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Issue date | Title | Topic | |
---|---|---|---|
ML20210U823 | 31 January 1999 | Technical Evaluation Rept Pump & Valve Inservice Testing Program Braidwood Nuclear Power Station,Units 1 & 2 | Boric Acid High Radiation Area Stroke time Weld Overlay Power Operated Valves Scaffolding |
ML20085K467 | 30 June 1995 | Technical Evaluation Rept:Evaluation of Utility Response to Suppl 1 to NRC Bulletin 90-01,Braidwood-1/2 | |
L-94-010, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01: Byron-1/-2, Technical Evaluation Rept | 31 October 1994 | Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01: Byron-1/-2, Technical Evaluation Rept | |
ML20091D173 | 31 July 1991 | Auxiliary Feedwater System RISK-BASED Inspection Guide for the Byron and Braidwood Nuclear Power Plants | Packing leak Probabilistic Risk Assessment |
ML20085C081 | 30 April 1991 | TER Rept on First 10-Yr Interval ISI Program Plan for Braidwood Nuclear Power Station Units 1 & 2 | Boric Acid High Radiation Area Hydrostatic VT-2 Incorporated by reference Scaffolding |
ML20059E197 | 24 August 1990 | Emergency Preparedness Exercise, Final Rept Per Insp Repts 50-454/90-16 & 50-455/90-15 | |
ML20084T303 | 30 June 1990 | Pump & Valve Inservice Testing Program,Braidwood Station, Units 1 & 2, Technical Evaluation Rept | Boric Acid Stroke time Cold shutdown justification Power Operated Valves |
ML20058K225 | 14 June 1990 | Technical Evaluation Rept,Braidwood Station Units 1 & 2 Station Blackout Evaluation | Safe Shutdown Battery sizing |
ML20058K165 | 3 April 1990 | Technical Evaluation Rept Byron Station Units 1 & 2 Station Blackout Evaluation | Safe Shutdown Battery sizing |
ML20011D105 | 30 September 1989 | Conformance to Generic Ltr 83-28,Item 2.2.1-Equipment Classification for All Other Safety-Related Components: Byron-1/-2, Technical Evaluation Rept | |
ML20011D103 | 30 September 1989 | Conformance to Generic Ltr 83-28,Item 2.2.1-Equipment Classification for All Other Safety-Related Components: Braidwood-1/-2, Technical Evaluation Rept | |
ML20246B973 | 31 March 1989 | Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept | Boric Acid |
ML20070Q515 | 31 January 1989 | Nuclear Power Plant Sys Sourcebook,Byron 1 & 2 | Safe Shutdown Boric Acid Ultimate heat sink Hydrostatic Emergency Lighting |
ML20070Q500 | 31 January 1989 | Nuclear Power Plant Sys Sourcebook,Braidwood 1 & 2 | Safe Shutdown Boric Acid Ultimate heat sink Hydrostatic Emergency Lighting |
ML20244A680 | 31 March 1988 | Technical Evaluation Rept for Review of Byron Nuclear Generating Station Essential Svc Water Cooling Tower Thermal Performance Test Rept | |
ML20042D070 | 31 January 1988 | TMI Action-NUREG-0737 (II.D.1),Braidwood Units 1 & 2, Technical Evaluation Rept | Loop seal Anticipated operational occurrence Earthquake |
ML20207E206 | 31 January 1988 | Technical Evaluation Rept,Tmi Action - NUREG-0737 (II.D.1), Byron Units 1 & 2 | Loop seal Anticipated operational occurrence Earthquake |
ML20235M359 | 31 August 1987 | Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept | Boric Acid |
ML20235M930 | 30 June 1987 | Final Evaluation of Braidwood Station Unit 1 Tech Specs, Informal Rept | |
ML20215L990 | 22 May 1987 | Essential Svc Water Cooling Tower Test Plan Preliminary Evaluation, Ltr Rept | |
ML20215H677 | 31 March 1987 | Conformance to Generic Ltr 83-28,Item 2.2.2,Vendor Interface Programs (All Other Safety-Related Components), Byron Station,Units 1 & 2, Technical Evaluation Rept | |
ML20213H068 | 28 February 1987 | Conformance to Generic Ltr 83-28,Item 2.2.2, 'Vendor Interface Programs (All Other Safety-Related Components),' Braidwood Station Units 1 & 2, Technical Evaluation Rept | |
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. | |
ML20211E964 | 31 October 1986 | Rev 3 to Conformance to Generic Ltr 83-28,Item 3.1.3 & 3.2.3,Braidwood Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Indian Point Unit 3,Trojan Nuclear Plant & Wolf Creek Generating Station | |
ML20206F521 | 30 June 1986 | Analysis of Allowed Outage Times at Byron Generating Station | Safe Shutdown Boric Acid Mission time Probabilistic Risk Assessment |
ML20133G480 | 9 October 1985 | Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28,Item 1.2 `Post-Trip Review:Data & Info Capabilities' for Byron Station,Units 1 & 2, Technical Evaluation Rept | |
ML20138K984 | 30 September 1985 | Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Byron Station Unit 1,Callaway Plant Unit 1,Indian Point Unit 3,Trojan Nuclear Plant & Wolf Creek Generating Station | |
ML20138M462 | 26 September 1985 | Design Verification Audit of SPDS for Byron Generating Station Units 1 & 2 | |
ML20137D556 | 31 July 1985 | Aerial Radiological Survey of Byron Station & Surrounding Area,Apr 1985 | |
ML20132D145 | 24 June 1985 | Final Review of Byron Limiting Condition for Operation Relaxation Study,Task 1, Interim Rept | Probabilistic Risk Assessment |
ML20083D085 | 30 November 1983 | Review of the Byron/Braidwood Units 1 and 2 Auxiliary Feedwater System Reliability Analysis | |
ML20112J145 | 31 July 1983 | Audit of Environ Qualification of Safety-Related Electrical Equipment at Byron Units 1 & 2 & Braidwood Units 1 & 2 | Boric Acid Anchor Darling |
ML20065C358 | 31 July 1982 | Control of Heavy Loads at Nuclear Power Plants,Byron Units 1 & 2 & Braidwood Units 1 & 2, Draft Technical Evaluation Rept | Safe Shutdown Overtravel Control of Heavy Loads |