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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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Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. Fitzpatrick NPP he Entergy RO. Box 110 Lycoming, NY 13093 Tel 315 349 6024 Fax 315 349 6480 T.A. Sullivan July 8, 2003 Site Vice President - JAF JAFP-03-0096 United States Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-Pl-17 Washington, DC 20555
Subject:
James A FitzPatrick Nuclear Power Plant Docket No. 50-333 Proposed Relief Request No. VRR-08 to the JAFNPP In-Service Testing Program
Dear Sir:
This submittal forwards proposed JAFNPP In-Service Testing (IST) Program Valve Relief Request VRR-08 for your review and approval. Within the scope of the current JAFNPP IST Program, certain Category C check valves are disassembled and inspected during each refueling outage in accordance with the provisions of ASME/ANSI OM-IO, Inservice Testing of Valves in Light Water Reactor Power Plants, Paragraphs 4.3.2.2(e) and 4.3.2.4(c). VRR-08 requests relief from the refueling outage restriction of Paragraphs 4.3.2.2(e) and 4.3.2.4(c) for these valves, permitting disassembly and inspection at a frequency of "at least once per operating cycle."
ASME/ANSI OM-10, Paragraph 4.3.2 requires check valves to be exercised to their safety position(s) quarterly, if practical, otherwise at cold shutdowns. If this, too, is impracticable, the Code allows testing to be deferred to refueling outages. Paragraph 4.3.2.2(e) states, "If exercising is not practicable during plant operation or cold shutdowns, it may be limited to full-stroke during refueling outage." Paragraph 4.3.2.4 addresses methods that may be used to perform these IST activities. Paragraph 4.3.2.4(c) states, "As an alternative to the testing in (a) or (b) above, disassembly every refueling outage to verify operability of check valves may be used."
Within the context of the approved JAFNPP Third Interval IST Program, testing of the following valves exercises the OM-10, Paragraph 4.3.2.4(c) disassemble and inspect option. These valves share the characteristic of having no position indication provision for the valve disc. Excerpts from the JAFNPP Third Interval IST Program Plan are provided in Attachment I which describe valve function and additional testing considerations for each of the listed valves.
15RBC-214 PASS Cooling Water Emerg Supply Check Valve 23HPI-13 HPCI Drain Pot Drain To Torus Stop Check Valve 23HPI-130 HPCI Gland Seal Cooling Return Check Valve 23HPI-131 HPCI Condensate Pump P-141 Disch Check Valve 23HPI-32 HPCI Booster Pump P-lB Suct From CST 33TK-12A and B Check Valve 23HPI-56 HPCI Drain Pot Drain To Torus Check Valve 23HPI-61 HPCI Booster Pump P-1B Suct From Suppression Pool Check Valve 23HPI-62 HPCI Min Flow Line To RHR Check Valve
United States Nuclear Regulatory Commission Attn: Document Control Desk
Subject:
Proposed Relief Request No. VRR-08 to the JAFNPP In-Service Testing Program Page 2 As stated, Paragraphs 4.3.2.2(e) and 4.3.2.4(c) of OM-10 limit the performance of check valve IST including disassembly and inspection activities to refueling outages. VRR-08 proposes as an alternative that the activities associated with Paragraphs 4.3.2.2(e) and 4.3.2.4(c) of OM-IO for the identified valves be performed on a frequency of at least once per operating cycle. The FitzPatrick staff considers this alternative acceptable for the following reasons:
- 1. Performance of these IST activities on a refueling outage frequency is currently acceptable in accordance with ASME/ANSI OM-10. By specifying testing activities on a frequency commensurate with each refueling outage, OM-10 recognizes and establishes an acceptable time period between testing. Historically, the refueling outages have provided a convenient and defined time period in which testing activities could be safely and efficiently performed.
However, an acceptable testing frequency can be maintained separately without being tied directly to a refueling outage. IST performed on a frequency that maintains the acceptable time period between testing activities during the operating cycle is consistent with the intent of OM-I0.
- 2. Over time, approximately the same number of tests would be performed using the proposed operating cycle test frequency as would be performed using the current refueling outage frequency. Thus, IST activities performed during the proposed operating cycle test frequency provide an equivalent level of quality and safety as IST performed at a refueling outage frequency.
- 3. A program for performing on-line maintenance is in place at FitzPatrick that complies with the requirements of 10 CFR5O.65(aX4), "Requirements for monitoring the effectiveness of maintenance at nuclear power plants." This program assures that, prior to performing a system outage on-line, its effect on risk is evaluated. Appropriate controls are implemented based on this evaluation. Within the context of this program, FitzPatrick has initiated efforts to perform additional maintenance, surveillance, and testing activities during normal operation. Planned activities are evaluated utilizing risk insights to determine the impact on safe operation ofthe plant and ability to maintain associated safety margins. Individual system components, a system train, or a complete system may be planned to be out of service to allow maintenance, or other activities, during normal operation.
As experience in performing on-line maintenance activities at FitzPatrick has increased, it has become evident that selected refueling outage IST activities could be performed during system outages on-line without sacrificing level of quality or safety. The disassembly and inspection activities required by OM-10 are examples of IST activities that can be performed safely and effectively on-line within the provisions of existing programmatic controls for on-line maintenance. The requested relief would permit these IST activities to be performed on-line, consistent with the performance of other on-line maintenance and testing activities, at no compromise to quality or safety.
Approval of the requested relief will remove a refueling outage constraint, allowing scheduling flexibility for inspection of these valves without compromising safety and without reduction of inspection frequency. Approval of the request will allow this work to be controlled in the same manner as other similar work within the affected systems. Similar relief has recently been approved for Entergy's River Bend Station Unit I (TAC NO. MB5834)
United States Nuclear Regulatory Commission Attn: Document Control Desk
Subject:
Proposed Relief Request No. VRR-08 to the JAFNPP In-Service Testing Program Page 3 provides excerpts from the approved JAFNPP Third Interval IST Program Plan as previously discussed. Attachment 2 contains the proposed relief request. If you have any questions, please contact Mr. John Hoddy at (315) 349-6538.
Very truly yours, Site Vice President cc:
Mr. Hubert J. Miller Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. Guy S. Vissing, Project Manager Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 8-C2 Washington, DC 20555-0001 Resident Inspector's Office James A. FitzPatrick U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093-0136 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza Albany, NY 12223 Mr. Peter R. Smith, Acting President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399
Attachment I to JAFP-03-0096 Excerpts from James A. Fitzpatrick Nuclear Power Plant Inservice Testing Program For Pumps And Valves Third Interval Plan
JAMES A. FITZPATRICK NUCLEAR POWER PLANT Pa Ss f 125 WNSERVICE TESTING PROGRAM FOR PUMPS AND VALVES JAFPRPT4MULTM4S3 Rsv. 5 VALVE TABLE SYSTEM DRAWING: FM-16C owe VALVE VALVE ACTUATOR SAFETY TEST REIEF ALTERNATE VALVE D, CO-ORD
_=_ _
CLASS CATEGORY SIZE (IN)
TYPE TYPE FUNCTION RTS CSROJ REQUEST TEST REMARKS
_--+ 15RBC-214 E-7 3 C 1.00 CK SA C RFC-1 ROJ-11 D153 ISSOV-215 E-7 3 a 1.00 Gl. so C P1T.5 PASSIVE
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JAMES A. FTPATRICK NUCLEA POWER PLANT Pe" of IN INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES JAF-RPTMULTW3S Rev. 6 VALVE TABLE SYSTEM DRAWING: FM-25A OWo VALVE VALVE ACTUATOR SAFETY TEST RELIEF ALTERNATE VALVE ID CLASS CATEGORY SZE (IN) TYPE TYPE FNCTn RMOYR rtRiOJ FP4ffT RV TET Rf 'UAR5
_--+ 23HP14- CO 2 C 2.00 SK SA 0 FFT-1 ROJ.13 RFC1 F0J.13 DIS3
_~ 23HP2 B..? 2 C 16.00 CK SA 0 FT1 P0J-15 Drr3 PFT-3 RFC1 ROJ-15 DS4
_ 23 2IM .4 2 C 4.00 CK SA 0 FFT-1 ROJ-l6 DIS-3 RFC-4 ROJ-16 23HPW5 C4 2 AC 20.00 LK S 0/C FFT7-IffC' FO12 RFC43 L4 23MOV.14 F-4 2 B 10.00 GA MO 0 STO.1 PIT4 231OV.15 F-4 I A 10.00 GA MO 0aC sTO-1 PITs LKJ4 23MOV.16 F-7 I A 10.00 GA MO OC 6701 ST ;1 LK14 23NOV.17 G4 2 B 14.00 GA MO C mlb PIT45 23NOV-19 F46 I A 14.00 A MO O/C STO-STC-1 PIT45 LK148 23MOV.20 F46 2 a 14.00 GA MO O ml P11W4 23MOV-21 G46 2 B 0.00 OL MO C 3TC81 PITB 23MOV.25 F4 2 B 4.00 GL MO 0 3T0-1 STC;1 PIT-4 23NOV.67 F4 2 B 14.00 GA MO 0 STO PIT-4
JAMES A. FITZPATRICK NUCLEAR POWER PLANT JAF-RPT-MULTI-03365 INS1RV TJ~Tm PROGRAM FOR PHMPS AND VATIVFR APPENDIX B DlAf-s-n dt L.-narn
-4n-r SYSTEM: CORE SPRAY (CSP)
COMPONENTS: 4CSP-62A,B C SAFETY FUNCTION: Th es close to prevent reverse fi the torus.
JUSTIFICATION: There ar ition indica ter means to verify closure of these valves. As a ,av ore must be verified by back-leakage testing.
Performing such a t plant operations would require setting up for and performin ydrostat t. As discussed in NUREG 1482, section 4.1.4, the has dete the need to set up test equipment is ad ustification to defer bac testing of a check valve until a re Kig outage. During cold shutdown, stem lineup changes and the ort involved with setting up test equi t would constitute an unreasonable burden on the plant staff.
AL E TEST These valves will be verified close each refueling outage i ance with OM-10 Section 4.3.2.2(e) and (h) during a hydrostatic leak rate tes R(T-1I SYSTEM: REACTOR BUILDING CLOSED LOOP COOLING (RBC)
COMPONENTS: lSRBC-214 CATEGORY: C SAFETY FUNCTION: This valve closes to prevent flow diversion when the Emergency Service Water system is supplying cooling water to RBC heat loads.
JUSTIFICATION: There is no provision on this valve that provides position indication of the disc. There are no test taps and block valves to enable a back-leakage test to verify closure.
ALTERNATE TEST OM-10, Section 4.3.2.4(c) allows disassembly each refueling outage to verify operability as an alternative to quarterly testing.
Rev. No. 6 Page 104 of 125
JAMES A. FITZPATRICK NUCLEAR POWR PLANT JAF-RPT-MULTI-03365 TNRIRVC¶. TF.WMGh1( PUROGRAM FOR PTMPS AND vAYVr APPENDIX B
-efni.1inlg Outage tifi'atins ROT-1 SYSTEM: HIGH PRESSURE COOLANT INJECTION (HOCI)
COMPONENTS: 23HPI-13 and 23HPI-56 CATEGORY: C SAFElY FUNCTION: These valves open to permit HPCI turbine condensate to drain to the Torus and close on cessation of flow.
JUSTIFICATION: There are no means for exercising these valves to the open position where positive indication of acceptable valve performance is verified. There is no provision that provides position indication of the disc. There are no test taps and block valves to enable a back-leakage test to verify closure.
ALTERNATE TEST OM-10, Section 4.3.2.4(c) allows disassembly each refueling outage to verify operability as an alternative to quarterly testing.
ROT-14 SYSTEM: HIGH PRESSURE COOLANT INJECTION (HPCI)
COMPONENTS: 23HPI-32 CATEGORY:C SAFETY FUNCTION: This valve closes during the suction swap from the Condensate Storage Tank to the torus to prevent diversion of the torus flow from the HPCI pump suction.
JUSTIFICATION: There is no provision on this valve that provides position indication of the disc. There are no block valves between this valve and the suction of the HPCI pump to enable a back-leakage test to verify closure.
ALTERNATE TEST OM-10, Section 4.3.2.4(c) allows disassembly each refueling outage to verify operability as an alternative to quarterly testing.
Rev. No. 6 Page 106 of 125
JAMES A. FITZPATRICK NUCLEAR POWER PLANT JAF-RPT-MULTI-03365 N.RVI(',E TRETJN( PROGRAM FOR PTM AD VAT.V APPENDIX B Rtfi-fin itngi TLstifinin-m ROI-1-5 SYSTEM: HIGH PRESSURE COOLANT INJECTION (HPCI)
COMPONENTS: 23HPI-61 CATEGORY:C SAFETY FUNCTION: This valve opens to provide a flowpath from the torus to the suction of the HPCI booster pump. It closes on cessation of flow.
JUSTIFICATION: The only practical method available to full flow exercise this valve is to pump water from the torus into the reactor vessel. Due to the lack of suitable water quality in the torus, this option is not practical. There is no provision on this valve that provides position indication of the disc. There are no test taps and block valves to enable a back-leakage test to verify closure.
ALTERNATE TEST OM-10, Section 4.3.2.4(c) allows disassembly each refueling outage to verify operability as an alternative to quarterly testing. In addition, this valve will be partial-flow tested once per operating cycle.
ROM16 SYSTEM: HIGH PRESSURE COOLANT INJECTION (HPCI)
COMPONENTS: 23HPI-62 CATEGORY: C SAFETY FUNCTION: This valve opens to provide a flowpath for minimum flow from the HPCI main pump. It closes on cessation of flow.
JUSTIFICATION: Due to the configuration of the minimum flow motor operated valve control logic, filly developed flow cannot be achieved through this check valve.
Additionally, full-stroke exercising cannot be verified with existing instumentation. There is no provision on this valve that provides position indication of the disc. There are no test taps and block valves to enable a back-leakage test to verify closure.
ALTERNATE TEST OM-10, Section 4.3.2.4(c) allows disassembly each refueling outage to verify operability as an alternative to quarterly testing.
Rev. No. 6 Page 107 of 125
JAMES A. FITZPATRICK NUCLEAR POWER PLANT JAF-RPT-MULTI-03365 INSERVIVE? TUMTIN(. PROG(RAM EOR PTMPS AmN) VAT.V APPENDIX B RQJT17 SYSTEM: HIGH PRESSURE COOLANT INJECTION (HPCI)
COMPONENTS: 23HPI-130 CATEGORY: C SAFETY FUNCTION: This valve opens to provide a flowpath for cooling water circulation through the HPCI turbine lube oil cooler and closes to prevent flow diversion.
JUSTIFICATION: This valve has no means of determining disc position or flowrate and, thus there is no mechanism for verifying full accident flow. In addition, there are no test taps and block valves to enable a back-leakage test to verify closure.
ALTERNATE TEST OM-10, Section 4.3.2.4(c) allows disassembly each refueling outage to verify operability as an alternative to quarterly testing. In addition, this valve will be partial-flow tested once per operating cycle.
ROA-1 SYSTEM: HIGH PRESSURE COOLANT INJECTION (PCI)
COMPONENTS: 23HPI-131 CATEGORY: C SAFETY FUNCTION: This valve closes to prevent flow diversion from the HPCI booster pump.
JUSTIFICATION: There is no provision on this valve that provides position indication of the disc. There are no test taps and block valves to enable a back-leakage test to verify closure.
ALTERNATE TEST OM-10, Section 4.3.2.4(c) allows disassembly each refueling outage to verify operability as an alternative to quarterly testing.
Rev. No. Page 108 of 125 to JAFP-03-0096 Proposed VRR-08
Attachment 2 to JAFP-03-0096 Proposed VRR-08 APPENDIX B Valve Relief Requests VRR-08 SYSTEM: Various Safety Related Check Valves (Listed Below) 15RBC-214 PASS Cooling Water Emerg Supply Check Valve 23HPI-13 HPCI Drain Pot Drain To Torus Stop Check Valve 23HPI-130 HPCI Gland Seal Cooling Return Check Valve 23HPI-131 HPCI Condensate Pump P-141 Disch Check Valve 23HPI-32 HPCI Booster Pump P-iB Suct From CST 33TK-12A and B Check Valve 23HPI-56 HPCI Drain Pot Drain To Torus Check Valve 23HPI-61 HPCI Booster Pump P-lB Suct From Suppression Pool Check Valve 23HPI-62 HPCI Min Flow Line To RHR Check Valve CATEGORY: C CLASS: 2, 3 FUNCTION: Various TEST REQUIREMENT: OM-10, Inservice Testing of Valves in Light Water Reactor Power Plants, section 4.3, Inservice Tests for Category C Valves", requires these valves to be tested nominally every 3 months, except as specified by paragraphs 4.3.2.2, 4.3.2.3, 4.3.2.4, and 4.3.2.5. For the listed valves, the FitzPatrick IST program exercises the provisions of OM-10, Sections 4.3.2.2(e) and 4.3.2.4(c) which together establish that: "As an alternative to the testing in [4.3.2.4] (a) or (b) above, disassembly every refueling outage to verify operability of check valves may be used." Thus, these valves are currently disassembled and inspected during each refueling outage.
RELIEF REQUESTED: Relaxation of the "refueling outage" restriction of OM-10, Sections 4.3.2.2(e) and 4.3.2.4(c) for testing of the listed valves to a test frequency of "at least once per operating cycle."
Attachment 2 to JAFP-03-0096 Proposed VRR-08 BASIS FOR RELIEF: Performance of these IST activities on a refueling outage frequency is currently acceptable in accordance with ASME/ANSI OM-10. By specifying testing activities on a frequency commensurate with each refueling outage, OM-10 recognizes and establishes an acceptable time period between testing. Historically, the refueling outages have provided a convenient and defined time period in which testing activities could be safely and efficiently performed. The specific restriction of these activities to a refueling outage is unnecessarily restrictive, however, as an acceptable testing frequency can be maintained separately without being tied directly to a refueling outage while still managing plant risk in accordance with 10 CFR 50.65(a)(4). IST performed on a frequency that maintains the acceptable time period between testing activities during the operating cycle is consistent with the intent of OM-10.
Over time, approximately the same number of tests would be performed using the proposed operating cycle test frequency as would be performed using the current refueling outage frequency.
Thus, IST activities performed during the proposed operating cycle test frequency provide an equivalent level of quality and safety as IST performed at a refueling outage frequency.
Any on-line IST activities associated with this relief will be performed subject to the FitzPatrick program for compliance with the requirements of 10 CFR 50.65(a)(4), "Requirements for monitoring the effectiveness of maintenance at nuclear power plants."
ALTERNATE TESTING: OM-10, Section 4.3.2.4(c) allows disassembly each refueling outage to verify operability as an alternative to quarterly testing.
This testing will be performed, with the exception that testing will at a frequency of at least once per operating cycle in lieu of during each refueling outage.