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| Issue date | Title | From | To | |
|---|---|---|---|---|
| IR 05000333/1988001 | 25 March 1988 | Insp Rept 50-333/88-01 on 870112-880312.Violation Noted. Major Areas Inspected:Ler Review,Operational Safety Verification,Surveillance & Maint Observations,Esf Sys Walkdown,Licensee Reorganization & Fitness for Duty Policy | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) Jerrica Johnson | |
| NRC Generic Letter 1988-07 | 7 April 1988 | NRC Generic Letter 1988-007: Modified Enforcement Policy Relating to 10 CFR 50.49 Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants. | Miraglia F Office of Nuclear Reactor Regulation | |
| JPN-88-041, Responds to Generic Ltr 88-01 Re NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.Includes Insp Plans & Mitigation Plans.Separate Submittals Will Address Resistance Heat Stress Improvement & Change to Tech Specs | 16 August 1988 | Responds to Generic Ltr 88-01 Re NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.Includes Insp Plans & Mitigation Plans.Separate Submittals Will Address Resistance Heat Stress Improvement & Change to Tech Specs | Power Authority of the State of New York John Brons | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| JPN-88-043, Forwards Info in Support of Util 880816 Response to Generic Ltr 88-01 Re IGSCC Program at Plant,Including Rev 1 to SIR-87-015, Welds II Residual Stress Analysis of Resistance Heating Stress Improvement Welded Pipes | 19 August 1988 | Forwards Info in Support of Util 880816 Response to Generic Ltr 88-01 Re IGSCC Program at Plant,Including Rev 1 to SIR-87-015, Welds II Residual Stress Analysis of Resistance Heating Stress Improvement Welded Pipes | Power Authority of the State of New York John Brons | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| IR 05000333/1988026 | 19 October 1988 | Insp Rept 50-333/88-26 on 880926-1007.No Violations Noted. Major Areas Inspected:Licensee Inservice Insp (ISI) Activities to Ascertain That ISI Activities Conducted in Accordance W/Applicable ASME Code & Regulatory Requirements | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) Strosnider J Mcbrearty R | |
| JPN-88-062, Forwards Addendum to Summary of IGSCC Insps During Reload 8/Cycle 9 Outage & Weld Overlay Design Info,Per Generic Ltr 88-01 | 10 November 1988 | Forwards Addendum to Summary of IGSCC Insps During Reload 8/Cycle 9 Outage & Weld Overlay Design Info,Per Generic Ltr 88-01 | Power Authority of the State of New York John Brons | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| ML20206H877 | 18 November 1988 | Concludes That Plant Can Be Safely Returned to Operation for at Least One Addl Fuel Cycle Based on Review of Info Provided in Util 881021 & 1110 Ltrs Re IGSCC Insps.Insps That Were Performed Meet Guidelines of Generic Ltr 88-01 | Office of Nuclear Reactor Regulation Capra R | Power Authority of the State of New York John Brons |
| IR 05000333/1988027 | 1 December 1988 | Insp Rept 50-333/88-27 on 881031-1104.No Violations Noted. Major Areas Inspected:Exam of IGSCC Conducted During 1988 Outage & Repair of in-vessel Core Spray Pipe Crack | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) Strosnider J Mcbrearty R | |
| ML20236A173 | 8 March 1989 | Forwards Request for Addl Info Re Util 880810 Response to Generic Ltr 88-01,within 60 Days of Ltr Receipt | Office of Nuclear Reactor Regulation Labarge D | Power Authority of the State of New York John Brons |
| JPN-89-012, Forwards Addl Info Re IGSCC Insps During Reload 8/Cycle 9 Operation.Crack Depth Noted by IGSCC Inspectors Determined to Be Extremely Conservative W/Respect to Crack Depth Sizing | 24 March 1989 | Forwards Addl Info Re IGSCC Insps During Reload 8/Cycle 9 Operation.Crack Depth Noted by IGSCC Inspectors Determined to Be Extremely Conservative W/Respect to Crack Depth Sizing | Power Authority of the State of New York John Brons | Office of Information Resources Management |
| JPN-89-053, Responds to Requesting Addl Info Re Generic Ltr 88-01.Util Pursuing Aggressive IGSCC Detection/Mitigation Program Which Includes Comprehensive Insps of Susceptible Welds Performed Per Generic Ltr.W/Seven Oversize Drawings | 26 July 1989 | Responds to Requesting Addl Info Re Generic Ltr 88-01.Util Pursuing Aggressive IGSCC Detection/Mitigation Program Which Includes Comprehensive Insps of Susceptible Welds Performed Per Generic Ltr.W/Seven Oversize Drawings | Power Authority of the State of New York John Brons | Office of Information Resources Management |
| JPN-89-063, Discusses Fall 1989 Maint Outage IGSCC Insps.Flaw Depths for Welds 28-33 & 28-112 Predicted to Remain Below Section XI Allowable Flaw Depths Until at Least End of Next Operating Cycle (Cycle 11) | 29 September 1989 | Discusses Fall 1989 Maint Outage IGSCC Insps.Flaw Depths for Welds 28-33 & 28-112 Predicted to Remain Below Section XI Allowable Flaw Depths Until at Least End of Next Operating Cycle (Cycle 11) | Power Authority of the State of New York John Brons | Office of Information Resources Management |
| NRC Generic Letter 1989-21 | 19 October 1989 | NRC Generic Letter 1989-021: Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements | Partlow J Office of Nuclear Reactor Regulation | |
| ML19332C921 | 17 November 1989 | Forwards Response to Generic Ltr 89-21 Re Implementation Status of USI Requirements | Power Authority of the State of New York John Brons | Office of Information Resources Management |
| ML20006C381 | 29 January 1990 | Forwards Preoutage IGSCC Insp Plan for Upcoming 1990 Refueling Outage.Util Will Not Routinely Submit Preoutage Plans in Future Per Generic Ltr 88-01 & NUREG-0313 | Power Authority of the State of New York John Brons | Office of Information Resources Management |
| ML20012A020 | 28 February 1990 | Forwards Response to NRC SALP Initial Rept 50-333/88-99 for May 1988 - Sept 1989.Emergency Operating Procedures Being Upgraded to Rev 4 of Emergency Procedures Guidelines & Will Be in Place Upon Startup from Spring Refueling Outage | Power Authority of the State of New York John Brons | Office of Information Resources Management |
| NRC Generic Letter 1990-04 | 25 April 1990 | NRC Generic Letter 1990-004: Request for Information on Status of Licensee Implementation of Generic Safety Issues Resolved with Imposition of Requirements or Corrective Actions | Partlow J Office of Nuclear Reactor Regulation | |
| ML20043G921 | 25 May 1990 | Forwards Summary of IGSCC Insp During 1990 Refueling Outage. All Weld Overlays Installed in Accordance w/NUREG-0313,Rev 2 Except One Which Was Slightly Undersized.Shrinkage Stress Evaluations Will Be Submitted 6 Wks After Startup | Power Authority of the State of New York John Brons | Office of Information Resources Management |
| NRC Generic Letter 1990-05 | 15 June 1990 | NRC Generic Letter 1990-005: Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping | Partlow J Office of Nuclear Reactor Regulation | |
| ML20056A939 | 2 August 1990 | Insp Rept 50-333/90-04 on 900527-0630.No Violations Noted. Major Areas Inspected:Plant Activities During Day & Backshift Hrs Including:Plant Operations,Radiological Protection,Surveillance & Maint & Security | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) Meyer G | |
| JPN-91-012, Forwards Application for Amend to License DPR-59,changing Tech Specs Re Inservice Insp Program,Per Generic Ltr 88-01 | 15 April 1991 | Forwards Application for Amend to License DPR-59,changing Tech Specs Re Inservice Insp Program,Per Generic Ltr 88-01 | Power Authority of the State of New York Ralph Beedle | Office of Information Resources Management |
| ML20084U604 | 15 April 1991 | Proposed Tech Spec Changes Re Inservice Insp Program,Per Generic Ltr 88-01 | Power Authority of the State of New York | |
| ML20084U603 | 15 April 1991 | Application for Amend to License DPR-59,changing Tech Specs Re Inservice Insp Program,Per Generic Ltr 88-01 | Power Authority of the State of New York Ralph Beedle | |
| JPN-91-028, Requests Exemption from Schedular Requirements of 10CFR50.71(e)(4) for Submittal of Periodic Update to FSAR & Also Seeks Exemption from Schedular Requirements of 10CFR50.54(a)(3) for Annual Submittal of Revs to QA Program | 28 June 1991 | Requests Exemption from Schedular Requirements of 10CFR50.71(e)(4) for Submittal of Periodic Update to FSAR & Also Seeks Exemption from Schedular Requirements of 10CFR50.54(a)(3) for Annual Submittal of Revs to QA Program | Power Authority of the State of New York Ralph Beedle | Office of Information Resources Management |
| ML20217C844 | 11 July 1991 | Discusses Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping & Concludes That Response Acceptable W/O Exception | Office of Nuclear Reactor Regulation Mccabe B | Power Authority of the State of New York Ralph Beedle |
| JPN-91-039, Responds to Request for Addl Info Re Generic Ltr 89-10, Suppl 3, Consideration of Results of NRC-Sponsored Tests of Motor-Operated Valves, Per | 1 August 1991 | Responds to Request for Addl Info Re Generic Ltr 89-10, Suppl 3, Consideration of Results of NRC-Sponsored Tests of Motor-Operated Valves, Per | Power Authority of the State of New York Ralph Beedle | Office of Information Resources Management |
| JAFP-92-0470, Ja Fitzpatrick Nuclear Power Plant Annual Summary of Changes,Tests & Experiments for 1990 | 18 June 1992 | Ja Fitzpatrick Nuclear Power Plant Annual Summary of Changes,Tests & Experiments for 1990 | Power Authority of the State of New York Harry Salmon | Office of Information Resources Management |
| ML20126H221 | 29 December 1992 | Discusses Licensee Plans to Restart Plant on 930111 After Shut Down of Plant on 911127 to Resolve Design Deficiency in Core Spray Sys Containment Isolation Logic.Concludes That Sufficient Progress Made to Support Safe Plant Operation | Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) | Power Authority of the State of New York Ralph Beedle |
| ML20072K717 | 22 August 1994 | Probabilistic Risk Assessment of Effects of Postulated Events w/360 Degree Shroud Through-Wall Crack | Power Authority of the State of New York | |
| JPN-94-043, Provides Response to GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs. Plant Specific Safety Analysis Supporting Continued Operation Until 1994 Refuel Outage & Engineering Rept JAF-RPT-MISC-01788 Encl | 24 August 1994 | Provides Response to GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs. Plant Specific Safety Analysis Supporting Continued Operation Until 1994 Refuel Outage & Engineering Rept JAF-RPT-MISC-01788 Encl | Power Authority of the State of New York Josiger W | Office of Information Resources Management |
| ML20085L519 | 15 June 1995 | ISI Summary Rept for 1995 Refuel Outage | Power Authority of the State of New York | |
| ML20136B705 | 4 March 1997 | Inservice Insp Summary Rept for Refueling Outage R012 at Jafnpp | Power Authority of the State of New York | |
| ML20149G246 | 7 July 1997 | Rev 1 to ISI Summary Rept for Refueling Outage RO12 at Jafnpp | Power Authority of the State of New York | |
| ML20199G566 | 6 January 1998 | Rev 0 to JAF-ISI-0002, Third ISI Interval,Isi Program. W/28 Oversize Drawings | Power Authority of the State of New York Anderson E Penny R Alexandra Smith | |
| ML20199G592 | 7 January 1998 | Rev 0 to JAF-ISI-0003, Third ISI Interval,Ten-Yr ISI Plan | Power Authority of the State of New York Anderson E Penny R Alexandra Smith | |
| ML20212J054 | 17 June 1999 | Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First | NRC (Affiliation Not Assigned) Strosnider J | Terry C Niagara Mohawk |
| JPN-99-020, Submits Response to RAI Re ISI Program Relief Requests for Second 10-yr Interval Closeout & Summary Rept,Per 990426 Telcon with Nrc.Info Provided to Clarify or Withdraw Individual Relief Requests Contained in Summary Rept | 21 June 1999 | Submits Response to RAI Re ISI Program Relief Requests for Second 10-yr Interval Closeout & Summary Rept,Per 990426 Telcon with Nrc.Info Provided to Clarify or Withdraw Individual Relief Requests Contained in Summary Rept | Power Authority of the State of New York James Knubel | Office of Information Resources Management |
| ML20217D996 | 13 October 1999 | Risk-Informed ISI Program Plan for Ja Fitzpatrick | Power Authority of the State of New York | |
| JAFP-02-0098, Part 7 of 7, James A. FitzPatrick Nuclear Power Plant - Revision J to Proposed Technical Specification Change (License Amendment) Conversion to Improved Standard Technical Specifications, Bases | 26 April 2002 | Part 7 of 7, James A. FitzPatrick Nuclear Power Plant - Revision J to Proposed Technical Specification Change (License Amendment) Conversion to Improved Standard Technical Specifications, Bases | Entergy Ted Sullivan | Office of Nuclear Reactor Regulation Document Control Desk |
| JPN-02-011, Request for Relief RR-29, Third 10-Year Inservice Inspection Interval Program Plan | 8 May 2002 | Request for Relief RR-29, Third 10-Year Inservice Inspection Interval Program Plan | Entergy Kansler M | Office of Nuclear Reactor Regulation Document Control Desk |
| ML021750508 | 12 June 2002 | Part 2 of 3 - James A. FitzPatrick Nuclear Power Plant, Technical Specifications Bases (License Amendment) as Part of Conversion to Improved Standard Technical Specifications | Entergy | Office of Nuclear Reactor Regulation Document Control Desk |
| ML021970092 | 3 July 2002 | Technical Specifications, Amendment Conversion to Improved Technical Specifications (TAC No. MA5049), B. 3.4 Reactor Coolant System (RCS) | Vissing G NRC/NRR/DLPM/LPD1 | Entergy Kansler M |
| ML021990299 | 7 August 2002 | Request for Relief No. RR-29 from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Requirements | Richard Laufer NRC/NRR/DLPM/LPD1 | Entergy Kansler M |
| ML062160553 | 31 July 2006 | James A. Fitzpatrick License Renewal Application, Appendix a, Update Final Safety Analysis Report Supplement | Entergy Peter Dietrich | Office of Nuclear Reactor Regulation Document Control Desk |
| ML062160556 | 31 July 2006 | James A. Fitzpatrick License Renewal Application, Appendix B Through Appendix D | Entergy Peter Dietrich | Office of Nuclear Reactor Regulation Document Control Desk |
| ML063400415 | 4 December 2006 | (PA-LR) AMP Audit Request and Response Items 50 - 417 | Office of Nuclear Reactor Regulation | |
| ML070380389 | 6 February 2007 | JAFNPP AMP and AMR Database | Office of Nuclear Reactor Regulation | |
| JAFP-07-0030, Fourth Inservice Inspection Interval Inspection Program Plan | 27 February 2007 | Fourth Inservice Inspection Interval Inspection Program Plan | Entergy Peter Dietrich | Office of Nuclear Reactor Regulation Document Control Desk |
| JAFP-07-0019, License Renewal Application, Amendment 9 | 6 April 2007 | License Renewal Application, Amendment 9 | Entergy Peter Dietrich | NRC/NRR/ADRO Document Control Desk |
| JAFP-06-0109, License Renewal Application, Amendment 10, RAI Responses | 24 April 2007 | License Renewal Application, Amendment 10, RAI Responses | Entergy Peter Dietrich | NRC/NRR/ADRO Document Control Desk |