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Issue date | Title | Topic | |
---|---|---|---|
ML20062J274 | 31 August 1993 | Technical Evaulation Rept, Evaluation of B&Wog Pressurizer Surge Line Thermal Stratification Program to Address NRC Bulletin 88-11 | |
ML20091J095 | 20 December 1991 | Final Technical Evaluation Rept - Oconee Nuclear Station, Station Blackout Evaluation | Safe Shutdown |
ML20072P671 | 24 April 1990 | Second Interval Inservice Insp Program Oconee Nuclear Station Units 1,2 & 3, Technical Evaluation Rept | Hydrostatic VT-2 Incorporated by reference Liquid penetrant Dissimilar Metal Weld |
ML20236B805 | 13 March 1989 | Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files | |
ML20245E927 | 31 August 1988 | Technical Evaluation Rept,Tmi Action--NUREG-0737 (II.D.1) Relief & Safety Valve Testing, Oconee Units 1,2 & 3 | Loop seal Anticipated operational occurrence |
ML20236E225 | 31 October 1987 | PRA Application Program for Inspection at Oconee Unit 3 | Internal Flooding Probabilistic Risk Assessment Earthquake |
ML20235X530 | 31 August 1987 | Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface Oconee 1,2 & 3 | |
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 |
ML20215G285 | 31 March 1987 | Technical Evaluation Rept for Oconee Nuclear Station Units 1,2 & 3 Response to Us Nrc,Nrr Generic Ltr 83-37, Informal Rept | Safe Shutdown |
ML20195G252 | 31 March 1987 | Conformance to Reg Guide 1.97,Oconee Nuclear Station,Units 1,2 & 3, Final Informal Rept | Boric Acid |
ML20199J204 | 30 June 1986 | a Review of the OCONEE-3 Probabilistic Risk Assessment Containment Performance,Radiological Source Terms and Risk Estimates | Probabilistic Risk Assessment Fatality |
ML20154R389 | 31 March 1986 | a Review of the OCONEE-3 Probabilistic Risk Assessment. Internal Events,Core Damage Frequency | Safe Shutdown Mission time Probabilistic Risk Assessment Earthquake Failure to Scram Manual Operator Action Loss of condenser vacuum |
ML20155K579 | 31 March 1986 | an Assessment of the Safety Implications of Control at the Oconee 1 Nuclear Plant Final Report | Boric Acid Stroke time Probabilistic Risk Assessment Operator Manual Action Earthquake Overspeed trip Loss of condenser vacuum |
ML20154R392 | 31 March 1986 | a Review of the OCONEE-3 Probabilistic Risk Assessment. External Events,Core Damage Frequency | Probabilistic Risk Assessment |
ML20211G943 | 30 December 1985 | Preliminary Development of an Integrated Approach to the Evaluation of Pressurized Thermal Shock as Applied to the Oconee Unit 1 Nuclear Power Plant | Loop seal Probabilistic Risk Assessment Earthquake Coast down Exclusive Use Loss of condenser vacuum |
ML20210K645 | 30 November 1985 | PRA Insights | Safe Shutdown Mission time Tornado Missile Internal Flooding Probabilistic Risk Assessment Earthquake Turbine Missile Fatality |
ML20138Q690 | 31 October 1985 | Failure Modes and Effects Analysis (FMEA) of the Ics/Nni Electric Power Distribution Circuitry at the OCONEE-1 Nuclear Plant | |
ML20151U348 | 15 October 1985 | Comparison of Plant-Specific Analyses of Pressurized Thermal Shock (Based on Oconee,Calvert Cliffs & Hb Robinson), Technical Ltr Rept | |
ML20135D344 | 31 August 1985 | Trac Analyses of Severe Overcooling Transients for the OCONEE-1 PWR | Shutdown Margin Loop seal |
ML20137S257 | 31 August 1985 | Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Arkansas 1,Crystal River 3,Oconee 1,2 & 3,Rancho Seco & TMI-1 | |
ML20209F815 | 30 June 1985 | Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Arkansas 1,Crystal River 3,Oconee 1,2 & 3,Rancho Seco & TMI-1 | |
ML20128G488 | 31 May 1985 | Conformance to Reg Guide 1.97,Oconee Nuclear Station, Units 1,2 & 3 | |
ML20116P119 | 30 April 1985 | Assessment of Selected Trac and RELAP5 Calculations for OCONEE-1 Pressurized Thermal Shock Study | |
ML20209E517 | 30 April 1985 | Dominant Accident Sequences in OCONEE-1 Pressurized Water Reactor | Safe Shutdown Boric Acid Loop seal Probabilistic Risk Assessment Coast down |
ML20127C429 | 11 January 1985 | Evaluation of Supplemental Info for Detailed Control Room Review,Summary Rept for Oconee Nuclear Station Units 1,2 & 3, Suppl to Final Technical Evaluation Rept | |
ML20108B401 | 30 September 1984 | Draft Final Rept,Vol 1, Assessment of Safety Implications of Control at Oconee-1 Nuclear Plant | |
ML20097F333 | 31 July 1984 | Possible Modes of Steam Generator Overfill Resulting from Control System Malfunctions at OCONEE-1 Nuclear Plant | |
ML20093J686 | 20 July 1984 | Evaluation of Detailed Control Room Design Review Summary Rept for Oconee Nuclear Station,Units 1,2 & 3, Final Technical Evaluation Rept | |
ML20151K219 | 24 April 1984 | Preliminary Draft Evaluation of Control Sys Failures Leading to RCS Overcooling in Oconee 1 Power Plant. NUREG/CR-3692, Possible Modes of Steam Generator Overfill Resulting from Control Sys Malfunctions... Encl | Boric Acid |
ML20080F293 | 4 February 1984 | Trac Analyses of Severe Overcooling Transients for Oconee-1 Pwr | Shutdown Margin Loop seal |
ML20105C761 | 2 February 1984 | Masonry Wall Design,Oconee Nuclear Station Units 1,2 & 3, Technical Evaluation Rept | Fire Barrier Tornado Missile Safe Shutdown Earthquake Operating Basis Earthquake Earthquake |
ML20080C253 | 31 July 1983 | RELAP5 Thermal-Hydraulic Analysis of Pressurized Thermal Shock Sequences for Oconee-1 Pwr | |
ML20077K834 | 6 April 1983 | Selected Operating Reactor Issues Program Ii,Rcs Sys Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept | Hot Short Safe Shutdown |
ML20072J748 | 31 March 1983 | Adequacy of Station Electric Distribution Sys Voltages, Oconee Nuclear Station,Units 1,2 & 3, Interim Rept | |
ML20072S670 | 31 March 1983 | Control of Heavy Loads (C-10), Oconee Nuclear Power Station Units 1,2 & 3, Technical Evaluation Rept | Safe Shutdown Control of Heavy Loads |
ML20073E284 | 14 March 1983 | Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Oconee Nuclear Station,Unit 3, Technical Evaluation Rept | Boric Acid Fire Barrier Post Accident Monitoring |
ML20073E272 | 11 March 1983 | Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Oconee Nuclear Station,Unit 2, Technical Evaluation Rept | Boric Acid Post Accident Monitoring |
ML20073E268 | 8 March 1983 | Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Oconee Nuclear Station,Unit 1, Technical Evaluation Rept | Boric Acid Fire Barrier Post Accident Monitoring |
ML20065B228 | 31 January 1983 | Adequacy of Station Electric Distribution Sys Voltages, Oconee Nuclear Station,Units 1,2 & 3, Informal Rept | |
ML20126E994 | 7 December 1982 | Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 | |
ML20065F725 | 28 September 1982 | PWR Main Steam Line Break W/Continued Feedwater Addition (B-69),Oconee Nuclear Station Units 1,2 & 3, Technical Evaluation Rept | Boric Acid Shutdown Margin Probabilistic Risk Assessment |
ML20062B078 | 31 July 1982 | Socioeconomic Impacts of Nuclear Generating Stations: Oconee Case Study.Docket Nos. 50-269 and 50-270.(Duke Power Company) | |
ML20054F638 | 4 June 1982 | Audit of Oconee Procedures & Training for Pressurized Thermal Shock | Shutdown Margin |
ML20244B561 | 6 August 1981 | Containment Leakage Rate Testing,Oconee Units 1,2 & 3, Technical Evaluation Rept | Local Leak Rate Testing |
ML20039F034 | 31 May 1981 | Reactor Safety Study Methodology Applications Program: Oconee #3 PWR Power Plant | |
ML20080J309 | 17 April 1981 | Metallurgical,Stress & Fracture Mechanics Analyses of Cracked Steam Generator Manway Studs from Oconee Unit 3 of Duke Power Co | |
ML20080J321 | 17 April 1981 | Attachment 1 to Stress Analysis of Failed Steam Generator Manway Studs from Oconee Unit 3,Duke Power Co | |
ML19309C471 | 29 February 1980 | Electrical,Instrumentation & Control Aspects of Override of Containment Purge Valve Isolation & Other Safety Feature Signals,Oconee Nuclear Station, Informal Rept | |
ML19296C978 | 30 November 1979 | Electrical,Instrumentation & Control Aspects of Override of Containment Purge Valve Isolation & Other Safety Feature Signals,Oconee Nuclear Station,Units 1,2 & 3, Informal Rept |