Semantic search
Jump to navigation
Jump to search
| Issue date | Title | Topic | |
|---|---|---|---|
| ML20202B389 | 15 September 1997 | Rev 1 to, Technical Evaluation of Duane Arnold Energy Ctr Analysis of Ampacity Loads for Fire Barriers Clad Power Cables | Fire Barrier |
| ML20149L654 | 31 August 1995 | Plant TER on IPE Back-End Submittal | Mission time Hardened vent |
| ML20149L649 | 31 August 1995 | Plant TER on IPE Front End Analysis | Mission time Internal Flooding Probabilistic Risk Assessment Squib Hardened vent Backfit Failure to Scram Overspeed trip Loss of condenser vacuum |
| ML20094P188 | 31 May 1995 | TER, Duane Arnold Energy Ctr Pump & Valve Inservice Testing Program,Rev 13,Third 10-Yr Interval | Reactor Vessel Water Level Stroke time Excess Flow Check Valve Water hammer |
| ML20063E906 | 30 December 1993 | Parametric Study of Potential for BWR ECCS Blockage Due to LOCA Generated Debris, Vol 2,Parts 1 & 2 | |
| ML112380516 | 12 November 1993 | TER to Request for TS Change,Ielp,Cipc & Cbpc,Daec. | |
| ML20118C095 | 1 August 1992 | Technical Evaluation of Duane Arnold Energy Ctr Emergency Svc Water | |
| ML20101Q343 | 30 June 1992 | Metallurgical Evaluation of Weld Overlaid Pipe Sections from Brunswick Unit 2 Nuclear Power Station | |
| ML20065C961 | 24 August 1990 | Rev 2 to Technical Evaluation Rept Brunswick Steam Electric Plant Units 1 & 2 Station Blackout Evaluation, Final Rept | Safe Shutdown Reactor Vessel Water Level |
| ML20011D915 | 30 November 1989 | Review of the Brunswick Steam Electric Plant Probabilistic Risk Assessment | High winds Ultimate heat sink Mission time Fire Barrier Internal Flooding Probabilistic Risk Assessment Feedwater Heater Earthquake Scaffolding Loss of condenser vacuum |
| ML20071P715 | 30 November 1989 | Rev 1 to Brunswick Steam Electric Plant Unit 2 Risk-Based Insp Guide, Final Version | Reactor Vessel Water Level Mission time Probabilistic Risk Assessment Squib High Energy Line Break Fuel cladding Water hammer |
| ML20005E997 | 30 November 1989 | Technical Evaluation Rept Pump & Valve Inservice Testing Program,Brunswick Steam Electric Plant,Units 1 & 2. | Safe Shutdown Stroke time Squib Scram Discharge Volume Excess Flow Check Valve Integrated leak rate test 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 |
| ML19325C145 | 10 July 1989 | Technical Evaluation Rept for Dcrdr at CP&L Brunswick Steam Electric Plant,Units 1 & 2. | |
| ML19325C147 | 7 July 1989 | Post-Implementation Audit Rept for CP&L Brunswick Steam Electric Plant Units 1 & 2 SPDS 890515-18. | |
| 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 | |
| ML20070Q525 | 31 January 1989 | Nuclear Power Plant Sys Sourcebook,Brunswick 1 & 2 | Safe Shutdown Reactor Vessel Water Level Ultimate heat sink Scram Discharge Volume Failure to Scram Overspeed trip |
| ML20205N943 | 31 October 1988 | Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 | |
| ML20196D878 | 18 February 1988 | Technical Evaluation Rept of Dcrdr for Iowa Electric Light & Power Co Duane Arnold Energy Ctr | |
| 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 |
| ML20246B722 | 31 January 1988 | Technical Evaluation Rept on First 10-Yr Interval Inservice Insp Relief Requests:Cp&L,Brunswick Steam Electric Plant, Units 1 & 2 | |
| ML20246P967 | 31 January 1988 | Technical Evaluation Rept on Second 10-yr Interval Inservice Insp Program Plan,Brunswick Steam Electric Plant Unit 1 | Hydrostatic VT-2 Incorporated by reference Intergranular Stress Corrosion Cracking |
| 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 Loss of condenser vacuum |
| 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 | |
| ML20215M088 | 31 May 1987 | Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, Duane Arnold, Informal Rept | |
| ML20215L882 | 31 May 1987 | Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Brunswick 1 & 2, 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 | |
| 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. | |
| 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 | |
| ML20215L863 | 30 April 1987 | Final Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components,Brunswick 1 & 2, Informal Rept | |
| ML20206F071 | 8 April 1987 | Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog | |
| 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 | |
| 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 | |
| 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 | |
| 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. | |
| 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 |