App B to Rev 1 to Control Sys Power Supply & Sensor Malfunction Study, Control Sys & Safety Functions.ML18040A709 |
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Susquehanna |
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Issue date: |
03/31/1982 |
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From: |
EDS NUCLEAR, INC. |
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Shared Package |
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ML17139B884 |
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References |
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02-0160-1102-AP, 02-0160-1102-R1-APPB, 2-160-1102-AP, 2-160-1102-R1-APPB, NUDOCS 8310180493 |
Download: ML18040A709 (12) |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML17146B1741999-08-0303 August 1999 GL 96-06 Risk Assessment for Sses. ML20195B2381999-03-31031 March 1999 Redacted Version for 10CFR2.790 Request for Decommissioning Status Rept for Sses,Units 1 & 2 ML20217Q4891998-04-21021 April 1998 Rev 1 to Draft LDCN 2482, FSAR Chapter 13.4 & FSAR Chapter 17.2 Changes to Support ITS Implementation ML20155F7661996-07-25025 July 1996 Partially Deleted Job Number 739619-96, Investigation of E Diesel Breaker Misalignment ML20155F7491996-07-24024 July 1996 Independent Safety Evaluation Svcs Project Rept 3-96, Investigation of E Diesel Generator In-Operability Event ML17164A6631995-04-11011 April 1995 Impact of Extending T-10 AOT from 3 to 7 Days. ML18026A5351994-10-31031 October 1994 SSES Unit 1 & 2 MSIV Leakage Alternate Treatment Method Seismic Evaluation. W/One Oversize Drawing ML17158A1631993-12-0909 December 1993 Remote Indication of Spent Fuel Pool Level & Temperature. ML18026A4281993-08-16016 August 1993 PP&L Response to NRC Concerns Re Loss of Spent Fuel Pool Cooling Following Loca,Sses,Units 1 & 2. ML17157C1421992-10-21021 October 1992 Engineering Assessment of Fuel Pool Cooling Piping EDR-G20020. ML17157C1401992-08-31031 August 1992 Review of Fuel Pool Cooling During Postulated Off-Normal & Accident Events SSES Units 1 & 2. ML17157C1411992-08-31031 August 1992 Loss of Fuel Pool Cooling Event Evaluation. ML20082C4941992-08-14014 August 1992 Evaluation of Unit 1 & Unit 2 Derating of Power Cables in Raceways Wrapped W/Thermo-Lag Matl ML17157C1381992-07-27027 July 1992 Safety Consequences of Boiling Spent Fuel Pool at Susquehanna Steam Electric Station. ML17157B0971990-11-0505 November 1990 COTTAP-2,Rev 1 Theory & Input Description Manual. ML20065L6651990-10-31031 October 1990 Environ Qualification Analysis of 250 Volt DC Limitorque Motor Operators for Valves Located Outside Containment of Susquehanna Steam Electric Station ML17157A4211990-08-31031 August 1990 Analysis of Pitting Corrosion Failures in ESW Sys RHR Lube Oil Coolers & RCIC Pump Room Unit Coolers at Susquehanna Steam Electric Station. ML17157A2171990-05-0303 May 1990 Rev 1 to SEA-EE-183, Evaluation of Unit 1 Computer Class 1E - Non-Class 1E Interfaces. ML17157A2191990-05-0303 May 1990 Rev 1 to SEA-EE-184, Evaluation of Unit 1 Annunciator Class 1E - Non-Class 1E Interfaces. ML17157A2201990-05-0303 May 1990 Rev 1 to SEA-EE-226, Evaluation of Welded Shut Class 1E Limitorque Limit Switches Used for Unit 2 Computer Inputs. ML17157A2221990-04-17017 April 1990 Rev 0 to SEA-EE-235, Evaluation of Potential High Voltage Sources Into Unit 1 & 2 Computers. ML17157A2211990-04-12012 April 1990 Rev 0 to SEA-EE-231, Evaluation of Welded Contacts of Class 1E Circuit Breaker Auxiliary Switches & Limit Switches Used for Unit 2 & Common Annunciator Inputs. ML20005F9831990-01-0505 January 1990 Rev 0 to Analysis of B & C 1989 Diesels Failure. ML20235Z1801989-01-31031 January 1989 Rev 2 to Pennsylvania Power & Light Co Approach to Risk Mgt & Risk Assessment ML17156A6921988-07-31031 July 1988 CRD Housing Cap Screw Corrosion. ML17146B0951987-11-30030 November 1987 Rev 1 to Susquehanna Unit 2 Cycle 3 Reload Analysis Design & Safety Analyses. ML17146B0941987-11-30030 November 1987 Rev 1 to Susquehanna Unit 2 Cycle 3 Plant Transient Analysis. ML18040A8521987-08-31031 August 1987 Suppl 4 to Evaluation of Selected Fire Door & Door Frame Assemblies, Technical Rept ML17146B0101987-05-31031 May 1987 Suppl 3 to Evaluation of Selected Fire Door Frame Assemblies, Technical Rept ML17146B0091986-06-30030 June 1986 Suppl 2 to Evaluation of Selected Fire Door & Door Frame Assemblies, Technical Rept ML18040B1191985-08-31031 August 1985 Suppl 1 to Evaluation of Selected Fire Door & Door Frame Assemblies. ML18040B1291985-04-17017 April 1985 Fact-Finding Rept on Air Duct Penetrations Through 1 H Fire Resistive Wall Assembly. ML20102C2131985-03-0101 March 1985 Detailed Control Room Design Review Supplementary Summary Rept ML18040A7861985-01-31031 January 1985 Evaluation of Selected Fire Door & Door Frame Assemblies, Technical Rept ML20092J2391984-06-0606 June 1984 Investigation of Unit 2 Power Transient of 840528. Related Info Encl ML20091B3401984-02-10010 February 1984 Reactor Mode Switch Functional Testing & Wear Characteristics Evaluation, Final Rept ML18040B0231983-09-0909 September 1983 Rev 4 to Equipment Qualification Rept. ML20023D1651983-04-29029 April 1983 Reactor Mode Switch Failure Modes & Mechanisms, Final Rept ML18031A4071982-10-27027 October 1982 Addendum to Final Rept Independent Design Review- Susquehanna Steam Electric Station. ML17139B0421982-08-24024 August 1982 Suppl to Investigation of Unit 1 Small Piping Sys Design Installation & Insp Program Adequacy & Implementation. Viewgraphs Encl ML17139B0401982-08-23023 August 1982 Investigation of Unit 1 Small Piping Sys Design Installation & Insp Program Adequacy & Implementation. ML18031A3861982-07-23023 July 1982 Pool Swell Forcing Functions for Mark II Wetwell-to-Drywell Vacuum Breakers. ML20050C2991982-04-30030 April 1982 Design Assessment Rept, Vol 2,Revision 6 ML17139B8881982-03-31031 March 1982 App D to Rev 1 to Control Sys Power Supply & Sensor Malfunction Study, Commonality Diagrams. ML17139B8851982-03-31031 March 1982 Rev 1 to Control Sys Power Supply & Sensor Malfunction Study. ML17139B8901982-03-31031 March 1982 App E to Rev 1 to Control Sys Power Supply & Sensor Malfunction Study, Failure Modes & Effects Analysis. ML17139B8911982-03-31031 March 1982 App F to Rev 1 to Control Sys Power Supply & Sensor Malfunction Study, Malfunction Analysis Tables. ML18040B0271982-03-31031 March 1982 App C to Rev 1 to Control Sys Power Supply & Sensor Malfunction Study, Control Sys Identification Diagrams. W/Five Oversize Diagrams.Aperture Cards Are Available in PDR ML18040A7091982-03-31031 March 1982 App B to Rev 1 to Control Sys Power Supply & Sensor Malfunction Study, Control Sys & Safety Functions. 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML17146B1741999-08-0303 August 1999 GL 96-06 Risk Assessment for Sses. ML20206D3331999-04-27027 April 1999 SER of Individual Plant Examination of External Events Submittal on Susquehanna Steam Electric Station,Units 1 & 2. Staff Notes That Licensee IPEEE Complete with Regard to Info Requested by Suppl 4 to GL 88-20 ML20195B2381999-03-31031 March 1999 Redacted Version for 10CFR2.790 Request for Decommissioning Status Rept for Sses,Units 1 & 2 ML17164A8451998-10-31031 October 1998 SSES Unit 1 Tenth Refueling & Insp Outage ISI Outage Summary Rept. ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps ML20217Q4891998-04-21021 April 1998 Rev 1 to Draft LDCN 2482, FSAR Chapter 13.4 & FSAR Chapter 17.2 Changes to Support ITS Implementation ML18026A4931998-03-30030 March 1998 LER 97-007-01:on 971017,entry Into TS 3.0.3 Occurred to Allow Completion of Surveillance Testing of One Channel of Rbm.Caused by Failure of Components in LPRM Output to Rbm. Submitted TS Change Request to Extend LCO Action Statement ML18026A5401998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Susquehanna Steam Electric Station.W/980313 Ltr ML18026A4891997-11-17017 November 1997 LER 97-007-00:on 971017,TS 3.0.3 Entry Voluntarily Made. Caused by Inadequate Post Maint Testing Following Earlier Work Associated W/Components.Failed Components Repaired, Replaced & Testing Completed ML18017A2921997-10-28028 October 1997 1997 Nrc/Fema Observed Exercise. ML17158C1861997-06-0505 June 1997 Proceedings of Intl Topical Meeting on Advanced Reactors Safety Vol II, on 970601-05 ML20140A9661997-05-29029 May 1997 Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum ML18026A4781997-03-28028 March 1997 Rev 1 to Application of Anfb to ATRIUM-10 for Susquehanna Reloads. ML20137G6261997-03-25025 March 1997 Svcs Part 21 Rept Re Emergency Generators Installed at Zion Station Which Developed Significant Drop in Crankcase Lube Oil Level.Caused by Crack in Liner Wall,Allowing Jacket Water to Enter Chamber ML20155F7661996-07-25025 July 1996 Partially Deleted Job Number 739619-96, Investigation of E Diesel Breaker Misalignment ML20155F7491996-07-24024 July 1996 Independent Safety Evaluation Svcs Project Rept 3-96, Investigation of E Diesel Generator In-Operability Event ML20117G4641996-05-14014 May 1996 Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs ML18026A5961996-01-0202 January 1996 LER 95-013-00:on 951119,thermally Induced Pressure Locking of HPCI Valve Occurred Under Bonnet Pressure of 3,000-7,000 Psig.Damaged HPCI Injection Valve repaired.W/960102 Ltr ML18017A0511995-11-30030 November 1995 Monthly Operating Repts for Nov 1995 for SSES Units 1 & 2. W/951215 Ltr ML20092H7641995-08-31031 August 1995 Monthly Operating Repts for Aug 1995 for Susquehanna Ses ML17158A8771995-08-15015 August 1995 Exercise Manual. ML17158A8061995-07-14014 July 1995 Books 1 & 2 of ISI Outage Summary Rept SSES Unit 1 8th Refuel Outage. ML18017A0461995-07-0707 July 1995 LER 95-008-00:on 950609,shift Average Licensed Core Thermal Power Was Exceeded.Caused by Failed Instrumentation Drift. Repaired & Recalibrated Subject Instrumentation ML17164A6631995-04-11011 April 1995 Impact of Extending T-10 AOT from 3 to 7 Days. ML17164A5871995-01-31031 January 1995 Monthly Operating Repts for Jan 1995 for Susquehanna Ses ML18026A5351994-10-31031 October 1994 SSES Unit 1 & 2 MSIV Leakage Alternate Treatment Method Seismic Evaluation. W/One Oversize Drawing ML17158A4821994-08-23023 August 1994 ISI Outage Summary Rept Unit 2 6th Refueling Outage, Books 1 & 2 of 2 ML17158A2391994-04-0505 April 1994 Books 1 & 2 of SSES Unit 1 Seventh Refueling & Insp Outage ISI Outage Summary Rept. ML18017A2701993-12-31031 December 1993 PP&L Annual Rept 1993. ML17158A2651993-12-31031 December 1993 Allegheny Electric Cooperative,Inc Annual Rept 1993. ML17158A1631993-12-0909 December 1993 Remote Indication of Spent Fuel Pool Level & Temperature. ML18026A4281993-08-16016 August 1993 PP&L Response to NRC Concerns Re Loss of Spent Fuel Pool Cooling Following Loca,Sses,Units 1 & 2. ML18026A4261993-06-0909 June 1993 LER 90-007-01:on 900705,primary Power Supply to RPS a Power Distribution Panel Lost When One Electrical Protection Assembly (EPA) Breaker Tripped.Epa Logic Cards Reviewed & RPS Power Supply Will Be redesigned.W/930609 Ltr ML17157C2441993-02-28028 February 1993 Monthly Operating Rept for Feb 1993 for Susquehanna Steam Electric Station,Units 1 & 2 ML18017A2031993-02-0101 February 1993 Books 1 & 2 of Unit 2 Fifth Refueling & Insp Outage,Isi Outage Summary Rept. ML20044C2741993-01-31031 January 1993 Corrected Monthly Operating Rept for Jan 1993 for Susquehanna Steam Electric Station,Unit 2,consisting of Info on Unit Shutdowns & Power Reductions ML17157C3691992-12-31031 December 1992 PP&L Annual Rept 1992. ML20056C3941992-12-31031 December 1992 Allegheny Electric Cooperative,Inc Annual Rept 1992 ML18017A0421992-12-14014 December 1992 Suppl to 921127 Part 21 Rept Re High Air Concentration in Reactor Bldg Making Area Uninhabitable for Retrieving Air Filters,Per NUREG-0737,Item II.F.1.Util Current Position Re Fuel Pool Cooling Issues Contrary to Reg Guide 1.3 ML18026A2481992-11-27027 November 1992 Part 21 Rept Re Substantial Safety Hazard in Design of Facility for Loss of Normal Spent Fuel Pool Cooling ML18026A4231992-11-17017 November 1992 LER 92-016-00:on 920416,discovered That Existing Analysis for Two Spent Fuel Storage Pools Did Not Reflect Current Fuel Design & Plant Operation.Caused by Failure to Modify FSAR Analysis.Fsar Will Be revised.W/921117 Ltr ML17157C1421992-10-21021 October 1992 Engineering Assessment of Fuel Pool Cooling Piping EDR-G20020. ML17157C1411992-08-31031 August 1992 Loss of Fuel Pool Cooling Event Evaluation. ML17157C1401992-08-31031 August 1992 Review of Fuel Pool Cooling During Postulated Off-Normal & Accident Events SSES Units 1 & 2. ML20082C4941992-08-14014 August 1992 Evaluation of Unit 1 & Unit 2 Derating of Power Cables in Raceways Wrapped W/Thermo-Lag Matl ML17157C1381992-07-27027 July 1992 Safety Consequences of Boiling Spent Fuel Pool at Susquehanna Steam Electric Station. ML17157B9331992-07-24024 July 1992 Sixth Refueling & Insp Outage Inservice Insp Outage Summary Rept, Books 1 & 2 ML20097D4681991-12-31031 December 1991 Pennsylvania Power & Light Company,1991 Annual Rept ML18017A0391991-07-26026 July 1991 LER 91-010-00:on 910628,RWCU Isolated on Two Occassions Due to Actuations of Steam Leak Detection Instrumentation. Caused by Design Deficiency & Elevated Ambient Penetration Room Temps.Temp Modules replaced.W/910726 Ltr 1999-09-30
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Text
Report No. 02-0160-1102 Revision 0 APPENDIX B CONTROL SYSTEMS AND SAFETY FUNCTXONS 83iOi80493 83iOi4 PDR ADOCK 05000387 PDR.
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Report No. 02-0160-1102 Revision 0 CONTROL SYSTEMS
- 1. Reactor Manual Control System
- 2. Recirculation Flow Control System
- 3. Reactor Feedwater Control System
- 4. Pressure Regulator and Turb'ine Generator Contxol System
- 5. Traversing In-Core Probe Control System
- 6. Reactor Water Cleanup Control System
- 7. Refueling Interlock Control System
- 8. Rod Block Monitor System
- 9. Nuclear Pressure Relief Control System 26
Core C Radio Mater:
Store Contr React Isola Contr Isolc Rod Reac Cont Rest powe Cont Coo Cont Env:
Con'
Report No. 02-0160-1102 Revision 0 PLANT OPERATING MODE STATE A (Conte)
Reactor Shutdown/Head Off SAFETY FUNCTIONS Title Descri tion Reference Secondary Secondary containment isola- SSES FSAR 15A. 6. 5. 3 Containment tion to minimize radiological Event 41 Isolation effects Radwaste Bldg. Radwaste system building SSES FSAR 15A.6.5.3 Isolation isolation to minimize radi- Event 48 ological effects Liquid Efflu- Liquid effluent system iso- SSES FSAR 15A.6.5.3 ent Isolation lation to minimize radio- Event 48 logical effects 28
Report No. 02-0160-1102 Revision 0 PLANT OPERATING MODE STATE B Reactor Not Shutdown/Head Off SAFETY FUNCTIONS Title Descri tion Reference SCRAM Control rod insertion to SSES FSAR 15A.6.3 prevent fuel damage Events 7, 16 Core Cooling Initial and extended safety- SSES FSAR 15A. 6. 3 grade core cooling to pre-vent fuel damage Event 18 Radioactive Radioactive material release SSES FSAR 15A. 6. 5 Material control to minimize radio- Events 48, 49 logical effects Stored Fuel Stored fuel cooling and SSES FSAR 15A.6.2.3.14 Control reactivity control to pre-vent stored fuel damage Reactor Vessel Reactor Pressure Vessel SSES FSAR 15A.6.3 Isolation Isolation to prevent fuel Events 18, 28, 29 damage Containment Primary Containment Isola- SSES FSAR 15A.6.3 Isolation tion to minimize radiologi- Events 28, 29 cal effects Prohibit Rod Prevention of adverse rod SSES FSAR 15.4.1 Motion motion to prevent exceeding and 15A.6.3, Event 17 fuel limits Reactivity Core nuclear reactivity SSES FSAR 15A. 6. 3 Control control to prevent fuel Events 28, 29 damage Restore AC Establishing on-site or SSES FSAR 15A.6.3 Power off-site AC Power for safety Event 29 systems to prevent fuel damage Containment Initial and extended primary SSES FSAR 15A.6.3 Cooling 'ontainment cooli'ng to pre- Events 28, 29 vent containment damage e? I 29
Report No. 02-0160-1102 Revision 0 PLANT OPERATING MODE STATE B (Cont.)
Reactor Not Shutdown/Head Off SAFETY FUNCTIONS Title Description Reference Control Room Conditioning of Control SSES FSAR 15A.6 ~ 5 Environmental Room environment to prevent Event 41 Control personnel overexposure Secondary Secondary containment iso- SSES FSAR 15A.6.5 Containment lation to minimize radio- Event 41 Isolation logical effects Radwaste Radwaste system building SSES FSAR 15A.6.5 Building isolation to minimize Event 48
.Isolation radiological effects J
Liquid Efflu- Liquid effluent system iso- SSES FSAR 15A.6.5 Isolation lation to minimize radio- Event 48 e ent logical effects 30
Report No. 02-0160-1102
.Revision 0 PLANT OPERATING MODE STATE C Reactor Shutdown/Head On SAFETY FUNCTIONS Title Descri tion Reference SCRAM Control rod insertion to SSES FSAR 15A.6.3 prevent fuel damage Events 7, 15, 24, 43, 44'5, 47 Pressure Nuclear Steam Supply System SSES FSAR 15A.6.3 Relief Pressure relief to prevent Events 8 I 11 14 15 excessive pressure 20I 22'4~ 26'8I 29~ 42'1 g 52~ 53 Core Initial and extended safety- SSES FSAR 15A.6.3 Cooling grade core cooling to prevent Events 8, 12, 14, 15, fuel 18I 20 I 22~ 23'4~
damage 28I 29'2'3'4~
45, 51, 53 Radioactive Radioactive material release SSES FSAR 15A.2.3.1 Material control to minimize radio-logical effects Stored Fuel Stored tionn fuel cooling and SSES FSAR 15A.6.2.3.14 Control reactivity control to pre-vent stored fuel damage Reactor Reactor Pressure Vessel SSES FSAR 15A.6.3 Vessel Isolation to prevent fuel Events 12, 15, 18, 20, Isolation damage 22'3'4'8145 29'3'4, Containment Primary Containment Isola- SSES FSAR 15A. 6.3 Isolation to minimi z'e r adio log i- Events 15, 26, 28, 29, cal effects 42 Prohibit Rod Prevention of adverse rod SSES FSAR 15A.6.3 Motion motion to prevent exceeding fuel limits Reactivity Core nuclear reactivity SSES FSAR 15A.6.3 Control control to prevent fuel Events 20, 28 damage 31
Report No. 02-0160-1102 Revision 0 PLANT OPERATING MODE STATE C (Cont.)
Reactor Shutdown/Head On SAFETY FUNCTIONS Title Descri tion Reference Restore AC Establishing on-site or off- SSES FSAR 15A.6.3 Power site AC Power for safety sos- Event 29P tems to prevent fuel damage Containment Initial and extended primary SSES FSAR 15A.6.3 Cooling containment cooling to pre-vent containment damage Control Room Conditioning of Control Room SSES FSAR 15A.6.5 Environmental environment to prevent per- Events 41, 42 Control sonnel overexposure Secondary Secondary containment isola- SSES FSAR 15A.6.5g Containment tion to minimize radiological 15A.'6.6 Isolation effects Events 41, 42, 50 Suppression Limit contamination release SSES FSAR 15A.6.5 Pool to environment Event 42 Stop Rod Control rod drive processing SSES FSAR 15A.6.5 Ejection support to prevent fuel Event 42 cladding failure Off-Gas System Off-Gas System isolation to SSES FSAR 15A.6.5 Isolation minimize radiological effect Events 46, 47 Radwaste Limit contamination release SSES FSAR 15A.6.5 Building Iso. to environment Events 48, 49 Liquid Efflu- Liquid effluent system iso- SSES FSAR 15A.6.5 ent Isolation lation to minimize radio- Events 48, 49 logical effects 32
Report No. 02-0160-1102 Revision 0 PLANT OPERATING MODE STATE D Reactor .Not Shutdown/Head On SAFETY FUNCTIONS Title Descri tion Reference SCRAM Control rod insertion to SSES FSAR 15A.6.5 prevent fuel damage Event 42 Recirculation Recirculation pump trip .to SSES FSAR 15A.6.5 Pump Trip prevent fuel damage Event 42 Pressure Nuclear Steam Supply System SSES FSAR 15A.6.5 Relief Pressure relief to prevent Event 42 excessive pressure Core Cooling Initial and extended safety- SSES FSAR 15A.6.5 grade core cooling to prevent Event 42 fuel damage Radioactive
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Radioactive material release SSES FSAR 15A.6.5 Material
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control to minimize radio- Events 48, 49 logical effects Stored Fuel Stored fuel cooling and SSES FSAR 15A.6.2.3.14 Control reactivity control to prevent stored fuel damage Reactor Vessel Reactor Pressure Vessel SSES FSAR 15A. 6. 5 Isolation Isolation to prevent fuel Event 43 damage Containment Primary Containment Isola- SSES FSAR 15A.6 Isolation tion to minimize radiologi- Event 42 cal effects.
Prohibit Rod Prevention of adverse rod SSES FSAR 15.6.3 Motion motion to prevent exceeding Event 17.
fuel limits Reactivity Core nuclear reactivity con- SSES FSAR 15A.6.3 Control trol to prevent fuel damage Event 29 Restore AC Establishing on-site or off- SSES FSAR 15A.6.3
- Power site AC Power for safety sys- Event 29 tems to prevent fuel damage 33 ~
Report No. 02-0160-1102 Revision 0 PLANT OPERATING MODE STATE D (Cont.)
Reactor Not Shutdown/Head On SAFETY FUNCTIONS Title Descri tion Reference Containment Initial and extended primary SSES FSAR 15A.6.5 Cooling containment cooling to pre- Event 42 vent containment damage Limit Reac- Passive control rod velocity SSES FSAR 15A.6.5 tivity Inser- limiter to prevent fuel Event 40 tion Rate cladding failure Control . Room Conditioning of Control Room SSES FSAR 15A.6.5 Environmental environment to prevent per- Event 42 Control sonnel overexposure Secondary Secondary containment iso- SSES FSAR 15A.6.5 Containment lation tominimize radiologi- Event 42 Isolation cal effects Restrict Loss Flow restrictors limiting SSES FSAR 15A.6.5 of Reactor reactor coolant loss to Events 43, 44, 45 Coolant prevent fuel damage Of f-Gas Sys- Off-Gas System isolation to SSES FSAR 15A.6.5 tem Isolation minimize radiological ef fect Events 46, 47 Radwaste. Radwaste system building SSES FSAR'15A.6.5 Building isolation to minimize radio- Event 48 Isolation logical effects Liquid Efflu- Liquid effluent system iso-' SSES FSAR 15A.6.5 ent Isolation lation to minimize radiologi- Event 48 cal effects Stop Rod Control rod drive processing. SSES FSAR 15A.6.5 Ejection support to prevent fuel Event 42 cladding failure 34