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 Issue dateTitleTopic
05000336/LER-1982-052, Forwards LER 82-052/03L-0.Detailed Event Analysis Encl28 January 1983Forwards LER 82-052/03L-0.Detailed Event Analysis Encl
05000336/LER-1982-053, Forwards LER 82-053/03L-028 January 1983Forwards LER 82-053/03L-0
05000336/LER-1983-001, Forwards LER 83-001/04T-011 March 1983Forwards LER 83-001/04T-0
05000336/LER-1983-002, Forwards LER 83-002/03L-024 February 1983Forwards LER 83-002/03L-0
05000336/LER-1983-003, Forwards LER 83-003/03L-0.Detailed Event Analysis Encl11 March 1983Forwards LER 83-003/03L-0.Detailed Event Analysis Encl
05000336/LER-1983-004, Forwards LER 83-004/03L-011 March 1983Forwards LER 83-004/03L-0
05000336/LER-1983-005, Forwards LER 83-005/03L-031 March 1983Forwards LER 83-005/03L-0
05000336/LER-1983-006, Forwards LER 83-006/03L-021 March 1983Forwards LER 83-006/03L-0
05000336/LER-1983-008, Forwards LER 83-008/01T-031 March 1983Forwards LER 83-008/01T-0
05000336/LER-1983-009, Forwards LER 83-009/01T-08 April 1983Forwards LER 83-009/01T-0
05000336/LER-1983-010, Forwards LER 83-010/03L-0.Detailed Event Analysis Encl31 March 1983Forwards LER 83-010/03L-0.Detailed Event Analysis Encl
05000336/LER-1983-013, Forwards LER 83-013/03L-022 April 1983Forwards LER 83-013/03L-0
05000336/LER-1984-005, Confirms That Rev to LER 84-005 Will Be Submitted within 2 Months,Clarifying Performance of Type A,B & C Testing During 1983 Refueling Outage as Discussed in 860604 Meeting18 June 1986Confirms That Rev to LER 84-005 Will Be Submitted within 2 Months,Clarifying Performance of Type A,B & C Testing During 1983 Refueling Outage as Discussed in 860604 Meeting
A01143, Forwards Support Details Re Emergency Svc Water Pump Shutdown Heat Exchanger & Oil Storage Day Tank.Info Provided for NRC Review of SEP Topic III-6.Four Oversize Drawings Encl.Aperture Cards Are Avabilable in PDR16 March 1981Forwards Support Details Re Emergency Svc Water Pump Shutdown Heat Exchanger & Oil Storage Day Tank.Info Provided for NRC Review of SEP Topic III-6.Four Oversize Drawings Encl.Aperture Cards Are Avabilable in PDR
A01328, Forwards Response to SER Open Items Re NUREG-0737,Item II.B.1, Reactor Coolant Sys Vents & Insp Rept 50-336/84-0725 November 1987Forwards Response to SER Open Items Re NUREG-0737,Item II.B.1, Reactor Coolant Sys Vents & Insp Rept 50-336/84-07Hot Short
A02009, Responds to 810924 Request for Addl Info Re Inservice Testing Program.Diagrams Encl22 June 1982Responds to 810924 Request for Addl Info Re Inservice Testing Program.Diagrams Encl
A02054, Comments on NRC Draft Evaluation of SEP Topic IX-5 Re Ventilation Sys,Transmitted in NRC .Util Considers NUREG-0737,Item II.B.2 to Be of No Consequence & Resolved29 July 1982Comments on NRC Draft Evaluation of SEP Topic IX-5 Re Ventilation Sys,Transmitted in NRC .Util Considers NUREG-0737,Item II.B.2 to Be of No Consequence & Resolved
A02327, Forwards Revised Page 4 to 790625 Inservice Insp & Test Program for Pumps,Valves & Pressure Tests, in Response to NRC 820226 Request14 April 1982Forwards Revised Page 4 to 790625 Inservice Insp & Test Program for Pumps,Valves & Pressure Tests, in Response to NRC 820226 Request
A02357, Forwards Cycle 5 Refueling Outage Steam Generator Profilometry Insp Results,Per Util .Results Confirm Integrity of Steam Generator Tubes & Supports & Assure Continued Applicability of Design Basis Analyses2 June 1982Forwards Cycle 5 Refueling Outage Steam Generator Profilometry Insp Results,Per Util .Results Confirm Integrity of Steam Generator Tubes & Supports & Assure Continued Applicability of Design Basis Analyses
A02375, Forwards Supplemental Info in Response to Generic Ltr 82-05 Re Status of NUREG-0737,Items II.B.2, Plant Shielding, II.B.3, Post-Accident Sampling, II.F.1.1,II.F.1.2 & II.F.1.6, Effluent & Hydrogen Monitoring10 June 1982Forwards Supplemental Info in Response to Generic Ltr 82-05 Re Status of NUREG-0737,Items II.B.2, Plant Shielding, II.B.3, Post-Accident Sampling, II.F.1.1,II.F.1.2 & II.F.1.6, Effluent & Hydrogen Monitoring
A02399, Discusses Position Re Actuation Logic for Reactor Protection Sys & ESF Actuation Sys.Operation in 2 of 3 Logic Configuration W/One Channel in Bypass Justified.More Restrictive Tech Specs Unnecessary25 June 1984Discusses Position Re Actuation Logic for Reactor Protection Sys & ESF Actuation Sys.Operation in 2 of 3 Logic Configuration W/One Channel in Bypass Justified.More Restrictive Tech Specs UnnecessaryHigh Energy Line Break
A02414, Comments on NRC 820331 Draft Evaluation of SEP Topic III-5.B Re Pipe Break Outside Containment.Remaining Open Items Re Pipe Break in Penetration Area & Jet Impingement Will Be Addressed in 820723 Submittal28 June 1982Comments on NRC 820331 Draft Evaluation of SEP Topic III-5.B Re Pipe Break Outside Containment.Remaining Open Items Re Pipe Break in Penetration Area & Jet Impingement Will Be Addressed in 820723 Submittal
A02427, Responds to Generic Ltr 81-14 Re Seismic Qualification of Auxiliary Feedwater Sys,Per 820415 Request.Auxiliary Feedwater Sys Reanalyzed to Include Condensate Storage Tank & Heat Sink of Main Steam Sys4 June 1982Responds to Generic Ltr 81-14 Re Seismic Qualification of Auxiliary Feedwater Sys,Per 820415 Request.Auxiliary Feedwater Sys Reanalyzed to Include Condensate Storage Tank & Heat Sink of Main Steam SysDesign basis earthquake
Earthquake
A02428, Notifies That Util Plans to Complete All Major HVAC Mods by End of 1984 Refueling Outage.Required Breathing Apparatus Will Be Provided Before Startup from Reload 8 Refueling Outage,Per TMI Action Item III.D.3.419 July 1982Notifies That Util Plans to Complete All Major HVAC Mods by End of 1984 Refueling Outage.Required Breathing Apparatus Will Be Provided Before Startup from Reload 8 Refueling Outage,Per TMI Action Item III.D.3.4
A02465, Advises That Util Does Not Possess Results of GE Analysis Requested in NRC Re SEP Topic VI-7.A.4, Core Spray Nozzle Effectiveness. Issue Is Generic in Nature & Util Should Not Be Asked to Perform plant-specific Analysis29 June 1982Advises That Util Does Not Possess Results of GE Analysis Requested in NRC Re SEP Topic VI-7.A.4, Core Spray Nozzle Effectiveness. Issue Is Generic in Nature & Util Should Not Be Asked to Perform plant-specific Analysis
A02468, Comments on Draft Branch Technical Position Re Radwaste Classification10 May 1982Comments on Draft Branch Technical Position Re Radwaste Classification
A02476, Responds to NRC Re Violations Noted in IE Insp Rept 50-423/82-04.Corrective Actions:Nonconformance & Disposition Rept Issued,Support Plate Accepted as Is & Courses Rescheduled7 June 1982Responds to NRC Re Violations Noted in IE Insp Rept 50-423/82-04.Corrective Actions:Nonconformance & Disposition Rept Issued,Support Plate Accepted as Is & Courses RescheduledLiquid penetrant
A02477, Forwards Response to Generic Ltr 82-10 Requesting Info Re Implementation Dates for Selected TMI Action Plan Items in NUREG-07374 June 1982Forwards Response to Generic Ltr 82-10 Requesting Info Re Implementation Dates for Selected TMI Action Plan Items in NUREG-0737
A02497, Forwards Addl Info Supporting Exemption Request from 10CFR50,App R Fire Protection Requirements16 July 1982Forwards Addl Info Supporting Exemption Request from 10CFR50,App R Fire Protection RequirementsSafe Shutdown
Fire Barrier
Safeguards Contingency Plan
Exemption Request
Fire Watch
Grace period
A02509, Responds to 820520 Request for Addl Info Re IE Bulletin 80-04, Main Steam Line Break W/Continued Feedwater Addition. No Damage Would Be Sustained If Pumps Ran for 30 Minutes Under Calculated Conditions6 July 1982Responds to 820520 Request for Addl Info Re IE Bulletin 80-04, Main Steam Line Break W/Continued Feedwater Addition. No Damage Would Be Sustained If Pumps Ran for 30 Minutes Under Calculated Conditions
A02529, Responds to SEP Topic III-04.A Re Tornado Missiles,Per 820525 Request.Sufficient Direct Reading Indications of Vital Parameters Needed for Safe Shutdown Available in Reactor Bldg29 June 1982Responds to SEP Topic III-04.A Re Tornado Missiles,Per 820525 Request.Sufficient Direct Reading Indications of Vital Parameters Needed for Safe Shutdown Available in Reactor BldgSafe Shutdown
Tornado Missile
A02539, Responds to NRC 820611 Request for Addl Info Re Emergency Preparedness Appraisal.Table Delineating Individuals & Actions Immediately Following Event Encl28 June 1982Responds to NRC 820611 Request for Addl Info Re Emergency Preparedness Appraisal.Table Delineating Individuals & Actions Immediately Following Event Encl
A02541, Confirms Validity of Assumption That Design of Control Rod Drive Sys Precludes Operation of More than One Control Rod, Excluding Reactor Trip,In Response to Draft Evaluation of SEP Topic IV-2.W/six Aperture Cards.Aperture Cards in PDR2 August 1982Confirms Validity of Assumption That Design of Control Rod Drive Sys Precludes Operation of More than One Control Rod, Excluding Reactor Trip,In Response to Draft Evaluation of SEP Topic IV-2.W/six Aperture Cards.Aperture Cards in PDR
A02544, Provides Final Response to IE Bulletin 82-02,Action Items 2 & 4 Re Degradation of Threaded Fasteners in Rcpb,Per .No Defects Found in 20 Pressurizer Manway Closure Studs Inspected During Cycle 6 Refueling Outage8 February 1984Provides Final Response to IE Bulletin 82-02,Action Items 2 & 4 Re Degradation of Threaded Fasteners in Rcpb,Per .No Defects Found in 20 Pressurizer Manway Closure Studs Inspected During Cycle 6 Refueling Outage
A02546, Responds to NRC Re Violations Noted in IE Insp Rept 50-423/82-06.Corrective Actions:Warning Signs Posted to Prevent Physical Damage to Mechanical Snubbers.New Policy Expected Addressing Snubber Installation8 July 1982Responds to NRC Re Violations Noted in IE Insp Rept 50-423/82-06.Corrective Actions:Warning Signs Posted to Prevent Physical Damage to Mechanical Snubbers.New Policy Expected Addressing Snubber Installation
A02589, Forwards Addl Info Re safety-related ECCS Tank Outages, Provided Verbally on 821220 in Response to NUREG-0737, Item II.K.3.1729 December 1982Forwards Addl Info Re safety-related ECCS Tank Outages, Provided Verbally on 821220 in Response to NUREG-0737, Item II.K.3.17
A02608, Submits Addl Clarifications of 820301 App R Review for Facilities,In Response to NRC 820625 & 0707 Requests30 July 1982Submits Addl Clarifications of 820301 App R Review for Facilities,In Response to NRC 820625 & 0707 Requests
A02611, Informs That Documentation for Compliance w/NUREG-0737,Item II.B.3 Criterion Re post-accident Sampling Sys Will Be Provided by 82091719 July 1982Informs That Documentation for Compliance w/NUREG-0737,Item II.B.3 Criterion Re post-accident Sampling Sys Will Be Provided by 820917
A02628, Responds to NRC Re Violations Noted in IE Insp Rept 50-336/82-06.Corrective Actions:Operator Watch Established at Boric Acid Pump Discharge Valve & Temporary Changes to Applicable Procedures Approved by 8207105 August 1982Responds to NRC Re Violations Noted in IE Insp Rept 50-336/82-06.Corrective Actions:Operator Watch Established at Boric Acid Pump Discharge Valve & Temporary Changes to Applicable Procedures Approved by 820710Boric Acid
A02644, Submits Comments on SEP Phase Ii,To Assist NRC in Development of Proposed Program for Phase III30 July 1982Submits Comments on SEP Phase Ii,To Assist NRC in Development of Proposed Program for Phase III
A02724, Forwards Proprietary & Nonproprietary Responses to NRC 820819 Request for Addl Info Re Measurement Uncertainties & Shape Annealing Factor Component of Axial Shape Index.... Proprietary Response & Rept Withheld (Ref 10CFR2.790)3 May 1983Forwards Proprietary & Nonproprietary Responses to NRC 820819 Request for Addl Info Re Measurement Uncertainties & Shape Annealing Factor Component of Axial Shape Index.... Proprietary Response & Rept Withheld (Ref 10CFR2.790)Affidavit
A02757, Responds to NRC Re Violations Noted in IE Insp Rept 50-336/82-17.Corrective Actions:Tech Specs Updated, Procedures,Figures & Forms Brought Up to Current Revision & Document Distribution List Expanded1 October 1982Responds to NRC Re Violations Noted in IE Insp Rept 50-336/82-17.Corrective Actions:Tech Specs Updated, Procedures,Figures & Forms Brought Up to Current Revision & Document Distribution List Expanded
A02777, Responds to NRC Re Violations Noted in IE Insp Rept 50-336/82-16.Corrective Actions:Verification of Fail Position of Valve Emphasized & Supervisor Log Updated W/Factual Info14 October 1982Responds to NRC Re Violations Noted in IE Insp Rept 50-336/82-16.Corrective Actions:Verification of Fail Position of Valve Emphasized & Supervisor Log Updated W/Factual Info
A02865, Provides Info in Response to Request to Provide Updated Relief Request for Inservice Exam of Reactor Coolant Pump Casing Welds.Surface Exam of Accessible Casing Welds on One Pump Will Be Done at End of First Insp Interval4 May 1984Provides Info in Response to Request to Provide Updated Relief Request for Inservice Exam of Reactor Coolant Pump Casing Welds.Surface Exam of Accessible Casing Welds on One Pump Will Be Done at End of First Insp Interval
A02893, Forwards Addl Fee for Class II Changes Re Large & Small Break LOCA Evaluations,Per NRC 821118 Request6 December 1982Forwards Addl Fee for Class II Changes Re Large & Small Break LOCA Evaluations,Per NRC 821118 Request
A02959, Forwards Addendum to 860930 Summary Rept Re Crdr.Emphasizes That SPDS Regarded as Being Part of Integrated Computer Sys. Attachment 2 Addresses Open Items Documented in 870212 SER31 July 1987Forwards Addendum to 860930 Summary Rept Re Crdr.Emphasizes That SPDS Regarded as Being Part of Integrated Computer Sys. Attachment 2 Addresses Open Items Documented in 870212 SER
A03035, Forwards Response to NRC Request for Addl Info Re Operability of 6-inch Butterfly Containment Purge & Vent Valves.Based on Analyses,Adequate Justification Does Not Exist to Warrant Mods to Equipment28 March 1983Forwards Response to NRC Request for Addl Info Re Operability of 6-inch Butterfly Containment Purge & Vent Valves.Based on Analyses,Adequate Justification Does Not Exist to Warrant Mods to Equipment
A03047, Responds to NRC Re Violations Noted in IE Insp Rept 50-423/83-01.Corrective Actions:Piping Installation Spec Changed to Require Listed Obligations.Nrc Reconsideration of Violation Requested25 March 1983Responds to NRC Re Violations Noted in IE Insp Rept 50-423/83-01.Corrective Actions:Piping Installation Spec Changed to Require Listed Obligations.Nrc Reconsideration of Violation RequestedLiquid penetrant
A03049, Forwards Response to Generic Ltr 83-10C Re Plans & Schedules for Resolving NUREG-0737,Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Trip Can Be Achieved Safely & Reliably by Operator,When Required22 April 1983Forwards Response to Generic Ltr 83-10C Re Plans & Schedules for Resolving NUREG-0737,Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Trip Can Be Achieved Safely & Reliably by Operator,When RequiredFuel cladding
A03074, Forwards Program Description & Schedule for Resolving NUREG-0737,Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Program Completion Scheduled for End of 1983.Results of Analysis & Training Dates Will Be Communicated by 8312311 July 1983Forwards Program Description & Schedule for Resolving NUREG-0737,Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Program Completion Scheduled for End of 1983.Results of Analysis & Training Dates Will Be Communicated by 831231Anticipated operational occurrence
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