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| Issue date | Title | |
|---|---|---|
| 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 |
| 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 |
| DD-97-21, Partial Director'S Decision DD-97-21 Denying Request for Immediate Suspension or Revocation of Licenses & Granting Request for Investigation of Possible Matl Misrepresentations,In Response to 961125 & 1223 Petitions | 12 September 1997 | Partial Director'S Decision DD-97-21 Denying Request for Immediate Suspension or Revocation of Licenses & Granting Request for Investigation of Possible Matl Misrepresentations,In Response to 961125 & 1223 Petitions |
| ML20149J337 | 21 July 1997 | Provides Update on 2.206 Petition That Recipient Submitted on 970410.Petition Requested NRC Take Actions Re Nuclear Facilities That Northeast Utilities Operates in Connecticut. Director'S Decision Expected to Be Issued Shortly |
| CY-97-059, Responds to NRC Re Violations Noted in Insp Repts 50-213/95-27,50-213/96-06,50-213/96-07,50-213/96-08, 50-213/96-11,50-213/96-80 & 50-213/96-201 on 951121-961122. Cas:Dedicated Individual Has Been Assigned as CA Manager | 11 June 1997 | Responds to NRC Re Violations Noted in Insp Repts 50-213/95-27,50-213/96-06,50-213/96-07,50-213/96-08, 50-213/96-11,50-213/96-80 & 50-213/96-201 on 951121-961122. Cas:Dedicated Individual Has Been Assigned as CA Manager |
| IR 05000213/1995027 | 12 May 1997 | Discusses Insp Repts 50-213/95-27,50-213/96-06,50-213/96-07, 50-213/96-08,50-213/96-11,50-213/96-80 & 50-213/96-201 on 951121-961122 & Forwards NOV & Proposed Imposition of Civil Penalty in Amount of $650,000 |
| ML20134B425 | 23 January 1997 | Notice of Receipt of Petition for Director'S Decision Under 10CFR2.206.Petition Requesting Certain Actions Associated W/Haddam Neck Plant Operated by Nu |
| ML20133A503 | 24 December 1996 | Insp Rept 50-213/96-11 on 960921-1115.Violations Noted. Major Areas Inspected:Plant Operations,Maint,Engineering & Plant Support |
| ML20140H548 | 19 December 1996 | Summary of 436th ACRS Meeting on 961107-09 Re Proposed Rule & Reg Guide Concerning SG Integrity.Completed Repts,Ltrs, Memos & Draft Repts Listed.Highlights of Key Issues, Considered by Committee,Submitted |
| 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 |
| ML20129H585 | 30 October 1996 | Forwards NRC AIT Insp Rept 50-213/96-80 on 960903-1002.AIT Chartered to Review Events Surrounding Inadvertent Decrease in Reactor Vessel Water Level During Plant Shutdown Conditions |
| 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 |
| ML20134B493 | 16 February 1994 | Forwards Updated Briefing Package for Visit by Util Officials W/Nrc Chairman,Commission,Edo,Director OI & Director Oe.Requests Replacement of Encls 1 & 2 in 940215 Package,Retaining Supporting Attachment 1 Documentation |
| 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 |
| B14323, Forwards Dpl for Millstone Unit 1,2,3 & Haddam Neck Plant. Dpl Lists Data Points That Will Be Transmitted for Erds. Update to ERDS Will Incorporate Changes Identified During Sys Testing Performed W/Nrc Contractor | 6 January 1993 | Forwards Dpl for Millstone Unit 1,2,3 & Haddam Neck Plant. Dpl Lists Data Points That Will Be Transmitted for Erds. Update to ERDS Will Incorporate Changes Identified During Sys Testing Performed W/Nrc Contractor |
| 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 |
| ML20248H160 | 2 October 1989 | Inservice Test Pump & Valve Program |
| B13127, Proposed Tech Specs,Revising Info on Core Exit Thermocouples,Main Stack wide-range Noble Gas Monitor, Reactor Vessel Water Level & RCS Subcooling Margin Monitor, Per Generic Ltr 83-37 | 1 March 1989 | Proposed Tech Specs,Revising Info on Core Exit Thermocouples,Main Stack wide-range Noble Gas Monitor, Reactor Vessel Water Level & RCS Subcooling Margin Monitor, Per Generic Ltr 83-37 |
| ML20235V085 | 1 March 1989 | Application for Amend to License DPR-61,revising Tech Specs Re Core Exit Thremocouples,Main Stack wide-range Noble Gas Monitor,Reactor Vessel Water Level & RCS Subcooling Margin Monitor,Per Generic Ltr 83-37 |
| A07615, Forwards Response to 881021 Request for Addl Info Re Tech Spec Changes for Generic Ltr 83-37 | 2 December 1988 | Forwards Response to 881021 Request for Addl Info Re Tech Spec Changes for Generic Ltr 83-37 |
| ML20246F835 | 30 November 1988 | Technical Evaluation Rept for Haddam Neck Plant Response to Us Nrc,Nrr Generic Ltr 83-37 |
| IR 05000213/1987099 | 4 October 1988 | SALP Rept 50-213/87-99 for Apr 1987 - Jul 1988 |
| A06214, Proposed Tech Specs,Providing Limiting Conditions for Operation Per Generic Ltr 83-37 | 1 July 1988 | Proposed Tech Specs,Providing Limiting Conditions for Operation Per Generic Ltr 83-37 |
| IR 05000213/1987021 | 10 September 1987 | Insp Rept 50-213/87-21 on 870715-0825.Violations Noted. Major Areas Inspected:Plant Operations,Outage Activities, Radiation Protection,Fire Protection,Security,Maint, Surveillance & Events Occurring During Insp Period |
| IR 05000213/1987018 | 28 July 1987 | Resident Insp Rept 50-213/87-18 on 870610-0714.No Violations Identified.Major Areas Inspected:Plant Operations,Radiation Protection,Fire Protection,Security Maint & Surveillance. Five Unresolved Items Closed |
| A05610, Responds to Generic Ltr 86-04 Re Policy Statement on Engineering Expertise on Shift.Comparison of INPO Shift Technical Advisor Guidelines W/Established Bachelors Degree Programs in Engineering Encl | 13 June 1986 | Responds to Generic Ltr 86-04 Re Policy Statement on Engineering Expertise on Shift.Comparison of INPO Shift Technical Advisor Guidelines W/Established Bachelors Degree Programs in Engineering Encl |
| A04790, Requests Extension to 860104 for Haddam Neck Re Environ Qualification of Electrical Equipment,Per Generic Ltr 85-15, 10CFR50.49(g) & Integrated Safety Assessment Program.Further Evaluation Proposed for Millstone.Fee Paid | 30 September 1985 | Requests Extension to 860104 for Haddam Neck Re Environ Qualification of Electrical Equipment,Per Generic Ltr 85-15, 10CFR50.49(g) & Integrated Safety Assessment Program.Further Evaluation Proposed for Millstone.Fee Paid |
| NRC Generic Letter 1985-08 | 23 May 1985 | NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format |
| NRC Generic Letter 1985-09 | 23 May 1985 | NRC Generic Letter 1985-009: Technical Specifications for Generic Letter 1983-028, Item 4.3 |
| B11537, Responds to 850402 Request for Addl Info Re Integrated Safety Assessment Program (Isap) Review.Description of All Plant Betterment Projects & Engineering Studies to Be Included in Isap Review Encl | 17 May 1985 | Responds to 850402 Request for Addl Info Re Integrated Safety Assessment Program (Isap) Review.Description of All Plant Betterment Projects & Engineering Studies to Be Included in Isap Review Encl |
| 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 |
| ML20204J115 | 4 October 1984 | Rev 2 to Emergency Operating Procedure EOP 3.1-48, Cavity Seal Failure |
| ML20238C367 | 31 December 1983 | Connecticut Yankee 1983 Core XI - XII Refueling Outage ALARA Rept |