Semantic search
Jump to navigation
Jump to search
| Issue date | Title | Topic | |
|---|---|---|---|
| L-96-026, Tech Evaluation Rept on Second 10 Year Inservice Insp Program Plan:Wolf Creek Nuclear Operating Corp | 31 July 1997 | Tech Evaluation Rept on Second 10 Year Inservice Insp Program Plan:Wolf Creek Nuclear Operating Corp | Boric Acid High Radiation Area Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Liquid penetrant Through-Wall Leak Dissimilar Metal Weld Scaffolding Backfit |
| ML20216C323 | 20 December 1996 | Rev 0 to, Technical Evaluation of Wolf Creek Nuclear Operating Corp,Analysis of Fire Barrier Ampacity Derating Factors | Fire Barrier |
| ML20134C742 | 5 September 1996 | Technical Evaluation Rept on IPE Submittal Human Reliability Analysis,Final Rept | Internal Flooding Probabilistic Risk Assessment |
| ML20216C344 | 19 April 1996 | Rev 0 to, Review of Wolf Creek Nuclear Operating Corp, Analysis of Fire Barrier Ampacity Derating Factors | Fire Barrier |
| ML20134C738 | 30 November 1995 | Technical Evaluation Rept of Wolf Creek Individual Plant Examination Back End Submittal,Final Rept,Nov 1995 | Loop seal Mission time Internal Flooding Probabilistic Risk Assessment |
| ML20134C735 | 28 November 1995 | Technical Evaluation Rept on Individual Plant Examination Front End Analysis for Wolf Creek Generating Station Task 44 | Mission time Internal Flooding Probabilistic Risk Assessment Fuel cladding |
| ML20071B069 | 31 March 1994 | Technical Evaluation Rept:Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01 | |
| ML20058M082 | 20 September 1993 | Transient Analysis Methodology for Wolf Creek Generating Station Technical Evaluation | |
| ML20097G001 | 8 May 1992 | Supplemental TER, Wolf Creek Generating Station Blackout Evaluation | Emergency Lighting Battery sizing |
| ML20086R998 | 17 December 1991 | Final Technical Evaluation Rept - Wolf Creek Generating Station,Station Blackout Evaluation | Safe Shutdown |
| ML20217C679 | 8 July 1991 | Notification of Contract Execution,Task Order 21,to Nuclear Power Reactor Operations,Mods & Maint Insp Svcs. Contractor:Parameter,Inc | |
| ML19354D797 | 31 December 1989 | Draft Rev 0 to Wolf Creek Generating Station Risk-Based Insp Guide (Based on Generic Insights from PRAs for Westinghouse Pwrs). | Safe Shutdown Boric Acid Ultimate heat sink Mission time Probabilistic Risk Assessment Feedwater Controller Failure Fuel cladding |
| ML20070Q788 | 31 December 1988 | Nuclear Power Plant Sys Sourcebook,Wolf Creek | |
| ML20148J809 | 31 December 1987 | Technical Evaluation Rept,Pump & Valve Inservice Testing Program,Wolf Creek Generating Station | Boric Acid Stroke time Cold shutdown justification Power Operated Valves |
| ML20214R046 | 30 April 1987 | Technical Evaluation Rept on First 10-Yr Interval Inservice Insp Program Plan:Kansas Gas & Electric Co,Wolf Creek Generating Station, Informal Rept | Hydrostatic VT-2 Incorporated by reference Liquid penetrant |
| ML20215L854 | 30 April 1987 | Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety Related Components:Wolf Creek, Final Informal Rept | Safe Shutdown |
| ML20211K510 | 30 November 1986 | Input for Ser,Mcguire Nuclear Station Units 1 & 2,Millstone Nuclear Power Station Unit 3,Seabrook Station Units 1 & 2, VC Summer Nuclear Station,Vogtle Electric...Reactor Trip Sys Reliability,Item 4.5.2 of 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 | |
| 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 | |
| ML20244D387 | 10 July 1985 | Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. | |
| ML20244D438 | 30 June 1985 | Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities | |
| ML20093C668 | 31 May 1984 | Conformance to Reg Guide 1.97,Wolf Creek Plant,Unit 1 | |
| ML20112J489 | 31 July 1983 | Audit of Environ Qualification of Safety-Related Electrical Equipment for Snupps | Anchor Darling |
| ML20041C277 | 31 January 1982 | Snupps Auxiliary Feedwater System Reliability Study Evaluation | |
| ML19242D750 | 2 July 1979 | Petrographic Rept,Project Examination of Concrete Samples from Reactor Containment Bldg Base Mat Ks Prepared by Army Corps of Engineers.Concrete Samples Are of Comparable Quality to Specimens Giving Normal Value | |
| ML20049A165 | 2 February 1979 | Rept of Investigation of Ks Gas & Electric Study of Low Concrete Cylinder Strengths of Reactor Containment Bldg Base Mat. |