ML22278A265
Text
'-'UCLEAR SAFETY UNACCEPTABLE RESULTS DESIGN CRITERIA..... ------------------1 PLANT SYSTEMS AS DESIGNED AND INSTALLED NUCLEAR SAFETY OPERATIONAL CRITERIA RULES FOR EVENT ANAL VSIS OPERATIONAL ANALYSIS IDENTIFICATION OF SAFETY ACTIONS ESSENTIAL TO AVOIDING UNACCEPTABLE RESULTS (EACH STATE)
IDENTIFICATION OF SYSTEMS AND 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 IDENTIFY ALLOWABLE REPAIR TIMES WHEN SYSTEM INOPERABLE (LIMITING CONDITION FOR OPERATION)
SIMPLIFICATION REDUNDANCY REQUIREMENT (SACFI AVAILABILITY CONSIDERATIONS 1 A~O~O BE TAK~l;-i I OPERATIONAL REQUIRE* I L.. ~~OT S~:.!,D -I r----- -------- --------
1 SYSTEM LEVEL
~-S-Y-ST_E_M.a.*L_E_V_E _L -~
I SYSTUJ LEVEL I
p~~~\1;:;~v/v I
QUALITATIVE PLArH DESIGN BASIS CONFIRMATIOI-J QUALITATIVE SYSTEM DESIGN BASIS CONFIRMATION I
TECHNICAL SPECIFICATIONS 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 A 1ST PROTECTION LEVEL OPERATIONAL 2ND PROTECTION REQUIREMENT LEVEL EVENT CATEGORY 1 EVENT A L---....L..----1 EVENT B PROTECTION LEVEL 1 PROTECTION LEVEL 1 3RD PROTECTION PROTECTION LEVEL OPERATIONAL LEVEL 2.
PROTECTION LEVEL 2
+------ REQUIREMENT SCRAM 4TH PROTECTION LEVEL 5TH PROTECTION LEVEL PROTECTION PROTECTION LEVEL 3 LEVEL 3 PROTECTION OPERATIONAL PL~~~iCtON LEVEL 4 REQUIREMENT SCRAM OPERATIONAL 6TH PROTECTION REQUIREMENT LEVEL IT IS INCONSISTENT TO PLACE OPERATIONAL REQUIREMENTS ON SEPARATED LEVELS OF PROTECTION FOR ANY ONE EVENT PANEL A IT IS INCONSISTENT TO PLACE OPERATIONAL REQUIREMENTS ARBITRARILY ON SOME ACTION (SCRAM) IN ALL CASES OF ONE EVENT CATEGORY.
BECAUSE THAT ACTION (SCRAM) MAY REPRESENT DIFFERENT LEVELS OF PROTECTION FOR THE VARIOUS CASES.
PANEL B SINGLE EQUIPMENT MALFUNCTION SINGLE OPERATOR ERROR SINGLE OPERATOR ERROR ADDITIONAL EQUIPMENT MALFUNCTION EVENT A 1ST PROTECTION LEVEL OPERATIONAL ~~gTECTION REQUIREMENT LEVEL 3RD PROTECTION LEVEL SINGLE OPERATOR ERROR EVENT B 1ST PROTECTION LEVEL OPERATIONAL p~gTECTION REQUIREMENT LEVEL 3RD PROTECTION 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
INTENTIONALL V LEFT BLANK LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 11.9-3
SAFETY SYSTEM Q
DIFFERENT PLANT CONDITION SAFETY SYSTEM s
SAFETY SYSTEM SAFETY SYSTEM R
NUMBER OF EVENT STATES IN WHICH THIS PROTECTION SEQUENCE IS APPLICABLE DIFFERENT PLANT CONDITION INDICATES THAT SYSTEMS Q AND R SHARE AS A PAIR THE REQUIREMENT TO MEET THE SINGLE FAILURE CRITERION PERSONNEL SAFETY SYSTEM u
S F
(MANUAL) ~
SAFETY.
ACTION
..-, SYSTEM/'....._
REQUIRED FOR
( P } W
( L)'
SYSTEM W
'-./
SYSTEMS MUST ITSELF MEET THE SINGLE FAILURE CRITERION S
F T
r...._
INDICATES THAT ONE OR MORE OF l ~)
THE KEY PROCESS PARAMETERS MUST BE LIMITED TO SATISFY NUCLEAR
~
S;FETY OPERATIONAL CRITERIA S
F SAFETY ACTION A
~
INDICATES THAT RESTRICTIONS ARE PLACED ON CERTAIN PLANT EQUIPMENT EACH CONNECTED PROTECTION SEQUENCE IS FOR JUST ONE SAFETY ACTION SAFETY ACTION B
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
DIAGRAM INDICATES THAT AUXILIARIES A, BAND CARE ESSENTIAL TO THE OPERATION OF THE FRONT LINE SAFETY SYSTEM X.
NO CHRONOLOGY OR ORDER OF ACTION IS IMPLIED I
FRONT LINE SAFETY SYSTEM X
AUXILIARY SYSTEM A
AUXILIARY SYSTEM B
AUXILIARY SYSTEM C
LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT FORMAT FOR SAFETY SYSTEM AUXILIARY DIAGRAMS
INTENTIONALL V LEFT BLANK LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.9-6
HPCI I
DC POWER SYSTEM -
I SUPPRESSION POOL STORAGE (PASSIVE) -
RCIC I
DC POWER SYSTEM I
SUPPRESSION POOL STORAGE -
(PASSIVE)
CONTROL LOGIC, VALVE POWER, LUBE OIL PUMP WATER SUPPLY FOR HPCI PUMP AND EXHAUST CONDENSING ADS SUPPRESSION POOL STORAGE (PASSIVE)
DC POWER SYSTEM STEAM CONDENSATION RELIEF VALVE
- CONTROLS, SENSORS, LOGIC AND SOLENOIDS ACCUML.LATORS FOR SHC RT TERM PCIG/INSTRUMENT AIR SYSTEMS FOR LONGTERM CONTROL LOGIC, VAL VE POWER, LUBE OIL PUMP WATER SUPPLY FOR RCIC PUMP AND EXHAUST CONDENSING RHR SUPPRESSION POOL COOLING AC POWER SYSTEM DC POWER SYSTEM PLANT J RHR SERVICE PUMP WATER COOLERS SYSTEM RHRSERVICE WATER SYSTEM EQUIPMENT AREA COOLING SUPPRESSION POOL STORAGE (PASSIVE)
VALVE AND PUMP POWER PUMP BREAKE CONTROL AND CONTROL LOG EMERGENCY SERVICE WATER SYSTEM RHR HEAT EXCHANGERS COOL AREA AROUND RHR EAUIPMENT R
IC WATER SUPPLY FOR RHR PUMP l
PLANT SERVICE WATER SYSTEM I
STANDBY LIQUID CONTROL SYSTEM I
AC POWER SYSTEM I
REDUNDANT REACTIVITY CONTROL SYSTEM RHR SHUTDOWN COOLING I
AC POWER SYSTEM I
DC POWER SYSTEM I
-PUMP-COOLERS I
EQUIPMENT AREA COOLING I
RHR SERVICE WATER SYSTEM PUMP POWER TANK HEATERS VALVE FIRING CIRCUITS AUTOMATIC INITIATION LOGIC
~~~'::t!E R BREAKER
- CONTROL, CONTROL LOGIC I
EMERGENCY SERVICE WATER SYSTEM I
AR0UNDRH EQUIPMENT RHR HEAT EXCHANGER s NEUTRON MONITORING SYSTEM I
AC POWER SYSTEM I
I DC PO\NER SYSTEM I
l PLANT RHR SERVICE i---PUMP-WATER COOLERS SYSTEM I
I EQUIPMENT AREA COOLING I
SUPPRESSION POOL STA0RAGE (PASSIVE)
VALVE AND PUMP POWER BREAKER
- CONTROL, CONTROL LOGIC I
EMERGENCY SERVICE WATER SYSTEM I
COOL AREA OF ENT RHR EQUIPM WATER SUPPLY T0RHR LPCI
(
)
PUMPS cs AC POWER SYSTEM DC POWER SYSTEM EQUIPMENT AREAC OLING SUPPRESSION POOL STORAGE (PASSIVE)
MSRV SYSTEM I
SUPPRESSION POOL STORAGE (PASSIVE)
VALVE AND PUMP POWER BREAKER
- CONTROL, CONTROL LOGIC COOLING AREA OFCORE SPRAY EQUIPMENT WATER SUPPLY TO PUMPS STEAM CONDENSATION LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SAFETY SYSTEM AUXILIARIES FIGURE 15.9-7 Rev. 11 9/02 I
AC POWER SYSTEM PRIMARY CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM DC POWER SYSTEM VALVE POWER OFFSITE AC POWER SYSTEM DC POWER SYSTEM RPS CAD REDUNDANT REACTIVITY CONTROL SYSTEM I
AC POWER SYSTEM I
DC POWER SYSTEM CONTROL LOGIC DC POWER SYSTEM BREAKER CONTROL FAIL SAFE FAIL SAFE SCRAM FUNCTION AREA ISOLATION CONTAINMENT CONTROL
{PASSIVE)
SYSTEM(S)
SUPPA ESSION DC POWER POOL PRESSURE CONTROL SYSTEM STORAGE SUPPRESSION LOGIC PLANT
{PASSIVE)
SERVICE WATER SYSTEM DRYWELL/
DRYWELL SUPPRESSION AC POWER EQUIPMENT VACUUM POOL SYSTEM POWER RELIEF DIFFERENTIAL SYSTEM PRESSURE CONTROL PCRVIC CONTAINMENT SYSTEM ISOLATION ESF DETECTION INITIATES MSL CIRCUITRY ESF SYSTEMS LEAKAGE PATHWAY CONTROL DC POWER CONTROL SYSTEM LOGIC DC POWER CONTROL SYSTEM LOGIC REACTOR MANUAL CONTROL SYSTEM AC POWER VALVE SYSTEM POWER AC POWER CONTROL ROOM HEATING VENTILATING AND AIR CONDITIONING SYSTEM CONTROL EMERGENCY STRUCTURE SERVICE CHILLED WATER WATER SYSTEM DC POWER CONTROL SYSTEM POWER VALVE AND ACPOWER PUMP POWER.
SYSTEM POWER TO AIR CONDITIONING EQUIPMENT STANDBY GAS TREATMENT SYSTEM DC POWER CONTROL AC POWER SYSTEM STANDBY AC POWER SYSTEM DC POWER SYSTEM CONTAINMENT HYDROGEN CONTROL SYSTEM DC POWER CONTROL SYSTEM POWER VALVE AND AC POWER BLOWER SYSTEM POWER OFFSITE AC POWER SYSTEM PLANT SERVICE BREAKER CONTROL AND WATER SYSTEM CONTROL LOGIC PLANT EQUIPMENT AREA COOLING AC POWER SYSTEM DC POWER SYSTEM ALTERNATE ROOM COOLING EMERGENCY SERVICE WATER SYSTEM POWER TO BLOWERS CONTROL POWER PLANT STANDBY AC HVAC POWER SYSTEM SYSTEM(S)
RADIATION SYSTEM SYSTEM LOGIC MONITORING DC POWER SYSTEM EMERGENCY SERVICE WATER SYSTEM DIESEL GENERATOR AUXILIARIES BREAKER CONTROL.
CONTROL LOGIC COOL DIESELS SUPPORT DIESELS REACTOR ENCLOSURE (PASSIVE) sas SYSTEM REAS DC POWER SYSTEM AC POWER SYSTEM ISOLATION AIR FLOW AND PRESSURE CONTROL CONTROL POWER EQUIPMENT POWER DC POWER SYSl'EM ROD BLOCK MONITOR ROD WORTH MINIMIZER CAD AC POWER SYSTEM REACTOR ENCLOSURE HVAC (PASSIVE)
OFFGAS SYSTEM AC POWER SYSTEM I
DC POWER SYSTEM I
DELIVER POWER TO BLOWERS AND HEATERS OOUNG ATER TO ECOMBINER
-w R
RESIDUAL HEAT REMOVAL SYSTEM DRYWELL RECIRCULA-TION SYSTEM LIQUID WASTE MANAGEMENT SYSTEM AC POWER SYSTEM COOLING WATER TO RECOMBINERS HYDROGEN MIXING EQUIPMENT DRAINS FLOOR DRAINS CONTROL LOGIC SYSTEM(S)
DC POWER SYSTEM AC POWER SYSTEM CONTROL LOGIC DC POWER SYSTEM AC POWER SYSTEM CONTROL LOGIC LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SAFETY SYSTEM AUXILIARIES FIGURE 15.9-8 Rev. 11 9/02
L L
EVENTS 1, 2 AND 6 LIQUID RADWASTE SYSTEM SOLID RADWASTE SYSTEM REFUELING FLOOR VENTILATION RADIATION MONITORING L
SYSTEM RADIOACTIVE MATERIAL RELEASE CONTROL 10CFR20 10CFR50 LIMIT 10 CFR 71 LIMIT APPLIED TO SHIPPING CASKS L
EVENTS 1, 2 AND 6 REACTOR FUEL REACTOR VESSEL WATER LEVEL CONTROL MONITOR ACTIVITY RELEASE THROUGH VENTILATING SYSTEM EVENTS 1, 2 AND 6 MINIMUM WATER LEVEL TO AVOID EXCESS TEMPERATURE L
REACTOR VESSEL NUCLEAR SYSTEM TEMPERATURE CONTROL STATE A NORMAL OPERATION EVENTS 1, 2 AND 6 L
EVENTS 1, 2 AND 6 REACTOR COOLANT NUCLEAR SYSTEM WATER QUALITY CONTROL WATER CHEMISTRY LIMIT MINIMUM TEMPERATURE TO BOLT DOWN VESSEL HEAD EVENT 1
CORE LOADING REACTOR PATTERN FUEL L
EVENTS 1, 2 AND 6 CORE REACTIVITY CONTROL R
R L
EVENT 1
CONTROL ROD DRIVE SYSTEM REACTOR FUEL REFUELING RESTRICTIONS EVENTS 1, 2 AND 6 CONTROL ROD DRIVE SYSTEM PROCEDURAL RESTRICTIONS (CONTROL ROD POSITION)
PROCEDURAL RESTRICTIONS (FUEL ASSEMBLY ORIENTATION)
LIMIT ON NUMBER OF DRIVES VALVED OUT OF SERVICE L
EVENTS 1, 2 AND 6 FUEL STORAGE FACILITIES STORED FUEL SHIELDING COOLING AND REACTIVITY CONTROL WATER TEMPERATURE WATER LEVEL FUEL HANDLING FUEL SPACING LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SAFETY ACTION SEQUENCES FOR NORMAL OPERATION IN STATE A FIGURE 15.9-9
L L
EVENTS 2 AND 5 LIQUID RADWASTE SYSTEM SOLID RADWASTE SYSTEM REFUELING FLOOR VENTILATION RADIATION MONITORING L
SYSTEM RADIOACTIVE MATERIAL RELEASE CONTROL 10CFR 20 10 CFR 50 LIMIT 10 CFR 71 LIMIT APPLIED TO SHIPPING CASK MONITOR ACTIVITY RELEASE THROUGH VENTILATION SYSTEM L
EVENTS 2AND 5 REACTOR FUEL CORE POWER LEVEL CONTROL EVENTS 2 AND5 MINIMUM POWER (SRM)
MAXIMUM POWER L
REACTOR FUEL REACTOR VESSEL WATER LEVEL CONTROL STATE B NORMAL OPERATION EVENTS 2 AND 5 L
EVENTS 2AND5 REACTOR VESSEL NUCLEAR SYSTEM TEMPERATURE CONTROL MINIMUM WATER LEVEL EVENTS 2 AND 5 RATE OF CHANGE TEMPERATURE LIMIT L
REACTOR COOLANT NUCLEAR SYSTEM WATER QUALITY CONTROL EVENTS 2 AND 5 CONTROL ROD DRIVE SYSTEM CORE REACTIVITY CONTROL POSITIONING OF CONTROL ROD DURING CORE ALTERATION EVENT 2
L EVENTS 2 AND 5 WATER TEMPERATURE, WATER LEVEL, FUEL SPACING, AND FUEL HANDLING FUEL STORAGE FACILITIES WATER CHEMISTRY LIMIT STORED FUEL SHIELDING COOLING AND REACTIVITY CONTROL L
CONTROL ROD DRIVE SYSTEM ROD WORTH CONTROL ROD PATTERN RWM, RBM LIMERICK GENERATING STATION UNITS 1 ANO 2 UPDATED FINAL SAFETY ANALYSIS REPORT SAFETY ACTION SEQUENCES FOR NORMAL OPERATION IN STATE B FIGURE 15.9-10 Rev. 11 9/02
L L
LIQUID RADWASTE SYSTEM SOLID RADWASTE SYSTEM REFUELING FLOOR AND REACTOR ENCLOSURE VENTILATION RADIATION MONITORING L
SYSTEM RADIOACTIVE MATERIAL RELEASE CONTROL L
REACTOR FUEL 10 CFR 20
~10CFR 50 LIMIT REACTOR VESSEL WATER LEVEL CONTROL 10 CFR 71
.,._ LIMIT APPLIED TO SHIPPING CASK MONITOR ACTIVITY
-- RELEASE THROUGH VENTILATING SYSTEM STATE C NORMAL OPE RATION EVENTS 2 AND 6 MINIMUM
.... WATER LEVEL L
L REACTOR VESSEL L
REACTOR VESSEL REACTOR FUEL NUCLEAR SYSTEM TEMPERATURE CONTROL TEMPERATURE RATE OF
--CHANGE, MINIMUM TEMPERATURE MAXIMUM
~FEEDWATER TEMPERATURE L
MAXIMUM
- PRESSURE,
--MINIMUM PRESSURIZATION REACTOR COOLANT TEMPERATURE L
MAXIMUM RHR SHUTDOWN
~
PRESSURE COOLING MODE LIMIT NUCLEAR SYSTEM WATER QUALITY CONTROL L
NUCLEAR SYSTEM PRESSURE CONTROL REACTOR VESSEL NUCLEAR SYSTEM LE.AKAGE CONTROL OVERSTRESS
..,_ PROTECTION AND MAKEUP CAPABILITY L
L CONTAINMENT (PASSIVE)
SUPPRESSION POOL STORAGE (PASSIVE)
CONTAINMENT PRESSURE AND TEMPERATURE CONTROL TEMPERATURE LIMIT
...., PRESSURE LIMIT WATER
~
TEMPERATURE AND VOLUME LIMIT L
FUEL STORAGE FACILITIES STORED FUEL SHIELDING COOLING AND REACTIVITY CONTROL WATER TEMPERATURE,
...., WATER LEVEL, FUEL SPACING, FUEL HANDLING WATER CHEMISTRY
-- LIMITS ACTIVITY LIMIT CONTROL ROD DRIVE SYSTEM NUMBER OF L
CORE REACTIVITY CONTROL
.,._ DRIVES VALVED OUT OF SERVICE LIMERICK GENERATING STATION UNITS 1 AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SAFETY ACTION SEQUENCES FOR NORMAL OPERATION IN STATE C FIGURE 15.9-11
EVENTS 2, 3, 4 AND 5 LIQUID RADWASTE L
SYSTEM L
OFFGAS SYSTEM SOLID RADWASTE L SYSTEM REFUELING FLOOR AND REACTOR ENCLOSURE VENTILATION RADIATION MONITORING SYSTEM L
RADIOACTIVE MATERIAL RELEASE CONTROL 10 CFR 20 10 CFR 50 LIMIT 10 CFR 20 10 CFR 50 LIMIT EVENTS 3, 4 AND 5 10 CFR 71 LIMIT APPLIED TO SHIPPING CASK EVENTS 2, 3,4 AND 5 REACTOR FUEL L
CORE POWER LEVEL CONTROL EVENTS 2, 3,4AND 5 MINIMUM POWER (SRM)
MAXIMUM L
POWER EVENTS 2, 3,4 AND 5, REACTOR FUEL REACTOR VESSEL WATER LEVEL CONTROL STATED NORMAL OPERATION EVENTS 2, 3, 4 AND 5 EVENTS 2, EVENTS 2, 3,4 AND 5 3, 4 AND 5 MINIMUM WATER LEVEL EVENTS EVENTS 3AND4 2 AND5 AHR SHUTDOWN MAXIMUM COOLING PRESSURE L MODE LIMIT EVE~TS 2, EVENTS 2, EVENTS 2, EVENTS 2, 3, 4 AND 5 3, 4 AND 5 3, 4 AND 5 3,4 AND 5 OVER-STRESS PROTEC-CONTROL ROD REACTOR VESSEL TION DRIVE L
MAKEUP L SYSTEM CAPABI-LITY NUCLEAR SYSTEM LEAKAGE CONTROL WATER NUMBER REACTOR CHEMISTRY CONTROL ROD DRIVES COOLANT LIMIT DRIVE OUTOF L
ACTIVITY L SYSTEM SERVICE LIMIT MAXIMUM PRESSURE REACTOR MONITOR ACTIVITY RELEASE THROUGH VENTILATION SYSTEM------......
L REACTOR FUEL CORE COOLANT FLOW RATE CONTROL MINIMUM FLOW RATE L
LIMIT REACTOR FUEL CORE NEUTRON FLUX DISTRI-BUTION CONTROL VESSEL L
POWER PEAKING L
NUCLEAR SYSTEM PRESSURE CONTROL REACTOR VESSEL NUCLEAR CORE MAXIMUM SYSTEM PRESSURE WATER QUALITY REACTIVITY LIMIT L
L REACTOR VESSEL REACTOR FUEL CONTROL RATE OF TEMPERATURE CHANGE MINIMUM TEMPERATURE WITH HEAD ON MAXIMUM FEEDWATER TEMPERATURE EVENT 2 EVENTS 3, 4 AND 5 REACTOR RECIRCULATION L
SYSTEM NUCLEAR SYSTEM TEMPERATURE CONTROL MAXIMUM TEMPERATURE DIFFERENCE IN RECIRCU-LATION LOOPS CONTROL EVENTS 2, EVENTS 2, 3, 4 AND 5 3, 4 AND 5 ROD WATER PATTERN FUEL TEMPERATURE CONTROL STORAGE WATER LEVEL
- RWM, LFACILITIES FUEL SPACING RBM FUEL HANDLING STORED FUEL SHIELDING, COOLING AND REACTIVITY CONTROL TEMPERATURE CONTAINMENT AND (PASSIVE)
L SUPPRESSION POOL STORAGE L (PASSIVE)
NTAINMEN MPERATUR PRESSURE CONTROL PRESSURE LIMITS WATER TEMPERATURE AND VOLUME LIMIT LIMERICK GENERATING STATION UNITS 1 ANO 2 UPDATED FINAL SAFETY ANALYSIS REPORT SAFETY SECTION SEQUENCES 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
REACTOR MODE SWITCH NOT IN RUN PLANNEC OPERATION SCRAM SIGNAL WHEN 3 MSIV's NOT FU LL OPEN INSERT CONTROL-----
ROD REACTOR MODE SWITCH IN RUN REACTOR PROTECTION SYSTEM S
F CONTROL ROD DRIVE SYSTEM S
F SCRAM EVENTS LOSS OF PLANT INSTRUMENT AND SERVICE AIR SYSTEM STATES A, B, C, D ESF DETECTION CIRCUITRY S
F SEE FIGURE 15.9-35 HIGH PRESSURE LIFTS VALVE TRANSFERRING HEAT TO SUP-PRESSION POOL INITIATE HPCI, RCIC, ADS ON LOW WATER LEVEL MSRV SYSTEM S
F PRESSURE RELIEF 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
PRESSURE REGULATOR OPERATING PLANNED OPERATION PRESSURE REGULATOR FAILS TO OPEN EVENT 9 INADVERTENT STARTUP NSSS PUMP STATES A, B, C AND D STATES B, D FEEDWATER CONTROLLER OPERATING SEE PLANNED EVENT OPERATION NO. 23 FEEDWATER CONTROLLER FAILS SEE EVENT NO. 22 STATES A, C PLANNED OPERATION LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCE FOR INADVERTENT STARTUP OF NSSS PUMP FIGURE 15.* 15
STATES B, D NEUTRON MONITORING SYSTEM APRM OR IRM HIGH FLUX SIGNAL SIGNAL< SETPOINT PLANNED OPERATION S
F SIGNAL> SETPOINT REACTOR PROTECTION SYSTEM S
F CONTROL ROD DRIVE SYSTEM S
F SCRAM EVENT10 STARTUP OF IDLE RECIRCULATION PUMPS STATES A, B, C, D SCRAM SIGNAL FROM NEUTRON MONITORING SYSTEM TRIP INSERT CONTROL RODS STATES A, C PLANNED OPERATION 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 MODE SWITCH IN RUN)
STATE C AND STATED (REACTOR MODE SWITCH NOT IN RUN)
NEUTRON MONITORING SYSTEM S
F CONTROL ROD DRIVE SYSTEM S
F SCRAM HIGH NEUTRON FLUX (APRM) TRIP SCRAM SIGNAL ON NEUTRON MONITORING SYSTEM TRIP INSERT CONTROL RODS PLANNED OPERATION LIMERICK GENERATING STATION UNITS 1 AND2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCE FOR RECIRCULATION LOOP FLOW CONTROL FAILURE (INCREASING FLOW)
MSRV SYSTEM S
F PRESSURE RELIEF EVENT12 RECIRCULATION LOOP FLOW CONTROL FAILURE (DECREASING FLOW)
STATES C AND D HIGH WATER LEVEL TURBINE TRIP STATED ONLY REACTOR PROTECTION SYSTEM S
F CONTROL ROD DRIVE SYSTEM S
F SCRAM SCRAM FROM TURBINE STOP VALVE CLOSURE INSERT CONTROL RODS HPCI NO HIGH WATER LEVEL TURBINE TRIP z
0
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<(
....I 0
CJ) a:
w I-LL.
<(
ESF DETECTION CIRCUITRY S
F S
F INITIAL CORE COOLING PLANNED OPERATION INITIATE HPCI, RCIC SYSTEM ON LOW WATER LEVEL RCIC PRIMARY CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM S
F CONTAINMENT ISOLATION INITIATE ISOLATION ON LOW WATER LEVEL LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCE FOR RECIRCULATION LOOP FLOW CONTROL FAILURE (DECREASING FLOW)
FIGURE 15.9-18
PLANNED OPERATION STATE C EVENT 13 RECIRCULATION LOOP PUMP TRIP (ONE OR BOTH)
STATES C AND D ONE PUMP TRIP STATED MSRV SYSTEM s F TWO PUMP TRIP HIGH WATER LEVEL TURBINE TRIP STATED ONLY REACTOR PROTECTION SYSTEM s F CONTROL ROD DRIVE SYSTEM S F SCRAM SCRAM FROM TURBINE STOP VALVE CLOSURE INSERT CONTROL RODS HPCI NO HIGH WATER LEVEL TURBINE TRIP AFTER ISOLATION ESF DETECTION CIRCUITRY s F INITIAL CORE COOLING PLANNED OPERATION INITIATE HPCI, RCIC SYSTEM ON LOW WATER LEVEL RCIC PRIMARY CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM s F CONTAINMENT ISOLATION INITIATE ISOLATION ON LOW WATER LEVEL LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR RECIRCULATION PUMP TRIP (ONE OR BOTH)
FIGURE 15.9-19
REACTOR MODE SWITCH NOT IN RUN SCRAM SIGNAL WHAN 3MSIVs NOT FULL OPEN PLANNED OPERATION INSERT CONTROL RODS REACTOR MODE SWITCH IN RUN REACTOR PROTECTION SYSTEM S
F EVENT14 INITIATE HPCI, RCIC, ADS ON LOWER WATER LEVEL CONTROL ROD DRIVE SYSTEM S
F SCRAM ESF DETECTION CIRCUITRY S
F SEE FIGURE 15.9-35 MSRV SYSTEM S
F PRESSURE RELIEF HEAT TO UPPRESSION POOL LIMERICK GENERATING STATION UNITS 2AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR ISOLATION OF ALL MAIN STEAM LINES FIGURE 15.9-20 Rev. 11 9/02
LESS THAN EVENT14 ISOLATION OF ONE MAIN STEAM LINE STATES C AND D APPROX. 90% POWER GREATER THAN APPROX. 90% POWER CONTINUE PLANNED OPERATION HIGH NEUTRON FLUX SIGNAL SCRAM SIGNAL ON NEUTRON MONITORING SYSTEM TRIP INSERT CONTROL RODS NEUTRON MONITORING SYSTEM S
F CONTROL ROD DRIVE SYSTEM S
F INITIATE
F PCRVIC SYSTEM S
F MSIVs S
F REACTOR VESSEL ISOLATION SEE FIGURE 15.~35 HIGH STEAM LINE FLOW MSRV SYSTEM S
F PRESSURE RELIEF HEAT TO SUPPRESSION POOL 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
PLANNED OPERATION STATE C EVENT15 DVERTENT OPEN OF AN MSRV STATES C AND D MSRV OPEN FOR< TIME LIMIT REACTOR PROTECTION SYSTEM S
F CONTROL ROD DRIVE SYSTEM S
>TIME LIMIT TIME LIMIT MODE SWITCH TO SHUTDOWN INSERT CONTROL RODS SUPPRESSION POOL TEMP-ERATURE LIMIT RHR SHUTDOWN COOLING MODE PLANNED OPERATION LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR INADVERTENT OPENING OF AN MSRV FIGURE 15.1-22
....J 0 <(
0~
er: <(
a:
wo ZI 01-
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PLANNED OPERATION EVENT16 CONTROL ROD WITHDRAWAL ERROR STARTUP AND REFUELING OPERATION STATES A AND B STATE A STATE B 0
0 a:
....J 0 a:
1-z 0
CJ 0 z 0
CJ w
Cl')
LL 0
....J
<(
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REACTOR MANUAL CONTROL SYSTEM S
F ROD BLOCK REACTOR MODE SWITCH "REFUEL" w a..
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<( CJ w l-a: ~
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NEUTRON MONITORING SYSTEM S
F CONTROL ROD DRIVE SYSTEM S
F SCRAM HIGH NEUTRON FLUX SIGNAL SCRAM SIGNAL ON NEUTRON MONITORING SYSTEM TRIP INSERT CONTROL RODS LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCE FOR CONTROL ROD WITHDRAWAL ERROR FOR STARTUP AND REFUELING OPERATIONS FIGURE 11.1-23
PLANNED OPERATION EVENT17 CONTROL ROD WITHDRAWAL ERROR POWER OPERATION STATES C AND D STATE C STATED REACTOR MODE SWITCH "STARTUP" NEUTRON MONITORING SYSTEM S
F CONTROL ROD DRIVE SYSTEM S
F SCRAM HIGH NEUTRON FLUX SIGNAL SCRAM SIGNAL FROM NMS TRIP INSERT CONTROL RODS ROD WORTH MINIMIZER ROD BLOCK REACTOR MODE SWITCH" RUN" POWER
< LOW POWER ALARM POINT POWER > LOW POWER ALARM POINT r
UNAUTHORIZED ROD WITHDRAWAL ACCEPTABLE DEVIATION FROM PLANNED OPERATION ROD BLOCK MONITOR ROD BLOCK LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCE FOR CONTROL ROD WITHDRAWAL ERROR-POWER OPERATION FIGUIIE15.I-M
LPCI p
s F
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 COOLING INTERLOCK PRESSURE MAINTAIN
- REACTOR_
WATER cs LEVEL p
s F
p MSRV SYSTEM S
F ST A TE C, P > SHUTDOWN COOLING INTERLOCK PRESSURE LPCI p
s F
MAINTAIN
~ DEPRES- -
SURIZATION ADS p
S F
RHR SUPPRESSION POOL COOLING p
MODE cs p
s F
PLANNED OPERATION LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PLANNED OPERATION PROTECTION SEQUENCES FOR RHR-LOSS OF SHUTDOWN COOLING FIGURE 11..1-21
AAND B PLANNED OPERATION EVENT19 AHR-SHUTDOWN COOLING INCREASED COOLING STATES A, B, C, AND D
)
C AND D PLANNED OPERATION LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR RHR (SHUTDOWN COOLING)
INCREASED COOLING FIGURE 15.9-26
STATED ONLY REACTOR PROTECTION SYSTEM S
F CONTROL ROD DRIVE SYSTEM s
F SCRAM INITIATE SCRAM ON LOW WATER LEVEL INSERT CONTROL RODS EVENT 20 LOSS OF ALL FEEDWATER FLOW STATES C AND D PRIMARY CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM s
F MSRV SYSTEM s
F PRESSURE RELIEF p < SHUTDOWN COOLING INTERLOCK SETPOINT PLANNED OPERATION SHUTDOWN COOLING TRANSFER DECAY HEAT TO SUPPRESSION POOL p > SHUTDOWN COOLING INTERLOCK SETPOINT p < HPCI/RCIC ISOLATION SETPOINT HPCI LPCI S
F p > HPCI/RCIC ISOLATION SETPOINT ESF DETECTION CIRCUITRY S
F MAINTAIN WATER LEVEL S
F INITIAL CORE COOLING RHR SUPPRESSION POOL COOLING MODE START HPt;I, ACIC ON LOWWATER LEVEL RCIC SUPPRESSION POOL TEMPERATURE LIMIT START DEPRESSURIZATION MSRV SYSTEM S
F MAINTAIN WATER LEVEL IN REACTOR VESSEL ADS S
F cs S
F LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PLANNED OPERATION PROTECTION SEQUENCES FOR LOSS OF FEEDWATER FLOW FIGURE 15.9-27
EVENT 21 LOSS OF A FEEDWATER HEATER STATED FLUX > SETPOINT FLUX < SETPOINT NEUTRON MONITORING SYSTEM S
F CONTROL ROD DRIVE SYSTEM S F SCRAM HIGH NEUTRON FLUX SIGNAL SCRAM SIGNAL ON NMS TRIP INSERT CONTROL RODS PLANNED OPERATION 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&
STATES A AND B STATED ONLY EVENT 22 FEEDWATER CONTROLLER FAILURE (MAXIMUM DEMAND)
STATES A, B, C AND D STATES C AND D POWER < TURBINE STOP VALVE CLOSURE SCRAM BYPASS SETPOINT POWER:> TURBINE STOP VALVE CLOSURE SCRAM BYPASS SETPOINT MODE SWITCH IN RUN PLANNED OPERATION PLANNED OPERATION MODE SWITCH NOT IN RUN NEUTRON MONITORING SYSTEM SCRAM SIGNAL REACTOR FROM TURBINE -
PROTECTION TRIP OR NMS SYSTEM S F CONTROL ROD DRIVE SYSTEM S F SCRAM RPT S F POWER REDUCTION PRIMARY CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM S
F CONTAINMENT ISOLATION
..,_ TURBINE STOP VALVE CLOSURE MSRV SYSTEM S
F PRESSURE RELIEF STATES A, B, C, D p< SHUTDOWN COOLING INTERLOCK SETPOINT I
PLANNED OPERATION SHUTDOWN COOLING TRANSFER
-- DECAY HEAT TO SUPPRESSION POOL STATES C, D p> SHUTDOWN COOLING INTERLOCK SETPOINT p< HPCI/RCIC ISOLATION SETPOINT I
HPCI I
p> HPCI/RCIC ISOLATION SETPOINT I
ESF DETECTION CIRCUITRY MAINTAIN
..... START HPCI, RCIC ON LOW WATER LEVEL I
~
WATER LEVEL -
RCIC INITIAL CORE COOLING I
I AHR SUPPRESSION POOL COOLING MODE I
SUPPRESSION POOL TEMPERATURE LIMIT START DEPRESSURIZATION MSRV P SYSTEM I
I LPCI p
s I F p
ADS s I F I
MAINTAIN I
-- WATER LEVEL IN -
CS REACTOR VESSEL p
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
MSRV SYSTEM S
F PRESSURE RELi EF STATED ONLY REACTOR PROTECTION SYSTEM S
F CONTROL ROD DRIVE SYSTEM S F SCRAM EVENT 23 PRESSURE REGULATOR FAILURE (OPEN)
STATES C AND D SCRAM SIGNAL FROM eMAIN STEAM LINE ISOLATION e TURBINE TRIP e LOW WATER LEVEL ESF DETECTION CIRCUITRY INITIATE HPCI, RCIC, ADS ON LOW WATER LEVEL PRIMARY CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM S F SEE FIGURE 15.9-35 INSERT CONTROL RODS MSIVs S F CLOSE ON LOW STEAM LINE PRESSURE REACTOR 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
PLANNED OPERATION ESF DETECTION CIRCUITRY S F SEE FIG. 15.9-35 EVENT 24 T PRESSURE REGUL FAILURE (CLOSED)
STATES C AND D SECOND PRESSURE REGULATOR OPERATES SECOND PRESSURE REGULATOR FAILS INITIATE HPCI, RCIC, ADS ON LOW WATER LEVEL NEUTRON-MONITORING SYSTEM REACTOR PROTECTION SYSTEM CONTROL ROD DRIVE SYSTEM SCRAM HIGH FLUX PRIMARY CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM CONTAINMENT ISOLATION MSRV SYSTEM PRESSURE RELIEF LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR PRESSURE REGULATOR FAILURE (CLOSED)
FIGURE 15.9-31
-0 I-z 0
- 0.
I-w Cl)
~
<(
- 0.
a:i
~
a:
~
w a:
Cl) 0 TURBINE
..J
(.)
STOP VALVE -
Cl)
CLOSURE I-
~
..J w
a:i PLANNED OPERATION ABOVE TSV CLOSURE SCRAM BYPASS SETPOINT RPT S
F POWER REDUCTION REACTOR PROTECTION SYSTEM S
F CONTROL ROD DRIVE SYSTEM S
F REACTIVITY CONTROL TURBINE
.. STOP VALVE CLOSURE INSERT
.. CONTROL RODS RCIC EVENT 25 TURBINE TRIP WITH BYPASS STATED ESF DETECTION CIRCUITRY S
F MAINTAIN REACTOR WATER LEVEL S
F INITIAL CORE COOLING PLANNED OPERATION INITIATE HPCI, RCIC ON LOW WATER LEVEL HPCI MSRV SYSTEM S
F PRESSURE RELIEF PCRVIC SYSTEM S
F CONTAINMENT ISOLATION LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR MAIN TURBINE TRIP WITH BYPASS SYSTEM OPERATION FIGURE 15.9-32
HIGH NEUTRON FLUX SCRAM SIGNAL ON NEUTRON MONITOR SYSTEM TRIP OR TURBINE STOP VALVE CLOSURE INSERT CONTROL RODS BELOW TSV CLOSURE SCRAM BYPASS SETPOINT NEUTRON MONITORING SYSTEM S
F CONTROL ROD DRIVE SYSTEM S
F SCRAM EVENT 26 LOSS OF MAIN CONDENSER VACUUM STATES C AND D STATED ONLY STATES C AND D ABOVE TSV CLOSURE SCRAM BYPASS SETPOINT INITIATE
F SEE FIGURE 15.9-35 RPT TURBINE STOP VALVE CLOSURE S
F POWER REDUCTION MSRV SYSTEM S F PRESSURE RELIEF MSIVs S
F PCRVIC SYSTEM S
F TRANSFER DECAY HEAT TO SUPPRES-SION POOL REACTOR VESSEL ISOLATION LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR LO~OF MAIN CONDENSER VACUUM FIGURE 15.9-33
.... z 2
w
(./J
(./J
(./J
<(
c..
al
- l!:
<(
cc u
(./J w
a:
- J
(./J 0
...J u
~
3:
0
...J w
al TURBINE CONTROL VALVE FAST CLOSURE PLANNED OPERATION ABOVE TCV CLOSURE SCRAM BYPASS SETPOINT RPT S
F POWER REDUCTION REACTOR PROTECTION SYSTEM S
F CONTROL ROD DRIVE SYSTEM S
F SCRAM TURBINE CONTROL VALVE FAST CLOSURE INSERT CONTROL RODS RCIC EVENT 27 GENERATOR TRIP WITH BYPASS STATED ESF DETECTION CIRCUITRY S
F MAINTAIN REACTOR WATER LEVEL S
F INITIAL CORE COOLING PLANNED OPERATION INITIATE HPCI, RCIC ON LOW WATER LEVEL HPCI MSRV SYSTEM S
F PRESSURE RELi EF PCRVIC SYSTEM S
F CONTAINMENT ISOLATION LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR MAIN GENERATOR TRIP WITH BYPASS SYSTEM OPERATION FIGURE 15.9-34
LPCI S
F r ____ T ____ 7 ESF
~
DETECTION I
ADS ON LOW WATER LEVEL L____ _ ___...J WATER LEVEL < L 1 WATER LEVEL < L2 ADS S
F WATER LEVEL < L1 cs INITIAL CORE COOLING RHR SUPPRESSION POOL COOLING MODE ADS ACTUATED ADS NOT ACTUATED MSRV p
SYSTEM LPCI p
S F
p PLANNED OPERATION HPCI RCIC WATER LEVEL> L1 SUPPRESSION POOL TEMPERATURE LIMIT - START DEPRESSURIZATION ADS cs S
F LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR ACHIEVING SHUTDOWN COOLING WITH REACTOR VESSEL ISOLATED FIGURE 15.1-35
ALL STATES STANDBY AC POWER SYSTEM RESTORE AC POWER LOW WATER LEVEL STATES BAND D
>TCV CLOSURE SCRAM BYPASS SETPOINT BYPASS SETPOINT REACTOR PROTECTION SYSTEM INSERT CONTROL RODS CONTROL ROD DRIVE SYSTEM SCRAM REACTOR PROTECTION SYSTEM TCV FAST CLOSURE EVENT 29 LOSS OF NORMAL AC POWER GRID CONNECTION LOSS STATES A,B,C AND D RPT S F POWER REDUCTION CLOSE ON LOSS OF CONDENSER VACUUM PCRVIC SYSTEM MSIVs REACTOR VESSEL ISOLATION STATES CANDO MSRV SYSTEM PRESSURE RELIEF STATES A, B, C, D p< SHUTDOWN COOLING INTERLOCK SETPOINT PLANNED OPERATION SHUTDOWN COOLING TRANSFER DECAY HEAT TO SUPPRESSION POOL CONTAINMENT ISOLATION STATES C, D p> SHUTDOWN COOLING INTERLOCK SETPOINT p< HPCI/RCIC ISOLATION SETPOINT HPCI p> HPCI/RCIC ISOLATION SETPOINT ESF DETECTION CIRCUITRY S
F MAINTAIN WATER LEVEL S
F INITIAL CORE COOLING RHR SUPPRESSION POOL COOLING MODE START HPCI, RCIC ON LOW WATER LEVEL RCIC SUPPRESSION POOL TEMPERATURE LIMIT START DEPRESSURIZATION MSRV p SYSTEM p
S F
S F
MAINTAIN WATER LEVEL IN REACTOR VESSEL S
F p
cs 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
BELOW TCV CLOSURE SCRAM BYPASS SETPOINT ABOVE TCV CLOSURE SCRAM BYPASS SETPOINT REACTOR PROTECTION SYSTEM S
F CONTROL ROD DRIVE SYSTEM S
F SCRAM SCRAM SIGNALS:
- 1. HIGH PRESSURE
- 2. HIGH FLUX RPT S
F POWER REDUCTION SCRAM SIGNAL:
TURBINE CONTROL VALVE FAST CLOSURE TURBINE CONTROL VALVE FAST CLOSURE REACTOR PROTECTION SYSTEM S
F CONTROL ROD DRIVE SYSTEM S
F SCRAM EVENT 30 GENERATOR TRIP WITH BYPASS FAILURE STATED INSERT CONTROL RODS ESF DETECTION CIRCUITRY S
F SEE FIGURE 15.9-35 INITIATE HPCI, RCIC, ADS ON LOW WATER LEVEL MSRV SYSTEM S
F PRESSURE RELIEF PCRVIC SYSTEM S
F CONTAINMENT 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
BELOW TSV CLOSURE SCRAM BYPASS SETPOINT ABOVE TSV CLOSURE SCRAM BYPASS SETPOINT REACTOR PROTECTION SYSTEM S
F CONTROL ROD DRIVE SYSTEM S
F SCRAM SCRAM SIGNALS:
- 1. HIGH PRESSURE
- 2. HIGH FLUX RPT S
F POWER REDUCTION SCRAM SIGNAL:
TURBINE STOP VALVE CLOSURE TURBINE STOP VALVE CLOSURE REACTOR PROTECTION SYSTEM S
F CONTROL ROD DRIVE SYSTEM S
F SCRAM EVENT 31 MAIN TURBINE TRIP WITH BYPASS FAILURE STATED ESF DETECTION CIRCUITRY S
F INSERT CONTROL RODS SEE FIGURE 15.9-35 INITIATE HPCI, RCIC, ADS ON LOW WATER LEVEL MSRV SYSTEM S
F PRESSURE RELIEF PCRVIC SYSTEM S
F CONTAINMENT 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
< TSV SCRAM BYPASS SETPOINT REACTOR PROTECTION SYSTEM S
F INSERT CONTROL RODS
> TSV SCRAM BYPASS SETPOINT REACTOR PROTECTION SYSTEM S
F LOW WATER LEVEL CONTROL ROD DRIVE SYSTEM S
F SCRAM SCRAM SIGNAL FROM TURBINE TRIP RPT S
F EVENT 38 RECIRCULATION PUMP SEIZURE STATED ONLY TURBINE TRIP RCIC ESF DETECTION CIRCUITRY S
F MAIN-TAIN WATER LEVEL S
F INITIAL CORE COOLING PLANNED OPERATION MSRV SYSTEM S
F INITIATE
F LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR RECIRCULATION PUMP SEIZURE FIGURE 15.9-40
< TSV SCRAM BYPASS SETPOINT REACTOR PROTECTION SYSTEM S
F INSERT CONTROL RODS
> TSV SCRAM BYPASS SETPOINT REACTOR PROTECTION SYSTEM S
F LOW WATER LEVEL CONTROL ROD DRIVE SYSTEM S
F SCRAM SCRAM SIGNAL FROM TURBINE TRIP RPT S
F EVENT 39 RECIRCULATION PUMP SHAFT BREAK STATED ONLY TURBINE TRIP RCIC ESF DETECTION CIRCUITRY S
F MAIN-TAIN WATER LEVEL S
F INITIAL CORE COOLING PLANNED OPERATION MSRV SYSTEM S
F INITIATE
F LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR RECIRCULATION PUMP SHAFT BREAK FIGURE 15.9-41
CONTROL ROD VELOCITY LIMITER (PASSIVE)
LIMIT REACTIVITY INSERTION RATE STATES BAND D NEUTRON MONITORING SYSTEM S
F CONTROL ROD DRIVE SYSTEM S
F SCRAM EVENT 40 CONTROL ROD DROP ACCIDENT STATES BAND D HIGH NEUTRON FLUX SIGNAL SCRAM SIGNAL ON NEUTRON MONITORING SYSTEM TRIP INSERT CONTROL RODS STATED ONLY MAIN STEAM LINE RADIATION MONITORING SYSTEM S
F MSIVs S
F REACTOR VESSEL ISOLATION PRIMARY CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM S
F CONTAINMENT ISOLATION ESF DETECTION CIRCUITRY SEE FIGURE 15.9-35 INITIATE HPCI, RCIC, ADS ON LOW WATER LEVEL MSRV SYSTEM S
F PRESSURE RELIEF RADIATION MONITOR TRIP CONTROL ROOM HVAC SYSTEM S
F CONTROL ROOM ENVIRONMENTAL CONTROL LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR CONTROL ROD DROP ACCIDENT FIGURE 15.9-42 Rev. 15, 09/10
EVENT41 FUEL HANDLING ACCIDENT STATES A, B, C, l,ND D FUELING AHEA VENTILATION RAD,ATiON MONTOHiNG RADIATION MONITOR TR IP RADIAT!ON MONITOR TRIP CONTROL ROOM HEATING V !::~!Ti LA TING
,"-,NO AIR CONDI-TIQi,JiNG SYSTEM Note:
SYS-.fEM REFUEli~JG AREA ISOLATION CONTROL SYSTEM STANDBY GAS TREATMENT SYSTEM F
REFUELING
{PASSIVE)
SECONDARY CONTAIMViENT ISOLATION n11TIATE RfFUlLING FLOOR ISOLATION The application of Alternative Source Terms per Regulatory 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 Specifications for SGTS and isolation requirements.
/
\
CONTROL flOOM ENVIRONMENTAL CONTFWL LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED F!Nt\.L SAFETY ANALYSIS REPORT ION SEQUENCES FOR FUEL Hfl,NDLING.ACCIDENT FIGURE 5.9-43 REV. 14, 09/08
STATED ONLY SCRAM SIGNAL ON LOW REACTOR WATER LEVEL OR PROTECTION HIGH SYSTEM DRYWELL PRESSURE CONTROL ROD DRIVE SYSTEM s F SCRAM PCRVIC SYSTEM s F MSIVs s F CONTAINMENT (PASSIVE)
PCRVIC SYSTEM REACTOR ENCLOSURE ISOLATION SYSTEM REACTOR ENCLOSURE PASSIVE STANDBY GAS TREATMENT SYSTEM RERS RHR SUPPRESSION POOL COOLING MODE p
s F SUPPRESSION POOL COOLING EVENT 42 PIPE BREAK INSIDE CONTAINMENT STATES C D CONTROL ROD DRIVE HOUSING RUPTURE CONTROL CONTROL ROD ROOM HEATING, DRIVE HOUSING SUPPORT VENTILATING AND (PASSIVE)
AIR CONDITIONING SYSTEM S F ONTROL ROO STOP ROD EJECTION NVIRONMENT CONTROL RADIATION MONITOR TRIP SMALL BREAKS ONLY MSRV SYSTEM s F PRESSURE RELIEF LPCI S F LARGE BREAKS OTHER BREAKS INITIAL CORE COOLING cs S F SEE FIGURE 15.9-35 ONE CS REQUIRED FOR LONG-TERM COOLING AHR SUPPRESSION POOL COOLING p
MODE 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
MSRV SYSTEM S
F PRESSURE RELIEF TRANSFER DECAY HEAT TO SUPPRESSION POOL FLOW RESTRICTORS (PASSIVE)
RESTRICT LOSS OF REACTOR COOLANT (PASSIVE)
CONTROL ROOM HVAC SYSTEM S
F ONTROL QOM EN-ONMENT ONTROL STATED ONLY RADIATION MONITOR TRIP REACTOR PROTECTION SYSTEM S
F CONTROL ROD DRIVE SYSTEM S
F SCRAM EVENT 43, 44, 45 PIPING BREAKS OUTSIDE CONTAINMENT STATES C AND D BREAKS RESULTING IN AUTOMATIC ISOLATION SCRAM SIGNAL ON LOW WATER LEVEL OR MAIN STEAM LINE ISOLATION PCRVIC SYSTEM S
F MSIVs REACTOR VESSEL ISOLATION BREAKS REQUIRING MANUAL ISOLATION BREAK ISOLATED STATES C,D OTHER PROCESS LINE BREAKS RHR SHUTDOWN COOLING BREAK ESF DETECTION CIRCUITRY S
F SEE FIGURE 15.9-35 INITIATE HPCI, RCIC ADS ON LOW WATER LEVEL LPCI S F ESF DETECTION CIRCUITRY S
F RHR SU.PPRESSION POOL COOLING MODE SUPPRESSION POOL TEMPERATURE LIMIT START DEPRESSURIZATION cs S
S F p
EXTENDED CORE COOLING S
F 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 SYSTEM MANUAL
.,._ 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 p
OFFGAS SYSTEM BREAK ISOLATED SEE LOSS OF CONDENSER VACUUM EVENT 26 FIGURE 15.9-33
.,_ MANUAL ISOLATION LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR AUGMENTED OFFGAS TREATMENT SYSTEM FAILURE Pll:1111....
GAS LEAK PROCESS RADIATION MONITORING SYSTEM HVAC SYSTEM HVAC SYSTEM ISOLATION EVENT 48 LIQUID RADWASTE SYSTEM LEAK OR FAILURE STATES A, B, C, D LIQUID LEAK HIGH RADIATION SIGNAL HIGH WATER SIGNAL FLOOR DRAIN MONITORING SYSTEM AUTO OR MANUAL AUTO OR MANUAL FLOOR DRAIN COLLECTION AND PROCESSING SYSTEM CONTAIN LIQUID 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
p GAS LEAK PROCESS RADIATION MONITORING SYSTEM HVAC SYSTEM HVAC SYSTEM ISOLATION EVENT 49 LIQUID RADWASTE SYSTEM STORAGE TANK FAILURE STATES A, B, C, D HIGH RADIATION SIGNAL LIQUID LEAK FLOOR DRAIN MONITORING SYSTEM FLOOR DRAIN COLLECTION AND PROCESSING SYSTEM CONTAIN LIQUID EFFLUENT HIGH WATER SIGNAL LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR LIQUID RADWASTE SYSTEM-STORAGE TANK FAILURE FIGURE 15.M9
p REFUELING AREA VENTILATION RADIATION MONITORING SYSTEMS REFUELING AREA HVAC SYSTEM STANDBY GAS TREATMENT SYSTEM REFUELING AREA (PASSIVE)
REFUELING AREA ISOLATION EVENT50 SHlf'PING CASK DROP STATES A, B, C, D RADIATION MONITOR TRIP AUTO OR MANUAL ISOLATION p
SERVICE WATER SYSTEM RESTORE CASK COOLING EXTERNAL SPRAY OR INTERNAL COOLING ESTABLISHED TEMPORARY CONTAINMENT LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR SHIPPING CASK DROP FIGURE 16.* 50
CONTROL ROD DRIVE SYSTEM (ARI)
NUCLEAR RRCS STANDBY LIQUID CONTROL SYSTEM ATWS/RPT NMS APRM INPUTS NBS PRESSURE, LEVEL INPUTS FEEDWATER RUNBACK EVENT 51 REACTOR SHUTDOWN FROM ANTICIPATED TRANSi ENT WITHOUT SCRAM, STATED START HPCI, RCIC SYSTEM ON LOW WATER LEVEL RCIC INITIATED ON HIGH PRESSURE ONLY ESF DETECTION CIRCUITRY MAINTAIN WATER LEVEL RHR SUPPRESSION POOL COOLING p
MODE p
p MSRV SYSTEM RHR SHUTDOWN COOLING MODE CORE COOLING TRANSFER HEAT TO SUPPRESSION POOL HPCI REMOVE HEAT FROM SUPPRESSION POOL MSRV SYSTEM LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR REACTOR SHUTDOWN/ATWS FIGURE 15. 9-51
STATES B, D p
REACTOR PROTECTION SYSTEM CONTROL ROD DRIVE SYSTEM SCRAM SCRAM BY DE-ENERGIZING SYSTEM MANUALLY RCIC p
RHR SUPPRESSION POOL COOLING MODE p
p MSRV SYSTEM EVENT 52 REACTOR SHUTDOWN FROM OUTSIDE CONTROL ROOM STATES B, C, D STATES C, D p<SDC INTERLOCK SETPOINT MAINTAIN WATER LEVEL REMOVE DECAY HEAT FROM SUPPRESSION POOL TRANSFER DECAY HEAT TO SUPPRESSION POOL RHR SHUTDOWN COOLING MODE p
OOL DOW REACTOR OM OUTSI CONTRO ROOM ISOLATE BY DE-ENERGIZING SYSTEM MANUALLY MSRV SYSTEM PRESSURE RELi EF p
PCRVIC SYSTEM MSIVs REACTOR VESSEL ISOLATION 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 p
STANDBY LIQUID CONTROL SYSTEM 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