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	Issue date	Title	Topic
ML20212D678	31 March 1999	Supplemental Technical Evaluation Report Based on Review of Additional Responses Concerning Individual Plant Examination of External Events at Point Beach Nuclear Plant,Units 1 & 2. Final Rept	Hot Short Safe Shutdown Fire Barrier Safe Shutdown Earthquake Earthquake
ML20212D641	31 March 1998	Technical Evaluation Report on Submittal Only Review of Individual Plant Examination of External Events at Point Beach Nuclear Plant,Units 1 & 2. Final Rept	Hot Short Safe Shutdown High winds Ultimate heat sink Mission time Fire Barrier Tornado Missile Safe Shutdown Earthquake Internal Flooding Probabilistic Risk Assessment Operating Basis Earthquake Earthquake Turbine Missile
ML20078E047	4 October 1994	TER on Front End IPE Submittal, Task 22,dtd 941004	Boric Acid Mission time Internal Flooding Probabilistic Risk Assessment
ML20078E122	30 September 1994	IPE Back-End TER Dtd Sept 1994	Mission time Internal Flooding Severe Accident Management Guideline
ML20078E150	31 August 1994	TER of IPE Submittal Human Reliability Analysis, Final Rept, Task 23.Draft Dtd 940131,final Aug 1994	Internal Flooding Probabilistic Risk Assessment
ML20141D327	31 August 1994	Dispersion Estimates in Vicinity of Buildings
ML20097A828	6 April 1992	Technical Evaluation Rept Pump & Valve Inservice Testing Program Point Beach Nuclear Power Plant,Units 1 & 2 Wepc, Per 10CFR50.55a(g)	Boric Acid Stroke time Anchor Darling Incorporated by reference Cold shutdown justification Power Operated Valves
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
ML20245E937	31 December 1988	Rev 1 to EGG-NTA-8030, TMI Action--NUREG-0737 (II.D.1) Point Beach,Units 1 & 2, Technical Evaluation Rept	Loop seal Stroke time Anticipated operational occurrence Earthquake
ML20205N943	31 October 1988	Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1
ML20155G752	14 June 1988	Review of Point Beach Nuclear Plant,Unit 1 & 2,Alternate Shutdown Capability	Safe Shutdown Fire Barrier
ML20042D053	7 June 1988	Technical Evaluation Rept of Dcrdr for Point Beach Nuclear Power Plant,Units 1 & 2.
ML20154H584	12 May 1988	App D,Evaluation of Offsite Dose Calculation Manual Rev 1 (Point Beach Nuclear Power Plant,Units 1 & 2)	Grab sample Offsite Dose Calculation Manual
ML20196C164	4 February 1988	Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131
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
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
ML20235Y659	16 October 1987	Technical Evaluation Rept for Wisconsin Electric Power Co Point Beach Nuclear Plant,Units 1 & 2 SPDS Sar
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
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
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
ML20236P640	31 July 1987	Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept
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
ML20153D767	11 May 1987	Evaluation of Fire Protection Exemption Requests from 10CFR50.48 & App R to 10CFR50, Technical Evaluation Rept	Safe Shutdown Boric Acid Fire Barrier Coatings Emergency Lighting Exemption Request Fire Protection Program
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
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.
ML20206F071	8 April 1987	Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog
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
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
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
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.
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
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
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)
ML17334B033	30 November 1986	Input for Ser,Beaver Valley Power Station Units 1 & 2, Braidwood Station Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Catawba Nuclear Station Units 1..., Reactor Trip Sys Reliability Item 4.5.2 Generic Ltr 83-28.

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