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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:L
MONTHYEARL-20-006, Unit 2, Emergency Plan Implementing Procedure Revision2020-02-10010 February 2020 Unit 2, Emergency Plan Implementing Procedure Revision L-12-001, Revised Response to NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System2019-12-26026 December 2019 Revised Response to NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System L-19-061, Unit 2 - Emergency Plan Implementing Procedure Revision2019-12-16016 December 2019 Unit 2 - Emergency Plan Implementing Procedure Revision L-19-058, Statement of Payment of Civil Penalty2019-12-11011 December 2019 Statement of Payment of Civil Penalty L-19-054, Unit 2 - Emergency Plan Implementing Procedure Revision2019-12-0505 December 2019 Unit 2 - Emergency Plan Implementing Procedure Revision L-19-046, Notification of Readiness for NRC Independent Review to Confirm Chilling Effect Letter and Cross-Cutting Issue Closure Criteria Have Been Met2019-10-0303 October 2019 Notification of Readiness for NRC Independent Review to Confirm Chilling Effect Letter and Cross-Cutting Issue Closure Criteria Have Been Met L-19-052, Revision 47 to Emergency Plan Implementing Procedure EPIP 12, Emergency Equipment and Supplies2019-09-30030 September 2019 Revision 47 to Emergency Plan Implementing Procedure EPIP 12, Emergency Equipment and Supplies L-19-048, Response to Apparent Violation in NRC Inspection Report 05000390/2019013 and 05000391/2019013, EA-19-0422019-09-12012 September 2019 Response to Apparent Violation in NRC Inspection Report 05000390/2019013 and 05000391/2019013, EA-19-042 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-19-044, Unit 2 - Forward Emergency Plan Implementing Procedure Revisions2019-08-0808 August 2019 Unit 2 - Forward Emergency Plan Implementing Procedure Revisions L-19-036, Notification of Readiness for NRC Inspection Procedure 95001 Inspection2019-06-20020 June 2019 Notification of Readiness for NRC Inspection Procedure 95001 Inspection L-19-034, Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report2019-06-18018 June 2019 Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report L-19-031, Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2019-02 - Preparation and Scheduling of Operator Licensing Examinations2019-05-15015 May 2019 Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2019-02 - Preparation and Scheduling of Operator Licensing Examinations L-19-016, Annual Radiological Environmental Operating Report - 20182019-05-15015 May 2019 Annual Radiological Environmental Operating Report - 2018 L-19-029, Submittal of Revision 0 of Cycle 3 Core Operating Limits Report2019-04-24024 April 2019 Submittal of Revision 0 of Cycle 3 Core Operating Limits Report L-19-015, Annual Non-Radiological Environmental Operating Report - 20182019-04-11011 April 2019 Annual Non-Radiological Environmental Operating Report - 2018 L-19-026, Revised Pressure and Temperature Limits Report (PTLR)2019-04-0404 April 2019 Revised Pressure and Temperature Limits Report (PTLR) L-19-023, Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual2019-03-19019 March 2019 Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual L-19-024, Unit 2 - Emergency Plan Implementing Procedures Revision2019-03-0707 March 2019 Unit 2 - Emergency Plan Implementing Procedures Revision L-19-019, Transmittal of 10 CFR 50.46 - 30-Day and Annual Report for Watts Bar Nuclear Plant, Units 1 and 22019-03-0707 March 2019 Transmittal of 10 CFR 50.46 - 30-Day and Annual Report for Watts Bar Nuclear Plant, Units 1 and 2 L-19-011, Plant, Unit 1 - Revision 1 of the Cycle 16 Core Operating Limits Report (COLR)2019-01-29029 January 2019 Plant, Unit 1 - Revision 1 of the Cycle 16 Core Operating Limits Report (COLR) 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 L-18-001, Notification of Readiness for NRC Inspection Procedure 95001 Inspection2018-11-26026 November 2018 Notification of Readiness for NRC Inspection Procedure 95001 Inspection L-04-001, Completion of Action Required in Response to NRC Bulletin 2004-01: Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors2018-01-25025 January 2018 Completion of Action Required in Response to NRC Bulletin 2004-01: Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors L-11-001, Submittal of 30-Day Response to NRC Bulletin 2011-01, Mitigating Strategies.2015-09-24024 September 2015 Submittal of 30-Day Response to NRC Bulletin 2011-01, Mitigating Strategies. L-11-011, Transmittal of Response to NRC Bulletin 2011-01, Mitigating Strategies.2015-06-29029 June 2015 Transmittal of Response to NRC Bulletin 2011-01, Mitigating Strategies. L-88-017, Response Clarification to Generic Letter 88-0172013-08-13013 August 2013 Response Clarification to Generic Letter 88-017 L-03-004, Tennessee Valley Authority Response to Nuclear Regulatory Commission Bulletin 2003-04, Rebaselining of Data in the Nuclear Materials Management and Safeguards System, Dated October 8, 20032003-12-18018 December 2003 Tennessee Valley Authority Response to Nuclear Regulatory Commission Bulletin 2003-04, Rebaselining of Data in the Nuclear Materials Management and Safeguards System, Dated October 8, 2003 2020-02-10
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Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 wBL-19-008 January 24,2019 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390
Subject:
American Society of Mechanical Engineers, Section Xl, Third 10-Year lnspection lnterual, lnservice lnspection Owner's Activity Report For Cycle 15 Operation The Tennessee Valley Authority is submitting the Watts Bar Nuclear Plant, Unit 1, American Society of Mechanical Engineers (ASME), Section Xl, Owner's Activity Report for Unit 1 Cycle 15 operation as required by Article IWA-6000, Section Xl, 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 lnspection 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 Xl boundary, up to and including the Unit 1 Cycle 15 refueling outage, during the first period of the third 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 January 25,2019.
There are no new regulatory commitments associated with this submittal. lf you have questions regarding this letter, please contact Kim Hulvey at @23) 365-7720.
Respectfully, n
Paul Simmons Site Vice President Watts Bar Nuclear Plant
U. S. Nuclear Regulatory Commission Page 2 January 24,2019
Enclosure:
American Society of Mechanical Engineers, Section Xl, Third 1O-Year lnservice lnspection lnterval, lnservice lnspection Owner's Activity Report for Cycle 15 Operation (Form OAR-1) cc (Enclosure):
NRC RegionalAdministrator - Region ll NRC Senior Resident lnspector NRR Project Manager
ENCLOSURE TEN NESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT {
AMERICAN SOCIETY OF II'IECHANICAL ENGINEERS, SECTION XI, THIRD 1 O.YEAR INSPECTION INTERVAL, INSERVICE INSPECTION OWNER'S ACTIVITY REPORT FOR CYCLE 15 OPERATION
FORM OAR-I OWNER,S ACTIVIW REPORT Report Number U1R15 Plant Watts Bar Nuclear Plant, P.O. Box 2000, Spring City, TN 37381-2000 Unit No. Commercial Service Date May 27, 1996 Refueling Outage No. U1R15 (if applicable)
Current lnspection lnterval
'r4 Current lnspection Period L st (l*,2no, 3t )
lSl/SPT - 2007 Edition, 2008 Addenda Edition and Addenda of Section Xl applicable to the lnspection Plans IWE - 2013 Edition lSl - January L7,20L9 / 1-TRl-0-10.3, Revision 003 lWE - September 07,2018 I O-tl-t00.012, Revision 000 Date / Revision of lnspection Plans SPT - April 29,20t7 I 0lt-t00.009 R002 Edition and Addenda of Section xl applicable to repair/replacement activities, lf different than the lnspection plans 2OO7 Edition 2008 Addenda Code Cases used: N-513-3, N-532-5, N-586-1, N-716-1, N-722-L, N-729-4, N-770-2 CERTIFrcATE OF COI{FORMAilCE I certify that (a) the statements made in this report are correcg (b) the examinations and tests, meet the lnspection Plan as required by the ASME Code, Section Xl; and (c) the repair/replacement activities and el,aluations supporting the completion of U1R15 (refueling outagc nurn ber) confurm to the requirements of Sectlon Xl Signed Shane Norton, Rep6ir Replacement and lnservice lnspection Program Owner
,/rt/,. _
CERNFrcAIE OF II{SERVICE INSPECTION l, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel lnspectors and the State or The Hartford Stam Boiler of lnspection and lnsurance Province of Tennessee and employed by Company Hartford, Connecticut have inspected the ftems described in this Owner's Actlvlty Report, and state that to the best of my knowledge and belief, the Owner has performed all actMtles represented by this report in accordance with the requirements of Section Xl By s'rgning this certificate nelther the lnspector nor hls employer makes any warranty expressed or implied concerning the repair/ replacement activities and evaluation descrlbed in this report. Furthermore, neither the lnspector nor his employer shall be liable ln any manner for any personal Commissions NB 14057tNR, TN 4132 Signature National Board, State, Province, and Endorsements
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TABLE 1 ITEMS W]TH FI.AWS OR RETEVANT COI{DITIOT{STHAT REQUIRED EVATUATION FOR CONNilUED SERVICE Examination Category and Item Number ltem Description Eval uation Description cR 1437950 A through wall leak in a 10" diameter Class 3 pipe was evaluated in accordance with ASME Code Case N-513-3. The leak rate was minimal and would have no effect on the D-B lD2.L0 10" High Pressure Fire Protection Piping safety function of the system. This condition is within the bounding condition for a flooding impact. therefore flooding is not a concern. Civil Analysis showed that structural integrity was maintained and there was no concern for a line break at the leak location.
cR 1333681 A through wall leak in a 10" diameter Class 3 pipe was evaluated in accordance with ASME Code Case N-513-3. The leak rate was minimal and would have no effect on the D-B / D2.L0 10" High Pressure Fire Protection Piping safety function of the system. This condition is within the bounding condition for a flooding impact. therefore flooding is not a concern. Civi! Analysis showed that structural integrity was maintained and there was no concern for a line break at the leak location.
cR 14s387r A rigid support was observed to be loose in the field. Civil Engineering evaluated the support drawings and concluded the support was not designed to provide support in the direction that it moved. Due to the flat base F-A I Fl.100 Safety lnjection System Rigid Hanger plate of the support being attached to a curved surface, there exists a small gap between the base plate and the wall on both sides. This small gap allows the support to move in the axial direction. Per design output, this support is not designed to resist movement in the axial direction.
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TABLE 2 ABSTRACT OF REPAIRS, REPIACEMENNi, OR CORRECTIVE MEAISURES REqUIRED FOR CONTITIUED SERVICE Item Description Date Repair/Replacement Code Class Description of Work Completed Plan Number containment Lower Replaced leaking coil with 3 L0/2212018 1186467L4 Compartment Cooler new coil.
10" High Pressure Fire Repaired through wall 3 0210s/2018 119003 4s7 Protection Piping leak.
Containment Lower lnstalled blank off plates 3 LLl06/2018 119954518 Compartment Cooler on (3) coils to stop leaks.
10" High Pressure Fire Repaired through wall 3 ru28/2018 119798618 Protection Piping leak.
MC Equipment Hatch Bolting Replaced rnissing washer. r0los/2018 119049319 Loop 2 Steam Generator 2 Upper Lateral Support Tightened Loose Bolting. LOlL2l2018 Lr992L087 Splice Plate Containment Lower lnstalled blank off plates 3 Ll08l201e Lr9877091 Compartment Cooler on (1) coils to stop leaks.
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REPORTING REQUIRED BY 10 cFR 50.ssa(bX2Xix)
ASME Section Xl, Subsectlon IWE Steel Contalnment Vesse! lnspection Program 10 CFR 50.55a(bX2Xix) requlres the reporting of inaccessible areas and additional examinations identified during the performance of ASME Section Xl, Subsection IWE Steel Containment Vessel lnspection Program when conditions exist in accessible areas that could indicate the presence of or result in degradation to such inaccessible areas.
The accessible portion of the interior and exterior surface of the containment vessel, including (7) bolted connections that were disassembled, were inspected in accordance with IWE Containment Vessel lnspection Program during this cycle. There were no conditions observed that would lndicate the presence of or result in degradation to inaccessible areas of the containment vessel during performance of those examinations.
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