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| {{#Wiki_filter:f Entergy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 Pete Dietrich Site Vice President | | {{#Wiki_filter:f Entergy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc. |
| -JAF JAFP-10-0019 February 5, 2010 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 | | James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 Pete Dietrich Site Vice President - JAF JAFP-10-0019 February 5, 2010 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| | Application for Amendment to Modify Technical Specifications Section 5.5.7, Inservice Testing Program, to Reference the Current Code of Record (TAC No. ME2809), Corrected Technical Specification Pages James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59 |
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| ==REFERENCE:== | | ==REFERENCE:== |
| | Entergy Letter, Application for Amendment to Modify Technical Specifications Section 5.5.7, Inservice Testing Program, to Reference the Current Code of Record, JAFP-09-0131, dated November 23, 2009 |
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| Application for Amendment to Modify Technical Specifications Section 5.5.7, Inservice Testing Program, to Reference the Current Code of Record (TAC No. ME2809), Corrected Technical Specification Pages James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59 Entergy Letter, Application for Amendment to Modify Technical Specifications Section 5.5.7, Inservice Testing Program, to Reference the Current Code of Record, JAFP-09-0131, dated November 23, 2009
| | ==Dear Sir or Madam:== |
| | |
| | On November 23, 2009, Entergy Nuclear Operations, Inc. (Entergy) requested an amendment to the Technical Specifications (TS) for the James A. FitzPatrick Nuclear Power Plant (JAF), |
| | revising the American Society of Mechanical Engineers (ASME) Code of Record for the Fourth Inservice Testing (IST) Interval [Reference]. |
| | Subsequent to that submittal, it was identified that both the mark-up and final revised Technical Specification pages had a typographical error in the section heading. This letter resubmits the pages with the error corrected. Since the error was contained only in the transmitted pages and not in the current Technical Specification page, the change is not marked.with a revision bar. provides the corrected, proposed TS change mark-up page. provides the corrected, proposed TS change final typed format with change bars. |
| | There are no new commitments made in this letter. |
| | Questions concerning this request may be addressed to Mr. Joseph Pechacek, Licensing \ |
| | Manager, at (315) 349-6766. |
| | Vol |
| | |
| | JAFP-10-0019 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. |
| | Executed on the 5h da f February, 2010. |
| | Sincerel / .) |
| | Pete Dietrich PD/JP/ed Attachments: 1. Proposed Technical Specification Change (Mark-up, Corrected) |
| | : 2. Proposed Technical Specification Change (Final Typed, Corrected) cc: |
| | Mr. Samuel Collins Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Resident Inspector's Office 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-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8-C2A Washington, DC 20555-0001 Mr. Paul Eddy New York State Department of Public Service 3Albany, State EmpireNY 12223Plaza, 101h Floor Mr. Francis Murray, President New York State Energy Research and Development Authority 17 Columbia Circle Albany, NY 12203-6399 |
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| ==Dear Sir or Madam:==
| | JAFP-1 0-0019 Attachment 1 Proposed Technical Specification Change (Mark-up, Corrected) |
| On November 23, 2009, Entergy Nuclear Operations, Inc. (Entergy) requested an amendment to the Technical Specifications (TS) for the James A. FitzPatrick Nuclear Power Plant (JAF), revising the American Society of Mechanical Engineers (ASME) Code of Record for the Fourth Inservice Testing (IST) Interval [Reference].
| | Page 5.5-6 |
| Subsequent to that submittal, it was identified that both the mark-up and final revised Technical Specification pages had a typographical error in the section heading. This letter resubmits the pages with the error corrected.
| | |
| Since the error was contained only in the transmitted pages and not in the current Technical Specification page, the change is not marked.with a revision bar.Attachment 1 provides the corrected, proposed TS change mark-up page.Attachment 2 provides the corrected, proposed TS change final typed format with change bars.There are no new commitments made in this letter.Questions concerning this request may be addressed to Mr. Joseph Pechacek, Licensing
| | Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Primary Containment Leakage Rate Testing Program (continued) |
| \Manager, at (315) 349-6766.Vol JAFP-10-0019 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct.Executed on the 5h da f February, 2010.Sincerel / .)Pete Dietrich PD/JP/ed Attachments:
| | : d. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program. |
| : 1. Proposed Technical Specification Change (Mark-up, Corrected)
| | : e. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J. |
| : 2. Proposed Technical Specification Change (Final Typed, Corrected) cc: Mr. Samuel Collins Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Resident Inspector's Office 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-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8-C2A Washington, DC 20555-0001 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza, 101h Floor Albany, NY 12223 Mr. Francis Murray, President New York State Energy Research and Development Authority 17 Columbia Circle Albany, NY 12203-6399 JAFP-1 0-0019 Attachment 1 Proposed Technical Specification Change (Mark-up, Corrected)
| | 5.5.7 Inservice Testing Program This program provides controls for inservice testing of certain ASME Code Class 1, 2, and 3 pumps and valves. The program shall include the following: |
| Page 5.5-6 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Primary Containment Leakage Rate Testing Program (continued) | | : a. Testing Frequencies specified in Seetion X!-of the ASME Beiler anid Pressure Vessel OM Code and applicable Addenda are as follows: |
| : d. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.e. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J.Inservice Testing Program This program provides controls for inservice testing of certain ASME Code Class 1, 2, and 3 pumps and valves. The program shall include the following: | | ASME Boiler and Pressure Vessel OM Code and applicable Addenda terminology for Required Frequencies inservice testing for performing inservice activities testing activities Weekly At least ence per 31 days Quarterly or every 3 months At least once per 92 days ever; 6 months A* laSt. once per 184 days Every 9 months At l one. per 276 days n's Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days |
| : a. Testing Frequencies specified in Seetion X!-of the ASME Beiler anid Pressure Vessel OM Code and applicable Addenda are as follows: 5.5.7 ASME Boiler and Pressure Vessel OM Code and applicable Addenda terminology for inservice testing activities Required Frequencies for performing inservice testing activities Weekly Quarterly or every 3 months ever; 6 months Every 9 months Yearly or annually Biennially or every 2 years At least ence per 31 days At least once per 92 days A* laSt. once per 184 days At l n's one. per 276 days At least once per 366 days At least once per 731 days b. The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities; C. The provisions of SR 3.0.3 are applicable to inservice testing activities; and (continued) | | : b. The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities; C. The provisions of SR 3.0.3 are applicable to inservice testing activities; and (continued) |
| JAFNPP 5.5-6 Amendment 2-74 JAFP-1 0-0019 Attachment 2 Proposed Technical Specification Change (Final Typed, Corrected) | | JAFNPP 5.5-6 Amendment 2-74 |
| Page 5.5-6 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Primary Containment Leakage Rate Testing Program (continued) | | |
| : d. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.e. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J.Inservice Testing Program 5.5.7 This program provides controls for inservice testing of certain ASME Code Class 1, 2, and 3 pumps and valves. The program shall include the following: | | JAFP-1 0-0019 Attachment 2 Proposed Technical Specification Change (Final Typed, Corrected) |
| : a. Testing Frequencies specified in the ASME OM Code and applicable Addenda are as follows: ASME OM Code and applicable Addenda terminology for inservice testing activities Quarterly or every 3 months Biennially or every 2 years Required Frequencies for performing inservice testing activities At least once per 92 days At least once per 731 days b. The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities; | | Page 5.5-6 |
| | |
| | Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Primary Containment Leakage Rate Testing Program (continued) |
| | : d. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program. |
| | : e. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J. |
| | 5.5.7 Inservice Testing Program This program provides controls for inservice testing of certain ASME Code Class 1, 2, and 3 pumps and valves. The program shall include the following: |
| | : a. Testing Frequencies specified in the ASME OM Code and applicable Addenda are as follows: |
| | ASME OM Code and applicable Addenda terminology for Required Frequencies inservice testing for performing inservice activities testing activities Quarterly or every 3 months At least once per 92 days Biennially or every 2 years At least once per 731 days |
| | : b. The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities; |
| : c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and (continued) | | : c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and (continued) |
| JAFNPP 5.5-6 Amendment}} | | JAFNPP 5.5-6 Amendment}} |
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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
f Entergy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 Pete Dietrich Site Vice President - JAF JAFP-10-0019 February 5, 2010 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
SUBJECT:
Application for Amendment to Modify Technical Specifications Section 5.5.7, Inservice Testing Program, to Reference the Current Code of Record (TAC No. ME2809), Corrected Technical Specification Pages James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59
REFERENCE:
Entergy Letter, Application for Amendment to Modify Technical Specifications Section 5.5.7, Inservice Testing Program, to Reference the Current Code of Record, JAFP-09-0131, dated November 23, 2009
Dear Sir or Madam:
On November 23, 2009, Entergy Nuclear Operations, Inc. (Entergy) requested an amendment to the Technical Specifications (TS) for the James A. FitzPatrick Nuclear Power Plant (JAF),
revising the American Society of Mechanical Engineers (ASME) Code of Record for the Fourth Inservice Testing (IST) Interval [Reference].
Subsequent to that submittal, it was identified that both the mark-up and final revised Technical Specification pages had a typographical error in the section heading. This letter resubmits the pages with the error corrected. Since the error was contained only in the transmitted pages and not in the current Technical Specification page, the change is not marked.with a revision bar. provides the corrected, proposed TS change mark-up page. provides the corrected, proposed TS change final typed format with change bars.
There are no new commitments made in this letter.
Questions concerning this request may be addressed to Mr. Joseph Pechacek, Licensing \
Manager, at (315) 349-6766.
Vol
JAFP-10-0019 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct.
Executed on the 5h da f February, 2010.
Sincerel / .)
Pete Dietrich PD/JP/ed Attachments: 1. Proposed Technical Specification Change (Mark-up, Corrected)
- 2. Proposed Technical Specification Change (Final Typed, Corrected) cc:
Mr. Samuel Collins Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Resident Inspector's Office 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-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8-C2A Washington, DC 20555-0001 Mr. Paul Eddy New York State Department of Public Service 3Albany, State EmpireNY 12223Plaza, 101h Floor Mr. Francis Murray, President New York State Energy Research and Development Authority 17 Columbia Circle Albany, NY 12203-6399
JAFP-1 0-0019 Attachment 1 Proposed Technical Specification Change (Mark-up, Corrected)
Page 5.5-6
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Primary Containment Leakage Rate Testing Program (continued)
- d. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.
- e. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J.
5.5.7 Inservice Testing Program This program provides controls for inservice testing of certain ASME Code Class 1, 2, and 3 pumps and valves. The program shall include the following:
- a. Testing Frequencies specified in Seetion X!-of the ASME Beiler anid Pressure Vessel OM Code and applicable Addenda are as follows:
ASME Boiler and Pressure Vessel OM Code and applicable Addenda terminology for Required Frequencies inservice testing for performing inservice activities testing activities Weekly At least ence per 31 days Quarterly or every 3 months At least once per 92 days ever; 6 months A* laSt. once per 184 days Every 9 months At l one. per 276 days n's Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days
- b. The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities; C. The provisions of SR 3.0.3 are applicable to inservice testing activities; and (continued)
JAFNPP 5.5-6 Amendment 2-74
JAFP-1 0-0019 Attachment 2 Proposed Technical Specification Change (Final Typed, Corrected)
Page 5.5-6
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Primary Containment Leakage Rate Testing Program (continued)
- d. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.
- e. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J.
5.5.7 Inservice Testing Program This program provides controls for inservice testing of certain ASME Code Class 1, 2, and 3 pumps and valves. The program shall include the following:
- a. Testing Frequencies specified in the ASME OM Code and applicable Addenda are as follows:
ASME OM Code and applicable Addenda terminology for Required Frequencies inservice testing for performing inservice activities testing activities Quarterly or every 3 months At least once per 92 days Biennially or every 2 years At least once per 731 days
- b. The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities;
- c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and (continued)
JAFNPP 5.5-6 Amendment