ML21130A097
Text
INDUSTRY CODES AND STANDARDS UNACCEPTABLE RESULTS NUCLEAR SAFETY DESIGN CRITERIA I
PLANT AND SYSTEMS DESIGN AND CONFIGURATION BWR OPERATING PLANNED STATES OPERATIONS EVENT SELECTION PROCESS TRANSIENTS ACCIDENTS I
SPECIAL EVENTS PLANT PROTECTION SEQUENCE, FUNCTIONS AUXILIARY SYSTEM AND COMMONALITY DIAGRAMS IDENTIFICATION OF SYSTEMS, LIMITS AND RESTRICTIONS
+
EVENT STATION ACCEPTANCE SAFETY LIMITS ANALYSIS SYSTEM LEVEL SYSTEM CONDITIONS SAFETY REQUIREMENTS TO PERFORM ESTABLISHED PLANT FUNCTIONS
+
INPUT TO OTHER SYSTEMS SAFETY ASSESSMENTS CLASSIFICATIONS "A/')n c-r1 c:-. rrif'\\14.1?1 REGULATIONS NUCLEAR SAFETY OPERATIONAL CRITERIA I
RULES FOR EVENT ANALYSIS AVAILABILITY CONSIDERATIONS SURVEILLANCE FREQUENCY AND LIMITING CONDITIONS PROPOSED TECHNICAL SPECIFICATIONS Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT {USAR)
BLOCK DIAGRAM FOR NUCLEAR SAF"ETY OPERATIONAL ANALYSIS rlGURE G-2-2 7/22/96
CADD FILE: C0014122 STATE/ F '
---s-_/
EVENTS~ G,H 1 SYSTEM APPLICABLE OPERATING STATE EVENT NUMBERS IN WHICH THIS PROTECTION SEQUENCE IS APPL! CABLE SYSTEM K
SYSTEM M
r J.
1 INDICATES A LIMITATION IS I -
NECESSARY TO OBSERVE THE----.... {C)
I s
OPERATING ENVELOPE FOR SYSTEM N
PLANT FUNCTION 8
PLANNED OPERATIONS REFER TO SECTION G-3.4.5 FOR LIMITATION TYPES AND DESCRIPTION PLANT FUNCTION 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
"*l"'lr-, ["'!tr",
/"l"'I/H,41")'t INDICATES PATH IS
\\
ONLY REQUIRED IN THE SPECIFIED STATE EVENT 1XY'
,_1 EVENT TITLE STATES I~!)
NUMBER OF EVENT,
STATES IN WHICH THIS PROTECTION SEQUENCE IS APPLICABLE STATE W ONLY SYSTEM p
PLANT FUNCTION D
SYSTEM Q
DIFFERENT PLANT CONDITION DIFFERENT PLANT CONDITION SYSTEM R
1 INDICATES THAT SYSTEMS j
Q AND R SHARE AS A 1~ ~1....____ PAIR THE REQUIREMENT TO MEET THE SINGLE SYSTEM s
FAILURE CRITERION SYSTEM S MUST (sJF,....,.
ITSELF MEET THE SINGLE j
FAILURE CRITERION SYSTEM T
PLANT FUNCTION E
MANUAL OPERATOR ACTION REQUIRED FOR SYSTEM V SYSTEM u
INDICATES THE SYSTEM I
(s-J....,.._- IS SAFETY RELATED s IF (ESSENTIAL) AND THE PLANT FUNCTION IS A SAFETY FUNCTION INDICATES THAT ONE OR
....,.._- MORE OF THE KEY PROCESS PARAMATERS MUST BE LIMITED TO SATISFY THE NUCLEAR SAFETY OPERATIONAL CRITERIA (PARAMATER LIMITS)
__ __. ___ LM-1 I
s PLANT FUNCTION F
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR}
FORMAT FOR PROTECTION SEQUENCE DIAGRAMS EVENTS FIGURE G-4-2 7/22/96
"'Af')I') rflr'*,:r,r,141?.d.
DIAGRAM INDICATES THAT AUXILIARY SYSTEMS A,B AND C ARE REQUIRED FOR THE OPERATION OF FRONT -
LINE SYSTEM X.
IF SYSTEM X IS SAFETY RELATED (ESSENTIAL), THEN AUXILIARY SYSTEMS A,B, AND C MUST ALSO BE SAFETY RELATED (ESSENTIAL).
FRONT LINE SYSTEM X AUXILIARY SYSTEM A
,s I F1
'.,'--._ INDICATES SYSTEM A MUST MEET THE SINGLE FAILURE CRITERIA AUXILIARY SYSTEM B AUXILIARY SYSTEM C Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
FORMAT FOR AUXILIARY SYSTEM DIAGRAMS rtGURE G--4-J 7/22/96
___s:[,fil_
_mfil_
A X, y B
X, y C
X, Y, Z D
X, Y, Z SlSl£M I I
--~l"lt'I rr,r.,...,v,~,,..,c I
ALJXL!ARY SYSTEM A
___s:[,fil_
_.EYEfil_
A U, V, W B
V, W C
U, V, W, X D
U, V, W, X SYSJ~
State and Events for which the auxiliary/required system relationship applies SYSTEM K
___s:[,fil_
_fYEJi[_
A B
C Y, W D
Y, W, Z
(
S>ST£M L
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT {USAR}
FORMAT FOR COMMONALITY DIAGRAMS FIGURE G-4-4 7/22/96
REACTOR BUILDING I JCS s
DC SYSTEM PAN~
PRIMARY CONTAINMENT ISOLATION VALVES UNIT AUXJLIARY AC POWER S'fSTEM s
DC SYSTEM PANELS STANDBY GAS TREATMENT SYSTEM CONTROL POWER VALVE POWER VALVE CONTROL POWER UNJT AUXILIARY I CONTROL AC POWER SYSTEM -
POWER s
UNIT AUXJUARY AC POWER SYSTEM s
PANELS 6.00 fll£: C0012750 DELIVER POWER TO BLOWERS AND HEATERS I
RHRS I
SUPPRESS[ON POOL COOLING DC POWER SYSTEM
'250/125V s
UNIT AUX[LlARY AC POWER SYSTEM RHR SERVICE WATER REACTOR EQUIPMENT COOLING SUPPRESSION POOL STORAGE (PASSIVE) s s
PUMP BREAKER CONTROL AND CONTROL LOGIC VAf.VE AND PUMP POWER COOLING WATER TO RHR HEAT EXCHANGERS COOL AREA OF RHR EQU[PMENT REQ'O WHEN OPERATING 2 RHR PUMPS [N A SINGLE QUAD WATER SOURCE I REACTOR BUILDING I HEATING AND VENTILATION SYSTEM DC POWER SYSTEM 250/125V PANELS DC SYSTEM HPCI PANELS JDC DC POWER s
s
- ~
SYSTEM 250/125V s
PANELS ISOLATION VALVE CONTROLS CONTROL LOGIC, VN...VE AND PUMP POWER COOL AREA OF HPCI EQUIPMENT SECONDARY WATER SUPPLY FOR HPCI PUMP WATER SUPPLY FOR HPCJ PUMP NORMAL LINE-UP POWER TO CONTROL CIRCUITRY I
CONTROL ROOM I I
REACTOR BUILDING fSOLATION VENTILATION VENTILATION RAOlATION SYSTEM MONITORING SYSTEM UNIT AUXILIARY I AtPOWER...
1 SYSTE}J_ 1---a---
CONTROL AC POWER SYSTEM POWER TO POWER s
AIR CONOITfONING EQUfPMENT DC POWER ISOLATION I
PANELS SYSTEM 250/125V DAMPER s
CONTROLS COOLING WATER TO AIR CONDITIONING EQUIPMENT PRESSURE RELJEF SYSTEM s
PANELS I___
CORE SPRAY SYSTEM
~
I f--
DECAY RELJEF VALVES HEAT S
TRANSFER UNJT AUXJL!ARY r---
VALVE ANO AC POWER SYS1EM PUMP POWER s
DC SYSTEM PANELS BREAKER CONTROL CONTROL LOGIC COOL AREA OF CORE SPRAY EQUIPMENT WATER SUPPLY TO PUMP LC'JN-LOW SET CfRCUITRY PANELS
- -NOT APPLICABLE FOR STATION BLACKOUT SET PO[NT CHANGES STEAM CONOENSAnoN Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
AUXILIARY SYSTEMS FOR FRONT-LINE SYSTEMS FIGURE G-5-1 8/3/00
CADO FILE: COO 12751 U'CI DC "{5o'f, 25v 1--
SYSTEM REACTOR EQUIPMENT COOLING s
VALVE ANO PUMP POWER BREAKER CONTROL CONTROL LOGIC, VIJ..V'i. POWER RHR PUMP COOLING COOL AREA OF RHR EQUIPMENT SI REQ'O WHEN OPERATING 2 RHR PUMPS IN A SINGLE QUAD WATER SUPPLY TO LPC1 PUMP PANELS EQUIPMENT f--
COOLJNG CONDENS/\\TE STORAGE TANK P~OOL STORAGE 1-----
(PASSIVE)
PANELS PRIMARY CONTAINMENT (PASSIVE)
PANELS CONTROL LOGIC, VALVE COOL AREA AROUND RClC TURBJNE PUMP WATER SUPPLY F'OR RCIC PUMP Al T SOURCE OF MAKE-UP WATER PRESSURE SUPRESSION DIFFERENTIAL PRESSURE CONTROL DC SYSTEM ADS PANELS SYSTEMS WITH NO REQUIRED AUXILIARY SYSTEMS FUEL ASSEMBLIES CONTROL ROOS CONTROL ROD DRIVES NEUTRON MONITORING ROD BLOCK MONITORING MAIN STEAM LINE RAO MONITORING RPS MSIV'S FLOW RESTRICTORS SAFETY VALVES RADWASTE BUILDING REACTOR BUILDING CONTROL ROD VELOCITY-LIMITER CONTROL ROD HOUSING DC POWER SYSTEM 250/ 125V SUPRESSION POOL STORAGE PRIMARY CONTAINMENT RELIEF SPENT FUEL POOL CRD HOUSING SUPPORTS CONTROL ROOM PANELS LOCAL PANELS AND RACKS EMERGENCY COND. STORAGE TANK STEAM CONOENSATJON RELIEF VALVE CONTROL SENSORS LOGIC AND SOLENOJDS PASSIVE X
X X
X X
X X
X X
X X
FAIL-SAFE X
X X
X X
X X
SELF CON-SAFETY TAINED RELATED X
X X
X X
X X
X X
X X
X X
X X
X X
X X
X X
X X
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT {USAR)
- -NOT APPLICABLE FOR STATION BLACKOUT AUXILIARY SYSTEMS FOR FRONT-LINE SYSTEMS FIGURE G-5-2 5/5/06
CAO* FIL£: C0012752 RHRS SHUTDOWN COOLING MOOE DC SYSTEM PANELS VALVE POWER, BREAKER CONTROL RHR PUMP COOUNG COOL AREA AROUND RHRS EQUJPMENT REQ'D WHEN OPERATING 2 RHR PUMPS IN A SINGLE QUAD COOLING WATER TO RHR HEAT EXCHANGERS VN...YE ANO PUMP POWER STANDBY LIQUID CONTROL SYSTEM PANELS ATWS-RPT DC POWER SYSTEM 250/1251/
PANELS PUMP POWER, TANK HEATERS, VALVE FIRING CIRCUITS LOGIC POWER SUPPLY 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
OFF sm: AC POWER SYSTEM DC SYSTEM PANELS SERVICE WATER SYSTEM s
UNrT AUX[UARY AC POWER SYSTEM s
DC SYSTEM PANELS CAD0 Flt£: C0012753 BREAKER CONTROL VALVE ANO PUMP POWER RHRS SERVICE WATER SYSTEM DC SYSTEM PANELS REACTOR EOU[PMENT COOUNG SERVICE WATER SYSTEM s
UNIT AUXILIARY AC POWER SYSTEM s
PANELS VALVE AND PUMP POWER WATER SUPPLY TO RHR SERVICE WATER SYSTEM COOLING WATER TO HEAT EXCHANGERS, BACKUP COOLING WATER SUPPLY PUMP POWER, VN...VE POWER, FAN POWER ELEVATED RELEASE POINT PANELS STANDBY AC POWER SYSTEM s
PUMP POWER, Z SUMP, LVL SWlTCH UNIT AUXILIARY AC POWER SYSTEM s
POWER SUPPLY DC POWER SYSTEM 250/125V s
PANELS OFF SITE AC POWER SYSTEM BREAKER CONTROL STANDBY AC POWER SYSTEM DC SYSTEM PANELS s
POWER SUPPLY BREAKER CONTROL COOL DIESEL LOW-LOW SET CIRCUITRY DC SYSTEM LOW PRESSURE JNTERLOCKS DC POWER SYSTEM 250/125V s
PANELS PANELS s
CONTROL POWER PANELS LOCAL PANELS AND RACKS CONTROL ROOM PANELS Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
AUXILIARY SYSTEMS FOR OTHER AUXILIARY SYSTE;MS FIGURE G-5-4 8/3/00
___s:((IIL A
8 C
D
...fil6I.E_
....Nfil_
A B
C D
NONE NONE 41 40,41 I
PRIMARY CONTAINMENT I (PASSIVE)
....Nfil_
31,60 31,60 13, 15, 18,22,23,24,25,28,28c,31, 32,41,43,60 11, 12, 13, 15, 18,22,23,24,25,26, 28,28c,31,32,40,41,43,60,62 RHR SUPPRESSION POOL COOLING
__.filill_
A B
C D
___s:((IIL
....Nfil_
A NONE 8
NONE I
SUPPRESSION POOL l
STORAGE l
.....lliIL A
8
....Nfil_
~
__EYflli_
31 A
NONE 31 8
NONE C
13, 15, 18,22,23,24,25,28,28c,31, C
13, 15, 18,22,23,24,25,28,280,31, C
13, 15, 18,22,23,24,25,28,28c,31, 32,41,43,60 D
11, 12, 13, 15, 18,22,23,24,25,26, 28,28c,31,32,40,41,43,60,62 l
HPCI J
....Nfil_
NONE NONE 13,15,18,22,23,24.25,28,28c,31, 32,41,43,60 dd.~ia~3i ;;i~;fo;1;~ils4a;lls\\
I PRESSURE RELIEF -1 SYSTEM I
....fileJL A
B C
D 32,41,43 D
11, 12, 13, 15, 18,22,23,24,25, 26,28.28c,31,32,40,41,43,62 I
....Nfil_
NONE NONE 13, 15, 18,22,23,24,25,28,280, 31,32 11, 12, 13, 15, 18,22,23,24, 25,26,28,2&,31,32,40,62 I
RCIC I 32,41,43,60 D
11, 12, 13, 15, 18,22,23,24, 25,26,28,28c,31,32,40, 41,43,60,62 I
ADS I
...fil6I.E_
_E'illiJ_
A 31 B
31 C
13, 15, 18,22,23,24,25,28,28c,31, 32,41,43,60 D
2~.1~}'a 1
c~~1~:i 1lla~l1\\
2 3~ici'.ti2 l
LPCI J Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
COMMONALITY DIAGRAMS FIGURE G-5-5 1/31/01
___fil8lL
~
___filML A
31,60 A
B 31,60 B
C 13, 15, 18,22,23,24,25,28,280,31, C
32,41,43,60 D
11, 12, 13, 15, 18,22,23,24,25,26, 28,280,31,32,40,41,43,60,62 D
RHR SUPPRESSION POOL COOLING
...filML
~
A 31 B
31 C
13, 15, 18,22,23,24,25,28,280,31, 32,41,43,60 D
11,.* 2, 13, 15, 18,22,23,24,25, 26,28,280,31,32,40,41,43,60,62 I
LPCJ I
~ADO FIL£: C0012756 REACTOR EQUIPMENT COOLING I
~
NONE NONE 13, 15, 18,22,23,24,25,28,280,31, 32,41,43,60 11, 12, 13, 15, 18,22,23,24,25,26, 28,280,31,32,40,41, 43,60,62 I
HPCI I
...filML A
B C
D
___fil8lL
--1:'illlL_
A 31 B
31 C
13, 15, 18,22,23,24,25,28,280,31, 32,41,43 D
11, 12, 13, 15, 18,22,23,24,25, 26.28,280,31,32,40,41,43,62 I
~
NONE NONE 13, 15, 18,22,23,24,25,28,280 I
31,32 11, 12, 13, 15, 18.22,23,24, 25,26,28,280,31,32,40,62 RCIC I Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
COMMONALITY DIAGRAMS FIGURE G-5-6 8/3/00
VACUUM RELIEF I
---2bIL
_fY£lli_
A NONE 8
NONE C
41 D
41 I
PRIMARY CONTAINMENT I (PASSIVE)
CADD FILE: C0012757 LOW-LOW SET CIRCUITRY RELIEF VALAVES
---2bIL A
B C
D
_fY£lli_
NONE NONE 13, 15, 18,22,23,24,25,28,280,31, 32,41,43,60 11, 12, 13, 15, 18,22,23,24,25,26, 28,280,31,32,40,41,43,60,62,63 PRESSURE RELIEF SYSTEM STANDBY AC POWER SYSTEM OFF SITE AC POWER
---2bIL
_fY£lli_
A B
C D
31,42,60 31,42,60,61 13, 15, 18,22,23,24,25,28,280,31, 32,41,42,43,60 11, 12, 13, 15, 18,22,23,24,25,26,28, 28a,31,32,40,41,42,43,60,61,62 UNIT AUXILIARY AC POWER RHR I
_S1fil_
_fY£lli_
A 31,60 8
31,60 C
13, 15, 18,22,23,24,25,28,28a,31, 32,41,43,60 D
11, 12, 13, 15, 18,22,23,24,25, 26,28,28a,31,32,40,41,43,60,62 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
__filfilE_
____DilliL_
A B
C D
31,60 31,60 13, 15, 18,22,23,24,25,28,280,31, 32.41,43,60 11, 12, 13, 15, 18,22,23,24,25,26, 28,280,31,32,40,41,43,60,62 REACTOR EOUJPMENT COOLING
---5I6IE_
A
~
42 B
C D
42 42 42 I
I REAc10RBUILD1NG -,s*LATION-1 VENTJLATION RADIATION MONITORING SYSTEM
__filfilE_
____DilliL_
A 31 B
31 C
13, 15, 18,22,23,24,25,28,280,31, 32,41,43 0
11, 12, 13, 15, 18,22,23,24.25, 26.28.280,31,32,40.41,43,62 j
CORE SPRAY CADD FILE: COO 12758
---5I6IE_
A B
C D
STATE
____E\\/lfil_
A B
C D
NONE NONE 41,43 40,41,43 PRIMARY CONTAINMENT ISOLATION VALVES
_..£YlliL_
42 I
42 41,42 41.42 CONTROL ROOM VENTILATlON UNIT AUXILIARY AC POWER I
I
__filfilE_
____DilliL_
A 31,60 B
31,60 C
13, 15, 18,22,23,24,25,28,280,31, D
32,41,43,60 11, 12, 13, 15, 18,22,23,24,25,26, 28,280,31,32,40,41,43,60,62 STATE A
B C
D I
I RHRSW I
____EliEill_
NONE I
61 41 41,61,62 I
STANDBY I UOUJD CONTROL SYSTEM
---5I6IE_
A B
C D
J
_fil8IE._
____DilliL_
A 31,42,60 B
31,42,60,61 C
13, 15, 18,22,23,24,25,28,280,31, 32.41,42,43,60 D
11, 12, 13,15, 18,22,23,24,25,26 28,280,31,32,40,41,42,43,60,61,62' J
I SW I STATE
____DilliL_
A 31,60 B
31,60 l
STATE
____E\\/lfil_
A 31 B
31 C
13, 15, 18,22,23,24,25,28,280,31, 0
32.41,43,60 11, 12, 13, 15, 18,22,23,24,25 26,28,280,31,32,40,41,43,60,62 I
I LPCI I C
13, 15, 18,22,23,24.25.28.280,31, 32.41.43,60 D
11, 12, 13, 15, 18,22.23.24,25,26, 28,280,31,32,40,41,43,60,62 l
t RHR j PRESSION. POOL COOLING
_f;'filIT_
NONE I
NONE 41 40,41 PRIMARY CONTAINMENTJ (PASSIVE)
---5I6IE_
A B
C D
STANDBY GAS I TREATMENT SYSTEM
~
42 42 41,42.43 41,42,43 I
I REACTOR BU]LDING I HEATJNG AND VENTILATION SYSTEM Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
COMMONALITY DIAGRAMS FIGURE G-5-8 02/05/10
l
~
~
A NONE B
NONE C
13,15, 18,22,23,24,25,28,280,31, 32,41,43,60 D
25.dJ:dl:dl,{~; '.flllr;:t;;,62 l
l ADS J
_SIAIL JYlliL A.
NONE B
NONE C
NONE D
62 I I I ATWS-RPT CAJJO FILE: C0012759 I
__sJfJ£_
~
A NONE B
NONE C
13, 15, 18,22,23,24,25,28,280, D
31,32 11~J~js~~s1~tl:it~t/ilt*
~
A B
C D
I I RCIC I
~
31 31 1 3, 15, 18,21a;:t:i:ga28,28o,31.
2s1.1ig~c~s1~:i~~:?d::?N3:f<r.s2 I
I LPCI I
_filAIL
~
A NONE 8
NONE C
13, 15, 18,22,23,24,25,28,280, 31,32,41,43,60 D
dJ:dJ:i:l; :52:fo~f ;:Nto~~2~t:i L<JII-L<J/1 SET CIRCUITRY I
DC POWER SYSTEM 250/125V I
I I
__sJfJ£_
__.EYEfil_
-5IAIL
....EYillL..
__sJfJ£_
A
_EYEtll_
42 A
31,42,60 B
31,42,60,61 C
13, 15, 18,22,23,24,25,28,280,31, 32,41,42,43,60 D
11, 12, 13, 15, 18,22,23,24,25,26, 28,280,31,32,40,41,42,43,60,61,62
_SIAfL A
B C
D I
UNIT AUXILIARY I AC POWER
_.ElilliL_
31 31 13, 15, 18,22,23,24,25,28,280,31, 32,41,43 11,12, 13, 15, 18,22,23,24,25, 26,28,280,31,32,40,41,43,62 l
[ CORE SPRAY I
_SIAIL
_.ElilliL_
A 8
C D
NONE NONE 41,43 40,41,43 PRIMARY CONTAINMENT
~
A B
ISOtATfON VALVES
__.f:iEfil_
31 31 C
13, 15, 18,22,23,24,25,28,2Ba,31, 32,41,43,60 D
dJJi:i:i, :52:~o:l;:ir.to:~2:i:i I
I IOC I A
NONE B
NONE B
C 13, 15, 18,22,23,24,25,28,280,31, 32,41,43,60 C
D 2
1;,2\\fa.
1l1 ;Jt\\~:l6~:6~:s5ls6:i D
I l
HPCf J
_£AIL
~
A 31,60 8
31,60 I
42 41,42 41,42 I
CONTROL ROOM I VENTflATION
__sJfJ£_
A
~
60 8
C D
60 15, 18,22,23,24,25,28,280,31, 32,41,43,60 dJ:dla:l, :Jll<?.Nti.~a:t:i l
I RV.ANDPC ISOLATION VALVES
_swE_
~
A 42 8
42 C
- 13. 15. 18,25iNi:l&i28,280,31, C
41,42,43 D
11,12, 13, 15, 18,22,23,24,25, D
41,42,43 26,28,280,31,32,40,41,43,60,62 RHR SUPPRESSION POOL COOLING REACTOR BUILDING HEATING AND VENTILATION SYSTEM Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT {USAR)
COMMONALITY DIAGRAMS FIGURE G-5-9 04/08/02
I SERVfCE WATER I
_filA[E.._
~
A 31,60 B
31,60 C
13, 15, 18,22,23,24,25,28,280,31, 32,41,43,60 D
11, 12, 13, 15, 18,22,23,24,25,26, 28,280,31,32,40,41,43,60,62 I
REC I
_filA[L
~
A 31,60 B
31,60 C
13, 15, 18,22,23,24,25,28,280,31, 32,41,43,60 D
11, 12, 13, 15, 18,22,23,24,25,26, 28,280,31,32,40,41,43,60,62 RHR SERVICE WATER SYSTEM CAO* FIL£: CO0l 2760 l
.....SIML
~
A B
C D
31,42,60 31,42,60,61 13, 15, 18,22,23,24,25,28,280,31, 32,41,42,43,60 11, 12, 13, 15, 18,22,23,24,25,26, 28,280,31,32,40,41,42,43,60,61,62 I
STANDBY AC I POWER
_filML
~
A 42 B
42 C
41,42 D
41,42 I
CONTROL ROOM I VENTILATION Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
COMMONALITY DIAGRAMS FIGURE G-5-10 04/08/02
ERP RADIATION MONJTORING SYSTEM PROCESS LIQUID RADIATION MONITORS REACTOR BUILDING VENTILATION EXHAUST RADIATION MONITORING SYSTEM L,R RAOWASTE/AUClMENTED RADWASTE BUILDING VENTILATION EXHAUST RADIATION MONITORING SYSTEM TURBINE BUJLDlNC VENTILATION EXHAUST RADIATION MONJTORlNG S'r'STEM RADIOACTIVE MATERIAL RELEASE CONTROL r.11.nn n, i;-. ~not?7if\\t 10 CFR 20 AND 10 CfR 50 UMITS 10 CFR 20 AND 10 CFR 50 UMITS 10 CFR 20 AND 10 CFR 50 LIMiTS 10 CFR 20 AND 10 CFR 50 LIMITS 10 CFR 20 AND 10 CfR 50 LIMITS 10 CFR 20 ANO to CfR 50 LIMITS 10 CFR 71 u~ns REACTOR VESSEL WATER LEVEL CONTROL MIN:MUM WATER L.EVEL EVENT 6 REACTOR VESSEL NUCLEAR SYSTEM TEMPERATURE CONTROL
~
PLANNED OPERATION STATE A RATE OF CHANGE TEMPERAT\\JRE LIMIT REACTOR COOL.ANT NUCLEAR SYSTEM WATER QUALlf'r' CONTROL COOLANT CHEMISTRY LIMITS CORE LOADING PATTERN (EVENT 1)
SRM MINIMUM COUNTS (EVENT 1)
REACTOR FUEL EVENT 1 R
REFUELING RESTRJCTroNS CRD REFUELING INTER-LOCKS CONTROL ROD POSITION PROCEDURAL LIMITATIONS (FUEL ASSEMBLY ORIENTATION)
LlM!T ON NUMBER OF DRIVES VALVED OUT Of SERVJCE SHUTDOWN MARGIN NEW FUEL STORAGE FACJLJTIES R
SPENT FUEL STORAGE FACILITIES L,R STORED FUEL SH[ELDJNG, COOLING ANO REACTNJTY CONTROL SEE FIGURE G-5-15 FUEL SPAC[NG WATER TEMP, WATER L£VEL, FUEL SPACING, FUEL HANDLING REACTOR BU!LO[NG CRANE (CASK HANDLING)
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFE1Y ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR PLANNED OPERATION IN STATE A FIGURE G-5-11 2/19/01
ERP RADIATION MONITORING SYSTEM PROCESS LIQUID RADIATION MONITORS REACTOR BUILDING VENTILATION EXHAUST RADIATION MONITORING SYSTEM L.R RADWASTE/AUGMENTEO RADWASTE BUILDING VENTILATION EXHAUST RADIATION MONITORING SYSTEM TVRB[NE BUILDING VENTILATION EXHAUST RADIATION MONITORING SYSTEM MPf VENTILATION EXHAUST RAOlATION MQNJTORING SYSTEM RADIOACTIVE MATERIAL REL£ASE CONTROL r.Ann rn,:-. r:nn1 ?7F.?
10 CFR 20 ANO 10 CfR 50 LIMITS 10 CFR 20 AND 10 CFR 50 LIMITS 10 CFR 20 ANO 10 CFR 50 WAITS 10 CfR 20 AND 10 CfR 50 LH,HTS 10 CFR 20 AND 10 CfR 50 LIMITS 10 CfR 20 ANO 10 CfR 50 LIMITS 10 CFR 71 UMJTS CORE POWER LEVEL CONTROL MINIMUM POWER (SRM)
MAXIMUM POWER MAXfMUM POWER L£VEL-LOW FLOW OR LOW PRESSURE REACTOR FUEL REACTOR VESSEL WATER L.£VEL CON7ROL EVENT 5 NUCLEAR SYSTEM TEMPERATURE CONTROL MINIMUM WATER L£VEL EVENTS 2,5 PLANNED OPERATION STATE 8 RATE Of CHANGE TEMPERATURE LIMIT REACfOR COOLANT NUCLEAR SYSTEM WATER QUALITY CONTROL COOLANT CHEMISTRY LIMITS NUMBER Of OPERABLE CONTROL RODS EVENT 2 ROD WORTH MJNIMJZER NEW FUEL STORAGE F AGILITIES R
SPENT FUEL STORAGE FACIUTIES
',_R STORED FUEL SHIELDING, COOLING AND REACT[VITY CONTROL ROD PATTERN WHEN POWER
<10~
SEE FIGURE G-5-15 FUEL SPACING WATER TEMP, MATER L£VEL, FUEL SPACING, FUEL HANDLING, REACTOR BUJLDING CRANE (CASK HANDLING)
Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR PLANNED OPERATION IN STATE B FIGURE G-5-12 2/19/01
~*
ERP RADIATION MONITORING SYSTEM PROCESS LIQUID RADIATION MONJTORS t,_R RADWASTE/AUGMENTEO RAOWASTE BU!LDJNG VENTilATION EXHAUST RADIATION MONITORfNG SYSTEM nJRBINE BUILDING VENTILATION EXHAUST RADIATION MONITORING SYSTEM MPF VENTILATION EXHAUST RADIATION MONITORING SYSTEM SOLID RADWASTE SYSTEM RADIOACTIVE MATERIAL RELEASE CONTROL f"'t.nn r11 ~- rnn1?7~~
10 CFR 20 AND 10 CFR 50 LIMITS
~O CFR 20 AND 10 CFR 50 LIMITS 10 CFR 20 AND 10 CFR 50 LIMtTS 10 CFR 71 LIMIT APPUEO TO SH[PPlNG CASK 10 CFR 20 AND 10 CFR 50 llMITS 10 CFR 20 ANO 10 CFR 50 UMJTS 10 CFR 20 AND 10 CFR 50 LIMITS 10 CFR 71 UMlTS REACTOR FUEL L
EV,NT 2 I
MINIMUM WATER LEVEL I
I REACTOR VESSEL REACTOR VESSEL PRESSURE CONTROL EVENT 6 L
I REACTOR VESSEL REACTOR FUEL L
,.....J_
NUCLEAR SYSTEM TEMPERATURE CONTROL
\\
MAXIMUM PRESSURE MtNIMUM PRESSURIZATION TEMPERATURE MAXIMUM PRESSURE LIMIT TEMPERATURE RATE Of" CHANGE MINIMUM TEMPERATURE WfTH HEAD ON MAXIMUM FEEDWATER TEMPERATURE EVENTS 2,6 PLANNED OPERATION STATE C REACTOR COOL.Afff NUCLEAR SYSTEM WATER QUALITY CONTROL REACTOR VESSEL NUCl..£AR SYSTEM LEAKAGE CONTROL COOLANT CHEMISTRY Ul\\4ITS RADJOACTIV[1Y LIMITS OVERSTRESS PROTECTION AND MAKE-UP CAPABfUTY LEAKAGE LIMIT CRD NEW FUEL STORAGE FACILITIES FUEL SP,CING SPENT FUEL STORAGE F"ACJLmES L,R STORED FUEL SHIELDING, COOLING AND REACTIVITY CONTROL WATER TEMPERATURE WATER LEVEL FUEL SPACING FUEL HANDLING REACTOR BUJLDfNG C=~J~K SEE fJCURE G-5-15 PRIMARY CONTAINMENT (PASSIVE)
PRIMARY CONTAINMENT ATMOSPHERfC PRESSURE AND TEMP. CONTROL NUMBER OF DRIVES OUT Of SERVICE SHUTDOWN MARGIN TEMPERA-TURE AND PRESSURE LIMITS WATER TEMPERA-TURE ANO VOLUME llMITS AVAJLABtLITY Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFElY ANALYSIS REPORT (USAR}
PROTECTION SEQUENCES FOR PLANNED OPERATION IN STATE C FIGURE G-5-13 2/19/01 LEVEL
EVENT$ 2 3 4 5 PLANNED OPERATION STATE D MINIMUM A<R EJECTOR Off-GAS~
I POWER (SRM)
MINIMUM RADIATION MONJTORING 10 CFR 20 ANO REACTOR FUEL WATER SYSTEM 10 CFR 50 I
REACTOR FUEL ~
%~~~M LE~~E I L,R LJMJTS I-- 10 CFR 20 AND ERP RADIATlON MONITORING SYSTEM 10 CFR 50 LIMITS PROCESS LIQUID
~
10 CFR 20 AND RADIATION MONITORS 1 0 CFR 50 L
LIMITS REACTOR BU[LOING VENTILATION EXHAUST 10 CFR 20 AND RADIATION MONITORING 10 CFR 50 SYSTEM LIMITS L,R RADWASTE/AUGMENTED ~
RADWASTE BUILDING VENTILATION EXHAUST 10 CFR 20 AND RADIATION MONITORING 10 CFR 50 SYSTEM LIMITS TURB{NE BUILDING
\\IENTTLATTON EXHAUST RADIATION MONITORING SYSTEM L
10 CFR 20 AND 10 CfR 50 w.ms 10 CFR 20 ANO 10 CfR 50 LIMITS I
I I
I L
(EVENT 4)
L CORE
)
(
POWER LEVEL CONTROL EVENTS 3,4,5 8fci \\Wr'iJT 42)
I <
I REACTOR FUEL L
CORE NEUTRON FLUX DISTRIBUTION CONTROL 10 CfR 71 LJMITS RECIRCULATION SYSTEM FLOW RUNOUT LJMJTS (EVENT 4)
RA.DIOACTNE MATERIAL RELEASE CONTROL CORE COOLANT FLOW RATE CONTROL MINIMUM FLOW RATE K1 (EVENT 4)
POWER/FLOW MAP REACTOR VESSEL PRESSURE CONTROL POWER PEAKING RHRS SHUTDOWN COOLING MOOE LEVEL I TEMPERAnJRE REACTOR VESSEL RATE OF L
I I
I MAXIMUM PRESSURE LIMIT L
(EVENTS 2,5)
MAXIMUM PRESSURE LIMIT CHANGE MINJIAUM TEMPERAnJRE WITH HEAD ON MAXIMUM REACTOR FUEL FEEDWAT'ER TEMPERATURE LOOP ANO VESSEL TEMPERATURE DIFFERENCE NUCLEAR SYSTEM TEMPERATURE CONTROL I
COOLANT I
CHEMJSTRY LIMITS RAOIO-ACTIVITY LJMITS I
NUCLEAR SYSTEM LEAKAGE CONTROL OVERSTRESS PROTECTION MAKE -
UP CAPABILITY LEAKAGE LIMITS I
I j n"'""~,_,..,~,..-AU.1l,,--.,..,. f I IPRESSUREP~giPRESSiONI NEW FUEL STORAGE FAC!LlTIES R
SPENT FUEL STORAGE fAC(LlTIES l,R STORAGE FUEL SHIELDJNG POOLING AND REACTIVITY CONTROL NUMBER DRfVES OUT OF SERVICE SCRAM TIMES ROD WORTH MINIMIZER TEMPERATURE AND PRESSURE LIMITS WATER TEMPERAl\\JRE AND VOLUME LIMIT FUEL SPACING WATER TEMPERATURE WATER l.£VEL FUEL SPAC(NG FUEL HANDLING REACTOR BUJLDJNG CRANE (CASK HANDLING)
ROD PATTERN WHEN POWER
<10" WHEN POWER
>.30" RIVER WATER ULTIMATE HEAT SJNK AVAILABILITY SEE FIGURE G-5-15 LEVEL.
TEMP Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR PLANNED OPERATION IN STATE D FIGURE G-5-14 2/19/01
(1)
RCPB:
- 1. RPV SEE FIGURES G-5-11, -12, -13 ANO -14 STATES A, B, C AND D REACTOR COOLANT PRESSURE EOUNDARY (PASSIVE) (1)
REACTOR VESSEL and PRIMARY CONTAINMENT ISOLATION and CONTROL SYSYTEM
- 6. RWCU Rv anc PC JCS
- 2. MAIN STEAM SYSTEM
- 7. CRD SYSTEM
- 3. RHR
- 8. SLCS
- 4. HPCI
- 9. FEED WATER SYSTEM
- 5. RCIC l\\00 FIL£; GCOOl 2765 REACTOR SYSTEM CORE GEOMETRY (PASSIVE) (2) s MA[NTAIN g~g~~ s STATES A AND C RCIC HPCI cs M
s IF cs SI F (2)
CORE GEOMETRY:
- 1. RPV
- 2. CORE SUPPORT STRUCTURES
- 3. CORE SHROUD
s IF Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR PLANNED OPERATION IN STATE A, B, C ~* D FIGURE G-5-15 8/J/00
mill_]J TURBJNE TRIP OR GENERATOR LOAD REJECTrON WITH BYPASS STATE 0
POWER <30%
POWER >30%
PLANNED OPERATION REESTABLISH POWER OPERATION OR ACH[EVE SHUIDOWN 100 FILE: C0012766
,_ _ _.__--, ___ SCRAM SIGNAL
- 1. FOR TURBlNE TRIP ON TURBINE STOP Vl>LVE CLOSURE
- 2. FOR GENERATOR TRIP ON TURBINE CONTROL VALVE FAST CLOSURE INSERT CONTROL ROOS PRESSURE RELIEF S
REACTOR VESSEL ISOLATION INITIATE MS[V CLOSURE ON LOW TURBINE INLET PRESSURE OR LOW REACTOR WATER LEVEL (LEVEL 1)
ISOLATE MAIN STEAM UNES RCIC HPCI START ON LOW REACTOR WATER LEVEL (LEVEL 2)
ADS PLANNED OPERATfON FEEDWATER MA[NTA!NS LEVEL CORE SPRAY s
I.PC!
BELOW ABOUT 25 PERCENT OF RATED POWER, THE BYPASS SYSTEM WILL TRANSFER 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 ACTION CAN REDUCE POWER TO WITHIN THE BYPASS CAPACITY.
SI F
~ ~ :-i EXTENDED CORE OOLING SEQUENCE BOUNDED BY LOSS OF I SHUTDOWN COOLING I L (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 GENERATOR WITH ;f;3YPASS TURBINE TRIP OR LOAD REJECTION FIGURE G-5-16 8/3/00
PLANNED OPERATION
- ADD f"JL£: C0012767 Mfil_l.2 T1JRBrNE TRIP OR GENERATOR LOAD REJECTJON WJTHOUT BYPASS STATE D
POWER <30%
HIGH NEUTRON FLUX POWER >30%
TRIP ON CLOSURE 1 UR8JNE STOP VALVE HIGH NEUTRON CONTROL VALVE FAST FLUX CLOSURE INSERT CONTROL RODS HIGH RV PRESSURE PRESSURE RELJEf SYSTEM PRESSURE RELIEF S
RV ANO PC JCS REACTOR 1S~&1~6N S IN!TTATE MSJV CLOSURE ON LOW TURBINE JNL£T PRESSURE OR LOW REACTOR WATER LEVEL (LEVEL 1)
ISOLATE MAIN STEAM UNES RCJC HPCI START ON LOW REACTOR WATER LEVEL (L£VEL 2)
ADS PLANNED OPERATION FEEOWATER MAINTAINS l£VEL CORE SPRAY s
~ ~ :-i EXTENDED CORE OOUNG SEQUENCE 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
PRESSURE RELJEF SYSTEM SIF SUPPRESS[ON POOL (PASSJVE)
PRESSURE RELIEF S
CA00 FlL£: C0012768 STATE D
>825PSIG STATE 0
<825PSJG SCRAM SIGNAL FROM MSIV POSJTION SWITCHES lNSERT CONTROL RODS lli:t!L.U ISOLATION OF AU.
MAIN STEAM UNES STATES C,D PLANNED OPERATION RCIC lNCIDENT DETECTION CfRCUITRY S
--;r;-
HPCI START ON LOW REACTOR WATER L£VEL (L£VEL 2)
SJF
~ -~
EXTENDED CORE OOLlNG SEQUENCE BOUNDED BY LOSS OF I SHUTDOWN COOLING I L (EVENT 31) _J LPCl 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
~DO FJL.£: C0012769 PLANNED OPERATION
.EYEt,JLU ISOLATION OF ONE MAIN STEAM UNE STATE 0 HIGH NEUTRON FLUX SIGNAL SCRAM SfGNAL ON NEUTRON MONJTORJNG SYSTEM TRIP 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 ISOLATION OF ONE MAIN STEAM LIN~*
FIGURE G-5-19 8/3/00
INITIATE s I ISOLATION ON LOW CONDENSER VACUUM ISOLATE MAIN HIGH NEUTRON STEAM LINES FLUX TRIP
_J SCRAM ON:
RPS f------. 1. TURBINE STOP VALVE CLOSURE SI F
- 2. REACTOR PRESSURE
- 3. NEUTRON MONITORING SYSTEM TRIP
- 4. MAIN STEAM ISOLATION VAL VE CLOSURE CRD I---
INSERT CONTROL RODS GADD flLE: C001277D mtil....!a LOSS OF CONDENSER VACUUM STATES C,D I PRESSURE RELIEF SYSTEM L
I SUPPr11ssJ~~) POOL 1 PRESSURE RELIEF I
RClC START ON LOW REACTOR WATER LEVEL (LEVEL 2)
HPC\\
ADS CORE SPRAY SI F
~ ~~
EXTENDED CORE DOLING SEQUENCE BOUNDED BY LOSS OF I SHUTDOWN COOLING I L (EVENT 31) _J LPCI 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 8/28/08
100 FILL C0012771 HIGH NEUTRON FLUX SCRAM SIGNAL ON NEUTRON MONITORJNG SYSTEM TRIP INSERT CONTROL RODS JcfillL.1§ LOSS OF FEEOWATER HEATING STATE D 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 LOSS OF FEEDWATER HEATit\\lG FIGURE G-5-21 8/3/00
CAOO FJL£: C0012772 PLANNED OPERATION rY£tiLJ.l SHUIDOWN COOLING MALFUNCTION (TEMPERATURE DECREASE)
ALL STATES 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
\\OD rnr: C0012773 NEUTRON MONITORlNG SYSTEM s
S /F RPS HIGH NEUTRON FLUX SCRAM ON:
- 1. TURBINE TRIP f~~GB~N:A~~P ~~~
POSHJON SWJTCH
- 2. HIGH NEUTRON f"LUX TRIP
[NSERT CONTROL RODS REACTOR VESSEL ISOLATION
.E\\!fJiL1B INADVERTENT HPCf PUMP START STATES C,O INITIATE MSJV CLOSURE ON LOW PR::SSURE
[SOLATE MAIN STEAM LINES PRESSURE REUEF RCIC HPCI S/F START ON LOW REACTOR WATER l£VEL (l£VEL 2)
AfJS LPCI
~-
=l EXTENDED CORE OGLING SEQUENCE BOUNDED BY LOSS OF l:
UTDOWN COOLING I (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
~DD nt..£: C0012774 TERMINATE ROD WITHDRAWAL HIGH FLUX SCRAM, !RM
.EIDIL.1.9 CONTROL ROD WITHDRA.WAL ERROR ALL STATES SCRAM SfGNAL ON NEUTRON MONITORING 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 CONTROL ROD WITHDRAWAL ERROR FIGURE G-5-24 8/3/00
AFTER ISOLATION PRESSURE RELIEF SYSTEM S/f SUPPRESSION POOL (PASSM)
PRESSURE RELIEF SCRAM SIGNAL FROM -
- 1. MS!V POSITION SW!TCH
- 2. TURBINE TR!P STOP VN..VE POSmON SWITCH
- 3. HIGH PRESSURE
- 4. LOW WATER l£VEL INSERT CONTROL ROOS MlfU2 PRESSURE REGULATOR FAILURE -
OPEN STATES C,O RCIC PLANNED OPERATION HPCI START ON LOW REACTOR WATER LEVEL (LEVEL 2)
AOS CORE SPRAY s
SI c f(XTENOED CORE 7 I COOLING SEQUENCE I BOUNDED BY LOSS OF I SHUffiOWN COOLINj L (EVENT 31)
LPCI REACTOR VESSEL ISOLATION CLOSE MS!Vs ON LOW PRESSURE (RUN MODE)
!SOL.ATE MAIN STE.AM LJNES 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 PRESSURE REGULATOR FAILURE -
OP.EN FIGURE G-5-25 1
8/3/00
- .ADD f"IL.E: C0012776 MANUAL SCRAM AT TECH SPEC SUPPRESSION POOL TEMPERAnJRE RPS STATE D fNITIATE SCRAM ON HIGH DRYWEU. PRESSURE SAFETY VN...VE OPEN INSERT CONTROL RODS PRESSURE
~
RELIEF S
£YEi'IL2.J lNAOVERTENT OPEN[NG OF A RELIEF OR SAFETY VALVE STATES C,D RV AND PC CLOSE ON LOW JCS CONDENSER s
VACUUM ISOIAIT MAIN SIDM s
LINES
(
R~CTOR VESSEL ISOLATION RCIC I
lNCIOENT DETECTION CIRCUITRY S
---;r,-
HPCI START ON LOW REACTOR WATER LEVEL (LEVEL 2)
AOS CORE SPRAY s
SI F
~ ~ :-i EXTENDED CORE DOLING SEQUENCE BOUNDED BY LOSS OF I SHUTDOWN COOUNj L (EVENT 31) lPC!
EDP SUPPRESS/ON POOL TEMPERATURE TRANSFER DECAY HEAT TO SERVICE WATER HEAT CAPACITY TEMPERATIJRE LIMIT ADS FOLLOWING SHUTDOWN 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 INADVERTENT OPENING OF A SAFETY OR RELIEf
- VALVE FIGURE G-5-26 8/3/00
- ADO FIL.£: C0012777 STATE O ONLY
!NIT[ATE SCRAM ON LOW WATER l.EV£L (l£VEL 3)
[NSERT CONTROL RODS
~
LOSS OF fEEDWATER FLOW SfAITS C,D PLANNED OPERATION PRESSURE RELIEF J SYSTEM PRESSURE '
RELIEF s
P<75 PSIG P>75 PSfG PLANNED OPERAflON SHUTDOWN COOLlNG I
RV AND PC
~ lNITIA'fE
ON LOW PRESSURE
!SOL.ATE MAfN STEAM LINES REACTOR IS~&1~6N S
\\__
RCfC HPC[
s Ir START ON LOW REACTOR WATER l£VEL (l£VEL 2)
AOS LPCl jEXTENOED CORE 7 I COOLING SEQUENCE I BOUNDED BY LOSS OF I SHUTDOWN COOL/Nj L (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
SCRAM SIGNAL
- l. TURB[NE CONTROL VALVE FAST CLOSURE (TURBINE 0\\/ERSPEED DUE TO GENERATOR LOAD REJECTION)
- 2. TURBINE TRIP STOP VALVE POSJTTON SWITCH (DUE TO HIGH REACTOR WATER LEVEL CAUSED BY REC!RC. PUMP COASTDDWN),
- 3.
MSIV CLOSURE (DUE TO LOW CONDENSER VACUUM)
ADO f"JL£: C0012778 RPS SIF CRD SI F STATES B, D INSERT CONTROL RODS STATES C.D PRESSURE > 75 PSIG PRESSURE RELIEF
=
LOSS OF OFF'-SlTE POWER AU. STATES AU. STATES PRESSURE <75 PS(G REACTOR VESSEL ISOLATION PLANNED OPERATION SHUTDOWN COOLING CLOSE ON LOW CONDENSER VACUUM OR RPS M-G SET COASTDOWN OR TRIP lSOlATE MAIN STEAM LlNES RC!C HPC!
START ON LOW REACTOR WATER L£VEL (L£VEL 2)
ADS CORE SPRAY LPCI S!F jEXITNOED CORE 7 I COOUNG SEQUENCE I BOUNDED BY LOSS or L:
UTDOWN COOLING I (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 LOSS OF OFF-SITE FOR POWER FIGURE G-5-28 8/J/00
I.DO FILI: C0012779
=
RECIRCULATION FLOW CONTROL FAlLURE -
DECREASING FLOW STATE D PLANNED OPERATION
INSERT CONTROL RODS PRESSURE RELIEF S
REACTOR VESSEL JSOLATJON BELOW ABOUT 25 PERCENT OF RATED POWER, THE BYPASS SYSTEM WILL TRANSFER INITIATE MS[V CLOSURE ON LOW PRESSURE ISOLATE MA(N STEAM LINES 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 ACTION CAN REDUCE POWER TO WITHIN THE BYPASS CAPACITY.
RCIC INCfDENT DETECTION CIRCUITRY S
;r,-
HPCI START ON LOW REACTOR WATER LEVEL (LEVEL 2)
LFCI SI F jEXTENDED CORE 7 I COOLING SEQUENCE I BOUNDED BY LOSS OF I SHUTDOWN COOLIN:J L (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 FLOW CONTROLLER FAILURE-DECREASING FLOW*
FIGURE G-5-29 8/3/00
CADO FIL.£: COOl 2780
.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
\\OD fll.E: C0012781
=r...2B TRIP OF TWO RECIRCULATJON PUMPS STATE C.D ABNORMAL PROCEDURE SCRAM ON TURBINE TRIP LOW WATER LEVEL (LEVEL 3)
INSERT CONTROL RODS PRESSURE REUEF S
REACTOR VESSEL ISOLATION INITIATE MSfV CLOSURE ON LOW PRESSURE ISOlATE MAIN STE.AN LINES 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 PERCENT AND 30 PERCENT POWER, A HIGH RPV PRESSURE SCRAM WILL RESULT UNLESS OPERATOR ACTION CAN REDUCE POWER TO WITHIN THE BYPASS CAPACITY HOWEVER, THE ABNORMAL PROCEDURE REQUIRES THE OPERATOR TO INITIATE A MANUAL SCRAM.
RCIC HPC)
START ON LOW REACTOR WATER LEVEL (LEVEL 2)
SI F jEXTENDEO CORE 7 I COOLING SEQUENCE I BOUNDED BY LOSS OF I SHUTDOWN COOUN:J L (EVENT 31)
LPCI NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
Nebroska Public Power District COOPER NUCLEAR STATION UPDATED SAFElY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR TRIP OF TWO RECIRCULATION PUMPS FIGURE G-5-31 8/3/00
CAOO FJLE: C0012782 PLANNED OPERATrON
.EYElil..2S RECIRCULATION FLOW CONTROL F A[LURE -
lNCREASING FLOW STATE D 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
CA00 flLE: C00t2783 PLANNED OPERATION
=uo START-UP Of l*LE RECJRCULATION PUMP All STATES 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
RPS STATES 8,0 INSERT CONTROL RODS SCRAM SIGNALS STATES C,O PRESSURE RELIEF' SYSTEM PRESSURE RELIEF S
- 1. TURBINE CONTROL VALVE FAST CLOSURE (TURBINE OVERSPEED DUE TO GENERATOR LOAD REJECTION)
- 2. TURBINE TRIP STOP VALVE POSITION SWITCH (DUE TO HIGH REACTOR WATER LEVEL CAUSED BY RECIRCULATION PUMP COAST DOWN)
- 4. REACTOR PROTECTION SYSTEM M-G SET COAST DOWN OR TRIP (FAIL-SAFE)
,OD FIL£: C0012784 STATES C,O CLOSED ON i',lllLJ.l LOSS OF SHUTDOWN COOLING ALL STATES
>75 PSJG RV ANO PC J--LOW CONDENSER ICS VACUUM OR s
R~Mro~Jf
<75 PS[G S F OR TRIP ISOLATE MAIN STEAM LlNES A,8 I
STATES RCJC r
I I
I I
I
___ I
,---_J I
I I
PLANNED OPERATION SHUTDOWN COOLING
- NOTE:
M EXTENDED CORE COOLING SEQUENCE BOUNDS OTHER SSD's LPCI L
BOUNDRY OF EXTENDED CORE COOLING M
HPCr SI' RESTORE ANO MAINTAIN WATER LEVEL START ON LOW REACTOR WATER l£VEL (LEVEL 2)
EOP SlJPRESS!ON POOL TEMPERATURE ADS TRANSFER DECAY HEAT TO SERVICE WATER EOP HEAT CAPACJTY TEMPERATURE LJM/T DEPRESSURIZE ANO TRANSFER DECAY HEAT TO SUPRESSION POOL CORE SPRAY M
S LPCI 7
I I
I I
I CORE SPRAY M
EOP LIMIT ON REACTOR WATER l£VEL LPCI 7
I I
I I
I EOP SUPPRESSION I POOL TEMPERATURE UM/T
____ _J I
I I
I I
NOTE:
RHR SUPPRESSION POOL COOUNG SI F THIS EVENT DEMONSTRATES THE CAPABILITY TO ATTAIN COLD SHUTDOWN FROM FULL POWER OPERATION CONSIDERING SINGLE FA! LURES AND THE LOSS OF OFFSITE POWER I NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
I Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
TRANSFER DECAY HEATI TO SERVICE WAITR I
I
_J I
PROTECTION SEQUENCES LOSS OF FOR FIGURE G-5-34 J
SHUTDOWN COOLIN~;
8/3/00
NEUTRON MONrTORfNG SYSTEM s
SI F ADD FIL£: C0012785 lRM SCRAM OR APRM SCRAM AT REDUCED SET POINT lN START -UP MODE APRM SCRAM JN RUN MOOE SCRAM ON
- 1. TURBINE STOP PLANNED OPEAATION VALVE POSrTION SWITCH OR TURBINE TRIP
- 2. NEUTRON MONrTORING SYSTEM TRJP INSERT CONTROL RODS
~
FEE*WATER C0NTR0LilR FAILURE MAXIMUM DEMAND STATES C,D PRESSURE RELIEF SYSTEM SI F SUPPRESSION POOL (PASSIVE)
PRESSURE RELIEF S
INITIATE MSIV CLOSURE ON LOW PRESSURE ISOLATE MAIN STEAM LINES RV AND PC
!CS SI F MSJV:s SI F REACTOR VESSEL ISOLATION RCIC JNCJOENT OETECT[QN CIRCUITRY S
--;v-HPCI START ON LOW REACTOR WATER LEVEL (LEVEL 2)
LPG!
SI F
~ ~~
EXTTNDED CORE OOLING SEQUENCE BOUNDED BY LOSS Of I SHUTDOWN COOLING I L (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
t MONITORING SYSTEM NEUTRON NEUTRON 1---
HlGH I
CAOO flt.£: C0012786 s
FLUX TRIP ON HIGH NEUTRON FLUX I
INSERT I
CONTROL ROOS RHR SUPRESSION POOL COOLING M
SJ F CONTAJNMENT COOLING S
I I
sl F REACTOR WATER SAMPLE VALVES s SJ F MECHANICAL VACUUM PUMP s SIF RADIOACTIVE MATERIAL REL£ASE CONTROL s
PLANNED OPERATJON HIGH RADIATION MAIN STEAM LINES lNJTIATE REACTOR WATER SAMPLE VALVE CLOSURE & MECH VACUUM PUMP ISOLATION ON HIGH RADIATION ISOLATE REACTOR WATER SAMPLE VALVES ISOLATE MECH. VACUUM PUMP OPERATOR ACTION BASED ON HIGH RADIATION MSJVs SJF REACTOR VESSEL S
ISO!ATION
~
CONTROL ROD DROP ACCIDENT STATE 0 PLANNED OPERATION G;
EOP RADrOACTTVE REL.£ASE FW ANO PC
!CS M
sl F PRIMARY CONTAINMENT ISOLATION VALVES SI F PRIMARY CONTAINMENT (PASSIVE)
ESTABUSH CO~~~m~NT S ISOLATE MAIN STEAM LINES I
RCIC HPCI START ON LOW REACTOR WATER LEVEL (LEVEL 2)
~-:-i EXTENDED CORE OOLING SEQUENCE BOUNDED BY LOSS OF I SHUTDOWN COOLING I L (EVENT 31) _J PRESSURE RELIEF S
LPCI CONTROL ROD VELOCITY-LIMITER (PASSIVE) s
~ I REACTIVITY INSERTION S
RATE 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
CADD FILE: COOl 2787 SCRAM ON LOW WATER LEVEL OR HIGH OR'tWELL PRESSURE INSERT CONTROL RODS SI F PRJMARY CONTAINMENT JSOLATION VALVES SI F SI F PRlMARY CONTAINMENT (PASSIVE)
ESTABLISH AND MAINTAIN PRIMARY CONTAINMENT LOW REACTOR WATER LEVEL OR HIGH ORYWELL PRESSURE ISOLATE PRIMARY CONTAINMENT ISOLATE MAIN STEAM LINES REACTOR BUILDING HEATING AND VENTILATION SYSTEM SI F SI F ELEVATED RELEASE POINT (PASSIVE) s ESTABLISH ci~~irJ:~T S MNL.+/-1 PIPE BREAKS INSIDE PRIMARY CONTAINMENT STATES C,D ISOLATE REACTOR BUILDING REACTOR BUILDJNG SHIELDING (PASSIVE)
CONTROL ROOM ENV~~~~5rTAl S SHEET 1 OF 2 SEE SHEET 2 OF 2 EDP HIGH WETWELL PRESSURE p
EOP SUPPRESSION POOL TEMPERATURE PLANNED OPERATJON RHR CONTAINMENT SPRAY COOLING M
SI F CONTROL ROOM HABITABILITY CRD HOUSING SUPPORT (PASSIVE)
M MAINTAIN PREVENT co~f&\\o:oo s EOP HJGH DRYWELL PRESSURE AND RADIATION OPERATOR ACTION BASED ON LOCA WJTH FUEL DAMAGE sutb~Es~~oN 5 TRANSFER DECAY HEAT TO SERVICE WATER RHR SUPPRESSION POOL COOLING TRANSFER DECAY HEAT TO SERVICE PRESSURE RELIEF SYSTEM M
WATER SI F CONTAINMENT COOLING S
SI F SUPPRESSION POOL (PASSIVE)
PRESSURE RELIEF 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 INSIDE PRIMARY CONTAINMENT SHEET 1 FIGURE G-5-37 02/05/10
LPCI S\\ F lPCI S\\ F E',LEtjLJj (CON'T)
INCIDENT DETECTION CIRCUITRY S
--r-S\\ F RECIR SUCTION ARK 1 CORE SPRAY + 2 LPC!
OTHER BREAKS 1 CORE SPRAY + 1 LPCJ OR 2 LPC! OR 2 CQ_RE _$PRAY 1 PUMP REQUIRED EOP REACTOR WATER LEVEL CORE SPRAY M
S si, LARGE BREAK INITIATE ECCS AT RESPECTIVE TRIP SETTING CORE SPRAY s
S\\ F LPCI lNTtRMEDCATE BREAK N
SMAU. BREAK JNJT[ATE ECCS AT RESPECTrvE TRIP SETTING 1 CORE SPRAY
._ PLUS I
s(
2LPCI CORE SPRAY s
S\\ F SjF S\\ F CORE SPRAY s
RESTORE AND MAINTAIN WATER LEVEL SI F 1 CORE SPRAY PLUS 2 LPCJ
!Nfl!.ATE ECCS AT RESPECTIVE TRfP sEmNG ADS LPG!
EOP HEAT CAPACITY TEMPERATURE UM!T JNCJOENT DETECT JON CIRCUITRY S
~
RESTORE AND MA!NTA[N WATER LEVEL CORE SPRAY s
SHEET 2 OF 2
!NJTIATE ECCS AT RESPECTIVE TRJP SETTT HPCI 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 2 FIGURE G-5-38 8/3/00
CADO FlLE; C0012789 SERVICE WATER EFF'LUENT UONITOR RADIATION MONITOR ALARM EOP 5.3,5 RIVER WATER ENVIROMENTAL CONTROL MAINTAIN DIF'F'ERENTIAL PRESSURE ACCROSS RHR Hx SW ABOVE RHR PRESSURE TS J.7.6 RADIOACTIVE I.AATERlAL RELEASE CONTROL WATER LEVEL
.!:l1lfU2 F'UEL HANDLING ACCJDENT ALL STATES TRI.I T 3,9, 1 TS 3.9.6 RADIOACTIVE MAT(RJAL RELEASE CONTROL WATER LEVEL REACTOR BUILDING ISOLATION VENTILATION RADIATION MONITORING SYSTEM SI F CONTROL ROOU VENTILATION SYSTEM REACTOR BUILDING SiHJELOING (PASSIVE)
CONTROL ROOM ENVbi~~6~TAl. s RADIATION MONITOR TRIP CONTROL ROOM HABITABILITY 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
PRESSURE RELIEF CAOO F"ILE: C0012790 ISOLATE ON L(JN WATER L£VEL, HIGH FLOW, OR HIGH
/.REA TEMPERATURE RESTR[CT LOSS OF REACTOR S
COOL.INT PR!WRY CONTA!NMEITT AN°v£~TOR S ISOLATION s
EOP SECONDARY CONTAINMENT CONTROL RPS M
S EOP SECONDARY CONTAINMENT CONIBOL ISOLATE MAIN STEAM LINES lNJT!ATE lSOLATION VAf-VE CLOSURE ISOLATE SYSTEM NS REQUIRED Mfil_i;J PIPE BREAKS OUTSIDE PRIMARY CONTAINMENT STATES C,D M
SCRAM SIGNAL ON LOW WATER LEVEL, MAIN STEAM LINE ISOLATION VALVE POSmON SWITCHES, TURBINE CONTROL VALVE FAST
INSERT CONTROL ROOS EOP SUPPRESSION POOL TEMPERATURE TRANSFER DECAY HEAT TO SERVICE WATER CONTAINMENT COOLING S
M EOP REACTOR WATER LEVEL M
PLANNED OPERATION ONE PUMP LPC!
M RHR SUPPRESSION POOL COOLING M
S!F EXTENDED CORE COOLING M
s M
LPCI J OTHER
~TION EOP REACTOR WATER LEVEL SHEET 1 OF 2 SEE SHEET 2 Of 2
~
I RES:ORE AND I M
ADS ADS SI F WA~rrtme:L ONE LPC!
PUMP I CORE SPRAY M
s M
S S F EOP HEAT CAPACITY TEMPERATURE LlMJT ADS s
M SI F CORE SPRAY M
s NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
MA!NTAfN DEPRESSUR!ZATION Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
PROTECTION SEQUENCES FOR PIPE BREAKS OUTSIDE PRIMARY CONTAINMENT SHEET 1 FIGURE G-5-4O 04/08/02
EVENT 43 (CONTINUED)
- aoo FR£: coo,2191 REACTOR BUJLOINC JSOL.ATJON AND CONTROL SYSTEM SI F REACTOR BUILDING HEATING ANO VENTILATION SYSTEM SI F ELEVAITO RELEASE POINT (PASSI\\'£}
ESTABLISH ctmt"~t~r s s
NOTE: REFER TO FIG. G-4-2 FOR DIAGRAM FORMAT.
SHEET 2 OF 2 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
PLANNED OPERATION
=
RECIRCULATION PUMP SEIZURE STATES C.0 CAOO fllf: C0012792 SCRAM ON TURB[NE TRIP OR LOW WATER LEVEL INSERT CONTROL ROOS PRESSURE RELIEF S
REACTOR VESSEL JSOLATJON LOW MAJN STEAM LINE PRESSURE ISOLATE MAIN STEAM LINES RC!C HPCI START ON LOW REACTOR WATER LfVEL (LEVEL 2)
I.PC!
SI f
~-:-i EXTENDED CORE OOLING SEQUENCE BOUNDED BY LOSS OF l:
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 PUMP RECIRCULATION SEIZURE FIGURE G-5-42 8/3/00
- ADO fll£: C0012793
~
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
PROCEDURAL REQUIREMENT
- ADO FILE: C0012796 STATES 8,0 M
I SHUT DOWN 0 REACTOR FROM OUTSIDE CONTROL ROOM SCRAM BY DE-ENERGJZJNG SYSTEM WINUALL Y INSERT CONTROL ROOS I
INCIDENT 1--
START HPC[
DETECTION SYSTEM ON CIRCUITRY LOW REACTOR WATER LEVEL T
RESTORE ANO f...lAINTA!N WATER LEVEL EOP SUPPRESSJON POOL TEMPERATURE I """
t--
rnANSFER SUPPRESSJON POOL DECAY HEAT COOLING TO SERVICE WATER M
M M
.E'lE£il.JiJJ SHUIDOWN FROM OUTSIDE CONTROL ROOM All STATES STATES C,0 I PRESSURE REUEF I SYSTEM I
SUPPRESSION POOL I (PASSIVE)
PRESSURE REUEF
( p )
PROCEDURAL REOU!REMENT I
RV AND PC ICS ISOLATE MSIV3 MAIN STEAM LINES 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
~OD f!LE: C0012797 E'IElil...fl.l SHUTDOWN WITHOUT CONTROL RODS STATES B,D EDP SHUTDOWN REOUJREO ON POWER>2 l/2 PERCENT SHUT DOWN REACTOR WITHOUT CONTROL RODS INSERT SORON SOLUTION INTO REACTOR VESSEL 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
PLANNED OPERATION PLANNED OPERATION CA00 FILE: C0014119 REACTOR SHUTDOWN HJGH REACTOR PRESSURE OR LOW REACTOR WATER LEVEL (L£VEL 2)
HIGH REACTOR PRESSURE OR LOW REACTOR WATER LEVEL (L£VEL 2)
EOP SUPPRESSION POOL TEMPERATURE PlANNED OPERATION PRESSURE REUEF
.EY£ljL£2 ANTICIPATED TRANSIENTS WITHOUT SCRAM STATE D SUPPRESSION POOL COOUNG EOP SUPPRESSION POOL TEMPERATURE PLANNED OPERATION TRANSFER ENERGY TO SERVICE WATER I COOLING SEQUENCE I BOUNDED BY LOSS OF I SHUTDOWN COOLING I L.-'.:'~3'.!._ J PLANNED OPERATION START ON LOW REACTOR WATER LEVEL (L£VEL 2)
RESTORE AND MArNTAIN WATER L£VEL 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
CAOO f!L.E: C0029890 SCRAM SIGNAL
- 1. TURBINE CONTROL VALVE FAST CLOSURE (TURBINE Ov£.RSPEEO DUE TO GENERATOR LO/>ll REJECTION)
- 2. TURBINE TRJP STOP VALVE POSfTJON SWITCH (DUE TO HIGH REACTOR WATER l.EVEL CAUSED BY RECIRC. PUMP
- COASTOOWN).
- 3.
MSN CLOSURE (DUE TO LOW CONDENSER VACUUM)
RPS INSERT CONTROL RODS PRESSURE REUEf
=
STATION BLACKOUT STATE 0 REACTOR VESSEL ISOLATION CLOSE ON LOW CONDENSER VACUUM OR RPS M-G SET COASTOOWN OR TR[P ISOLATE MAIN STEAM LINES START ON LOW REACTOR WATER LEVEL (L£VEL 2)
RESTORE WATER LEVEL MAINTAIN WATER LEVEL 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 A TION BLACKOU_T FIGURE G-5-47 8/3/00 1.,