ML22278A265
| ML22278A265 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 09/19/2022 |
| From: | Constellation Energy Generation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML22278A223 | List:
|
| References | |
| Download: ML22278A265 (53) | |
Text
UNACCEPTABLE RESULTS PLANT SYSTEMS NUCLEAR SAFETY
'-'UCLEAR SAFETY DESIGN CRITERIA .....------------------1 AS DESIGNED OPERATIONAL AND INSTALLED CRITERIA OPERATIONAL ANALYSIS IDENTIFICATION OF SAFETY ACTIONS RULES FOR ESSENTIAL TO AVOIDING UNACCEPTABLE EVENT ANAL VSIS RESULTS (EACH STATE)
REDUNDANCY REQUIREMENT IDENTIFICATION OF SYSTEMS AND (SACFI LIMITS ESSENTIAL FOR ACHIEVING SAFETY ACTIONS (EACH STATE)
IDENTIFICATION OF INTRASYSTEM ACTIONS WHICH MUST BE REQUIRED OR RE:STRICTED (EACH SYSTEM)
IDENTIFICATION OF MINIMUM SYSTEM HARDWARE CONDITIONS TO ACCOMPLISH ACTIONS (EACH SYSTEM I IDENTIFICATION OF HARDWARE CONDITIONS TO SATISFY REDUNDANCY REQUIREMENTS EACH SYSTEM (OPERATIONAL NUCLEAR SAFETY REQUIREMENTS. LIMITING CONDITIONS FOR OPERATION)
IDENTIFY SURVEILLANCE TEST FREQUENCIES AVAILABILITY CONSIDERATIONS IDENTIFY ALLOWABLE REPAIR TIMES 1 A~O~O BE TAK~l;-i WHEN SYSTEM INOPERABLE (LIMITING CONDITION FOR OPERATION)
I OPERATIONAL REQUIRE* I L.. ~ ~ O T S~:.!,D-I SIMPLIFICATION r-----
1 SYSTEM LEVEL ~-S-Y-ST_E_M.a.*L_E_V_E_L- ~
,I I SYSTUJ LEVEL QUALITATIVE QUALITATIVE TECHNICAL I p~~~\1;:;~v/v PLArH DESIGN BASIS CONFIRMATIOI-J SYSTEM DESIGN BASIS CONFIRMATION SPECIFICATIONS I
I TOTAL SAFETY REQUIREMENT I L--------------------------------------~
LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT BLOCK DIAGRAM OF METHOD USED TO DERIVE NUCLEAR SAFETY OPERATIONAL REQUIREMENTS SYS"rEM, LEVEL QUALITATIVE FMEA, DESIGN BASIS CONFIRMATION AUDITS AND TECHNICAL SPECIFICATIONS FIGURE 15.9-1
EVENT SINGLE EQUIPMENT SINGLE OPERATOR EVENT A CATEGORY 1 MALFUNCTION ERROR 1ST PROTECTION LEVEL EVENT A L---....L..----1 EVENT B SINGLE OPERATOR OPERATIONAL 2ND PROTECTION ERROR REQUIREMENT LEVEL PROTECTION PROTECTION LEVEL 1 LEVEL 1 3RD PROTECTION PROTECTION LEVEL OPERATIONAL LEVEL 2. PROTECTION SINGLE OPERATOR
+------ REQUIREMENT SCRAM LEVEL 2 ERROR 4TH PROTECTION LEVEL PROTECTION PROTECTION LEVEL 3 LEVEL 3 ADDITIONAL 5TH PROTECTION LEVEL OPERATIONAL 6TH PROTECTION
____ _____ PROTECTION
_._LEVEL 4 OPERATIONAL PL~~~iCtON REQUIREMENT SCRAM IT IS INCONSISTENT TO PLACE OPERATIONAL EQUIPMENT MALFUNCTION REQUIREMENT LEVEL REQUIREMENTS ARBITRARILY ON SOME ACTION (SCRAM) IN ALL CASES OF ONE EVENT CATEGORY.
IT IS INCONSISTENT TO PLACE OPERATIONAL BECAUSE THAT ACTION (SCRAM) MAY REPRESENT EVENT A EVENT B REQUIREMENTS ON SEPARATED LEVELS OF DIFFERENT LEVELS OF PROTECTION FOR THE PROTECTION FOR ANY ONE EVENT 1ST 1ST VARIOUS CASES.
PROTECTION PROTECTION PANEL A LEVEL LEVEL PANEL B OPERATIONAL ~~gTECTION OPERATIONAL p~gTECTION REQUIREMENT LEVEL REQUIREMENT LEVEL 3RD 3RD PROTECTION PROTECTION LEVEL LEVEL IT IS INCONSISTENT TO PLACE OPERATIONAL RE-REQUIREMENTS ON EVEN THE SAME LEVELS OF PROTECTION. IF THE EVENTS ARE NOT OF THE SAME CATEGORY.
PANEL C LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT POSSIBLE INCONSISTENCIES IN THE SELECTION OF NUCLEAR SAFETY OPERATIONAL REQUIREMENTS FIGURE 15.9-2
INTENTIONALLV LEFT BLANK LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 11.9-3
NUMBER OF EVENT STATES IN WHICH THIS PROTECTION SEQUENCE IS APPLICABLE DIFFERENT PLANT CONDITION DIFFERENT PLANT CONDITION SAFETY SAFETY SAFETY SYSTEM SYSTEM SYSTEM Q R u S F INDICATES THAT SYSTEMS Q AND R SHARE AS A PAIR THE REQUIREMENT TO MEET THE SINGLE FAILURE CRITERION PERSONNEL SAFETY (MANUAL) ~ SAFETY .
SYSTEM ACTION ..-, SYSTEM/'....._
s REQUIRED FOR ( P }W ( L)'
SYSTEM W '- ./ '-
S F SYSTEMS MUST ITSELF MEET THE SINGLE FAILURE SAFETY CRITERION SYSTEM T r...._ INDICATES THAT ONE OR MORE OF l ~) THE KEY PROCESS PARAMETERS MUST
....,_ _- ._ _,._,__. BE LIMITED TO SATISFY NUCLEAR S F
~ S;FETY OPERATIONAL CRITERIA
~ INDICATES THAT RESTRICTIONS ARE PLACED ON CERTAIN PLANT EQUIPMENT SAFETY SAFETY ACTION ACTION A
B EACH CONNECTED PROTECTION SEQUENCE IS FOR JUST ONE SAFETY ACTION LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT FORMAT FOR PROTECTION SEQUENCE DIAGRAMS FIGURE 15.9-4 Rev. 11 9/02
FRONT LINE SAFETY SYSTEM X
I AUXILIARY SYSTEM A
DIAGRAM INDICATES THAT AUXILIARIES A, BAND CARE ESSENTIAL TO THE AUXILIARY OPERATION OF SYSTEM THE FRONT LINE B
SAFETY SYSTEM X.
NO CHRONOLOGY OR ORDER OF ACTION IS IMPLIED AUXILIARY SYSTEM C
LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT FORMAT FOR SAFETY SYSTEM AUXILIARY DIAGRAMS
INTENTIONALLV LEFT BLANK LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.9-6
cs ADS HPCI NEUTRON AC POWER VALV E AND I STANDBY LIQUID MONITORING SYSTEM PUMP POW ER SUPPRESSION STEAM DC POWER CONTROL LOGIC, POOL STORAGE CONDENSATION CONTROL SYSTEM SYSTEM SYSTEM VALVE POWER, LUBE OIL PUMP (PASSIVE)
I I BREA KER PUMP POWER DC POWER CONT ROL, I
SUPPRESSION POOL STORAGE (PASSIVE) - WATE R SUPPLY FOR HPCI PUMP AND EXHA UST DC POWER SYSTEM RELIEF VALVE CONTROLS, SENSORS, LOGIC AND SOLENOIDS AC POWER SYSTEM - TANK HEATERS VALVE FIRING CIRCUITS DC POWE R SYSTEM SYSTEM CONT ROL LOGIC COOL ING AREA CONDENSING I OFCO RE EQUIPMENT ACCUML.LATORS FOR SHC RT TERM PCIG/INSTRUMENT AIR SYSTEMS FOR REDUNDANT REACTIVITY CONTROL SYSTEM
- AUTOMATIC INITIATION LOGIC AREA C OLING SPRA Y EQUI PMEN T I
RCIC RHR SUPPRESSION POOL COOLING LONG TERM RHR SHUTDOWN COOLING LPCI SUPPRESSION POOL STORAGE (PASSIVE) - WATE R SUPPLY TO PUMP S I I I AC POWER AC POWER SYSTEM - VALVE AND AC POWER VALVE AND PUMP POWER CONT ROL LOGIC, SYSTEM - ~~~ '::t!E R I DC POWER PUMP POWER SYSTEM - VALVE POWER, SYSTEM I LUBE OIL PUMP I BREAKER MSRV BREAKER I WATE R SUPPLY PUMP BREAKE R DC POWER CONTROL, DC PO\NER CONTROL, CONTROL SYSTEM DC POWER SYSTEM SUPPRESSION CONTROL AND SYSTEM - CONTROL FOR RCIC PUMP LOGIC POOL STORAGE - AND EXHA UST SYSTEM CONTROL LOG IC LOGIC I I J I (PASSIVE)
CONDENSING SUPPRESSION I l I POOL STORAGE - STEA M l PLANT RHR EMERGENCY (PASSIVE)
COND ENSA TION PLANT EMERGENCY SERVICE EMERGENCY RHR SERVICE i---P UMP -
SERVICE WATE R PLANT RHR SERVICE SERVICE -PU MP - WATER COOLERS SERVICE PUMP WATER SYSTEM WATER
_____ WATER COOLERS SYSTEM WATER COOLERS SYSTEM SYSTEM SYSTEM
.__ SYSTEM I I I I I I
RHRS ERVIC E WATER SYSTEM RHR HEAT EXCHANGERS EQUIPMENT AREA COOLING -
COOLING AR EA AR0U NDRH R EQUIPMENT EQUI PMEN T AREA COOLING I
- COOL AREA OF RHR EQUIPM ENT I SUPPRESSION WATER LIMERICK GEN ERAT ING STAT ION SUPPLY UNITS 1 AND 2 RHR SERVICE POOL STA0 RAGE EQUIPMENT COOL AREA AROUND RHR WATE R SYSTEM - RHR HEAT EXCHANGERs (PASSIVE)
- T0RH R
( LPCI )
UPDATED FINAL SAFETY ANAL YSIS REPORT AREA COOLING EAUIPMENT PUMPS SAFETY SYSTEM AUX ILIA RIES SUPPRESSION Rev. 11 9/02 POOL STORAGE WATER SUPPLY FIGURE 15.9-7 (PASSIVE) FOR RHR PUMP
PRIMARY AREA CONTROL ROOM CONTAINMENT AND ISOLATION CONTAINMENT HEATING REACTOR VESSEL AC POWER CONTROL {PASSIVE) VENTILATING AND EQUIPMENT AREA ISOLATION SYSTEM(S) SYSTEM AIR CONDITIONING COOLING CONTROL SYSTEM SYSTEM SUPPA ESSION DC POWER CONTROL DC POWER POOL PRESSURE CONTROL SYSTEM LOGIC SYSTEM STORAGE SUPPRESSION ALTERNATE LOGIC
{PASSIVE) PLANT CONTROL EMERGENCY ROOM STANDBY OFFSITE SERVICE STRUCTURE SERVICE COOLING AC AC WATER CHILLED WATER POWER POWER SYSTEM WATER SYSTEM SYSTEM DRYWELL/ SYSTEM DRYWELL SUPPRESSION AC POWER EQUIPMENT VACUUM SYSTEM POOL POWER RELIEF DIFFERENTIAL SYSTEM PRESSURE AC POWER VALVE DC POWER CONTROL PLANT SYSTEM EMERGENCY POWER SYSTEM SERVICE SERVICE WATER WATER DC POWER BREAKER SYSTEM CONTROL DC POWER SYSTEM CONTROL AND PCRVIC SYSTEM POWER SYSTEM CONTAINMEN T CONTROL SYSTEM ISOLATION LOGIC VALVE AND OFFSITE ACPOWER PUMP POWER. CONTAINMENT ESF DETECTION INITIATES POWER TO AIR HYDROGEN AC POWER AC POWER MSL SYSTEM POWER TO CIRCUITRY ESF SYSTEMS LEAKAGE CONDITIONING CONTROL SYSTEM SYSTEM SYSTEM PATHWAY BLOWERS CONTROL EQUIPMENT DC POWER CONTROL DC POWER BREAKER DC POWER CONTROL DC POWER CONTROL DC POWER CONTROL SYSTEM POWER SYSTEM CONTROL SYSTEM LOGIC SYSTEM LOGIC SYSTEM POWER STANDBY GAS REACTOR MANUAL TREATMENT CONTROL SYSTEM SYSTEM VALVE AND AC POWER VALVE AC POWER SYSTEM SYSTEM BLOWER POWER POWER AC POWER DC POWER CONTROL PLANT RPS FAIL STANDBY AC SYSTEM SYSTEM LOGIC RADIATION PLANT
- SAFE POWER SYSTEM HVAC MONITORING RESIDUAL SYSTEM(S) SYSTEM(S)
HEAT COOLING REMOVAL WATER TO SYSTEM RECOMBINERS DELIVER DC POWER AC POWER POWER TO BREAKER SYSl'EM SYSTEM BLOWERS AND DC POWER CONTROL.
REACTOR HEATERS DC POWER SYSTEM CONTROL CONTROL DC POWER CONTROL ENCLOSURE DRYWELL SYSTEM LOGIC LOGIC (PASSIVE) HYDROGEN SYSTEM LOGIC FAIL RECIRCULA-TION SYSTEM MIXING CAD - SAFE SCRAM ROD REACTOR FUNCTION EMERGENCY BLOCK ENCLOSURE SERVICE COOL MONITOR HVAC AC POWER WATER DIESELS EQUIPMENT AC POWER (PASSIVE) SYSTEM SYSTEM sas ISOLATION LIQUID WASTE DRAINS SYSTEM SYSTEM MANAGEMEN T SYSTEM FLOOR ROD DRAINS WORTH DIESEL MINIMIZER GENERATOR SUPPORT REDUNDANT DIESELS REACTIVITY AUXILIARIES AIR FLOW OFFGAS CONTROL SYSTEM AND SYSTEM REAS PRESSURE CONTROL I CAD AC POWER SYSTEM AC POWER DC POWER SYSTEM CONTROL LIMERICK GENERATIN G STATION SYSTEM POWER I UNITS 1 AND 2 CONTROL UPDATED FINAL SAFETY ANALYSIS REPORT I DC POWER SYSTEM LOGIC DC POWER AC POWER SYSTEM SYSTEM EQUIPMENT POWER I AC POWER SYSTEM SERVICE C OOUNG SAFETY SYSTEM AUXILIAR IES WATER -w ATER TO RECOMBINER FIGURE 15.9-8 Rev. 11 9/02
STATE A NORMAL OPERATION EVENTS 1, 2 AND 6 EVENTS EVENTS EVENTS EVENTS EVENTS EVENT EVENTS 1, 2 AND 6 1, 2 AND 6 1, 2 AND 6 1, 2 AND 6 1, 2 AND 6 1 1, 2 AND 6 MINIMUM WATER PROCEDURAL WATER CONTROL REACTOR LEVEL TO AVOID REACTOR RESTRICTIONS CHEMISTRY ROD DRIVE FUEL EXCESS COOLANT (CONTROL ROD LIMIT SYSTEM L TEMPERATURE L POSITION)
R REACTOR NUCLEAR PROCEDURAL WATER LIQUID 10CFR20 RESTRICTIONS FUEL TEMPERATURE VESSEL SYSTEM REACTOR RADWASTE 10CFR50 (FUEL STORAGE WATER LEVEL WATER LEVEL WATER QUALITY FUEL SYSTEM LIMIT ASSEMBLY FACILITIES FUEL HANDLING CONTROL CONTROL L R ORIENTATION) L FUEL SPACING STORED FUEL SOLID 10 CFR 71 LIMIT SHIELDING REACTOR MINIMUM TEMPERATURE REFUELING RADWASTE APPLIED TO COOLING AND VESSEL TO BOLT DOWN VESSEL HEAD RESTRICTIONS SYSTEM SHIPPING CASKS REACTIVITY L L CONTROL REFUELING FLOOR EVENT EVENTS NUCLEAR VENTILATION MONITOR ACTIVITY 1 1, 2 AND 6 SYSTEM RADIATION RELEASE THROUGH TEMPERATURE MONITORING VENTILATING SYSTEM CONTROL L SYSTEM LIMIT ON CONTROL CORE LOADING REACTOR NUMBER OF RADIOACTIVE ROD DRIVE PATTERN FUEL DRIVES VALVED MATERIAL SYSTEM L OUT OF SERVICE RELEASE L CONTROL CORE LIMERICK GENERATING STATION REACTIVITY CONTROL UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SAFETY ACTION SEQUENCES FOR NORMAL OPERATION IN STATE A FIGURE 15.9-9
STATE B NORMAL OPERATION EVENTS 2 AND 5 EVENTS EVENTS EVENTS EVENTS EVENTS EVENTS EVENT EVENTS 2 AND 5 2AND 5 2 AND5 2AND5 2 AND 5 2 AND 5 2 2 AND 5 MINIMUM RATE OF POSITIONING REACTOR POWER (SRM) REACTOR CHANGE CONTROL ROD OF CONTROL FUEL MAXIMUM VESSEL TEMPERATURE DRIVE SYSTEM ROD DURING POWER LIMIT CORE WATER L L ALTERATION TEMPERATURE, WATER LEVEL, FUEL SPACING, AND FUEL HANDLING LIQUID CORE POWER NUCLEAR 10CFR 20 CORE SYSTEM FUEL RADWASTE 10 CFR 50 LEVEL REACTIVITY TEMPERATURE STORAGE SYSTEM LIMIT CONTROL CONTROL CONTROL FACILITIES L L STORED FUEL REACTOR MINIMUM REACTOR WATER CHEMISTRY SHIELDING FUEL WATER LEVEL COOLANT LIMIT COOLING AND REACTIVITY L L CONTROL REACTOR NUCLEAR SOLID 10 CFR 71 LIMIT CONTROL ROD VESSEL SYSTEM RADWASTE APPLIED TO DRIVE ROD PATTERN WATER LEVEL WATER QUALITY SYSTEM SHIPPING CASK SYSTEM RWM, RBM CONTROL CONTROL L L REFUELING FLOOR VENTILATION MONITOR ACTIVITY RADIATION RELEASE THROUGH ROD WORTH MONITORING VENTILATION SYSTEM CONTROL L SYSTEM RADIOACTIVE MATERIAL LIMERICK GENERATING STATION RELEASE UNITS 1 ANO 2 CONTROL UPDATED FINAL SAFETY ANALYSIS REPORT SAFETY ACTION SEQUENCES FOR NORMAL OPERATION IN STATE B FIGURE 15.9-10 Rev. 11 9/02
STATE C NORMAL OPE RATION EVENTS 2 AND 6 TEMPERATURE OVERSTRESS TEMPERATURE MINIMUM RATE OF REACTOR REACTOR REACTOR ..,_ PROTECTION CONTAINMENT LIMIT
.... WATER --CHANGE, FUEL VESSEL VESSEL AND MAKEUP (PASSIVE) ...., PRESSURE LEVEL MINIMUM CAPABILITY LIMIT L L TEMPERATURE L L REACTOR NUCLEAR WATER 10 CFR 20 WATER LIQUID MAXIMUM SUPPRESSION FUEL TEMPERATURE, VESSEL REACTOR SYSTEM ~ TEMPERATURE RADWASTE ~10CFR 50 ~FEEDWATER POOL STORAGE STORAGE ...., WATER LEVEL, WATER LEVEL FUEL LE.AKAGE AND VOLUME SYSTEM LIMIT TEMPERATURE (PASSIVE) FACILITIES FUEL SPACING, CONTROL CONTROL LIMIT L L L L FUEL HANDLING NUCLEAR STORED FUEL CONTAINMENT SYSTEM SHIELDING PRESSURE AND TEMPERATURE COOLING AND TEMPERATURE CONTROL REACTIVITY CONTROL CONTROL MAXIMUM WATER 10 CFR 71 CHEMISTRY SOLID PRESSURE, NUMBER OF
.,._ LIMIT APPLIED REACTOR REACTOR CONTROL ROD RADWASTE --MINIMUM - - LIMITS .,._ DRIVES VALVED TO SHIPPING VESSEL COOLANT DRIVE SYSTEM SYSTEM PRESSURIZATION ACTIVITY OUT OF SERVICE CASK L L TEMPERATURE L LIMIT L REFUELING FLOOR MONITOR NUCLEAR AND REACTOR MAXIMUM CORE ENCLOSURE ACTIVITY RHR SHUTDOWN ~ PRESSURE SYSTEM REACTIVITY
-- RELEASE COOLING MODE WATER QUALITY VENTILATION LIMIT CONTROL THROUGH CONTROL RADIATION VENTILATING L
MONITORING SYSTEM L SYSTEM LIMERICK GENERATING STATION UNITS 1 AND2 NUCLEAR UPDATED FINAL SAFETY ANALYSIS REPORT RADIOACTIVE SYSTEM MATERIAL PRESSURE RELEASE CONTROL SAFETY ACTION SEQUENCES CONTROL FOR NORMAL OPERATION IN STATE C FIGURE 15.9-11
STATED NORMAL OPERATION EVENTS 2, 3, 4 AND 5 EVENTS 2, EVENTS EVENTS 2, EVENTS 2, EVENTS 2, EVENTS 2, EVENTS 2, EVE~TS 2, EVENTS 2, EVENTS 2, EVENTS 2, EVENTS 2, EVENTS 2, 3, 4 AND 5 3, 4 AND 5 3,4 AND 5 3,4AND 5 3,4 AND 5, 3,4 AND 5 3, 4 AND 5 3, 4 AND 5 3, 4 AND 5 3, 4 AND 5 3,4 AND 5 3, 4 AND 5 3, 4 AND 5 OVER-MINIMUM ROD WATER LIQUID 10 CFR 20 STRESS POWER MINIMUM PROTEC- CONTROL ROD PATTERN FUEL RADWASTE REACTOR REACTOR REACTOR CONTROL TEMPERATURE 10 CFR 50 (SRM) WATER TION DRIVE FUEL FUEL VESSEL STORAGE WATER LEVEL L SYSTEM LIMIT MAXIMUM LEVEL MAKEUP L SYSTEM RWM, L POWER L L RBM LFACILITIES FUEL SPACING CAPABI- FUEL HANDLING LITY REACTOR STORED CORE POWER VESSEL NUCLEAR FUEL 10 CFR 20 LEVEL WATER SYSTEM SHIELDING, OFFGAS 10 CFR 50 CONTROL LEVEL LEAKAGE COOLING AND SYSTEM LIMIT CONTROL CONTROL REACTIVITY L
CONTROL EVENTS EVENTS 3AND4 2 AND5 SOLID 10 CFR 71 LIMIT RADWASTE APPLIED TO WATER L SYSTEM SHIPPING CASK AHR NUMBER SHUTDOWN MAXIMUM CHEMISTRY CONTROL ROD REACTOR DRIVES COOLING PRESSURE LIMIT DRIVE COOLANT OUTOF L MODE LIMIT ACTIVITY L SYSTEM L LIMIT SERVICE MAXIMUM TEMPERATURE PRESSURE REACTOR VESSEL CONTAINMENT AND REFUELING MONITOR LIMIT (PASSIVE) PRESSURE ACTIVITY L NUCLEAR FLOOR MAXIMUM SYSTEM CORE L LIMITS RELEASE REACTOR AND REACTOR ENCLOSURE THROUGH VESSEL PRESSURE WATER QUALITY REACTIVITY CONTROL VENTILATION LIMIT CONTROL VENTILATION L SYSTEM------......
RADIATION WATER MONITORING REACTOR MINIMUM REACTOR POWER RATE OF SUPPRESSION TEMPERATURE POOL STORAGE TEMPERATURE SYSTEM FUEL FLOW RATE FUEL PEAKING REACTOR CHANGE AND VOLUME L L L L (PASSIVE)
VESSEL MINIMUM LIMIT L TEMPERATURE WITH HEAD ON CORE RADIOACTIVE CORE NUCLEAR NEUTRON MAXIMUM NTAINMEN MATERIAL COOLANT SYSTEM REACTOR FLUX DISTRI- FEEDWATER MPERATUR RELEASE FLOW RATE PRESSURE FUEL CONTROL BUTION TEMPERATURE PRESSURE CONTROL CONTROL L CONTROL CONTROL EVENTS EVENT 2 3, 4 AND 5 MAXIMUM REACTOR TEMPERATURE RECIRCULATION DIFFERENCE L SYSTEM IN RECIRCU-LATION LOOPS LIMERICK GENERATING STATION UNITS 1 ANO 2 UPDATED FINAL SAFETY ANALYSIS REPORT NUCLEAR SYSTEM TEMPERATURE SAFETY SECTION SEQUENCES CONTROL FOR NORMAL OPERATION IN STATE D FIGURE 15.9-12 Rev. 11 9/02
EVENT 7 MANUAL OR INADVERTENT SCRAM STATES A, B, C, D REACTOR PROTECTION SYSTEM s F
~ CONTROL ROD INSERT
.,.._ CONTROL DRIVE SYSTEM RODS s F SCRAM LIMERICK GENEftATING STATION UNITS 1 AMO 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCE FOR MANUAL OR INADVERTENT SCRAM FIGURE 11 ... 13
EVENTS LOSS OF PLANT INSTRUMENT AND SERVICE AIR SYSTEM STATES A, B, C, D REACTOR MODE SWITCH REACTOR MODE NOT IN RUN SWITCH IN RUN PLANNEC OPERATION HIGH PRESSURE SCRAM SIGNAL REACTOR LIFTS VALVE TRANSFERRING MSRV WHEN 3 MSIV's PROTECTION HEAT TO SUP- SYSTEM NOT FU LL OPEN SYSTEM PRESSION POOL S F S F INITIATE HPCI, INSERT ESF CONTROL ROD RCIC, ADS PRESSURE CONTROL----- DETECTION DRIVE SYSTEM ON LOW RELIEF ROD CIRCUITRY WATER LEVEL S F S F SEE FIGURE 15.9-35 SCRAM LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR LOSS OF PLANT INSTRUMENT AND SERVICE AIR SYSTEM FIGURE 15.9-14
EVENT 9 INADVERTENT STARTUP NSSS PUMP STATES A, B, C AND D STATES B, D STATES A, C PRESSURE PRESSURE REGULATOR FEEDWATER FEEDWATER REGULATOR FAILS TO CONTROLLER CONTROLLER OPERATING OPEN OPERATING FAILS PLANNED OPERATION PLANNED SEE PLANNED SEE OPERATION EVENT OPERATION EVENT NO. 23 NO. 22 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCE FOR INADVERTENT STARTUP OF NSSS PUMP FIGURE 15.* 15
EVENT10 STARTUP OF IDLE RECIRCULATION PUMPS STATES A, B, C, D STATES B, D STATES A, C APRM PLANNED OR OPERATION NEUTRON IRM MONITORING HIGH SYSTEM FLUX SIGNAL S F SIGNAL< SETPOINT SIGNAL> SETPOINT PLANNED OPERATION REACTOR SCRAM SIGNAL FROM PROTECTION NEUTRON MONITORING SYSTEM SYSTEM TRIP S F CONTROL ROD INSERT CONTROL RODS DRIVE SYSTEM S F SCRAM LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCE FOR INADVERTENT STARTUP OF IDLE RECIRCULATION LOOP PUMP FIGURE 15.9-16
EVENT 11 CIRCULATION LO W CONTROL FAIL NCREASING FLO STATES C AND D STATED (REACTOR STATE C AND STATED (REACTOR MODE SWITCH IN RUN) MODE SWITCH NOT IN RUN)
PLANNED NEUTRON OPERATION HIGH NEUTRON FLUX MONITORING (APRM) TRIP SYSTEM S F SCRAM SIGNAL REACTOR ON NEUTRON PROTECTION MONITORING SYSTEM SYSTEM TRIP S F CONTROL ROD DRIVE INSERT CONTROL RODS SYSTEM S F SCRAM LIMERICK GENERATING STATION UNITS 1 AND2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCE FOR RECIRCULATION LOOP FLOW CONTROL FAILURE (INCREASING FLOW)
EVENT12 RECIRCULATION LOOP FLOW CONTROL FAILURE (DECREASING FLOW)
STATES C AND D HIGH WATER LEVEL TURBINE TRIP NO HIGH WATER LEVEL TURBINE TRIP z
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INITIATE PRIMARY SCRAM FROM INITIATE REACTOR ESF HPCI, RCIC CONTAINMENT MSRV TURBINE ISOLATION PROTECTION DETECTION SYSTEM AND REACTOR SYSTEM STOP VALVE ON LOW SYSTEM CIRCUITRY ON LOW VESSEL ISOLATION CLOSURE WATER LEVEL WATER LEVEL CONTROL SYSTEM S F S F S F S F INSERT CONTAINMENT PRESSURE CONTROL ROD HPCI RCIC CONTROL ISOLATION RELIEF DRIVE SYSTEM RODS S F S F INITIAL SCRAM CORE COOLING PLANNED LIMERICK GENERATING STATION OPERATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCE FOR RECIRCULATION LOOP FLOW CONTROL FAILURE (DECREASING FLOW)
FIGURE 15.9-18
EVENT 13 RECIRCULATION LOOP PUMP TRIP (ONE OR BOTH)
STATES C AND D STATE C STATED ONE PUMP TRIP TWO PUMP TRIP PLANNED OPERATION HIGH WATER LEVEL TURBINE TRIP NO HIGH WATER LEVEL TURBINE TRIP AFTER ISOLATION STATED ONLY INITIATE PRIMARY REACTOR SCRAM FROM ESF HPCI, RCIC CONTAINMENT INITIATE MSRV PROTECTION TURBINE STOP DETECTION SYSTEM ON AND REACTOR ISOLATION ON SYSTEM SYSTEM VALVE CLOSURE CIRCUITRY LOW WATER VESSEL ISOLATION LOW WATER LEVEL LEVEL CONTROL SYSTEM s F s F s F s F CONTROL ROD INSERT DRIVE SYSTEM CONTROL RODS S F HPCI RCIC SCRAM INITIAL CONTAINMENT CORE ISOLATION COOLING LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PLANNED OPERATION PROTECTION SEQUENCES FOR RECIRCULATION PUMP TRIP (ONE OR BOTH)
FIGURE 15.9-19
EVENT14 REACTOR MODE REACTOR MODE SWITCH NOT IN RUN SWITCH IN RUN SCRAM SIGNAL REACTOR WHAN 3MSIVs PROTECTION NOT FULL OPEN SYSTEM S F INITIATE HPCI, PLANNED ESF RCIC, ADS ON MSRV HEAT TO OPERATION DETECTION LOWER WATER SYSTEM UPPRESSION CIRCUITRY LEVEL POOL S F S F INSERT CONTROL ROD CONTROL RODS DRIVE SYSTEM SEE FIGURE 15.9-35 S F PRESSURE RELIEF SCRAM LIMERICK GENERATIN G STATION UNITS 2AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTEC TION SEQUENCES FOR ISOLATION OF ALL MAIN STEAM LINES FIGURE 15.9-20 Rev. 11 9/02
EVENT14 ISOLATION OF ONE MAIN STEAM LINE STATES C AND D LESS THAN GREATER THAN APPROX. 90% POWER APPROX. 90% POWER HIGH NEUTRON NEUTRON PCRVIC HIGH STEAM FLUX SIGNAL MONITORING SYSTEM LINE FLOW SYSTEM CONTINUE PLANNED S F S F OPERATION SCRAM SIGNAL REACTOR ON NEUTRON PROTECTION MSIVs MONITORING SYSTEM SYSTEM TRIP S F S F REACTOR INSERT CONTROL ROD VESSEL CONTROL RODS DRIVE SYSTEM ISOLATION S F INITIATE HPCI, RCIC, ESF HEAT TO ADS ON DETECTION MSRV SUPPRESSION SYSTEM POOL LOW CIRCUITRY WATER LEVEL S F S F SEE FIGURE 15.~35 PRESSURE SCRAM RELIEF LIMERICK GENERATING STATION UNITS 1 AND2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECT ION SEQUENCES FOR ISOLATION OF ONE MAIN STEAM LINE FIGURE 16.9-21
EVENT15 DVERTENT OPEN OF AN MSRV STATES C AND D STATE C STATED MSRV OPEN FOR MSRV OPEN FOR< TIME LIMIT >TIME LIMIT SUPPRESSION PLANNED POOL TEMP-OPERATION ERATURE LIMIT TIME LIMIT RHR SHUTDOWN COOLING MODE REACTOR PROTECTIO N MODE SWITCH PLANNED SYSTEM TO SHUTDOWN OPERATION S F CONTROL ROD INSERT DRIVE SYSTEM CONTROL RODS S F SCRAM LIMERICK GENERAT ING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTEC TION SEQUENCES FOR INADVER TENT OPENING OF AN MSRV FIGURE 15.1-22
EVENT16 CONTROL ROD WITHDRAW AL ERROR STARTUP AND REFUELING OPERATION STATES A AND B STATE A STATE B
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SCRAM SIGNAL REACTOR REACTOR REACTOR ON MANUAL CONTROL MODE SWITCH PROTECTIO N NEUTRON SYSTEM "REFUEL" SYSTEM MONITORIN G SYSTEM TRIP S F S F CONTROL ROD INSERT DRIVE SYSTEM CONTROL RODS S F ROD BLOCK SCRAM LIMERICK GENERAT ING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCE FOR CONTRO L ROD WITHDR AWAL ERROR FOR STARTUP AND REFUEL ING OPERATIONS FIGURE 11.1-23
EVENT17 CONTROL ROD WITHDRAW AL ERROR POWER OPERATION STATES C AND D STATE C STATED PLANNED REACTOR REACTOR OPERATION MODE SWITCH "STARTUP " MODE SWITCH" RUN" POWER
< LOW POWER ALARM POWER > LOW POWER POINT ALARM POINT NEUTRON HIGH MONITORIN G NEUTRON SYSTEM FLUX SIGNAL S F ROD WORTH ROD BLOCK MINIMIZER MONITOR REACTOR PROTECTIO N SCRAM r
UNAUTHOR IZED SIGNAL SYSTEM ROD FROM NMS WITHDRAW AL TRIP S F INSERT CONTROL ROD CONTROL DRIVE SYSTEM RODS S F ACCEPTABL E DEVIATION ROD ROD SCRAM FROM BLOCK BLOCK PLANNED OPERATION LIMERICK GENERAT ING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTEC TION SEQUENCE FOR CONTRO L ROD WITHDR AWAL ERROR-POWER OPERAT ION FIGUIIE15.I-M
EVENT18 RHR LOSS OF SHUTDOWN COOLING STATES A, B, AND C ISOLATION SHUTDOWN COOLING SUCTION LINE ALL OTHER SINGLE FAILURES STATES A, B OR C P < SHUTDOWN ST A TE C, P > SHUTDOWN COOLING INTERLOCK COOLING INTERLOCK PRESSURE PRESSURE MAINTAIN
- REACTOR _
LPCI WATER cs LPCI cs p LEVEL p p p s F s F s F s F PLANNED OPERATION MSRV MAINTAIN
~ DEPRES- - ADS SYSTEM SURIZATION p p S F S F RHR SUPPRESSION POOL COOLING p MODE LIMERICK GENERATIN G STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES PLANNED OPERATION FOR RHR-LOSS OF SHUTDOWN COOLING FIGURE 11..1-21
EVENT19 AHR-SHUTDO WN COOLING INCREASED COOLING STATES A, B, C, AND D
)
AAND B C AND D PLANNED OPERATION PLANNED OPERATION LIMERICK GENERATIN G STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR RHR (SHUTDOWN COOLING)
INCREASE D COOLING FIGURE 15.9-26
EVENT 20 LOSS OF ALL FEEDWATER FLOW STATES C AND D STATED ONLY p < SHUTDOWN COOLING p > SHUTDOWN COOLING INTERLOCK SETPOINT INTERLOCK SETPOINT p < HPCI/RCIC p > HPCI/RCIC ISOLATION ISOLATION SETPOINT SETPOINT PLANNED INITIATE OPERATION SCRAM REACTOR SHUTDOWN ON ESF PROTECTION COOLING START HPt;I, ACIC ON LOW DETECTION SYSTEM LOWWATER LEVEL WATER CIRCUITRY LEVEL S F S F HPCI MAINTAIN RCIC WATER LEVEL S F PRIMARY TRANSFER INSERT CONTAINMENT DECAY INITIAL CONTROL ROD MSRV CORE CONTROL AND REACTOR HEAT TO DRIVE SYSTEM SYSTEM COOLING RODS VESSEL ISOLATION SUPPRESSION CONTROL SYSTEM POOL s F s F s F RHR SUPPRESSION POOL COOLING MODE SUPPRESSION POOL TEMPERATURE LIMIT START DEPRESSURIZATION PRESSURE SCRAM RELIEF MSRV ADS SYSTEM S F S F MAINTAIN LPCI WATER LEVEL IN cs REACTOR VESSEL LIMERICK GENERATING STATION S F S F UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PLANNED PROTECTION SEQUENCES FOR OPERATION LOSS OF FEEDWATER FLOW FIGURE 15.9-27
EVENT 21 LOSS OF A FEEDWATER HEATER STATED FLUX > SETPOINT FLUX < SETPOINT PLANNED OPERATION NEUTRON MONITORING HIGH NEUTRON SYSTEM FLUX SIGNAL S F REACTOR PROTECTION SCRAM SIGNAL ON NMS TRIP SYSTEM S F CONTROL ROD DRIVE INSERT CONTROL RODS SYSTEM S F SCRAM LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCE FOR LOSS OF A FEEDWATER HEATER F IGUIIE 11.1-2&
EVENT 22 FEEDWATER CONTROLLER FAILURE (MAXIMUM DEMAND)
STATES A, B, C AND D STATES A AND B STATES C AND D STATES A, B, C, D STATES C, D STATED ONLY p< SHUTDOWN COOLING p> SHUTDOWN COOLING INTERLOCK SETPOINT INTERLOCK SETPOINT POWER < TURBINE STOP VALVE CLOSURE SCRAM BYPASS SETPOINT POWER:> TURBINE STOP VALVE CLOSURE SCRAM BYPASS SETPOINT I
PLANNED p< HPCI/RCIC p> HPCI/RCIC ISOLATION ISOLATION OPERATION SETPOINT SETPOINT SHUTDOWN PRIMARY CONTAINMENT COOLING I
MSRV TRANSFER ESF MODE AND REACTOR SYSTEM - - DECAY DETECTION ..... START HPCI, RCIC ON SWITCH MODE SWITCH HEAT TO LOW WATER LEVEL IN RUN NOT IN RUN VESSEL ISOLATION CIRCUITRY CONTROL SYSTEM SUPPRESSION S F POOL S F I I MAINTAIN RCIC NEUTRON HPCI CONTAINMENT PRESSURE ~ WATER LEVEL -
MONITORING SYSTEM ISOLATION RELIEF I I INITIAL CORE PLANNED COOLING OPERATION SCRAM SIGNAL REACTOR
..,_ TURBINE STOP I
FROM TURBINE - PROTECTION RPT VALVE CLOSURE I
TRIP OR NMS SYSTEM AHR PLANNED SUPPRESSION OPERATION S F S F POOL COOLING MODE CONTROL SUPPRESSION POOL ROD TEMPERATURE LIMIT DRIVE START DEPRESSURIZATIO N SYSTEM S F .....
MSRV ADS P SYSTEM p POWER I s IF SCRAM REDUCTION I I I MAINTAIN LPCI - - WATER LEVEL IN - CS p REACTOR VESSEL p s IF I
PLANNED OPERATION LIMERICK GENERATING STATION UNITS 1 AND2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR FEEDWATER CONTROLLER FAILURE (MAXIMUM DEMAND)
FIGURE 15.9-29
EVENT 23 PRESSURE REGULATOR FAILURE (OPEN)
STATES C AND D STATED ONLY SCRAM SIGNAL FROM eMAIN STEAM LINE PRIMARY ISOLATION INITIATE REACTOR ESF CONTAINMENT MSRV HPCI, RCIC, ADS PROTECTION e TURBINE TRIP DETECTION ON LOW WATER AND REACTOR SYSTEM SYSTEM CIRCUITRY VESSEL ISOLATION e LOW WATER LEVEL LEVEL CONTROL SYSTEM S F S F S F SEE FIGURE 15.9-35 CONTROL CLOSE ON PRESSURE INSERT ROD DRIVE MSIVs LOW STEAM RELi EF CONTROL RODS LINE PRESSURE SYSTEM S F S F REACTOR SCRAM VESSEL ISOLATION LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR PRESSURE REGULATOR FAILURE (OPEN)
FIGURE 15.9-30
EVENT 24 T PRESSURE REGUL FAILURE (CLOSED)
STATES C AND D SECOND PRESSURE SECOND PRESSURE REGULATOR OPERATES REGULATOR FAILS PRIMARY INITIATE HIGH ESF NEUTRON- CONTAINMENT HPCI, RCIC, ADS FLUX MSRV DETECTION MONITORING AND REACTOR ON LOW WATER SYSTEM CIRCUITRY SYSTEM VESSEL ISOLATION LEVEL CONTROL SYSTEM S F SEE FIG. 15.9-35 PLANNED OPERATION REACTOR PRESSURE PROTECTION RELIEF SYSTEM CONTROL ROD CONTAINMENT DRIVE ISOLATION SYSTEM SCRAM LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR PRESSURE REGULATOR FAILURE (CLOSED)
FIGURE 15.9-31
EVENT 25 TURBINE TRIP WITH BYPASS STATED
-0 ABOVE TSV CLOSURE SCRAM BYPASS SETPOINT I-z 0
~ SYSTEM CLOSURE CIRCUITRY WATER LEVEL
<(
0.
a:i S F S F
~
<a:
~
w a:
Cl) 0 TURBINE MAINTAIN
..J INSERT
(.) STOP CONTROL ROD REACTOR _ MSRV PCRVIC RPT .. CONTROL RCIC HPCI Cl)
VALVE - DRIVE SYSTEM RODS WATER SYSTEM SYSTEM I- CLOSURE LEVEL
~..J w S F S F S F S F a:i S F PLANNED OPERATION POWER INITIAL CORE REACTIVITY PRESSURE CONTAINMENT REDUCTION CONTROL COOLING RELIEF ISOLATION PLANNED LIMERICK GENERATING STATION OPERATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR MAIN TURBINE TRIP WITH BYPASS SYSTEM OPERATION FIGURE 15.9-32
EVENT 26 LOSS OF MAIN CONDENSER VACUUM STATES C AND D STATED ONLY STATES C AND D BELOW TSV ABOVE TSV CLOSURE CLOSURE SCRAM BYPASS SCRAM BYPASS SETPOINT MSIVs SETPOINT S F INITIATE HPCI, HIGH NEUTRON RCIC, ESF NEUTRON MONITORING ADS ON PCRVIC DETECTION FLUX SYSTEM LOW SYSTEM CIRCUITRY WATER LEVEL S F S F S F SEE FIGURE 15.9-35 SCRAM SIGNAL ON NEUTRON TRANSFER MONITOR REACTOR TURBINE MSRV DECAY SYSTEM PROTECTION RPT STOP HEAT TO TRIP OR VALVE SYSTEM SYSTEM SUPPRES-TURBINE CLOSURE SION POOL STOP VALVE CLOSURE S F S F S F INSERT REACTOR CONTROL CONTROL ROD DRIVE SYSTEM VESSEL RODS ISOLATION S F POWER PRESSURE SCRAM REDUCTION RELIEF LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR LO~OF MAIN CONDENSER VACUUM FIGURE 15.9-33
EVENT 27 GENERATOR TRIP WITH BYPASS STATED ABOVE TCV CLOSURE SCRAM BYPASS SETPOINT
....z 2.... TURBINE CONTROL ESF INITIATE REACTOR HPCI, RCIC w DETECTION
(./J PROTECTION VALVE ON LOW
(./J SYSTEM FAST CIRCUITRY
(./J WATER LEVEL
<( CLOSURE c..
al S F S F
- l!:
<(
cc u
(./J w
a:
- J
(./J TURBINE 0 MAINTAIN
...J CONTROL INSERT u VALVE RPT CONTROL ROD REACTOR MSRV PCRVIC CONTROL RCIC HPCI
> FAST DRIVE SYSTEM RODS WATER SYSTEM SYSTEM
~ CLOSURE LEVEL 3:
0
...J w S F S F S F S F al S F PLANNED OPERATION POWER INITIAL CORE PRESSURE CONTAINMENT SCRAM REDUCTION COOLING RELi EF ISOLATION PLANNED LIMERICK GENERATING STATION OPERATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR MAIN GENERATOR TRIP WITH BYPASS SYSTEM OPERATION FIGURE 15.9-34
r ____T ____ 7
L____ _ ___ ...J WATER LEVEL < L1 WATER LEVEL < L2 HPCI RCIC WATER LEVEL < L1 WATER LEVEL> L1 ADS S F LPCI cs S F INITIAL CORE COOLING RHR SUPPRESSION POOL COOLING MODE ADS NOT ADS ACTUATED ACTUATED SUPPRESSION POOL TEMPERATURE LIMIT - START DEPRESSURIZATION MSRV ADS p SYSTEM LPCI cs p p S F S F LIMERICK GENERATING STATION PLANNED UNITS 1 AND 2 OPERATION UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR ACHIEVING SHUTDOWN COOLING WITH REACTOR VESSEL ISOLATED FIGURE 15.1- 35
EVENT 29 LOSS OF NORMAL AC POWER GRID CONNECTION LOSS STATES A,B,C AND D ALL STATES STATES BAND D STATES A, B, C, D STATES C, D
< TCV CLOSURE SCRAM >TCV CLOSURE SCRAM STATES p< SHUTDOWN COOLING p> SHUTDOWN COOLING BYPASS SETPOINT BYPASS SETPOINT CANDO INTERLOCK SETPOINT INTERLOCK SETPOINT p< HPCI/RCIC p> HPCI/RCIC PLANNED ISOLATION ISOLATION OPERATION SETPOINT SETPOINT SHUTDOWN LOW REACTOR REACTOR TCV COOLING WATER PROTECTION PROTECTION FAST RPT LEVEL SYSTEM SYSTEM CLOSURE TRANSFER MSRV ESF DECAY SYSTEM HEAT TO DETECTION START HPCI, RCIC ON S F LOW WATER LEVEL SUPPRESSION CIRCUITRY POOL S F STANDBY INSERT CONTROL ROD POWER PRESSURE MAINTAIN AC POWER CONTROL HPCI RCIC DRIVE SYSTEM REDUCTION RELIEF WATER LEVEL SYSTEM RODS S F INITIAL RESTORE CORE SCRAM AC POWER COOLING RHR PCRVIC SUPPRESSION SYSTEM POOL COOLING MODE SUPPRESSION POOL CLOSE ON TEMPERATURE LIMIT LOSS OF START DEPRESSURIZATION CONDENSER MSIVs VACUUM MSRV p SYSTEM ADS p
S F S F REACTOR CONTAINMENT VESSEL ISOLATION ISOLATION MAINTAIN LPCI WATER LEVEL IN cs p REACTOR VESSEL p S F S F PLANNED OPERATION LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR LOSS OF NORMAL AC POWER (GRID CONNECTION LOSS)
FIGURE 15.9-36
EVENT 30 GENERATOR TRIP WITH BYPASS FAILURE STATED BELOW TCV CLOSURE ABOVE TCV CLOSURE SCRAM BYPASS SETPOINT SCRAM BYPASS SETPOINT SCRAM SIGNAL:
REACTOR SCRAM SIGNALS: TURBINE REACTOR INITIATE ESF PROTECTION 1. HIGH PRESSURE CONTROL PROTECTION HPCI, RCIC, DETECTION SYSTEM 2. HIGH FLUX VALVE FAST SYSTEM ADS ON LOW CIRCUITRY CLOSURE WATER LEVEL S F S F S F TURBINE CONTROL CONTROL SEE CONTROL INSERT ROD DRIVE VALVE FIGURE 15.9-35 MSRV PCRVIC RPT ROD DRIVE CONTROL SYSTEM FAST SYSTEM RODS SYSTEM SYSTEM CLOSURE S F S F S F S F S F SCRAM POWER PRESSURE SCRAM CONTAINMENT REDUCTION RELIEF ISOLATION LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR MAIN GENERATOR TRIP WITH BYPASS SYSTEM FAILURE FIGURE 15.9-37
EVENT 31 MAIN TURBINE TRIP WITH BYPASS FAILURE STATED BELOW TSV CLOSURE ABOVE TSV CLOSURE SCRAM BYPASS SETPOINT SCRAM BYPASS SETPOINT REACTOR SCRAM SIGNALS: SCRAM SIGNAL: REACTOR INITIATE ESF PROTECTION 1. HIGH PRESSURE TURBINE STOP PROTECTION HPCI, RCIC, DETECTION SYSTEM 2. HIGH FLUX VALVE CLOSURE SYSTEM ADS ON LOW CIRCUITRY WATER LEVEL S F S F S F CONTROL TURBINE SEE CONTROL INSERT ROD DRIVE STOP FIGURE 15.9-35 MSRV PCRVIC RPT ROD DRIVE CONTROL SYSTEM VALVE SYSTEM SYSTEM SYSTEM RODS CLOSURE S F S F S F S F S F SCRAM POWER PRESSURE SCRAM CONTAINMENT REDUCTION RELIEF ISOLATION LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR MAIN TURBINE TRIP WITH BYPASS SYSTEM FAILURE FIGURE 15.9-38
EVENT 32 INADVERTENT LOADING AND OPERATION - FUEL ASSEMBLY IN IMPROPER POSITION STATES A, B, C, D PLANNED OPERATION LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCE FOR INADVERTENT LOADING AND OPERATION OF FUEL ASSEMBLY IN IMPROPER POSITION FIGURE 15.9-39
EVENT 38 RECIRCULATION PUMP SEIZURE STATED ONLY
< TSV SCRAM > TSV SCRAM BYPASS SETPOINT BYPASS SETPOINT MSRV SYSTEM S F INITIATE SCRAM REACTOR SIGNAL ESF HPCI, PROTECTION FROM RCIC ON PCRVIC DETECTION TURBINE LOW SYSTEM SYSTEM CIRCUITRY TRIP WATER LEVEL S F S F S F REACTOR LOW PROTECTION WATER RPT TURBINE PRESSURE SYSTEM LEVEL TRIP RELIEF S F S F INSERT CONTROL MAIN-CONTROL ROD DRIVE RCIC TAIN HPCI RODS SYSTEM WATER LEVEL S F S F INITIAL SCRAM CORE COOLING PLANNED OPERATION LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR RECIRCULATION PUMP SEIZURE FIGURE 15.9-40
EVENT 39 RECIRCULATION PUMP SHAFT BREAK STATED ONLY
< TSV SCRAM > TSV SCRAM BYPASS SETPOINT BYPASS SETPOINT MSRV SYSTEM S F SCRAM INITIATE REACTOR SIGNAL ESF HPCI, PROTECTION FROM RCIC ON PCRVJC DETECTION TURBINE LOW SYSTEM SYSTEM CIRCUITRY TRIP WATER LEVEL S F S F S F REACTOR LOW PROTECTION WATER RPT TURBINE PRESSURE SYSTEM LEVEL TRIP RELIEF S F S F INSERT CONTROL MAIN-CONTROL ROD DRIVE RCIC TAIN HPCI RODS SYSTEM WATER LEVEL S F S F INITIAL SCRAM CORE COOLING PLANNED OPERATION LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR RECIRCULATION PUMP SHAFT BREAK FIGURE 15.9-41
EVENT 40 CONTROL ROD DROP ACCIDENT STATES BAND D STATES BAND D STATED ONLY HIGH NEUTRON NEUTRON MONITORING FLUX SYSTEM SIGNAL S F RADIATION MONITOR TRIP CONTROL SCRAM MAIN PRIMARY INITIATE ROD REACTOR SIGNAL ON STEAM LINE CONTAINMENT HPCI, RCIC, MSRV ESF DETECTION CONTROL ROOM VELOCITY PROTECTION NEUTRON RADIATION AND REACTOR ADS ON SYSTEM CIRCUITRY HVAC SYSTEM LIMITER SYSTEM MONITORING MONITORING VESSEL ISOLATION LOW WATER (PASSIVE) SYSTEM TRIP SYSTEM CONTROL SYSTEM LEVEL S F S F S F S F S F SEE FIGURE 15.9-35 CONTROL CONTROL ROD INSERT PRESSURE ROOM CONTROL MSIVs RELIEF ENVIRONMENTAL DRIVE SYSTEM RODS CONTROL S F S F LIMIT LIMERICK GENERATING STATION REACTOR UNITS 1 AND 2 REACTIVITY CONTAINMENT SCRAM VESSEL INSERTION ISOLATION UPDATED FINAL SAFETY ANALYSIS REPORT ISOLATION RATE PROTECTION SEQUENCES FOR CONTROL ROD DROP ACCIDENT Rev. 15, 09/10 FIGURE 15.9-42
EVENT41 FUEL HANDLING ACCIDENT STATES A, B, C, l,ND D FUELING AHEA CONTROL VENTILATION ROOM HEATING RAD,ATiON RADIATION RADIAT!ON V !::~!Ti LA TING MONTOHiNG MONITOR TR IP MONITOR TRIP ,"-,NO AIR CONDI-SYS-.fEM TIQi,JiNG SYSTEM
/ \
CONTROL REFUEli~JG AREA n11TIATE RfFUlLING flOOM ISOLATION FLOOR ISOLATION ENVIRONMENTAL CONTROL SYSTEM CONTFWL STANDBY GAS TREATMENT SYSTEM F
REFUELING
{PASSIVE)
SECONDARY CONTAIMViENT ISOLATION LIMERICK GENERATING STATION Note: UNITS 1 AND 2 The application of Alternative Source Terms per Regulatory UPDATED F!Nt\.L SAFETY ANALYSIS REPORT Guide 1.183 no longer requires refuel area isolation, or use of Standby Gas Treatment System for certain activities that could result in a fuel handling accident. See LGS Technical ION SEQUENCES FOR Specifications for SGTS and isolation requirements.
FUEL Hfl,NDLING .ACCIDENT FIGURE 5.9-43 REV. 14, 09/08
EVENT 42 PIPE BREAK INSIDE CONTAINMENT STATES C D STATED ONLY CONTROL ROD SMALL DRIVE HOUSING BREAKS ONLY SCRAM RUPTURE SIGNAL RHR CONTROL ON LOW CONTROL ROD LARGE BREAKS REACTOR SUPPRESSION ROOM HEATING, RADIATION OTHER BREAKS WATER PCRVIC PCRVIC DRIVE HOUSING MSRV PROTECTION POOL VENTILATING AND MONITOR LEVEL OR SYSTEM SYSTEM SUPPORT SYSTEM HIGH SYSTEM COOLING MODE AIR CONDITIONING TRIP (PASSIVE)
DRYWELL p SYSTEM PRESSURE s F s F S F s F SEE FIGURE 15.9-35 REACTOR SUPPRESSION ONTROL ROO CONTROL ROD ENCLOSURE STOP ROD PRESSURE MSIVs POOL NVIRONMENT DRIVE SYSTEM ISOLATION EJECTION RELIEF COOLING CONTROL SYSTEM s F s F CONTAINMENT REACTOR ONE CS REQUIRED SCRAM (PASSIVE) ENCLOSURE LPCI cs FOR LONG-TERM PASSIVE COOLING S F S F STANDBY GAS INITIAL TREATMENT CORE SYSTEM COOLING AHR SUPPRESSION POOL COOLING p MODE RERS EXTENDED CORE COOLING LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR LOSS-OF-COOLANT PIPING BREAKS IN RCPB INSIDE CONTAINMENT FIGURE 15.9-44
EVENT 43, 44, 45 PIPING BREAKS OUTSIDE CONTAINMENT STATES C AND D STATED ONLY STATES C,D OTHER PROCESS RHR SHUTDOWN LINE BREAKS COOLING BREAK TRANSFER INITIATE DECAY CONTROL RADIATION ESF MSRV ROOM HPCI, RCIC ESF HEAT TO MONITOR BREAKS DETECTION ADS ON DETECTION SYSTEM SUPPRESSION HVAC TRIP RESULTING CIRCUITRY LOW WATER CIRCUITRY POOL SYSTEM IN AUTOMATIC BREAKS REQUIRING LEVEL ISOLATION MANUAL ISOLATION S F S F S F S F SCRAM SIGNAL FLOW REACTOR ON LOW WATER PCRVIC BREAK RESTRICTORS PROTECTION LEVEL OR MAIN SYSTEM ISOLATED LPCI cs (PASSIVE) SYSTEM STEAM LINE ISOLATION S F S F S F S F SEE FIGURE 15.9-35 CONTROL ROD DRIVE MSIVs SYSTEM S F RHR RESTRICT SU.PPRESSION ONTROL LOSS OF QOM EN- REACTOR POOL COOLING PRESSURE REACTOR ONMENT SCRAM VESSEL MODE RELIEF COOLANT ONTROL ISOLATION (PASSIVE)
SUPPRESSION POOL TEMPERATURE LIMIT START DEPRESSURIZATION MSRV ADS SYSTEM p p S F S F EXTENDED CORE COOLING LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS- REPORT PROTECTION SEQUENCES FOR PIPING BREAKS OUTSIDE CONTAINMENT FIGURE 15.9-46
EVENT 46 GASEOUS RADWASTE SYSTEM LEAK OR FAILURE STATES C AND D OFFGAS MANUAL SYSTEM .,._ ISOLATION p
BREAK ISOLATED SEE LOSS OF CONDENSER VACUUM EVENT 26 FIGURE 15.9-33 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR GASEOUS RADWASTE SYSTEM LEAK OR FAILURE FIGURE 15....
EVENT 47 AUGMENTED OFFGAS TREATMENT SYSTEM FAILURE STATES C AND D OFFGAS .,_ MANUAL SYSTEM ISOLATION p
BREAK ISOLATED SEE LOSS OF CONDENSER VACUUM EVENT 26 FIGURE 15.9-33 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR AUGMENTED OFFGAS TREATMENT SYSTEM FAILURE Pll:1111 . . . .
EVENT 48 LIQUID RADWASTE SYSTEM LEAK OR FAILURE STATES A, B, C, D GAS LEAK LIQUID LEAK PROCESS FLOOR DRAIN RADIATION HIGH RADIATION HIGH WATER MONITORING MONITORING SIGNAL SIGNAL SYSTEM SYSTEM FLOOR DRAIN HVAC AUTO OR AUTO OR COLLECTION SYSTEM MANUAL MANUAL AND PROCESSING SYSTEM HVAC CONTAIN SYSTEM LIQUID ISOLATION EFFLUENT LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR LIQUID RADWASTE SYSTEM LEAK OR FAILURE FIGURE 15.9-48
EVENT 49 LIQUID RADWASTE SYSTEM STORAGE TANK FAILURE STATES A, B, C, D GAS LEAK LIQUID LEAK PROCESS HIGH FLOOR DRAIN HIGH RADIATION RADIATION MONITORING WATER MONITORING SIGNAL SYSTEM SIGNAL SYSTEM FLOOR DRAIN COLLECTION HVAC AND SYSTEM PROCESSING p SYSTEM HVAC CONTAIN SYSTEM LIQUID ISOLATION EFFLUENT LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR LIQUID RADWASTE SYSTEM-STORAGE TANK FAILURE FIGURE 15.M9
EVENT50 SHlf'PING CASK DROP STATES A, B, C, D REFUELING AREA EXTERNAL VENTILATION SERVICE SPRAY OR RADIATION RADIATION WATER INTERNAL MONITOR TRIP MONITORING SYSTEM COOLING SYSTEMS p ESTABLISHED REFUELING AREA AUTO OR HVAC MANUAL SYSTEM ISOLATION STANDBY GAS TREATMENT SYSTEM p
REFUELING AREA (PASSIVE)
REFUELING RESTORE TEMPORARY AREA CASK CONTAINMENT ISOLATION COOLING LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR SHIPPING CASK DROP FIGURE 16.*50
EVENT 51 REACTOR SHUTDOWN FROM ANTICIPATED TRANSi ENT WITHOUT SCRAM, STATED NMS START HPCI, RCIC ESF TRANSFER APRM INPUTS HEAT TO MSRV SYSTEM DETECTION RRCS SYSTEM ON LOW CIRCUITRY SUPPRESSION NBS PRESSURE, POOL WATER LEVEL INPUTS LEVEL CONTROL STANDBY MAINTAIN ROD DRIVE LIQUID WATER HPCI RCIC SYSTEM CONTROL LEVEL (ARI) SYSTEM RHR REMOVE HEAT NUCLEAR SUPPRESSION FROM POOL COOLING SUPPRESSION POOL p MODE INITIATED MSRV FEEDWATER ON HIGH SYSTEM ATWS/RPT RUNBACK PRESSURE p ONLY RHR SHUTDOWN COOLING MODE p
CORE COOLING LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR REACTOR SHUTDOWN/ATW S FIGURE 15. 9-51
EVENT 52 REACTOR SHUTDOWN FROM OUTSIDE CONTROL ROOM STATES B, C, D STATES B, D STATES C, D SCRAM BY ISOLATE BY REACTOR DE-ENERGIZING PCRVIC DE-ENERGIZING PROTECTION SYSTEM SYSTEM SYSTEM SYSTEM MANUALLY MANUALLY p p
p<SDC INTERLOCK SETPOINT TRANSFER DECAY CONTROL ROD MSRV HEAT TO MSIVs DRIVE SYSTEM SYSTEM SUPPRESSION MAINTAIN POOL RCIC WATER LEVEL p
REACTOR PRESSURE SCRAM VESSEL RELi EF RHR REMOVE ISOLATION SUPPRESSION DECAY POOL HEAT FROM COOLING MODE SUPPRESSION p POOL MSRV SYSTEM p
RHR SHUTDOWN COOLING MODE p
OOL DOW REACTOR OM OUTSI CONTRO ROOM LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR REACTOR SHUTDOWN FROM OUTSIDE CONTROL ROOM FtGURE 15.9-52
EVENT 53 REACTOR SHUTDOWN WITHOUT CONTROL RODS STATES BAND D STANDBY LIQUID CONTROL SYSTEM p
NUCLEAR SHUTDOWN BOP IS CONTROLLED BY NORMAL OPERATION LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR REACTOR SHUTDOWN WITHOUT CONTROL RODS FIGURE 15.9-53