|
---|
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
[Table view] |
Text
- -=- Entergy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel 315-342-3840 Joseph Pechacek Licensing Manager - JAF JAFP-11-0009 January 18, 2011 United States Nuclear Regulatory Commission ATTN: Samuel L. Hansell Jr.
Chief, Operations Branch, Division of Reactor Safety USNRC, Region I 475 Allendale Road King of Prussia, PA 19406-1415
Subject:
Inservice Inspection Summary Report 2010 Refuel Outage (Reload 19/Cycle 20)
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59
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-1 0-00008, Rev. 0 (Enclosure 1) which contains a summary of the Inservice Inspection (lSI) examinations conducted during the plant's fall 2010 Refuel Outage (Reload19/Cycle 20).
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).
JAFP-11-0009 Page 2 of 2 There are no commitments contained in this letter.
jJosep Licens
Enclosure:
JAF Owner's Activity Report (OAR) Second Outage, First Period, Fourth Interval JP/ed cc: Mr. William Dean 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 K. Vaidya Project Manager, LPL1-1 Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulations, Mail Stop: 08C2A Washington DC 20555 Mr. Francis J. Murray Jr., President NYSERDA 17 Columbia Circle Albany, NY 12203-6399
JAFP-11-0009 ENCLOSURE JAF Owner's Activity Report (OAR)
Second Outage, First Period, Fourth Interval (7 Pages)
ATTACHMENT 9.1 ENGINEERING REPORT COVER SHEET & INSTRUCTIONS SHEET 1 OF 2 Engineering Report No. JAF-RPT-1O-00008 Rev 0 Page 1 of 7 J!l
~Entergy ENTERGY NUCLEAR Engineering Report Cover Sheet Engineering Report
Title:
JAF Owner's Activity Report (OAR) Second Outage, First Period, Fourth Interval Engineering Report Type:
New [8J Revision 0 Cancelled 0 Superseded 0 Superseded by: N/A Applicable Site(s)
IP1 0 IP2 0 IP3 0 JAP [8J PNPS 0 yyD WPO 0 AN01 0 AN02 0 ECH 0 GGNS 0 RBS 0 WF3 0 PLP 0 EC No. 0000026741 Report Origin: [8J Entergy 0 Vendor Vendor Document No.: N/A Quality-Related: [8J Yes o No Prepared by: - ': :SC~o~t :. !R~e~e~d_- :,. : S=-: ::--~/=-..:~:::::)::..-
Responsible Engineer (Print Name/Sign)
_ Date: 01/0512011 Design Verified: Design Verification is not required Date: -...:N:...:,/:..;.A.:........_ _
Design Verifier (if required) (Print Name/Sign)
Reviewed by: Mike Rose 'it72 ~. p,..!..oA--~""~'"""",, _ Date: 01/05/2011 Reviewer (Prin~e/Slgn)
Reviewed by*: ~C:!!h~ar:!!li~e.!:R~o~se~~~~~~~========= _ Date: 01105/2011
~~?d) (Print N,m,/SrJ Approved by: -=-p.::at:...:s:..:c:.:a=n:::la=n_~....Llc¥:.!:::~*
!S:*: . . -12:. . . .l.,.,:. ~l~ ~ J~d JfL:s.: .:. :!:-
Supervisor / Manager (Print Name/Sign)
_ Date:
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number JAF-RPT-10-00008 Plant James A. FitzPatrick Nuclear Power Plant, 268 Lake Road East, Lycoming New York 13093 Unit No. 1 Commercial Service Date July 28, 1974 Refueling Outage Number R19
'-=---
(if applicable)
Current Inspection Interval 4th (1'" 2nd , 3rd, 4th, other)
Current Inspection Period 1st (1", 2nd , 3rd )
Edition and Addenda of Section XI applicable to the Inspection Plans 2001 Edition, 2003 Addenda Date I Revision of Inspection Plans March 1,2007/151 Program Plan No. ENN-SEP-JAF-007 Revision 2 Edition and Addenda of Section XI applicable to repairlreplacement activities, if different than the inspection plans Same Code Cases used: .-:...:N_-4:..=1..::.6--=3:L'.:...:N-=-S:..=3..::.2_-4:...- _
CERTIFICATE OF CONFORMANCE I certify that Ca) 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 repairlreplacement activities and evaluations supporting the completion of R19 "n'o,m to the '""'cem,,,ts of 5edJon XI . __~ ( _ i " , """" "mw' Signed Scott Reed Sc-.r-- ~ Date 01/05/2011
{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. Furthenmore, neither the Inspector nor his employer shall be liable in any manner for any personal inju r property damage or a loss of any kind arising from or connected with this inspection
~C~ha~r~lie~Ro~s~e~:;:~~~~~~====~=elmmissions NY5364 National Board, State, Province, and Endorsements Date 01/05/2011 Engineering Report No. JAF-RPT-10-00008 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-G-1 / B6.200 02-2-P-1A CR-JAF-2010-06107 - Yr-1 examination of pump bolting, nuts and washers identified a nick on the washer flange inner taper that extended into the first (leading) thread of the nut.
The damaQed nut and all 16 washers were replaced.
R-A / R1.16-5 24-10-130 CR-JAF~201O-05601 - Thickness measurements taken on the valve adjacent to RHR weld 24-10-130 indentified thicknesses below the min-wall thickness of 2.38".
The lowest thickness measurement found was 2.18".
Engineering evaluated the condition and accepted as is. Acceptability of the identified condition is demonstrated in EC 0000024812 which shows that the valve thickness meets ASME code requirements.
R-A / R1.16-5 24-10-130 CR-JAF-2010-05602 - In conjunction with CR-JAF-2010-05601, this CR is being written to document thickness readings below the calculated minimum wall taken on the weld centerline of RHR weld 24-10-130.
Engineering evaluated the condition and accepted as is. The area of reduced wall thickness in weld 24-10-130 was evaluated in revision 1 of JAF-CALC-10-00028 issued under EC 0000024635, Rev. 1. The evaluation concluded that the weld is acceptable as is based on the use of ASME section XI, AppendiX C methods to show acceptable structural margin for loads (including circumferential pressure stress) inciudinQ the effects on the locally thin reQion.
F-A / F1.10b 29-1D-AN-33A CR-JAF-2010-05922 - Conflicting information stamped on component vs drawing.
During the examination the inspection identified hot and cold setting of 6956 and 7567 pounds respectfully on the spring hangers. Drawing Number 6.21-H29-7B Rev. 4 shows the cold setting of 9478 pounds.
Engineering evaluated the condition and accepted as is. No changes to existing spring hangers were required. EC 0000024992 and calculation for drawing chanQes was completed.
Engineering Report No. JAF-RPT-10-00008 Rev.O Page 3 of 7
TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE R-A / R1.13-1 ESW-022 CR-JAF-2010-02540 - Condition report generated for engineering evaluation of UT thickness examination results, remaining service life and identification of re-examination requirements.
Engineering evaluated the condition and accepted as is. EC 0000023804 generated for calculation update and remaining service life. Work order 00247538 for reolacement of oioina aenerated.
E-A / E1.ll Torus Saddle Support / CR-JAF-2010-00895 - IWE General Visual examination of the primary containment SC-SD-Azm @ 10°-54' (Torus) saddle support assembly identified hold down brackets with relevant SC-SD-Azm @ 100°-54' conditions per the ASME Section XI program.
SC-SD-Azm @ 124°-6' SC-SD-Azm @ 145°-54' Engineering evaluated the condition and accepted as is. EC 0000021438 SC-SD-Azm @ 235°-54' evaluated the base tie-down bracket gaps that were identified in this condition SC-SD-Azm @ 259°-6' report that did not meet the requirements prOVided on the plant drawings. The EC SC-SD-Azm @ 280°-54' evaluation clarified and added gap tolerances on plant draWings 3.72-16 and 3.72-SC-SD-Azm @ 304°-6' 17. These drawing changes are attached to the EC as draWing markups.
SC-SD-Azm @ 349°-6' E-A / E1.11, E1.30 Primary Containment Moisture CR-JAF-2010-05936 - 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. Primary Containment Liner corrosion identified in CR-JAF-2008-03508 could not be adequately addressed under WO 00166758. The work order was written to determine the extent of corrosion and subsequent repairs of areas identified in the IWE examinations performed in R18 and discussed in CR-JAF-2008-03508.
These conditions were evaluated and acceptable to Engineering for continued service. Work Order 00166758 was revised to perform additional concrete excavation and the surface area was cleaned and prepped for a VT-1 of the steel liner. Pit depth measurements and UT examination of the steel liner was performed. Examinations were accepted based on pitting not exceeding enaineerina acceotance criteria.
Engineering Report No. JAF-RPT-10-00008 Rev.O Page 4 of 7
TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE E-A / E1.ll, E1.30 Torus Interior CR-JAF-2010-06235 - 151 VT-1 examination of the Torus wetted surface areas identified delaminated coatings from the 2006 repaired areas at ring girders 15 and 16.
As identified in the condition report, Underwater Construction Company (UCC) divers removed the delaminated / loose coatings during the examination. The coatings removed were essentially the entire coating applied during the 2006 repairs and consisted of an approximate 10" round area. Surface condition of the repaired areas was found in good condition and no FME concerns exists. Work order 00254828 generated to recoat the repair areas during future torus work.
N/A Hydraulic Snubber / 10-15B-HS-1l9B CR-JAF-2010-05115 - Examination of snubber 10-15B-HS-119B identified settings not in accordance with the design drawing.
Engineering evaluation the condition and accepted as is drawings revised.
N/A Hydraulic Snubber / 12-1-HS-20 CR-JAF-2010-05592 - Examination of snubber 12-1-HS-20 identified a low fluid level.
The removed snubber tested satisfactory, snubber replacement installed. No additional corrective actions are required.
N/A Hydraulic Snubber / 12-1-HS-18 and CR-JAF-2010-05680 - Examination identified snubbers misalignment with their 12-1-HS-19 associated pipe clamps.
Snubber clamp realignment was completed per WO 51693915.
N/A Hydraulic Snubber / 29-R1F-HS-123A CR-JAF-2010-05781 - Examination identified snubber missing spacers on the end attachments.
Spacers installed per WO 51693915.
N/A Hydraulic Snubber / 23-19A-HS-2 CR-JAF-2010-06318 - Examination of snubber 23-19A-HS-2 identified a low fluid level.
The removed snubber tested satisfactory, snubber replacement installed per WO 00252032.
N/A 10S-5Bl CR-JAF-2010-03442 - ESW Strainer Leak Pinhole leak was evaluated and acceptable to Engineering for continued service.
Strainer repair performed per Work Order 00241657.
Engineering Report No. JAF-RPT-10-00008 Rev.O Page 5 of 7
TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Date Repair/Replacement Class Description Of Work Completed Plan Number 3 66UC-22G(PM) Unit Cooler maintenance / repair 02/18/2009 07-022 2 10E-2A Heat ExchanQer repair 06/26/2009 08-002 3 46SWS-63A Valve Replacement 03/11/2009 08-036 3 46ESW-8B Valve Replacement 09/28/2010 08-059 2 23HPI-61 Valve Bolting Replacement 01/22/2009 09-003 3 70RWC-2A Chiller Replacement 09/24/2009 09-006 3 70RWC-2B Chiller Replacement 09/24/2009 09-007 3 70PCV-I00Bl and 100B2 Valve Replacement 06/01/2009 09-008 3 70PCV-I00Al and 100A2 Valve Replacement 04/22/2009 09-009 3 10P-1O RHR Pump Replacement 03/18/2010 09-012 3 PFSK-2188 Reoair of Pipe Support 12/09/2009 09-014 3 67UC-16A Piping Replacement 12/10/2009 09-015 3 66UC-22E Unit Cooler maintenance / repair 06/04/2010 09-017 3 66UC-22F Unit Cooler maintenance / repair OS/21/2010 09-018 1 02-2-1A-HS-15 Snubber Replacement 10/01/2010 09-019 1 02-2-1A-HS-16 Snubber Replacement 10/01/2010 09-020 1 02-2-1A-HS-17 Snubber Replacement 10/01/2010 09-021 1 12-1-HS-18 Snubber Replacement 09/25/2010 09-022 1 29-1A-HS-4 Snubber Replacement 09/25/2010 09-024 1 29-1B-HS-ll Snubber Replacement 09/24/2010 09-025 1 02-2-2A-HS-4 Snubber Replacement 09/26/2010 09-026 2 14SV-20A Valve Replacement 04/26/2010 09-027 2 23-19-HS-13 Snubber Replacement 08/16/2010 10-002 2 10-10B-HS-19 Snubber Replacement 09/13/2010 10-003 3 70AHU-19B Air handling unit maintenance / Piping 2/2/2010 10-004 replacement 2 03TK-125 (HCU-14-23) Accumulator replacement 9/26/2010 10-005 1 34-5D-HS-26 Snubber Replacement 9/24/2010 10-008 1 02RV-71A Valve Replacement (Pilot) 10/08/2010 10-009 1 02RV-71B Valve Replacement (Pilot) 10/11/2010 10-010 Engineering Report No. JAF-RPT-10-00008 Rev.O Page 6 of 7
TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE 1 02RV-71D Valve Replacement Pilot 10/08/2010 10-011 1 02RV-71G Valve Replacement Pilot 10/11/2010 10-012 1 02RV-71H Valve Replacement Pilot 10/11/2010 10-013 1 02RV-71J Valve Replacement Pilot 10/11/2010 10-014 1 02RV-71K Valve Replacement Pilot 10/11/2010 10-015 1 02RV-71L Valve Replacement Pilot 10/11/2010 10-016 1 02RV-71F Valve Replacement Main Body) 10/02/2010 10-017 1 02RV-71C Valve Replacement Main Body) 10/01/2010 10-018 1 02RV-71E Valve Replacement Main Body) 10/02/2010 10-019 1 39ACC-256E Accumulator replacement 10/02/2010 10-020 1 39ACC-256C Accumulator replacement 10/02/2010 10-021 1 03CRDU-(06-15,10-47,14-47,22-31,30- CROM Replacement 09/29/2010 10-022 1530-39,42-15 and 50-23) 2 1O-13A-HS-109A Snubber Replacement 08/24/2010 10-024 2 10-9A-HS-39 Snubber Replacement 08/262010 10-025 2 10-9A-MS-254 Snubber Replacement 09/09/2010 10-026 2 10-15B-HS-122 Snubber Replacement 09/24/2010 10-027 2 10-15B-MS-124B Snubber Replacement 09/12/2010 10-028 2 10-3B-HS-153 Snubber Replacement 09/11/2010 10-029 2 10-8B-HS-l0 Snubber Replacement 09/13/2010 10-030 2 10-9B-HS-7 Snubber Replacement 09/14/2010 10-031 2 14SV-20B Valve Replacement 08/06/2010 10-032 3 10S-5Bl Strainer pressure boundary repair 07/14/2010 10-033 1 02-2P-1A Pump rotating element and cover 10/07/2010 10-036 replacement 1 02-2P-1B Pump Mechanical Seal replacement 10/04/2010 10-041 1 12-1-HS-20 Snubber Replacement 10/01/2010 10-042 1 29AOV-80C Valve Repair 09/29/2010 10-043 1 02-2-2B-HS-8 Snubber Replacement 09/28/2010 10-045 2 14-9A-HS-15 Snubber Replacement 09/25/2010 10-046 2 23-19A-HS-2 Snubber Replacement 10/10/2010 10-047 3 46EXJ-9A Expansion Joint Replacement 9/25/2010 10-048 3 46EXJ-9C Expansion Joint Replacement 9/25/2010 10-049 1 02V-l Vent Piping Bolting Replacement 10/06/2010 10-050 Engineering Report No. JAF-RPT-10-00008 Rev.O Page 7 of 7