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| Issue date | Title | |
|---|---|---|
| 3F1010-04, Nine-Month Supplemental (Post-Outage) Response to NRC Generic Letter 2008-01 | 8 October 2010 | Nine-Month Supplemental (Post-Outage) Response to NRC Generic Letter 2008-01 |
| ML20212E691 | 21 September 1999 | Safety Evaluation Supporting Proposed EALs Changes for Plant Unit 3.Changes Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 |
| 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 |
| 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 |
| ML20203D161 | 20 February 1998 | Proposed Tech Specs,Providing Revs to CR-3 Improved TS Bases That Update NRC Copies of Improved TS |
| 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 |
| ML20137X536 | 18 April 1997 | Proposed Tech Specs,Providing Revs to CR-3 Improved TS Bases That Update NRC Copies of Improved TS |
| 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 |
| ML071040017 | 28 April 1994 | 59 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations |
| Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications | 26 November 1993 | Potential Problems with BWR Level Instrumentation Backfill Modifications |
| 3F1093-12, Proposed Tech Specs Reflecting Results of Numerous Meetings Re Improved TS | 15 October 1993 | Proposed Tech Specs Reflecting Results of Numerous Meetings Re Improved TS |
| 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 |
| ML20236Q166 | 16 November 1987 | Insp Rept 50-302/87-35 on 871014-16.Violations Noted:Failure to Lock,Post Barricade & Issue Radiation Work Permit to Control Access to High Radiation Area & Failure to Provide Instructions to Worker in Restricted Area |
| 3F0985-10, Forwards Supplemental Response to Violations Noted in Insp Rept 50-302/85-29.Corrective actions:short-term Instruction Issued W/Applicable Offsite Dose Calculation Manual Requirements & SP-220 Performed Satisfactorily | 12 September 1985 | Forwards Supplemental Response to Violations Noted in Insp Rept 50-302/85-29.Corrective actions:short-term Instruction Issued W/Applicable Offsite Dose Calculation Manual Requirements & SP-220 Performed Satisfactorily |
| IR 05000302/1985029 | 13 August 1985 | Insp Rept 50-302/85-29 on 850626-0726.Violation Noted: Failure to Adhere to Offsite Dose Calculation Manual & Failure to Perform Functional Test of Source Range Nuclear Instrument |
| 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 |
| 3F1184-05, Application for Amend to License DPR-72,consisting of Rev 0 to Tech Spec Change Request 125 to Consider DHR Loop in Operation During Mode 6 If Circulating Less than 27,000 Gpm. Certificate of Svc Encl.Fee Paid | 9 November 1984 | Application for Amend to License DPR-72,consisting of Rev 0 to Tech Spec Change Request 125 to Consider DHR Loop in Operation During Mode 6 If Circulating Less than 27,000 Gpm. Certificate of Svc Encl.Fee Paid |
| ML20080M908 | 16 February 1984 | Proposed Changes to Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements for DHR |
| ML19331E208 | 4 September 1980 | Forwards Evaluation of Instrumentation to Detect Inadequate Core Cooling.Responses to IE Bulletin 79-05C & NUREG-0578, Included Operator Guidelines & Evaluation of Supplemental Instrumentation.No Addl Instrumentation |
| ML20150A646 | 22 September 1978 | Forwards Tech Spec Change Request 33 to Amend Apps a & B of License DPR-72.Certificate of Svc & License Fee Encl |
| ML19308D693 | 27 July 1977 | Startup Rept |
| ML19317G403 | 3 December 1976 | App a to License DPR-72,Tech Specs,Sections 1.0-6.12 Re Definitions,Safety Limits & Limiting Safety Sys Settings, Limiting Conditions for Operation & Surveillance Requirements,Design Features & Administrative Controls |