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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 I"1-Lycoming, NY 13093 Tel 315-342-3840 January 10, 2009 JAFP-09-0004 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59 Inservice Inspection Summary Report 2008 Refuel Outage (Reload 18/Cycle 19)
Reference:
- 1. Entergy letter to USNRC (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) Owner's Activity Report, JAF-RPT 00019, Rev. 0 (Enclosure 1) which contains a'summary of the Inservice Inspection (ISI) examinations conducted during the plant's fall 2008 Refuel Outage (Reload1 8/Cycle 19).
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 JAF's approved Fourth Inservice Inspection Interval Inspection Program Plan (Reference 1).
Should you have any questions concerning this letter, please contact Mr. Joseph Pechacek at (315) 349-6766.
This letter contains no new commitments.
Very truly yours, Joseph Pechacek Licensing Manager JP:ed Enclosure I: JAF Owner's Activity Report (OAR), First Outage, First Period, Fourth Interval (Report No. JAF-RPT-08-00019, rev.0) cc: Next page / 3 4f,7 Page 1 of 5
JAFP-09-0004 Page 2 of 2 cc: Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Office of the Resident Inspector U.S. Nuclear Regulatory Commission James A. FitzPatrick Nuclear Power Plant P.O. Box 136 Lycoming, NY 13093 Mr. Bhalchandra Vaidya, Project Manager Plant Licensing Branch I I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8-C2 Washington, DC 20555-0001 Mr. Paul Tonko, President NYSERDA 17 Columbia Circle Albany, NY 12203-6399
Enclosure I to JAFP-09-0004 Entergy Nuclear Operations, Inc. - J. A. FitzPatrick Docket No. 50-333 JAF Owner's Activity Report (OAR), First Outage, First Period, Fourth Interval (Report No. JAF-RPT-08-00019, Rev. 0)
ATTACHMENT 9.1 ENGINEERING REPORT COVER SHEET & INSTRUCTIONS SHEET 1 OF 2 Engineering Report No. JAF-RPT-08-00019 Rev. 0 Page 1 of 6
- ? Entergy ENTERGY NUCLEAR Engineering Report Cover Sheet Engineering Report
Title:
JAF Owner's Activity Report (OAR) First Outage, First Period, Fourth Interval Engineering Report Type:
New [ Revision 13 Cancelled 11 Superseded E3 Applicable Site(s)
IP 1 El IP2 13 IP3 E3 JAF E PNPS El vy El wpo EI ANO1 El ANO2 13 ECH El GGNS F] RBS El WF3 F1 PLP [I DRN No. ON/A; 13 Report Origin: [ Entergy 13 Vendor Vendor Document No.:
Quality-Related: Z Yes [] No Prepared by: Scott Reed Date: 12/30/2008 Responsible Engineer (Print Name/Sign)
Design Verified/ Design Verification is not required Date: N/A Design Verifier (if required) (Print Name/Sign)
Reviewed by:
Neal Chapman "4 - -- _- Date: 12/30/2008 Reviewer (Print Na mý/Sign)
Reviewed by*: Ron Fabiny Date: 12/30/2008 ANII (if*ud)(#
e int men )
Approved by: Joe Pechacek'... , Date: 12/30/2008 Supervis (Print Name/Sign)
FORM OAR-i OWNER'S ACTIVITY REPORT Report Number JAF-RPT-08-00019 Plant James A. FitzPatrick Nuclear Power Plant, 268 Lake Road East, Lycominc New York 13093 Unit No. 1 Commercial Service Date July 28, 1974 Refueling Outage Number R18 (if applicable)
Current Inspection Interval 4th (1st, 2nd, 3", 4-, other)
Current Inspection Period 1st (1st, 2"d, 3rd)
Edition and Addenda of Section XI applicable to the Inspection Plans 2001 Edition, 2003 Addenda Date / Revision of Inspection Plans March 1, 2007 / ISI Proqram Plan, Rev. 1 No. JAF-RPT-06-001 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Same Code Cases used: N-416-3, N-532-4 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 R18 conform to the requirements of Section XI (refueling outage number)
Signed Scott Reed ' 1 / jz . Date 12/30/2008 (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 CT of Hartford, CT 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 injLor property damage or a loss of any kind arising from or connected with this inspection Ron Fabiny \ Commissions NY3061 (Inspector's Signaturaizý National Board, State, Province, and Endorsements Date 12/30/2008 Engineering Report No. JAF-RPT-08-00019 Rev.0 Page 2 of 6
TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description B-F / B5.10 Nozzle to Safe End Weld / N-2C-SE CR-JAF-2008-03311 - ISI examination of the N2C-SE identified an axial indication requiring repair.
Weld overlay repair performed per ISI program plan Relief Request #7 (RR-7) and Work Order 00166023.
C-A / C1.20 Head to Shell Weld / TH1-A CR-JAF-2008-02724 - ISI examination identified two subsurface planar indications requiring further evaluation per ASME Section XI requirements.
Evaluation of the indications was performed and acceptable per ASME Section XI Table IWC-3510-1 requirements.
E-A /E1.11 Torus Saddle Support/ CR-JAF-2008-02842 - IWE General Visual examination of the primary containment SC-SD-Azm @ 100-54' (Torus) saddle support assembly identified hold down brackets exhibiting SC-SD-Azm @ 1000-54' recordable conditions per the ASME Section XI program.
SC-SD-Azm @ 1240-6' SC-SD-Azm @ 1450-54' Engineering evaluation identified the degraded condition of the saddle hold-down SC-SD-Azm @ 2350-54' anchor bracket locations are capable of performing their design function of SC-SD-Azm @ 2590-6' restraining the torus when subjected to all required design loading conditions.
SC-SD-Azm @ 2800-54' Work Order 00167052 generated to reposition the torus saddle hold down bracket SC-SD-Azm @ 3040-6' shim plates identified.
SC-SD-Azm @ 3490-6' E-A / E1.11 Torus Shell Plates / SC-PL-Bay (A CR-JAF-2008-03439 - ASME Section XI, IWE, General Visual examination of the through P) Torus exterior surfaces identified coating (paint) was either missing or had minor degradation in various locations.
Engineering evaluated the condition and the indication was accepted as is. The integrity of the Torus Shell remains intact as there is no degradation of the steel Torus shell and it is capable to perform its intended design function.
E-A / E1.11, E1.30 Primary Containment Moisture CR-JAF-2008-03508 - During scheduled IWE inspection of drywell 256' elevation, Barrier Area degraded conditions at the carbon steel drywell liner interface were recorded per the ASME Section XI program.
These conditions were evaluated and acceptable to Engineering for continued operational service. Work Order 00166758 was initiated for repairof concrete and coatings in the area of interest.
Engineering Report No. JAF-RPT-08-00019 Rev.0 Page 3 of 6
TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE F-A / F1.10 Class 1 Piping Supports / 12-14-NS-3 CR-JAF-2008-02959 - ISI examination of piping box support 12-14-NS-3 / PFSK 1896 identified an approximate 1/4" gap between the support and bottom side of the pipe.
A shim or spacer plate was installed to correct the condition per Work Order 00167099.
N/A Whip Restraint / 02-2-6A-NN-1E CR-JAF-2008-03738 - VT-3 examination identified clearances not in accordance with the drawing.
___Engineering evaluated the condition and the indication was accepted as is.
N/A Hydraulic Snubber / 10-32B-HS-277 CR-JAF-2008-04139 - ISI examination of snubber 10-32B-HS-277 identified settings not in accordance with the design drawing.
Engineering evaluation accepted all conditions identified.
N/A 15-3"-WES-151-136 Piping CR-JAF-2007-03665 - Small Bore Piping Leak Replacement Pinhole leak was evaluated and acceptable to Engineering for continued service.
Piping replacement performed per Work Order 00127395, reference repair replacement plan #07-025.
N/A 67-2-3"-WS-151-1 Piping CR-JAF-2007-03693 - Small Bore Piping Leak Replacement Pinhole leak was evaluated and acceptable to Engineering for continued service.
Piping replacement performed per Work Order 00127709, reference repair replacement plan #07-026.
N/A 15-8"-WES-151-100 Piping CR-JAF-2008-01914 - Piping Leak Replacement Pinhole leak was evaluated and acceptable to Engineering for continued service.
Piping replacement performed per Work Order 00155590, reference repair replacement plan #08-052.
N/A 29AOV-80D Repair CR-JAF-2008-03062 - MSIV 29AOV-80D LLRT failure.
Valve seats repaired per Work Order 00165300, reference repair replacement plan
- 08-058.
Engineering Report No. JAF-RPT-08-00019 Rev.0 Page 4 of 6
TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Class Item Description Date Repair/Replacement Description Of Work Completed Plan Number 1 02-2P-1B Seal Replacement 07/08/2005 05-019 3 46EXJ-7A Expansion Joint Replacement 12/06/2005 05-024 3 46EXJ-7B Expansion Joint Replacement 10/28/2006 06-040 3 70TCV-120A Valve Replacement 10/23/2007 07-003 3 70TCV-121A Valve Replacement 10/25/2007 07-004 3 70TCV-121B Valve Replacement 04/19/2007 07-005 3 70TCV-120B Valve Replacement- 04/20/2007 07-006 3 02RV-71F Valve Replacement 08/21/2007 07-007 3 70RWC-2B(CND) Tube Sheet Replacement 07/16/2007 07-010 3 BFSK-457 (66UC-22D) Support Repair (Removal and replacement 12/11/2008 07-019 for maintenance) 3 46P-2A Pump Replacement 12/14/2007 07-020 2 11P-2B Pump Replacement 01/03/2008 07-024 3 15-3"-WES-151-136 Piping Replacement -- 10/26/2007.07-025 3 67-2-3"-WS-151-1 Piping Replacement 10/31/2007 07-026 2 10-2B-HS-162 Snubber Replacement 02/20/2008 07-027 3 46RO-101A1 Repair Flange (weld Buildup) 12/12/2007 07-028 3 46(70)SWS-50A Valve Replacement 12/14/2007 07-029 2 1ORHR-51A AND 10RHR-52A Valve Replacement 04/29/2008 08-003 2 13RCIC-3 Valve Replacement 10/03/2008 08-004 2 10-9B-HS-287 Snubber Replacement 09/08/2008 08-005 1 02RV-71B Valve Replacement 10/05/2008 08-008 1 02RV-71F Valve Replacement (Main Body) 10/03/2008 08-010 1 02RV-71A Valve Replacement 10/05/2008 08-011 1 02RV-71C Valve Replacement 10/05/2008 08-012 1 02RV-71D Valve Replacement 10/05/2008 08-013 1 02RV-71F Valve Replacement 10/05/2008 08-014 1 02RV-71E Valve Replacement 10/05/2008 08-015 1 02RV-71G Valve Replacement 10/05/2008 08-016 1 02RV-71H Valve Replacement 10/05/2008 08-017 1 02RV-71J Valve Replacement 10/05/2008 08-018 1 02RV-71K Valve Replacement 10/05/2008 08-019 1 02RV-71L Valve Replacement 10/05/2008 08-020 2 27-2"-N-152A-23 Piping Replacement 09/29/2008 08-021 Engineering Report.No. JAF-RPT-08-00019 Rev.0 Page 5 of 6
TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE 1 02RV-71D Valve Replacement (Main Body) 10/05/2008 08-022 1 02RV-71E Valve Replacement (Main Body) 10/05/2008 08-023 1 34-4B-HS-36 Snubber Replacement 09/23/2008 08-024 1 34-4A-HS-16 Snubber Replacement 09/26/2008 08-025 1 29-1D-HS-41 Snubber Replacement 09/26/2008 08-026 1 29-1D-HS-36 Snubber Replacement 09/27/2008 08-027 1 29MOV-102 Valve Replacement 09/23/2008 08-028 1 02-2-1B-HS-20 Snubber Replacement 09/20/2008 08-029 1 03CRDU-(26-11, 26-43, 02-23, 02-31, 10- CRDM Replacement 09/26/2008 08-030 11, 10-15, 10-19, 18-07, 22-39, 22-51,
.26-35, 30-19, 34-23, 34-27, 42-11, 46-39) 2 23-19-HS-17 Snubber Replacement 09/02/2008 08-032 2 10-17-HS-57 Snubber Replacement 07/24/2008 08-033 2 23-1-HS-92 Snubber Replacement 08/18/2008 08-034 2 10-12A-HS-117 Snubber Replacement 07/23/2008 08-035 1 29-1B-HS-15 Snubber Replacement 09/20/2008 08-037 2 10-9B-HS-8 Snubber Replacement 09/08/2008 08-038 1 02-2-2A-HS-3 Snubber Replacement 09/24/2008 08-039 1 02-2-2B-HS-4 Snubber Replacement 09/19/2008 08-040 1 02-2-2A-HS-4 Snubber Replacement 09/24/2008 08-041 1 02-2-2B-HS-3 Snubber Replacement 09/19/2008 08-042 1 10-1-HS-208 Snubber Replacement 09/22/2008 08-043 1 14-5B-HS-43 Snubber Replacement 09/22/2008 08-044 1 14-5B-HS-44 Snubber Replacement 09/22/2008 08-045 1 34-5D-HS-27 Snubber Replacement 09/19/2008 08-046 3 BFSK-915 Support Repair (Removal and replacement 07/09/2008 08-047 for maintenance) 2 10-15A-MS-307 Snubber Replacement 08/11/2008 08-049 2 10-15A-MS-303 Snubber Replacement 08/18/2008 08-050 3 15-8"-WES-151-100 Piping Replacement 08/05/2008 08-052 1 29AOV-80D Repair 29AOV-80D LLRT Failure 10/01/2008 08-058 1 10-14B-HS-245A Snubber Replacement 09/26/2008 08-061 1 29-1C-HS-26 Snubber Replacement 09/26/2008 08-062 1 N2C-SE N2C Weld Overlay Repair 10/05/2008 08-063 Engineering Report No. JAF-RPT-08-00019 Rev.0 Page 6 of 6