ML18040A709

App B to Rev 1 to Control Sys Power Supply & Sensor Malfunction Study, Control Sys & Safety Functions.

ML18040A709
Person / Time
Site:	Susquehanna
Issue date:	03/31/1982
From:	EDS NUCLEAR, INC.
To:
Shared Package
ML17139B884	List: ML17139B883 ML17139B885 ML17139B887 ML17139B888 ML17139B890 ML17139B891 ML18040A709 ML18040B027
References
02-0160-1102-AP, 02-0160-1102-R1-APPB, 2-160-1102-AP, 2-160-1102-R1-APPB, NUDOCS 8310180493
Download: ML18040A709 (12)

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 Title Secondary Containment Isolation Radwaste Bldg.Isolation Liquid Efflu-ent Isolation SAFETY FUNCTIONS Descri tion Secondary containment isola-tion to minimize radiological effects Radwaste system building isolation to minimize radi-ological effects Liquid effluent system iso-lation to minimize radio-logical effects Reference SSES FSAR 15A.6.5.3 Event 41 SSES FSAR 15A.6.5.3 Event 48 SSES FSAR 15A.6.5.3 Event 48 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 Core Cooling Radioactive Material Stored Fuel Control Reactor Vessel Isolation Containment Isolation Prohibit Rod Motion Reactivity Control Restore AC Power Containment Cooling e?I Control rod insertion to prevent fuel damage Initial and extended safety-grade core cooling to pre-vent fuel damage Radioactive material release control to minimize radio-logical effects Stored fuel cooling and reactivity control to pre-vent stored fuel damage Reactor Pressure Vessel Isolation to prevent fuel damage Primary Containment Isola-tion to minimize radiologi-cal effects Prevention of adverse rod motion to prevent exceeding fuel limits Core nuclear reactivity control to prevent fuel damage Establishing on-site or off-site AC Power for safety systems to prevent fuel damage Initial and extended primary'ontainment cooli'ng to pre-vent containment damage SSES FSAR 15A.6.3 Events 7, 16 SSES FSAR 15A.6.3 Event 18 SSES FSAR 15A.6.5 Events 48, 49 SSES FSAR 15A.6.2.3.14 SSES FSAR 15A.6.3 Events 18, 28, 29 SSES FSAR 15A.6.3 Events 28, 29 SSES FSAR 15.4.1 and 15A.6.3, Event 17 SSES FSAR 15A.6.3 Events 28, 29 SSES FSAR 15A.6.3 Event 29 SSES FSAR 15A.6.3 Events 28, 29 29 Report No.02-0160-1102 Revision 0 PLANT OPERATING MODE Title STATE B (Cont.)Reactor Not Shutdown/Head Off SAFETY FUNCTIONS Description Reference Control Room Environmental Control Secondary Containment Isolation Radwaste Building.Isolation Liquid Efflu-e ent Isolation Conditioning of Control Room environment to prevent personnel overexposure Secondary containment iso-lation to minimize radio-logical effects Radwaste system building isolation to minimize radiological effects J Liquid effluent system iso-lation to minimize radio-logical effects SSES FSAR 15A.6~5 Event 41 SSES FSAR 15A.6.5 Event 41 SSES FSAR 15A.6.5 Event 48 SSES FSAR 15A.6.5 Event 48 30 Report No.02-0160-1102.Revision 0 Title SCRAM Pressure Relief Core Cooling Radioactive Material Stored Fuel Control Reactor Vessel Isolation Containment Isolation Prohibit Rod Motion Reactivity Control PLANT OPERATING MODE STATE C Reactor Shutdown/Head On SAFETY FUNCTIONS Descri tion Control rod insertion to prevent fuel damage Nuclear Steam Supply System Pressure relief to prevent excessive pressure Initial and extended safety-grade core cooling to prevent fuel damage Radioactive material release control to minimize radio-logical effects Stored fuel cooling and reactivity control to pre-vent stored fuel damage Reactor Pressure Vessel Isolation to prevent fuel damage Primary Containment Isola-tionn to minimi z'e r adio log i-cal effects Prevention of adverse rod motion to prevent exceeding fuel limits Core nuclear reactivity control to prevent fuel damage Reference SSES FSAR 15A.6.3 Events 7, 15, 24, 43, 44'5, 47 SSES FSAR 15A.6.3 Events 8 I 11 14 15 20I 22'4~26'8I 29~42'1 g 52~53 SSES FSAR 15A.6.3 Events 8, 12, 14, 15, 18I 20 I 22~23'4~28I 29'2'3'4~45, 51, 53 SSES FSAR 15A.2.3.1 SSES FSAR 15A.6.2.3.14 SSES FSAR 15A.6.3 Events 12, 15, 18, 20, 22'3'4'81 29'3'4, 45 SSES FSAR 15A.6.3 Events 15, 26, 28, 29, 42 SSES FSAR 15A.6.3 SSES FSAR 15A.6.3 Events 20, 28 31

Report No.02-0160-1102 Revision 0 PLANT OPERATING MODE Title STATE C (Cont.)Reactor Shutdown/Head On SAFETY FUNCTIONS Descri tion Reference Restore AC Power Establishing on-site or off-SSES FSAR 15A.6.3 site AC Power for safety sos-Event 29P tems to prevent fuel damage Containment Cooling Control Room Environmental Control Secondary Containment Isolation Suppression Pool Stop Rod Ejection Off-Gas System Isolation Radwaste Building Iso.Liquid Efflu-ent Isolation Initial and extended primary containment cooling to pre-vent containment damage Conditioning of Control Room environment to prevent per-sonnel overexposure Secondary containment isola-tion to minimize radiological effects Limit contamination release to environment Control rod drive processing support to prevent fuel cladding failure Off-Gas System isolation to minimize radiological effect Limit contamination release to environment Liquid effluent system iso-lation to minimize radio-logical effects SSES FSAR 15A.6.3 SSES FSAR 15A.6.5 Events 41, 42 SSES FSAR 15A.6.5g 15A.'6.6 Events 41, 42, 50 SSES FSAR 15A.6.5 Event 42 SSES FSAR 15A.6.5 Event 42 SSES FSAR 15A.6.5 Events 46, 47 SSES FSAR 15A.6.5 Events 48, 49 SSES FSAR 15A.6.5 Events 48, 49 32 Report No.02-0160-1102 Revision 0 PLANT OPERATING MODE STATE D Reactor.Not Shutdown/Head On SAFETY FUNCTIONS Title SCRAM Recirculation Pump Trip Pressure Relief Core Cooling Radioactive Material~~Stored Fuel Control Descri tion Control rod insertion to prevent fuel damage Recirculation pump trip.to prevent fuel damage Nuclear Steam Supply System Pressure relief to prevent excessive pressure Initial and extended safety-grade core cooling to prevent fuel damage Radioactive material release control to minimize radio-logical effects Stored fuel cooling and reactivity control to prevent stored fuel damage Reference SSES FSAR 15A.6.5 Event 42 SSES FSAR 15A.6.5 Event 42 SSES FSAR 15A.6.5 Event 42 SSES FSAR 15A.6.5 Event 42 SSES FSAR 15A.6.5 Events 48, 49 SSES FSAR 15A.6.2.3.14 Reactor Vessel Reactor Pressure Vessel Isolation Isolation to prevent fuel damage SSES FSAR 15A.6.5 Event 43 Containment Isolation Prohibit Rod Motion Reactivity Control Restore AC-Power Primary Containment Isola-tion to minimize radiologi-cal effects.Prevention of adverse rod motion to prevent exceeding fuel limits Core nuclear reactivity con-trol to prevent fuel damage Establishing on-site or off-site AC Power for safety sys-tems to prevent fuel damage SSES FSAR 15A.6 Event 42 SSES FSAR 15.6.3 Event 17.SSES FSAR 15A.6.3 Event 29 SSES FSAR 15A.6.3 Event 29 3 3~

Report No.02-0160-1102 Revision 0 Title PLANT OPERATING MODE STATE D (Cont.)Reactor Not Shutdown/Head On SAFETY FUNCTIONS Descri tion Reference Containment Cooling Limit Reac-tivity Inser-tion Rate Control.Room Environmental Control Secondary Containment Isolation Restrict Loss of Reactor Coolant Of f-Gas Sys-tem Isolation Radwaste.Building Isolation Liquid Efflu-ent Isolation Stop Rod Ejection Initial and extended primary containment cooling to pre-vent containment damage Passive control rod velocity limiter to prevent fuel cladding failure Conditioning of Control Room environment to prevent per-sonnel overexposure Secondary containment iso-lation tominimize radiologi-cal effects Flow restrictors limiting reactor coolant loss to prevent fuel damage Off-Gas System isolation to minimize radiological ef f ect Radwaste system building isolation to minimize radio-logical effects Liquid effluent system iso-'lation to minimize radiologi-cal effects Control rod drive processing.

support to prevent fuel cladding failure SSES FSAR 15A.6.5 Event 42 SSES FSAR 15A.6.5 Event 40 SSES FSAR 15A.6.5 Event 42 SSES FSAR 15A.6.5 Event 42 SSES FSAR 15A.6.5 Events 43, 44, 45 SSES FSAR 15A.6.5 Events 46, 47 SSES FSAR'15A.6.5 Event 48 SSES FSAR 15A.6.5 Event 48 SSES FSAR 15A.6.5 Event 42 34