Semantic search

This page or action requires JavaScript to work. Please enable JavaScript in your browser or use a browser where it is supported, so that functionality can be provided as requested. For further assistance, please have a look at the noscript help page.

Search Clear all entries

	Issue date	Title	Topic
ML20211K768	30 July 1999	Evaluation of Fuel Pin Failure Timing in Boiling Water Reactors
ML20236U724	31 March 1998	Technical Evaluation Rept on Third 10-Year Interval ISI Program Plan:Nneco Millstone Nuclear Power Station,Unit 2, Dtd Mar 1998
ML20216E872	13 March 1998	Rept to NRC Environ Monitoring at Grand Gulf Nuclear Station CY97, Conducted by Contract NRC-29-83-621
ML20140E299	2 June 1997	Proposed Criteria for ECCS Strainer Design,Technical Evaluation Rept	Foreign Material Exclusion
ML20140G590	27 March 1997	Rev 0 to, Review of Millstone Nuclear Power Station Response to USNRC RAI of 960812 on Fire Barrier Ampacity Derating	Fire Barrier
L-96-018, Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2	31 December 1996	Rev 1 to INEL-96/0188, TER on Third 10-Yr Interval Inservice Insp Program Plan:Gpc,Ei Hatch Nuclear Plant Units 1 & 2	Safe Shutdown Boric Acid High Radiation Area Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Liquid penetrant Pressure boundary leak Through-Wall Leak Scaffolding
ML20106H126	12 December 1995	IPE Insight Rept NUREG-1150 Plants	Ultimate heat sink Probabilistic Risk Assessment Containment Hardened Vent
ML20117D074	30 November 1995	Unit 2-TER on IPE Submittal Human Reliability Analysis - Final Rept	Probabilistic Risk Assessment
ML20117D080	30 November 1995	TER on IPE - Back-End Analysis	Probabilistic Risk Assessment
ML20117D068	27 November 1995	NPP TER on IPE Front End Analysis	Safe Shutdown Mission time Internal Flooding Probabilistic Risk Assessment
ML20101C894	16 October 1995	Plant IPE Insight Support Rept for NUREG-1150 Plants	Internal Flooding Probabilistic Risk Assessment
ML20087K369	31 July 1995	Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Summary of Results	Mission time Internal Flooding Probabilistic Risk Assessment Earthquake Fatality
ML20086G516	29 June 1995	Technical Evaluation Rept on Individual Plant Exam Front End Analysis	Mission time Internal Flooding Hardened vent
ML20082D526	31 March 1995	Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage.Supporting Melcor Calculations	Ultimate heat sink Internal Flooding Hydrostatic Probabilistic Risk Assessment Fuel cladding
ML20082B741	31 March 1995	Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage.Main Report and Appendices
ML20086G521	31 December 1994	Technical Evaluation Rept on Individual Plant Exam Back-End Analysis	Probabilistic Risk Assessment Hardened vent
L-94-021, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-3	30 November 1994	Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-3
ML20086G528	30 November 1994	Technical Evaluation Rept on Individual Plant Exam Human Reliability Analysis	Mission time Hardened vent
ML20079S078	26 September 1994	Technical Evaluation Rept;Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Hatch-1/-2
ML20073C367	31 August 1994	Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf, Unit 1.Analysis of Core Damage Frequency from Seismic Events During Mid-Loop Operations.Main Report	Safe Shutdown Earthquake Internal Flooding Probabilistic Risk Assessment Operating Basis Earthquake Seismically rugged Earthquake
ML20072D058	31 July 1994	Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage	Safe Shutdown Fire Barrier Probabilistic Risk Assessment
ML20072N999	31 July 1994	Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internally Induced Flooding Events for Plant Operational State 5 During a Refueling.	Mission time Internal Flooding Probabilistic Risk Assessment Earthquake
ML20071L611	30 June 1994	Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During Refueling Outage.Internal
ML20071L719	30 June 1994	Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Internal
ML20071L741	30 June 1994	Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Internal	Mission time Internal Flooding Probabilistic Risk Assessment
ML20071L597	30 June 1994	Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Main Report
ML20071L583	30 June 1994	Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Section 10
ML20071L566	30 June 1994	Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Sections 1-9
ML20063B550	24 January 1994	Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001,Grand Gulf,Unit 1, Technical Evaluation Rept
ML20058E891	30 November 1993	Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Seismic Analysis
ML20064K051	31 October 1993	Summary Rept Of:Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Final Ltr Rept
ML20045B948	31 May 1993	Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant:Phenomenology and Risk Uncertainty Evaluation Program (Pruep).Appendices D-G
ML20045A521	31 May 1993	High Pressure Coolant Injection System RISK-BASED Inspection Guide for Hatch Nuclear Power Station	Reactor Vessel Water Level Probabilistic Risk Assessment Overtravel
ML20045B904	31 May 1993	Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant.Phenomenology and Risk Uncertainty Evaluation Program (Pruep) Appendices A-C	Probabilistic Risk Assessment
ML20116J479	31 October 1992	Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Flood Analysis	Safe Shutdown Internal Flooding Probabilistic Risk Assessment VT-2
ML20116J655	31 October 1992	Integrated Risk Assessment for the Lasalle Unit 2 Nuclear Power Plant. Phenomenology and Risk Uncertainty Evaluation Program (Pruep).Melcor Code Calculations
ML20116J531	31 October 1992	Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Initiating Events and Accident Sequence Delineation	Reactor Vessel Water Level Ultimate heat sink Probabilistic Risk Assessment Feedwater Controller Failure
ML20105C763	31 August 1992	Integrated Risk Assessment for Lasalle Unit 2 Nuclear Power Plant.Phenomenology and Risk Uncertainty Evaluation Program (Pruep)	Ultimate heat sink Probabilistic Risk Assessment Earthquake
ML20105C817	31 August 1992	Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Main Report
ML20105C822	31 August 1992	Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Internal Events Accident Sequence Quantification.Appendices	Probabilistic Risk Assessment
ML20099D625	31 July 1992	Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).External Event Scoping Quantification
ML20099D528	31 July 1992	Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep).Summary	Reactor Vessel Water Level Ultimate heat sink Fire Barrier Internal Flooding Probabilistic Risk Assessment Earthquake Fire Watch
ML20113H989	31 July 1992	Analysis of the Lasalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (Rmiep). Integrated Quantification and Uncertainty Analysis
ML20126M423	31 July 1992	TER on Third 10-Yr Interval ISI Program Plan:Northeast Utils,Millstone Nuclear Power Station,Unit 1	Boric Acid Packing leak High Radiation Area Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Liquid penetrant Scaffolding
ML20097H316	30 June 1992	Trip Rept:Onsite Analysis of Human Factors of Event at LaSalle 2 920420 (Reactor Water Cleanup Sys Isolation Bypass)
ML18151A899	31 May 1992	Summary Rept of :Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Draft Ltr Rept
ML20071A637	31 January 1991	Trip Rept: Onsite Analysis of Human Factors of Event at Millstone 3 on 901231 (Turbine Bldg Pipe Break)	Through Wall Leak
ML20066D342	31 December 1990	Evaluation of Severe Accident Risks: Grand Gulf,Unit 1. Appendices	Probabilistic Risk Assessment Fatality
ML20066D298	31 December 1990	Evaluation of Severe Accident Risks: Grand Gulf,Unit 1.Main Report
ML20058H599	15 November 1990	Analysis of Ei Hatch Unit 2 Integrated Leakage Rate Testing Data Using Sbir Analysis of State-of-Art Methods of Containment Integrated Leakage Rate Testing

Semantic search

Query log

Navigation menu