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| Issue date | Title | |
|---|---|---|
| RS-04-160, Request for Amendment to Technical Specifications to Eliminate Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports | 21 October 2004 | Request for Amendment to Technical Specifications to Eliminate Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports |
| 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 |
| A98020, Application for Amends to Licenses DPR-39 & DPR-48,to Eliminate License Conditions No Longer Applicable & Replace Existing Operational Custom TS with Permanently Defueled TS | 2 October 1998 | Application for Amends to Licenses DPR-39 & DPR-48,to Eliminate License Conditions No Longer Applicable & Replace Existing Operational Custom TS with Permanently Defueled TS |
| 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 |
| ML20202H364 | 28 November 1997 | Proposed Improved TSs Using Guidance Provided in NUREG-1431 |
| ML20199D625 | 10 November 1997 | Proposed Improved TS Bases Changes & Supporting Info & Final Proposed TS Bases for Section 3.3,including Revised Table of Contents & List of Effective Pages |
| A97052, Responds to NRC Re Violations Noted in Insp Repts 50-295/97-02,50-304/97-02,50-295/97-07 & 50-304/97-07, Respectively.Corrective Actions:Placed Both Units in Cold Shutdown & Removed Operators Involved in Event | 1 October 1997 | Responds to NRC Re Violations Noted in Insp Repts 50-295/97-02,50-304/97-02,50-295/97-07 & 50-304/97-07, Respectively.Corrective Actions:Placed Both Units in Cold Shutdown & Removed Operators Involved in Event |
| ML20217R244 | 2 September 1997 | Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $330,000.Violation Noted:Primary Nso Did Not Establish Power at or Less than Point of Adding Heat IAW GOP-4,step 5.21.f |
| ML20149H996 | 16 July 1997 | Predecisional Enforcement Conference Rept on 970703.Areas Discussed:Violations Noted in Insp Repts 50-295/97-02, 50-304/97-02,50-295/97-07 & 50-304/97-07 on 970206-0402 & 0312-0428 & Corrective Actions |
| ML20140G829 | 4 June 1997 | Insp Repts 50-295/97-02 & 50-304/97-02 on 970206-0402. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| ML20247E742 | 8 September 1989 | Safety Evaluation Supporting Amends 118 & 107 to Licenses DPR-39 & DPR-48,respectively |
| IR 05000295/1988016 | 9 September 1988 | Insp Repts 50-295/88-16 & 50-304/88-16 on 880720-0823.No Violations Noted.Major Areas Inspected:Operational Safety Verification & Engineered Safety Feature Sys Walkdown, Surveillance Observation & Maint Observation |
| ML20235J271 | 25 September 1987 | Forwards Info Assessing Safe Operation of PWRs When RCS Water Level Below Top of Reactor Vessel,Per Generic Ltr 87-12 |
| ML20205F589 | 19 March 1987 | Amends 102 & 92 to Licenses DPR-39 & DPR-48,respectively, Revising Tech Specs to Allow Disabling of Rod Control Sys During Periods That Reactor in Mode 3 W/Less than Four Reactor Coolant Pumps Operating |
| ML20197B123 | 16 October 1986 | Proposed Tech Specs Re RCS Limiting Conditions for Operation & Surveillance Requirements,Authorizing Disabling of Rod Control Sys When Reactor in Mode 3 W/Less than Four Reactor Coolant Pumps Operating |
| PNO-III-85-102, on 851214,during Outage,Both Trains of RHR Sys Lost When Water in Reactor Vessel Drained Below Level of Suction Line.Caused by Erroneous Control Room Indication of RCS Configuration Used for Outage | 16 December 1985 | PNO-III-85-102:on 851214,during Outage,Both Trains of RHR Sys Lost When Water in Reactor Vessel Drained Below Level of Suction Line.Caused by Erroneous Control Room Indication of RCS Configuration Used for Outage |
| NRC Generic Letter 1985-09 | 23 May 1985 | NRC Generic Letter 1985-009: Technical Specifications for Generic Letter 1983-028, Item 4.3 |
| 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 |
| NRC Generic Letter 1985-02 | 17 April 1985 | NRC Generic Letter 1985-002: Staff Recommended Actions Stemming from NRC Integrated Program for the Resolution of Unresolved Safety Issues Regarding Steam Generator Tube Integrity |
| NRC Generic Letter 1985-05 | 31 January 1985 | NRC Generic Letter 1985-005: Inadvertent Boron Dilution Events |
| ML031150585 | 29 January 1985 | Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations |