Semantic search
Jump to navigation
Jump to search
Issue date | Title | Topic | |
---|---|---|---|
L-94-014, Rev 1 to Safety Analysis of Radiological Consequences of SBLOCA at U2 with Delayed CNMT Spray Actuation & NUREG-1465 Core Damage Progression | 30 January 1998 | Rev 1 to Safety Analysis of Radiological Consequences of SBLOCA at U2 with Delayed CNMT Spray Actuation & NUREG-1465 Core Damage Progression | |
ML20195D022 | 26 January 1998 | Rev 1 to Assessment of Doses in Unit 2 CR Due to Locked Rotor Accident at Unit 2 Assuming 18% Failed Fuel | |
ML20195C642 | 16 January 1998 | Change 1 to Rev 1 of Calculation 456, Combined BV1-BV2 Control Room Doses Due to Waste Gas Sys Line Rupture Accident at BV1 | |
ML20217J836 | 2 October 1997 | Rev 1 to DE&S-SR/EM01, Ampacity Derating Factors of Fire- Protected Conduits | Safe Shutdown Fire Barrier |
L-96-010, Safety Analysis of Eab,Lpz & CR Doses from Main Steam Line Break Outside of CNMT at U2 W/Increased Primary-to-Secondary Leakage (SG Apc) | 25 February 1997 | Safety Analysis of Eab,Lpz & CR Doses from Main Steam Line Break Outside of CNMT at U2 W/Increased Primary-to-Secondary Leakage (SG Apc) | |
L-95-008, Rev 2 to SA of Common CR Eab,Lpz Doses from MSLB Outside of CNMT at Unit 1 W/Increased Primary-to-Secondary Leakage | 24 February 1997 | Rev 2 to SA of Common CR Eab,Lpz Doses from MSLB Outside of CNMT at Unit 1 W/Increased Primary-to-Secondary Leakage | Non-Destructive Examination Coast down |
ML20195F232 | 24 January 1997 | Rev 0 to Calculation 93C1783.2-03, IPEEE Seismic Fragility (SPRA) Review for Beaver Valley Unit 2 Structures | |
ML20195F211 | 23 January 1997 | Rev 0 to Calculation 93C1783.2-02, IPEEE Fragility Evaluation for Beaver Valley Unit 2 Development of Beaver Valley Unit 2 HCLPFs for Flat Bottom Tanks | |
L-96-021, Rev 0 to RG 1.145 Short-Term Accident X/Q Values for Eab & LPZ Units 1 & 2 Based on 1986-1995 Observations | 19 December 1996 | Rev 0 to RG 1.145 Short-Term Accident X/Q Values for Eab & LPZ Units 1 & 2 Based on 1986-1995 Observations | |
L-96-012, Rev 1 to Unit 1 RCS & SG Isotopic Concentrations,Pre- Incident Spike Concentrations & Iodine Spike Appearance Rates Corresponding to 0.35 & 0.5 Uci/Gm RCS Specific Activity | 19 December 1996 | Rev 1 to Unit 1 RCS & SG Isotopic Concentrations,Pre- Incident Spike Concentrations & Iodine Spike Appearance Rates Corresponding to 0.35 & 0.5 Uci/Gm RCS Specific Activity | |
L-96-011, RCS & SG Isotopic Concentrations,Pre-Incident Spike Concentrations & Iodine Spike Appearance Rates Corresponding to 0.35 & 0.5 Uci/Gm RCS Specific Activity | 19 December 1996 | RCS & SG Isotopic Concentrations,Pre-Incident Spike Concentrations & Iodine Spike Appearance Rates Corresponding to 0.35 & 0.5 Uci/Gm RCS Specific Activity | |
ML20141F302 | 13 December 1995 | Battery Chargers & Inverters Anchorage Evaluation | Earthquake |
ML20141F276 | 30 November 1995 | Anchorage Evaluation for Various Instruments | |
ML20096B435 | 6 November 1995 | SA of Common CR Doses from MSLB Outside of CNMT at U1 W/ Increased Primary-to-Secondary Leakage | Coast down |
ML20141F282 | 30 October 1995 | GE Switchgear Anchorage Evaluation | Earthquake |
ML20141F307 | 1 May 1995 | Anchorage Evaluation for BAT-CHG-2 | |
ML20195F196 | 31 January 1994 | Rev 0 to Calculation 93C1783-13, Seismic Fragility (SPRA) Analysis,Beaver Valley Unit 1,Reactor Coolant Pump | Earthquake |
ML20195F244 | 31 January 1994 | Rev 0 to Calculation 93C1783-07, Seismic Fragility (SPRA) Analysis,Beaver Valley Unit 1 DG,EE-EG-1,2 | |
ML20195F251 | 31 January 1994 | Rev 0 to Calculation 93C1783-40, Seismic Fragility (SPRA) Analysis,Beaver Valley Unit 1 DG Building | Earthquake |
L-89-021, Rev 0123 to ERS-SFL-89-021, Safety Analysis of Dose Consequences of Locked Rotor Accident at Beaver Valley Power Station 1 w/18% Fuel Failure,Exclusion Area Boundary,Low Population Zone,Control Room | 28 July 1989 | Rev 0123 to ERS-SFL-89-021, Safety Analysis of Dose Consequences of Locked Rotor Accident at Beaver Valley Power Station 1 w/18% Fuel Failure,Exclusion Area Boundary,Low Population Zone,Control Room | |
ML20195E098 | 10 May 1988 | Rev 1 to Calculation 456, Combined BV1-BV2 Control Room Habitability Due to Design Bases Accidents (Except LOCA) at BV1 | |
ML20236Y540 | 26 November 1987 | RM-GW-101 Tech Spec Change Justification | |
ML20245C673 | 1 October 1987 | Rev 1 to Calculation 211X-G(B)-290, Differential Settlement of SWS Lines Between Reactor & Safeguards. Oversize Info Encl | |
ML20207F647 | 13 April 1987 | Doses in Combined Unit 1 & 2 CR Due to Waste Gas Sys Rupture at Unit 1 with 500 CFM Normal CR Ventilation | |
ML20151E805 | 2 February 1987 | Settlement of SWS Piping - Intake Structure to Valve Pit. W/Four Oversize Encls |