ML23129A304
| ML23129A304 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 04/20/2023 |
| From: | Nebraska Public Power District (NPPD) |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML23129A261 | List:
|
| References | |
| NLS2023022 | |
| Download: ML23129A304 (1) | |
Text
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~:J:.......>o G - AC GENERATOR Nebraska Public Power District C - ADJUSTABLE SPEED COUPLING COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT {USAR)
Single-Cycle-BWR Control System (Flow Control Section) Functional Control Diagram Figure VII-1-2 CADD FILE: C0045079 04/22/02
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IA 11 11 11 11 I40A 1408 CH.A CH.B SCRAM SCRAM B.UP
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(I) CONTAINS 3 SIGNALS, MAY BE RUN IN SAME CONDUIT.
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(2) MAY BE RUN IN SAME CONDUIT. SCRAM SOL'S. TYP. FOR 127 RODS ('3) FOR EACH ROD, MAY BE RUN IN SAME CONDUIT. (4) MAY BE RUN IN SAME CONDUIT FOR EACH VALVE. LEGEND Nebraska Public Power District COOPER NUCLEAR STATION s------i SCRAM SIGNAL OTHER THAN APRM. UPDATED SAFETY ANALYSIS REPORT (USAR) APRM SYSTEM 0 INDICATES ONLY ONE SENSOR PER
-s-PARAMETER. MAY INDICATE ONE OR MORE PARAMETERS. (SEE TABLES II SDI) Reactor Protection System S INDICATES SEPARATION Scram Trip Circuits Figure VII-1-3
PROCESS TAP PROCESS TAP SENSORS SENSORS DIV. I TRAY DIV. I[ TRAY et: w ~ 0 uJ ....0
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0 TO SYSTEM A" PUMPS Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) ESF Separation Concept Figure VII-1-4 1/23/01
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CONT. DIV. I DIV. U CONT. 1 1 INB D. POWER POWER OUTB D. OUTBOARD VALVE 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 NEUTRON MONITORING INSTRUMENT TRIPS FOR A E TURB STOP INITIAL FUEL C G LOADING ONLY VALVE CLOSURE A TURBINE CONTROL A BYPASS C VALVE FAST CLOSURE DISCHARGE I A VOLUME HIGH A BYPASS C C MODE } SHUTDOWN WATER LEVEL SWITCH MODE (OPEN IN AUTOMATIC MAIN STM SHUTDOWN) RESET A LINE E A BYPASS C G C ISO VALVE A PRIMARY CONTAINMENT C HIGH PRESSURE A NUCLEAR SYSTEM A MANUAL C HIGH PRESSURE SCRAM A REACTOR LOW C WATER LEVEL C A} NEUTRON MONITORING SYSTEM E G REACTOR PROTECTION SYSTEM REACTOR PROTECTION SYSTEM REACTOR PROTECTION SYSTEM LOGIC LOGIC LOGIC A1 A2 A3 Nebraska Public Power District COOPEJR NUCLEAR STATION NOTE: CONTACTS SHOWN IN NORMAL CONDITION UPDATED SAFETY ANALYSIS REPORT (USAR) Schematic Diagram of Logics in One Trip System Figure VII-2-3 07/22/94 CADD FILE: C00l 4194
LOGIC LOGIC LOGIC LOGIC LOGIC LOGIC Al A2 A3 Bl B2 B3 EAl CAz GA2 AA3 CA3 Bs1 FBl Ds2 Hs2 Bs3 Ds3 A"l ACTUATOR LOGICS ASSOCIATED ACTUATOR LOGICS ASSOCIATED WTH TRIP SYSTEM A WITH TRIP SYSTEM B c>ij Cf) u AA! EA! EA! AA! Ds2 HB2 Hs2 ~ 0s2 (") *>-3
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NEUTRON MONITORING SYSTEM TRIP CHANNELS IRM LPRM LPRM DETECTOR DETECTOR 1other detectors 1 DETECTOR NEUTRON AMPLIFIER AMPLIFIER MONITOR* AMPLIFIER 1LPRM1 1LPRM1 ING SYSTEM AMPLI Fl ER-SUMMER A (APRM) BYPASS UPSCALE TRIP A A INOP UPSCALE TRIP IRM CH ANN EL A ione of e1ght1 A A I\ E E E MODE SW IRM IRM IN RUN BYPASS INOP A A E E E REACTOR IRM APRM PROTECTION UPSCALE DOWN-SYSTEM TRIP ' SCI\LE A APRr,i E A INOP 1\PRM BY PASS A E 1\PRM UPSCALE TRIP 0 NEUTRON MONITORING SYSTEM LOGICS 1 two of e1ghtr NOTE CO~TAL'TS c;,;fJ\'.', l'J rJQJi!,\,~I ClJNUITICl': i-i:.,ACT Jfi f'RJTECTILHI SYSTEtA 1 LOGlf' 011p ,.r 10 1:,
- 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
CNS
--,~ * -~ IRM CHANNELS IRM CHANNELS ' C, G(0, HJ A, E (B, F) PERMISSIVE PERMISSIVE 1-.-1-------- ---~---
PERMISSIVE _ WHEN REACTOR WHEN AUTO E . AUTO SIGNAL WHEN REACTOR MODE SWITCH IN MOOE SWITCH IN SIGNAL NOT RUN POSITION I RUN POSITION PRESENT 0 I UPSCALE TRIP ON LEVEL 0 UPSCALE TRIP ON LEVEL
~ TRIP ON INSTRUMENT INOPERATIVE 0 TRIP ON INSTRUMENT INOPERATIVE PERMISSIVE AUTO PERMISSIVE WHEN AUTO SIGNAL WHEN AUTO SIGN~L NOT SIGNAL NOT PRESENT PRESENT C C APRM CHANNELS A, E(B, F) C, EID, B)
L PERMISSIVE AUTO AUTO PERMISSIVE WHEN AUTO SIGNAL SIGNAL WHEN AUTO SIGNAL NOT SIGNAL NOT _,_j 0 PRESENT
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OOE OF TWO NEUTRON MONITORING SYSTEM ONE OF TWO NEUTRON MONITORING SYSTEM LOGICS LOGICS ASSOCIATED WITH REACTOR PROTECTION ASSOCIATED WITH REACTOR PROTECTION SYSTEM
~STEM LOGIC Al 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
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TRIP SYSTEM A TRIP SYSTEM B POWER POWER BUS BUS CHANNELS TRIP SYSTEM A TRIP SYSTEM B
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NOTE: CONTACTS SHOWN IN NORMAL CONDITION Al A2 Bl B2 REACTOR PROTECTION SYSTEM LOGICS TYPICAL CONFIGURATION FOR: SCRAM DISCHARGE VOLUME HIGH WATER LEVEL PRIMARY CONTAINMENT HIGH PRESSURE TURBINE CONTROL VALVE FAST CLOSURE NUCLEAR SYSTEM HIGH PRESSURE REACTOR VESSEL LOW WATER LEVEL 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
F022A(l) F022Ar2l F022B(l) F022B(2) ! F022C (1) F022C (2) F0220( 1l F022D(2l F028A(l) F028A(21 F028B11 l F028B(2) # F028C (1) F028C (2) F0280(1) F028Di 21 AC POWER AC POWER I (MOTOR- !MOTOR GENERATOR GENERATOR SET Al A B H SET Bl rlc I{" *
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STEAM STEAM STEAM STEAM STEAM STEAM l STEAM LINE B STEAM LINED LINE A LINE B LINE C LINE D LINE A LINE C MAIN STEAM LINE ISOLATION CHANNELS (SWITCH CONTACTS SHOWN IN POSITIONS WHEN ISOLATION VALVES LESS TH.AN 10°0 CLOSED) TRIP SYSTEM A TRIP SYSTEM B C
'"tJ u STEAM STEAM] STEAM t-3 *>-3 STEAM { A E ..,..} STEb.M STEAM{ C * }STEAM STEAM{ z. B F D H
'-<: LINE A ,,,_ LINE B LINE C G""'- LINED LI NE LINED trj } LINE C LINE C/l 'd }
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N* 54 ft O in. TE-13-77D TS-13-82D TS-13-828 RCIC PUMP A.HD TURBINE TS-13-79A TS-13-79C TS-13-818 TE-13-77C TS-13-810 TS-13-80A - TS-13-808 TS-13-SOC- TS-13-SOD TS-13-790 TS-13-798 51/tOin. TE-13-77A TS-13-81A - TS-13-81C -
<t_ RPV 13 ft O in. ---1-d>-<""'--- 44 ft O in. ----I 49ftOin.
TE-23-1058 ~ I TS-2l-101B"-. ) TE lOSC TS-23-103C TS-23-104C TS-23-1028 40 It O In. TS-23-1038 TS-23-1040 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 ft O in.
PIPE TUNNEL
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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
9H' K9 (IND $W'S TYP) 9I K9 RESET 120 VAC I )K?A K?C LOGIC PAIR CONTROL SWITCHES 125 voe K78 CONTROL SWITCHES AC SOLENOIDS DC SOLENOIDS INBOARD MSIV 9I 9I K10 K10 RESET RESET (IND SW'S TYP) K?A K?B 120 VAC CONTROL 125 voe CONTROL K7C SWITCHES K7D SWITCHES AC SOLENOIDS DC SOLENOIDS OUTBOARD MSIV
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FUSE FUSE STEAM LINE LP ~ RUN SW LOW CONDENSER VACUUM SWITCH I REACTOR h~6A-S17C LOW WTR I } MAIN STEAM LINE BREAK TRIP CHANNEL A-2
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K7C K19C Nebraska Public Power District COOPER NUCLEAR STATION 1YPE FOR TRIP CHANNELS A-1, A-2, 81 & 82 UPDATED SAFETY ANALYSIS REPORT (USAR) TRIP CH A2 SHOWN
,. A1 USES K7A
" 81 USES K7B Main Steam Power Supply and Logic
" 82 USES K7D Figure VIl-3-5 1/23/01 CADD FILE, C0014I95
REACTOR VESSEL SUCTION SUCTION VALVE A VALVE B PUMPA PUMP B DISCHARGE VALVE B L-{X}- _ * - B
- *~ LPCI ~A - .- . - ~
INJECTION J INJECTION '---------'- VALVE A VP..LVE B Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) LPCI Component Arrangement Figure VII-4-9 08/14/00
l LWL I IT LWL 1 I
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DEC]S]ON MAK]NG LOG]C (TRIP SYSTEM LOGIC) d-c BUS LWL LWL I T I HDP'.I ~DP f I j L _____ =l HPCl TRJP SYSTEM ACTUATlON LOG JC (1) V 2 7 7 Z 7 7 Z Z Z 7 Z 7 7 7 Z 2 7 2 7 Z Z 2 7 Z 2 7 7 7 7 7 Z Z 2 7 7 Z Z 7 2 7 Z 2 7 Z Z 7 Z Z 7 7 Z 7 Z Z Z Z Z Z Z 2 2 Z 7 7 7 7 Z Z Z Z Z 2 Zt l d-c BUS LPCJPT~~~TCSP ILWL ILwL PERMJSSJVE LPCJP
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T_ . _ J_LWL CSP TlMERI TlMER ADS TRJP SYSTEM ACTUATION LOGJC (1) V V 7 7 7 7 Z 7 7 7 7 Z 7 2 7 7 2 7 2 Z Z 2 Z 2 Z 2 Z 7 7 7 2 7 7 7 7 7 7 7 7 Z 7 2 2 Z Z Z Z Z Z Z I 7 7 7 Z Z Z Z I Z Z Z Z Z Z 2 7 7 7 7 7 7 7 7 71 tI 1 1 IHOP$==~ I -_ - T DEC]S]ON MAKJNG LOG]C 1 LWL LWL (TRIP SYSTEM LOGIC)
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I 11 d-c BUS LWL LWL I HDP¥ _HDP I ___,_j_ _ _ _ _<:~_AC_T_U_AT_E_LP_C_f= ___ tic~ ACTUAT? LPC! LPCl TRJP SYSTEM ACTUATION LOGJC (2) i==if: V V 7 7 7 7 7 Z 7 7 7 2 Z 7 2 2 2 2 2 2 2 Z 7 7 7 Z 2 2 Z 2 2 7 7 2 7 7 7 7 2 2 2 2 Z Z Z 7 2 7 7 7 2 7 7 7 2 7 7 7 7 7 7 7 I 7 7 7 7 7 7 7 7 7 2 7 /I l d-c BUS LWL I IT LWL I I
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DEC]SION MAKING LOGIC (TRIP SYSTEM LOGIC) I II IDP'.I _!_IDP I LWL LWLI j 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 Nebraska Public Power District CSP - ONE CORE SPRAY PUMP RUNNJNG COOPER NUCLEAR STATION LPCJP - ONE LPCl PUMP RUNNING UPDATED SAFETY ANALYSIS REPORT (USAR) RLP - REACTOR LOW PRESSURE TYPJCAL EMERGENCY CORE COOUNG SYSTEM (ECCS) INSTRUMENTATJON FIGURE Vll-4-10 CADD FILE: C00l 7889 05/07/04
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Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Detector Drive System Figure Vll-5-2a
TO SCAL"ER OPERATIONAL OPERATIONAL AMPUFIER NO. l 1"""""'" ro.,,.,,., AMPLI Fl ER NO. 2 0~ ~GUNTER ,....._I_____.._ PULSE Sl LOG ET ECTOR : PRE-AMPLIFIER 10 ? \l 105 INTEGRATOR CPS I I CPS
-15V I SIGNAL 1 GEN ERATOR LOCAL PERIOD METER REMOTE DETECTOR DRIVE PERIOD
} RECORDER
..,..REMOTE REMO TE BIOLOGI L SHIELD RIVE SHAFT LOCAL LAMP PERIOD METER
*} TRIP F l TRIP F ,________
OijTPUT PERIOD L------~ (") LOCAL LAMP z (/l TRIP RESET TRIP E
'} OUTPUT C: TRIPE UPSCALE (Hi-Hli "O _~_,ro*,"~ L - - - - - - ~. - - - - - - LEVEL t:I LOCAL LAMP TRIP D
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X SRM System Detector Locations - 4
.& Design Neutron Source Locations - 5
- 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
OPERATIONAL AMPLIFIER REACTOR CONTAINMENT r-c.:H~BER AMPLIFIER MEAN VOLTAGE INVERTER SQUARE OPERATE ANO ANO m~ETECTOR PRE AMPLIFIER ANALOG CALIBRATE SWITCH II ATTENUATOR LOCAL LOW LEVEL MET}R REMOTE HIGH LEVEL RECORDER CALIBRATE AND DETECTOR DRIVE DIODE LOGIC UNIT COM
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@ 1------
L OCAL LAMP REMOTE
>rj DRIVE CONTROL TRIP C OUTPUT UPSCALE TRIP C
§
§ t:!Oz
..,_______ } (HI) ALARM ON LEVEL 0 w Oro rt ::i,-Oo" LOCAL LAMP I-'* >-rj "'O '"' +15 -15
>rj 0 t_:rj t_:rj g; TRIP B OUTPUT DOWN*
,..;ipj:,;- TRIP B ,__ } SCALE ALARM ON LEVEL I-'* ::i ______
IJQ H Pl ~ +ZOV +15V
>< z ~
8 ~ r' -24V -ZOV VOLTAGE L....:.ill'. H.V. LOCAL LAMP
>C~ PRE-REGULATOR COM POWER SUPPLY (D td COM COM REGULATOR I n r' zo2'.
>t""'" TRIP A OUTPUT
.q ::r 0 t"' t_:rj (") TRIP A H Pl 0 OPERATE ANO 1 - - - - - - , . . . } INSTRUMENT INOPERATIVE
>-<:>"'O REF H ::l ;,,' CALIBRATE SWITCH I ::l ~~~
V, (D t::I wwro I r' I-'* pj--:i; MODULE
°' Pl l)Q trJ~ oo* INTERLOCKS ri "'O .... e-t-Pl o~z(") o ::S-El ...;i ,....
0 H1 cw E.?
TYPICAL INTERMEDIATE RANGE ;v10NITORL:G svsTE" ( IRM) CCY'..S 'I'OP VL~*T oo C (\J...:: \D a: C :-, ..::r '-l:.::: C' C'J...:.; *,:; :_:c C 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
~N
~~
51
~~ ~~
49 47 45 43
~ N:: N~ ~ N: N' ~ N~ ~~
41 ~~ '\ ~~ ~~ ~~ -~ ~ ~~
) I
- 39 37
~~ ~~ ~~ ~~ ~~ ~~
35
~ ~ ~~ '- ~ ~ ~~ ~~ ~~
33 l 31 29 - - 27 - ~~ ~ N: ~~ ~ N: ~ N: ~ N 25 - ~~ ~~ Iii ~ ~ '\, ~~ ~~ ~~ 23
~
"' ,,J 21 -
19 - ~
~~
N: ~ (\'
~~
~ N:
~~
~ N:
~~
~~
~~
~ ~
~ ~
17
, 1-.
15 I/ 13
~~ ~~ ~~ ~~ ~~ ~~
11
~ ~
. ~~ ~~ ;<;;; ~ ~
~~ ~~
09
~-
~~
07 05
~ ~~
03 I I I I I I I I I I---
~~ ~~
01 X +
+
IRM DETECTOR, TRIP SYSTEM A NEXT CONTROL ROD WITHDRAWN IN SEQUENCE
- IRM DETECTOR, TRIP SYSTEM B CONTROL ROD WITHDRAWN OUT OF SEQUENCE
,$ CONTROL ROD WITHDRAWN @ IRM DETECTOR BYPASSED Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Control Rod Withdrawal Error Figure VII-5-8
100 ,-------,------,-----,-------r------i-----,----, 50 10 1.0 X w..
- LJ.l
~
0:: 0.5 0 z 0.10 0.05 0.01 -10 -5 10 15 20 25 FUEL BUNDLES 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 m=- 49 47 45 43 41 39 37 35
-~
r"'""' I l 33
~
31
+
29 = 27 - 25 - 23 ' 21 19 17 15 -~ I 1 tH 13 11 1-1 09 07 05 II 03 I I I I I I l I I I 01 I 8 N""3"WC:0 0000 ONQ" l.0COON,q,WCOO
,-.-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
3 CHANNEL A 2 0:: -= UJ 0 1 Q.. UJ 0:: I- 0
- E 0
0:: u... z: E -1 ~ s: UJ C Cl I- -2 z: UJ (.) 0:: UJ Q.. -3
-4 1.0 0 0.2 0.4 0.6 0.8 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: Assignmen t 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 $
+1+1+1+1~
10 09 - - 0801 06 05 -"'81111r......___~ 04 0 3 --+-+--+--lf --+--1-- 02 01 -4~-f- +--i--+--t -l!-"-........~...,....---.,.-:-..,.....!---f ON~~~O~A~ncN-~~ON~~~CNA~~cu OOOOOrlrlrlrlrlNNN~~M MMMMAAA=A~~ rlM~~~rlM~~arlM~~~rlM~~a~M~~~rl OOOOOrlrlrlrlrlNNNN~MMMMMAAAA~~ //1RBM Automatic ally 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)
Assignmen t of LPRM Assemblie s 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 0 0 0 0 0 C' C:\ ...: ,..;; .;_; C C\J ..::r *..:; CC C (',
~ ~ ~ .--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~~MM MMMJ..:r..::r..::r...:r~ Lette r= TIP Machine Assign ed to LPRM String Nebrask a Public Power District COOPE R NUCLEAR STATIO N UPDAT ED SAFETY ANALYSIS REPOR T (USAR) Assign ment of LPRM String s to TIP Machin es Figure VII 18
REACTOR CORE CROSS CALIBRATION r--, - INDEXING MECHANISM I I CONTAINMENT CONTAINMENT PENETRATION PENETRATION I 1-----
'I BALL VALVE VALVE
~--- SHEAR VALVE I I TO PURGE SYSTEM ~--- CHAMBER SHIELD I I 1 I ~-- DRIVE I MECHANISM 1 I L_, - - _J Nebraska Public Power District ELECTRICAL SIGNALS COOPER NUCLEAR STATION (TO CONTROL ROOM) UPDATED SAFETY ANALYSIS REPORT (USAR) Traversing In-Core Probe Subsystem Block Diagram Figure VII-5-19
SRM IRM LPRM APRM OPERATION 1014
-~d l -~ .
T I- 100 c...:> a::: I-LL.J 0:: 1013 p 0::
. 10 t
LL.J
~
0.. T - 1012 ,_ c.::, z: I-
> 0 <
C: I- LL.J 1011 ::c
- 0.1 c...:>
X < 0::
- > I-
...J u.. LL.J 0:: z: 0 0:: I-10 10
- > p LL.J z: .01 0:::
i-, LU ...J
~
0.. 0:: I-LL.J
- c z:
10 9 . 10- 3 I- LU c...:> LL.J c.::, 0::: 0:: LU 0.. LL.J < 0..
-~
I-0:: 108 < p I-V, 10-4 Cl LL.J
,_ I-0::
LL.J V,
~
...J
...J u..
. 10-6 '
SOURCE* Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Ranges of Neutron Monitoring System Figure VII-5-23
BUS A 24VDC BUS B 24VDC S4A 1 -7 I I I I v., v., v., (/) v., v., v., v., O<l ~ I u ol!l~ O<l ~ O<l~ O<l ~ v., I O<l ~ O<l ~ 0:: z: 0:: z: _J 0:: z: 0:: z: 0:: z: 0:: z: 0:: z: 00 O<l z: 00 00 00 v., 0:: w I 0:: ~ 00 00 v., 0:: 00 v., 0:: v., 0:: v., 0:: z: v., 0:: v., 0:: z: f- z:f-z: Of-v., u I z: f- z: f- z: f- z: f- z: f- w (_) wU
<t:
I wU wU wu w (_) wu v., w v., w
~w v., w v., w v., w _J v., w v., w _J _J
- r: _J _J _J _J u V) j I w w w w w I w w I
I A C I I I E I I I G B D F I I I H I I I I I I Kl28 lKl B ]K48 Kl2B lKlB ]K48 4C Kl2D lKlD lK4D Kl2D ]KlD ]K4D Kl2A I 4A J Kl2A lKlA ]K4A L __ J r-3 C: .r-----,
>-cl
'-<: I
~ '"CJ. v I (1) I-'* I =#=KlD I =#=KlD Pl o ~
trl KlA I o Pl _L _L I'IB _L I'!B _L IK!C _L ~K!C rt I-' 0 onz w.Oco ul Kl2A gj I TK12A IK!A TK128 TK128 TK12C TK12C _J I-! H >0~ K4A K48 K48 K4C ?f= K4C I 7f=K4D I =n:=K4D
>zj'i::11)) K4A I 'rj >tj ~ I I-'* I-!
t.:ritrl"' C)Q O (") >-3 ;,j s I i:: rt I-'* ><: z >-cl I I-! (1) I-! C:::i:o (1) () () *zog: I I rt i::
<: I-'* I-'* >t-<n* L ____ J HO rt t"' M >-cl I __________________________;
H:::J ><:>o . \ I w ;,.,~ Vl (J) I-!
* ...... TO REACTOR PROftCTION SYSTEM I '-<: I-! w wco >-3..; LEGEND: KlA. 8, C, D - INOPERATIVE TRIP N 00 Pl
..,.. rt :::J s:J > >-300S?. K4A. 8, C, D, - UPSCALE TRIP (1) C)Q >,:;I....., ff S4A, 8 - BYPASS SWITCH
!:l (1) OOn*
!:l ;,j z ,+ I H (1) >-3
- J :::J NOTE: CONTACTS ALSO SHOWN IN NORMAL OPERATION POSITION
'"CJ rt i::
cw rt H. 0 I-! c*
r- --, I I I r---"--~ I 17 17 14 14 14
- LP~S I LPRM'S LPRM'S LPRM'S LPRM'S LPRM'S V, I .............,.""" I
_J UJ z: z:
<C
- c (J
I ~. . . . . . : 1, APRM I APRM APRM APRM APRM APRM C E B D F A I I ------ I KIB LI Kl 3 14 I 3 )1(14 14 _ _ _ _J r----7 rl C
',j I I
'"d u I ::;::K3 ::;=Kl8 ::;FK3 TK3 ::::;::= Kla =;FKJ t kl8 =:.FK3 =;=KlS
~ f-'*
I KlB =t=Kl8 (D (l *--3 Pl Pl t_Tj ~ I I () I-' uoz . .. rt m0ro 91 Kl8 I 'I .... :::;::KI8 'I, ::;::KlB 1, ... =;=Kl8 'I, =;::Kl8 'I, =;::: KIB g ?;; *"lj ',j0 piO"' t_Tj t_Tj u., I I rrj '1j ~ f-'* r! --3~~ ' L _____ _J (jQ O (J ><: z ',j i:: rt f-'* r! (D r! C~ (D (l (l
*zog:
rt i:: r;:;*
<! f-'* f-'* --------------------"""I ,_ ____________________,/
*rtrl',j HO rt v H :;:l
>-<:
- o
~~:!:
LEGEND S3A, S4A - BYPASS SWITCH I lJ> [/). [/). ~ Kl - UPSCALE TRIP
\J1 (/) r! TO REACTOR PROCTION SYSTEM I '-<: r! ~--30 K3 - DOWNSCALE TRIP N Ul Pl t_Tj *,.... \J1 rt ::l ',j --3 u., Kl4 - INOPERATIVE TRIP H~
(D 00 00,...* i::l ~ ~z~ NOTE: CONTACTS ARE SHOWN IN NORMAL OPERATION POSITION H (D --3
- l ::l
'"d rt 2[/).
i:: rt Mi 0 I r! cl
MONORAIL MOUNTED FUEL GRAPPLE HOIST LOADED FRAME MOUNTED FUEL GRAPPLE MONORAIL MOUNTED FRAME MOUNTED HOIST LOADED LOADED NOT FULLY UP FUEL GRAPPLE FUEL GRAPPLE HOIST LOADED HOIST LOADED LOADED NOT FULLY UP NOT ALL RODS IN SERVI CE PLATFORM REFUELING REFUELING SELECTION OF PLATFORM NEAR SERVICE PLATFORM REFUELING HOIST LOADED SECOND ROD PLATFORM NEAR PLATFORM NEAR MORE THAN ONE OR OVER CORE OR OVER CORE HOIST LOADED NOT ALL ROOS IN OR OVER CORE ROD WITHDRAWN MODE SWITCH MODE SWITCH REFUELING IN "REFUEL" IN "STARTUP" PLATFORM NEAR OR OVER CORE ROD BLOCK REFUELING MODE SWITCH PLATFORM NEAR MODE SWITCH IN "STARTUP" "IN REFUEL" OR OVER CORE FRAME MOUNTED MONORAIL MOUNTED STOP REFUELING HOIST LOADED HOIST LOADED PLATFORM TRAVEL TOWARD CORE NOT ALL RODS IN NOT ALL RODS IN NOT ALL RODS IN NOT ALL RODS IN NOTE: I "LOADED" IS DEFINED AS SLIGHTLY LESS THAN THE PRE-MEASURED AVERAGE WEIGHT OF ONE FUEL ASSEMBLY REFUELING SERVICE PLATFORM REFUELING REFUELING PLATFORM NEAR PLATFORM NEAR PLATFORM NEAR HOIST LOADED OR OVER CORE OR OVER CORE OR OVER CORE I I STOP FUEL STOP SERVICE STOP FRAME Nebraska Public Power District STOP MONORAIL COOPER NUCLEAR STATION GRAPPLE PLATFORM HOIST MOUNTED HOIST MOUNTED HOIST OPERATION UPDATED SAFETY ANALYSIS REPORT (USAR) OPERATION OPERATION OPERATION Refueling Interlocks Figure VII-6-1
~
ll:: 0.. u.. o o_ I- (!l 3: Oz
.Jo u..u ll:: ll:: ll:: ll::
W 0 W 0 W 0 w 0 ll:: l ll:: l ll:: I- I- ll:: 1 -ci:O* -ci:O* -ci:O* <O*
- ioD:: ::ioD:: ::ioD:: ::ioD::
cll::1- cD::1- cD::1- O'll::1-
>< >< V> >< V> ><
V> w V> w w w
~>
,z o..o
<lu 8 d007 u< *:n11::,3~
~ 0..
UC WO ll:: .J Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) REM Flow Variance Circuit Schematic Figure VII- 7-2
51 xx xx xx xx xx 47 xx xx xx xx xx xx xx xx xx 43 xx xx xx xx xx xx xx xx xx xx xx 39 xx xx xx xx xx xx xx xx xx xx xx 35 xx xx xx xx xx xx xx xx xx xx xx xx xx 31 xx xx xx xx xx xx xx xx xx xx xx xx xx 27 xx xx xx xx xx xx xx xx xx xx xx xx xx 23 xx xx xx xx xx xx xx xx xx xx xx xx xx 19 xx xx xx xx xx xx xx xx xx xx xx xx xx 15 xx xx xx xx xx xx xx xx xx xx xx 11 xx xx xx xx xx xx xx xx xx xx xx 07 xx xx xx xx xx xx xx xx xx 03 xx xx xx xx xx 02 06 10 14 18 22 26 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
TURBINE CONTROL MECH.
-- PRES.
ADMISSION VALVE INITIAL PRESSURE REGULATOR t MANUAL TURBINE BYPASS VALVES REACTOR
'======= 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 CADD FILE: C0026412
Div. I Div. II LOW LEVEL HI PRESS J LOW LEVEL HI PRESS LOW LEVEL Hi PRESS LOW LEVEL REC!RC RECBRC M-G M-G SETB SETA LOGIC 2/2 FIELD BKR FIELD BKR TRIP COILS TRIP COILS REACTOR VESSEi. Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR) Recircu lation Pump Trip (RPT) Logic Configu ration Figure VII-9-4 07/22/90
HVAC EXHAUST DUCT FLOW INLET OUTLET SQRT DUAL DUAL FILTER FILTER FR FQ FLOW FLOW TRANS/FIS TRANS/FIS CNTR A B r------------------- ------------------,I PUMP PUMP I I I I I 1
'-----+------+--------'
'--lMPF BLDG VENT MON EXHAUST FLOW TO :
I 1 SYS LO FLO/TRBL PMIS 1 I I _______ I L ______ _ I I
----7 :
1 MPF BLDG VENT MON I
~~
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 CADD FILE: C0073626
QQQ - - - A T ARW DRUM HANDLING CONTROL ROOM (YELLOW) (BLUE) ( RED) POT.
~~~~~c:801 c:82 q) 3 (I) (2) (3) (4) (5) c:8 4 q) 5
~--BELL
~---YELLOW LIGH
~ - - BLUE LIGHT
- - - RED LIGHT PROBE INDICATOR CONVEYOR CONVEYOR CONTROL ROOM ABOVE CONTROL ROOM PROBE STATIONS l THRU
( LOCATED IN DRUM HANDLING
- 5) Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)
Area Radiation Monitoring System Figure VII-13-2}}