ML18249A154

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6 to Updated Final Safety Analysis Report, Chapter 15A, Operational Safety Analysis, Figures
ML18249A154
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 08/13/2018
From:
Duke Energy Progress
To:
Office of Nuclear Reactor Regulation
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ML18249A165 List:
References
RA-18-0131
Download: ML18249A154 (39)
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Text

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

26 Appendix:

15A Page:

1 of 2 LIST OF FIGURES FIGURE NUMBER TITLE FIGURE 15A-1 POSSIBLE INCONSISTENCIES IN THE SELECTION OF OPERATIONAL REQUIREMENTS FIGURE 15A-2 BLOCK DIAGRAM OF METHOD USED TO DERIVE NUCLEAR SAFETY OPERATIONAL REQUIREMENTS AND TECHNICAL SPECIFICATIONS FIGURE 15A-3 FORMAT FOR PROTECTION SEQUENCE DIAGRAMS FIGURE 15A-4 FORMAT FOR SAFETY SYSTEM AUXILIARY DIAGRAMS FIGURE 15A-5 FORMAT FOR COMMONALITY OF AUXILIARY DIAGRAMS FIGURE 15A-6 SAFETY SYSTEM AUXILIARIES FIGURE 15A-7 SAFETY SYSTEM AUXILIARIES FIGURE 15A-8 SAFETY ACTION SEQUENCES FOR PLANNING OPERATIONS IN STATE A FIGURE 15A-9 SAFETY ACTION SEQUENCES FOR PLANNING OPERATIONS IN STATE B FIGURE 15A-10 SAFETY ACTION SEQUENCES FOR PLANNING OPERATIONS IN STATE C FIGURE 15A-11 SAFETY ACTION SEQUENCES FOR PLANNING OPERATIONS IN STATE D FIGURE 15A-12 PROTECTION SEQUENCE FOR TURBINE AND GENERATOR TRIPS FIGURE 15A-13 PROTECTION SEQUENCES FOR ISOLATION OF ALL MAIN STEAM LINES FIGURE 15A-14 PROTECTION SEQUENCES FOR ISOLATION OF ONE MAIN STEAM LINE FIGURE 15A-15 PROTECTION SEQUENCES FOR LOSS OF CONDENSER VACUUM FIGURE 15A-16 PROTECTION SEQUENCES FOR A LOSS OF A FEEDWATER HEATER FIGURE 15A-17 PROTECTION SEQUENCE FOR ROD WITHDRAWAL ERROR FIGURE 15A-18 PROTECTION SEQUENCES FOR PRESSURE REGULATOR FAILURE FIGURE 15A-19 PROTECTION SEQUENCES FOR INADVERTENT OPENING OF A RELIEF OR SAFETY VALVE

( ~ DUKE ENERGY

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

26 Appendix:

15A Page:

2 of 2 LIST OF FIGURES FIGURE NUMBER TITLE FIGURE 15A-20 PROTECTION SEQUENCES FOR LOSS OF FEEDWATER FLOW FIGURE 15A-21 PROTECTION SEQUENCES FOR TOTAL LOSS OF OFFSITE A-C POWER FIGURE 15A-22 PROTECTION SEQUENCE FOR RECIRCULATION FLOW CONTROL FAILURE MAXIMUM DEMAND FIGURE 15A-23 PROTECTION SEQUENCES FOR STARTUP OF IDLE RECIRCULATION PUMP FIGURE 15A-24 PROTECTION SEQUENCES FOR LOSS OF SHUTDOWN COOLING FIGURE 15A-25 PROTECTION SEQUENCES FOR FEEDWATER CONTROLLER FAILURE - MAXIMUM DEMAND FIGURE 15A-26 PROTECTION SEQUENCES FOR CONTROL ROD DROP ACCIDENT FIGURE 15A-27 PROTECTION SEQUENCES FOR PIPE BREAKS INSIDE PRIMARY CONTAINMENT FIGURE 15A-28 PROTECTION SEQUENCES FOR FUEL HANDLING ACCIDENT FIGURE 15A-29 PROTECTION SEQUENCES FOR PIPE BREAKS OUTSIDE PRIMARY CONTAINMENT FIGURE 15A-30 PROTECTION SEQUENCES FOR SHUTDOWN FROM OUTSIDE CONTROL ROOM FIGURE 15A-31 PROTECTION SEQUENCES FOR SHUTDOWN WITHOUT CONTROL RODS FIGURE 15A-32 COMMONALITY OF AUXILIARY D-C POWER SYSTEM 125 VOLT FIGURE 15A-33 COMMONALITY OF AUXILIARY EQUIPMENT AREA COOLING SYSTEM FIGURE 15A-34 COMMONALITY OF AUXILIARY PLANT SERVICE WATER SYSTEM FIGURE 15A-35 COMMONALITY OF AUXILIARY A-C POWER SYSTEM FIGURE 15A-36 COMMONALITY OF AUXILIARY RHRS SERVICE WATER SYSTEM FIGURE 15A-37 COMMONALITY OF AUXILIARY SUPPRESSION POOL STORAGE

( ~ DUKE ENERGY

UPDATED FSAR CHAPTER TITLE CHAPTER X FIGURES Revision:

24 Figure:

15A-1 Page:

1 of 1 POSSIBLE INCONSISTENCIES IN THE SELECTION OF OPERATIONAL REQUIREMENTS

( ~ DUKE

~ ENERGY EVENT A 1ST PROTECTION LEVEL OPERATIONAL REQUIREMENT 2ND PROTECTION LEVEL 3RD PROTECTION LEVEL 4TH PROTECTION LEVEL 5TH PROTECTION LEVEL OPERATIONAL REQUIREMENT 6TH PROTECTION LEVEL IT IS INCONSISTENT TO PLACE OPERATIONAL REQUIREMENTS ON SEPARATED LEVELS OF PROTECTION FOR ANY ONE EVENT.

PANEL A EVENT CATEGORY 1 EVENT A EVENT B PROTECTION PROTECTION LEVEL 1 LEVEL 1 OPERATIONAL PROTECTION PROTECTION LEVEL 2 -

REQUIREMENT SCRAM LEVEL 2 PROTECTION PROTECTION LEVEL 3 LEVEL 3 PROTECTION OPERATIONAL PROTECTION LEVEL 4 REQUIREMENT LEVEL 4 -

SCRAM IT IS INCONSISTENT TO PLACE OPERATIONAL REQUIREMENTS ARBITRARL YON 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 2ND PROTECTION REQUIREMENT LEVEL 3RD PROTECTION LEVEL SINGLE OPERATOR ERROR EVENT B OPERATIONAL REQUIREMENT 1ST PROTECTION LEVEL 2ND PROTECTION LEVEL 3RD PROTECTION LEVEL IT IS INCONSISTENT TO PLACE OPERATIONAL REQUIREMENTS ON EVEN THE SAME LEVELS OF PROTECTION, IF THE EVENTS ARE NOT OF THE SAME CATEGORY.

PANEL C

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-2 Page:

1 of 1 BLOCK DIAGRAM OF METHOD USED TO DERIVE NUCLEAR SAFETY OPERATIONAL REQUIREMENTS AND TECHNICAL SPECIFICATIONS NUCLEAR SAFETY DESIGN CRITERIA BWR OPERATING STATES RULES FOR EVENT ANALYSIS AVAILABILITY CONSIDERATIONS PLANNED OPERATIONS UNACCEPTABLE RESULTS PLANT SYSTEMS AS DESIGNED ANO INSTALLED OPERATIONAL ANALYSIS IDENTIFICATION OF SAFETY AC -

TIONS ESSENTIAL TO AVOIDING UN-ACCEPTABLE RESULTS(EACH STATE)

IDENTIFICATION OF SYSTEMS AND NUCLEAR SAFETY OPERATIONAL CRITERIA REDUNDANCY REQUIREMENT LIMITS ESSENTIAL FOR ACHIEVING.._ _______ __.

SAFETY ACTIONS (EACH STATE)

IDENTIFICATION OF INTRA-SYSTEM ACTIONS WHICH MUST BE REQUIRED 0A RESTRICTED (EACH SYSTEM)

IDENTIFICATION OF MINIMUM SYSTEM HARDWARE CONDITIONS TO CCOMPLISH ACTIONS(EACH SYSTEM 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 (LIM-ITING CONDITION FOR OPERATION)

SIMPLIFICATION TECHNICAL SPEC! FICA TIONS REDUNDANCY REQUIREMENT ACTION TO BE TAKEN IF OPERATIONAL REQUIRE-MENTS NOT SATISFIED

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-3 Page:

1 of 1 FORMAT FOR PROTECTION SEQUENCE DIAGRAMS

( ~ DUKE ENERGY

._EVENT EVENT TITLE STATES NUMBER OF EVENT DIFFERENT DIFFERENT PLANT CONDITION SAFETY SYSTEM a

PLANT CONDITION SAFETY SYSTEM s

SAFETY SYSTEM R

INDICATES THAT SYSTEMS Q AND R

__j

=- SHARE AS A PAIR THE REO\\JIREMENT

~

TO MEET THE SINGLE FAILURE CRITERION PERSONNEL IMANUALl ~

ACTION REQUIRED FOR SYSTEM W SAFETY SYSTEM u

S F SAFETY r '\\ SYSTEM l p I w

S F

~

SYSTEMS MUST ITSELF

~

MEET THIE SINGLE FAILURE CRITERION SAFETY SYSTEM T

S F SAFETY ACTION A

INDICATES THAT ONE OR MORE OF THE KEY PROCESS PARAMETERS MUST ~ ~

L BE LIMITED TO SATISFY NUCLEAR SAFETY OPERATIONAL CRITERIA EACH CONNECTED PROTECTION SEQUENCE IS FOR JUST ONE SAFETY ACTION SAFETY ACTION A

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-4 Page:

1 of 1 FORMAT FOR SAFETY SYSTEM AUXILIARY DIAGRAMS

( ~ DUKE ENERGY DIAGRAM INDICATES THAT AUXILIARIES A,B, AND CARE ESSENTIAL TO THE OPERATION OF THE FRONT LINE SAFETY SYSTEM X.

NO CHRONOLOGY OR ORDER OF ACTION IS IMPLIED FRONT LINE SAFETY SYSTEM X

SAFETY SYSTEM AUXILIARY A SAFETY SYSTEM AUXILIARY B SAFETY SYSTEM AUXILIARY C

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-5 Page:

1 of 1 FORMAT FOR COMMONALITY OF AUXILIARY DIAGRAMS

( ~ DUKE ENERGY STATE EVENTS STATE EVENTS A

x:v A

u,v,w B

X,Y B

v,w C

X,Y,Z C

u,v,w,x D

X,Y, Z D

u,v,w,x s

F s

F I

SAFE TY SAFETY SYSTEM SYSTEM y

a r-, INDICATES TH-'T SYSTEM IS INCLUDED I

I IN COMBINATION BUT DOES NOT L _.J REQUIRE THE AUXILIARY.

AUXILIARY SYSTEM A STATES ANO EVENTS STATE

~

FOR WHICH THE AUX* -

-A--

B ILIARY / SAFETY SYSTEM C

RELATIONSHIP APPLIES I

SAFETY SYSTEM

/J SAFETY SYSTEM e

D r-1-7 SAFETY I

SYSTEM I

I t:

I L __ _J s

EVENTS Y,W Y,W,Z F

SAFETY SYSTEM I

SAFETY SYSTEM 1T STATE s.YE!ill

-A-B Q,R C

D Q,R,S SAFETY SYSTEM 6

UPDATED FSAR CHAPTER TITLE CHAPTER X FIGURES Revision:

24 Figure:

15A-6 Page:

1 of 1 SAFETY SYSTEM AUXILIARIES

( ~ DUKE ENERGY ADS SUPPRESSION POOL STEAM STORAGE (PASSIVE)

CONDENSATION HPCIS RELIEF VALVE DC POWER SYSTEM CONTROLS; SENSORS, 12SV LOGIC, AND SOLENOIDS DC POWER SYSTEM CONTROL LOGIC 12SV EQUIPMENT COOL AREA OF AREA COOLING HPCS EQUIPMENT, SYSTEM 140°F MAXIMUM SUPPRESSION WATER SUPPLY POOL STORAGE FOR HPCI' PUMP RH RS-SUPPRESSION POOL COOLING AUXILIARY AC VALVE AND POWER SYSTEM PUMP POWER DC POWER PUMP BREAKER CONTROL RCICS SYSTEM AND CONTROL LOGIC 125V DC POWER CONTROL CIRCUIT PLANT SERVICE SYSTEM VALVE POWER, WATER SYSTEM RHRS PUMP COOLER 125V LUBE OIL PUMP EQUIPMENT COOL AREA AROUND RHRS SERVICE RHRS AREA COOLING SYSTEM i>CICS TURBINE PUMP WATER SYSTEM HEAT EXCHANGERS (EAC) 1400 F MAXIMUM SUPPRESSION EQUIPMENT COOL AREA OF RHR WATER SUPPLY FOR AREA COOLING EQUIPMENT, POOL STORAGE RCICS PUMP SYSTEM (PASSIVE) 140° MAXIMUM cs s AUXILIARY VALVE AND A C Pl),'IE R SYSTEM PUMP POWER DC POWER BREAKER CONTROL.

SYSTEM 125V CONTROL LOGIC EQUIPMENT AREA C*JOL AREA OF CORE COOLING SYSTEM SPRAY EQUIPMENT, 141:PF MAXIMUM SUPPRESSION WATER SUPPLY POOL STORAGE TO PUMPS RHRS-SHUTDOWN COOLING MODE AUXILIARY VALVE AND AC POWER PUMP POWER SYSTEM DC POWER VALVE POWER, SYSTEM BREAKER CONTROL 1,sv PLANT SERVICE RHRS PUMP COOLER WATER SYSTEM EQUIPMENT COOL AREA AROUND AREA COOLING RHRS EQUIPMENT, SYSTEM 140°F MAXll\\fJM RHRS SERVICE RHRS WATER SYSTEM HEAT EXCHANGERS RHRS-LPCI AUXILIARY AC POWER SYSTEM STANDBY LIQUID CONTROL SYSTEM DC POWER SYSTEM AUXILIARY PUMP POWER, 12SV AC POWER SYSTEM TANK HEATERS, VALVE FIRING CIRCUITS PLANT SER'.'ICE WATER SYSTEM EQUIPMENT AREA COOLING SYSTEM SUPPRESSION POOL STORAGE (PASSIVE\\

PRESSURE RELIEF SYSTEM I

SUPPRESSION POOL STORAGE (PASSIVE) ~

VALVE. BLOWER AND PUMP POWER BREAKER CONTROL CONTROL LOGIC RHRS PUMP COOLER COOL AREA OF RHRS EQUIPMENT, 140°F MAXIMUM WATER SUPPLY TO LPCI PUMPS STEAM CONDENSATION

UPDATED FSAR CHAPTER TITLE CHAPTER X FIGURES Revision:

24 Figure:

15A-7 Page:

1 of 1 SAFETY SYSTEM AUXILIARIES

( ~ DUKE ENERGY AUXILIARY AC POWER SYSTEM INCIDENT DETECTION CIRCUITRY DC POWER SYSTEM 125V OFF SITE AC POWER SYSTEM DC POWER SYSTEM 125V PRIMARY CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM DC POWER SYSTEM I25V VALVE POWER VALVE CONTROL POWER DC POWER SYSTEM 250V POWER TO CONTROL CIRCUITRY BREAKER CONTROL STANDBY AC POWER SYSTEM DC POWER SYSTEM 125V PLANT SERVICE WATER SYSTEM PRIMARY CONTAINMENT (PASSIVE)

SUPPRESSION POOL STORAGE (PASSIVE)

PRIMARY CONTAINMENT VACUUM RELIEF SYSTEM BREAKER CONTROL CONTROL ROOM HEATING. VENTILATING AND AND AIR CONDITIONING PRESSURE SUPPRESSION DRYWELL/ SUPPRESSION POOL DIFFERENTIAL PRESSURE CONTROL SYSTEM I

AUXILIARY AC POWER SYSTEM PLANT SERVICE WATER SYSTEM DC POWER SYSTEM 125V AUXILIARY AC POWER SYSTEM

~

POWER TO AIR CON-DITIONING EQUIPMENT CO,ffROL POWER VALVE AND PUMP POWER STANDBY AC POWER SYSTEM STANDBY GAS TREATMENT SYSTEM DC POWER SYSTEM 125V AUXILIARY AC POWER SYSTEM AUXILIARY AC POWER SYSTEM DC POWER SYSTEM 125V.

CONTROL POWER DELIVER POWER TO BLOWERS AND HEATERS OFF-SITE AC POWER SYSTEM BREAKER CONTROL EQUIPMENT AREA COOLING SYSTEM PLANT SERVICE WATER SYSTEM AUXILIARY AC POWER SYSTEM RHRS SERVICE WATER SYSTEM AUXILIARY AC POWER SYSTEM COOL ARF.A COOLERS POWER TO BLOWERS VIILVE ANO PUMP POWER

UPDATED FSAR CHAPTER TITLE CHAPTER X FIGURES Revision:

24 Figure:

15A-8 Page:

1 of 1 SAFETY ACTION SEQUENCES FOR PLANNING OPERATIONS IN STATE A

( ~ DUKE ENERGY L

L L

EVENTS 1,2,AND 6 OFFGAS VENT RADIATION MONITORING SYSTEM LIQUID RADWASTE SYSTEM OFFGAS VENT SYSTEM SOLID RAOWASTE SYSTEM REACTOR BUILD-ING VENTILATION RADIATION MONITORING SYSTEM RADIOACTIVE MATERIAL RELEASE CONTROL EVENTS 1,2, AND 6 MAIN STACK RELEASE 10CFR 501 10CFR 20 LIMIT 10CFR 5 01 10 CFR 20 LIMIT 10 CFR 71 LIMIT APPLIED TO SHIPPING CASKS REACTOR FUEL L

MONITOR ACTIVITY RELEASE THROUGH VENTILATING SYSTEM EVENTS 1 ANDS MINIMUM WATER LEVEL TO AVOID EXCESS TEMPERATURE L

REACTOR VESSEL L

STATE A PLANNED OPERATION EVENTS 1,2, AND 6 EVENTS 1,2,AND 6 REACTOR WATER CHEMISTRY COOLANT LIMIT MINIMUM TEMPERATURE TO BOLT DOWN VESSEL HEAD CORE LOADING PATTERN L

REACTOR FUEL EVENTS EVENT l,2,AND6 1

CONTROL ROD DRIVE SYSTEM L

REACTOR FUEL R

REFUELING RESTRICTIONS EVENTS 1,2,AND 6 L

CORE REACTIVITY CONTROL CONTROL ROD DRIVE SYSTEM PROCEDURAL RESTRICTIONS (CONTROL ROD POSITION)

PROCEDURAL RESTRICTIONS (FUEL ASSEMBLY ORIENTATION)

LIMITON NUMBER OF DRIVES VALVED OUT OF SERVICE EVENTS 1,2, AND 6 NEW FUEL STORAGE FUEL SPACING FACILITIES L

SPENT FUEL WATER TEMPERATURE, STORAGE FACILITIES WATER LEVEL, FUEL SPACING, FUEL HANDLING STORED FUEL SHIELDING,

COOLING, AND REACTIVITY CONTROL

UPDATED FSAR CHAPTER TITLE CHAPTER X FIGURES Revision:

24 Figure:

15A-9 Page:

1 of 1 SAFETY ACTION SEQUENCES FOR PLANNING OPERATIONS IN STATE B

( ~ DUKE ENERGY EVENTS 2 AND 5 OFF GAS VENT RADIATION MONITORING SYSTEM LIOUID RADWASTE SYSTEM L

L OFF GAS VENT SYSTEM SOLID RADWASTE SYSTEM REACTOR BUILDING VENTILATION RADIATION MONITORING SYSTEM RADIOACTIVE MATERIAL RELEASE CONTROL MAIN STACK RELEASE 10CFR20 LIMIT 10CFR 501 IOCFR20 LIMIT L

EVENTS 2AND5 REATOR FUEL CORE POWER LEVEL CONTROL IOCFR71 LIMIT APPLIED TO SHIPPING CASK MONITOR ACTIVITY RELEASE THROUGH VENTILATING SYSTEM MINIMUM EVENTS 2AND5 POWER (SRM),

MAXIMUM POWER EVENTS 2AND5 REACTOR VESSEL RATE OF CHANGE TEMP-STATE B PLANNED OPERATIONS EVENTS 2, AND 5 EVENTS 2AND5 EVENTS 2 ANDS CONTROL ROD DRIVE SYSTEM L

ERATURE L

LIMIT NUCLEAR SYSTEM CORE TEMPERATURE REACTIVITY CONTROL CONTROL MINIMUM WATER EVENT 2

POSITIONING OF CONTROL RODS DURING CORE ALTERATION REACTOR FUEL LEVEL TO AVOID REACTOR EXCESS COOLANT TEMPERATURE WATER CHEMISTRY LIMIT L

REACTOR VESSEL WATER LEVEL CONTROL L

NUCLEAR SYSTEM WATER DUALITY CONTROL L

CONTROL ROD DRIVE SYSTEM ROD WORTH CONTROL L

L ROD PATTERN EVENTS 2AND5 NEW FUEL STORAGE FACILITIES SPENT FUEL STORAGE FACILITIES STORED FUEL SHIELDING, COOLING AND REACTIVITY CONTROL FUEL SPACING WATER TEMPERATURE, WATER LEVEL, FUEL SPACING, AND FUEL HANDLING

UPDATED FSAR CHAPTER TITLE CHAPTER X FIGURES Revision:

24 Figure:

15A-10 Page:

1 of 1 SAFETY ACTION SEQUENCES FOR PLANNING OPERATIONS IN STATE C

( ~ DUKE ENERGY OFFGAS VENT RADIATION MONITORING SYSTEM UOUID RADWASTE SYSTEM L

OFFGAS VENT SYSTEM L

SOLID RADWASTE L

SYSTEM REACTOR BUILDING VENTILATION RADIATION MONITORING SYSTEM RADIOACTIVE MATERIAL RE LEASE CONTROL MAIN REACTOR STACK FUEL RELEASE L

10CFR50, 10CFR20 LIMIT
10CFR50, 10CFR20 LIMIT 10CFR71 LIMIT APPLIED TO SHIPPING CASK MONITOR ACTIVITY RELEASE THROUGH VENTILATING SYSTEM MINIMUM WATER LEVEL L

L REACTOR VESSEL L

TEMP-ERATURE RATE OF

CHANGE, REACTOR MINIMUM VESSEL TEMP*

ERATURE STATE C PLANNED OPERATIONS EVENTS 2 ANO 6 REACTOR VESSEL L

MAXIMUM FEED*

NUCLEAR REACTOR WATER SYSTEM FUEL TEMP-LEAKAGE CONTROL ERATURE NUCLEAR SYSTEM TEMPERATURE CONTROL MAXIMUM

PRESSURE, REACTOR MINIMUM COOLANT WATER PRESSURIZATION CHEMISTRY L
LIMITS, OVER STRESS PRIMARY PROTECTION CONTAINMENT TEMPERATURE LIMIT AND MAKEUP

!PASSIVE)

PRESSURE LIMIT CAPABILITY L

SUPPRESSION POOL WATER TEMPERATURE AND VOLUME LIMIT (PASSIVE )

L PRIMARY CONTAINMENT PRESSURE AND TEMPERATURE CONTROL NUMBER OF DRIVES CONTROL ROD DRIVE SYSTEM VALVED OUT OF SERVICE L

TEMPERATURE ACTIVITY LIMIT MAXIMUM NUCLEAR CORE RH RS-SHUTDOWN PRESSURE SYSTEM REACTIVITY COOLING MODE WATER QUALITY CONTROL LIMIT CONTROL L

NEW FUEL STORAGE FUEL SPACING FACILITIES L

SPENT FUEL STORAGE WATER TEMPERATURE, FACILITIES WATER LEVEL, L

FUEL SPACING, FUEL HANDLING STORED FUEL SHIELDING, COOLING. Al'<D REACTIVITY CONTROL

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-11 Page:

1 of 1 SAFETY ACTION SEQUENCES FOR PLANNING OPERATIONS IN STATE D

( ~ DUKE

~ ENERGY EVENTS 2,3,4, AND 5 OFFC.,S VENT RADIATION MONITORING SYSTEM LIQUID RAOWASTE SYSTEM L

OFFGAS VENT SYSTEM L

SOLID RAOWASTE SYSTEM I.

REACTOR BUILDING VENTILATION RADIATION MONITORING SYSTEM RADIOACTIVE MATERIAL RELEASE CONTROL EVENTS EVENTS 3,*, AND 6 2,3,*, AND 5 MAIN STACK REACTOR RELEASE FUEL L

10CFRSO, CORE POWER 10CFR20 LEVEL LIMIT CONTROL 10CFRSO 10CFR20 REACTOR MINIMUM EVENTS EVENTS 2,3.4. AND 5 2,3,4, ANO 5 MINIMUM POWER ISRMl, REACTOR MAXIMUM FUEL POWER L

filll..Q PLANNED OPE RATIONS EVENTS 2.3,*. ANO 5 EVENTS 234 ANDS MINIMUM WATER LEVEL EVENTS 3 ANO 4 EVENTS 2 ANO 5 EVENTS EVENTS EVENTS 2.3,4, ANO 6 2,3,4, AND 6 2,3,4, ANO 6 L

REACTOR VESSEL NUCLEAR SYSTEM LEAKAGE CONTROL EVENTS EVENTS 2,3,4. ANO 6 2.3,4, ANO 6 OVERSTRESS PROTECTION MAKEUP CAPABILITY CONTROLROO DRIVE SYSTEM L

ROD WORTH CONTROL LIMIT FUEL FLOW RATE L

l4 10CFR71 LIMIT APPLIED TO SHIPPING CASK MONITOR ACTIVITY RELEASE THROUGH VENTILATION SYSTEM CORE COOLANT FLOW RATE CONfRO,.4 L

MAXIMUM PRESSURE LIMIT REACTOR FUEL CORE NEUTRON FLUX DISTRI*

8\\JTION CONTROL L

REACTOR VESSEL POWER PEAKING REACTOR VESSEL PRESSURE CONTROL REACTOR VESSEL L

REACTOR COOLANT WATER CHEMISTRY LIMIT ACTIVITY LIM IT L

MAXIMUM PRESSURE LIMIT NUCLEAR SYSTEM WATER QUALITY CONTROL L

REACTOR VESSEL REACTOR FUEL NUCLEAR SYSTEM TEMPERATURE CONTROL RATE OF TEMPERATURE CHANGE.

MINIMUM TEMPERATURE Willi HEAOON MAXIMUM FEEOWATER TEMPERATURE MAXIMuM TEMPERATURE DIFFERENCE IN RECIRCU*

LATION LOOPS CONTROL ROO DRIVE SYSTEM L

CORE REACTIVITY CONTROL NUMBER DRIVES OUT OF SERVICE EVENTS EVENTS 2,3,4, ANO 5 2.3,4, AND 5 ROD PATTERN WHEN POWER

<10%

L NEW FUEL STORAGE FACILITIES SPENT FUEL STORAGE FACILITIES L

TORAGE FUEL StOELOING.

COOLING, ANO REACTIVITY CONTROL FUEL SPACING WATER TEMPfRATURE,

WATER LEVEL,

FUEL SPACING, FUEL HANDLING PRIMARY CONTAINMENT IPASSlVEl TEMPERATURE AHO L

SUPPRESSION POOL L IPASSIVEI PRIMARY CONTAINMENT TEMPERATURE&

PRESSURE CONTf'IOL PRESSURE LIMITS WATER TEMPERATURE ANO VOLUME LIMIT

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-12 Page:

1 of 1 PROTECTION SEQUENCE FOR TURBINE AND GENERATOR TRIPS

( ~ DUKE ENERGY PLANNED OPERATION:

REESTABLISH POWER Of'ERATION 01t ACHIEVE SHUTDOWN EVENT 8 GENERATOR TRIP STATED REACTOR PROTECTION SYSTEM S

F CONTROL ROD DRIVE SYSTEM S

F SCRAM EVENT9 TURBINE TRIP WITH

BYPASS, STATED SCRAM SIGNALS:

1. FOR TURBINE TRIP, TURBINE STOP VALVE CLOSURE PRESSURE RELIEF SYSTEM

2. FOR GENERATOR TRIP, TURBINE CONTROL VALVE FAST CLOSURE INSERT CONTROL RODS S F PRESSURE RELIEF

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-13 Page:

1 of 1 PROTECTION SEQUENCES FOR ISOLATION OF ALL MAIN STEAM LINES

( ~ DUKE ENERGY STATED p > 600 psig EVENT 10 ISOLATION OF ALL MAIN STEAM LINES STATES C,D

>----- PLANNED STATE D OPERATION p < 600 psig REACTOR PROTECTION SYSTEM S F CONTROL ROD DRIVE SYSTEM S F SCRAM SCRAM SIGNAL WHEN 3 MAIN STEAM LINES CLOSED> lO'lb INSERT CONTROL ROOS RCICS START ON LOW WATER LEVEL MAINTAIN WATER LEVEL S F CORE COOLING PRESSURE RELIEF SYSTEM S F PRESSURE RELIEF INCIDENT DETECTION CIRCUITRY HPCS HIGH PRESSURE LIFTS VALVE TRANSFERRING HEAT TO SUP-PRESSION POOL START HPCIS ON LOW WATER LEVEL MAINTAIN WATER LEVEL

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-14 Page:

1 of 1 PROTECTION SEQUENCES FOR ISOLATION OF ONE MAIN STEAM LINE

( ~ DUKE ENERGY EVENT 11 ISOLATION OF ONE MAIN STEAM LINE STATES C, D STATES C AND D LESS THAN STATED OVER 90% POWER CONTINUE PLANNED OPERATION 90% POWER NEUTRON MONITORING SYSTEM S F REACTOR PROTECTION SYSTEM S F CONTROL ROD DRIVE SYSTEM S F SCRAM HIGH NEUTRON FLUX SIGNAL SCRAM SIGNAL ON NEUTRON MONITORING SYSTEM TRIP INSERT CONTROL ROOS

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-15 Page:

1 of 1 PROTECTION SEQUENCES FOR LOSS OF CONDENSER VACUUM

( ~ DUKE ENERGY STATED ONLY BELOW 30'!1,POWER NEUTRON MONITORING SYSTEM S F REACTOR PROTECTION SYSTEM S F CONTROL ROD DRIVE SYSTEM S

F SCRAM RCICS ABOVE 30% POWER HIGH NEUTRON FLUX SCRAM SIGNAL ON NEUTRON MONITOR SYSTEM TRIP OR TURBINE STOP VALVE CLOSURE INSERT CONTROL RODS p

EVENT12 LOSS OF CONDENSER VACUUM STATES C, D START ON LOW WATER LEVEL; MAINTAIN WATER LEVEL INCIDENT DETECTION CIRCUITRY HPCI AHRS - SUPP POOL COOLING MODE p

START HPCS ON LOW WATER LEVEL MAINTAIN WATER LEVEL RHRS HEAT EXCHANGER I RHRS PUMP TRANSFER DECAY HEAT TO SUPPRES-SION POOL PRESSURE RELIEF SYSTEM S F PRESSURE RELIEF 2 RHRS SERVICE WATER PUMPS SUPPRESSION POOL

>----TEMPERATURE LIMIT 120F ADS p

S F S F EXTENDED CORE COOLING START DEPRESSURIZATION 2 OR LESS VALVES REQUIRED FOR CONTROLLED DEPRESSU RIZA TION cs p

}

MAINTAIN WATER LEVEL

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-16 Page:

1 of 1 PROTECTION SEQUENCES FOR A LOSS OF A FEEDWATER HEATER

( ~ DUKE ENERGY EVENT 14 LOSS OF FEEOWATER HEATING STATE D RECIRCULATION FLOW IN MANUAL RECIRCULATION FLOW IN AUTO NEUTRON MONITORING SYSTEM S F REACTOR PROTECTION SYSTEM S F CONTROL ROD DRIVE SYSTEM S F SCRAM HIGH FLUX SCRAM SIGNAL SCRAM SIGNAL ON NEUTRON MONITORING SYSTEM TRIP INSERT CONTROL RODS PLANNED OPERATION

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-17 Page:

1 of 1 PROTECTION SEQUENCE FOR ROD WITHDRAWAL ERROR

( ~ DUKE ENERGY STATES B, D EVENT 17 CONTROL ROD WITHDRAWAL ERROR STATES A, B, C, D STATE 0 LOW POWER IIRM RANGEi HIGH POWER CAPRM RANGEi NEUTRON MONITORING SYSTEM S F REACTOR PROTECTION SYSTEM S

F CONTROL ROD DRIVE SYSTEM S F SCRAM HIGH FLUX SCRAM, I RM STATES A AND C SCRAM SIGNAL ON NEUTRON MONITORING SYSTEM TRIP INSERT CONTROL RODS PLANNED OPERATION PLANNED OPERATION

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-18 Page:

1 of 1 PROTECTION SEQUENCES FOR PRESSURE REGULATOR FAILURE

( ~ DUKE

~ ENERGY PRESSURE RELIEF SYSTEM S F PRESSURE RELIEF STATED ONLY REACTOR PROTECTION SYSTEM CONTROL ROD DRIVE SYSTEM S F SCRAM SCRAM SIGNAL FROM

1. MAIN STEAM LINE ISOLATION (RUN MODE; POWER 5-25%

AND 50-100%1

2. TURBINE TRIP (RUN MODE POWER 30-50%1 3, 111GH PRESSURE (RUN MODE; POWER 25-30%)
4. LOW WATER LEVEL (OTHER THAN RUN MODE; POWER 0-10 %)

INSERT CONTROL RODS EVENT 21 PRESSURE REGULATOR FAILURE - OPEN STATES C, D INCIDENT DETECTION CIRCUITRY HPCI AFTER ISOLATION START HPCI SYSTEM ON LOW WATER LEVEL PLANNED OPERATION:

REESTABLISH COOLING VIA MAIN CONDENSER RCIC

--P-R-IM_._A_R_Y __ INITIATE ISOLATION ON CONTAINMENT

1. DEPRESSURIZATION TO 880 pslg AND REACTOR (RUN MODE; POWER 0-lOM,)

VESSEL ISOLATION 2. LOW WATER LEVEL CONTROL (OTHER THAN RUN MODE,*

SYSTEM MAIN STEAM LINE ISOLATION VALVES POWER 0-10 'l&)

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-19 Page:

1 of 1 PROTECTION SEQUENCES FOR INADVERTENT OPENING OF A RELIEF OR SAFETY VALVE

( ~ DUKE ENERGY Rl!.ACTOlt l'IIOTECTION SYSTEM CONTROLROO DRIVE SYSTEM 5

SCRAM I l,.ITIATE SCRAM 0111 HIGH OflVWEI..L,RESSUAE 1AuTOMAT1C HEOWATEIII FLOW CONTROL, STATE D1

,i,UMARV OIIITAINMENT "'"

RE... CTOR VESSEL ISOL... TIO,.

CONTROL SYSTEM

2. 1N1t1A fl SCIIIAM ON LOW WAT(tll LE\\IEL IMA,.UAL FUOWATEA FLOW CONTtllOL 0111,.0FEEDWATl;R s

STATED*

INSl:IIT CONTtllOL IIIODS MAIi! STEAM LINE SOLATION VALVES I. INITIATE CLOSUtllE OF ALL l'IIIIM,illRV CQjljT,IUNMENT ISOLATION 'I/ALVES UCEPT MAIN $TEAM LINE VAlVn ON HIGH ORVWELL l'RESSuR(

l"UTOMATIC FUOWATER CONTROL I OR LOW WATER EVENT 22 lHADVERTENT OPENING OF A SAl'ETY RELIEF' OR SAl'[TY VALVE STATES C AND 0

'tUClfAR SVSTUII

  • RESSuRE RELIEF SYSTEM
f~!LJ
~~~i~~~~:i,ER,_ _____ _

2, IIWITIATI CLOSUtllE OF MAIIW STEAM LINE ISOLATION VALVES ON LOW TURBINE INLET l'RES-SORE I.AUTOMATIC FEEOWATER FLOWCONTROLIOR LOW WATER LEVEL !MANUAL FEEOWATER l'LOW CONTROL OR NO FUDWATEl'II, s

F mssuRE RELIEF AUTOMATIC OE,RESS-URIZ"TIO,.-

SYSTEM l"ICl[l£"1T DETECTION CIACUITIIY S

F

& VALVES REQUIRED FOR WORtf CONDI-TION (MANUAL INITIA*

TION REQUIRED WHEN FEEDWATER IS OFF OR IN MANUAL FLOW CONTROL) l!HRS-SUPPRESSION POOL p COOLING MOOE s

START HPCl,LPCI, AND CS ON RE~PECTl'IIE TRIP SETTINGS START ADS (AUT~ fl C FE.E.OWA fER FLOW CONTROL, STATE Dl HPCS MAINTAIN WATIIII 1.l'IIEL ADS ACTUATED HPCS ACTUATED S

F S F I

F EJCT£NOEO COl!E COOLING ACS Sl#RESSION ll'OOL TEMl'EtllATUIIIIE LIMIT 120F, START 0£,RESSI.JIIIIZATION

1\\'ALVES RE0U1tllfO 1'011 CONTIIOLLEO OE,IIISSURIZA.TION MA**',IIUM OF :1 VALVES REOUltllEO TO IIA1111TAIN OEl'RES&UIUZATION

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-20 Page:

1 of 1 PROTECTION SEQUENCES FOR LOSS OF FEEDWATER FLOW

( ~ DUKE

~ ENERGY EVENT 23 LOSS OF FEEDWATER FLOW STATES C AND D STATED.--------------------....1.--------------------,

ONLY REACTOR PROTECTION SVSTEM S

F CONTROL ROO DRIVE SVSTEM S

F SCRAM INITIATE SCRAM ON LOW WATER LEVEL INSERT CONTROL ROOS PRIMARY CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM s

F MAIN STEAM LINE ISOLATION VALVES S

F INITIATE MAIN STEAM LINE ISOLATION ON LOW WATER LEVEL PRESSURE RELIEF SYSTEM s

F TRANSFER DECAY HEAT TO SUPPRESSION POOL START ON LOW WATER LEVEL; MAINTAIN CORE COOLING RCIC STATES C,D p> 136 psijj START HPC I ON LOW WATER LEVEL INCIDENT DETECTION CIRCUITRY RHRS-SUPPRESSION POOL COOLING MOOE p

p s

F EXTENDED CORE COOLING 1 RHRS HEAT EXCHANGE 1 RHRSPUMP MAINTAIN CORE COOLING 2 RHRS SERVICE WATER PUMPS SUPPRESSION POOL TEMPERATURE LIMIT 120F, START DEPRESSURIZATION MAXIMUM OF 2 VALVES REQUIRED FOR CONTROLLED DEPRESSURIZATION MAINTAIN WATER LEVEL IN REACTOR VESSEL p

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-21 Page:

1 of 1 PROTECTION SEQUENCES FOR TOTAL LOSS OF OFFSITE A-C POWER

( ~ DUKE

~ ENERGY ALL STATES STANDBY AC POWER SYSTEM RESTORE AC POWER START DIESELS EVENT 24 TOTAL LOSS OF OFFSITE AC POWER ALL STATES STA TES B AND D STATES C AND D REACTOR PROTECTION SYSTEM S F CONTROL ROD DRIVE SYSTEM S

F SCRAM INITIATE SCRAM ON LOSS OF RPS M-G SETS OR TURBINE TRIP INSERT CONTROL RODS PRESSURE RELIEF SYSTEM S F PRESSURE RELIEF TRANSFER DECAY HEAT TO SUP-PRESSION POOL STATESC. D F < 135 psiG PLANNED OPERATION:

STA TES C, D P > 135 psla SHUTDOWN COOLING,---------....&...--------,

START ON LOW WATER LEVEL, MAIN-TAIN CORE COOLING STATES A, B RCIC LPCI p

START HPCS ON LOW WATER LEVEL S

F INITIAL CORE COOLING s

F INCIDENT DETECTION CIRCUITRY HPCI MAINTAIN CORE COOLING 1 RHRS HEAT EXCHANGER 1 RHRS PUMP 2 RHRS SERVICE WATER PUMPS

.,__ ___ SUPPRESSION POOL TEMPERATURE LIMIT 120F,. START OEPRESSURI ZATION ADS MAXIMUM OF 2 VALVES REQUIRED FOR CONTROLLED DEPRESSURIZATION S

F cs p

s F

MAINTAIN

___. __ ""._ ____ CORE COOLING EXTENDED CORE COOLING

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-22 Page:

1 of 1 PROTECTION SEQUENCE FOR RECIRCULATION FLOW CONTROL FAILURE MAXIMUM DEMAND

( ~ DUKE ENERGY EVENT 29 RECIRCULATION FLOW CONTROL FAILURE MAXIMUM DEMAND STATES C AND D STATE C STATE 0, MOOE SWITCH IN RUN, POWER OPERATION STATED (MODE SWITCH NOT IN RUN)

NEUTRON MONITORING SYSTEM S F REACTOR PROTECTION SYSTEM S F CONTROL ROD DRIVE SYSTEM S F SCRAM HIGH NEUTRON FLU><

(APRMI SIGNAL TO RPS SCRAM SIGNAL ON NEUTRON MONITORING SYSTEM TRIP INSl:RT CONTROL ROOS PLANNED OPERATION

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-23 Page:

1 of 1 PROTECTION SEQUENCES FOR STARTUP OF IDLE RECIRCULATION PUMP

( ~ DUKE ENERGY IRM HIGH FLUX a:

SIGNAL UJ f EVENT 30 STARTUP OF IDLE RECIRCULATION PUMPS STATES A, B. C, D APRM HIGH FLUX SIGNAL POWER lMO'lf, POWER<~

NEUTRON MONITORING SYSTEM NEUTRON MONITORING SYSTEM PLANNED OPERATION S F REACTOR PROTECTION SYSTEM S F CONTROL ROD DRIVE SYSTEM S F SCRAM S F SCRAM SIGNAL ON NEUTRON MONITORING SYSTEM TRIP INSERT CONTROL RODS STA TES A, B, C PLANNED OPERATION

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-24 Page:

1 of 1 PROTECTION SEQUENCES FOR LOSS OF SHUTDOWN COOLING

( ~ DUKE ENERGY LPCI p

S F EVENT 31 LOSS OF SHUTOOWN COOLING STATES A. B. C, D ISOLATION OF SHUTDOWN COOLING SUCTION Ll,-N_E_..L---------~A:.::L:.::L..:0:..:T.:.H:.::E.:.R..:S::;IN.:.G=LE:..:..FA=IL:.::U::;R:.:Ea;S STATES A, B STATES C, D p >135 psi&

LPCI MAINTAIN CORE COOLING BY FLOODING AND/OR SPRAYING S F ADS S F RHRS

  • SUPPRESSION POOL COOLING MODE S F cs PLANNED OPERATION:

REESTABLISH RHRS SHUTDOWN COOLING MODE WITH ALTERNATE EQUIPMENT 2 OR LESS VALVES REQUIRED TO MAINTAIN P< 135 PSIG 1 RHRS HEAT EXCHANGER 1 RHRS PUMP 2 RHRS SERVICE WATER PUMPS

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-25 Page:

1 of 1 PROTECTION SEQUENCES FOR FEEDWATER CONTROLLER FAILURE - MAXIMUM DEMAND

( ~ DUKE ENERGY

~

FEEDWATER CONTROLLER FAILURE

- MAXIMUM DEMAND STATESC, D STATED OTHER OPERATING MODES STATED RUN MODE NEUTRON MONITORING SYSTEM S F HIGH FLUX SCRAM SIGNAL ORMI REACTOR PROTECTION SYSTEM S F CONTROL ROD DRIVE SYSTEM S F SCRAM SCRAM SIGNAL FROM TURBINE TRIP (RUN MODEi OR NEUTRON MONITORING SYSTEM INSERT CONTROL RODS

'RESSURE RELIEF SYSTEM S F

'RESSURE RELIEF

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15-26 Page:

1 of 1 PROTECTION SEQUENCES FOR CONTROL ROD DROP ACCIDENT

( ~ DUKE ENERGY NEUTRON HIGH MAIN STEAM MONITORING NEUTRON LINE RADIATION FLUX MONITORING SYSTEM SYSTEM SIGNAL s

f SCRAM s

F SIGNAL ON PRIMARY REACTOR NEUTRON CONTAINMENT PROTECTION NITORING AND REACTOR SYSTEM VESSEL ISOLATION SYSTEM CONTROL SYSTEM TRIP s

s F

CONTROL ROO INSERT MAIN STEAM DRIVE SYSTEM CONTROL LINE ISOLATION RODS VALVES s

f s

F SCRAM PRIMARY CONT Al )IME NT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM p

S F

PRIMARY CONTAINMENT

!PASSIVE)

S F

ESTABLISH PRIMARY INITIATE CLOSURE OF ALL PRIMARY CONTAINMENT ISOLATION VALVES EXCEPT MAIN STEAM LINES ON HI GH DRYWELL PRESSURE MAINTAIN WATER LEVEL. IN REACTOR VESSEL P

RCIC cs EVENT 33 ROD DROP ACCIDENT STATED START RClC ON LOW WATER LEVEL, MAINTAIN CORE COOLING S

F INITIAL CORE CDOLING RHRS SUPPRtSStON POOL COOLING MODE s

F ADS p

S F

F EXTENDICI CORI; COOLING INCIDENT DETECTION CIRCUITRY HPCI CONTROL ROD VELOCITY LIMITER (PASSIVE)

LIMIT REACTIVITY INSERTION RATE START HPCS ON LOW WATER LEVEL MAINTAIN CORE COOLING lRHRSHEATEXCHANGER 1 RHRSPUMP 2 RHRS SERVICE WATER PUMPS SUPPRESSION POOL TEMPERATURE LIMIT 120F, START DEPRESSURIZATION p

MAXIMUM OF 2 VALVES REQUIRED FOR CONTROLLED DEPRESSURIZATIOH LPCI PRESSURE RELIEF SYSTEM S

F PRESSURE RELIEF MAIN CONTROL ROOM ENVIRON*

MENTAL CONTROL SYSTEM p

s CONTROL ROOM ENVIRONMENTAL CONTROL TRANSFER DECAY HEAT TO SUPPRESSION POOL

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15-27 Page:

1 of 1 PROTECTION SEQUENCES FOR PIPE BREAKS INSIDE PRIMARY CONTAINMENT

( ~ DUKE

~ ENERGY STAT£ D SCIIAMSIGIIAL ON LOW WATfR LEVEL l'IEACTOII Oft HIGH l"ROTECTION DftVWELL SYSTEM PftESSURE CONTROL ROD DRIVE SYSTEM SCRAM

,RIMA.RY CONTAINMENT AND REACTOR VESSEL lSOLATION CONTROL SVSTEM s

MAIN STEAM LINE ISOLATION VALVES PRIMAR"t' CONTAINMENT (PASSIVE I ESTABLISH PRIMARY CONTAINMENT PRIMARY CONTAINMENT ANO*REACTOR VESSEL ISOLATION CONTROL SYSTEM SECONDARY CONlAINMENT ISOLATION CONTROL SYSTEM S F REACTOR BUILDING (PASSIVE )

STANDBY GAS TREATMENT SYSTEM OFFGAS VENT SYSTEM I PASSIVE)

ESTABLISH IECONDARV CONTAINMENT RHRS

!SUPPRESSION POOL COOLING MODE) p s

CONTAINMENT COOLING CONTROL ROD DRIVE HOUSING RUPTURE CONTROL ROD CONTROL ROOM DRIVE HOUSING

HEATING, SUPPORT COOLING ANO (P'ASSIVE)

VENTILATION SYSTEM STOP ROO CONTROL ROOM ENVIRONMENTAL EJECTIOt<

CONTROL

~

PIPE BREAK INSIDE PFUMARY CONTAINMENT STATES CD SMALL BREAKS ONLY RADIATION MONITORING INTAKE AIR NUCLEAR SYSTEM PRESSURE TRANSFER DECAY HEAT TO SUPPRESSION POOL RELIEF SYSTEM PRESSURE RELIEF DETECT LOW WATER LEVEL HIGH DRYWELL PRESSURE INITIATE HPCI, LPCI AND CS ON RESPECTIVE TRIP SETTINGS RESTORE COOLING BY FLOOD! NG ANO/OR SPRAYING 2 OR LESS VALVES REQUIRED TO MAINTAIN OEPRESSUAIZATION INCIDENT DETECTION CIRCUITRY ADS S

F LARGE BREAKS SMALL BREAKS INTERMEDIATE BREAKS------------..

,REAKS INCAPACITATING HPCS RESTORE COOL ING BY PLOOOli'.IG AND/OR SPRAYING OTHER BREAKS INCIDENT DETECTION CIRCUITRY RHRS-SUPPRESSION POOL COOLING MOOE OETECT LOW WATER LEVEL.

HIGH DRYWELL PRESSURE INI Tl ATE HPCI. LPCI ANO CS ON RESPECTIVE TRIP SETTINGS 6 VALVES REQUIRED TO DEPRESSURIZE REACTOR RESTORE COOLING INCIDENT DETECTION CIRCUITRY BY FLOOOI NG ANO/OR SPRAYING I RHRS HEAT EXCHANGER I RHRS PUMP 2 RHRS SERVICE WATER PLMPS

.._--:;-r-:,-_, SUPPRESSION POOL 73 TEMPERATURE LIMIT 1300 F, START DEPRESSURIZATION 2 OR LESS VALVES REQUIRED FOR CONTROLLED DEPRESSUR I ZA TION OTHER BREAKS MAINTAIN CORE COOLING EXTENDED CORE COOLING INCIOENT DETECTION CtRCUITRY 73 DETECT LOW WATER LEVEL,HIGH ORYWELL PRESSURE; INITIATE HPCI, LPCI ANO LPCS ON RESPECTIVE TRIP SETTINGS 6 VALVES REQUIRED TO DEPRESSURIZE REACTOR p

RHRS-SUPPRESS ION POOL COOLING MODE F

ADS ACTUATED HPCI ACTUATED SUPPRESSION POOL TEMPERATURE LIMIT ADS 12.0F START 0£-

PRESSURIZTION 2 OR LESS VALVES REQUIRED FOR a>NTROLLED DE,AESSURIZA TION

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-28 Page:

1 of 1 PROTECTION SEQUENCES FOR FUEL HANDLING ACCIDENT

( ~ DUKE ENERGY REACTOR BUILDING VENTILATION RADIATION MONITORING SYSTEM S F SECONDARY CONTAINMENT ISOLATION CONTROL SYSTEM S F STANDBY GAS TREATMENT SYSTEM S F REACTOR BUILDING

!PASSIVE OFFGAS VENT SYSTEM

!PASSIVE)

ESTABLISH SECONDARY CONTAINMENT RADIATION MONITOR TRIP INITIATE SECONDARY CONTAINMENT ISOLATION EVENT 35 FUEL HANDLING ACCIDENT ALL STATES CONTROL ROOM HEATING VENTILATING AND AIR CONDITIONING SYSTEM S F RADIATION LEVEL INDICATION

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15-29 Page:

1 of 1 PROTECTION SEQUENCES FOR PIPE BREAKS OUTSIDE PRIMARY CONTAINMENT

( ~ DUKE ENERGY PRESSURE TRAllSFER RELIEF DECAY HEAT SYSTEM TO SUPPRESSION POOL s

f PRESSURE RELIEF MAJOR PIPE BREAKS CONSIDERED I. REACTOR CLEANUP SYSTEM 0

RHR/SHUTDOWN COOLING

3. MAINSTEAM LINE
4. FEEDWATER LI NE
5. RCICS STEAM LINE CONTROL ROOM FLOW RESTRICTORS HEATl,NG, COOLING ANO (PASSIVE)

VENTILATION F

RESTRICT CONTROL LOSS OF ROOM EN-REACTOR VIRONMENTAL COOLANT CONTROL

  • VARIOUS INDICATIONS I. FEED SIGNALS TO PUMPS
2. FEED TEMPERATURE
3. SPACE TEMPERATURE
4. FLOW I NOi CATIONS
5. REACTOR VESSEL WATER FLOW
6. FEEDWATER FLOW-STE.AM FLOW
7. HOTWELL LEVEL
8. VISUAL INSPECTION
9. LEAKAGE INDICATIONS STATED ONLY RADIATION MONITORING INTAIIE AIR

~

PIPE BREAKS OUTSIDE PRIMARY CONTAINMEN"t.

STATES C AND D PRIMARY CON-TAINMENT AN9 REACTOR VES-SEL !SOLA TION CONTROL SYS.

s F

PRIMARY CON-TAINMENT ANO REACTOR VES-SEL ISOLATION CONTROL SYS.

s ISOLA TE ON LOW WATER LEVEL, HIGH FL<M OR HIGH AREA TEMPERATURE ISOLATE ON VARIOUS INDICATIONS*

p MAIN STEAM LINE ISOLATION VALVES S

F RESTORE COOLING BY FLOODING AND/OR SPRAYING REACTOR VESSEL ISOLATION REACTOR PROTECTION SYSTEM SCRAM SIGNAL ON LOW WATER LEVEL OR MAIN STEAM LINE ISOLATION STATES C, D OTHER PROCESS LINE BREAKS RHRS SHUTDOWN COOLING BREAK INCIDENT START LPCI, INCIDENT START LPCI, CS AND CS AND HPCI DETECTION HPCI ON RESPECTIVE DETECTION CIRCUITRY ON RESPECTIVE CIRCUITRY TRIP SETTINGS 6 VALVES REQUIRED TO DEPRESSURIZE REACTOR RESTORE COOLING BY FLOODING p

s f RHRS-SUPPRESSION POOL COOLING MOOE TRIP SETTINGS HPCI cs F

RH RS-SUPPRESSION POOL COOLING MODE p

S F

I RESTORE AND MAINTAIN COOLING BY FLOODING, AND/OR SPRAYING I RHRS HEAT EXCHANGER I RHRS PUMP 2 RHRS SERVICE WATER Pl.UPS SUPPRESSION POOL TEMPERATURE LIMIT ADS ACTUATED 120F. START DEPRESSURIZATION CONTROL ROD DRIVI: SYSTEM S

F SCRAM S

F SUPPRESSION POOL TEMPERATIJRE LIMIT 130 °F. START DEPRESSURIZATION 2 OR LESS VALVES REQUIRED FOft CONTROLLED DEPRESSURI-ZA TION ADS S

F EXTENDED CORE COOLING 20R LESS VALVES RE-QUIRED TO MAINTAIN DE-PRESSURIZA TI0N

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15-30 Page:

1 of 1 PROTECTION SEQUENCES FOR SHUTDOWN FROM OUTSIDE CONTROL ROOM

( ~ DUKE ENERGY STATE A PLANNED OPERATION:

CONTINUE SHUTDOWN COOLING p

STATES B, D REACTOR PROTECTION SYSTEM CONTROL ROD DRIVE SYSTEM SHUTDOWN REACTOR FROM OUTSIDE CON-TROL ROOM SCRAM BY DE-ENERGIZING SYSTEM MANUALLY EVENT38 SHUTDOWN FROM OUTSIDE CONTROL ROOM ALL STATES REACTOR NOT ISOLATED FROM MAIN CONDENSER PLANNED OPERATION:

CONTROL COOLDOWN USING NORMAL EQUIPMENT REACTOR ISOLATED FROM MAIN CONDENSER STATES C,D TRANSFER DECAY HEAT TO SUPPRESSION POOL PRESSURE RELIEF SYSTEM STATES C, D PRESSURE > 135 psig INCIDENT DETECTION CIRCUITRY HPCI RHRS-SUPPRESSION POOL COOLING MODE p

p START HPCS SYSTEM ON LOW WATER LEVEL MAINTAIN WATER LEVEL REMOVE DECAY HEAT FROM SUPPRESSION POOL RH RS-SHUTDOWN COOLING MODE COOL DOWN REACTOR FROM OUTSIDE CONTROL ROOM PRESSURE RELIEF STATES B, C, D PRESSURE<l35 PSIG WHEN NUCLEAR SYSTEM PRESSURE

< 135 psi& START SYSTEM

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-31 Page:

1 of 1 PROTECTION SEQUENCES FOR SHUTDOWN WITHOUT CONTROL RODS

( ~ DUKE ENERGY EVENT 39 SHUTDOWN WITHOUT CONTROL RODS STATES 8,0 STANDBY LIQUID CONTROL SYSTEM p

SHUTDOWN REACTOR WITHOUT CONTROL RODS INSERT BORON SOLUTION INTO REACTOR VESSEL

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15-32 Page:

1 of 1 COMMONALITY OF AUXILIARY D-C POWER SYSTEM 125 VOLT

( ~ DUKE

~ ENERGY DC POWER SYSTl!II 125 VOLT l

$TATE EIIEHTS STATE

..m.!ill.

1!fil l.ru:u.

.1Iill..

~ STATE

~VEJITS

.J!!!L

~ STATE EVENT!

A 31 A

A 24,ll A

,r;rr,Ja I

31 II II II 24,31 e

II II 31,35,ll C

31 C

10,12,23,24 C

22,24,116 C

12,22,23,24, 31,34,36 C

12,22,23,24,31,34,36 C

12,22.23.2*,Sl,S4,S6,SI-C 12,21,22,Zl,24,ll,34,SS,36,31 D

31 D

10,12,23,24,Sl D

22,2,,116 D

!2,22,23,24,31,33,34,36 0

12,22,23,24,ll,33,34,36 0

12,22.23,24.31,33,34,36,31" D

12,21,22,23,24,31,33,34,35,:11 s f s f s If

_L I

_[

l l

r INCIDENT 1 s

F s

f s

F D£T£CTIOII l1INCID~

CIIICUITIIY DETECTI IICIC CIIICUI ADS' Hl'CI L.PCI cs ADS""

RHRS -

PL,\\NT SUPPRESSION POOL SERVICE lliA TER l

COOLING MODE SVSTDI r H,CS I

I HPCS I run.

-'Will STATE

~ Fill

~ j.Illi.

~ ~

~

A 31,!S II S!,SS,!9 e

II II B

e C

10,12,21,22,2i,2,,n.S4,35,36,36 C

II C

34,SS C

12,22,23,24,ll,34,36,31 C

21,22,23.,.,.

D 10,12,21,22,23,24,31,:11,3O5,SUl,39 D

31 D

34,35 D

12.22, 23,24,31,33,34,36,31 D

21.22,23.JS.34.116 s,

s f

I F

s f

l'IINAltY AUXIUA!n' lt411S-STANCIii' 11!1RS -

CONTAINMENT AC-R SHUTO()WN GAS TREATIIIE:lfT SERVICE lliATER AND REACTOII VESSEL IIYSTDI COOLING MOOE SYSTEM SYSTEM 1SOL.ATI0N CONTROL SYSTEM

  • IIL.DIIDa.N
    • COIITIIOLUD DEPRESSURIZATION IIOTE. SF REQUIREMENT NOT APPUCABLE IN El/lNT 31

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-33 Page:

1 of 1 COMMONALITY OF AUXILIARY EQUIPMENT AREA COOLING SYSTEM

(., DUKE ENERGY STATE B

EVENTS STATE

~

-A--

H,31 B

24, 31 C

10, 12, 21, 23, 24, 34, 36 C 12, 22, 23, 24, 31, 34, 36 D

10, 12,21,23, 24, 33,34,36 D 12, 22, 23, 24, 31, 33, 34, 36 I

RCIC F

J_

f"'"j' NCIDE NT' loETECTION I

~

_j_

LPCI r - 7 INDICATES THAT SYSTEM IS I

I INCLUDED IN COMBINATION BUT DOES NOT REQUIRE L _ _J THE AUXILIARY s

F

=i_

cs NOTE SF REQUIREMENT NOT APPLICABLE IN EVENT 38 EQUIPMENT AREA COOLING SYSTEM STATE EVENTS l

-A-- -

B C

D 38 38 38 RHRS -

SHUTDOWN COOLIN G MODE STATE A

B C

D ST ATE EVENTS A

B C 12, 22,23. 24, 31, 34,36, 38 D 12, 22, 23, 24, 31, 33, 34, 36,38 s

F RHRS -

SUPPRESSION POOL COOLING MOOE EVENT 38 38 38 38 INCIDENT DETECTION l CIRCUITRY I

HPCI l

l STATE

~

A--

B C

22, 34, 36 0

22,34, 36 s l F

I r

I ADS I

HPC I I

I L _

_J

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-34 Page:

1 of 1 COMMONALITY OF AUXILIARY PLANT SERVICE WATER SYSTEM

(., DUKE ENERGY STATE B

C D

STATg e

C 0

12,22,23,24,3_1,34,36,38 12,22.23,24,31,U.34,36,38 s

f RHRS SU"'"RESSION l"OOL COOLING MOOE I

2',3~

24,31 12,22,23,24,31,34,36 12.,22,23,24,31,ll,3-4,16 I

PLANT SERVICE WATER SYSTEM l

_n,._-rr A

B

(;

0 I

s IF STANDBY AC LPCI STATE A--

11 C

0 EVENTS 38-RHRS -

SHUTDOWN COOLING MOOE 38

)8 l8 POWER SYSTEM NOTE: Sf' REQUIREMENT NOT APPLICAISLf IN EVENT 38.

f

~

)

~

24 24,34,36 24,34,36

)

I

)

I STATE l

31,38 8

31,38 C 10, 12.2 l,22.23.24.3U4.l6. 38 0 10, 12,21.22.23.24,31.33,34,36.38

)

1 EQUIPMENT AREA COOLING SYSTEM i

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15-35 Page:

1 of 1 COMMONALITY OF AUXILIARY A-C POWER SYSTEM

( ~ DUKE ENERGY I

l I

STATE

-A--

EVENTS 31, 3~

31, 35, 38 10, 12,21,22,23,24,31,34,36,38 STATE

~ STATE

-A--

STATE

-A--

B C

0 s

F B

C D 10, 12,21,22,23.24,31,33,34,36,38 PLANT SERVICE WATER SYSTEM EVENTS STATE

_3_5_

A--

35 B

34,35,36 C

33,34,35,36 0

CONTROL ROOM HEATING, VENTILATING ANO AIR CONDITIONING HPCI SYSTEM

  • BLDWDOWN A

35 B

35 C

34,35 D

34,35 slF STANDBY GAS TREATMENT SYSTEM EVENTS STATE A

B 10,12,21,23,24,34,36 C

10,12,21,23,24,33,34,36 0

S F

RCIC LPCI NOTE: SF REQUIREMENT NOT APPLICABLE IN EVENT 38.

r -

7 INDICATES THAT SYSTEM IS I

I INCLUDED IN COMBINATION BUT DOES NOT REQUIRE L-.J THE AUXILIARY B

C D

I STANDBY LIQUID CONTROL SYSTEM

..fYf.!ru.

12,22,23,24,31,34,36 12,22,23,24,31,33,34,36 S

F cs AUXILIARY AC POWER SYSTEM I

39 39 STATE A

B C

0 s

F rl, I Aos*I I

I L_J I

l STATE llAll..

A 24,31~

24,31 12,22,23,24,31,34,36 12,22,2S,24,31,33,34,36 A

B B

C 10,ll,21,22,23,24,31,34,36,38 C

D l0,12,21,22,23,24,31,33,34,36,38 0

EQUIPMENT AREA COOLING SYSTEM EVENTS filIE.

A B

22,34,36 C

22,34,36 0

_L HPCI RHRS-SUPPR ESSION POOL COOLING MODE nooi llAif....

A B

12,22,23,24,31,34,36,38 C

12,22,23,24,31,34,36,38 S

F RHRS SERVICE WATER SYSTEM 0

S F

RHRS-SHUTDOWN COOLING MOOE

.f.'ifJ'ill_

38 38 38 38

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-36 Page:

1 of 1 COMMONALITY OF AUXILIARY RHR SERVICE WATER SYSTEM

( ~ DUKE ENERGY STATE A

B EVENTS C

12.22,23,24.31,34.36,38 r,

12.22,23,24,31.33,34.36,38 S

F RHRS -

SUPPRESSION POOL COOLING MODE RHRS -

SERVICE WATER SYSTEM I

NOTE: SF REQUIREMENT NOT APPLICABLE IN EVENT 38.

STATE A

B C

D EVENTS 38 RHRS-SHUTOOWN COOLING MOOE 38 38 38

UPDATED FSAR OPERATIONAL SAFETY ANALYSIS APPENDIX 15A FIGURES Revision:

24 Figure:

15A-37 Page:

1 of 1 COMMONALITY OF AUXILIARY SUPPRESSION POOL STORAGE

(., DUKE ENERGY

.llfil..

A 8

I

~

C I0,12,21,23,24,S4,36 D 10,12,21,23,24,33,34,36 I

I I

HPCI RCICS

  • 8UlWOOWN CONTROLLED DEPRESSURIZATION illli..

EVENTS A

B C

12,22,23,24,31,34,36,38 D 12,22,23,24,31,33,!14,36,31 I

LPCI PRESSURE RELIEF SYSTEM NOTE: SF REQUIREMENT NOT APPLICABLE IN EVENT 38.

SUPPRESSION POOL STORAGE (PASSIVE)

STATE EVENTS A

24,31 B

24,31 C

12,22,23,24,31,34,36 r,

12,22,23,24,31,33,34,36 illI.L..

.f.Yftill...

il8I.L

~

A A

B B

24,31 C

22,34,36 C

l 2,22,23,24,31,34,36,38 D

22,34,36 D 12,22,23,24,31,33,34,36,38 I

PRIMARY cs CONTAINMENT (PASSIVE)

.w.IL

~

A ADS*

HPC.I B

C 12,22,23,24,31,34,36 D 12,22,23,24,31,33,34,36 s

F Aos**

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