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 Issue dateTitle
JAFP-21-0028, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements16 April 2021Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
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 4b30 July 2021License 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-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position27 September 2021Application 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-21-0093, Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation18 October 2021Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation
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 Primary14 January 2022Response 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-23-0014, Enclosure 1 - FSAR 2023 Redacted Version10 August 2023Enclosure 1 - FSAR 2023 Redacted Version
JAFP-88-0450, Forwards Response to NRC 880411 Request for Addl Info Re IE Bulletin 85-003.Values Inputed Into Calculation for Target Thrust Values & Treated No Differently than Any Other Thrust Requirement12 May 1988Forwards Response to NRC 880411 Request for Addl Info Re IE Bulletin 85-003.Values Inputed Into Calculation for Target Thrust Values & Treated No Differently than Any Other Thrust Requirement
JAFP-91-0292, Forwards Justification for Continued Operation Re Failure of Licensed Operator Requalification Training Program During Exams Administered Prior to Wk of 910429.List of Corrective Actions & Commitments Also Encl10 May 1991Forwards Justification for Continued Operation Re Failure of Licensed Operator Requalification Training Program During Exams Administered Prior to Wk of 910429.List of Corrective Actions & Commitments Also Encl
JAFP-94-0150, Annual Summary of Changes,Tests & Experiments for 199331 December 1993Annual Summary of Changes,Tests & Experiments for 1993
JPN-87-022, Forwards Revised Human Engineering Discrepancies Resulting from June 1986 Onsite Dcrdr Audit.Schedule for Control Room Enhancement Program Revised Due to Problems Re Mods to Install Reg Guide 1.97 Instruments & Spds/Epic Sys20 April 1987Forwards Revised Human Engineering Discrepancies Resulting from June 1986 Onsite Dcrdr Audit.Schedule for Control Room Enhancement Program Revised Due to Problems Re Mods to Install Reg Guide 1.97 Instruments & Spds/Epic Sys
JPN-87-033, Informs of Licensee Rev to Commitment to Upgrade Reactor Vessel Water Level Instrumentation Per Rev 2 to Reg Guide 1.97.Mod Schedule Unchanged.Detailed Justification for Changes to Implementation of Upgrade Encl9 June 1987Informs of Licensee Rev to Commitment to Upgrade Reactor Vessel Water Level Instrumentation Per Rev 2 to Reg Guide 1.97.Mod Schedule Unchanged.Detailed Justification for Changes to Implementation of Upgrade Encl
JPN-87-051, Comment Opposing Draft NUREG-1150, Reactor Risk Ref Document. Reduced Uncertainty in Risk Assessment Found to Be Significant W/Respect to NUREG-1150.NUREG Also Does Not Consider Value of Operator Actions.Addl Comments Encl28 September 1987Comment Opposing Draft NUREG-1150, Reactor Risk Ref Document. Reduced Uncertainty in Risk Assessment Found to Be Significant W/Respect to NUREG-1150.NUREG Also Does Not Consider Value of Operator Actions.Addl Comments Encl
JPN-88-025, Proposed Tech Specs,Changing Reactor Vessel Water Level Instrumentation Sys to Reduce Instrument Errors Resulting from post-accident Containment Heat Up & to Increase Redundancy & Reliability of Control Room Indication27 May 1988Proposed Tech Specs,Changing Reactor Vessel Water Level Instrumentation Sys to Reduce Instrument Errors Resulting from post-accident Containment Heat Up & to Increase Redundancy & Reliability of Control Room Indication
JPN-88-029, Forwards Addl Info Re Plant Dcrdr,Per NRC 880314 Request. Rept Addresses Eleven Items Listed in Section 4.0 of Technical Evaluation Rept,Including Revised Implementation Schedule for Mods10 June 1988Forwards Addl Info Re Plant Dcrdr,Per NRC 880314 Request. Rept Addresses Eleven Items Listed in Section 4.0 of Technical Evaluation Rept,Including Revised Implementation Schedule for Mods
JPN-89-020, Proposed Tech Specs Re Pertubation of Reactor Water Level Following Instrument Functional Tests24 April 1989Proposed Tech Specs Re Pertubation of Reactor Water Level Following Instrument Functional Tests
JPN-91-026, Forwards Response to SALP Rept 50-333/89-99 Covering Oct 1989 to Jan 1991,per SALP 910604 Meeting.Efforts to Upgrade Procedures to Add Human Performance Enhancements Will Continue to Address Category 2 Rating in Plant Operations21 June 1991Forwards Response to SALP Rept 50-333/89-99 Covering Oct 1989 to Jan 1991,per SALP 910604 Meeting.Efforts to Upgrade Procedures to Add Human Performance Enhancements Will Continue to Address Category 2 Rating in Plant Operations
JPN-91-031, Requests Relief from Certain Diversity Requirements for Alternate Rod Injection Sys,Based on Results of Individual Plant Exam,Per Generic Ltr 88-202 July 1991Requests Relief from Certain Diversity Requirements for Alternate Rod Injection Sys,Based on Results of Individual Plant Exam,Per Generic Ltr 88-20
JPN-92-061, Provides Response to Generic Ltr 92-04, BWR Reactor Vessel Water Level Instrumentation Issues. Licensee Making Mods to Correct Instrument Line Slopes Prior to Plant start-up as Detailed in Attachment to Ltr29 September 1992Provides Response to Generic Ltr 92-04, BWR Reactor Vessel Water Level Instrumentation Issues. Licensee Making Mods to Correct Instrument Line Slopes Prior to Plant start-up as Detailed in Attachment to Ltr
JPN-93-066, Informs That Util Will Install back-fill Mod on All Five Instrumentation Ref Legs & Complete pre-start-up Testing During 1993 Fall Maint Outage,Per NRC Bulletin 93-003 to Address NRC Concerns20 September 1993Informs That Util Will Install back-fill Mod on All Five Instrumentation Ref Legs & Complete pre-start-up Testing During 1993 Fall Maint Outage,Per NRC Bulletin 93-003 to Address NRC Concerns
JPN-94-012, Submits Updated Response to NRC Bulletin 93-003, BWR Reactor Vessel Water Level Instrumentation Issues2 March 1994Submits Updated Response to NRC Bulletin 93-003, BWR Reactor Vessel Water Level Instrumentation Issues
JPN-95-007, Application for Amend to License DPR-59,to Impose Operability & Surveillance Requirements for Rv Overfill Protection Instrumentation22 February 1995Application for Amend to License DPR-59,to Impose Operability & Surveillance Requirements for Rv Overfill Protection Instrumentation
JPN-95-020, Informs of Completion of Rc Water Level Instrumentation Mods Associated W/Bulletin 93-003 Issues28 March 1995Informs of Completion of Rc Water Level Instrumentation Mods Associated W/Bulletin 93-003 Issues
JPN-95-026, Forwards Response to NRC RAI Re Proposed EALs for Plant3 May 1995Forwards Response to NRC RAI Re Proposed EALs for Plant
ML02127000624 April 2002Part 1 of 2, James A. FitzPatrick Nuclear Power Plant - Revised Emergency Plan & Implementing Procedure/Volume 2
ML0216205043 July 2002Amendment Conversion to Improved Technical Specifications
ML02175046712 June 2002Certification of Technical Specification & Technical Specification Bases Pages (License Amendment) as Part of Conversion to Improved Standard Technical Specifications
ML02175048812 June 2002Part 1 of 3 - James A. FitzPatrick Nuclear Power Plant, Technical Specifications Bases (License Amendment) as Part of Conversion to Improved Standard Technical Specifications
ML02175050812 June 2002Part 2 of 3 - James A. FitzPatrick Nuclear Power Plant, Technical Specifications Bases (License Amendment) as Part of Conversion to Improved Standard Technical Specifications
ML0219700283 July 2002Amendment Conversion to Improved Technical Specifications (TAC No. MA5049), Attachment Table a - Administrative Changes Matrix
ML0219700713 July 2002Amendment Conversion to Improved Technical Specifications (TAC No. MA5049), Attachment 4, Table L - Less Restrictive Changes Matrix
ML0219700843 July 2002Technical Specifications, Amendment Conversion to Improved Technical Specifications (TAC No. MA5049), Table of Contents
ML0219700923 July 2002Technical Specifications, Amendment Conversion to Improved Technical Specifications (TAC No. MA5049), B. 3.4 Reactor Coolant System (RCS)
ML0219701383 July 2002Technical Specifications, Amendment Conversion to Improved Technical Specifications (TAC No. MA5049), Table of Contents
ML0219701423 July 2002Technical Specifications, Amendment Conversion to Improved Technical Specifications (TAC No. MA5049), B 3.3 Instrumentation
ML02231040129 July 2002Revised James A. Fitzpatrick Emergency Plan Implementing Procedures. Includes Emergency Plan Implementation Checklist IAP-1, Revision 27, Table of Contents - Attachment B
ML03115058529 January 1985Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations
ML03149068219 May 20034 to Emergency Plan Implementing Procedure IAP-2, Classification of Emergency Conditions.
ML03157020219 May 2003Revised Emergency Plan and Implementing Procedures
ML04072042117 February 2004Revised Emergency Plan Implementing Procedures
ML0434502448 December 2004Technical Specifications, Amendment Elimination of Requirements for Hydrogen/Oxygen Monitors
ML05140034925 January 2004Draft - RO & SRO Written Exam (Folder 2)
ML07043006517 May 2007License Amendment, Issuance of Amendment Implementation of Average Power Rate Monitor, Rod Block Monitor Technical Specification Improvements with Maximum Extended Operating Domain Analysis
ML07104001728 April 199459 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations
ML07142001930 June 2007NUREG-1437, Supp 31, Dfc Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding James A. FitzPatrick Nuclear Power Plant Draft for Comment
ML08017018331 January 2008NUREG-1437, Supplement 31, Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Regarding James A. FitzPatrick Nuclear Power Plant, Final Report.
ML0810102428 September 2008Renewed Facility Operating License No. DPR-59 / Appendix a - Technical Specifications
ML08137023228 February 2008Draft - RO & SRO Written Exam (Folder 2)
ML08137026728 February 2008Draft - Section B Operating Exam (Folder 2)
ML08137031925 March 2008Final - RO & SRO Written Examination with Answer Key (401-5 Format) (Folder 3)
ML08137044225 March 2008Final - Section B Operating Exam (Folder 3)
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