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Issue date | Title | Topic | |
---|---|---|---|
ML20127E329 | 30 September 1992 | TER Pump & Valve IST Program Ano,Unit 2 | Stroke time Cold shutdown justification Backfit |
ML20137S257 | 31 August 1985 | Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Arkansas 1,Crystal River 3,Oconee 1,2 & 3,Rancho Seco & TMI-1 | |
ML20138F081 | 27 November 1995 | TER on IPE Front End Analysis | Mission time Internal Flooding Probabilistic Risk Assessment |
ML20138F092 | 30 November 1995 | TER on IPE Back End Analysis | Mission time Probabilistic Risk Assessment |
ML20138G522 | 25 October 1996 | Technical Evaluation Rept of IPE Submittal & RAI Responses for Plant,Unit 1 Npp | Mission time Internal Flooding Probabilistic Risk Assessment Severe Accident Management Guideline |
ML20138K062 | 30 November 1995 | TER on IPE Submittal Human Reliability Analysis, Final Rept | Internal Flooding |
ML20138N926 | 31 October 1985 | Audit Rept of Dcrdr for Arkansas Nuclear One,Unit 1, for Oct 1985 | |
ML20140C780 | 31 October 1985 | Technical Evaluation Rept,Second Interval Inservice Insp Program,Arkansas Nuclear Power Plant Unit 1 | Hydrostatic VT-2 Dissimilar Metal Weld |
ML20150F344 | 31 March 1988 | PRA Applications Program for Inspection at Arkansas Nuclear One Unit 1.Docket No. 50-313.(Arkansas Power and Light Company) | Probabilistic Risk Assessment Emergency Lighting |
ML20153D432 | 31 March 1988 | User'S Guide for Prisim Arkansas Nuclear One - Unit 1.Volume 1,Program for Inspectors | |
ML20153D495 | 31 March 1988 | User'S Guide for Prisim Arkansas Nuclear One - Unit 1.Volume 2,Program for Regulators | |
ML20154D302 | 21 January 1986 | Site Survey of Arkansas Nuclear One Unit 2 Maint Program & Practices, Technical Ltr Rept | Systematic Assessment of Licensee Performance |
ML20154H545 | 31 August 1988 | Evaluation of Risks Associated with AOT and STI Requirements at the ANO-1 Nuclear Power Plant | |
ML20154K301 | 30 June 1998 | Technical Evaluation Rept, Third Ten-Year Interval Pump & Valve Inservice Testing Program, for Arkansas Nuclear One, Unit 1,Entergy Operations,Inc | Hot Short Safe Shutdown Boric Acid Incorporated by reference |
ML20155F914 | 31 October 1985 | Addendum a to First Internal Inservice Insp Program, Arkansas Nuclear Power Plant,Unit 1 Technical Evaluation Rept | VT-2 Liquid penetrant |
ML20206F072 | 31 March 1999 | Technical Evaluation Rept on Third 10-Year Interval ISI Program Plan,Entergy Operations,Inc,Arkansas Nuclear One, Unit 1 | Boric Acid Nondestructive Examination VT-2 Incorporated by reference |
ML20209F815 | 30 June 1985 | Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Arkansas 1,Crystal River 3,Oconee 1,2 & 3,Rancho Seco & TMI-1 | |
ML20210A581 | 30 October 1985 | Review of Licensee & Applicant Responses to Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2,Arkansas Nuclear One, Units 1 & 2..., Technical Evaluation Rept | |
ML20210K684 | 30 April 1986 | Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Arkansas Nuclear One 2,Calvert Cliffs 1 & 2,Palo Verde 1,2 & 3 & San Onofre 2 & 3 | |
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 | |
ML20211L047 | 31 August 1985 | Conformance to Reg Guide 1.97,Arkansas Nuclear One,Unit 1 | |
ML20212M276 | 31 July 1986 | Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components), Arkansas 1 & 2,Calvert Cliffs 1 & 2,Crystal River 3 & Davis-Besse 1 | |
ML20214L287 | 25 August 1986 | Evaluation of Arkansas Power & Light Co Dcrdr of Arkansas Nuclear One - Unit 1 Plant, Technical Evaluation Rept | |
ML20214L988 | 25 August 1986 | Evaluation of Dcrdr for Arkansas Power & Light Co Arkansas Nuclear One,Unit 2, Technical Evaluation 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 | |
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 |