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Category:ARCHIVE RECORDS
MONTHYEARL-94-014, Rev 1 to Safety Analysis of Radiological Consequences of SBLOCA at U2 with Delayed CNMT Spray Actuation & NUREG-1465 Core Damage Progression1998-01-30030 January 1998
Rev 1 to Safety Analysis of Radiological Consequences of SBLOCA at U2 with Delayed CNMT Spray Actuation & NUREG-1465 Core Damage Progression
ML20195D0221998-01-26026 January 1998
Rev 1 to Assessment of Doses in Unit 2 CR Due to Locked Rotor Accident at Unit 2 Assuming 18% Failed Fuel
ML20195C6421998-01-16016 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
ML20217J8361997-10-0202 October 1997
Rev 1 to DE&S-SR/EM01, Ampacity Derating Factors of Fire- Protected Conduits
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)1997-02-25025 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 Leakage1997-02-24024 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
ML20195F2321997-01-24024 January 1997
Rev 0 to Calculation 93C1783.2-03, IPEEE Seismic Fragility (SPRA) Review for Beaver Valley Unit 2 Structures
ML20195F2111997-01-23023 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
ML20133F3281997-01-13013 January 1997
Press Release I-97-03, NRC Staff to Meet W/Officials of Dl to Discuss Apparent Violations at Bvnp
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 Activity1996-12-19019 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 Activity1996-12-19019 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-96-021, Rev 0 to RG 1.145 Short-Term Accident X/Q Values for Eab & LPZ Units 1 & 2 Based on 1986-1995 Observations1996-12-19019 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
ML20134L2991996-11-20020 November 1996
Press Release I-96-75, Bvnp Rated 'Good' in Three Areas, 'Superior' in Fourth Area of NRC Assessment Rept
ML20134D2211996-10-17017 October 1996
Press Release 96-145, NRC Asks Utility Licensees for Info on Concrete Containment Foundations at Nine Nuclear Plants
ML20141F3021995-12-13013 December 1995
Battery Chargers & Inverters Anchorage Evaluation
ML20141F2761995-11-30030 November 1995
Anchorage Evaluation for Various Instruments
ML20096B4351995-11-0606 November 1995
SA of Common CR Doses from MSLB Outside of CNMT at U1 W/ Increased Primary-to-Secondary Leakage
ML20141F2821995-10-30030 October 1995
GE Switchgear Anchorage Evaluation
ML20141F3071995-05-0101 May 1995
Anchorage Evaluation for BAT-CHG-2
ML20195F1961994-01-31031 January 1994
Rev 0 to Calculation 93C1783-13, Seismic Fragility (SPRA) Analysis,Beaver Valley Unit 1,Reactor Coolant Pump
ML20195F2441994-01-31031 January 1994
Rev 0 to Calculation 93C1783-07, Seismic Fragility (SPRA) Analysis,Beaver Valley Unit 1 DG,EE-EG-1,2
ML20195F2511994-01-31031 January 1994
Rev 0 to Calculation 93C1783-40, Seismic Fragility (SPRA) Analysis,Beaver Valley Unit 1 DG Building
ML20128E3111992-11-17017 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
ML20079N0931989-12-31031 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
ML20127C7441989-11-0808 November 1989
Partially Deleted Incident Rept 1-89-97 Dose Assessments & Associated Hpes Involvong Rj Brooks & Assoc Steam Generator Fosar Activities at Facility
ML20247N1491989-09-26026 September 1989
Handout on Beaver Valley Unit 2 MSIV Mod & Test Program
ML20127A5651989-09-11011 September 1989
Package of Handwritten Radiological Work Sheets Re Steam Generator Annulus Secondary Side Hand Hole Insps
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 Room1989-07-28028 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
ML20195E0981988-05-10010 May 1988
Rev 1 to Calculation 456, Combined BV1-BV2 Control Room Habitability Due to Design Bases Accidents (Except LOCA) at BV1
ML20236Y5401987-11-26026 November 1987
RM-GW-101 Tech Spec Change Justification
ML20245C6731987-10-0101 October 1987
Rev 1 to Calculation 211X-G(B)-290, Differential Settlement of SWS Lines Between Reactor & Safeguards. Oversize Info Encl
ML20151M9601987-07-20020 July 1987
Package of NRC Administered Requalification Exam Results Summary
ML20207F6471987-04-13013 April 1987
Doses in Combined Unit 1 & 2 CR Due to Waste Gas Sys Rupture at Unit 1 with 500 CFM Normal CR Ventilation
ML20151E8051987-02-0202 February 1987
Settlement of SWS Piping - Intake Structure to Valve Pit. W/Four Oversize Encls
ML20203H2851986-07-28028 July 1986
Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131
IA-86-445, Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 8201311986-07-28028 July 1986
Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131
ML20204J1551986-07-0707 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
ML20129F4831985-05-0909 May 1985
Package of Compilations of Results of Operator Licensing & Requalification Exams
ML20079F1761984-01-13013 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
ML20133N1301979-04-10010 April 1979
Record of 790320 Telcon W/D Ford of Ucs Re Participation in Facility Pipe Stress Issue
1998-01-30
[Table view]
Category:OPERATIONS SUPPORT-CALCULATIONS
MONTHYEARL-94-014, Rev 1 to Safety Analysis of Radiological Consequences of SBLOCA at U2 with Delayed CNMT Spray Actuation & NUREG-1465 Core Damage Progression1998-01-30030 January 1998
Rev 1 to Safety Analysis of Radiological Consequences of SBLOCA at U2 with Delayed CNMT Spray Actuation & NUREG-1465 Core Damage Progression
ML20195D0221998-01-26026 January 1998
Rev 1 to Assessment of Doses in Unit 2 CR Due to Locked Rotor Accident at Unit 2 Assuming 18% Failed Fuel
ML20195C6421998-01-16016 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
ML20217J8361997-10-0202 October 1997
Rev 1 to DE&S-SR/EM01, Ampacity Derating Factors of Fire- Protected Conduits
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)1997-02-25025 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 Leakage1997-02-24024 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
ML20195F2321997-01-24024 January 1997
Rev 0 to Calculation 93C1783.2-03, IPEEE Seismic Fragility (SPRA) Review for Beaver Valley Unit 2 Structures
ML20195F2111997-01-23023 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 Observations1996-12-19019 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 Activity1996-12-19019 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 Activity1996-12-19019 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
ML20141F3021995-12-13013 December 1995
Battery Chargers & Inverters Anchorage Evaluation
ML20141F2761995-11-30030 November 1995
Anchorage Evaluation for Various Instruments
ML20096B4351995-11-0606 November 1995
SA of Common CR Doses from MSLB Outside of CNMT at U1 W/ Increased Primary-to-Secondary Leakage
ML20141F2821995-10-30030 October 1995
GE Switchgear Anchorage Evaluation
ML20141F3071995-05-0101 May 1995
Anchorage Evaluation for BAT-CHG-2
ML20195F1961994-01-31031 January 1994
Rev 0 to Calculation 93C1783-13, Seismic Fragility (SPRA) Analysis,Beaver Valley Unit 1,Reactor Coolant Pump
ML20195F2441994-01-31031 January 1994
Rev 0 to Calculation 93C1783-07, Seismic Fragility (SPRA) Analysis,Beaver Valley Unit 1 DG,EE-EG-1,2
ML20195F2511994-01-31031 January 1994
Rev 0 to Calculation 93C1783-40, Seismic Fragility (SPRA) Analysis,Beaver Valley Unit 1 DG Building
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 Room1989-07-28028 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
ML20195E0981988-05-10010 May 1988
Rev 1 to Calculation 456, Combined BV1-BV2 Control Room Habitability Due to Design Bases Accidents (Except LOCA) at BV1
ML20236Y5401987-11-26026 November 1987
RM-GW-101 Tech Spec Change Justification
ML20245C6731987-10-0101 October 1987
Rev 1 to Calculation 211X-G(B)-290, Differential Settlement of SWS Lines Between Reactor & Safeguards. Oversize Info Encl
ML20207F6471987-04-13013 April 1987
Doses in Combined Unit 1 & 2 CR Due to Waste Gas Sys Rupture at Unit 1 with 500 CFM Normal CR Ventilation
ML20151E8051987-02-0202 February 1987
Settlement of SWS Piping - Intake Structure to Valve Pit. W/Four Oversize Encls
1998-01-30
[Table view] |
Text
4 Client: Da g u e e,m Li, M /PL C, J ,, c , Calculation No. 92c / 7 eJ o 7
Title:
5 e ; s m ;r p,.. ; ll 4 v (SPRA) A n a Iv.r; r s , - - Beaver l/o lle,v /An;f #/
D;e se l G r ee > olo < EE- fn- 1,2 Project: BEAVGR VALLEY FR A n tL tiv A A)A L Yl lJ FOR INPrviouAL PLA NT E VA Me dA TIONS POR Pu TE R NAL E VE M TJ _
Method:
Acceptance Criteria:
i Remarks:
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i
- ATTACHMENT G 4
l Fragility Calculation for BVPS-1 Emergency Diesel Generator Building i
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