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	Issue date	Title	Topic
ML18039A787	31 January 1999	Technical Evaluation Rept on Second 10-Year Interval Inservice Insp Program Plan, for Browns Ferry Nuclear Plant,Unit 3	Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Dissimilar Metal Weld
ML20072E054	30 June 1994	Plant IPE,Front-End Review	Mission time Internal Flooding Probabilistic Risk Assessment
ML20072E122	31 March 1994	Plant Ipe,Submittal Human Reliability Analysis Final Rept	Safe Shutdown Internal Flooding Probabilistic Risk Assessment
ML20059C203	30 September 1993	High Pressure Coolant Injection (HPCI) System RISK-BASED Inspection Guide for Browns Ferry Nuclear Power Station
ML18037A417	31 July 1993	Trip Rept: On-Site Analysis of Human Factors of Event at Browns Ferry 2 on May 11, 1993, Ari/Rpt ESF Actuation Due to Shutdown Overpressurization.	Hydrostatic
ML20058L964	31 July 1993	Technical Evaluation Rept,Pump & Valve Inservice Testing Program,Browns Ferry Nuclear Plant,Units 1,2 & 3	Stroke time Squib Incorporated by reference Cold shutdown justification Power-Operated Valves Power Operated Valves
ML18037A521	31 May 1993	Technical Evaluation Rept on Second 10-Yr Interval Insp Program Plan.	Incorporated by reference Liquid penetrant
ML20072E104	20 January 1993	Plant IPE,Back-End Submittal
ML20082S010	13 August 1990	Review of Inservice Testing Program for TVA Nuclear Power Plants	Stroke time Cold shutdown justification Power Operated Valves
ML18033B395	31 December 1989	Welding-Related Employee Concerns Evaluations, Technical Rept	Non-Destructive Examination Weld Overlay
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
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
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
ML20205N943	31 October 1988	Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1
ML20196C164	4 February 1988	Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131
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
ML18040B189	31 August 1987	Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs.
ML20235M359	31 August 1987	Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept	Boric Acid
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
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
ML17347A593	31 July 1987	Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept
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
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
ML20234C112	31 May 1987	Severe Accident Sequence Analysis Program - Anticipated Transient Without Scram Simulations for Browns Ferry Nuclear Plant Unit 1	Safe Shutdown Hydrostatic Probabilistic Risk Assessment Scram Discharge Volume Fuel cladding Coast down Failure to Scram
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.
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
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
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
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
ML20206F071	8 April 1987	Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog
ML20213A034	31 March 1987	Demonstration Testing of a Surveillance Robot at Browns Ferry Nuclear Plant.Analysis of Costs and Benefits	High Radiation Area
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
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
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
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
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.
ML20214A788	28 February 1987	RAMONA-3B Calculations for Browns Ferry ATWS Study	Hydrostatic Probabilistic Risk Assessment
ML20211N503	9 January 1987	Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,HB Robinson Steam Electric Plant,Unit 2, Salem Generating Station Units 1 & 2,Shearon Harris Nuclear Power Plant Unit 1..., Technical Evaluation Rept
ML20210Q448	9 January 1987	Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Arkansas Nuclear One Unit 2,Calvert Cliffs Units 1 & 2,Fort Calhoun,Maine Yankee,Millstone Unit 2, Palisades,Palo Verde Units..., Technical Evaluation Rept
ML20210A013	31 December 1986	BWR Environ Radioactivity Survey for 1986	Grab sample Chernobyl
ML20210A005	31 December 1986	Environ Radioactivity Survey for 1986	Grab sample Chernobyl
ML20207N246	16 December 1986	Technical Assistance to Nrc,Region Iv,For Preservice Insp, Monthly Ltr Rept for Nov 1986
ML20211K510	30 November 1986	Input for Ser,Mcguire Nuclear Station Units 1 & 2,Millstone Nuclear Power Station Unit 3,Seabrook Station Units 1 & 2, VC Summer Nuclear Station,Vogtle Electric...Reactor Trip Sys Reliability,Item 4.5.2 of Generic Ltr 83-28
ML20207S523	30 November 1986	Technical Evaluation Rept for Gessar II Responses for Resolution of Humphrey Safety Concerns (Hsc) Re Mark III Containment Sys	Hydrostatic
ML20207S520	30 November 1986	Technical Evaluation Rept for River Bend Station on SER Outstanding Issue (8) - Mark III Containment Sys Issues - Humphrey Safety Concerns (Hsc)

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