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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARL-23-051, Plan, Nineteenth Inservice Inspection Summary Report2023-06-22022 June 2023 Plan, Nineteenth Inservice Inspection Summary Report L-21-282, Proposed Inservice Inspection Alternative IR-0632022-01-0505 January 2022 Proposed Inservice Inspection Alternative IR-063 L-21-017, Eighteenth Inservice Inspection Summary Report2021-06-29029 June 2021 Eighteenth Inservice Inspection Summary Report L-21-028, 10 CFR 50.55a Request Number SR-2, Revision 0, Snubber Testing Extension2021-01-15015 January 2021 10 CFR 50.55a Request Number SR-2, Revision 0, Snubber Testing Extension L-19-143, Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2020-04-17017 April 2020 Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements L-19-257, Submittal of Perry Nuclear Power Plant Inservice Testing Programs2020-02-13013 February 2020 Submittal of Perry Nuclear Power Plant Inservice Testing Programs L-19-119, Seventeenth Inservice Inspection Summary Report2019-06-26026 June 2019 Seventeenth Inservice Inspection Summary Report L-18-104, 10 CFR 50.55a Requests in Support of the Fourth 10-Year In-Service Testing Interval2018-06-21021 June 2018 10 CFR 50.55a Requests in Support of the Fourth 10-Year In-Service Testing Interval L-17-038, Submittal of Report of Facility Changes, Tests, and Experiments2017-10-23023 October 2017 Submittal of Report of Facility Changes, Tests, and Experiments L-17-072, Sixteenth Inservice Inspection Summary Report2017-06-29029 June 2017 Sixteenth Inservice Inspection Summary Report L-15-165, Fifteenth Inservice Inspection Summary Report2015-07-22022 July 2015 Fifteenth Inservice Inspection Summary Report L-14-105, Notification of Impracticality for the Third 10-Year Inservice Inspection Interval2014-03-0707 March 2014 Notification of Impracticality for the Third 10-Year Inservice Inspection Interval ML14043A1082014-02-12012 February 2014 Notification of Impracticality for the Third 10-Year Lnservice Inspection Interval L-13-190, Fourteenth Inservice Inspection Summary Report2013-08-0909 August 2013 Fourteenth Inservice Inspection Summary Report L-11-260, Thirteenth Inservice Inspection Summary Report2011-09-0101 September 2011 Thirteenth Inservice Inspection Summary Report L-11-083, Submittal of Inservice Examination Plan2011-03-28028 March 2011 Submittal of Inservice Examination Plan L-11-082, Submittal of Inservice Testing Programs2011-03-25025 March 2011 Submittal of Inservice Testing Programs L-10-246, 10 CFR 50.55a Requests in Support of the Third 10-Year In-Service Inspection Interval2011-01-24024 January 2011 10 CFR 50.55a Requests in Support of the Third 10-Year In-Service Inspection Interval L-09-197, Twelfth Inservice Inspection Summary Report2009-08-0505 August 2009 Twelfth Inservice Inspection Summary Report L-08-350, 10 CFR 50.55a Request Number PR-3, Inservice Testing Program2009-02-18018 February 2009 10 CFR 50.55a Request Number PR-3, Inservice Testing Program L-08-270, Response to Request for Additional Information Regarding Relief Request IR-054, Revision 02008-09-17017 September 2008 Response to Request for Additional Information Regarding Relief Request IR-054, Revision 0 L-08-066, Inservice Inspection Program Relief Requests IR-043, Revision 1, IR-055, IR-056, and IR-0572008-02-20020 February 2008 Inservice Inspection Program Relief Requests IR-043, Revision 1, IR-055, IR-056, and IR-057 ML0722503652007-08-0707 August 2007 Submittal of Eleventh Inservice Inspection Summary Report ML0522303272005-08-0202 August 2005 Owners Report for Inservice Inspections as Required by the Provisions of the ASME Code Rules ML0327314232003-08-28028 August 2003 Inservice Inspection Summary Report 2023-06-22
[Table view] Category:Letter type:L
MONTHYEARL-23-207, License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2024-01-24024 January 2024 License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs L-24-017, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2024-01-24024 January 2024 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative L-23-171, CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency2023-12-0808 December 2023 CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency L-23-244, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation L-23-238, Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 202023-11-10010 November 2023 Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 20 L-23-052, Submittal of the Updated Safety Analysis Report, Revision 232023-10-27027 October 2023 Submittal of the Updated Safety Analysis Report, Revision 23 L-23-206, Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD2023-09-12012 September 2023 Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual L-23-001, License Amendment Request to Remove the Table of Contents from the Technical Specifications2023-08-0707 August 2023 License Amendment Request to Remove the Table of Contents from the Technical Specifications L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-174, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2023-07-19019 July 2023 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative L-23-146, License Renewal Application for the Perry Nuclear Power Plant2023-07-0303 July 2023 License Renewal Application for the Perry Nuclear Power Plant L-23-051, Plan, Nineteenth Inservice Inspection Summary Report2023-06-22022 June 2023 Plan, Nineteenth Inservice Inspection Summary Report L-23-050, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-22022 June 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-22-249, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener2023-06-0505 June 2023 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener L-23-134, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-23023 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report L-23-121, Annual Radiological Effluent Release Report2023-04-26026 April 2023 Annual Radiological Effluent Release Report L-23-122, Annual Radiological Environmental Operating Report2023-04-26026 April 2023 Annual Radiological Environmental Operating Report L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports L-23-049, Core Operating Limits Report for Operating Cycle 202023-03-30030 March 2023 Core Operating Limits Report for Operating Cycle 20 L-23-037, and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2023-03-29029 March 2023 and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023 Annual Notification of Property Insurance Coverage L-23-085, 1 to Emergency Plan2023-03-10010 March 2023 1 to Emergency Plan L-23-057, Energy Harbor Nuclear Corp Retrospective Premium Guarantee2023-02-20020 February 2023 Energy Harbor Nuclear Corp Retrospective Premium Guarantee L-23-017, Mid-Cycle Revisions to the Core Operating Limits Report for Operating Cycle 192023-01-31031 January 2023 Mid-Cycle Revisions to the Core Operating Limits Report for Operating Cycle 19 L-22-271, Emergency Plan2022-12-20020 December 2022 Emergency Plan L-22-272, Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis (EPID L-2021-LLA-0067) and Withdrawal of Exemption Requests (EPIDs L-2021-LLE-0022 and L-2021-LLE-0023)2022-12-16016 December 2022 Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis (EPID L-2021-LLA-0067) and Withdrawal of Exemption Requests (EPIDs L-2021-LLE-0022 and L-2021-LLE-0023) L-22-263, Spent Fuel Storage Cask Registration2022-12-12012 December 2022 Spent Fuel Storage Cask Registration L-22-254, Emergency Plan for Perry Nuclear Power Plant, Including EAL Matrix Revision 222022-11-18018 November 2022 Emergency Plan for Perry Nuclear Power Plant, Including EAL Matrix Revision 22 L-22-250, Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 192022-11-0808 November 2022 Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 19 L-22-221, Supplement to Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-10-18018 October 2022 Supplement to Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position L-22-201, Submittal of Evacuation Time Estimates2022-09-12012 September 2022 Submittal of Evacuation Time Estimates L-22-050, Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual2022-08-0909 August 2022 Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual L-20-239, Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-08-0505 August 2022 Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position L-22-171, Response to Request for Additional Information Regarding Proposed Inservice Inspection Alternative IR-0632022-07-14014 July 2022 Response to Request for Additional Information Regarding Proposed Inservice Inspection Alternative IR-063 L-22-099, Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis2022-06-0101 June 2022 Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis L-22-104, Annual Radiological Environmental Operating Report2022-04-28028 April 2022 Annual Radiological Environmental Operating Report L-22-110, Response to Request for Additional Information Re 10CFR50.55a Request Number VR-12, Revision 0, Request for Relief from Containment Isolation Valve ASME OM Code Requirement2022-04-28028 April 2022 Response to Request for Additional Information Re 10CFR50.55a Request Number VR-12, Revision 0, Request for Relief from Containment Isolation Valve ASME OM Code Requirement L-22-105, Annual Radiological Effluent Release Report2022-04-27027 April 2022 Annual Radiological Effluent Release Report L-22-082, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-23023 March 2022 Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations L-22-056, Energy Harbor Nuclear Corp., Annual Notification of Property Insurance Coverage2022-03-22022 March 2022 Energy Harbor Nuclear Corp., Annual Notification of Property Insurance Coverage L-22-052, Deviation from BWRVIP-42 Revision 1-A, BWR Vessel and Internals Project, Low Pressure Coolant Injection (LPCI) Coupling Inspection and Flaw Evaluation Guidelines2022-03-16016 March 2022 Deviation from BWRVIP-42 Revision 1-A, BWR Vessel and Internals Project, Low Pressure Coolant Injection (LPCI) Coupling Inspection and Flaw Evaluation Guidelines L-22-073, Submittal of the Decommissioning Funding Status Report for Perry Nuclear Power Plant2022-03-16016 March 2022 Submittal of the Decommissioning Funding Status Report for Perry Nuclear Power Plant L-22-023, Retrospective Premium Guarantee2022-02-17017 February 2022 Retrospective Premium Guarantee L-21-280, 10 CFR 50.55a Request Number VR-12, Revision 0, Request for Relief from Containment Isolation Valve ASME OM Code Requirements2022-01-0505 January 2022 10 CFR 50.55a Request Number VR-12, Revision 0, Request for Relief from Containment Isolation Valve ASME OM Code Requirements L-21-282, Proposed Inservice Inspection Alternative IR-0632022-01-0505 January 2022 Proposed Inservice Inspection Alternative IR-063 L-21-259, 10 CFR 50.55a Requests Number VR-10 and VR-11, Inservice Valve Testing2021-12-28028 December 2021 10 CFR 50.55a Requests Number VR-10 and VR-11, Inservice Valve Testing L-21-287, Submittal of Revision 22 to Updated Safety Analysis Report (Supplement Letter)2021-12-20020 December 2021 Submittal of Revision 22 to Updated Safety Analysis Report (Supplement Letter) 2024-01-24
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FENOC Perry Nuclear Power Plant 10 Center Road PO. Box 97 FirstEnergy Nuclear Operating Company Perry, Ohio 44081 June 26, 2019 L-19-119 10 CFR 50.55a(g)
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 Perry Nuclear Power Plant Seventeenth lnservice Inspection Summary Report In accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, "lnservice Inspection," 2001 Edition through 2003 Addenda, Article IWA-6000, and ASME Code Case N-532-5, enclosed please find the Owner's Activity Report (Form OAR-1) covering inservice inspection (ISi) activities performed during operating cycle 17 and refueling outage 17 at the Perry Nuclear Power Piant (PNPP). This submittal provides the PNPP inservice inspection summary for the timeframe of April 4, 2017 to April 6, 2019.
There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Phil H. Lashley, Acting Manager - Nuclear Licensing and Regulatory Affairs, at (330) 315-6808.
Enclosure:
Form OAR-1 Owner's Activity Report cc: NRC Region Ill Administrator NRC Resident Inspector NRC Project Manager Ohio Department of Commerce, Boiler Inspection Section
Enclosure L-19-119 Form OAR-1 Owner's Activity Reporl (3 Pages Follow)
Report No.: PY-OARI-17 FORM OAR-I OWNER'S ACTIVITY REPORT Report Number PY-OARl-17 Plant Perry Nuclear Power Plant, 10 Center Road, Perry, OH 44081 UnitNo. Commercial service date November 18. 1987 Refueling outage no. IR17 (if applicable)
Current inspection interval Third (lst;2nd, 3rd, 4th, other)
Current inspection period Third
( I st, 2nd, 3rd)
Edition and Addenda of Section XI applicable to the inspection plans 2001 Edition through 2003 Addenda Inservice Examination Plan (ISEP) Revision 18 dated 11/18/16, Revision 19 dated 9/6/17, Date and revision of inspection plans Revision 20 dated 11/15/18. and Revision 21 dated 1/24/19 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans _N_/A_ _ _ __
Code Cases used for inspection and evaluation: The following are pennitted by the ISEP: N-461-1, N-513-3, N-513-4, N-526, (if applicable. including cases modified by Case N-532 and later revisions)
N-528-1, N-532-5, N-537, N-552, N-561-2, N-562-2, N-566-2. N-578, N-586-1, N-613-1, N-624, N-648-1, N-652-1, N-658, N-661-2, N-663, N-664, N-665, N-666, N-683, N-685, N-695, N-700, N-705, N-716-1, N-735, N-747 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 lRl 7 (refueling outage number)
Signed Date 04/40, CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by Hartford Steam Boiler Inspection and Insurance of having inspected the items described in this Company Hartford, CT Owner's Activity Report, and state that, to the best ofmy 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. Furthennore, neither the Inspector nor his employer shall be L i ~ ~ manner for any personal injury or property damage o.r a loss o:,_any kind arising fr~m or connect with this inspection.
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- Commission .A(B IS <?a Z- tJ ff I 1--~!!!=!ii!=::=.>-~~;;.;..,.&::=~- (National Bolll'd Number and Endorsement)
Date ,/4-/4 f (06/11)
Page 1 of 3
Report No.: PY-OARl-17 TABLE 1
. h Fl awsor RI I terns wit e evan tCon d°f I IODS Th at . R eqmre
- dEva uabon fior ContmuedS erv1ce Examination Category and Item Number Item Description Evaluation Description CR-2017-08106 identified a through wall 3" ESW B Piping in Vicinity of leak that subsequently required evaluation for D-B /02.10 1P45F5466B continued operation in accordance with ASME Code Case N-513-3.
14" Emergency Service Water "B" Piping between 1P45F0541B CR-2017-08581 identified a through wall and heat exchanger 1P42B000 lB. leak that subsequently required evaluation for D-B /02.10 Also between valve 1P45F0541B continued operation in accordance with and second elbow downstream of ASME Code Case N-513-4.
the valve.
3" Emergency Service Water "ff' CR-2017-08736 identified wall thinning that D-B /02.10 Piping in the vicinity of was evaluated and determined to be above 1P45F5466B minimum wall thickness limits.
CR-2018-05504 identified a through wall 20" Emergency Service Water leak that subsequently required evaluation for D-B /02.10 "A" Piping between valves continued operation in accordance with 1P4SF0SS0A and 1P4SF0068A ASME Code Case N-513-3.
24" Emergency Service Water CR-2018-10362 identified wajl thinning that D-B /02.10 "A" Piping downstream of was evaluated and determined to be above discharge valve 1P45F0130A minimum wall thickness limits.
CR-2019-02328 identified a 2 in 2 area on the containment vessel interior surface with a damaged coating (checking). The evaluation E-A I El.11 Containment Surface 1T23-022-1 determined that containment structural integrity or leak tightness are not affected, and the condition is acceptable.
CR-2019-01634 identified this variable spring support being found outside of its design hot/cold settings. Previously F-A / Fl.SP Variable Spring 1E21-H0089 performed engineering analysis bounded this condition and therefore the condition is acceptable.
TABLEl Ab stract o fR epa1r . /Rep Iacement A ctlvities R eqmre . dfior C ontmuedS erv1ce Code Repair/Replacement Plan Class Item Descriotion Description of Work Date Completed Number High Pressure Core Spray Starting Air 3 Replace piping 07/18/2017 200691740 Piping with flange and hardware High Pressure Core Spray Piping elbow Weld overlay of 4" 2 downstream of orifice 03/01/2018 200737512 elbow 1E22D000 1 on HPCS Minimum Flow Line Control Complex Replace hex screws for 3 Chilled Water Chiller 03/01/2018 200617253 reassembly "B" Hardware Div. 1 Standby Diesel Generator Left Bank 3 Receiver Outlet Replaced valve disc 03/01/2018 200559512 Isolation Valve 1R44F0562A Page 2 of 3
Report No.: PY-OARI-17 High Pressure Core Spray Piping elbow 2 downstream of orifice Replace 4" elbow 06/12/2018 200737508 1E22D0001 on HPCS Minimum Flow Line Emergency Service Water "A" Piping Install reinforcing pad 3 between valves 10/09/2018 200757942 over leak in 20" piping 1P45F0550A and 1P45F0068A Fuel Pool Cooling and 3 Cleanup Pump 0041- Replace pump 01/25/2019 200251252 C0003B Emergency Service Patch piping using rolled 3 Water "B" Piping near 04/01/2019 200767679 plate valve 1P45F0541B
., Emergency Service Remove 3" bypass 3 Water "B" Piping in the 04/03/2019 200726587 piping/components vicinitv of 1P45F5466B Emergency Service Water "B" Piping between 1P45F0541B and heat exchanger 3 1P42B0001B. Also Replace 14" piping 04/03/2019 200726587 between valve 1P45F0541B and second elbow downstream of the valve.
Reactor Water Cleanup Piping between heat 3 exchangers Replace 4" piping 04/11/2019 200724734 1G33B0001C and 1G33B0002a Residual Heat Removal Replace stud and nut 2 04/16/2019 200007545 Valve IE12F0011B hardware Bolting Hardware for Reactor Core Isolation Cooling Head Spray Replace stud and nut 1 Piping Flanges # 1, #3, 05/01/2019 200694625 hardware
- 7, (IB13-N8-B, 1E51-0009-B, and 1821-0186-B)
Emergency Service Water "A" Piping 3 between valves Replace 20" piping 06/05/2019 200757843 1P45F0550A and 1P45F0068A Page 3 of 3