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	Issue date	Title	Topic
ML20195C427	6 November 1998	Safety Evaluation Supporting Proposed Ocnpp Mod to Install Core Support Plate Wedges to Structurally Replace Lateral Resistance Provided by Rim Hold Down Bolts for One Operating Cycle	Safe Shutdown Earthquake
ML20154L305	14 October 1998	Safety Evaluation Accepting Licensee Request to Defer Insp of 79 Welds from One Fuel Cycle at 17R Outage
ML20217A463	23 March 1998	Safety Evaluation Accepting Use of Three Heats/Lots of Hot Rolled XM-19 Matl in Core Shroud Repair Assemblies Re Licenses DPR-16 & DPR-59,respectively
ML20199E456	13 November 1997	Safety Evaluation Accepting Ampacity Derating Analysis in Response to NRC RAI Re GL-92-08, Thermo-Lag 330-1 Fire Barriers, for Plant	Fire Barrier
ML20149F996	18 July 1997	Safety Evaluation Re Gpu Nuclear Operational Quality Assurance Plan,Rev 10 for Three Mile Island Nuclear Generating Station,Unit 1 & Oyster Creek Nuclear Generating Station
ML20133E168	7 January 1997	Safety Evaluation Re Third 10-yr Interval ISI Plan,Rev 1 to Relief Request R11 for Plant.Proposed Alternative to ASME Requirements Authorized	Nondestructive Examination Incorporated by reference
ML20128L160	3 October 1996	Safety Evaluation Accepting Third 10-yr Interval Inservice Insp Plan Request for Relief R15	VT-2 Incorporated by reference
ML20128F479	1 October 1996	Safety Evaluation Accepting Rev to Inservice Testing Program Re Leakage Testing of Containment Isolation Valves	Incorporated by reference
ML20056H265	24 August 1993	SE Re Inservice Testing Program Requests for Relief	Stroke time Incorporated by reference Operability Determination Cold shutdown justification Power-Operated Valves Power Operated Valves
ML20056E091	4 August 1993	SE Re Util 930614 Response to Bulletin 93-03, Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in Bwrs. Util Justification for Not Implementing Addl Short Term Actions Acceptable	Reactor Vessel Water Level
ML20128P465	18 February 1993	Safety Evaluation Accepting Util Justification for Cancelling Commitment on Five Plant Control Room Human Engineering Discrepancies Re Relocation of Shift Supervisor Ofc
ML20128F136	5 February 1993	Safety Evaluation Re Leak on Core Spray in-vessel Annulus Piping.Plant Can Be Safely Operated for One Fuel Cycle W/O Repairing Observed Leak at Listed 1/4-inch Fillet Weld
ML20125C390	7 December 1992	Safety Evaluation Re Upper Reactor Bldg & Nonsafety Architectural Components Subjected to tornado-wind Loading	High winds Tornado Generated Missile
ML20127P225	23 November 1992	Safety Evaluation Accepting Response to SBO Rule
ML20058A762	18 October 1990	SE Accepting Util Insp & Repairs for Igscc,Per Generic Ltr 88-01
ML20246M756	30 August 1989	Safety Evaluation Accepting Util 890624 Response to Integrated Plant Safety Assessment Section 4.11, Seismic Design Consideration, Items 4.11(1), Piping Sys & 4.11(3), Electrical Equipment	Safe Shutdown Earthquake Operating Basis Earthquake
ML20247A706	17 July 1989	Safety Evaluation Supporting Generic Ltr 83-28,Item 4.5.2 Re Periodic on-line Testing of Reactor Trip Sys
ML20245C171	15 June 1989	Safety Evaluation Re Generic Ltr 83-28,Item 4.5.3 Re Reactor Trip Sys Reliability for All Domestic Operating Reactors
ML20244C850	12 June 1989	Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Item 4.5.3 Re on-line Testing for Reactor Trip Sys
NUREG-1000, Safety Evaluation Accepting Util 831114 & 851023 Responses to Generic Ltr 83-28,Item 2.1 (Part 1),confirming That All Applicable Components Identified as safety-related	3 April 1989	Safety Evaluation Accepting Util 831114 & 851023 Responses to Generic Ltr 83-28,Item 2.1 (Part 1),confirming That All Applicable Components Identified as safety-related
ML20235X128	6 March 1989	Safety Evaluation Supporting Licensee Request to Extend Second 10-yr Inservice Insp & Testing Interval Until 911014	Incorporated by reference Liquid penetrant
ML20205P529	4 November 1988	Safety Evaluation Supporting Util Submittal Re Compliance W/Atws Rule 10CFR50.62 Concerning Alternate Rod Injection & Recirculation Pump Trip Sys
ML20207L083	11 October 1988	Safety Evaluation Re Systematic Evaluation of Ipsar Topic VII-1.A, Isolation of Reactor Protection Sys from Non-Safety Sys. Issue Resolved
IR 05000219/1984031	4 March 1988	Safety Evaluation Concluding Util Compliance W/Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1,based on Util 831114,850809,0509,1023 & 871223 Descriptions of Planned & Completed Actions & Insp Rept 50-219/84-31 on 841126-30	Half scram
ML20149L638	18 February 1988	Safety Evaluation Supporting Proposed Standby Liquid Control Sys Operation
ML20236Q531	6 November 1987	Safety Evaluation Re Safety Limit Violation on 870911.Safety Significance Considered Low Due to Adequate Core Cooling & Low Decay Heat Levels.Basis for Conclusion Elaborated in Encl Insp Rept 50-219/87-29	Stroke time
ML20235E066	22 September 1987	Safety Evaluation Re Corrosion of Drywell Shell.Licensee Meets NRC Requirements as Specified in 861224 Safety Evaluation	Coatings
ML20207S231	13 March 1987	Safety Evaluation Re Generic Ltr 84-09 Re Hydrogen Recombiner Capability.Licensee Should Provide Nitrogen Containment Atmosphere Dilution Sys Capable of Isolating Air from Containment Whenever Isolation Signal Occurs
ML20212M356	3 March 1987	Safety Evaluation Rejecting Util Schedule for Completion of Mark I Containment Program Re Vacuum Breaker Integrity. Required Vacuum Breaker Parts Should Be Replaced Prior to Startup from Cycle 12 Refueling Outage
ML20207M208	29 December 1986	Safety Evaluation Re Corrosion of Drywell Shell Line Break in Isolation Condenser.Operation of Plant for Cycle 12 Safe W/Drywell Steel Plates Not Fully in Conformance W/Fsar.Util Shall Provide Plans for Mitigating Problem by 870630	Operating Basis Earthquake Earthquake
ML20215F368	15 December 1986	Safety Evaluation Supporting Util Response to IE Bulletin 86-002 Re Static O-Ring Differential Pressure Switches	Reactor Vessel Water Level Half scram
ML20211M391	28 November 1986	Safety Evaluation Re Deferment of NRC Required Mods from Cycle 11R Outage,Including SPDS Implementation,Isolation Condenser Makeup Pump,Intake Canal Level Instrumentation & Masonry Wall Mods.Request Acceptable	Safe Shutdown High winds Tornado Missile
ML20214A557	14 November 1986	Safety Evaluation Re Insp & Repair of Reactor Coolant Piping Sys & Supporting Return to Operation for Next Operating Cycle	Weld Overlay Liquid penetrant
ML20213G555	31 October 1986	Safety Evaluation Supporting Util 860903 Submittal Re Insp of Core Spray Sparger Sys in Current Cycle 11 Refueling Outage.Licensee Satisfied Requirements of License Condition 2.C.(7) for Current Cycle 11 Refueling Outage
NUREG-0822, Safety Evaluation Finding Integrated Plant SAR (NUREG-0822), Section 4.12 Complete W/Exception of Three Issues,Including Evaluation of Drywell for Concrete Subj to High Temps & Thermal Transients	29 October 1986	Safety Evaluation Finding Integrated Plant SAR (NUREG-0822), Section 4.12 Complete W/Exception of Three Issues,Including Evaluation of Drywell for Concrete Subj to High Temps & Thermal Transients	Earthquake
ML20197B880	10 October 1986	Safety Evaluation Supporting Util 850924 Proposal Not to Replace Existing Containment Purge & Vent Isolation Valves W/New Clow Valves
ML20215E726	1 October 1986	Safety Evaluation Supporting Cancellation of Torus Pool Temp Indication & Thermal Mixing Mods
ML20204F972	28 July 1986	Corrected Page 3 to 860522 Safety Evaluation Re Integrated Plant Safety Assessment Rept,Section 4.38, Locas. Correction Concerns Licensee Maint to Repack Four MSIVs Each Refueling Outage
ML20210K248	22 April 1986	Safety Evaluation Supporting Util 831114 Response to Generic Ltr 83-28,Item 1.2, Post-Trip Review,Data & Info Capability
ML20141D426	31 March 1986	Safety Evaluation Re Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Post-Maint Testing (Program Description & Procedure). Tech Specs Incorporating post-maint Testing of Reactor Protection Sys Components Should Be Proposed
ML20141N045	24 February 1986	Safety Evaluation Supporting Deferment of Feedwater Nozzle Insps Until Cycle 12R Outage Scheduled for 1988	Finite Element Analysis
ML20205H798	21 January 1986	Safety Evaluation Re Venting & Purging Containment During Plant Operation.Rationale Utilized for Design & Operation of Purge/Vent Sys Acceptable	Backfit
ML20136A935	23 December 1985	Safety Evaluation Accepting Licensee Response to Items 2(b) & 3 of IE Bulletin 80-11, Masonry Wall Design. Licensee 850726 Request Re Wall Mods to Be Completed During Operating Cycle 11 Not Addressed	Operating Basis Earthquake
ML20137Q762	22 November 1985	Safety Evaluation Supporting Determination That Max 150 F Drywell Temp Acceptable for Containment Safety,Drywell Steel & Concrete Structural Components & Normal Plant Operations. Tech Specs Re Limiting Factors Requested
ML20128H524	28 May 1985	Safety Evaluation Supporting Environ Qualification of Electric Equipment Important to Safety.Proposed Resolutions for Environ Qualification Deficiencies Acceptable	Safe Shutdown
ML20126K122	29 March 1981	Safety Evaluation Supporting Amend 54 to License DPR-16

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