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| Issue date | Title | |
|---|---|---|
| PNP 2012-097, Report to NRC of Changes to Technical Specifications Bases | 9 November 2012 | Report to NRC of Changes to Technical Specifications Bases |
| ML091520516 | 7 July 2009 | Proposed Written Exam |
| ML082250612 | 14 August 2008 | Ro/Sro Administered Written Exam and Answer Key |
| ML080670419 | 7 March 2008 | CDBI Findings |
| ML070110053 | 10 January 2007 | Facility Operating License DPR-20, Appendix a (Technical Specifications) |
| ML052410213 | 22 August 2005 | Report of Changes to Technical Specifications Bases |
| ML051930220 | 14 July 2005 | NPP 2005 Ro/Sro Initial Written Examination |
| ML052270408 | 23 May 2005 | NRC - Proposed Written Exam for the Palisades Initial Examination - May 2005 |
| ML050560016 | 22 February 2005 | Corrected Technical Specification Pages, Amendment No. 221 |
| ML050140372 | 11 January 2005 | Technical Specifications, Elimination of Requirements for Hydrogen Recombiners and Hydrogen Monitors (MC1903) |
| ML043340195 | 22 October 2004 | Revisions to Palisades Nuclear Plant Emergency Action Levels |
| ML040420424 | 30 January 2004 | Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process |
| ML18066A650 | 17 September 1999 | Final Clean Copies of ITS & Bases Pages Incorporating Proposed Changes,Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to ITS LCOs 3.5.2,3.6.3,3.6.6, 3.7.5 & 3.7.7 & 3.7.8 |
| ML18066A647 | 17 September 1999 | Forwards Final Clean Copies of ITS & Bases Pages Which Incorporate All Changes Proposed in Listed Ltrs.Clean Copies Also Incorporate Some Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to LCOs |
| ML18066A597 | 30 July 1999 | Forwards Markup of Draft NRC SE Re Util Proposal to Convert to Its.Ltr Contains No New Commitments & No Revs to Existing Commitments |
| ML18066A501 | 11 June 1999 | Proposed Tech Specs Pages Re 980126 Submittal & Replacement Pages for Sections 3.3,3.4 & 3.9 |
| Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick | 5 May 1999 | Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick |
| ML20217A819 | 29 April 1999 | Forwards Listed Matls Related to Palisades Plant June 1999 Initial License Exam |
| NRC Generic Letter 1998-02 | 28 May 1998 | NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition |
| Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown | 5 December 1997 | Recent Events Involving Reactor Coolant System Inventory Control During Shutdown |
| Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown | 11 December 1996 | Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown |
| Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power | 22 October 1996 | Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power |
| Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
| Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown | 18 June 1996 | Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown |
| Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel | 18 January 1996 | Partial Bypass of Shutdown Cooling Flow from Reactor Vessel |
| ML18065A176 | 17 October 1995 | Proposed Tech Specs,Changing Pressurizer Cooldown Limit from 100 to 200 F/H,Adding Word Shall to TS 3.1.2c,adding Average Hourly to Column Headings in TS 3.1.2c & Removing Action 3.3.3C from Page 3-31 to 3-30 |
| ML20092G011 | 11 September 1995 | Ro:On 950801,loss of One Channel of Reactor Vessel Level Sys Occurred.Reactor Water Level Instrument LE-0101A & signal-&-power Cable Will Be Replaced During Next Refueling Outage |
| ML18064A663 | 30 March 1995 | Proposed Tech Specs for One Time Surveillance Deferment |
| ML18064A613 | 10 February 1995 | Proposed Tech Specs,Supporting One Time Deferral of Refueling Interval Surveillance Tests |
| Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 | 15 July 1994 | Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 |
| Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System | 24 May 1994 | Undetected Accumulation of Gas in Reactor Coolant System |
| ML20070C161 | 6 May 1994 | 1994 Palisades Emergency Exercise Scenario |
| ML071040017 | 28 April 1994 | 59 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations |
| ML18059A694 | 22 February 1994 | Proposed Instrumentation & Control TSs |
| Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications | 26 November 1993 | Potential Problems with BWR Level Instrumentation Backfill Modifications |
| Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels | 10 August 1993 | Thermal Stratification of Water in BWR Reactor Vessels |
| Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization | 8 April 1993 | Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization |
| ML18058B426 | 29 January 1993 | Forwards Vols 1,2 & 3 of Palisades Nuclear Plant IPE, Per Generic Ltrs 88-12 & 88-20.Rept Shows That Operation of Plant Poses No Undue Risk to Health & Safety of Public |
| NRC Generic Letter 1992-04 | 19 August 1992 | NRC Generic Letter 1992-004 - Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(F) |
| Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown | 25 February 1992 | Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown |
| ML18057B302 | 26 September 1991 | Application for Amend to License DPR-20,consisting of Rev 2 to 890628 Request,In Response to Recommendations of Generic Ltr 88-17 to Add Shutdown Cooling Sys Operability Requirements to Tech Specs |
| ML18057A888 | 1 May 1991 | Rev 1 to Application for Amend to License DPR-20,changing TS Re Shutdown Cooling Sys Per Generic Ltr 88-17,by Adding Operability Requirements for Shutdown Cooling Sys & Steam Generators |
| Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units | 23 March 1990 | Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units |
| ML18054A815 | 27 June 1989 | Forwards Info Needed for NRC to Design Emergency Response Data Sys Interface & Data Base for Facility,Per NRC 890405 Survey.Util Cannot Support Emergency Response Data Sys Program W/O Extensive Mods |
| ML18054A527 | 31 January 1989 | Forwards Response to Recommended Programmed Enhancements, Generic Ltr 88-17, Loss of Dhr. Procedures That Cover Reduced Inventory Operation & Provide Adequate Basis for Entry Into Reduced Inventory Condition Addressed |
| ML18052A623 | 1 August 1986 | Submits Addl Info Re Use of Feed & Bleed During Loss of Feedwater Event & Contents of Upgraded Emergency Operating Procedures,Per 860515 Telcon Re MSIV Single Failure Issue. Summary of Procedure Guidance Encl |
| ML20211G936 | 6 June 1986 | Summary of Operating Reactor Events Meeting 86-18 on 860602 Re Events Occurring Since 860519 Meeting.Attendee List, Events,Significant Elements of Events & Completion Dates for Assignments Encl |
| ML18052A438 | 19 May 1986 | Forwards Response to NRC 860317 Request for Addl Info Re Spds,Including Range of Displayed Neutron Flux,Reactor Vessel Level,Radiation Monitoring of Isolated Steam Generator,Per Generic Ltr 82-33 & Suppl 1 to NUREG-0737 |
| NRC Generic Letter 1985-08 | 23 May 1985 | NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format |
| NRC Generic Letter 1985-07 | 2 May 1985 | NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications |