Semantic search
Jump to navigation
Jump to search
| Issue date | Title | Topic | |
|---|---|---|---|
| IA-86-445, Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131 | 28 July 1986 | Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131 | Hydrostatic |
| 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 | |
| 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 | |
| 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 |
| 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-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 | |
| 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-96-021, 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 | |
| ML20079F176 | 13 January 1984 | Amended Slides & Diagrams Utilized During 831220 Meeting W/Nrc Re Cable Separation Program.W/One Oversize Figure. Aperture Card Is Available in PDR | Coatings |
| ML20079N093 | 31 December 1989 | Response to Questions Re Beaver Valley Unit 1 Impingement, Entrainment Monitoring rept,890131 Observation of Gizzard Shad Discharge of BVPS,1983 Annual Environment Rept Nonradiological | |
| ML20096B435 | 6 November 1995 | SA of Common CR Doses from MSLB Outside of CNMT at U1 W/ Increased Primary-to-Secondary Leakage | Coast down |
| ML20127A565 | 11 September 1989 | Package of Handwritten Radiological Work Sheets Re Steam Generator Annulus Secondary Side Hand Hole Insps | |
| ML20127C744 | 8 November 1989 | Partially Deleted Incident Rept 1-89-97 Dose Assessments & Associated Hpes Involvong Rj Brooks & Assoc Steam Generator Fosar Activities at Facility | |
| ML20128E311 | 17 November 1992 | Package Consisting of Insp Rept 50-344/PA-92-02 on 921021- 22.No Violations Noted.Major Areas Inspected:Shipping Documentation,Packaging/Package Insp,Labeling,Marking, Placarding,Vehicle Insp,Radiation & Contamination Surveys | |
| ML20129F483 | 9 May 1985 | Package of Compilations of Results of Operator Licensing & Requalification Exams | |
| ML20133F328 | 13 January 1997 | Press Release I-97-03, NRC Staff to Meet W/Officials of Dl to Discuss Apparent Violations at Bvnp | |
| ML20133N130 | 10 April 1979 | Record of 790320 Telcon W/D Ford of Ucs Re Participation in Facility Pipe Stress Issue | |
| ML20134D221 | 17 October 1996 | Press Release 96-145, NRC Asks Utility Licensees for Info on Concrete Containment Foundations at Nine Nuclear Plants | |
| ML20134L299 | 20 November 1996 | Press Release I-96-75, Bvnp Rated 'Good' in Three Areas, 'Superior' in Fourth Area of NRC Assessment Rept | Missed surveillance Systematic Assessment of Licensee Performance |
| ML20141F276 | 30 November 1995 | Anchorage Evaluation for Various Instruments | |
| ML20141F282 | 30 October 1995 | GE Switchgear Anchorage Evaluation | Earthquake |
| ML20141F302 | 13 December 1995 | Battery Chargers & Inverters Anchorage Evaluation | Earthquake |
| ML20141F307 | 1 May 1995 | Anchorage Evaluation for BAT-CHG-2 | |
| ML20151E805 | 2 February 1987 | Settlement of SWS Piping - Intake Structure to Valve Pit. W/Four Oversize Encls | |
| ML20151M960 | 20 July 1987 | Package of NRC Administered Requalification Exam Results Summary | |
| 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 | |
| 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 | |
| ML20195E098 | 10 May 1988 | Rev 1 to Calculation 456, Combined BV1-BV2 Control Room Habitability Due to Design Bases Accidents (Except LOCA) at BV1 | |
| ML20195F196 | 31 January 1994 | Rev 0 to Calculation 93C1783-13, Seismic Fragility (SPRA) Analysis,Beaver Valley Unit 1,Reactor Coolant Pump | Earthquake |
| 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 | |
| ML20195F232 | 24 January 1997 | Rev 0 to Calculation 93C1783.2-03, IPEEE Seismic Fragility (SPRA) Review for Beaver Valley Unit 2 Structures | |
| 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 |
| ML20203H285 | 28 July 1986 | Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131 | Hydrostatic |
| ML20204J155 | 7 July 1986 | Telcon of Significant Deficiency Rept SDR 86-09 Re Erratic Position Indication from Masoneilan Control Valves.Cause Unstated.Operators May Take Inappropriate Actions Based on Faulty Indication.Indicator Arms Upgraded | |
| 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 | |
| ML20217J836 | 2 October 1997 | Rev 1 to DE&S-SR/EM01, Ampacity Derating Factors of Fire- Protected Conduits | Safe Shutdown Fire Barrier |
| 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 | |
| ML20247N149 | 26 September 1989 | Handout on Beaver Valley Unit 2 MSIV Mod & Test Program |