ML21130A097
Text
INDUSTRY CODES AND STANDARDS REGULATIONS UNACCEPTABLE RESULTS NUCLEAR SAFETY NUCLEAR SAFETY DESIGN CRITERIA OPERATIONAL CRITERIA I PLANT AND SYSTEMS DESIGN AND CONFIGURATION I
BWR OPERATING STATES PLANNED OPERATIONS EVENT SELECTION PROCESS TRANSIENTS ACCIDENTS I SPECIAL EVENTS PLANT FUNCTIONS PROTECTION SEQUENCE, AUXILIARY SYSTEM AND COMMONALITY DIAGRAMS RULES FOR EVENT ANALYSIS IDENTIFICATION OF SYSTEMS, LIMITS AND RESTRICTIONS EVENT
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STATION ACCEPTANCE AVAILABILITY SAFETY LIMITS ANALYSIS CONSIDERATIONS SYSTEM LEVEL SYSTEM CONDITIONS SURVEILLANCE SAFETY REQUIREMENTS TO PERFORM FREQUENCY AND ESTABLISHED PLANT FUNCTIONS LIMITING CONDITIONS Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT {USAR)
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INPUT TO OTHER SAFETY ASSESSMENTS SYSTEMS CLASSIFICATIONS
- PROPOSED TECHNICAL SPECIFICATIONS BLOCK DIAGRAM FOR NUCLEAR SAF"ETY OPERATIONAL ANALYSIS rlGURE G-2-2 "A/')n c-r1 c:-. rrif'\14.1?1 7/22/96
APPLICABLE OPERATING STATE
-STATE/
--s-_ F /'
EVENTS~G,H 1 EVENT NUMBERS IN WHICH THIS PROTECTION SEQUENCE IS APPL! CABLE SYSTEM SYSTEM K M r I -
SYSTEM J.
1 INDICATES A LIMITATION IS NECESSARY TO OBSERVE THE----.... {C)
SYSTEM N
I s ' OPERATING ENVELOPE FOR PLANNED OPERATIONS REFER TO SECTION G-3.4.5 PLANT FOR LIMITATION TYPES PLANT FUNCTION AND DESCRIPTION FUNCTION 8 C Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFElY ANALYSIS REPORT (USAR)
FORMAT FOR PROTECTION SEQUENCE .DIAGRAMS PLANNED OPERATION FIGURE G-4-1 8/J/00 CADD FILE: C0014122
NUMBER OF EVENT ,
EVENT 1,_1 XY' INDICATES PATH IS \ EVENT TITLE ONLY REQUIRED IN THE SPECIFIED STATE STATES IN WHICH THIS STATES I~!) PROTECTION SEQUENCE IS APPLICABLE STATE W ONLY DIFFERENT DIFFERENT PLANT CONDITION PLANT CONDITION SYSTEM SYSTEM SYSTEM SYSTEM p Q R u INDICATES THE SYSTEM I (s-J ....,.._- IS SAFETY RELATED s IF > (ESSENTIAL) AND THE PLANT FUNCTION IS
_ INDICATES THAT SYSTEMS A SAFETY FUNCTION 1 j 1 1
Q AND R SHARE AS A
~ ~ ....____ PAIR THE REQUIREMENT TO MEET THE SINGLE SYSTEM FAILURE CRITERION INDICATES THAT ONE OR s ....,.._- MORE OF THE KEY PROCESS PARAMATERS MUST BE LIMITED
,, SYSTEM S MUST (sJF,....,. ITSELF MEET THE SINGLE TO SATISFY THE NUCLEAR SAFETY OPERATIONAL CRITERIA
' j FAILURE CRITERION (PARAMATER LIMITS)
SYSTEM T
____.___ LM-1 s MANUAL OPERATOR - ' I ACTION REQUIRED FOR SYSTEM V PLANT PLANT PLANT FUNCTION FUNCTION FUNCTION D E F Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR}
FORMAT FOR PROTECTION SEQUENCE DIAGRAMS
- EVENTS FIGURE G-4-2
"*l"'lr-, ["'!tr", /"l"'I/H,41")'t 7/22/96
FRONT LINE SYSTEM X AUXILIARY SYSTEM A
,s IF1
' . , ' - - . _ INDICATES SYSTEM A MUST MEET DIAGRAM INDICATES THAT AUXILIARY THE SINGLE FAILURE CRITERIA SYSTEMS A,B AND C ARE REQUIRED FOR THE OPERATION OF FRONT - AUXILIARY SYSTEM B LINE SYSTEM X. IF SYSTEM X IS SAFETY RELATED (ESSENTIAL), THEN AUXILIARY SYSTEMS A,B, AND C MUST ALSO BE SAFETY RELATED (ESSENTIAL).
AUXILIARY SYSTEM C Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
FORMAT FOR AUXILIARY SYSTEM DIAGRAMS rtGURE G--4-J
"'Af')I') rflr'* ,:r,r,141?.d. 7/22/96
ALJXL!ARY SYSTEM A
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A X, y A U, V, W A B X, y B V, W State and Events for which the auxiliary/required system B C X, Y, Z C U, V, W, X relationship applies C Y, W D X, Y, Z D U, V, W, X D Y, W, Z
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SlSl£M I I I SYSJ~ SYSTEM K
S>ST£M L
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT {USAR}
FORMAT FOR COMMONALITY DIAGRAMS FIGURE G-4-4
--~l"lt'I rr,r. ,...,v,~,,..,c 7/22/96
REACTOR BUILDING JCS I I RHRS POOL SUPPRESS[ON I I REACTOR BUILDING HEATING AND VENTILATION I I CONTROL ROOM VENTILATION I I REACTOR BUILDING fSOLATION VENTILATION RAOlATION MONITORING SYSTEM SYSTEM SYSTEM s COOLING DC SYSTEM CONTROL POWER DC POWER
'250/125V PUMP BREAKER DC SYSTEM POWER 250/125V ISOLATION VALVE UNIT AUXILIARY AC POWER SYSTEM POWER TO I AtPOWER...
1 SYSTE}J_ 1---a--- CONTROL POWER SYSTEM s
CONTROL AND CONTROL LOGIC s CONTROLS s AIR CONOITfONING EQUfPMENT ISOLATION PAN~ UNIT AUX[LlARY VAf.VE AND PANELS DC SYSTEM POWER 250/125V DAMPER I PANELS AC POWER SYSTEM PUMP POWER s s CONTROLS s
COOLING WATER TO AIR CONDITIONING EQUIPMENT PRIMARY CONTAINMENT HPCI PRESSURE RELJEF ISOLATION VALVES SYSTEM RHR COOLING WATER PANELS s
TO RHR HEAT EXCHANGERS I___
DC CONTROL LOGIC, UNIT AUXJLIARY SYSTEM VN...VE AND VALVE AC POWER S'fSTEM POWER PUMP POWER s
REACTOR COOL AREA CORE SPRAY EQUIPMENT OF RHR SYSTEM f--
COOLING I
EQU[PMENT
~ r---
REQ'O WHEN OPERATING 2 RHR PUMPS [N COOL AREA DC VALVE OF HPCI RELJEF VALVES DECAY HEAT CONTROL A SINGLE QUAD SYSTEM EQUIPMENT S TRANSFER POWER *~
SUPPRESSION UNJT AUXJL!ARY VALVE ANO POOL STORAGE WATER SOURCE AC POWER SYS1EM PUMP POWER (PASSIVE) s LC'JN-LOW SET SET PO[NT PANELS CfRCUITRY CHANGES SECONDARY WATER SUPPLY FOR HPCI PUMP DC BREAKER CONTROL SYSTEM CONTROL LOGIC STEAM STANDBY GAS WATER SUPPLY CONOENSAnoN TREATMENT FOR HPCJ PUMP SYSTEM NORMAL LINE-UP COOL AREA OF CORE SPRAY EQUIPMENT I
PANELS UNJT AUXILIARY CONTROL PANELS AC POWER SYSTEM - POWER s
WATER SUPPLY TO PUMP UNIT AUXJUARY AC POWER SYSTEM DELIVER POWER TO BLOWERS * -NOT APPLICABLE FOR s AND HEATERS JDC STATION BLACKOUT Nebraska Public Power District COOPER NUCLEAR STATION DC POWER POWER UPDATED SAFETY ANALYSIS REPORT (USAR)
SYSTEM 250/125V TO CONTROL s CIRCUITRY PANELS AUXILIARY SYSTEMS FOR FRONT-LINE PANELS PANELS SYSTEMS FIGURE G-5-1 8/3/00 6.00 fll£: C0012750
U'CI ADS CONTROL LOGIC, VALVE ANO VALVE PUMP POWER DC SYSTEM "{5o'f, 25v 1-- BREAKER CONTROL CONTROL LOGIC, EQUIPMENT COOLJNG f-- COOL AREA AROUND RClC TURBJNE PUMP STEAM CONOENSATJON VIJ..V'i. POWER REACTOR EQUIPMENT RELIEF VALVE COOLING RHR PUMP DC CONTROL SENSORS COOLING CONDENS/\TE WATER SUPPLY SYSTEM LOGIC AND s STORAGE F'OR RCIC PUMP SOLENOJDS TANK COOL AREA OF SI RHR EQUIPMENT REQ'O WHEN OPERATING 2 RHR PUMPS IN P~OOL STORAGE (PASSIVE) 1----- Al T SOURCE OF MAKE-UP WATER PANELS A SINGLE QUAD WATER SUPPLY TO LPC1 PUMP PANELS SELF SYSTEMS WITH NO FAIL- CON- SAFETY REQUIRED AUXILIARY SYSTEMS PASSIVE SAFE TAINED RELATED FUEL ASSEMBLIES X X CONTROL ROOS X X CONTROL ROD DRIVES X X NEUTRON MONITORING X X PRIMARY CONTAINMENT ROD BLOCK MONITORING X (PASSIVE) X X MAIN STEAM LINE RAO MONITORING RPS X X MSIV'S X X PANELS FLOW RESTRICTORS X X SAFETY VALVES X X RADWASTE BUILDING X PRESSURE REACTOR BUILDING X X SUPRESSION CONTROL ROD VELOCITY-LIMITER X X CONTROL ROD HOUSING X X DC POWER SYSTEM 250/ 125V X X SUPRESSION POOL STORAGE X X PRIMARY CONTAINMENT RELIEF X X SPENT FUEL POOL X X DIFFERENTIAL X PRESSURE CONTROL CRD HOUSING SUPPORTS X CONTROL ROOM PANELS X X LOCAL PANELS AND RACKS X X EMERGENCY COND. STORAGE TANK X PANELS Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT {USAR)
AUXILIARY SYSTEMS FOR FRONT-LINE
- -NOT APPLICABLE FOR SYSTEMS STATION BLACKOUT FIGURE G-5-2 5/5/06 CADO FILE: COO 12751
RHRS STANDBY SHUTDOWN LIQUID CONTROL COOLING MOOE SYSTEM DC PUMP POWER, VALVE POWER, TANK HEATERS, SYSTEM BREAKER CONTROL VALVE FIRING CIRCUITS RHR PUMP PANELS COOUNG COOL AREA AROUND RHRS EQUJPMENT REQ'D WHEN OPERATING 2 RHR PUMPS IN A SINGLE QUAD ATWS-RPT DC POWER LOGIC COOLING WATER SYSTEM 250/1251/ POWER TO RHR HEAT SUPPLY EXCHANGERS PANELS VN...YE ANO PUMP POWER PANELS Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFE1Y ANALYSIS REPORT (USAR)
AUXILIARY SYSTEMS FOR FRONT-LINE.
SYSTEMS FIGURE G-5-3 8/3/00 CAO
- FIL£: C0012752
OFF sm: AC POWER REACTOR EOU[PMENT UNIT AUXILIARY AC POWER SYSTEM LOW-LOW SET CIRCUITRY SYSTEM COOUNG s s SERVICE COOLING WATER TO STANDBY AC OFF SITE AC POWER DC CONTROL DC HEAT EXCHANGERS, POWER POWER SYSTEM SYSTEM BREAKER WATER SYSTEM POWER SYSTEM SUPPLY SYSTEM SUPPLY POWER CONTROL s BACKUP COOLING WATER SUPPLY s UNIT AUXILIARY DC POWER BREAKER PANELS PANELS AC POWER SYSTEM PUMP POWER, SYSTEM 250/125V VN...VE POWER, CONTROL s FAN POWER s
PANELS PANELS ELEVATED STANDBY AC LOW PRESSURE PANELS SERVICE RHRS JNTERLOCKS WATER SYSTEM SERVICE WATER RELEASE POINT POWER SYSTEM s SYSTEM s LOCAL PANELS PUMP POWER, AND RACKS UNrT AUX[UARY Z SUMP, AC POWER SYSTEM VALVE ANO PUMP POWER VALVE AND LVL SWlTCH s PUMP POWER CONTROL ROOM DC POWER PANELS DC SYSTEM 250/125V SYSTEM WATER SUPPLY TO RHR SERVICE s WATER SYSTEM DC BREAKER PANELS SYSTEM PANELS CONTROL DC SYSTEM COOL PANELS DIESEL PANELS Nebraska Public Power District PANELS COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
AUXILIARY SYSTEMS FOR OTHER AUXILIARY SYSTE;MS FIGURE G-5-4
- 8/3/00 CAD0 Flt£: C0012753
lISUPPRESSION POOL STORAGE l
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A 31,60 A NONE A 31 A NONE 8 31,60 8 NONE 8 31 8 NONE C 13, 15, 18,22,23,24,25,28,28c,31, C 13, 15, 18,22,23,24,25,28,28c,31, C 13, 15, 18,22,23,24,25,28,280,31, 13, 15, 18,22,23,24,25,28,28c,31, 32,41,43,60 32,41,43,60 C 32,41,43 32,41,43,60 D 11, 12, 13, 15, 18,22,23,24,25,26, D 11, 12, 13, 15, 18,22,23,24,25,26, D 11, 12, 13, 15, 18,22,23,24,25, 11, 12, 13, 15, 18,22,23,24, 28,28c,31,32,40,41,43,60,62 28,28c,31,32,40,41,43,60,62 D 26,28.28c,31,32,40,41,43,62 25,26,28,28c,31,32,40, 41,43,60,62 RHR SUPPRESSION POOL COOLING l HPCI J I CORE SPRAY I I ADS I
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A NONE A NONE A NONE A 31 B NONE B NONE B NONE B 31 C 41 C 13,15,18,22,23,24.25,28,28c,31 , C 13, 15, 18,22,23,24,25,28,280, C 13, 15, 18,22,23,24,25,28,28c,31, 32,41,43,60 31,32 32,41,43,60 D 40,41 D dd.~ia~ i ;;i~;fo;1;~ils4a;lls\
3 D 11, 12, 13, 15, 18,22,23,24, 25,26,28,2&,31,32,40,62 D 1 1 2 2~.1~}'a c~~1~:i lla~l1\ 3~ici'.ti2 I I I l
-1 I I I J PRIMARY CONTAINMENT PRESSURE RELIEF (PASSIVE) RCIC LPCI SYSTEM Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
COMMONALITY DIAGRAMS FIGURE G-5-5 1/31/01
REACTOR EQUIPMENT COOLING I
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A NONE A 31 A 31,60 B NONE B 31 B 31,60 13, 15, 18,22,23,24,25,28,280,3 1, C 13, 15, 18,22,23,24,25,28,280,3 1, C 13, 15, 18,22,23,24,25,28,280,3 1, C 32,41,43 32,41,43,60 32,41,43,60 11, 12, 13, 15, 18,22,23,24,25,26, D 11, 12, 13, 15, 18,22,23,24,25, D 11, 12, 13, 15, 18,22,23,24,25,26, D 26.28,280,31,32,40,41,4 3,62 28,280,31,32,40,41,43,6 0,62 28,280,31,32,40,41, 43,60,62 RHR SUPPRESSION POOL I HPCI I I CORE SPRAY I COOLING
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A NONE A 31 B NONE B 31 C 13, 15, 18,22,23,24,25,28,280 C 13, 15, 18,22,23,24,25,28,280,3 1, 31,32 32,41,43,60 D 11, 12, 13, 15, 18.22,23,24, D 11, .* 2, 13, 15, 18,22,23,24,25, 25,26,28,280,31,32,40,6 2 26,28,280,31,32,40,41,4 3,60,62 I LPCJ I I RCIC I
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
COMMONALITY DIAGRAMS FIGURE G-5-6 8/3/00
~ADO FIL£: C0012756
I PRIMARY CONTAINMENT VACUUM RELIEF I LOW-LOW SET CIRCUITRY RELIEF VALAVES STANDBY AC POWER SYSTEM OFF SITE AC POWER RHR SERVICE WATER I
_fY£lli_ _S1fil_ _fY£lli_
---2bIL _fY£lli_ ---2bIL _fY£lli_ ---2bIL A 31,42,60 A 31,60 A NONE A NONE B 31,42,60,61 8 31,60 8 NONE B NONE C 13, 15, 18,22,23,24,25,28,280,3 1, C 13, 15, 18,22,23,24,25,28,28a,3 1, C 41 C 13, 15, 18,22,23,24,25,28,280,3 1, 32,41,43,60 32,41,43,60 32,41,42,43,60 D 11, 12, 13, 15, 18,22,23,24,25,26,28, D 11, 12, 13, 15, 18,22,23,24,25, D 41 D 11, 12, 13, 15, 18,22,23,24,25,26, 26,28,28a,31,32,40,41,4 3,60,62 28,280,31,32,40,41,43,6 0,62,63 28a,31,32,40,41,42,43,6 0,61,62 I PRIMARY CONTAINMENT (PASSIVE)
I PRESSURE RELIEF SYSTEM UNIT AUXILIARY AC POWER RHR SUPPRESSION POOL COOLING Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
COMMONALITY DIAGRAMS i FIGURE G-5-7 8/3/00 CADD FILE: C0012757
UNIT AUXILIARY AC POWER I
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I
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J ____DilliL_ STATE l____E\/lfil_
A 31,60 A NONE A 31,60 A 31,42,60 A 31 B 31,60 B NONE B 31,60 B 31,42,60,61 B 31 C 13, 15, 18,22,23,24,25,28,280,31, C 41,43 C 13, 15, 18,22,23,24,25,28,280,31, C 13, 15, 18,22,23,24,25,28,280,31, C 13, 15, 18,22,23,24,25,28,280,31, 32.41,43,60 32,41,43,60 32.41,42,43,60 32.41,43,60 D 11, 12, 13, 15, 18,22,23,24,25,26, D 40,41,43 D 11, 12, 13, 15, 18,22,23,24,25,26, D 11, 12, 13,15, 18,22,23,24,25,26 0 11, 12, 13, 15, 18,22,23,24,25 28,280,31,32,40,41,43,60,62 28,280,31,32,40,41,43,60,62 28,280,31,32,40,41,42,43,60,61,62' 26,28,280,31,32,40,41,43,60,62 I
I J I REACTOR EOUJPMENT COOLING PRIMARY CONTAINMENT ISOLATION VALVES I RHRSW '---
I SW I '---
I LPCI I
---5I6IE_ ~ STATE ____EliEill_ STATE ____DilliL_
A 42 A NONE A 31,60 B 42 B 61 B 31,60 C 42 C 41 C 13, 15, 18,22,23,24.25.28.280,31, 32.41.43,60 D 42 D 41,61,62 D 11, 12, 13, 15, 18,22.23.24,25,26, 28,280,31,32,40,41,43,60,62 I l j I
t I
I I REAc10RBUILD1NG -,s LATION-1 STANDBY UOUJD CONTROL RHR VENTJLATION RADIATION MONITORING SYSTEM SYSTEM PRESSION. POOL COOLING
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A 31 A 42 A NONE A 42 B 31 B 42 B NONE B 42 C 13, 15, 18,22,23,24,25,28,280,31, C 41,42 C 41 C 41,42.43 32,41,43 0 11, 12, 13, 15, 18,22,23,24.25, D 41.42 D 40,41 D 41,42,43 26.28.280,31,32,40.41,43,62 j I I I I I
I CORE SPRAY CONTROL ROOM PRIMARY CONTAINMENTJ STANDBY GAS REACTOR BU]LDING VENTILATlON (PASSIVE) TREATMENT HEATJNG AND VENTILATION SYSTEM SYSTEM Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
COMMONALITY DIAGRAMS FIGURE G-5-8 CADD FILE: COO 12758 02/05/10
I DC POWER SYSTEM 250/125V l __sJfJ£_
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31,42,60 A NONE A 42 A NONE A NONE A B 31,42,60,61 B NONE B 42 B NONE B NONE C 13, 15, 18,22,23,24,25,28,2 80,31, C 41,42 C 13,15, 18,22,23,24,25,28,2 80,31, C 13, 15, 18,22,23,24,25,28,2 80, C 13, 15, 18,22,23,24,25,28,2 80,31, 31,32 32,41,42,43,60 32,41,43,60 11~J~js~~s1~tl:it~t/ilt*
32,41,43,60
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25.dJ:dl:dl,{~; '.flllr;:t;;,62 D 28,280,31,32,40,41 ,42,43,60,61,62 2 l I I I I I I l ADS J I RCIC I UNIT AUXILIARY AC POWER '--
l HPCf J I CONTROL ROOM VENTflATION
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31 A 60 A. NONE A 31 A B NONE B 31 B 31 8 60 13, 15, 18,22,23,24,25,28,2 80,31, C 15, 18,22,23,24,25,28,2 80,31, NONE C 13, 15, 18,21a;:t:i:ga28,2 8o,31. C 32,41,43,60 C 32,41,43 D 62 D 1.1ig~c~s1~:i~~:?d::?N3:f<r.s2 D 11,12, 13, 15, 18,22,23,24,25, 26,28,280,31,32,40 ,41,43,62 D
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2s I I l I I I I I I RV.ANDPC LPCI [ CORE SPRAY ISOLATION VALVES ATWS-RPT
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31,32,41,43,60 11,12, 13, 15, 18,22,23,24,25, D 41,42,43 dJ:dJ:i:l; :52:fo~f;:Nto~~2~t:i D D 40,41,43 D 26,28,280,31,32,40 ,41,43,60,62 REACTOR BUILDING L<JII-L<J/1 SET PRIMARY CONTAINMENT RHR HEATING AND VENTILATION CIRCUITRY ISOtATfON VALVES SUPPRESSION POOL SYSTEM COOLING
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A 31 31 Nebraska Public Power District B
COOPER NUCLEAR STATION C 13, 15, 18,22,23,24,25,28,2 Ba,31, 32,41,43,60 UPDATED SAFETY ANALYSIS REPORT {USAR)
D dJJi:i:i, :52:~o:l;:ir.to:~2:i:i I COMMONALITY DIAGRAMS I I FIGURE G-5-9 IOC 04/08/02 CAJJO FILE: C0012759
I SERVfCE WATER l
I
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31,60 A 31,42,60 A
B 31,42,60,61 B 31,60 C 13, 15, 18,22,23,24,25,28,2 80,31, C 13, 15, 18,22,23,24,25,28,2 80,31, 32,41,42,43,60 32,41,43,60 D 11, 12, 13, 15, 18,22,23,24,25,26, D 11, 12, 13, 15, 18,22,23,24,25,26, 28,280,31,32,40,41 ,42,43,60,61,62 28,280,31,32,40,41 ,43,60,62 I I I I STANDBY AC REC POWER
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SYSTEM Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
COMMONALITY DIAGRAMS FIGURE G-5-10 04/08/02 CAO* FIL£: CO0l 2760
~
PLANNED OPERATION STATE A SEE EVENT 6 FIGURE EVENT 1 G-5-15 RATE OF COOLANT REACTOR VESSEL CHANGE REACTOR COOL.ANT REFUELING NEW FUEL TEMPERAT\JRE CHEMISTRY FUEL LIMITS INTER- STORAGE FACJLJTIES SPAC[NG LIMIT R LOCKS R REACTOR NUCLEAR NUCLEAR WATER TEMP, VESSEL SYSTEM SYSTEM CONTROL SPENT FUEL WATER L£VEL, WATER LEVEL TEMPERATURE WATER QUALlf'r' ROD STORAGE FACILITIES FUEL SPACING, 10 CFR 20 AND CONTROL CONTROL CONTROL POSITION FUEL HANDLING ERP RADIATION L,R MONJTORING SYSTEM 10 CfR 50 REACTOR BU!LO[NG UMITS CRANE (CASK HANDLING)
STORED FUEL SH[ELDJNG, COOLING ANO 10 CFR 20 AND REACTNJTY PROCESS LIQUID CONTROL RADIATION MONITORS 10 CFR 50 MIN:MUM UMITS WATER L.EVEL REFUELING RESTRJCTroNS REACTOR BUILDING VENTILATION EXHAUST 10 CFR 20 AND RADIATION MONITORING 10 CFR 50 PROCEDURAL SYSTEM LIMiTS LIMITATIONS L,R (FUEL ASSEMBLY ORIENTATION)
RAOWASTE/AUClMENTED RADWASTE BUILDING 10 CFR 20 AND VENTILATION EXHAUST 10 CFR 50 RADIATION MONITORING LIMITS SYSTEM CORE LOADING LlM!T ON PATTERN NUMBER OF (EVENT 1) REACTOR FUEL CRD DRIVES VALVED OUT Of SERVJCE SRM MINIMUM SHUTDOWN MARGIN TURBINE BUJLDlNC COUNTS VENTILATION EXHAUST 10 CFR 20 AND (EVENT 1)
RADIATION 10 CfR 50 MONJTORlNG S'r'STEM LIMITS 10 CFR 20 ANO to CfR 50 LIMITS 10 CFR 71 Nebraska Public Power District u~ns COOPER NUCLEAR STATION UPDATED SAFE1Y ANALYSIS REPORT (USAR)
RADIOACTIVE PROTECTION SEQUENCES FOR MATERIAL RELEASE PLANNED OPERATION IN STATE A CONTROL FIGURE G-5-11 r.11.nn n, i;-. ~not?7if\t 2/19/01
EVENTS 2,5 PLANNED OPERATION STATE 8 SEE FIGURE G-5-15 EVENT 5 EVENT 2 MINIMUM NEW FUEL POWER (SRM) RATE Of NUMBER Of STORAGE FAGILITIES FUEL SPACING MAXIMUM CHANGE OPERABLE R POWER TEMPERATURE CONTROL LIMIT RODS MAXfMUM POWER L£VEL-LOW FLOW OR LOW PRESSURE CORE NUCLEAR SPENT FUEL POWER LEVEL SYSTEM STORAGE FACIUTIES WATER TEMP, CONTROL TEMPERATURE MATER L£VEL,
',_R FUEL SPACING, 10 CFR 20 ANO CONTROL ERP RADIATION FUEL HANDLING, MONITORING SYSTEM 10 CfR 50 LIMITS REACTOR BUJLDING CRANE (CASK HANDLING)
STORED FUEL SHIELDING, COOLING AND REACT[VITY CONTROL PROCESS LIQUID 10 CFR 20 AND RADIATION MONITORS 10 CFR 50 LIMITS REACTOR BUILDING ROD WORTH VENTILATION EXHAUST 10 CFR 20 ANO MJNIMJZER RADIATION MONITORING 10 CFR 50 SYSTEM WAITS L.R MINIMUM COOLANT REACTOR FUEL WATER REACfOR COOLANT CHEMISTRY ROD L£VEL LIMITS PATTERN WHEN POWER RADWASTE/AUGMENTEO <10~
RADWASTE BUILDING 10 CfR 20 AND VENTILATION EXHAUST 10 CfR 50 RADIATION MONITORING LH,HTS SYSTEM REACTOR NUCLEAR VESSEL SYSTEM WATER L.£VEL WATER QUALITY CON7ROL CONTROL TVRB[NE BUILDING VENTILATION EXHAUST 10 CFR 20 AND RADIATION 10 CfR 50 MONITORING SYSTEM LIMITS MPf VENTILATION EXHAUST 10 CfR 20 ANO RAOlATION 10 CfR 50 MQNJTORING SYSTEM LIMITS 10 CFR 71 UMJTS Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
RADIOACTIVE MATERIAL REL£ASE PROTECTION SEQUENCES FOR CONTROL PLANNED OPERATION IN STATE B FIGURE G-5-12 r.Ann rn ,:-. r:nn1 ?7F.?
2/19/01
EVENTS 2,6 PLANNED OPERATION STATE C SEE fJCURE G-5-15 EV,NT 2 I EVENT 6 I
TEMPERATURE
~*
RATE Of" OVERSTRESS MINIMUM CHANGE PROTECTION 10 CFR 20 AND REACTOR FUEL REACTOR VESSEL REACTOR VESSEL AND MAKE-UP PRIMARY CONTAINMENT TEMPERA-WATER (PASSIVE) LEVEL
- 10 CFR 50 L CAPABfUTY TURE AND LIMITS L LEVEL MINIMUM PRESSURE TEMPERATURE LEAKAGE WfTH HEAD ON LIMIT LIMITS REACTOR FUEL NUCl..£AR MAXIMUM WATER FEEDWATER SYSTEM TEMPERA-L LEAKAGE TEMPERATURE TURE ANO ERP RADIATION ~ O CFR 20 AND CONTROL VOLUME MONITORING SYSTEM 10 CFR 50 llMITS LIMITS I ,.....J_
AVAJLABtLITY NUCLEAR SYSTEM TEMPERATURE PRIMARY CONTROL CONTAINMENT I \ ATMOSPHERfC PROCESS LIQUID 10 CFR 20 AND PRESSURE AND RADIATION MONJTORS 10 CFR 50 TEMP. CONTROL LIMtTS 10 CFR 71 LIMIT APPUEO COOLANT TO SH[PPlNG MAXIMUM CHEMISTRY NUMBER OF DRIVES CASK REACTOR VESSEL PRESSURE REACTOR COOL.Afff Ul\4ITS CRD OUT Of SERVICE t,_R MtNIMUM RADJOACTIV[1Y SHUTDOWN MARGIN PRESSURIZATION LIMITS TEMPERATURE RADWASTE/AUGMENTEO RAOWASTE BU!LDJNG MAXIMUM NUCLEAR VENTilATION EXHAUST 10 CFR 20 AND SYSTEM 10 CFR 50 PRESSURE RADIATION MONITORfNG LIMIT WATER QUALITY SYSTEM llMITS CONTROL REACTOR nJRBINE BUILDING VESSEL VENTILATION EXHAUST 10 CFR 20 ANO PRESSURE RADIATION 10 CFR 50 CONTROL MONITORING SYSTEM UMJTS NEW FUEL FUEL STORAGE FACILITIES SP,CING MPF VENTILATION EXHAUST 10 CFR 20 AND RADIATION 10 CFR 50 MONITORING SYSTEM LIMITS WATER TEMPERATURE SPENT FUEL WATER LEVEL STORAGE F"ACJLmES L,R FUEL SPACING FUEL HANDLING SOLID RADWASTE SYSTEM 10 CFR 71 REACTOR BUJLDfNG C=~J~K UMlTS STORED FUEL Nebraska Public Power District SHIELDING, COOLING AND COOPER NUCLEAR STATION REACTIVITY UPDATED SAFElY ANALYSIS REPORT (USAR}
CONTROL RADIOACTIVE MATERIAL RELEASE PROTECTION SEQUENCES FOR PLANNED OPERATION CONTROL IN STATE C FIGURE G-5-13 f"'t.nn r11 ~- rnn1?7~~ 2/19/01
EVENT$ 2 3 4 5 PLANNED OPERATION STATE D SEE FIGURE G-5-15 NUMBER II I DRfVES MINIMUM OUT OF
- POWER (SRM) SERVICE
~ %~~~M A<R EJECTOR Off-GAS~ MINIMUM TEMPERAnJRE RADIATION MONJTORING 10 CFR 20 ANO REACTOR FUEL REACTOR VESSEL RATE OF RIVER WATER REACTOR FUEL LE~~E WATER I
SYSTEM 10 CFR 50 SCRAM L (EVENT 4) L LEVEL L CHANGE TIMES L,R LJMJTS 8fci \Wr'iJT 42) MINJIAUM TEMPERAnJRE LEVEL.
TEMP ROD WORTH ROD WITH HEAD ON PATTERN MINIMIZER WHEN POWER ULTIMATE
<10" HEAT I-- SJNK I I< I 10 CFR 20 AND CORE ) MAXIMUM ERP RADIATlON ( POWER LEVEL REACTOR FUEL FEEDWAT'ER MONITORING SYSTEM 10 CFR 50 CONTROL LIMITS L TEMPERATURE AVAILABILITY WHEN POWER
>.30" I I LOOP PROCESS LIQUID ~ 10 CFR 20 AND ANO VESSEL RADIATION MONITORS 10 CFR 50 TEMPERATURE L LIMITS DIFFERENCE REACTOR BU[LOING NUCLEAR VENTILATION EXHAUST 10 CFR 20 AND SYSTEM REACTOR FUEL POWER TEMPERATURE RADIATION MONITORING 10 CFR 50 PEAKING SYSTEM LIMITS L CONTROL L,R II j n"'""~
I
,_,..,~,..-AU.1l,,--.,..,. f TEMPERATURE AND PRESSURE LIMITS RADWASTE/AUGMENTED ~ CORE I I I RADWASTE BUILDING NEUTRON FLUX COOLANT VENTILATION EXHAUST 10 CFR 20 AND RADIATION MONITORING SYSTEM 10 CFR 50 LIMITS DISTRIBUTION CONTROL CHEMJSTRY LIMITS I IPRESSUREP~giPRESSiONI WATER TEMPERAl\JRE AND VOLUME LIMIT RAOIO-ACTIVITY LJMITS I I I TURB{NE BUILDING
\IENTTLATTON EXHAUST 10 CFR 20 AND RADIATION 10 CfR 50 MONITORING SYSTEM w.ms L
10 CFR 20 ANO 10 CfR 50 LIMITS EVENTS RHRS 3,4,5 MAXIMUM NEW FUEL FUEL SHUTDOWN STORAGE FAC!LlTIES COOLING MOOE PRESSURE SPACING LIMIT R RECIRCULATION SYSTEM FLOW RUNOUT 10 CfR 71 LJMJTS (EVENT 4) (EVENTS 2,5) WATER TEMPERATURE LJMITS WATER l.£VEL SPENT FUEL FUEL SPAC(NG NUCLEAR STORAGE fAC(LlTIES SYSTEM FUEL HANDLING MAXIMUM l,R PRESSURE LEAKAGE CONTROL REACTOR BUJLDJNG LIMIT CRANE (CASK HANDLING)
MINIMUM RA.DIOACTNE FLOW RATE MATERIAL STORAGE FUEL RELEASE CONTROL SHIELDJNG Nebraska Public Power District K1 (EVENT 4)
POWER/FLOW MAP REACTOR POOLING AND REACTIVITY COOPER NUCLEAR STATION VESSEL CONTROL UPDATED SAFETY ANALYSIS REPORT (USAR)
CORE PRESSURE OVERSTRESS COOLANT CONTROL PROTECTION FLOW RATE CONTROL MAKE -
CAPABILITY UP PROTECTION SEQUENCES LEAKAGE LIMITS FOR PLANNED OPERATION IN STATE D FIGURE G-5-14 2/19/01
SEE FIGURES G-5-11, -12, -13 ANO -14 STATES A, B, C AND D STATES A AND C REACTOR COOLANT REACTOR SYSTEM PRESSURE EOUNDARY CORE GEOMETRY (PASSIVE) (2) RCIC HPCI ADS (PASSIVE) (1) s SI F REACTOR VESSEL and PRIMARY CONTAINMENT ISOLATION cs IJ'CI and CONTROL SYSYTEM M Rv anc PC s IF s IF JCS SI F MA[NTAIN g~g~~ s cs LPC!
SI F s IF (1) RCPB: (2) CORE GEOMETRY:
- 2. MAIN STEAM SYSTEM 7. CRD SYSTEM 2. CORE SUPPORT STRUCTURES Nebraska Public Power District
- 5. RCIC PROTECTION SEQUENCES FOR PLANNED OPERATION IN STATE A, B, C ~* ., .
D FIGURE G-5-15 8/J/00 l\00 FIL£; GCOOl 2765
mill_]J TURBJNE TRIP OR GENERATOR LOAD REJECTrON WITH BYPASS STATE 0 POWER <30% POWER >30%
, __ _.__--, _ _ _ SCRAM SIGNAL INITIATE MS[V CLOSURE ON LOW
Vl>LVE CLOSURE
- 2. FOR GENERATOR TRIP ON TURBINE CONTROL VALVE FAST CLOSURE ISOLATE MAIN STEAM UNES PLANNED OPERATION
- PLANNED OPERATfON FEEDWATER MA[NTA!NS REESTABLISH POWER LEVEL OPERATION OR INSERT CONTROL PRESSURE REACTOR START ON LOW ACH[EVE SHUIDOWN RELIEF S ROOS VESSEL REACTOR WATER ISOLATION LEVEL (LEVEL 2)
RCIC HPCI ADS CORE SPRAY I.PC!
s SI F
~ ~
EXTENDED CORE
- -i OOLING SEQUENCE BOUNDED BY LOSS OF I I L
SHUTDOWN COOLING (EVENT 31) _J NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION
- BELOW ABOUT 25 PERCENT OF RATED POWER, THE BYPASS SYSTEM WILL TRANSFER UPDATED SAFETY ANALYSIS REPORT {USAR)
STEAM AROUND THE TURBINE AND AVOID REACTOR SCRAM. BETWEEN ABOUT 25 PERCENT AND 30 PERCENT POWER, A HIG'-1 RPV PRESSURE SCRAM WILL RESULT UNLESS OPERATOR PROTECTION SEQUENCES FOR ACTION CAN REDUCE POWER TO WITHIN THE BYPASS CAPACITY.
TURBINE TRIP OR GENERATOR LOAD REJECTION WITH ;f;3YPASS FIGURE G-5-16
- 8/3/00 100 FILE: C0012766
Mfil_l.2 T1JRBrNE TRIP OR GENERATOR LOAD REJECTJON WJTHOUT BYPASS STATE D POWER <30% POWER >30%
PRESSURE RELJEf RV ANO PC IN!TTATE MSJV CLOSURE ON LOW SYSTEM JCS TURBINE JNL£T PRESSURE OR LOW REACTOR WATER LEVEL (LEVEL 1)
ISOLATE MAIN STEAM UNES HIGH NEUTRON PLANNED FLUX OPERATION PLANNED OPERATION 1
REACTOR FEEOWATER MAINTAINS 1S~&1~6N PRESSURE l£VEL RELIEF S S UR8JNE STOP VALVE START ON LOW TRIP ON CLOSURE REACTOR WATER HIGH NEUTRON CONTROL VALVE FAST LEVEL (L£VEL 2)
FLUX CLOSURE HIGH RV PRESSURE INSERT RCJC HPCI ADS CONTROL RODS CORE SPRAY LPCI s
SI F
~ ~
EXTENDED CORE OOUNG SEQUENCE
- -i BOUNDED BY LOSS OF L: umowN cooLJN:J (EVENT 31)
NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR TURBINE TRIP OR GENERATOR LOAD REJECTION W/OUTi. BYPASS FIGURE G-5-17 '
8/3/00
- ADD f"JL£: C0012767
lli:t!L.U ISOLATION OF AU.
MAIN STEAM UNES STATES C,D lNCIDENT START ON LOW DETECTION REACTOR WATER STATE D
--;r;-
CfRCUITRY S L£VEL (L£VEL 2)
>825PSIG PLANNED OPERATION STATE 0
<825PSJG SCRAM SIGNAL ADS PRESSURE RELJEF FROM MSIV POSJTION RCIC HPCI SYSTEM SWITCHES SIF lNSERT SUPPRESS[ON POOL CONTROL CORE SPRAY LPCl (PASSJVE) RODS s SJF PRESSURE RELIEF S
~ -~
EXTENDED CORE OOLlNG SEQUENCE BOUNDED BY LOSS OF I I L
SHUTDOWN COOLING (EVENT 31) _J NOTE: REFER TO FIG. G-4-2 FOR OlAGRAM FORMAT.
Nebrosko Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR ISOLATION OF ALL MAIN STEAM LIN,ES FIGURE G-5-18 ., '
8/3/00 CA00 FlL£: C0012768
.EYEt,JLU ISOLATION OF ONE MAIN STEAM UNE STATE 0 HIGH NEUTRON FLUX SIGNAL SCRAM SfGNAL ON NEUTRON MONJTORJNG SYSTEM TRIP INSERT CONTROL RODS PLANNED OPERATION NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR ISOLATION OF ONE MAIN STEAM LIN~*
FIGURE G-5-19 '
8/3/00
~DO FJL.£: C0012769
mtil....!a LOSS OF CONDENSER VACUUM STATES C,D START ON LOW I PRESSURE RELIEF REACTOR WATER INITIATE SYSTEM LEVEL (LEVEL 2) sI L
ISOLATION ON LOW CONDENSER VACUUM ISOLATE MAIN I SUPPr11ssJ~~) POOL 1 I RClC HPC\ ADS STEAM LINES HIGH NEUTRON
_J FLUX TRIP PRESSURE CORE SPRAY LPCI SCRAM ON: RELIEF RPS f------. 1. TURBINE STOP VALVE CLOSURE
- 2. REACTOR PRESSURE SI F
- 3. NEUTRON MONITORING SYSTEM TRIP SI F
- 4. MAIN STEAM ISOLATION VALVE CLOSURE CRD I--- INSERT CONTROL RODS
~~
~
EXTENDED CORE DOLING SEQUENCE BOUNDED BY LOSS OF I I L
SHUTDOWN COOLING (EVENT 31) _J NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR LOSS OF CONDENSER VACUUM FIGURE G-5-2O GADD flLE: C001277D 8/28/08
JcfillL.1§ LOSS OF FEEOWATER HEATING STATE D HIGH NEUTRON FLUX SCRAM SIGNAL ON NEUTRON MONITORJNG SYSTEM TRIP PLANNED OPERATION INSERT CONTROL RODS NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR LOSS OF FEEDWATER HEATit\lG FIGURE G-5-21 ' '
8/3/00 100 FILL C0012771
rY£tiLJ.l SHUIDOWN COOLING MALFUNCTION (TEMPERATURE DECREASE)
ALL STATES PLANNED OPERATION HIGH NEUTRON FLUX TRIP ON HIGH N£UTRON FLUX JNSERT CONTROL ROOS NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR SHUTDOWN COOLING (RHRS)
MALFUNCTION - TEMP ,OECREASE FIGURE G-5-22 '
8/3/00 CAOO FJL£: C0012772
.E\!fJiL1B INADVERTENT HPCf PUMP START STATES C,O NEUTRON HIGH START ON LOW MONITORlNG SYSTEM NEUTRON INITIATE FLUX MSJV CLOSURE REACTOR WATER s ON LOW PR::SSURE l£VEL (l£VEL 2)
S /F
[SOLATE AfJS SCRAM ON: RCIC HPCI MAIN STEAM
- 1. TURBINE TRIP LINES RPS f~~GB~N:A~~P ~~~
POSHJON SWJTCH
- 2. HIGH NEUTRON f"LUX TRIP REACTOR PRESSURE CORE SPRAY LPCI VESSEL REUEF s
[NSERT ISOLATION CONTROL RODS S/F
~ - =l EXTENDED CORE OGLING SEQUENCE l: I BOUNDED BY LOSS OF UTDOWN COOLING (EVENT 31) _J NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT, Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR INADVERTENT HPCI.
PUMP START i, FIGURE G-5-23 8/3/00
\OD rnr: C0012773
.EIDIL.1.9 CONTROL ROD WITHDRA.WAL ERROR ALL STATES HIGH FLUX SCRAM, !RM TERMINATE SCRAM SfGNAL ON ROD WITHDRAWAL NEUTRON MONITORING SYSTEM TRIP PLANNED OPERATION INSERT CONTROL RODS NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR CONTROL ROD WITHDRAWAL ERROR FIGURE G-5-24 ., '
8/3/00
~DD nt..£: C0012774
MlfU 2 PRESSURE REGULATOR FAILURE - OPEN STATES C,O PLANNED OPERATION AFTER ISOLATION CLOSE MS!Vs START ON LOW ON LOW PRESSURE SCRAM SIGNAL FROM - REACTOR WATER (RUN MODE)
LEVEL (LEVEL 2)
- 1. MS!V POSITION SW!TCH
- 2. TURBINE TR!P STOP VN..VE POSmON SWITCH
- 3. HIGH PRESSURE
- 4. LOW WATER l£VEL
!SOL.ATE MAIN STE.AM INSERT HPCI AOS LJNES CONTROL RCIC PRESSURE RELIEF ROOS SYSTEM S/f REACTOR CORE SPRAY LPCI VESSEL s ISOLATION SUPPRESSION POOL (PASSM )
SI c PRESSURE RELIEF 7
I f(XTEN OED CORE I COOLING SEQUENCE BOUNDED BY LOSS OF I
L SHUffiOWN COOLI Nj (EVENT 31)
DIAGRAM FORMAT.
NOTE: REFER TO FIG. G-4-2 FOR Nebraska Public Power Distri ct COOPER NUCLEAR STATION (USAR)
UPDATED SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR PRESSURE REGULATOR FAILURE - OP.E 1 N
FIGURE G-5-2 5 8/3/0 0
£YEi'IL2.J lNAOVERTENT OPEN[NG OF A RELIEF OR SAFETY VALVE STATES C,D STATE D MANUAL SCRAM EDP SUPPRESS/ON AT TECH SPEC POOL TEMPERATURE SUPPRESSION POOL TEMPERAnJRE TRANSFER fNITIATE SCRAM ON DECAY HEAT RPS HIGH DRYWEU. PRESSURE TO SERVICE SAFETY VN...VE OPEN WATER INSERT HEAT CAPACITY CONTROL TEMPERATIJRE LIMIT RODS ADS FOLLOWING SHUTDOWN PLANNED lNCIOENT START ON LOW OPERATION DETECTION REACTOR WATER
---;r,-
CIRCUITRY S LEVEL (LEVEL 2)
CLOSE ON RV AND PC LOW JCS CONDENSER s VACUUM CORE SPRAY lPC!
s ISOIAIT MAIN SIDM s LINES SI F
( R~CTOR PRESSURE ~ VESSEL RELIEF S ISOLATION
~ ~
EXTENDED CORE DOLING SEQUENCE
- -i NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
BOUNDED BY LOSS OF Nebraska Public Power District I COOPER NUCLEAR STATION L
SHUTDOWN COOUNj (EVENT 31) UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR INADVERTENT OPENING OF A SAFETY OR RELIEf
- VALVE FIGURE G-5-26 8/3/00
- .ADD f"IL.E: C0012776
~
LOSS OF fEEDWATER FLOW SfAITS C,D STATE O ONLY P<75 PSIG P>75 PSfG PLANNED OPERATION PLANNED OPERAflON START ON LOW
!NIT[ATE SCRAM ON REACTOR WATER RPS LOW WATER l.EV£L SHUTDOWN COOLlNG l£VEL (l£VEL 2)
(l£VEL 3)
[NSERT RCfC HPC[ AOS CONTROL RODS CORE SPRAY LPCl s
PRESSURE RELIEF SYSTEM J
I RV AND PC
!CS S
~ lNITIA'fE MSIV CLOSURE ON LOW PRESSURE s Ir
!SOL.ATE MAfN STEAM LINES REACTOR IS~&1~6N S
\__
7 I
jEXTENOED CORE PRESSURE '
RELIEF s I COOLING SEQUENCE BOUNDED BY LOSS OF I
L SHUTDOWN COOL/Nj (EVENT 31)
NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebrosko Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR LOSS OF FEEDWATER FLOW FIGURE G-5-27 8/3/00
- ADO FIL.£: C0012777
=
LOSS OF OFF'-SlTE POWER AU. STATES AU. STATES PRESSURE <75 PS(G PLANNED OPERATION SHUTDOWN COOLING STATES C.D PRESSURE > 75 PSIG STATES B, D CLOSE ON LOW SCRAM SIGNAL CONDENSER VACUUM START ON LOW RPS OR RPS M-G SET REACTOR WATER
- l. TURB[NE CONTROL COASTDOWN OR L£VEL (L£VEL 2)
VALVE FAST CLOSURE (TURBINE 0\/ERSPEED TRIP DUE TO GENERATOR SIF LOAD REJECTION)
- 2. TURBINE TRIP STOP VALVE POSJTTON SWITCH (DUE TO INSERT HIGH REACTOR WATER LEVEL CRD lSOlATE RC!C HPC! ADS CONTROL MAIN STEAM CAUSED BY REC!RC. PUMP RODS LlNES COASTDDWN),
SI F
- 4. RPS M-G SET COASTDOWN OR TRIP (FAIL-SAFE) LPCI CORE SPRAY PRESSURE REACTOR RELIEF VESSEL ISOLATION S!F 7
I I jEXITNOED CORE COOUNG SEQUENCE or L: I BOUNDED BY LOSS UTDOWN COOLING (EVENT J1) _j NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebrosko Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR LOSS OF OFF-SITE POWER FIGURE G-5-28 ADO f"JL£: C0012778 8/J/00
=
RECIRCULATION FLOW CONTROL FAlLURE -
DECREASING FLOW STATE D y
INITIATE SCRAM ON MS[V CLOSURE TURBJNE TRIP ON LOW PRESSURE LOW WATER l.£V£L (LE'IEL 3) INCfDENT START ON LOW DETECTION REACTOR WATER CIRCUITRY S LEVEL (LEVEL 2)
INSERT CONTROL ISOLATE MA(N STEAM
;r,-
RODS LINES PLANNED
- OPERATION RCIC HPCI ADS REACTOR VESSEL JSOLATJON CORE SPRAY LFCI s
PRESSURE SI F RELIEF S 7
I jEXTENDED CORE I COOLING SEQUENCE BOUNDED BY LOSS OF I
L SHUTDOWN COOLIN:J (EVENT 31)
NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION
- BELOW ABOUT 25 PERCENT OF RATED POWER, THE BYPASS SYSTEM WILL TRANSFER UPDATED SAFETY ANALYSIS REPORT (USAR)
STEAM AROUND THE TURBINE AND AVOID REACTOR SCRAM. BETWEEN ABOUT 25 PERCENT AND 30 PERCENT POWER, A HIGH RPV PRESSURE SCRAM WILL RESULT UNLESS OPERATOR PROTECTION SEQUENCES FOR ACTION CAN REDUCE POWER TO WITHIN THE BYPASS CAPACITY.
RECIRCULATION FLOW CONTROLLER FAILURE-DECREASING FLOW*
FIGURE G-5-29 8/3/00 I.DO FILI: C0012779
.El:'.El!L21 TRIP OF ONE RECIRCULATION PUMP STATES C,O PLANNED OPERATrON NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFE1Y ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR TRIP OF ONE RECIRCULATION PUMP
FIGURE G-5-JO 8/3/00 CADO FIL.£: COOl 2780
=r...2B TRIP OF TWO RECIRCULATJON PUMPS STATE C.D START ON LOW INITIATE REACTOR WATER SCRAM ON MSfV CLOSURE TURBINE TRIP LEVEL (LEVEL 2)
ABNORMAL PROCEDURE ON LOW PRESSURE LOW WATER LEVEL (LEVEL 3)
ISOlATE MAIN STE.AN INSERT LINES ADS CONTROL RCIC HPC)
RODS REACTOR VESSEL ISOLATION CORE SPRAY LPCI s
SI F PRESSURE REUEF S 7
I jEXTENDEO CORE I COOLING SEQUENCE BOUNDED BY LOSS OF I
L SHUTDOWN COOUN:J (EVENT 31)
NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebroska Public Power District COOPER NUCLEAR STATION UPDATED SAFElY ANALYSIS REPORT (USAR)
- THE ANALYSIS ASSUMES BELOW ABOUT 25 PERCENT OF RATED POWER, THE BYPASS SYSYTEM WILL TRANSFER STEAM AROUND THE TURBINE AND AVOJD REACTOR SCRAM. BETWEEN ABOUT 25 AND 30 PERCENT POWER, A HIGH RPV PRESSURE SCRAM WILL RESULT UNLESS OPERATOR PERCENT ACTION PROTECTION SEQUENCES FOR CAN REDUCE POWER TO WITHIN THE BYPASS CAPACITY HOWEVER, THE ABNORMAL PROCEDURE REQUIRES TRIP OF TWO THE OPERATOR TO INITIATE A MANUAL SCRAM.
RECIRCULATION PUMPS FIGURE G-5-31
- 8/3/00
\OD fll.E: C0012781
.EYElil..2S RECIRCULATION FLOW CONTROL FA[LURE -
lNCREASING FLOW STATE D PLANNED OPERATrON HIGH NEUTRON FLUX (APRM) SIGNAL TO RPS SCRAM SIGN.A.L ON NEUTRON MONITORING SYSTEM TRJP INSERT CONTROL ROOS NOTE: REFER TO FIG. G--4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR RECIRCULATION FLOW CONTROLLER FAILURE-INCREASING FuOW FIGURE G-5-32 ., '
8/3/00 CAOO FJLE: C0012782
=uo START-UP Of l LE RECJRCULATION PUMP All STATES PLANNED OPERATION HJGH NEUTRON FLUX (APRM) SlGNAL TO RPS SCRAM SIGNAL ON NEUTRON MONITORING SYSTEM TRIP INSERT CONTROL RODS NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFE1Y ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR START-UP OF IDLE RECIRCULATION PUMP FIGURE G-5-33 '
8/3/00 CA00 flLE: C00t2783
i',lllLJ.l LOSS OF SHUTDOWN COOLING ALL STATES 7
STATES 8,0 STATES C,O STATES C,O
>75 PSJG RPS PRESSURE RELIEF' SYSTEM ICS CLOSED ON RV ANO PC J--LOW CONDENSER VACUUM OR 7 I I
<75 PS[G START ON LOW s R~Mro~Jf REACTOR WATER I
OR TRIP l£VEL (LEVEL 2) EOP LIMIT ON S F REACTOR WATER l£VEL I
INSERT ISOLATE I
CONTROL MAIN STEAM I
RODS LlNES RCJC HPCr ADS I
STATES A,8 PRESSURE I
I CORE SPRAY LPCI RELIEF S s CORE SPRAY LPCI I
M SI' I EOP SUPPRESSION POOL TEMPERATURE I
I UM/T
_ _ _ _ _J r EOP SlJPRESS!ON POOL TEMPERATURE RHR SUPPRESSION POOL COOUNG TRANSFER DECAY HEATI TO SERVICE I
WAITR SI F I
TRANSFER DECAY HEAT TO SERVICE I
SCRAM SIGNALS M WATER
- 1. TURBINE CONTROL VALVE FAST CLOSURE (TURBINE I
I OVERSPEED DUE TO
_J GENERATOR LOAD REJECTION)
- 2. TURBINE TRIP STOP VALVE I I POSITION SWITCH (DUE TO HIGH REACTOR WATER LEVEL CAUSED BY RECIRCULATION NOTE: THIS EVENT DEMONSTRATES THE I
PUMP COAST DOWN) EOP HEAT CAPACJTY TEMPERATURE LJM/T CAPABILITY TO ATTAIN COLD I
___I DEPRESSURIZE FA! LURES AND THE LOSS OF ANO TRANSFER OFFSITE POWER I
- 4. REACTOR PROTECTION SYSTEM DECAY HEAT TO M-G SET COAST DOWN OR SUPRESSION POOL
,---_J TRIP (FAIL-SAFE)
I I PLANNED OPERATION I NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
SHUTDOWN COOLING Nebraska Public Power District I
RESTORE I
LPCI ANO MAINTAIN CORE SPRAY COOPER NUCLEAR STATION M WATER LEVEL M S UPDATED SAFETY ANALYSIS REPORT (USAR)
I NOTE:
I EXTENDED CORE COOLING SEQUENCE BOUNDS PROTECTION SEQUENCES FOR OTHER SSD's LOSS OF J
SHUTDOWN COOLIN~;
,OD FIL£: C0012784 L BOUNDRY OF EXTENDED CORE COOLING - - -
FIGURE G-5-34 8/3/00
~
FEE WATER C0NTR0LilR FAILURE MAXIMUM DEMAND STATES C,D PLANNED OPEAATION JNCJOENT START ON LOW PRESSURE RELIEF OETECT[QN REACTOR WATER
--;v-SYSTEM CIRCUITRY S LEVEL (LEVEL 2)
SI F NEUTRON lRM SCRAM OR APRM SCRAM SUPPRESSION POOL RCIC HPCI ADS MONrTORfNG SYSTEM AT REDUCED SET POINT lN (PASSIVE) s START -UP MODE SI F APRM SCRAM JN RUN MOOE SCRAM ON PRESSURE CORE SPRAY LPG!
- 1. TURBINE STOP RELIEF S s VALVE POSrTION SWITCH OR TURBINE TRIP
- 2. NEUTRON MONrTORING SYSTEM TRJP SI F INSERT RV AND PC CONTROL !CS RODS SI F INITIATE MSIV CLOSURE ON LOW PRESSURE MSJV:s
~~
~
SI F EXTTNDED CORE ISOLATE MAIN STEAM OOLING SEQUENCE LINES REACTOR BOUNDED BY LOSS Of VESSEL I I L
ISOLATION SHUTDOWN COOLING (EVENT 31) _J NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR FEEDWATER CONTROLLER FAILURE-MAXIMUM DEMAND ., '
FIGURE G-5-35 8/3/00 ADD FIL£: C0012785
t ~
CONTROL ROD DROP ACCIDENT STATE 0 PLANNED PLANNED OPERATJON OPERATION 1---
G; NEUTRON HlGH MONITORING SYSTEM NEUTRON I
EOP START ON LOW s FLUX I RADrOACTTVE REL.£ASE REACTOR WATER LEVEL (LEVEL 2)
HIGH RADIATION s MAIN STEAM LINES TRIP ON HIGH NEUTRON FLUX I I I RCIC HPCI ADS PRESSURE lNJTIATE REACTOR OPERATOR WATER SAMPLE VALVE ACTION FW ANO PC RELIEF S CLOSURE & MECH BASED ON !CS VACUUM PUMP ISOLATION HIGH M sl F ON HIGH RADIATION RADIATION INSERT CONTROL ROOS I sl F CORE SPRAY LPCI s
REACTOR WATER ISOLATE PRIMARY CONTAINMENT SAMPLE VALVES REACTOR WATER ISOLATION VALVES s SAMPLE VALVES SJ F SI F SIF CONTROL ROD VELOCITY-LIMITER I
(PASSIVE) s PRIMARY CONTAINMENT MECHANICAL ISOLATE (PASSIVE)
VACUUM PUMP MECH. VACUUM
~
s PUMP
~ -:-i SIF REACTIVITY INSERTION S ESTABUSH EXTENDED CORE RATE RHR SUPRESSION POOL RADIOACTIVE OOLING SEQUENCE COOLING MATERIAL CO~~~m~NT S REL£ASE BOUNDED BY LOSS OF I I M CONTROL L
SJ F SHUTDOWN COOLING (EVENT 31) _J MSJVs ISOLATE MAIN STEAM LINES CONTAJNMENT COOLING S SJF REACTOR VESSEL S ISO!ATION NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT {USAR)
PROTECTION SEQUENCES FOR CONTROL ROD DROP ACCIDENT FIGURE G-5-36 04/08/02 CAOO flt.£: C0012786
SHEET 1 OF 2 MNL.+/-1 PIPE BREAKS INSIDE PRIMARY CONTAINMENT STATES C,D SEE SHEET 2 OF 2 SCRAM ON LOW REACTOR LOW WATER WATER LEVEL OR LEVEL OR HIGH ORYWELL HIGH OR'tWELL EDP HIGH WETWELL EOP SUPPRESSION PLANNED PRESSURE PRESSURE p PRESSURE POOL TEMPERATURE OPERATJON SI F INSERT RHR TRANSFER CONTROL PRJMARY CONTAINMENT ISOLATE REACTOR BUILDING CONTAINMENT SPRAY DECAY HEAT JSOLATION VALVES ISOLATE COOLING RODS PRIMARY HEATING AND VENTILATION REACTOR TO SERVICE CONTAINMENT SYSTEM BUILDING M WATER SI F SI F SI F ISOLATE MAIN PRESSURE RELIEF STEAM LINES CRD RHR TRANSFER SYSTEM CONTROL ROOM HOUSING SUPPORT SUPPRESSION POOL DECAY HEAT HABITABILITY (PASSIVE) COOLING TO SERVICE SI F M WATER SI F SI F PRlMARY CONTAINMENT (PASSIVE) SUPPRESSION POOL (PASSIVE)
REACTOR BUILDJNG PREVENT CONTAINMENT SHIELDING (PASSIVE) co~f&\o:oo s COOLING S SI F PRESSURE RELIEF S ESTABLISH ELEVATED RELEASE AND MAINTAIN POINT (PASSIVE) CONTROL ROOM EOP HJGH DRYWELL PRIMARY s PRESSURE AND CONTAINMENT ENV~~~~5rTAl S RADIATION ESTABLISH ci~~irJ:~T S OPERATOR ACTION BASED ON LOCA WJTH M FUEL DAMAGE MAINTAIN sutb~Es~~oN 5 NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR PIPE BREAKS INSIDE PRIMARY CONTAINMENT SHEET 1 FIGURE G-5-37 CADD FILE: COOl 2787 02/05/10
SHEET 2 OF 2 E',LEt jLJj (CON'T)
SMAU. BREAK LARGE BREAK INCIDENT INITIATE ECCS AT DETECTION RESPECTIVE TRIP SETTING lNTtRMEDCATE CIRCUITRY S BREAK
--r- JNCJOENT !NJTIATE ECCS AT DETECT JON RESPECTIVE TRJP SETTT CIRCUITRY S S\ F RECIR SUCTION ARK
+ 2 LPC!
~
1 CORE SPRAY CORE SPRAY RESTORE LPCI OTHER BREAKS s !Nfl!.ATE ECCS AT AND 1 CORE SPRAY + 1 LPCJ RESPECTIVE TRfP sEmNG ADS MA!NTA[N HPCI OR S\ F WATER S\ F 2 LPC! OR 2 CQ_RE _$PRAY LEVEL RESTORE AND MAINTAIN WATER LEVEL N S\ F SI F LPG! CORE SPRAY s
EOP REACTOR WATER LEVEL 1 CORE SPRAY CORE SPRAY PLUS s 2 LPCJ JNJT[ATE ECCS AT RESPECTrvE TRIP SETTING 1 PUMP CORE SPRAY lPCI REQUIRED M S S\ F si, 1 CORE SPRAY
._ PLUS CORE SPRAY LPCI s
I s( 2LPCI SjF EOP HEAT CAPACITY S\ F TEMPERATURE UM!T DIAGRAM FORMAT.
NOTE: REFER TO FIG. G-4-2 FOR Nebra ska Publi c Powe r Distri ct COOPER NUCLEAR STATION (USAR)
UPDATED SAFETY ANALYSIS REPORT PROTECTION SEQUENCES FOR PIPE BREAKS INSIDE PRIMARY CONTAINMENT SHEET 2 FIGURE G-5-3 8 8/3/0 0
.!:l1lfU2 F'UEL HANDLING ACCJDENT ALL STATES TRI.I T 3,9, 1 SERVICE WATER EFF'LUENT RADIATION TS J.7.6 TS 3.9.6 UONITOR MONITOR ALARM REACTOR BUILDING ISOLATION WATER LEVEL WATER LEVEL VENTILATION RADIATION RADIATION EOP 5.3,5 MONITORING SYSTEM MONITOR TRIP SI F MAINTAIN DIF'F'ERENTIAL PRESSURE ACCROSS RADIOACTIVE RADIOACTIVE RHR Hx SW ABOVE I.AATERlAL MAT(RJAL CONTROL ROOU RELEASE CONTROL RELEASE CONTROL VENTILATION CONTROL ROOM RHR PRESSURE HABITABILITY SYSTEM RIVER WATER ENVIROMENTAL CONTROL REACTOR BUILDING SiHJELOING (PASSIVE)
ENVbi~~6~TAl. s CONTROL ROOM NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALY51S REPORT (USAR)
PROTECTION SEQUENCES FOR FUEL HANDLING ACCIDENT FIGURE G-5-39 03/09/07 CADO FlLE; C0012789
SHEET 1 OF 2 Mfil_i;J PIPE BREAKS PLANNED OUTSIDE PRIMARY OPERATION CONTAINMENT STATES C,D SEE SHEET 2 Of 2 OTHER
~TION SCRAM SIGNAL ON LOW WATER LEVEL, MAIN STEAM LINE EOP EOP ISOLATION VALVE REACTOR SECONDARY POSmON SWITCHES, EOP WATER CONTAINMENT TURBINE CONTROL REACTOR LEVEL CONTROL VALVE FAST WATER CLOSURE, LEVEL TlJRBlNE STOP VALVE POSITION SWITCHES, OR RPS M-G SET I
~ I RPS COASTDOWN (FAIL-SAFE) ADS M S M RES:ORE AND M RESTR[CT LOSS OF INSERT CONTROL ROOS WA~rrtme:L REACTOR S I
COOL.INT ONE ONE PUMP PUMP CORE SPRAY LPC! CORE SPRAY LPC!
M s M s M s M S PRESSURE S F RELIEF EOP HEAT CAPACITY TEMPERATURE LlMJT ADS ADS M s M SI F MA!NTAfN J
DEPRESSUR!ZATION LPCI CORE SPRAY M M s EOP SI F SECONDARY CONTAINMENT CONIBOL ISOLATE ON lNJT!ATE L(JN WATER L£VEL, lSOLATION HIGH FLOW, OR HIGH VAf-VE EOP
/.REA TEMPERATURE CLOSURE SUPPRESSION POOL TEMPERATURE ISOLATE MAIN NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
STEAM LINES TRANSFER DECAY HEAT RHR SUPPRESSION POOL Nebraska Public Power District TO SERVICE WATER M COOLING COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
M ISOLATE SYSTEM S!F NS REQUIRED s
PROTECTION SEQUENCES FOR CONTAINMENT COOLING S EXTENDED CORE PIPE BREAKS OUTSIDE PRIMARY CONTAINMENT COOLING PR!WRY CONTA!NMEITT AN°v£~TOR S SHEET 1 ISOLATION FIGURE G-5-4O 04/08/02 CAOO F"ILE: C0012790
SHEET 2 OF 2 EVENT 43 (CONTINUED)
REACTOR BUJLOINC JSOL.ATJON AND CONTROL SYSTEM SI F REACTOR BUILDING HEATING ANO VENTILATION SYSTEM SI F ELEVAITO RELEASE POINT (PASSI\'£}
s ESTABLISH ctmt"~t~r s NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR PIPE BREAKS OUTSIDE PRIMARY CONTAINMENT SHEET 2 FIGURE G-5-41 8/3/00
- aoo FR£: coo,2191
=
RECIRCULATION PUMP SEIZURE STATES C.0 START ON LOW PLANNED LOW MAJN REACTOR WATER SCRAM ON STEAM LINE LfVEL (LEVEL 2)
OPERATION TURB[NE TRIP PRESSURE OR LOW WATER LEVEL ISOLATE MAIN STEAM INSERT LINES RC!C HPCI ADS CONTROL ROOS REACTOR VESSEL JSOLATJON CORE SPRAY I.PC!
s SI f PRESSURE RELIEF S
~ -:-i EXTENDED CORE OOLING SEQUENCE l:
BOUNDED BY LOSS OF UTDOWN COOllNj (EVENT 31)
NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR RECIRCULATION PUMP SEIZURE FIGURE G-5-42 8/3/00 CAOO fllf: C0012792
~
FUEL LOADING ERROR AU. STATES PLANNED OPERATION NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFElY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR FUEL LOADING ERROR FIGURE G-5-43 8/3/00
- ADO fll£: C0012793
.E'lE£il.JiJJ SHUIDOWN FROM OUTSIDE CONTROL ROOM All STATES STATES 8,0 STATES C,0 PROCEDURAL REQUIREMENT I I 1--
PROCEDURAL I
INCIDENT START HPC[ PRESSURE REUEF ( p ) REOU!REMENT SCRAM BY DE-ENERGJZJNG DETECTION SYSTEM ON SYSTEM CIRCUITRY LOW REACTOR M I SYSTEM WINUALLY WATER LEVEL T
INSERT CONTROL RESTORE ANO f...lAINTA!N ISUPPRESSION POOL (PASSIVE)
I I RV AND PC ICS ROOS WATER LEVEL EOP SUPPRESSJON ISOLATE PRESSURE MSIV3 MAIN STEAM POOL TEMPERATURE REUEF LINES I """ t--
0 SHUT DOWN SUPPRESSJON POOL rnANSFER DECAY HEAT REACTOR COOLING TO SERVICE WATER FROM OUTSIDE M CONTROL ROOM M
M NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR SHUTDOWN FROM OUTSIDE THE CONTROL ROOM FIGURE G-5-44 '
8/3/00
- ADO FILE: C0012796
E'IElil...fl.l SHUTDOWN WITHOUT CONTROL RODS STATES B,D EDP SHUTDOWN REOUJREO ON POWER>2 l/2 PERCENT INSERT SORON SOLUTION INTO REACTOR VESSEL SHUT DOWN REACTOR WITHOUT CONTROL RODS NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR SHUTDOWN WITHOUT CONTROL RODS, FIGURE G-5-45 8/3/00
~OD f!LE: C0012797
.EY£ljL£2 ANTICIPATED TRANSIENTS WITHOUT SCRAM STATE D PLANNED PLANNED PlANNED PLANNED OPERATION OPERATION OPERATION OPERATION HJGH REACTOR EOP START ON SUPPRESSION LOW REACTOR PRESSURE OR POOL WATER LEVEL LOW REACTOR TEMPERATURE (L£VEL 2)
WATER LEVEL (L£VEL 2)
TRANSFER ENERGY TO SERVICE WATER RESTORE AND PLANNED MArNTAIN OPERATION WATER L£VEL SUPPRESSION POOL COOUNG HIGH REACTOR PRESSURE OR LOW REACTOR WATER LEVEL (L£VEL 2)
PRESSURE REUEF EOP SUPPRESSION POOL TEMPERATURE I COOLING SEQUENCE I BOUNDED BY LOSS OF I SHUTDOWN COOLING I L .-'.:'~3'.!._ J REACTOR SHUTDOWN NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR ANTICIPATED TRANSIENTS WITHOUT SCRAt,vf FIGURE G-5-46 . '
8/3/00 CA00 FILE: C0014119
=STATION BLACKOUT STATE 0 CLOSE ON LOW START ON LOW SCRAM SIGNAL CONDENSER VACUUM RPS OR RPS M-G SET REACTOR WATER
- 1. TURBINE CONTROL LEVEL (L£VEL 2)
COASTOOWN OR VALVE FAST CLOSURE TR[P (TURBINE Ov£.RSPEEO DUE TO GENERATOR LO/>ll REJECTION)
- 2. TURBINE TRJP STOP VALVE POSfTJON SWITCH (DUE TO INSERT ISOLATE RESTORE HIGH REACTOR WATER l.EVEL CONTROL MAIN STEAM WATER LEVEL CAUSED BY RECIRC. PUMP RODS LINES
- COASTOOWN).
- 3. MSN CLOSURE (DUE TO LOW CONDENSER VACUUM)
PRESSURE REACTOR MAINTAIN REUEf VESSEL WATER LEVEL ISOLATION NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR ST ATION BLACKOU_T 1.,
FIGURE G-5-47 8/3/00 CAOO f!L.E: C0029890