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	Issue date	Title	Topic
ML20236U724	31 March 1998	Technical Evaluation Rept on Third 10-Year Interval ISI Program Plan:Nneco Millstone Nuclear Power Station,Unit 2, Dtd Mar 1998
ML20140G590	27 March 1997	Rev 0 to, Review of Millstone Nuclear Power Station Response to USNRC RAI of 960812 on Fire Barrier Ampacity Derating	Fire Barrier
ML20117D074	30 November 1995	Unit 2-TER on IPE Submittal Human Reliability Analysis - Final Rept	Probabilistic Risk Assessment
ML20117D080	30 November 1995	TER on IPE - Back-End Analysis	Probabilistic Risk Assessment
ML20117D068	27 November 1995	NPP TER on IPE Front End Analysis	Safe Shutdown Mission time Internal Flooding Probabilistic Risk Assessment
L-94-021, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-3	30 November 1994	Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-3
ML20126M423	31 July 1992	TER on Third 10-Yr Interval ISI Program Plan:Northeast Utils,Millstone Nuclear Power Station,Unit 1	Boric Acid Packing leak High Radiation Area Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Liquid penetrant Scaffolding
ML20071A637	31 January 1991	Trip Rept: Onsite Analysis of Human Factors of Event at Millstone 3 on 901231 (Turbine Bldg Pipe Break)	Through Wall Leak
ML20058K973	18 July 1990	Technical Evaluation Rept - Millstone Nuclear Power Station Unit 1,Station Blackout Evaluation, Final Rept
ML20063P933	18 July 1990	Technical Evaluation Rept Millstone Nuclear Power Station Unit 3 Station Blackout Evaluation, Final Rept	Safe Shutdown
ML19332B614	31 October 1989	Conformance to Generic Ltr 83-28,Item 2.2.1--Equipment Classification for All Other Safety-Related Components:Quad Cities 1 & 2, Final Technical Evaluation Rept	Safe Shutdown
ML19332B582	30 September 1989	Conformance to Reg Guide 1.97:Millstone-2, Technical Evaluation Rept	Post Accident Monitoring
ML20246B815	30 April 1989	Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Duane Arnold,Enrico Fermi-2,Hope Creek,Lasalle County 1 & 2, Limerick 1 & 2,Millstone 1,Monticello,Nine Mile Point 1 & 2 & Oyster Creek, Technical Evaluation Rept
ML20067E716	31 March 1989	First Interval ISI Program Millstone Nuclear Power Station Unit 3, Technical Evaluation Rept
ML20246B973	31 March 1989	Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept	Boric Acid
ML20236B805	13 March 1989	Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files
ML20070Q456	31 January 1989	Nuclear Power Plant Sys Sourcebook,Millstone 2	Safe Shutdown Boric Acid Ultimate heat sink Emergency Lighting Design basis earthquake
ML20070Q433	31 January 1989	Nuclear Power Plant Sys Sourcebook,Millstone 3
ML20246F835	30 November 1988	Technical Evaluation Rept for Haddam Neck Plant Response to Us Nrc,Nrr Generic Ltr 83-37	Safe Shutdown Reactor Vessel Water Level Offsite Dose Calculation Manual
ML20247M636	30 November 1988	Combustion Gas Control Cogap Analysis, Ltr Rept
ML20205N943	31 October 1988	Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1
ML20154B831	30 April 1988	Rev 1 to EGG-NTA-7895, TMI Action-NUREG-0737 (II.D.1), Technical Evaluation Rept	Loop seal Stroke time Anticipated operational occurrence Earthquake
ML20196C164	4 February 1988	Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131
ML20205N936	31 January 1988	Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Haddam Neck	Safe Shutdown
ML20205N948	31 January 1988	Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2	Safe Shutdown
ML20205N953	31 January 1988	Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3	Safe Shutdown
ML20195G527	2 October 1987	Technical Evaluation Rept:Millstone Nuclear Power Station, Unit 1,Post-Fire Shutdown Evaluation,App R	Safe Shutdown Scram Discharge Volume
ML20235V152	31 August 1987	Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Peach Bottom 2 & 3,Perry 1 & 2,Pilgrim 1,Quad Cities 1 & 2,River Bend 1, Shoreham,Susquehanna 1 & 2,Vermont Yankee & WNP-2
ML20235M359	31 August 1987	Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept	Boric Acid
ML18040B189	31 August 1987	Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs.
ML20237J062	19 August 1987	Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds	Backfit
ML20237J141	17 August 1987	Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807
ML20236P640	31 July 1987	Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept
ML20236D918	31 July 1987	Methodology and Application of Surrogate Plant PRA Analysis to the Rancho Seco Power Plant.Task 1 - Analysis of ANO-1 and Oconee PRAs	Probabilistic Risk Assessment Earthquake
ML17347A593	31 July 1987	Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept
ML18052B193	30 June 1987	Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Calvert Cliffs-1 & -2, Millstone-2 & Palisades, Final Informal Rept
ML20214Q898	30 April 1987	Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Hatch-1 & 2,Millstone-1, Final Rept
ML18150A188	30 April 1987	Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, North Anna Units 1 & 2 & Surry Units 1 & 2, Informal Rept
ML18150A119	30 April 1987	Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2, Final Informal Rept
ML18152A583	30 April 1987	Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2.
ML20214R068	30 April 1987	Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Arnold,Brunswick-1 & 2, Informal Rept
ML20214M803	22 April 1987	Draft Addendum to Review of Risk-Based Evaluation of Isap Issues for Connecticut Yankee (Haddam Neck) Plant (Addl Issues)	Safe Shutdown Probabilistic Risk Assessment Earthquake Failure to Scram
ML20206F071	8 April 1987	Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog
ML20214R216	31 March 1987	Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, Haddam Neck & Millstone 1,2 &3, Informal Rept
ML20214R743	31 March 1987	Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Arkansas Nuclear One-2,Calvert Cliffs 1 & 2,Fort Calhoun, Main Yankee,Millstone 2,Palisades,Palo Verde 1,2 & 3,San Onofre 2 & 3,St Lucie 1 & 2,Waterford 3 & WNP 3
ML20214R153	31 March 1987	Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Maine Yankee,St Lucie 1 & 2 & Waterford 3, Informal Rept
ML17334B072	31 March 1987	Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface,Cook Units 1 & 2 & Haddam Neck.
ML20214R865	31 March 1987	Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Cook-1 & -2,Haddam Neck, Final Informal Rept
ML20215G274	31 March 1987	Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface Maine Yankee,St Lucie Units 1 & 2 & Waterford 3
ML20212H371	14 January 1987	Technical Evaluation of Dcrdr for Millstone Nuclear Power Station,Unit 2

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