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 Issue dateTitle
HL-1122, Application for Amends to Licenses DPR-57 & NPF-5,changing Tech Specs Re Protective Instrumentation21 September 1990Application for Amends to Licenses DPR-57 & NPF-5,changing Tech Specs Re Protective Instrumentation
HL-1453, Application for Amends to Licenses DPR-57 & NPF-5,modifying Instrumentation SRs by Adding Action Statements Which Allow Instruments Channels to Be Inoperable for Required Surveillance Testing W/O More Restrictive Actions4 February 1992Application for Amends to Licenses DPR-57 & NPF-5,modifying Instrumentation SRs by Adding Action Statements Which Allow Instruments Channels to Be Inoperable for Required Surveillance Testing W/O More Restrictive Actions
HL-2104, Forwards Data Point Library & Plant Attribute Library,Per Rev 1 to NUREG-1394 as Part of Emergency Response Data Sys11 March 1992Forwards Data Point Library & Plant Attribute Library,Per Rev 1 to NUREG-1394 as Part of Emergency Response Data Sys
HL-2376, Forwards Response to NRC 920708 Meeting Request to Provide Addl Info Re Resolution of Human Engineering Discrepancies, Specifically,Differences in Annunicator Arrangements Between Units 1 & 2 & History of Dcrdr Project16 September 1992Forwards Response to NRC 920708 Meeting Request to Provide Addl Info Re Resolution of Human Engineering Discrepancies, Specifically,Differences in Annunicator Arrangements Between Units 1 & 2 & History of Dcrdr Project
HL-2923, Forwards Response to GL 92-04, Resolution of Issues Re Reactor Vessel Water Level Instrumentation in BWRs Per 10CFR50.54(f). Walkdown Performed on Instrument Panels & Ref Leg Tubing.No Visible Leakage Indentified25 September 1992Forwards Response to GL 92-04, Resolution of Issues Re Reactor Vessel Water Level Instrumentation in BWRs Per 10CFR50.54(f). Walkdown Performed on Instrument Panels & Ref Leg Tubing.No Visible Leakage Indentified
HL-2979, Suppls 920204 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Reflect Change in Various Instrumentation Sr,Per Discussions W/Nrc21 December 1992Suppls 920204 Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Reflect Change in Various Instrumentation Sr,Per Discussions W/Nrc
HL-4455, Informs of Completion of Actions Per NRC Bulletin 93-003, Resolution of Issues Rv Water Level Instrumentation in Bwrs, Re Commitment to Install Keepfill Sys on Each Affected Water Level Instrument Reference Legs on Each Unit6 December 1993Informs of Completion of Actions Per NRC Bulletin 93-003, Resolution of Issues Rv Water Level Instrumentation in Bwrs, Re Commitment to Install Keepfill Sys on Each Affected Water Level Instrument Reference Legs on Each Unit
HL-4495, Application for Amends to Licenses DPR-57 & DPR-5 Revising Units 1 & 2 TS to Be Consistent w/NUREG-1433 Standard TS GE Plants,BWR/425 February 1994Application for Amends to Licenses DPR-57 & DPR-5 Revising Units 1 & 2 TS to Be Consistent w/NUREG-1433 Standard TS GE Plants,BWR/4
HL-4637, Forwards Response to Violations Noted in Insp Rept 50-366/94-11.Corrective Actions:Insulation on Safety Relief Valves Installed According to Design Drawing on 9404218 July 1994Forwards Response to Violations Noted in Insp Rept 50-366/94-11.Corrective Actions:Insulation on Safety Relief Valves Installed According to Design Drawing on 940421
HL-4740, Advises of Completion of Actions Re NRC Bulletin 93-003, Resolution of Issues Re Reactor Vessel Water Level Instrumentation in Bwrs14 November 1994Advises of Completion of Actions Re NRC Bulletin 93-003, Resolution of Issues Re Reactor Vessel Water Level Instrumentation in Bwrs
HL-4789, Application for Amend to License NPF-5 Re Elimination of Selected Response Time Testing Requirements from TS14 April 1995Application for Amend to License NPF-5 Re Elimination of Selected Response Time Testing Requirements from TS
HL-4794, Forwards Response to NRC 950213 RAI Re Scope of GL 89-10 for Plant14 March 1995Forwards Response to NRC 950213 RAI Re Scope of GL 89-10 for Plant
HL-4812, Forwards Response to NRC 950310 RAI Re Util 950113 Power Uprate Submittal.Info Relative to Plant Setpoint Methodology & Calculations Also Encl5 April 1995Forwards Response to NRC 950310 RAI Re Util 950113 Power Uprate Submittal.Info Relative to Plant Setpoint Methodology & Calculations Also Encl
HL-5115, Ei Hatch Nuclear Plant - Units 1 & 2 Annual Operating Rept 199531 December 1995Ei Hatch Nuclear Plant - Units 1 & 2 Annual Operating Rept 1995
HL-5212, Special Rept:On 960721,flood-up Range Reactor Vessel Water Level Instrument 1B21-R605 Out of Svc for Greater than 30 Days.Caused by Packing Leak on Equalizing Valve.Packing Leak on Equalizing Valve Repaired30 July 1996Special Rept:On 960721,flood-up Range Reactor Vessel Water Level Instrument 1B21-R605 Out of Svc for Greater than 30 Days.Caused by Packing Leak on Equalizing Valve.Packing Leak on Equalizing Valve Repaired
IA-85-771, Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities3 January 1986Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities
IR 05000321/198604224 March 1987SALP Repts 50-321/86-42 & 50-366/86-42 for Jul 1985 - Dec 1986
IR 05000321/198700822 May 1987Insp Repts 50-321/87-08 & 50-366/87-08 on 870328-0424.No Violations Noted.Major Areas Inspected:Licensee Action on Previous Enforcement Matters,Operational Safety Verification,Maint & Surveillance Observations & ROs
IR 05000321/198800711 April 1988Insp Repts 50-321/88-07 & 50-366/88-07 on 880220-0325. Violations Noted.Major Areas Inspected:Licensee Action on Previous Enforcement Matters,Operational Safety Verification,Radiological Protection & Physical Security
IR 05000321/198801516 June 1988Insp Repts 50-321/88-15 & 50-366/88-15 on 880509-20. Violations Noted.Major Areas Inspected:Operational Performance Assessment Re Effectiveness of Various Plant Groups Including,Operations,Qa & Engineering & Training
IR 05000321/198802912 October 1988Insp Repts 50-321/88-29 & 50-366/88-29 on 880820-0923.No Violations or Deviations Noted.Major Areas Inspected: Operational Safety Verification,Maint Observations & Surveillance Testing Observations & Physical Security
IR 05000321/198901620 September 1989Insp Repts 50-321/89-16 & 50-366/89-16 on 890722-0825. Violations Noted Re Surveillance Tracking Software Deficiency Resulting in Deactivation of Task.Major Areas Inspected:Operational Safety Verification & Maint
IR 05000321/199001412 July 1990Insp Repts 50-321/90-14 & 50-366/90-14 on 900512-0622.No Specific Strengths or Weaknesses of Licensee Programs Noted. Major Areas Inspected:Operational Safety Verification,Maint Observation,Surveillance Testing Observation & Events
IR 05000321/19900165 November 1990Insp Repts 50-321/90-16 & 50-366/90-16 on 901001-12.No Violations or Deviations Noted.Major Areas Inspected: Verification of Corrective Actions for Previous Findings in Areas of EOPs
IR 05000321/199203222 December 1992Insp Repts 50-321/92-32 & 50-366/92-32 on 921108-1205. Violations Noted But Not Cited.Major Areas Inspected: Operations,Surveillance Testing,Including Standby Liquid Control Sys Testing,Maint Activities & Control of Overtime
IR 05000321/199301722 September 1993Insp Repts 50-321/93-17 & 50-366/93-17 on 930808-0904.No Violations or Deviations Noted.Major Areas Inspected: Operations,Surveillance Testing,Maint Activities,Rv Water Level Instrumentation Mods & Review of Open Items
IR 05000321/199330019 March 1993Exam Rept 50-321/93-300 on 930218-25.Exam Results:Seven Senior Reactor Operators Passed Initial Exam & One Senior Reactor Operator Passed Requalification Retake Exam.No Violations or Deviations Noted
Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units23 March 1990Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units
Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown25 February 1992Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization8 April 1993Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels10 August 1993Thermal Stratification of Water in BWR Reactor Vessels
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications26 November 1993Potential Problems with BWR Level Instrumentation Backfill Modifications
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System24 May 1994Undetected Accumulation of Gas in Reactor Coolant System
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 115 July 1994Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel18 January 1996Partial Bypass of Shutdown Cooling Flow from Reactor Vessel
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown18 June 1996Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves5 August 1996Unexpected Opening of Multiple Safety Relief Valves
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power22 October 1996Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power
Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown11 December 1996Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown
Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown5 December 1997Recent Events Involving Reactor Coolant System Inventory Control During Shutdown
Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick5 May 1999Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick
L-85-044, Forwards Response to NRC Questions Re Proposed Tech Spec Changes for GE Analog Transmitter Trip Sys9 December 1985Forwards Response to NRC Questions Re Proposed Tech Spec Changes for GE Analog Transmitter Trip Sys
ML01299036221 July 1995Issuance of Amendments Nos. 196 and 136, Revising TS to Lower Anticipated Transient Without Scramrecirculation Pump Trip Setpoint by Approximately 2 Feet 2 Inches
ML0130604123 March 1995Part 1- Edwin I. Hatch, Units 1 & 2, License Amendments, Replace Current Technical Specification & Associated Bases
ML02093009227 March 2002Response to Request for Additional to Information Relative to Request to Revise Technical Specifications, 18-to 24-Month Fuel Cycle Extension
ML02093042228 March 2002Part 1 of 2, Edwin I. Hatch Nuclear Plant, Units 1 & 2, Technical Specifications
ML0210204305 April 2002Issuance of Amendment (Tac No. MB3756)
ML02137035817 May 2002License Amendment Revises Technical Specifications to Eliminate the Response Time Testing Requirements for the Reactor Protection System Signals of Reactor High Steam Dome Pressure and Reactor Vessel Water Level Low
ML02141028817 May 2002Tech Spec Pages for Amendment 173 Regarding Technical Specifications to Eliminate the Response Time Testing Requirements for the Reactor Protection System Signals of Reach High Steam Dome Pressure and Reactor Vessel Water Level Low
ML02203045512 July 2002Tech Spec Pages, Amendment No. 174 Dated July 12, 2002
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