical Engineers, Section XI, First 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 2 Operation2019-08-14014 August 2019 American Society of Mechanical Engineers, Section XI, First 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 2 Operation L-19-008, American Society of Mechanical Engineers, Section Xl, Third 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 15 Operation2019-01-24024 January 2019 American Society of Mechanical Engineers, Section Xl, Third 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 15 Operation ML18047A3702018-02-16016 February 2018 Cycle 1 Steam Generator Tube Inspection Report ML17214A4942017-08-0202 August 2017 Updated Inservice Test Program ML17212A5502017-07-31031 July 2017 American Society of Mechanical Engin, Section XI, Second and Third 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 14 Operation ML17005A3182017-01-0303 January 2017 American Society of Mechanical Engineers, Section XI, Initial Inservice Inspection Report ML16293A5652016-10-0505 October 2016 Report No. R-P2455, Wall Thickness Profile Sheet. (Sketch) ML16293A5522016-10-0505 October 2016 Report No. R-P2184, Wall Thickness Profile Sheet. (Sketch) NL-16-135, Report No. R-P2438, Wall Thickness Profile Sheet. (Sketch)2016-10-0505 October 2016 Report No. R-P2438, Wall Thickness Profile Sheet. (Sketch) ML16293A5592016-10-0505 October 2016 Report No. R-P2439, Wall Thickness Profile Sheet. (Sketch) ML16293A5672016-10-0505 October 2016 Report No. R-P2472, Wall Thickness Profile Sheet. (Sketch) NL-16-135, Report No. R-P2439, Wall Thickness Profile Sheet. (Sketch)2016-10-0505 October 2016 Report No. R-P2439, Wall Thickness Profile Sheet. (Sketch) ML16293A5662016-10-0505 October 2016 Report No. R-P2466, Wall Thickness Profile Sheet. (Sketch) NL-16-135, Report No. R-P2455, Wall Thickness Profile Sheet. (Sketch)2016-10-0505 October 2016 Report No. R-P2455, Wall Thickness Profile Sheet. (Sketch) NL-16-135, Report No. R-P2440, Wall Thickness Profile Sheet. (Sketch)2016-10-0505 October 2016 Report No. R-P2440, Wall Thickness Profile Sheet. (Sketch) NL-16-135, Report No. R-P2444, Wall Thickness Profile Sheet. (Sketch)2016-10-0505 October 2016 Report No. R-P2444, Wall Thickness Profile Sheet. (Sketch) ML16293A5642016-10-0505 October 2016 Report No. R-P2444, Wall Thickness Profile Sheet. (Sketch) NL-16-135, Report No. R-P2443, Wall Thickness Profile Sheet. (Sketch)2016-10-0505 October 2016 Report No. R-P2443, Wall Thickness Profile Sheet. (Sketch) ML16293A5632016-10-0505 October 2016 Report No. R-P2443, Wall Thickness Profile Sheet. (Sketch) NL-16-135, Report No. R-P2442, Wall Thickness Profile Sheet. (Sketch)2016-10-0505 October 2016 Report No. R-P2442, Wall Thickness Profile Sheet. (Sketch) ML16293A5622016-10-0505 October 2016 Report No. R-P2442, Wall Thickness Profile Sheet. (Sketch) ML16293A5582016-10-0505 October 2016 Report No. R-P2438, Wall Thickness Profile Sheet. (Sketch) ML16293A5602016-10-0505 October 2016 Report No. R-P2440, Wall Thickness Profile Sheet. (Sketch) NL-16-135, Report No. R-P2441, Wall Thickness Profile Sheet. (Sketch)2016-10-0505 October 2016 Report No. R-P2441, Wall Thickness Profile Sheet. (Sketch) ML16293A5612016-10-0505 October 2016 Report No. R-P2441, Wall Thickness Profile Sheet. (Sketch) NL-16-135, Report No. R-P2437, Wall Thickness Profile Sheet. (Sketch)2016-10-0505 October 2016 Report No. R-P2437, Wall Thickness Profile Sheet. (Sketch) ML16293A3342016-10-0505 October 2016 Watts Bar Nuclear Plant (Wbn), Unit 2 - Request for Approval of a Relief from the American Society of Mechanical Engineers, Section Xi Coverage Examinations for Preservice Inspection (PSI) - Number WBN-2/PSI-1, Revision 1, and Submittal of ML16293A5502016-10-0505 October 2016 Report No. R-P2182, Wall Thickness Profile Sheet. (Sketch) NL-16-135, Report No. R-P2182, Wall Thickness Profile Sheet. (Sketch)2016-10-0505 October 2016 Report No. R-P2182, Wall Thickness Profile Sheet. (Sketch) NL-16-135, Report No. R-P2184, Wall Thickness Profile Sheet. (Sketch)2016-10-0505 October 2016 Report No. R-P2184, Wall Thickness Profile Sheet. (Sketch) NL-16-135, Report No. R-P2183, Wall Thickness Profile Sheet. (Sketch)2016-10-0505 October 2016 Report No. R-P2183, Wall Thickness Profile Sheet. (Sketch) ML16293A5532016-10-0505 October 2016 Report No. R-P2185, Wall Thickness Profile Sheet. (Sketch) NL-16-135, Report No. R-P2185, Wall Thickness Profile Sheet. (Sketch)2016-10-0505 October 2016 Report No. R-P2185, Wall Thickness Profile Sheet. (Sketch) NL-16-135, Report No. R-P2265, Wall Thickness Profile Sheet. (Sketch)2016-10-0505 October 2016 Report No. R-P2265, Wall Thickness Profile Sheet. (Sketch) ML16293A5492016-10-0505 October 2016 Report No. R-P2148, Wall Thickness Profile Sheet. (Sketch) NL-16-135, Report No. R-P2475, Wall Thickness Profile Sheet. (Sketch)2016-10-0505 October 2016 Report No. R-P2475, Wall Thickness Profile Sheet. (Sketch) ML16293A5572016-10-0505 October 2016 Report No. R-P2437, Wall Thickness Profile Sheet. (Sketch) NL-16-135, Report No. R-P3450, Wall Thickness Profile Sheet. (Sketch)2016-10-0505 October 2016 Report No. R-P3450, Wall Thickness Profile Sheet. (Sketch) CNL-16-135, Report No. R-P3450, Wall Thickness Profile Sheet. (Sketch)2016-10-0505 October 2016 Report No. R-P3450, Wall Thickness Profile Sheet. (Sketch) 2023-08-07
[Table view] Category:Letter type:WBL
MONTHYEARWBL-24-003, Emergency Plan Implementing Procedure Revision. Includes EPIP-6, Revision 58, Activation and Operation of the Technical Support Center (TSC)2024-01-30030 January 2024 Emergency Plan Implementing Procedure Revision. Includes EPIP-6, Revision 58, Activation and Operation of the Technical Support Center (TSC) WBL-23-058, Emergency Plan Implementing Procedure Revision. Includes EPIP-5, Revision 63, General Emergency2023-12-19019 December 2023 Emergency Plan Implementing Procedure Revision. Includes EPIP-5, Revision 63, General Emergency WBL-23-055, of the Unit 2 Cycle 6 Core Operating Limits Report2023-11-22022 November 2023 of the Unit 2 Cycle 6 Core Operating Limits Report WBL-23-051, Response to an Apparent Violation (EA-23-117); NRC Special Inspection Report 50-390, 391/2023440, Preliminary Greater than Green and Apparent Violation2023-11-22022 November 2023 Response to an Apparent Violation (EA-23-117); NRC Special Inspection Report 50-390, 391/2023440, Preliminary Greater than Green and Apparent Violation WBL-23-052, Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual2023-11-0808 November 2023 Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual WBL-23-045, 10 CFR 50.59 Summary Report2023-11-0707 November 2023 10 CFR 50.59 Summary Report WBL-23-038, American Society of Mechanical Engineers, Section XI, Third 10-Year Inservice Inspection Interval, Inservice Inspection Owners Activity Report for Cycle 18 Operation2023-08-0707 August 2023 American Society of Mechanical Engineers, Section XI, Third 10-Year Inservice Inspection Interval, Inservice Inspection Owners Activity Report for Cycle 18 Operation WBL-23-033, Emergency Plan Implementing Procedure Revision. Includes EPIP 1, Revision 59, Emergency Plan Classification Logic2023-07-13013 July 2023 Emergency Plan Implementing Procedure Revision. Includes EPIP 1, Revision 59, Emergency Plan Classification Logic WBL-23-026, Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2023-01 - Preparation and Scheduling of Operator Licensing Examinations2023-05-18018 May 2023 Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2023-01 - Preparation and Scheduling of Operator Licensing Examinations WBL-23-021, 2022 Annual Radiological Environmental Operating Report2023-05-11011 May 2023 2022 Annual Radiological Environmental Operating Report WBL-23-025, Emergency Plan Implementing Procedure Revision2023-05-0505 May 2023 Emergency Plan Implementing Procedure Revision WBL-23-020, Annual Non-Radiological Environmental Operating Report - 20222023-05-0404 May 2023 Annual Non-Radiological Environmental Operating Report - 2022 WBL-23-023, of Cycle 19 Core Operating Limit Report2023-04-27027 April 2023 of Cycle 19 Core Operating Limit Report WBL-23-019, Annual Radioactive Effluent Release Report2023-04-27027 April 2023 Annual Radioactive Effluent Release Report WBL-23-018, Revised Pressure and Temperature Limits Report (PTLR)2023-04-10010 April 2023 Revised Pressure and Temperature Limits Report (PTLR) WBL-23-013, 10 CFR 50.46 Annual Report for 20222023-03-29029 March 2023 10 CFR 50.46 Annual Report for 2022 WBL-23-015, Emergency Plan Implementing Procedure Revision2023-03-21021 March 2023 Emergency Plan Implementing Procedure Revision WBL-23-010, Emergency Plan Implementing Procedure Revisions2023-02-0909 February 2023 Emergency Plan Implementing Procedure Revisions WBL-23-008, Unit 1 Revision 1 of the Cycle 18 Core Operating Limits Report (COLR) and Units 2 Revision 1 of the Cycle 5 Core Operating Limits Report (COLR)2023-02-0707 February 2023 Unit 1 Revision 1 of the Cycle 18 Core Operating Limits Report (COLR) and Units 2 Revision 1 of the Cycle 5 Core Operating Limits Report (COLR) WBL-23-003, Emergency Plan Implementing Procedure Revision. Includes EPIP-16, Revision 25, Termination of the Emergency and Recovery2023-01-12012 January 2023 Emergency Plan Implementing Procedure Revision. Includes EPIP-16, Revision 25, Termination of the Emergency and Recovery WBL-23-001, Emergency Plan Implementing Procedure Revision. Includes EPIP-1, Revision 57, Emergency Plan Classification Logic2023-01-10010 January 2023 Emergency Plan Implementing Procedure Revision. Includes EPIP-1, Revision 57, Emergency Plan Classification Logic WBL-22-068, Submittal of Emergency Plan Implementing Procedure Revision2022-12-12012 December 2022 Submittal of Emergency Plan Implementing Procedure Revision WBL-22-062, Emergency Plan Implementing Procedure Revision. Includes EPIP-13, Revision 34, Initial Dose Assessment for Radiological Emeregencies2022-11-0101 November 2022 Emergency Plan Implementing Procedure Revision. Includes EPIP-13, Revision 34, Initial Dose Assessment for Radiological Emeregencies WBL-22-061, Unit 2 - Emergency Plan Implementing Procedure Revisions2022-10-17017 October 2022 Unit 2 - Emergency Plan Implementing Procedure Revisions WBL-22-060, Unit 2 - Emergency Plan Implementing Procedure Revisions. Includes EPIP-6, Revision 56, Activation and Operation of the Technical Support Center (TSC)2022-10-17017 October 2022 Unit 2 - Emergency Plan Implementing Procedure Revisions. Includes EPIP-6, Revision 56, Activation and Operation of the Technical Support Center (TSC) WBL-22-057, American Society of Mechanical Engineers, Section XI, First 10-Year Inservice Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 4 Operation2022-09-26026 September 2022 American Society of Mechanical Engineers, Section XI, First 10-Year Inservice Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 4 Operation WBL-22-046, Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2)2022-09-0808 September 2022 Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2) WBL-22-034, Update to Fire Protection Report Figures Redacted2022-08-0101 August 2022 Update to Fire Protection Report Figures Redacted WBL-22-037, Emergency Plan Implementing Procedure Revision. Including EPIP-13, Revision 33, Initial Dose Assessment for Radiological Emergencies2022-07-14014 July 2022 Emergency Plan Implementing Procedure Revision. Including EPIP-13, Revision 33, Initial Dose Assessment for Radiological Emergencies WBL-22-032, Dual Unit Updated Final Safety Analysis Report (UFSAR) Amendment 42022-06-0101 June 2022 Dual Unit Updated Final Safety Analysis Report (UFSAR) Amendment 4 WBL-22-033, Emergency Plan Implementing Procedure Revisions2022-06-0101 June 2022 Emergency Plan Implementing Procedure Revisions WBL-22-030, Emergency Plan Implementing Procedure Revision2022-05-18018 May 2022 Emergency Plan Implementing Procedure Revision WBL-22-026, Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual2022-05-11011 May 2022 Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual WBL-22-015, Update to Fire Protection Report2022-05-11011 May 2022 Update to Fire Protection Report WBL-22-021, Unit 2 - 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022 Unit 2 - 2021 Annual Radiological Environmental Operating Report WBL-22-028, of the Unit 2 Cycle 5 Core Operating Limits Report (COLR)2022-05-0404 May 2022 of the Unit 2 Cycle 5 Core Operating Limits Report (COLR) WBL-22-019, Annual Radioactive Effluent Release Report2022-04-29029 April 2022 Annual Radioactive Effluent Release Report WBL-22-024, Unit 2 - Emergency Plan Implementing Procedure Revisions. Includes EPIP 14, Revision 292022-04-27027 April 2022 Unit 2 - Emergency Plan Implementing Procedure Revisions. Includes EPIP 14, Revision 29 WBL-22-008, 10 CFR 50.59 Summary Report2022-04-27027 April 2022 10 CFR 50.59 Summary Report WBL-22-020, Annual Non-Radiological Environmental Operating Report - 20212022-04-27027 April 2022 Annual Non-Radiological Environmental Operating Report - 2021 WBL-22-018, Cycle F214 Steam Generator Tube Inspection Report2022-03-28028 March 2022 Cycle F214 Steam Generator Tube Inspection Report WBL-22-017, Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report2022-03-22022 March 2022 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report WBL-22-016, Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2022-01 - Preparation and Scheduling of Operator Licensing Examinations2022-03-17017 March 2022 Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2022-01 - Preparation and Scheduling of Operator Licensing Examinations WBL-22-009, Submittal of Initial Operator Licensing Outline2022-03-10010 March 2022 Submittal of Initial Operator Licensing Outline WBL-22-006, American Society of Mechanical Engineers, Section XI, Third 10-Year Inservice Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 17 Operation2022-03-0404 March 2022 American Society of Mechanical Engineers, Section XI, Third 10-Year Inservice Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 17 Operation WBL-22-012, Submittal of 10 CFR 50.46 - Annual Report for Watts Bar Nuclear Plant Units 1 and 22022-03-0202 March 2022 Submittal of 10 CFR 50.46 - Annual Report for Watts Bar Nuclear Plant Units 1 and 2 WBL-22-010, Response to Request for Confirmation of Information Regarding the Watts Bar Nuclear Plant, Unit 2, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Final Report2022-03-0202 March 2022 Response to Request for Confirmation of Information Regarding the Watts Bar Nuclear Plant, Unit 2, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Final Report WBL-22-007, Unit 2 - Emergency Plan Implementing Procedure Revision2022-02-17017 February 2022 Unit 2 - Emergency Plan Implementing Procedure Revision WBL-21-057, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-12-16016 December 2021 Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report WBL-21-056, Revised Pressure and Temperature Limits Report (PTLR)2021-12-0909 December 2021 Revised Pressure and Temperature Limits Report (PTLR) 2024-01-30
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TENNESSEE 1\/4 VALLEY AUTHORITY Post Office Box 2000 , Spring City, Tennessee 37381 WBL-21 -008 February 11 , 2021 10 CFR 50.55a ATTN : Document Control Desk U.S . Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 Facility Operating License No. NPF-96 NRC Docket No. 50-391
Subject:
American Society of Mechanical Engineers,Section XI, First 10-Year Inspection Interval, lnservice Inspection Owner's Activity Report For Cycle 3 Operation The Tennessee Valley Authority is submitting the Watts Bar Nuclear Plant (WBN), Unit 2, American Society of Mechanical Engineers (ASME),Section XI, Owner's Activity Report for Unit 2 Cycle 3 operation as required by Article IWA-6000,Section XI , Division 1. The report is contained in the enclosure to this letter and is in accordance with the requirements of ASME Code Case N-532-5, "Repair/Replacement Activity Documentation Requirements and lnservice Inspection Summary Report Preparation and Submission ."
The report is an overview of the results from inservice examinations that were performed on components within the ASME Section XI boundary, up to and including the Unit 2 Cycle 3 refueling outage, during the second period of the first inspection interval. The applicable provisions of the ASME Code require that this report be submitted 90 days from the end of the applicable outage, i.e., by February 17, 2021.
There are no new regulatory commitments associated with this submittal. If you have questions regarding this letter, please contact Tony Brown, WBN Licensing Manager, at (423) 365-7720 .
Anthony L. Williams IV Site Vice President Watts Bar Nuclear Plant
U.S. Nuclear Regulatory Commission WBL-21-008 Page 2 February 11, 2021
Enclosure:
American Society of Mechanical Engineers,Section XI, First 10-Year lnservice Inspection Interval, lnservice Inspection Owner's Activity Report for Cycle 3 Operation (Form OAR-1) cc:
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Watts Bar Nuclear Plant NRR Project Manager- Watts Bar Nuclear Plant
ENCLOSURE TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 2 AMERICAN SOCIETY OF MECHANICAL ENGINEERS, SECTION XI, FIRST 10-YEAR INSPECTION INTERVAL, INSERVICE INSPECTION OWNER'S ACTIVITY REPORT FOR CYCLE 3 OPERATION
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number U2R3 Plant Watts Bar Nuclear Plant, P.O. Box 2000, Spring City, TN 37381-2000 Unit No. 2 Commercial Service Date October 19, 2016 Refueling Outage No. U2R3 (if applicable)
Current Inspection Interval 1st (1", 2, 3, 4" , other)
Current Inspection Period 2nd ISI/SPT - 2007 Edition, 2008 Addenda Edition and Addenda of Section XI applicable to the Inspection Plans IWE - 2013 Edition ISi - December 10, 2020 / 2-TRl-0-10.1, Revision 006 IWE - September 07, 2018 / O-Tl -100.012, Revision 000 Date/ Revi sion of Inspection Plan s SPT - August 24, 2020 / O-Tl -100.009 Revision 003 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the in spection plan s 2007 Edition, 2008 Addenda Code Cases used: N-532-5, N-586-1, N-716-1, N-722-1, N-729-6, N-770-5 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 U2R3 conform to the requirements of Section XI (refueling outage number)
Signed I>-.__/ John Norman , Repair/Replacement program owner Date 2/3/21 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors The Hartford Steam Boiler of Inspection and Insurance and employed by Company 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 ha s performed all activities represented by this report in accordance with the requirements of Section XI.
By signing thi s certificate neither the Inspector nor hi s 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 Commissions 15440 Al, I, N, R
~ p e c t o r ' s Signature (National Board Number and Endorsement)
Date 03Feb21 E-lofS
TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description While performing the enhanced visual examination of the WBN Unit 2 Reactor Vessel Closure Head an area of discoloration was discovered within the 1" annular area of CRDM penetration 57.
In accordance with ASME CC N-729-6, -3140(c) this was documented as a relevant condition.
Previous data of this penetration 57 was reviewed and the condition has existed since U2Rl and has remained unchanged since.
The source of leakage was most likely minor leakage when disconnecting one of the mechanical connections above the head for refueling activities. This was an isolated event that Reactor Vessel occurred multiple operating cycles ago and determination of the N-729-6 / 84.10 Closure Head CRDM source cannot be done conclusively.
Penetration 57 There were no boric acid crystals associated with this indication to be removed. The examiners attempted to remove some of the surface corrosion to evaluate for any degradation. After attempting to scrap some of the corrosion away a subsequent VE was performed and there was no measurable material loss due to corrosion to be evaluated.
Considering this indication has remained unchanged over multiple operating cycles, there was no boric acid residue or crystals observed, and there was no measurable material loss, the indication was not considered indicative of possible nozzle leakage While performing the enhanced visual examination of the WBN Unit 2 Reactor Vessel Closure Head a white material was discovered underneath the degraded head coating. After some mechanical agitation of the head coating the debris was blown away and revea led an additional white spot outside the examination area . A follow-up examination removed additional coating from the annular area of the penetration and confirmed the white substance wa s under the coating and did not appear to have run down the CRDM tube . The condition was declared a relevant condition and an additional assessment was performed Reactor Vessel to determine if the condition was indicative of possible nozzle N-729-6 / 84.10 Closure Head CRDM leak.
Penetration 33 There was insufficient sample quantity to perform any chemical analysis on site. The swabs were analyzed using gamma spectroscopy on site with a 900-second count time, and no gamma activity was detected. The swabs were shipped to Teledyne Brown for additional analysis. No gamma activity was detected using a 3600-second count time. The swabs were analyzed with an extended count (54000 seconds), and Co-58 and Co-60 were detected . Based on the ratio of C0-58/Co-60, this relevant condition was not indicative of an active RCS leak.
After the extended count gamma spectroscopy was performed the samples were sent to a secondary laboratory in an attempt E-2 of 5
to identify the material. The contracted Chemistry Lab, MCL, stated "The sma ll amount of residue on the swabs limited the amount of material available to be removed for analysis. As free-standing values the results offer no interpretable clues as to the identity of the substance on the swabs. The major constituents found are iron, zinc, chloride and sulfate. The proportion of zinc to iron may offer a clue as to the source of the residue ... " However, the lab was unable to provide any conclusive material identification .
After the samples for chemical analysis were taken, the white material was completely removed and a subsequent VE of the affected area was performed . After the material was removed there were no signs of degradation to be evaluated .
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TABLE 2 Abstract of Repairs/replacement Activities for Continued Service Item Description Date Repair/Replacement Code Class Description of Work Completed Plan Number Replace Cooler Coil due 2B-B Penetration Room 3 to through wall tube 7/23/2019 117348693 Cooler Coil leak.
Replace length of pipe 3 2" eves Pipe due to through wall pin 2/18/2020 120394576 hole leak.
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REPORTING REQUIRED BY 10 CFR 50.55a(b)(2)(ix)
ASME Section XI, Subsection IWE Steel Containment Vessel Inspection Program 10 CFR 50.55a(b)(2)(ix) requires the reporting of inaccessible areas and additional examinations identified during the performance of ASME Section XI, Subsection IWE Steel Containment Vessel Inspection Program when conditions exist in accessible areas that could indicate the presence of or result in degradation to such inaccessible areas.
(1) bolted connection that was disassembled, was inspected in accordance with IWE Containment Vessel Inspection Program during this cycle . There were no conditions observed that would indicate the presence of or result in degradation to inaccessible areas of the containment vessel.
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