Semantic search
Jump to navigation
Jump to search
| Issue date | Title | Topic | |
|---|---|---|---|
| ML20198S194 | 30 November 1998 | Technical Evaluation Rept on Second 10-Year Interval Inservice Insp Program Plan,Southern Nuclear Operating Co, Vogtle Electric Generating Plant,Units 1 & 2 | Boric Acid Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Dissimilar Metal Weld |
| ML20101S041 | 30 November 1995 | Plant TER on Individual Plant Exam Back-End Analysis | Mission time Internal Flooding Fuel cladding |
| ML20101S045 | 20 November 1995 | TER of IPE Submittal,Human Reliability Analysis, Final Rept | Internal Flooding Probabilistic Risk Assessment |
| ML20101S038 | 15 November 1995 | Plant TER on Individual Plant Exam Front End Analysis | Safe Shutdown Packing leak Mission time Internal Flooding Probabilistic Risk Assessment |
| ML20080A672 | 30 September 1994 | Technical Evaluation Rept,Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Vogtle-1/-2 | |
| ML20091D275 | 22 August 1991 | Final Rept SAIC-91/6686, Technical Evaluation Electric Vogtle Electric Generating Plant Units 1 & 2 Station Blackout Evaluation | Safe Shutdown Battery sizing |
| ML20043H926 | 31 March 1990 | Draft Rev 0 to, Vogtle Electric Generating Plant Risk-Based Insp Guide (Based on Generic Insights from Probabilistic Risk Assessments for Westinghouse Pwrs). | Probabilistic Risk Assessment |
| ML20084T251 | 31 October 1989 | Technical Evaluation Rept on First 10-Yr Interval Inservice Insp Program Plan:Georgia Power Co,Vogtle Electric Generating Plant,Unit 1 | Weld Overlay Hydrostatic VT-2 Incorporated by reference Through-Wall Leakage |
| 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 |
| 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 | |
| ML20011D101 | 31 July 1988 | Conformance to Generic Ltr 83-28,Item 2.2.1,Equipment Classification for All Other Safety-Related Components: Vogtle-1/-2, Technical Evaluation Rept | |
| ML20196C164 | 4 February 1988 | Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 | |
| 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 |
| 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 |
| 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 | |
| ML17347A593 | 31 July 1987 | Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept | |
| 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 |
| ML20235M420 | 30 June 1987 | Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Vogtle 1 & 2, Informal 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 | |
| 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 | |
| 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. | |
| 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 | |
| ML20206F071 | 8 April 1987 | Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog | |
| 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 | |
| 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 | |
| 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 | |
| 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 | |
| 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 | |
| ML20215J270 | 28 February 1987 | Pump & Valve Inservice Testing Program,Vogtle Electric Generating Plant,Unit 1, Final Technical Evaluation Rept | Boric Acid Stroke time Power Operated Valves |
| 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 | |
| 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 | |
| ML20210A005 | 31 December 1986 | Environ Radioactivity Survey for 1986 | Grab sample Chernobyl |
| ML20210A013 | 31 December 1986 | BWR Environ Radioactivity Survey for 1986 | Grab sample Chernobyl |
| ML20207N246 | 16 December 1986 | Technical Assistance to Nrc,Region Iv,For Preservice Insp, Monthly Ltr Rept for Nov 1986 | |
| 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 | |
| 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. | |
| ML20207S523 | 30 November 1986 | Technical Evaluation Rept for Gessar II Responses for Resolution of Humphrey Safety Concerns (Hsc) Re Mark III Containment Sys | Hydrostatic |
| ML20207S520 | 30 November 1986 | Technical Evaluation Rept for River Bend Station on SER Outstanding Issue (8) - Mark III Containment Sys Issues - Humphrey Safety Concerns (Hsc) | |
| 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 |