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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
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ATTACHMENT H 1 i i i
l Detailed Description of the Top 5 i Seismic Core Damage Sequences
,i i
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l Detailed Description of the Top 5 Seismic Core Damage Sequences Seismic Frequency Earthquake Independent CDF per year Acceleration Seismic Failures Guaranteed Failures Non-seismic Operator Action Sequence (Percent of Level (g) Failures Failures / Timing Seismic Total) 1 5.3935E-07 SEIS4 (0.5 - 1.0) . ZC4 - Offsite Grid . OGF- Offsite Grid N/A N/A (10.13%) . ZD4 - Normal AC/DC Power + DSF - 125V DC Battery 2-5 Supply
. ZE4 - Emergency AC Power + D6F - 125V DC Battery 2-6 Supply
+ ZB4 - ERF Diesel Generator . AOF - Emergency AC Orange Train Power . BPF - Emergency AC Purple Train
. XTF - Station AC Power Cross Tie *
. OSF - Operator Initiates Safety injection
. WAF- Service / Standby SW Train-A Pumps &
Flow Path
. WBF- Service / Standby SW Train-B Pumps &
Flow Path
. BKF - ERF (Black) Diesel Generator Power
. CSF - Turbine Plant Component Cooling Water
. IAF - Station instrument Air Supply
. CCF - Primary Component Cooling Water System
. ICF - Containment Instrument Air System
. TBF - RCP Thermal Barrier Cooling
. AFF - Auxiliary Feedwater
. PRF - Pressurizer Relief at:d Reciosure
. OFF - Manual Actions to Reestablish MFW
. OBF - Bleed & Feed Cooling
. HHF - High Head Safety injection Pumps i
. LHF - Low Head Safety injection Pumps
. NRF - Recirculation from sumo not required i
. NMF- No melt condition from injection phase
. QSF - Quench Spray Pumps
. SMF- Containment Sump Water Level, Plugging
. CIF -Containmentisolation ,
. REF - Electric power recovery prior to core uncovery 2 3.6910E-07 SSS4 (0.5 - 1.0) . ZC4 - Offsite Grid . OGF- Offsite Gnd N/A N/A (6.93 %) . ZD4 - Normal AC/DC Power . DSF - 125V DC Battery 2-5 Supply
. ZB4 - ERF Diesel Generator . D6F - 125V DC Battery 2-6 Supply Power . OSF - Operator Initiates Safety injection ;
e WAF- Service / Standby SW Train-A Pumps &
Flow Path
. WBF Service / Standby SW Train-B Pumps &
Detailed Description of the Top 5 Seismic Core Damage Sequences l Seismic Frequency Earthquake Independent #
CDF per year Acceleration Seismic Failures Guaranteed Failures Non-seismic Operator Action Sequence (Percent of Level (g) Failures Failures / Timing Seismic Total)
Flow Path
. BKF - ERF (Black) Diesel Generator Power
. CSF - Turbine Plant Component Cooling Water
. IAF - Station instrument Air Supply
. CCF - Primary Component Cooling Water System
. ICF - Containment instrument Air System
. TBF - RCP Thermal Barrier Cooling *
. AFF - Auxiliary Feedwater
. PRF - Pressurizer Relief and Reciosure
. OFF - Manual Actions to Reestablish MFW
. OBF - Bleed & Feed Cooling
. HHF - High Head Safety injection Pumps
. LHF - Low Head Safety injection Pumps
. NRF - Recirculation from sump not required
. NMF- No melt condition from injection phase
. OSF - Quench Spray Pumps
. SMF - Containment Sump Water Level, Plugging
. CIF -ContainmentIsotation
. REF - Electric power recovery prior to core uncovery 3 2.8510E-07 SEIS3 (0.35 - 0.5) . ZC3 - Offsite Grid . OGF- Offsite Grid N/A N/A (5.35%) . ZE3 - Emergency AC Power . AOF - Emergency AC Orange Train
. ZB3 - ERF Diesel Generator . BPF - Emergency AC Purple Train Power . XTF - Station AC Power Cross Tie
. WAF- Service / Standby SW Train-A Pumps &
Flow Path
. WBF- Service / Standby SW Train-B Pumps &
Flow Path
. BKF - ERF (Black) Diesel Generator Power
. CSF - Turbine Plant Component Cooling Water
. !AF - Station Instrument Air Supply
. CCF - Primary Component Coohng Water System
. ICF - Containment instrument Air System
. TBF - RCP Thermal Barrier Cooling
. HHF - High Head Safety injection Pumps
. SEF - RCP Sealinjection
. LHF - Low Head Safety injection Pumps
. ODF- Depressurization of RCS for RHR Entry i
Detailed Description of the Top 5 Seismic Core Damage Sequences Seismic Frequency Earthquake independent CDF per year Acceleration Seismic Failures Guaranteed Failures Non-seismic Operator Action Sequence (Percent of Level (g) Failures Failures / Timing ,
Seismic Total)
. NRF - Recirculation from sump not required
. NMF- No mert condition from injection phase
. QSF- Quench Spray Pumps
. SMF - Containment Sump Water Level. Plugging
. REF - Electric power recovery prior to core >
uncovery 4 2.1881E-07 SEIS3 (0.35 - 0.5) . ZC3 -Offsite Grid . OGF- Offsite Grid N/A N/A "
(4.11%) . ZD3 -Normal AC/DC Power . D5F - 125V DC Battery 2-5 Supply
. ZE3 - Emergency AC Power . D6F - 125V DC Battery 2-6 Supply
. ZB3 - ERF Diesel Generator . AOF - Emergency AC Orange Train Power . BPF - Emergency AC Purple Train .
. XTF - Station AC Power Cross Tie
. WAF- Service / Standby SW Trasn-A Pumps & L Flow Path
. WBF- Service / Standby SW Train-B Pumps &
Flow Path
. BKF - ERF (Black) Diesel Generator Power
. CSF - Turbirse Plant Component Cooling Water
. IAF - Station Instrument Air Supply
. CCF - Primary Component Cooling Water System
. ICF - Containment Instrument Air System
. TBF - RCP Tiiermal Barrier Cooling I
. HHF - High Head Safety injection Pumps
. SEF - RCP Sealinjection i
. LHF - Low Head Safety injection Pumps
. ODF - Depressurization of RCS for RHR Entry
. NRF - Recirculation from sump not required
. NMF- No melt condition from injection phase
. OSF - Quench Spray Pumps
. SMF - Containment Sump Water Level. Plugging *
- REF - Electric power recovery prior to core uncovery I r
5 2.0439E-07 SETS 4 (0.5 1.0) . ZC4 - Offsite Grid . OGF- Offsite Grid N/A N/A (3.84 %) . ZE4 - Emergency AC Power . AOF- Emergency AC Orange Train !
. ZB4 - ERF Diesel Generator + BPF - Emergency AC Purple Train Power . XTF - Station AC Power Cross Tie :
. OSF - Operator initiates Safety injection !
L i
i
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Detailed Description of the Top 5 Seismic Core Damage Sequences Seismic Frequency Earthquake .
Independent CDF per year Acceleration Selsmic Failures Guaranteed Failures Non-seismic Operator Action Sequence (Percent of Level (g) Failures Failures / Timing .
Seismic Total)
. WAF- Service / Standby SW Train-A Pumps &
Flow Path
. WBF- Service / Standby SW Train-B Pumps &
Flow Path
. BKF - ERF (Black) Diesel Generator Power
. CSF - Turbine Plant Component Cooling Water
. IAF - Station Instrument Air Supply -
. CCF - Primary Component Cooling Water System
. ICF - Containment instrument Air System
. TBF - RCP Thermal Barrier Cooling
. AFF - Auxiliary Feedwater
. PRF - Pressurizer Relief and Reclosure
. OFF - Manual Actions to Reestablish MFW
. OBF- Bleed & Feed Cooling
. HHF - High Head Safety injection Pumps -
. LHF - Low Head Safety injection Pumps
. NRF - Recirculation from sump not required
. NMF- No melt condition from injection phase
. QSF - Quench Spray Pumps
. SMF - Containment Sump Water Level, Ptugging
. CIF - Containment isolation
. REF - Electric power recovery prior to core uncovery I
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