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TRIP SIGNAL TRIP SYSTEM -7 I I I I I I I LOGIC I I PROTECTIVE ACTION ACTUATION ACTUATED 11 SENSOR I ~ t-f" CHANNEL DEVICE DEVICE TRIP SIGNAL tHANNEL .-;.,-'f--t,~~___/\\r-- - - _J j I SENWR I, ~ -I TRIP SIGNAL LEGEND: -"v- -;tf-t><J ELECTRICAL RELAY SOLENOID MECHANICAL CONNECTION ELECTRICAL CONNECTION TRIP SIGNAL ELECTRICAL CONTACTS !SHOWN CLOSED) VALVE TYPICAL PROTECTION SYSTEM (CONTROL AND INSTRUMENTATION PORTIONS)
SUPPLEMENTARY CONTROL_--11..i (MANUAL OR AUTO. DISPATCH) SYNCH. MOTOR SPEED GOV. MECH. ADMISSION VALVE PRES. INITIAL ........ __... PRESSURE REGULATOR GOV. REG. FREQ./ MANUAL SPEED PUMP SPEED CONTROLLER REACTOR SP INDI EED CATOR I SCOOP TUBE POSITION ER G>- C --@ 1 I TYPICAL FOR EACH LOOP I I _____ J M - INDUCTION MOTOR ~:J:.......>o G - AC GENERATOR C - ADJUSTABLE SPEED COUPLING CADD FILE: C0045079 TURBINE Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT {USAR) Single-Cycle-BWR Control System (Flow Control Section) Functional Control Diagram Figure VII-1-2 04/22/02
IDIV. !IA I (I) r..17 I I L,-1 I CHANNEL 11A 11 SUB CHANNEL "Ai°'l TRIP LOGIC Al t C \\ \\. J i I I DIV.Ti l!A I I ,..l7 I I LT_j I SUB CHANNEL 11A2 11 TRIP LOGIC A2 TRIP ACTUATOR TRIP ACTUATOR IA 2A 31\\ 4A 5A 6A (4) 11 I40A 11 CH.A SCRAM '-------------/ B.UP VALVE ~<( 00
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TRAY Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) ESF Separation Concept Figure VII-1-4 1/23/01 w 0
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.,,,SEPARATE ---->"f-......j._J I \\ CABLES ~:::::-c-+_-_~---_-_-_,.::::-1--t=-+:P ____ _ ~ TYPICAL SENSOR HAVING TWO OR MORE INDEPENDENT CONTACTS WIRED OUT SEPARATELY TO DIFFERENT SUB SYSTEMS COMMON DIVI WIREWAY -+-r--- --t--r-- ---~ - -~r--- - --,--- -7 1-{D} - ~ - f gTvHiR SUB SYS. T~O!r ~ SENSOR RELAYS I I ~f~~t DIVISION I E A > AUX. LOGIC T _J L SUB SYSTEM RELAY (TYP.) RELAY PANEL I / -f
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SEPARATION I DIV I ~N~ - 7 r-- I OTHER AUX. LOGIC ~ I I DIV II: YS ~ RELAY (TYP.) SENSOR RELAYS ~ ~~tty. DIVISION It: J PANEL SUB SYSTEM I CONTROL R!CLAY P~EL-1 FUSE"~' -,-r--- - ---;--r - --- _ ___ -t-- _ COMMON DIVE WIREWAY----i I I I I I I I I I I I SENSOR CONTACTS DIVISION lI ~SEPARATE/--== 's.l: h CABLES B D ~ PARAMETER NO. I -1 B
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SENSORS-----,.--------------,.---------------,------------ II DIV. 1 11 CONT. PWR. (RPS sus':0."> DIV. JI A l j .....-T-RI_P_C_.H __ A_N_N_E_L-:_ __ .....__---11.,.. TRIP CHANNEL ~, 11A1 11 11A2 11 I I 11DIV. II" CONT. PWR. ( R P S 8 US 118 11 ) DIV. IB DIV. JIB ~R-:- CHAN: i----'---~:: CHAN: 17 I "e i" "e2" I I 19-15 I DIV. :a: I I I s-11 I I L ___ _ DIV. I AUX. RELAYS INBOARD VAL. CONT. INB 1D. DIV. I POWER DIV. I DIV. U POWER DIV. Il AUX. RELAYS OUTBOARD VAL. CONT. OUTB 1D. 9-42 OUTBOARD VALVE I J FOR OTHER VALVES----- LEGEND 0 INDICATES ONE OR MORE SENSORS, NO MORE THAN ONE SENSOR PER PARAMETER Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Primary Containment Isolation System Separation Concept Figure VII-1-6
TEST SWITCH A A E TURB STOP VALVE CLOSURE A TURBINE CONTROL VALVE FAST CLOSURE DISCHARGE A VOLUME HIGH WATER LEVEL MAIN STM A LINE E ISO VALVE A PRIMARY CONTAINMENT HIGH PRESSURE A NUCLEAR SYSTEM HIGH PRESSURE A REACTOR LOW WATER LEVEL A} NEUTRON MONITORING SYSTEM E REACTOR PROTECTION SYSTEM LOGIC A1 C G A BYPASS A BYPASS C A BYPASS C G C C C C G REACTOR PROTECTION LOGIC A2 NOTE: CONTACTS SHOWN IN NORMAL CONDITION CADD FILE: C00l 4194 SYSTEM C C C NEUTRON MONITORING INSTRUMENT TRIPS FOR INITIAL FUEL LOADING ONLY MODE } SHUTDOWN SWITCH MODE (OPEN IN I AUTOMATIC SHUTDOWN) RESET A MANUAL SCRAM REACTOR PROTECTION SYSTEM LOGIC A3 Nebraska Public Power District COOPEJR NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Schematic Diagram of Logics in One Trip System Figure VII-2-3 07/22/94
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NEUTRON MONITOR* ING SYSTEM NEUTRON MONITORING SYSTEM TRIP CHANNELS IRM DETECTOR AMPLIFIER A BYPASS UPSCALE TRIP LPRM DETECTOR AMPLIFIER 1LPRM1 1 other detectors 1 AMPLI Fl ER-SUMMER (APRM) A INOP LPRM DETECTOR AMPLIFIER 1LPRM1 A UPSCALE TRIP IRM CH ANN EL A ione of e1ght1 A IRM BYPASS REACTOR PROTECTION SYSTEM A IRM INOP A IRM UPSCALE TRIP A APRM DOWN-SCI\\LE A 1\\PRM I\\ MODE SW IN RUN A APRr,i INOP BY PASS A 1\\PRM UPSCALE TRIP E E E E E E E E 0 NEUTRON MONITORING SYSTEM LOGICS 1two of e1ghtr i-i:.,ACT 1Jfi f'RJTECTILHI SYSTEtA LOGlf' 011p,.r 101:,
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Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Relationship Between Neutron Monitoring System and Reactor Protection System Figure VII-2-7
IRM CHANNELS A, E (B, F) AUTO SIGNAL 0 UPSCALE TRIP ON LEVEL ~ TRIP ON INSTRUMENT INOPERATIVE --,~ PERMISSIVE WHEN REACTOR MODE SWITCH IN RUN POSITION I I L PERMISSIVE WHEN AUTO SIGN~L NOT PRESENT PERMISSIVE WHEN AUTO SIGNAL NOT PRESENT _,_j c---- Al (Bl) OOE OF TWO NEUTRON MONITORING SYSTEM LOGICS ASSOCIATED WITH REACTOR PROTECTION ~STEM LOGIC Al APRM CHANNELS A, E(B, F) C, EID, B) AUTO SIGNAL AUTO C C AUTO SIGNAL SIGNAL 0 UPSCALE TRIP ON LEVEL w] TRIP ON INSTRUMENT INOPERATIVE PERMISSIVE WHEN REACTOR MOOE SWITCH IN RUN POSITION PERMISSIVE WHEN AUTO SIGNAL NOT PRESENT PERMISSIVE WHEN AUTO SIGNAL NOT CNS
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IRM CHANNELS C, G (0, HJ PERMISSIVE E. WHEN AUTO SIGNAL NOT 1-.-1-----------~--- PRESENT 0 UPSCALE TRIP ON LEVEL 0 TRIP ON INSTRUMENT INOPERATIVE ~ __ _J i-+-----fC A2 (B2) ONE OF TWO NEUTRON MONITORING SYSTEM LOGICS ASSOCIATED WITH REACTOR PROTECTION SYSTEM LOGIC A2 Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Functional Control Diagram for Neutron Monitoring System Logics Figure VII-2-8
SENSORS D ~ [ D TRIP SYSTEM A POWER BUS NOTE: CONTACTS SHOWN IN NORMAL CONDITION Al TRIP SYSTEM A © A2 © ~ CHANNELS TRIP SYSTEM B © Bl B2 TRIP SYSTEM B POWER BUS REACTOR PROTECTION SYSTEM LOGICS TYPICAL CONFIGURATION FOR: SCRAM DISCHARGE VOLUME HIGH WATER LEVEL TURBINE CONTROL VALVE FAST CLOSURE REACTOR VESSEL LOW WATER LEVEL PRIMARY CONTAINMENT HIGH PRESSURE NUCLEAR SYSTEM HIGH PRESSURE Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Typical Arrangement of Channels and Logics Figure VII-2-9 4/14/97
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TS-13-SOC-51/tOin. TS-13-81A - TS-13-81C - 49ftOin. 40 It O In. 54 ft O in. TE-13-77D TS-13-82D TS-13-828 TS-13-818 TS-13-810 TS-13-808 TS-13-SOD TS-13-790 TS-13-798 TE-13-77A <t_ RPV 13 ft O in. ---1-d>-<""'--- 44 ft O in. ----I TE-23-1058 ~ I TS-2l-101B"-. ) TS-23-1028 TS-23-1038 TS-23-1040 TE lOSC TS-23-103C TS-23-104C TS-23-1030 TS-23-1020 Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Reactor Building - Plan Elevation 859 ft. 0 in. Figure VI I-3-3
TO RCIC TUR!IMP!: ]3 ft O in. PIPE TUNNEL ~{: ~ f, M0-13-16 if: /"c TS-23-101.+.. TO HPCI TURBIME Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Reactor Building - Plan Elevation 903 ft. 6 in. Figure VII-3-4
120 VAC 120 VAC K9 9H' (IND $W'S TYP) )K?A I LOGIC PAIR CONTROL 125 voe K?C SWITCHES AC SOLENOIDS INBOARD MSIV 9 K10 RESET (IND SW'S TYP) K?A I CONTROL 125 voe K7C SWITCHES AC SOLENOIDS OUTBOARD MSIV --5---..-------------, STEAM LINE LP REACTOR LOW WTR TRIP CHANNEL A-2 FUSE ~ RUN SW h~6A-S17C I I } MAIN STEAM LINE BREAK K7C --s---~----------' FUSE LOW CONDENSER VACUUM SWITCH K19C 1YPE FOR TRIP CHANNELS A-1, A-2, 81 & 82 TRIP CH A2 SHOWN A1 USES K7A 81 USES K7B 82 USES K7D CADD FILE, C0014I95 9 K9 RESET K78 I CONTROL SWITCHES DC SOLENOIDS 9 K10 RESET K?B I CONTROL K7D SWITCHES DC SOLENOIDS Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Main Steam Power Supply and Logic Figure VIl-3-5 1/23/01
SUCTION VALVE B PUMP B DISCHARGE VALVE B REACTOR VESSEL SUCTION VALVE A PUMPA -{X}- _ LPCI - ~ L B~ ~A.. J INJECTION INJECTION VALVE A VP..LVE B Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) LPCI Component Arrangement Figure VII-4-9 08/14/00
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I (TRIP SYSTEM LOGIC) I d--=6 V DEC]SION MAKING LOGIC I I IDP'.I _!_IDP f I j T I L _____ =J CORE SPRAY SYSTEM ACTUATION LOGIC (2) V 2 7 7 Z 2 2 2 7 7 Z Z Z 2 2 2 Z Z 7 7 7 Z 7 7 2 2 7 7 7 2 2 7 7 Z 7 2 7 7 7 7 7 7 7 7 2 7 7 Z 7 7 7 7 7 7 7 7 7 7 7 Z 7 7 7 7 7 7 7 7 7 Z 7 7 2 Zl LEGEND: LWL LOW WATER LEVEL HDP HIGH DRYWELL PRESSURE ADS AUTOMATJC DEPRESSURJZATION SYSTEM CSP ONE CORE SPRAY PUMP RUNNJNG LPCJP - ONE LPCl PUMP RUNNING RLP REACTOR LOW PRESSURE CADD FILE: C00l 7889 Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) TYPJCAL EMERGENCY CORE COOUNG SYSTEM (ECCS) INSTRUMENTATJON FIGURE Vll-4-10 05/07/04
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- 6. Spare Neutron Source Locations - 4 Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Source Range Monitoring System Core Locations Figure VII-5-5
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TYPICAL INTERMEDIATE RANGE ;v10NITORL:G svsTE" ( IRM) C CY'..S 'I'OP VL~*T oo C (\\J...:: \\D a: C ..::r '-l:.::: C' C'J...:.;
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C _. *.C a' c., (\\J...::: .' a* r-, C.. 0 0 0 C O r-1 rl ,-1 .-' -< C, CJ,. c, C'J rv, rv" rv, rv" <"'...::: ..::r..::r ~..::r t:- u rl M 1.0 t-0-- rl rv, 1.0 t'-- G ,-j rv,.r-t- C' rl ( L0 t'-- r* M L0 t-2* r--1 0 c' 0 0 0 rl rl rl rl rl ('J ('. (\\J C\\. c'a rv, ( "' '.""' rv,...:1 ..::r...::: ..::r .c: c" )( Intermediate Range ?vioni taring Channels - 4 Safety System Logic Bus A II Intermediate Range Moni taring Channels - 4 Safety System Logic Bus B Total IRM Channels - 8 Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) IRM Locations Figure VII-5-7
53 51 49 47 45 43 41 39 37 35 33 31 29 27 25 23 21 19 17 15 13 11 09 07 05 03 01 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ N:: N ~ ~ '\\ ~ ~ ) ~ ~ ~ ~ ~ ~ ~ ~ N: ~ ~ ~ N: ~ (\\' ~ ~ ~ ~ ~ ~ ~ ~ ~ X IRM DETECTOR, TRIP SYSTEM A IRM DETECTOR, TRIP SYSTEM B CONTROL ROD WITHDRAWN ~ N ~ ~ ~ N: ~ ~ ~ ~ '- ~ ~ l ~ ~ Iii ~ ~ ~ "' ~ N: ~ ~ ~ ~ ~ ~ ~- ~ ~ ~ I I I I I ~ ~ ~ ~ N' ~ N ~ ~ ~ ~ ~ -~ ~ ~ ~ I * ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ N: ~ N: ~ N '\\, ~ ~ ~ ~ ~ ~ ,,J ~ N: ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ , 1-. I/ ~ ~ ~ ~ ~ ~ ~ ~
- <;;; ~ ~
~ ~ ~ ~ ~ ~ ~ ~ --- I I I I I + NEXT CONTROL ROD WITHDRAWN IN SEQUENCE + CONTROL ROD WITHDRAWN OUT OF SEQUENCE IRM DETECTOR BYPASSED Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Control Rod Withdrawal Error Figure VII-5-8
X w.. LJ.l ~ 0:: 0 z 100,-------,------,-----,-------r------i-----,----, 50 10 1.0 0.5 0.10 0.05 0.01 -10 -5 FUEL BUNDLES 10 15 20 25 Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Normalized Flux Distribution for Rod Withdrawal Error Figure VII-5-9
53 51 49 47 45 43 41 39 37 35 33 31 29 27 25 23 21 19 17 15 13 11 09 07 05 03 01 m= -~ I l r"'""' ~ = + -~ I 1 tH 1-1 II I I I I I I I l I I I 8 N""3"WC:0 ONQ" l.0COON,q,WCOO 0000.-..-..-,-.-NNNNNM + CONTROL RODS ... CENTRAL CONTROL ROD 9 LPRM ASSEMBLIES Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) LPRM Locations Figure VII-5-11
ON~~OOON~~OOON~~OOON~~OOON~~OOON ooooo~~~~~NNNNNMMMMM~~~~~~~ ~M~~~~M~~~~M~~~-M~~~~M~~~~ ooooo~~~~~NNNNNMMMMM~~~~~~ (i LPRM Strings providing input to APRM Channels 1, ~, & 3 LoRic Bus A Upper left; letter 1111 Input for APRM Channel 1 Lower left; letter
- Input for APRM Channel 2 Lower right letter* Input for APRM Channel 3 Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
LPRM to APRM Assignment Scheme (System A) Figure VII-5-13a
LEGEND D - TOP LPRM DETECTOR POSITION C - UPPER MIDDLE LPRM DETECTOR POSITION B - LOWER MIDDLE LPRM DETECTOR POSITION A - BOTTOM LPRM DETECTOR POSITION LPRM Strings providing input to APRM Channels 8, D, & F Upper left letter = Input for APRM Channel B { FOR REACTOR PROTECTION Lower left letter = Input for APRM Channel O SYSTEM TRIP Lower right letter = Input for APRM Channel F SYSTEM B Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) LPRM to APRM Assignment Scheme (System B) Figure VII-5-13b
u.J ~ CL u.J 1-
- ,e 0
- ': -2 z:
- ,e 0
Se t: > u.J Cl -4 --6 100 90 80 70 60 50 40 PE RC ENT POWER NOTE: LETTERS 'A' THROUGH 'F' REFER TO APRM ASSIGNMENT DESIGNATIONS Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Envelope of Maximum APRM Deviation Reduction in Power by Flow Control Figure VII-5-14
0:: UJ -= 0 Q.. UJ 0:: I-
- E 0 0::
u... z: E ~ s: UJ Cl I-z: UJ (.) 0:: UJ Q.. 3 2 1 0 -1 -2 -3 -4 0 CHANNEL A C 0.2 0.4 0.6 0.8 1.0 CONTROL ROD POSITION (FRACTION WITHDRAWAL) Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) APRM Tracking With On-Limits Control Rod Withdrawal Figure VII-5-15 5/12/98
Note: Assignment is auto-matically initiated upon rod selection. 53 --------t-7":'1""7"..,.-;--,-,--,-,.._.,~,.....,.... 52 51 ------ 50 49 ----.....,..,...,....,..; ~~~~ l*1~H+i ~~ ~~ A+1+1f-r-f1+1+i+ ~~ ~~ =- +~+1+~+1+.+1+!+1+ ~~ ~~: +1+1+1+1+1+1+1+1+1+1+
- ~ ;~ =.+1+~+ l~l-+~1+/--!+l+~t
!~:;= +1+1+Ht1+1f1+/-1+1+1+1t !~ :: = +1-t:!+l~~i::Utl+~+l+1+ ~~ ~~ = +1+1+1+1+ltr+1+1+1+i+ ~i ~; 1+1+1+~-t-J.+~+1~-----,. 12 11 +1+1+1-+1 +1+1$ 10 09 -- 0801 +1+1+1+1~ 06 05 -"'81111r......___~ 04 0 3 --+-+--+--lf--+--1-- 02 01 -4~-f--1-+--i--+--t-l!-"-........ ~...,....---.,.-:-..,.....!---f ON~~~O~A~ncN-~~ON~~~CNA~~cu OOOOOrlrlrlrlrlNNN~~MMMMMAAA=A~~ rlM~~~rlM~~arlM~~~rlM~~a~M~~~rl OOOOOrlrlrlrlrlNNNN~MMMMMAAAA~~ //1RBM Automatically bypassed (Reading Zeroed)
- Typical Rod Yielding Two LPRM Strings as Input 0 Typical Rod Yielding Three LPRM Strings as INput
- Typical Rod Yielding Four LPRM Strings as INput Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Assignment of LPRM Assemblies to RBM' s Figure VII-5-16
CORE TOP VIEW oo 0 C\\J..:r \\.0 CD C
- '\\J..::r '-Ll ::0 C C'J ~,::; CC C' C:\\
C C\\J..::r *.. :; CC C (', 0 0 0 0 0 ~ ~ ~.--4 -i C'o (' J C\\, ('~ (' J M M M M M..:t...:r..::t.:t -=t Lf', LI' ~M~~~~M~~O~M~~~rlM~~~~M~~~rl ooooo~~~~rlC\\JC\\JC\\J~~MMMMMJ..:r..::r..::r...:r~ Letter= TIP Machine Assigned to LPRM String Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Assignment of LPRM Strings to TIP Machines Figure VII-5-18
REACTOR CORE CROSS CALIBRATION r--, - I I INDEXING MECHANISM CONTAINMENT PENETRATION I 1----- BALL VALVE ~--- I ~--- 1 I ~-- 1 L_, - SHEAR VALVE CHAMBER SHIELD DRIVE MECHANISM --1-, ELECTRICAL SIGNALS (TO CONTROL ROOM) CONTAINMENT PENETRATION I VALVE I TO PURGE SYSTEM I I I I _J Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Traversing In-Core Probe Subsystem Block Diagram Figure VII-5-19
SRM IRM LPRM 1014 ~d l -I-c...:> a::: I-LL.J 1013 0:: p 1012 ,_ T z: 0 C: 1011 X ...J u.. I-c...:> 0:: I-LL.J 0:: z: 0 0:: I-10 10 LL.J p z: ...J 0:: LL.J
- c I-109 LL.J c.::,
0:: LL.J 108 -~ p Cl LL.J I-0:: LL.J V, ~ ...J ...J u.. APRM OPERATION -~ T . 100 0:: LL.J ~ 10 0.. t c.::, I-LL.J
- c
- 0.1 ..01 0::: i-, LU ~ 0.. I-z: . 10-3 LU c...:> 0::: LU 0.. 0.. I-0:: I-V, 10-4 . 10-6' SOURCE* Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Ranges of Neutron Monitoring System Figure VII-5-23
r-3 C: >-cl v ~ '"CJ. ~ (1) I-'* Pl o o Pl trl rt I-' onz 0 w.Oco I-! H >0~ 'rj >tj ~ >zj'i::11)) t.:ritrl"' I-'* I-! >-3 ;,j s C)Q O (") i:: rt I-'* ><: z >-cl I-! (1) I-!
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- ,j z,+
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- J
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- r:
I V) j u I I A I I I I (/) v., v., v., v., v., v., O<l ~ ol!l~ O<l ~ O<l ~ O<l~ O<l ~ O<l ~ 0:: z: 0:: z: 0:: z: 0:: z: 0:: z: 0:: z: 0:: z: 00 00 00 00 00 00 00 v., 0:: v., 0:: z: f-z: f-v., 0:: v., 0:: v., 0:: v., 0:: v., 0:: z: f-z: f-z: f-z: f-z:f-wU wU wu w (_) wu w (_) wU v., w v., w v., w v., w v., w v., w v., w _J _J w w _J _J _J _J _J w w w w w C I I I E I I I G B D F I I I H I I Kl2A I 4A J Kl2A lKlA ]K4A Kl28 lKl B ]K48 Kl2B lKlB ]K48 4C Kl2D lKlD lK4D Kl2D ]KlD ]K4D L __ J .r-----, I I ul KlA I _L IK!A _L I'IB _L I'!B _L IK!C _L ~K!C I =#=KlD I =#=KlD gj Kl2A I TK12A TK128 TK128 TK12C TK12C _J K4A I K4A K48 K48 K4C ?f= K4C I 7f=K4D I =n:=K4D I I I I I L ____ J \\ TO REACTOR PROftCTION SYSTEM LEGEND: KlA. 8, C, D - INOPERATIVE TRIP K4A. 8, C, D, - UPSCALE TRIP S4A, 8 - BYPASS SWITCH NOTE: CONTACTS ALSO SHOWN IN NORMAL OPERATION POSITION
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r-I I I r---"--~ I LP~S I I.............,.""" I I~ 1, APRM I A I I ------ I KIB LI Kl 3 14 I ___ _J r----7 I I I KlB I ~ I I 91 Kl8 I I I L _____ _J 17 LPRM'S APRM C 3 )1(14
- K3
- =Kl8
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- KI8 17 LPRM'S APRM E
14
- FK3
=t=Kl8 'I,
- KlB 14 LPRM'S APRM B
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- = Kla 1,...
=;=Kl8 =;FKJ 'I, 14 LPRM'S APRM D t kl8 =;::Kl8 =:.FK3 'I, 14 LPRM'S APRM F =;=KlS =;::: KIB --------------------"""I,_ _________________ ___,/ v LEGEND S3A, S4A - BYPASS SWITCH TO REACTOR PROCTION SYSTEM Kl - UPSCALE TRIP K3 - DOWNSCALE TRIP Kl4 - INOPERATIVE TRIP NOTE: CONTACTS ARE SHOWN IN NORMAL OPERATION POSITION
MONORAIL MOUNTED HOIST LOADED SERVI CE PLATFORM HOIST LOADED NOT ALL RODS IN REFUELING PLATFORM NEAR OR OVER CORE STOP FUEL GRAPPLE OPERATION FRAME MOUNTED HOIST LOADED NOT ALL RODS IN SELECTION OF SECOND ROD MODE SWITCH IN "REFUEL" NOT ALL RODS IN I SERVICE PLATFORM HOIST LOADED I I STOP SERVICE PLATFORM HOIST OPERATION FUEL GRAPPLE LOADED REFUELING PLATFORM NEAR OR OVER CORE ROD BLOCK FRAME MOUNTED HOIST LOADED NOT ALL RODS IN REFUELING PLATFORM NEAR OR OVER CORE STOP FRAME MOUNTED HOIST OPERATION FUEL GRAPPLE NOT FULLY UP REFUELING PLATFORM NEAR OR OVER CORE MONORAIL MOUNTED HOIST LOADED SERVICE PLATFORM HOIST LOADED MODE SWITCH IN "STARTUP" MONORAIL MOUNTED HOIST LOADED NOT ALL RODS IN REFUELING PLATFORM NEAR OR OVER CORE STOP MONORAIL MOUNTED HOIST OPERATION FRAME MOUNTED HOIST LOADED REFUELING PLATFORM NEAR OR OVER CORE MODE SWITCH IN "STARTUP" NOTE: FUEL GRAPPLE LOADED NOT ALL ROOS IN REFUELING PLATFORM NEAR OR OVER CORE STOP REFUELING PLATFORM TRAVEL TOWARD CORE FUEL GRAPPLE NOT FULLY UP MORE THAN ONE ROD WITHDRAWN REFUELING PLATFORM NEAR OR OVER CORE MODE SWITCH "IN REFUEL" "LOADED" IS DEFINED AS SLIGHTLY LESS THAN THE PRE-MEASURED AVERAGE WEIGHT OF ONE FUEL ASSEMBLY Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Refueling Interlocks Figure VII-6-1
ll:: W 0 ll:: l -ci:O*
- ioD::
cll::1-V> >< w ~> ,z o..o <lu ll:: W 0 ll:: l -ci:O*
- ioD::
cD::1-V> u< ~ 0.. UC WO ll::.J w 3: > Oz .Jo u..u ~ ll:: 0.. u.. o o_ I-(!l ll:: W 0 ll:: I-I- -ci:O*
- ioD::
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- n11::,3~
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O'll::1-V> >< w Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) REM Flow Variance Circuit Schematic Figure VII-7-2
51 xx xx 47 xx xx xx xx 43 xx xx xx xx xx 39 xx xx xx xx xx 35 xx xx xx xx xx xx 31 xx xx xx xx xx xx 27 xx xx xx xx xx xx 23 xx xx xx xx xx xx 19 xx xx xx xx xx xx 15 xx xx xx xx xx 11 xx xx xx xx xx 07 xx xx xx xx 03 xx xx 02 06 10 14 18 22 xx xx xx xx xx xx xx xx xx xx xx xx xx 26 xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx 30 34 38 42 46 50 Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Typical Process Computer Printout Figure VII-7-4
t REACTOR CADD FILE: C0026412 MANUAL TURBINE CONTROL MECH. PRES. ADMISSION VALVE INITIAL PRESSURE REGULATOR TURBINE BYPASS VALVES '======= COND. M - INDUCTION MOTOR G - AC GENERATOR C -ADJUSTABLE SPEED COUPLING ~ RECIRCULATION FLOW CONTROL COMPONENTS Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFEn' ANALYSIS REPORT (USAR) RECIRCULATION FLOW CONTROL ILLUSTRATION FIGURE VII-9-1 04/22/02
RECBRC M-G SETA Div. I LOW LEVEL LOW LEVEL FIELD BKR TRIP COILS Div. II HI PRESS J LOW LEVEL HI PRESS Hi PRESS LOW LEVEL LOGIC 2/2 REACTOR VESSEi. FIELD BKR TRIP COILS REC!RC M-G SETB Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Recirculation Pump Trip (RPT) Logic Configuration Figure VII-9-4 07/22/90
CADD FILE: C0073626 HVAC EXHAUST DUCT FLOW DUAL FILTER FLOW TRANS/FIS PUMP INLET A B DUAL FILTER FLOW TRANS/FIS PUMP OUTLET SQRT FR FQ CNTR r------------------- ------------------, I I I I I I I I '-----+------+--------' 1'--lMPF BLDG VENT MON EXHAUST FLOW TO 1 SYS LO FLO/TRBL PMIS 1 L ______ _ I I I I 1 MPF BLDG VENT MON I
7
~~ I '-------' I I I I I I I OO~Q~ L--------------------------------------J Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) MPF VENTILATION MONITORING SYSTEM FIGURE Vll-12-2 02/22/07
CONVEYOR CONVEYOR QQQ (YELLOW) (BLUE) ( RED) POT. ~~~~~c:801 c:82 q) 3 (I) (2) (3) (4) (5) c:8 4 q) 5 CONTROL ROOM ---AT ARW DRUM HANDLING CONTROL ROOM ~--BELL ~---YELLOW LIGH ~-- BLUE LIGHT --- RED LIGHT PROBE INDICATOR ABOVE CONTROL ROOM ( PROBE STATIONS l THRU 5) LOCATED IN DRUM HANDLING Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Area Radiation Monitoring System Figure VII-13-2}}