Letter Sequence Other |
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Results
Other: JAFP-06-0109, License Renewal Application, Amendment 10, RAI Responses, JAFP-07-0019, License Renewal Application, Amendment 9, JAFP-07-0021, License Renewal Application, Amendment 6, ML062160494, ML062780187, ML070380370, ML070520059, ML071270080, ML071270377, ML071580049, ML071970491, ML072690528, ML072690529, ML080140266, ML080420252, ML081010259, ML081010277, ML081010332
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MONTHYEARML0621604942006-07-31031 July 2006 James A. Fitzpatrick License Renewal Application, Cover Page Through Chapter 4 Project stage: Other ML0627801872006-10-23023 October 2006 Memorandum - Audit and Review Plan for Plant Aging Management Reviews and Programs, and Time-Limited Aging Analyses for the James A. Fitzpatrick Power Plant Project stage: Other ML0627801552006-10-23023 October 2006 License Renewal Audit and Review Plan Project stage: Acceptance Review ML0634004152006-12-0404 December 2006 (PA-LR) AMP Audit Request and Response Items 50 - 417 Project stage: Acceptance Review ML0700800142007-01-12012 January 2007 Requests for Additional Information Regarding the Review of the License Renewal Application for James A. FitzPatrick Nuclear Power Plant Project stage: RAI ML0701201962007-01-19019 January 2007 Requests for Additional Information Regarding the Review of the License Renewal Application for James A. FitzPatrick Nuclear Power Plant Project stage: RAI ML0703803892007-02-0606 February 2007 JAFNPP AMP and AMR Database Project stage: Acceptance Review ML0703803702007-02-0707 February 2007 Docketing of Audit Date Base for Aging Management Programs (AMP) and Aging Management Reviews (AMR) Pertaining to License Renewal Application of the James A. Fitzpatrick Nuclear Power Plant Project stage: Other JAFP-07-0021, License Renewal Application, Amendment 62007-02-12012 February 2007 License Renewal Application, Amendment 6 Project stage: Other ML0705200592007-02-20020 February 2007 Note to File: Docketing of Email Pertaining to License Renewal Application of the James A. Fitzpatrick Nuclear Power Plant. Project stage: Other ML0703700232007-02-23023 February 2007 Requests for Additional Information Regarding the Review of the License Renewal Application for James A. FitzPatrick Nuclear Power Plant Project stage: RAI ML0713504332007-04-0505 April 2007 JAF-RPT-05-AMM30, Rev 4, Draft, Aging Management Review of Nonsafety-Related Systems and Components Affecting Safety-Related Systems, (FitzPatrick) Project stage: Draft Other JAFP-07-0019, License Renewal Application, Amendment 92007-04-0606 April 2007 License Renewal Application, Amendment 9 Project stage: Other JAFP-06-0109, License Renewal Application, Amendment 10, RAI Responses2007-04-24024 April 2007 License Renewal Application, Amendment 10, RAI Responses Project stage: Other ML0712700802007-05-0404 May 2007 Docketing of E-mail Pertaining to License Renewal Application of the James A. FitzPatrick Nuclear Power Plant Project stage: Other ML0712703772007-05-0404 May 2007 License Renewal Application Amendment 10 - Added Item (4) Project stage: Other ML0705804642007-05-25025 May 2007 Audit Summary for the JAFNPP LRA Safety Site Audits Project stage: Acceptance Review ML0715800492007-06-19019 June 2007 Audit Summary Report for Plant Aging Management Reviews and Programs for the James A. FitzPatrick Nuclear Power Plant on License Renewal Application Project stage: Other ML0719704912007-07-10010 July 2007 Docketing of Document Received from the Applicant Pertaining to License Renewal Application of the James A. FitzPatrick Nuclear Power Plant Project stage: Other ML0720102672007-07-25025 July 2007 Request for Additional Information Regarding the Review of the License Renewal Application for James A. FitzPatrick Nuclear Power Plant Project stage: RAI ML0715802992007-07-31031 July 2007 Transmittal of Safety Evaluation Report with Open and Confirmatory Items Related to the License Renewal of James A. FitzPatrick Nuclear Power Plant Project stage: Approval ML0726905292007-09-0505 September 2007 ACRS License Renewal Subcommittee Presentation September 5, 2007 Project stage: Other ML0726905372007-09-0505 September 2007 License Renewal Safety Evaluation Report Staff Presentation to the ACRS Project stage: Approval ML0726905282007-09-26026 September 2007 Docketing of Slides Presentation to ACRS Subcommittee Pertaining to License Renewal Application of the James A. FitzPatrick Nuclear Power Plant Project stage: Other ML0801402662008-02-0808 February 2008 Audit Q&A Database for FitzPatrick Nuclear Plant Aging Mgmt Programs, Aging Mgmt Reviews, and Time-Limited Aging Analyses - Audit Team'S Evaluation of the Applicant'S Responses Project stage: Other ML0801404662008-02-0808 February 2008 Q & a Database - Audit Team'S Evaluation Project stage: Acceptance Review ML0804202522008-02-14014 February 2008 Audit Question and Answer Database for James A. FitzPatrick Nuclear Power Plant Aging Management Programs, Aging Management Reviews, and Time-Limited Aging Analyses - Audit Team'S Evaluation of the Applicant'S Responses Project stage: Other ML0808400482008-03-0606 March 2008 ACRS NRC, Fitzpatrick Lr SER Project stage: Request ML0808400822008-03-0606 March 2008 ACRS Fitzparick Lr Presentation Project stage: Request ML0808000342008-03-24024 March 2008 Docketing of Slides Presentations to ACRS Full Committee Meeting Pertaining to License Renewal Application of the James A. Fitzpatrick Nuclear Power Plant Project stage: Meeting ML0810102592008-09-0808 September 2008 Renewed Facility Operating License No. DPR-59 Project stage: Other ML0810102772008-09-0808 September 2008 Renewed Facility Operating License No. DPR-59 / Appendix C - Additional Conditions Project stage: Other ML0810102422008-09-0808 September 2008 Renewed Facility Operating License No. DPR-59 / Appendix a - Technical Specifications Project stage: Acceptance Review ML0810103322008-09-0808 September 2008 Renewed Facility Operating License No. DPR-59 / FRN Project stage: Other ML0824903692008-09-0808 September 2008 Issuance of Renewed Facility Operating License No. DPR-59 for James A. Fitzpatrick Nuclear Power Plant Project stage: Approval 2007-04-06
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Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARJAFP-24-0047, License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software2024-09-25025 September 2024 License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software JAFP-24-0045, Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2024-09-20020 September 2024 Supplemental Information for 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-24-0036, Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-07-29029 July 2024 Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis ML24190A1932024-07-0909 July 2024 Correction Letter of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition JAFP-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-23-0048, 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-23-0040, 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-23-0038, 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 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments ML21181A0572021-11-0404 November 2021 Issuance of Amendment No. 344 Adoption of TSTF-545 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-21-0069, 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-21-0053, 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-21-0051, 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 ML21144A1072021-05-17017 May 2021 Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-582 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 RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments JAFP-20-0083, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule2020-12-11011 December 2020 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-20-0080, Application to Revise Surveillance Requirement (SR) 3.5.1.62020-12-11011 December 2020 Application to Revise Surveillance Requirement (SR) 3.5.1.6 JAFP-20-0047, License Amendment Request: Application to Modify Technical Specifications 3.6.1.3, Primary Containment Isolation Valves2020-06-30030 June 2020 License Amendment Request: Application to Modify Technical Specifications 3.6.1.3, Primary Containment Isolation Valves JAFP-20-0046, License Amendment Request for Adoption of TSTF-478-A, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control, Using the Consolidated Line Item.2020-06-30030 June 2020 License Amendment Request for Adoption of TSTF-478-A, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control, Using the Consolidated Line Item. RS-20-025, Supplement to Exelon Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2020-02-24024 February 2020 Supplement to Exelon Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls JAFP-20-0012, License Amendment Request - Application to Adopt Technical Specification Task Force Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, Using the Consolidated Line...2020-01-23023 January 2020 License Amendment Request - Application to Adopt Technical Specification Task Force Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, Using the Consolidated Line... ML19295G7832019-12-19019 December 2019 Issuance of Amendment No. 331 Regarding Change to Technical Specifications to Remove Ultimate Heat Sink Bar Rack Heaters ML19277G0852019-10-0404 October 2019 Emergency License Amendment Request: One Time Extension to the TS 3.8.1 Action A.3 Completion Time for an Inoperable Offsite Source ML19277D5522019-10-0404 October 2019 Draft James A. FitzPatrick Nuclear Power Plant - Emergency License Amendment Request - One Time Extension to the TS 3.8.1 Action A.3 Completion Time for an Inoperable Offsite Source ML19276G3132019-10-0202 October 2019 Draft Exigent License Amendment Request - One Time Extension to the TS 3.8.1 Action A.3 Completion Time for an Inoperable Offsite Source JAFP-19-0092, Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers2019-09-26026 September 2019 Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers JAFP-19-0089, License Amendment Request - Proposed Changes to the Technical Specifications Related to Primary Containment Hydrodynamic Loads2019-09-12012 September 2019 License Amendment Request - Proposed Changes to the Technical Specifications Related to Primary Containment Hydrodynamic Loads JAFP-19-0083, License Amendment Request - Proposed Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation2019-09-0505 September 2019 License Amendment Request - Proposed Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions ML19157A2032019-07-11011 July 2019 Issuance of Amendment No. 325 Reactivity Anomalies Surveillance JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program RS-19-038, Supplement to the Application to Adopt TSTF-564, Safety Limit MCPR2019-03-0707 March 2019 Supplement to the Application to Adopt TSTF-564, Safety Limit MCPR JAFP-19-0033, License Amendment Request - Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Revision 02019-03-0707 March 2019 License Amendment Request - Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Revision 0 RS-19-003, Application to Adopt TSTF-564, Safety Limit Mcpr.2019-02-0101 February 2019 Application to Adopt TSTF-564, Safety Limit Mcpr. JAFP-18-0106, License Amendment Request: Proposed Change to the Technical Specifications to Remove Ultimate Heat Sink Bar Rack Heaters from Technical Specifications2018-11-29029 November 2018 License Amendment Request: Proposed Change to the Technical Specifications to Remove Ultimate Heat Sink Bar Rack Heaters from Technical Specifications RS-18-130, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2018-11-0101 November 2018 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO JAFP-18-0093, License Amendment Request - Reactivity Anomalies Surveillance2018-10-0202 October 2018 License Amendment Request - Reactivity Anomalies Surveillance ML18292A5282018-09-25025 September 2018 Technical Evaluation Input for License Amendment Request to Remove Requirements for Deicing Heaters from Technical Specification 3.7.2 RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement 2024-09-25
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Text
Renewed License No. DPR-59 ENTERGY NUCLEAR FITZPATRICK, LLC AND ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT RENEWED FACILITY OPERATING LICENSE Renewed License No. DPR-59
- 1. The Nuclear Regulatory Commission (NRC or the Commission), having previously made the findings set forth in Facility Operating License No. DPR-59, dated November 21, 2000, has found that:
A. The application to renew Facility Operating License No. DPR-59 filed by Entergy Nuclear FitzPatrick, LLC (ENF) and Entergy Nuclear Operations, Inc.
(ENO) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. Actions have been identified and have been or will be taken with respect to: (1) managing the effects of aging on the functionality of structures and components that have been identified to require review under 10 CFR 54.21(a)(1) during the period of extended operation, and (2) time-limited aging analyses that have been identified to require review under 10 CFR 54.21(c), such that there is reasonable assurance that the activities authorized by this renewed operating license will continue to be conducted in accordance with the current licensing basis, as defined in 10 CFR 54.3 for the facility, and that any changes made to the facility's current licensing basis in order to comply with 10 CFR 54.29(a) are in accordance with the Act and the Commission's regulations; D. There is reasonable assurance (i) that the activities authorized by this renewed operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; E. ENF and ENO are financially and technically qualified to engage in the activities authorized by this renewed operating license; F. ENF and ENO have satisfied the applicable provisions of 10 CFR Part 140, "Financial Protection Requirements and Indemnity Agreements" of the Commission's regulations;
Renewed License No. DPR-59 G. The issuance of this renewed operating license will not be inimical to the common defense and security or to the health and safety of the public; H. The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this renewed operating license will be in accordance with the Commission's regulations; in 10 CFR Parts 30, 40, and 70, including 10 CFR Sections 30.33, 40.32, 70.23, and 70.31; and I. The issuance of this renewed operating license is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, Facility Operating License No. DPR-59 (previously issued to the Power Authority of the State of New York and Niagara Mohawk Power Corporation pursuant to the Atomic Safety and Licensing Board's Initial Decision and Supplemental Initial Decision dated November 12, 1973, and January 10, 1974, respectively; and the Atomic Safety and Licensing Appeal Board's Decision dated January 29, 1974) as previously amended and transferred to ENF and ENO dated November 21, 2000, is superseded by Renewed Facility Operating License No. DPR-59, hereby issued to ENF and ENO to read as follows:
A. This renewed operating license applies to the James A. FitzPatrick Nuclear Power Plant, a boiling water nuclear reactor and associated equipment (the facility), owned by ENF and operated by ENO. The facility is located in Scriba, Oswego County, New York, and is described in the "Final Safety Analysis Report," as supplemented and amended, and the Environmental Report, as supplemented and amended.
B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:
(1) Pursuant to Section 104b of the Act and 10 CFR Part 50, "Licensing of Production and Utilization Facilities," a) ENF to possess and use and b) ENO to possess, use and operate the facility at the designated location in Scriba, Oswego County, New York, in accordance with the procedures and limitations set forth in this renewed operating license; (2) ENO pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time, special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3) ENO pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use, at any time, any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; Renewed License No. DPR-59 (4) ENO pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use, at any time, any byproduct, source and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration; or associated with radioactive apparatus, components or tools.
(5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level ENO is authorized to operate the facility at steady state reactor core power levels not in excess of 2536 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 291, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protections program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated November 20, 1972; the SER Supplement No. 1 dated February 1, 1973; the SER Supplement No. 2 dated October 4, 1974; the SER dated August 1, 1979; the SER Supplement dated October 3, 1980; the SER Supplement dated February 13, 1981; the NRC Letter dated February 24, 1981; Technical Specification Amendments 34 (dated January 31, 1978), 80 (dated May 22, 1984), 134 (dated July 19, 1989), 135 (dated September 5, 1989), 142 (dated October 23, 1989), 164 (dated August 10, 1990), 176 (dated January 16, 1992), 177 (dated February 10, 1992), 186 (dated February 19, 1993), 190 (dated June 29, 1993), 191 (dated July 7, 1993), 206 (dated February 28, 1994), and 214 (dated June 27, 1994); and NRC Exemptions and associated safety evaluations dated April 26, 1983, July 1, 1983, January 11, 1985, April 30, 1986, September 15, 1986 and September 10, 1992 subject to the following provision:
Renewed License No. DPR-59 ENO may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
(4) Systems Integrity Deleted by Amendment No. 274 (5) Iodine Monitoring Deleted by Amendment No. 274 (6) New or Revised ITS Surveillance Requirements Applicability:
The schedule for performing Surveillance Requirements (SRs) that are new or revised in Amendment No. 274 shall be as follows:
(a) For SRs that are new in this amendment, the first performance is due at the end of the first surveillance interval that begins on the date of implementation of this amendment.
(b) For SRs that existed prior to this amendment whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.
(c) For SRs that existed prior to this amendment whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to implementation of this amendment.
(d) For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance is due at the end of the first surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.
D. Physical Protection ENO shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans 1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "James A. FitzPatrick Nuclear Power Plant Physical Security, Training & Qualification and 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Renewed License No. DPR-59 Safeguards Contingency Plan, Revision 0," submitted by letter dated October 26, 2004, as supplemented by letter dated May 17, 2006.
E. Power Uprate License Amendment Implementation The licensee shall complete the following actions as a condition of the approval of the power uprate license amendment.
(1) Recirculation Pump Motor Vibration Perform monitoring of recirculation pump motor vibration during initial Cycle 13 power ascension for uprated power conditions.
(2) Startup Test Program The licensee will follow a startup testing program, during Cycle 13 power ascension, as described in GE Licensing Topical Report NEDC-31897P-1, "Generic Guidelines for General Electric Boiling Water Reactor Power Uprate."
The startup test program includes system testing of such process control systems as the feedwater flow and main steam pressure control systems. The licensee will collect steady-state operational data during various portions of the power ascension to the higher licensed power level so that predicted equipment performance characteristics can be verified. The licensee will do the startup testing program in accordance with its procedures. The licensee's approach is in conformance with the test guidelines of GE Licensing Topical Report NEDC-31897P-1, "Generic Guidelines for General Electric Boiling Water Reactor Power Uprate," June 1991 (proprietary), GE Licensing Topical Report NEDO-31897, "Generic Guidelines for General Electric Boiling Water Reactor Power Uprate," February 1992 (nonproprietary), and NEDC-31897P-AA, Class III (proprietary), May 1992.
(3) Human Factors The licensee will review the results of the Cycle 13 startup test program to determine any potential effects on operator training. Training issues identified will be incorporated in Licensed Operator training during 1997. Simulator discrepancies identified will be addressed in accordance with simulator Configuration Management procedural requirements.
F. Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 289, are hereby incorporated into this renewed operating license. ENO shall operate the facility in accordance with the Additional Conditions.
Renewed License No. DPR-59 G. ENF and ENO shall take no action to cause Entergy Global Investments, Inc. or Entergy International Ltd. LLC, or their parent companies, to void, cancel, or modify the $70 million contingency commitment to provide funding for the facility as represented in the application for approval of the transfer of the facility license from PASNY to ENF and ENO, without the prior written consent of the Director, Office of Nuclear Reactor Regulation.
H. The decommissioning trust agreement shall provide that the use of assets in the decommissioning trust fund, in the first instance, shall be limited to the expenses related to decommissioning of the facility as defined by the NRC in its regulations and issuances, and as provided in this license and any amendments thereto I. The decommissioning trust agreement shall provide that no contribution to the decommissioning trust that consists of property other than liquid assets shall be permitted.
J. With respect to the decommissioning trust fund, investments in the securities or other obligations of the PASNY, Entergy Corporation, Entergy Nuclear IP3, LLC, ENF, ENO, or affiliates thereof, or their successors or assigns, shall be prohibited. Except for investments that replicate the composition of market indices or other non-nuclear-sector mutual funds, investments in any entity owning one or more nuclear plants is prohibited.
K. The decommissioning trust agreement shall provide that no disbursements or payments from the trust, other than for ordinary administrative expenses, shall be made by the trustee until the trustee has first given the NRC 30 days' prior written notice of the payment. In addition, the trust agreement shall state that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the Director, Office of Nuclear Reactor Regulation.
L. The decommissioning trust agreement shall provide that the trust agreement shall not be modified in any material respect without the prior written consent of the Director, Office of Nuclear Reactor Regulation.
M. ENF, or its successors or assigns shall take no action that would adversely affect any contract between it and PASNY for PASNY's eventual payment of decommissioning funds from the trust.
N. ENF, or its successors or assigns shall inform the NRC within 30 days of any adverse developments with respect to PASNY's ownership of the decommissioning trust that could reasonably be expected to lead to a significant diminution of funds available for decommissioning the facility.
O. The decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a "prudent investor" standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commission's regulations.
Renewed License No. DPR-59 P. For purposes of ensuring public health and safety, ENF, upon the transfer of this license to it, shall provide decommissioning funding assurance for the facility, to be held in a decommissioning trust fund for the facility by the prepayment or equivalent method, of no less than the amount required under NRC regulations at 10 CFR 50.75. Any amount held in any decommissioning trust maintained by PASNY for the facility after the transfer of the facility license to ENF may be credited towards the amount required under this paragraph.
Q. ENF shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for the transfer of this license to ENF and ENO and the requirements of the order approving the transfer, and consistent with the safety evaluation supporting such order.
R. Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:
(a) Fire fighting response strategy with the following elements: 1. Pre-defined coordinated fire response strategy and guidance 2. Assessment of mutual aid fire fighting assets 3. Designated staging areas for equipment and materials 4. Command and control
- 5. Training of response personnel (b) Operations to mitigate fuel damage considering the following: 1. Protection and use of personnel assets 2. Communications
- 3. Minimizing fire spread 4. Procedures for implementing integrated fire response strategy 5. Identification of readily-available pre-staged equipment 6. Training on integrated fire response strategy 7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of: 1. Water spray scrubbing 2. Dose to onsite responders S. The licensee shall implement and maintain all Actions required by Attachment 2 to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.
Renewed License No. DPR-59 T. License Renewal Commitments/Conditions - The UFSAR supplement, as revised, describes certain future activities to be completed prior to and during the period of extended operation. ENF and ENO shall complete these activities in accordance with Appendix A of NUREG-1905, Safety Evaluation Report Related to the License Renewal of James A. FitzPatrick Nuclear Power Plant, issued April 2008. ENF and ENO shall notify the NRC in writing within 10 days of completion of those activities required prior to the period of extended operation and those activities required during the period of extended operation.
U. UFSAR Supplement Changes - The UFSAR supplement, as revised, submitted pursuant to 10 CFR 54.21(d), shall be included in the next scheduled update to the UFSAR required by the 10 CFR 50.71(e)(4) following the issuance of this renewed operating license. Until that update is complete, ENF and ENO may make changes to the programs and activities described in the supplement without prior Commission approval, provided that ENF and ENO evaluate such changes pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
V. Capsule withdrawal schedule - All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of the most recent NRC-approved version of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Integrated Surveillance Program (ISP) appropriate for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation. All capsules placed in storage must be maintained for future insertion. Any changes to storage requirements must be approved by the NRC, as required by 10 CFR Part 50, Appendix H.
- 3. This renewed operating license is effective as of the date of issuance and shall expire at midnight on October 17, 2034.
FOR THE NUCLEAR REGULATORY COMMISSION
\RA\ Eric J. Leeds, Director Office of Nuclear Reactor Regulation Attachments/Appendices: 1. Appendix A - Technical Specifications 2. Appendix B - Deleted
- 3. Appendix C - Additional Conditions Date of Issuance: September 8, 2008