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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARJAFP-23-0008, Supplement to Inservice Inspection Summary Report Cycle 252023-02-22022 February 2023 Supplement to Inservice Inspection Summary Report Cycle 25 JAFP-22-0053, Inservice Inspection Summary Report Cycle 252022-12-20020 December 2022 Inservice Inspection Summary Report Cycle 25 JAFP-20-0087, Inservice Inspection Summary Report Cycle 242020-12-28028 December 2020 Inservice Inspection Summary Report Cycle 24 JAFP-19-0004, Inservice Inspection Summary Report Cycle 232019-01-0404 January 2019 Inservice Inspection Summary Report Cycle 23 JAFP-18-0113, Fifth Ten-Year Lnservice Inspection Interval Program Plan2018-12-17017 December 2018 Fifth Ten-Year Lnservice Inspection Interval Program Plan JAFP-18-0078, Fifth Ten-Year Interval Inservice Testing Program Plan2018-08-0606 August 2018 Fifth Ten-Year Interval Inservice Testing Program Plan JAFP-17-0057, Inservice Inspection Summary Report 2017 Refuel Outage 222017-05-25025 May 2017 Inservice Inspection Summary Report 2017 Refuel Outage 22 JAFP-16-0136, Alternative Examination Requirements Nozzle-to-Vessel Welds and Nozzle Inner Radii Using ASME Code Case N-702 and BWRVIP-2412016-08-24024 August 2016 Alternative Examination Requirements Nozzle-to-Vessel Welds and Nozzle Inner Radii Using ASME Code Case N-702 and BWRVIP-241 JAFP-14-0012, Inservice Testing Program 10 CFR 50.55a Request PRR-052014-02-21021 February 2014 Inservice Testing Program 10 CFR 50.55a Request PRR-05 JAFP-13-0004, Inservice Inspection Summary Report 2012 Refuel Outage (Reload 20/Cycle 21)2013-01-14014 January 2013 Inservice Inspection Summary Report 2012 Refuel Outage (Reload 20/Cycle 21) JAFP-11-0009, Inservice Inspection Summary Report 2010 Refuel Outage (Reload 19/Cycle 20)2011-01-18018 January 2011 Inservice Inspection Summary Report 2010 Refuel Outage (Reload 19/Cycle 20) JAFP-09-0088, Proposed Relief Request VRR-06 for the Fourth Interval In-Service Testing Program2009-07-31031 July 2009 Proposed Relief Request VRR-06 for the Fourth Interval In-Service Testing Program JAFP-09-0008, Response to Request for Additional Information Regarding: Request for Additional Information Third Ten-Year Inservice Inspection Interval Program Plan Relief Request RR-CRV-012009-01-20020 January 2009 Response to Request for Additional Information Regarding: Request for Additional Information Third Ten-Year Inservice Inspection Interval Program Plan Relief Request RR-CRV-01 JAFP-09-0004, Inservice Inspection Summary Report 2008 Refuel Outage (Reload 18/Cycle 19)2009-01-10010 January 2009 Inservice Inspection Summary Report 2008 Refuel Outage (Reload 18/Cycle 19) JAFP-08-0109, Submittal of the Final Ultrasonic Test Results on the N2C-SE Weld Overlay2008-10-20020 October 2008 Submittal of the Final Ultrasonic Test Results on the N2C-SE Weld Overlay JAFP-08-0038, Inservice Inspection Program Relief Requests Third Ten-year Interval Closeout2008-04-30030 April 2008 Inservice Inspection Program Relief Requests Third Ten-year Interval Closeout JAFP-07-0116, Fourth Interval Inservice Testing Program for Pumps and Valves2007-09-26026 September 2007 Fourth Interval Inservice Testing Program for Pumps and Valves JAFP-07-0107, Response to Request for Additional Information Regarding Proposed Relief Request PRR-01 for the Fourth Interval In-Service Testing Program2007-08-29029 August 2007 Response to Request for Additional Information Regarding Proposed Relief Request PRR-01 for the Fourth Interval In-Service Testing Program JAFP-07-0050, Proposed Relief Requests for the James A. FitzPatrick Power Plant Fourth Interval In-Service Testing Program2007-04-11011 April 2007 Proposed Relief Requests for the James A. FitzPatrick Power Plant Fourth Interval In-Service Testing Program JAFP-07-0030, Fourth Inservice Inspection Interval Inspection Program Plan2007-02-27027 February 2007 Fourth Inservice Inspection Interval Inspection Program Plan JAFP-07-0020, Submittal of James A. Fitzpatrick - Inservice Inspection Summary Report 2006 Refuel Outage (Reload 17/Cycle 18)2007-02-0202 February 2007 Submittal of James A. Fitzpatrick - Inservice Inspection Summary Report 2006 Refuel Outage (Reload 17/Cycle 18) JAFP-05-0151, Request for Approval of Relief Request No. RR-39, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspection2005-10-0707 October 2005 Request for Approval of Relief Request No. RR-39, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspection ML0515802032005-05-26026 May 2005 Request for Relief from System Hydrostatic Test Requirements for Small Bore (5 1 Inch), ASME Code Class 1 Reactor Coolant Pressure Boundary (RCPB) Vent, Drain, and Branch (Vtdb) Lines and Connections JAFP-05-0013, Inservice Inspection Summary Report 2004 Refuel Outage (Reload 16/Cycle 17)2005-01-19019 January 2005 Inservice Inspection Summary Report 2004 Refuel Outage (Reload 16/Cycle 17) JPN-04-010, Request to Use 1998 Edition, 2000 Addenda of American Society of Mechanical Engineers (ASME) Section Xl Code Requirements for Examination of Reactor Vessel Closure Studs2004-04-14014 April 2004 Request to Use 1998 Edition, 2000 Addenda of American Society of Mechanical Engineers (ASME) Section Xl Code Requirements for Examination of Reactor Vessel Closure Studs JAFP-03-0096, James a FitzPatrick Nuclear Power Plant, Proposed Relief Request No. VRR-08 to In-Service Testing Program2003-07-0808 July 2003 James a FitzPatrick Nuclear Power Plant, Proposed Relief Request No. VRR-08 to In-Service Testing Program JAFP-02-0251, In-Vessel Visual Inspection Summary Report 2002 Refuel Outage (Reload 15/Cycle 16)2002-12-26026 December 2002 In-Vessel Visual Inspection Summary Report 2002 Refuel Outage (Reload 15/Cycle 16) JPN-02-026, Relief Request RR-28, Revision 3 for Third 10-Year Inservice Inspection Interval Program Plan2002-09-12012 September 2002 Relief Request RR-28, Revision 3 for Third 10-Year Inservice Inspection Interval Program Plan JPN-02-022, License DPR-59, Relief Request RR-28, Revision 2 for the Third 10-Year Inservice Inspection Interval Program Plan2002-07-10010 July 2002 License DPR-59, Relief Request RR-28, Revision 2 for the Third 10-Year Inservice Inspection Interval Program Plan JPN-02-001, Submittal of James A. FitzPatrick Owner'S Activity Report, JAF-RPT-MULTI-04331, Rev. 0 Which Contains Inservice Inspection Results & Repair/Replacement Activities Performed During 1st Period of Third 10-Year ISI Interval2002-01-28028 January 2002 Submittal of James A. FitzPatrick Owner'S Activity Report, JAF-RPT-MULTI-04331, Rev. 0 Which Contains Inservice Inspection Results & Repair/Replacement Activities Performed During 1st Period of Third 10-Year ISI Interval 2023-02-22
[Table view] Category:Letter type:JAFP
MONTHYEARJAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications JAFP-23-0069, Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements JAFP-23-0057, and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation JAFP-23-0064, Emergency Plan Document Revision2023-11-15015 November 2023 Emergency Plan Document Revision JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023 Registration of Spent Fuel Cask Use JAFP-23-0059, Registration of Spent Fuel Cask Use2023-10-24024 October 2023 Registration of Spent Fuel Cask Use JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-31031 August 2023 Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0050, Physical Security Plan, Revision 242023-08-31031 August 2023 Physical Security Plan, Revision 24 JAFP-23-0047, Correction to the 2022 Annual Radioactive Effluent Release Report2023-08-30030 August 2023 Correction to the 2022 Annual Radioactive Effluent Release Report JAFP-23-0040, License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-0303 August 2023 License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0043, 10 CFR 50.46 Annual Report2023-07-31031 July 2023 10 CFR 50.46 Annual Report JAFP-23-0038, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2023-07-28028 July 2023 License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance JAFP-23-0033, License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation2023-06-28028 June 2023 License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation JAFP-23-0025, 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Annual Radiological Environmental Operating Report JAFP-23-0023, 2022 Annual Radioactive Effluent Release Report2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report JAFP-23-0010, 2022 REIRS Transmittal of NRC Form 52023-03-20020 March 2023 2022 REIRS Transmittal of NRC Form 5 JAFP-23-0008, Supplement to Inservice Inspection Summary Report Cycle 252023-02-22022 February 2023 Supplement to Inservice Inspection Summary Report Cycle 25 JAFP-22-0053, Inservice Inspection Summary Report Cycle 252022-12-20020 December 2022 Inservice Inspection Summary Report Cycle 25 JAFP-22-0046, Core Operating Limits Report Cycle 262022-10-17017 October 2022 Core Operating Limits Report Cycle 26 JAFP-22-0040, 10 CFR 50.46 Annual Report2022-07-29029 July 2022 10 CFR 50.46 Annual Report JAFP-22-0033, Core Operating Limits Report Mid-Cycle 252022-06-23023 June 2022 Core Operating Limits Report Mid-Cycle 25 JAFP-22-0032, Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b..2022-06-16016 June 2022 Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.. JAFP-22-0030, Oswego County and New York State Participation in the Emergency Plan2022-05-13013 May 2022 Oswego County and New York State Participation in the Emergency Plan JAFP-22-0029, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022 2021 Annual Radiological Environmental Operating Report JAFP-22-0028, 2021 Annual Radioactive Effluent Release Report2022-04-27027 April 2022 2021 Annual Radioactive Effluent Release Report JAFP-22-0026, 2021 REIRS Transmittal of NRC Form 52022-04-0707 April 2022 2021 REIRS Transmittal of NRC Form 5 JAFP-22-2020, Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Info2022-03-0404 March 2022 Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Informed JAFP-22-0017, Amendments to Indemnity Agreements2022-02-15015 February 2022 Amendments to Indemnity Agreements JAFP-22-0007, Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102022-01-31031 January 2022 Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 JAFP-22-0010, Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments2022-01-24024 January 2022 Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments JAFP-22-0008, Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary2022-01-14014 January 2022 Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary JAFP-21-0093, Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation2021-10-18018 October 2021 Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0083, Notification of Readiness for NRC 95001 Inspection2021-09-0909 September 2021 Notification of Readiness for NRC 95001 Inspection JAFP-21-0081, Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-0303 September 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements JAFP-21-0075, Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2021-08-12012 August 2021 Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs JAFP-21-0073, Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance.2021-08-0909 August 2021 Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance. JAFP-21-0069, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2021-07-30030 July 2021 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors JAFP-21-0070, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b2021-07-30030 July 2021 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b JAFP-21-0071, 10 CFR 50.46 Annual Report2021-07-29029 July 2021 10 CFR 50.46 Annual Report JAFP-21-0064, Supplemental Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-07-0707 July 2021 Supplemental Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting JAFP-21-0053, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-14014 June 2021 Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0052, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021 Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0051, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021 Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0050, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-12012 June 2021 Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0042, Reply to a Notice of Violation; EA-20-1382021-06-0303 June 2021 Reply to a Notice of Violation; EA-20-138 JAFP-21-0041, Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2021-05-17017 May 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing JAFP-21-0040, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2021-05-14014 May 2021 Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs 2023-08-31
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Text
Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel 315-342-3840 Chris M. Adner Licensing Manager - JAF JAFP-13-0004 January 14, 2013 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
Inservice Inspection Summary Report 2012 Refuel Outage (Reload 20/Cycle 21)
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59
Reference:
Entergy letter to NRC (JAFP-07-0030), Fourth Inservice Inspection Interval Inspection Program Plan, dated February 27, 2007
Dear Sir or Madam:
This letter submits the James A. FitzPatrick (JAF) Owners Activity Report, Second Period, Fourth Interval JAF-RPT-13-00001, Rev. 0 (Enclosure 1) which contains a summary of the Inservice Inspection (ISI) examinations conducted during the plants fall 2012 Refuel Outage (Reload 20/Cycle 21).
Table 1 of the enclosed report summarizes the items with flaws or relevant indications that required evaluation for continued service and Table 2 provides an abstract of repair/replacement activities required for continued service.
This Report is being submitted in accordance with JAFs approved Fourth Inservice Inspection Interval Inspection Program Plan (Reference 1).
There are no commitments contained in this letter
JAFP-13-0004 Page 2 of 2 If you should have any questions, please contact Mr. Mark Dooley, Programs and Components Manager, at (315) 349-6529.
Very truly yours,
$?/Itlk-Chris M. Adner Licensing Manager
Enclosure:
JAF Owner's Activity Report (OAR) Second Period, Fourth Interval CA/mg cc: Mr. William Dean Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 2100 Renaissance Boulevard Suite 100 King of Prussia, PA 19406-2713 United States Nuclear Regulatory Commission ATTN: James Noggle U.S. NRC Region I 2100 Renaissance Boulevard Renaissance Park King of Prussia, PA 19406 Office of the Resident Inspector U.S. Nuclear Regulatory Commission James A. FitzPatrick Nuclear Power Plant P.O. Box 136 Lycoming, NY 13093 Mr. Mohan Thadani Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-8-C2A Washington, DC 20555-0001 Mr. Francis J. Murray Jr., President NYSERDA 17 Columbia Circle Albany, NY 12203-6399
JAFP-13-0004 ENCLOSURE JAF Owners Activity Report (OAR)
Second Period, Fourth Interval (7 Pages)
ATTACHMENT 9.1 ENGINEERING REPORT COVER SHEET & INSTRUCTIONS SHEET 1 OF 2 Engineering Report No. JAF-RPT-13-0000I Rev 0 Page 1 of 7 ENTERGY NUCLEAR Engineering Report Cover Sheet Engineering Report
Title:
JAF Owner's Activity Report (OAR) Second Period, Fourth Interval Engineering Report Type:
New [gj Revision 0 Cancelled 0 Superseded 0 Superseded by: N/A Applicable Site(s)
IPI 0 IP2 0 IP3 0 JAF [gj PNPS 0 VY 0 WPO 0 ANOI 0 AN02 0 ECH 0 GGNS 0 RBS 0 WF3 0 PLP 0 EC No. 0000041887 Report Origin: [gj Entergy 0 Vendor Vendor Document No.: N/A o No Prepared by: -,S~c~o~tt:...!R~e~e~d _ _~--;::=--.-:~~~:::::::::;-:---,----- _ Date: //3//3 Responsible Engineer (Print Name/Sign)
Design Verified: Design Verification is not required Date: N/A Design Verifier (if required) (Print Name/Sign)
Reviewed by: . . . : .: K: : :ar:. : ac. : .Mc. : .U1: : :p=hy~ = .: . = - -;'2"' ' - '"'//"9"~/"'--..,-- _ Date: ,/,/13
'ReVieWeT(P?i~)
Reviewed by: _M=ik:::::e:....:R:..:.o:.:s:..:.e~';f?2""-'-'
. ,--,-_0_£_.,..0.:....~-'-:....:e..tA.---:-,::-=--
Reviewer (Print N me/Sign)
_ Date:
~/G i~
/-;1 Reviewed by: --=-=..:..:.:...::..:..:c~-.,-:-----jr-=---c:--:--:-:---:----- Date:
Approved by: Duane Bittin er ~..........o.... Date: '1 g / 20 ( 3 Supervisor / Manager (Print Name/Si )
EN-DC-147 REV 5
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number JAF-RPT-13-00001 Plant James A. FitzPatrick Nuclear Power Plant, 268 Lake Road East, Lycoming New York 13093 Unit No. 1 Commercial Service Date _ _ _..::J.::u:.Lly-.:2",,8:L'..::1c::.
9-'...74-'--___ Refueling Outage Number _ _-.:.:R.::20"---_ _
(if applicable)
Current Inspection Interval 4th (1 st, 2nd, 3"', 4th, other)
Current Inspection Period 2nd (1 st, 2nd, 3'd )
Edition and Addenda of Section XI applicable to the Inspection Plans 2001 Edition, 2003 Addenda Date / Revision of Inspection Plans March 1, 2007 I lSI Program Plan No. ENN-SEP-JAF-007 Revision 3 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Same Code Cases used: -:..:.N-..=5c::.3=.2--:4 _
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 R20 conform to the requirements of Section XI _~ (refueling outage number)
Signed Scott Reed 'CS ~ I ~ Date 1/9" 113 (Owner or Owner's designee.
Title:
Sr Lead Technical Spec (Nuc))
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 New York and employed by HSB cr of Hartford, cr 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 property damage or a loss of any kind arising from or connected with this inspection
-fCh!l!a~rllilieUR~o~s~e_~~~~~~:;:===-- Commissions NB 13519 A,N,I NY5364 National Board, State, Province, and Endorsements Date Engineering Report No. JAF-RPT-13-00001 Rev.O Page 2 of 7
TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description B-K / B10.20 Integral Attachment 22-02-2-86B CR-JAF-2012-06033 - ISI examination of the attachment identified a linear indication exceeding ASME Section XI requirements.
Rejectable indication removed with additional surface preparation. Re-examination of the component was acceptable.
F-A / F1.20a Support 10-13B-NS-130 CR-JAF-2012-03893 - ISI examination identified the lower clamp nut was not in contact with the clamp and required further evaluation per ASME Section XI requirements.
Evaluation determined the support to be operable and capable of performing its design function. Work order 00321112 generated for tightening of the loose nut.
F-A / F1.10b Support 10-14B-AN-246 CR-JAF-2012-06302 - ISI examination identified the Spring can setting out of tolerance and required further evaluation per ASME Section XI requirements.
Evaluation determined the spring can setting acceptable as is. Drawing revised to indentify specified settings.
E-A / E1.11, E1.30 Primary Containment IWE General CR-JAF-2012-06616 - During scheduled IWE inspection of Primary Containment Examination, DW 256 - 268; IWE drywell elevation 256 to 268, General Paint degradation and corrosion / pitting General / Detailed Examination, DW conditions at the drywell liner to floor interface were recorded per the ASME Liner Interface 256 Section XI program.
These conditions were evaluated and acceptable by Engineering for continued service. General paint degradation was acceptable as is: Re-examination of drywell liner to floor interface corrosion / pitting accepted based on pit depth measurements (less than 10% wall thickness). SIPD JAF-971 is in place for Drywell Liner to floor interface repair and installation of seal. Drywell liner to floor interface corrosion / pitting continues to be monitored.
E-A / E1.11 Primary Containment IWE General CR-JAF-2012-06562 - ASME Section XI, IWE, General Visual examination of the Examination, DW 268 - 292 containment surfaces identified coating deficiencies exceeding procedure screening criteria. Coating (paint) was either missing or had minor degradation in various locations.
Engineering evaluated the condition and accepted as is (no material loss identified).
Engineering Report No. JAF-RPT-13-00001 Rev.0 Page 3 of 7
TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description E-A / E1.11 Primary Containment IWE General CR-JAF-2012-06558 - ASME Section XI, IWE, General Visual examination of the Examination, DW 292 - 324 containment surfaces identified coating deficiencies exceeding procedure screening criteria. Coating (paint) was either missing or had minor degradation in various locations.
Engineering evaluated the condition and accepted as is (no material loss identified).
E-A / E1.11 Primary Containment IWE General CR-JAF-2012-06361 - ASME Section XI, IWE, General Visual examination of the Examination, DW 324 - 340 containment surfaces identified coating deficiencies exceeding procedure screening criteria. Coating (paint) was either missing or had minor degradation in various locations.
Engineering evaluated the condition and accepted as is (no material loss identified).
E-A / E1.11 Primary Containment IWE General CR-JAF-2012-07201 - ASME Section XI, IWE, General Visual examination of the Examination Torus Interior RB 227 torus interior surfaces identified coating deficiencies exceeding procedure to 272. screening criteria. Coating (paint) degradation and minor corrosion identified in various locations.
Engineering evaluated the condition and accepted as is (no material loss identified).
N/A ESW leak Line Number 15 WES- CR-JAF-2011-01705 - ASME Section XI, Class III piping pinhole leak (< 4).
151-137 Piping replaced per work order 00271482. Reference Repair/Replacement package 11-008.
Engineering Report No. JAF-RPT-13-00001 Rev.0 Page 4 of 7
TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Repair/Replacement Class Item Description Description Of Work Date Completed Plan Number 3 29-1D-HS-36 Snubber Replacement 9/22/2012 12-001 1 02RV-71C Pilot Valve Replacement 10/4/2012 12-002 1 02RV-71E Pilot Valve Replacement 9/29/2012 12-003 1 02RV-71F Pilot Valve Replacement 9/28/2012 12-004 3 10S-5B2 Strainer Body Replacement 8/17/2012 12-005 1 02RV-71K Valve Replacement (Main Body) 9/26/2012 12-007 1 29MST-717B Valve Replacement 9/23/2012 12-008 1 29MST-717C Valve Replacement 9/23/2012 12-009 1 03-SE-HS-8 Snubber Replacement 9/18/2012 12-010 1 02RV-71G Valve Replacement (Main Body) 9/28/2012 12-011 1 02RV-71L Valve Replacement (Main Body) 9/28/2012 12-012 1 02RV-71D Valve Replacement (Main Body) 10/15/2012 12-013 3 46ESW-13B Unit Cooler Replacement 10/3/2012 12-014 1 29-1C-HS-22 Snubber Replacement 9/29/2012 12-015 1 29-1D-HS-39 Snubber Replacement 9/19/2012 12-017 1 29-1B-HS-13A Snubber Replacement 9/23/2012 12-018 2 10-15B-MS-125B Snubber Replacement 8/3/2012 12-020 2 10-9B-MS-286 Snubber Replacement 8/1/2012 12-021 2 10-15B-MS-124B Snubber Replacement 8/2/2012 12-022 2 10-15B-MS-125 Snubber Replacement 8/3/2012 12-023 2 10-35-MS-221A Snubber Replacement 7/17/2012 12-024 3 13-22-HS-13 Snubber Replacement 7/26/2012 12-025 2 10-12A-HS-117 Snubber Replacement 7/16/2012 12-026 3 10-30A-HS-1001 Snubber Replacement 7/16/2012 12-027 2 10-7B-MS-3 Snubber Replacement 8/1/2012 12-028 2 10-8B-HS-12 Snubber Replacement 8/2/2012 12-029 2 10-15B-HS-291 Snubber Replacement 8/2/2012 12-030 Engineering Report No. JAF-RPT-13-00001 Rev.0 Page 5 of 7
TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Repair/Replacement Class Item Description Description Of Work Date Completed Plan Number 2 10-10B-HS-20 Snubber Replacement 8/6/2012 12-031 2 10-15B-MS-119A Snubber Replacement 8/7/2012 12-032 2 10-17-HS-55 Snubber Replacement 9/30/2012 12-033 2 10-15B-MS-124 Snubber Replacement 8/7/2012 12-034 2 10-39-HS-166 Snubber Replacement 8/6/202 12-035 2 10-32B-HS-277 Snubber Replacement 8/6/2012 12-036 2 10-2C-HS-186B Snubber Replacement 8/14/2012 12-037 1 CRDM EXCHANGE CRD Replacements 9/24/2012 12-038 2 23SV-66 Valve Replacement 9/2/2012 12-042 3 46EXJ-10D Bolting Replacement 9/27/2012 12-043 2 14SV-20A Valve Replacement 10/5/2012 12-044 2 10MOV-38A Valve Bolting Replacement 9/29/2012 12-048 2 03TK-125(HCU-22-35) Accumulator Replacement 10/20/2012 12-049 2 03TK-125(HCU-26-03) Accumulator Replacement 10/15/2012 12-050 3 46(70)EXJ-1A Expansion Joint Replacement 3/28/2011 11-002 3 10S-5B2 Strainer Repair 7/19/2011 11-004 3 46-2"-WES-151-117 Spool Piece Replacement 6/3/2011 11-005 3 15-3-WES-151-137 Piping Replacement 3/31/2011 11-008 3 10S-5A1 Strainer Body Replacement 10/14/2011 11-010 3 10S-5A2 Strainer Repair 6/30/2011 11-011 1 02RV-71A Pilot Valve Replacement 10/14/2012 11-012 1 02RV-71B Pilot Valve Replacement 10/16/2012 11-013 1 02RV-71D Pilot Valve Replacement 10/15/2012 11-014 1 02RV-71H Pilot Valve Replacement 10/15/2012 11-015 1 02RV-71G Pilot Valve Replacement 10/15/2012 11-016 1 02RV-71J Pilot Valve Replacement 10/16/2012 11-017 1 02RV-71K Pilot Valve Replacement 10/16/2012 11-018 1 02RV-71L Pilot Valve Replacement 10/16/2013 11-019 Engineering Report No. JAF-RPT-13-00001 Rev.0 Page 6 of 7
TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Repair/Replacement Class Item Description Description Of Work Date Completed Plan Number 1 03TK-125(HCU-46-43) HCU Water Cylinder Replacement 9/202012 11-020 3 46-2"-WES-151-118 Spool Piece Replacement 1/26/2012 11-022 1 11EV-14B Valve Replacement 10/4/2012 11-024 3 10S-5A2 Strainer Body Replacement 3/1/2012 11-025 1 12-1-HS-20A Snubber Replacement 10/1/2012 11-026 1 14-5B-HS-44 Snubber Replacement 9/17/2012 11-027 1 02-202B-HS-4 Snubber Replacement 9/22/2012 11-028 3 46SWS-122H Valve Replacement 10/4/2012 11-029 3 10S-5B1 Strainer Body Replacement 3/22/2012 11-031 3 46SWS-127H Valve Replacement 10/4/2012 11-032 3 46SWS-127A Valve Replacement 10/3/2012 11-033 3 67E-14 Unit Cooler End Cover Repair 1/26/2012 11-034 3 46SWS-120E Valve Replacement 10/12/2012 08-055 3 46SWS-120H Valve Replacement 10/4/2012 08-056 Engineering Report No. JAF-RPT-13-00001 Rev.0 Page 7 of 7