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Issue date | Title | Topic | |
---|---|---|---|
ML20212D678 | 31 March 1999 | Supplemental Technical Evaluation Report Based on Review of Additional Responses Concerning Individual Plant Examination of External Events at Point Beach Nuclear Plant,Units 1 & 2. Final Rept | Hot Short Safe Shutdown Fire Barrier Safe Shutdown Earthquake Earthquake |
ML20212D641 | 31 March 1998 | Technical Evaluation Report on Submittal Only Review of Individual Plant Examination of External Events at Point Beach Nuclear Plant,Units 1 & 2. Final Rept | Hot Short Safe Shutdown High winds Ultimate heat sink Mission time Fire Barrier Tornado Missile Safe Shutdown Earthquake Internal Flooding Probabilistic Risk Assessment Operating Basis Earthquake Earthquake Turbine Missile |
ML20078E047 | 4 October 1994 | TER on Front End IPE Submittal, Task 22,dtd 941004 | Boric Acid Mission time Internal Flooding Probabilistic Risk Assessment |
ML20078E122 | 30 September 1994 | IPE Back-End TER Dtd Sept 1994 | Mission time Internal Flooding Severe Accident Management Guideline |
ML20078E150 | 31 August 1994 | TER of IPE Submittal Human Reliability Analysis, Final Rept, Task 23.Draft Dtd 940131,final Aug 1994 | Internal Flooding Probabilistic Risk Assessment |
ML20141D327 | 31 August 1994 | Dispersion Estimates in Vicinity of Buildings | |
ML20097A828 | 6 April 1992 | Technical Evaluation Rept Pump & Valve Inservice Testing Program Point Beach Nuclear Power Plant,Units 1 & 2 Wepc, Per 10CFR50.55a(g) | Boric Acid Stroke time Anchor Darling Incorporated by reference 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 |
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 | |
ML20245E937 | 31 December 1988 | Rev 1 to EGG-NTA-8030, TMI Action--NUREG-0737 (II.D.1) Point Beach,Units 1 & 2, Technical Evaluation Rept | Loop seal Stroke time Anticipated operational occurrence Earthquake |
ML20205N943 | 31 October 1988 | Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 | |
ML20155G752 | 14 June 1988 | Review of Point Beach Nuclear Plant,Unit 1 & 2,Alternate Shutdown Capability | Safe Shutdown Fire Barrier |
ML20042D053 | 7 June 1988 | Technical Evaluation Rept of Dcrdr for Point Beach Nuclear Power Plant,Units 1 & 2. | |
ML20154H584 | 12 May 1988 | App D,Evaluation of Offsite Dose Calculation Manual Rev 1 (Point Beach Nuclear Power Plant,Units 1 & 2) | Grab sample Offsite Dose Calculation Manual |
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 |
ML20235Y659 | 16 October 1987 | Technical Evaluation Rept for Wisconsin Electric Power Co Point Beach Nuclear Plant,Units 1 & 2 SPDS Sar | |
ML20235M359 | 31 August 1987 | Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept | Boric Acid |
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 | |
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 | |
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 |
ML20236P640 | 31 July 1987 | Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept | |
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 | |
ML20153D767 | 11 May 1987 | Evaluation of Fire Protection Exemption Requests from 10CFR50.48 & App R to 10CFR50, Technical Evaluation Rept | Safe Shutdown Boric Acid Fire Barrier Coatings Emergency Lighting Exemption Request Fire Protection Program |
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 | |
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. | |
ML20206F071 | 8 April 1987 | Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog | |
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 | |
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 | |
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 | |
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 | |
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. | |
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 | |
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 | |
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 | |
ML20210A013 | 31 December 1986 | BWR Environ Radioactivity Survey for 1986 | Grab sample Chernobyl |
ML20210A005 | 31 December 1986 | 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 | |
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) | |
ML20207S523 | 30 November 1986 | Technical Evaluation Rept for Gessar II Responses for Resolution of Humphrey Safety Concerns (Hsc) Re Mark III Containment Sys | Hydrostatic |
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. |