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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20203K412 | 28 February 1998 | H. B. ROBINSON-2 Pressure Vessel Benchmark | Power change |
| ML20203F021 | 26 November 1997 | Technical Evaluation Rept for Calvert Cliffs Nuclear Power Plant,Units 1 & 2,Baltimore Gas & Electric Co, Third 10-Yr Interval Pump & Valve Inservice Testing Program | Safe Shutdown Boric Acid Cold shutdown justification |
| ML20135F949 | 28 February 1997 | Experiments to Investigate Direct Containment Heating Phenomena with Scaled Models of the Calvert Cliffs Nuclear Power Plant | Grab sample Finite Element Analysis |
| ML20106J148 | 31 January 1996 | Technical Evaluation Rept of Calvert Cliffs Individual Plant Exam Back-End Submittal, Final Rept | Internal Flooding Probabilistic Risk Assessment Severe Accident Management Guideline |
| ML20106J138 | 16 January 1996 | Technical Evaluation Rept on IPE Front End Analysis | Shutdown Margin Mission time Internal Flooding Probabilistic Risk Assessment |
| ML20107F945 | 10 January 1996 | TER on IPE Submittal Human Reliability Analysis Final Rept | Internal Flooding |
| ML20062J274 | 31 August 1993 | Technical Evaulation Rept, Evaluation of B&Wog Pressurizer Surge Line Thermal Stratification Program to Address NRC Bulletin 88-11 | |
| ML20091J095 | 20 December 1991 | Final Technical Evaluation Rept - Oconee Nuclear Station, Station Blackout Evaluation | Safe Shutdown |
| ML20072P671 | 24 April 1990 | Second Interval Inservice Insp Program Oconee Nuclear Station Units 1,2 & 3, Technical Evaluation Rept | Hydrostatic VT-2 Incorporated by reference Liquid penetrant Dissimilar Metal Weld |
| 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 |
| ML20006D679 | 31 July 1989 | Second 10-Yr Interval Inservice Insp Program:Bg&E,Calvert Cliffs Nuclear Power Plant,Units 1 & 2, Technical Evaluation Rept | Hydrostatic Temporary Modification VT-2 Incorporated by reference |
| ML20246A359 | 30 June 1989 | PRA Applications Program for Inspection at Calvert Cliffs Unit 1 Nuclear Power Plant | Boric Acid Probabilistic Risk Assessment |
| 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 | |
| ML20245E927 | 31 August 1988 | Technical Evaluation Rept,Tmi Action--NUREG-0737 (II.D.1) Relief & Safety Valve Testing, Oconee Units 1,2 & 3 | Loop seal Anticipated operational occurrence |
| 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 |
| ML20236E225 | 31 October 1987 | PRA Application Program for Inspection at Oconee Unit 3 | Internal Flooding Probabilistic Risk Assessment Earthquake |
| ML18040B189 | 31 August 1987 | Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. | |
| ML20235X530 | 31 August 1987 | Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface Oconee 1,2 & 3 | |
| 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 |
| 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 | |
| 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 | |
| ML20235P082 | 8 July 1987 | Technical Evaluation of Bg&E Topical Rept:Retran Computer Code Reactor Transient Analysis Model Qualification | |
| 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 | |
| ML20215M051 | 31 May 1987 | Conformance to Generic Ltr 83-28,Item 2.2.1, 'Equipment Classification for All Other Safety-Related Components,' Calvert Cliffs Units 1 & 2, Informal Technical Evaluation Rept | Safe Shutdown |
| 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 | |
| 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 | |
| ML20206F071 | 8 April 1987 | Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog | |
| 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 | |
| ML20195G252 | 31 March 1987 | Conformance to Reg Guide 1.97,Oconee Nuclear Station,Units 1,2 & 3, Final Informal Rept | Boric Acid |
| ML20215G285 | 31 March 1987 | Technical Evaluation Rept for Oconee Nuclear Station Units 1,2 & 3 Response to Us Nrc,Nrr Generic Ltr 83-37, Informal Rept | Safe Shutdown |
| 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 | |
| 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 | |
| ML20214N821 | 31 March 1987 | a Retran Model of the Calvert CLIFFS-1 Pressurized Water Reactor for Assessing the Safety Implications of Control Systems | |
| 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 | |
| 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 | |
| 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 |