Catawba Nuclear Station UFSAR Appendix 7B. Figures Appendix 7B. Figures
Catawba Nuclear Station UFSAR Appendix 7B. Figures
Appendix 7B. Figures
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ure 7
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UALOG PROTECTION SYSTEM HUCLEAR INS"RIJMENTATIDN SYSTE~
OR f I ELD :ONTACTS
CDNTl!Oi. BOlRD SWJ TCHE:S TRAIN B
COIITR~L BOARD S-llCHES TfiAIN A
PRQT£CTI ON SY STEM TRllN B
PROTECTION SYSTE~ TRAIN A
o,m, l I NPuT
I NPuT
MASTER ANO SLIYE RELAY$
•ASTER ANO SI.AIE RELAYS
ICT~AH ----------t---~ TU IN 8 SlFEGUA~DS
IS0LHI0N
~~,- CABLE
CONUOL BOAR) MONITOR I NG
ISOLATION
CONTROL BOARD OEMLX CAB 1Nc1
1---------+-•~i~~;j~iRi~AIN A
TO ROD DIIY!: MECNAN I 5M5
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Te.IP ;,i ;>tfoYFASS 1au: !
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Catawba Nuclear Station UFSAR Figure 7-2 (Page 1 of 25)
(17 OCT 2013)
Figure 7-2. Instrumentation and Control System Diagrams - Index and Symbols
,. '---Q ni!\\,~ec~,,m
A •EVICEWHICHPOO•UCESANOUTPUT OJLYWl-£NTIEIN'UTIIIESN'.ITHIST
A •EVICEWHICHPOO•UCESONOUTPUT OJLYWl-£NE¥EaYINPUTEXISTS
A •EVICE WHICH PERMITS ON MOL•C SIGNAL r• PASS IN AN IStATISEVERY ~~l/c~~~/ll.~ti~%tnAl.\~Jf.LI~JEIN~ljgt~ LiMif~a"e"~Er ~~~f.LL INSTllJMENT CH"ff:Ls,a1ST•BLES,
~i:./~1~~M~.~faF.=,~~~tr.~i1.i"l/Jll:s0~~•~ft1:~~:8,~ ~~~"\i~1~s"l:~E~~0rim11i ,~0~1il~~ANT) 3, WHENEVER A l'l!IJCESS SIGNOI. IS USED SCA Cet/TRO. AND IS IJEIIIVEO SROO A l'l!OTECTIO~ CHMNEL,ISOL.OTIIJI MUST BE PAOVIIEl,
[F THE REACTOR CONTRtl. ONO F'AJTECTmN s•STEM.
5.THISSETCJ' • ... wINuS!Sl•ENTI""'-F
Catawba Nuclear Station UFSAR Figure 7-2 (Page 2 of 25)
(17 OCT 2013)
Instrumentation and Control System Diagrams - Index and Symbols
~::~'-.n [NPUT +
ACEVICEWltPROOUCEBANOLJTPUTONLT WHENES>'EIIV!""'1,:XIST"-
ACEV![J;Wl
ACEVICEWl
Catawba Nuclear Station UFSAR Figure 7-2 (Page 3 of 25)
(17 OCT 2013)
Instrumentation and Control System Diagrams - Index and Symbols
STEAM GENERATOR TRIP SIGNALS (SHEET 71
SAFETYINJECTIONSIGNALISHEETBI
TURBINETRIPSIGNALISHEET16l
STEAMGENERATORTRIPSIGNALSISHEET71
SAFETYINJECTI•NSIGNALISHEETBI TUR81NETRIPSJGNALISHEET161
LOGICTRA!NAREACTORTRIPSIGNALS
LDGICTRAINBREACTORTRIPSIGNALS
MANUALREACT•RTRIPSIGNALISHEET31 MANUALSAFETYINJECTIONSIGNALISHEETBI
l.TRIPPINGTHEREACT•RTRIPBREAKERS52/RTAAN052/RTBREDUNDANTLYDE-ENERGIZESTHER0D •HIVES.ALLFULLLENGTHC•NTROLRODSAN• SHUT•D\IN RODS ARE THEREBY RELE/\SE• FOR GRAVITY INSERH•N JNT• THE REACTOR CORE.
ERIC
3.ALLCIRCUITS •NTHISSHEETAREN•TRE•UN•ANTBECAUSEB•THTRAINSARESHD\IN. 4. •PEN/CLDSEDIND!CATIONFOREACHTRlPBREAKERANDEACHBY-PAS5BREAKERINCONTRDLRODM.
RODDRIVESUPPLY •NELINEDIAGRAM ® --©---~4-"-"-"-''-"'-.---~ ~~-~~E~~_;__j \ 52/RTB I) 52/BYB
Catawba Nuclear Station UFSAR Figure 7-2 (Page 4 of 25)
(17 OCT 2013)
Instrumentation and Control System Diagrams - Index and Symbols
2. I/N 33A IS IN L•ulC TRAIN A. !IN 338 IS IN LOGIC TRMN B.
3.I/N38AISINL•GICTRAINA. I/N38BISINLOGICTRAINB.
4.I/N47AISINLOGICTRAINA. I/N47BISINL•GICTRAINB.
6.MANUALRESETCONTR•LSCDNSIST •FFOURM•MENTARYCONTR•LSINTHECDNTROLR •• M. ONECONTROLFDREACHINSTRUMENTCHANNEL.
DEVEL•PEDFR•M CNM 1399.01-~024.003, REV. D9 DA CONDITION I
- , '"'-''""'"'"'""""'""'""'""·"""""""'" -••m
Catawba Nuclear Station UFSAR Figure 7-2 (Page 5 of 25)
(17 OCT 2013)
Instrumentation and Control System Diagrams - Index and Symbols
HI
Catawba Nuclear Station UFSAR Figure 7-2 (Page 6 of 25)
(17 OCT 2013)
Instrumentation and Control System Diagrams - Index and Symbols
....
IV TB
"' C cf'
__ '.~~~~~1 _________ . :::\ ____ ----------------~:~~~-~------------------OVERTEMPERATUREAT
ILrn•ILAGCOMPENSATE•I OVERPOWER AT
(LEA• /LAGCOMPENSATEDI
'---------------LO-LOT AVG--------~•---------••-••-••--- LOW T"AVG•-••-••-••-------------
P-12 ISHEET\0)
DEVELOPED FROM CNM 1399.~1-~024. 005. REV. 06
I[] TB
"' c-i_
Catawba Nuclear Station UFSAR Figure 7-2 (Page 7 of 25)
(17 OCT 2013)
PRESSURIZER LOW PRESSURE
PRESSURIZER HIGH PRESSURE
PRESSURIZER HIGH WATER LEVEL
PRESSURIZER LOW PRESSURE PRESSURIZER PRESSURE
1. IBE AE•UN•ANT l'IINUAL 11._•CK CCNTAt1 CONSISTS •F l1«l C•NTAt15 ON HE CCNTROLB•ARO, •NEF'•REACHTRAIN.
2. TW• C!M'UTER INF'UISAREC•~ECTE• TOTHISCIRCUIT, IN• IVID.JALF'~
llEYELJl .. • FRllM-LFIICTll,_8,..0. _,__.,._,_ ... _ .... QA CONDITION I lftll~-ILJ.CIR,11~•'!!': .. @
•"4:E POWER COMP~~ ruNCTIO~AL OIAGRIIMS
PRES5Ufl.lZERTRIP511JNAL5
ff[TZZ44045
Catawba Nuclear Station UFSAR Figure 7-2 (Page 8 of 25)
(17 OCT 2013)
iTE ISl
Catawba Nuclear Station UFSAR Figure 7-2 (Page 9 of 25)
(17 OCT 2013)
STE OBl
Catawba Nuclear Station UFSAR Figure 7-2 (Page 10 of 25)
(17 OCT 2013)
STEAM GENERATOR PRESSURIZER
J. 01£ M•l'EmARY comRO... PER LOCI' ON THE CONTROL BOAR•• 4. CtNTAINMENTl'RESSUREBISTAII._ESF•RSPMYACTUATIOOARE
ENEAOIZE-TO---IICTUATE!OTHERBI5TABLESAAE •E-ENEAOIZE-TO-ACTUATE.1 5. EICl...•SEO CIRCUITRY IS NOT PART (F nE SAFEOL}IR•S SYSTEM AN• 15 "'1T
&. Cc»-PONENTS ARE ALL INOIVICUALLY SEAL.EO IN ILATCHEOI. SO THAT LOSS OF THEACTUATIOOSIGNALWILLN•TCAUSETfESECOMPONENTSTDRETURNTD THE C0"'11TIO~ fELO PRIOR TO THE A•VE~T (F lfE Ac;TUATION 5lri'¥'L,
8. SERVICEw'ATERSYSTEM ISOLATIONISUSEOO~YIFREGUIREO,
9, THEREllUN[)'INTMANUALRESETC~SISTSOCTWOM•MENTARYDJNTR•LSON THE CONTROL BOAR•, ONEFOREACHTMIN,
CONTA!Nfi£NT PRESSLRE
12.ALSOCLOSESTHEBYPASSYALVEINPARALLELWITHTHE ASS•CIATE• STEAMLINEST•PVALYE,
13.LIOHT55H•UL• BEPROYl•EOINTHECONTROLRO•MFCREACH STEAM LlilE snp VALVE TD IN• ICATE WfEN TfE VALVE IS FULLTCLOSEall,FULLT •PEN.
14. THEACTUUIONMAYBE •ELAYEOA~SECUE~E• lFTHEEMEROENCY • IESELP•WERCAPAB!LlTYlSLESSTHANTfET•TALLOAllWllHALL SYSTEMSSTARTINO.TfETIME •ELAYISl,IFUSE•.MAYN•TEXCEE• THEMAK!r-1.JMSTARTINGT!r-EREOUIREMENTSFDREACHSYSTEM.
MANUAL ACTUATION FROM CONTROL BOARO
,--------------"mesas ---7 I I
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~ ~ : TITLE EAR [U::F;;:~i~~~{ttfJfJJ!~1tU~N~: Al \=1 .................. ,."""·"'"''"~" - ""' ... 7244045 ..,...,_,_....,.""""·"'"' ...... "" "-' ,,.
Catawba Nuclear Station UFSAR Figure 7-2 (Page 11 of 25)
(17 OCT 2013)
NOTES•
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OA CONDITION I
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Catawba Nuclear Station UFSAR Figure 7-2 (Page 12 of 25)
(17 OCT 2013)
-
-
-
-
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P•,~U~A~~~~~~R•N
~ I I I I I I
I I I I I I I I I I I I I ---•J . .i...L ___ L ___ .i,. ___________ ,.. ____________ _.__...i, ____________ t_,l' ____________ .i,__
CCNTRCLIL.G•RIIH" "'1sEENOTEe1c. •,..,•.;,.,.c,
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a.F•RC[NTINUATl•N,SEEN•TEa •NSHT,1. 9,FaRC[NT!NUATI•N,5EEN•TElG •NSHT,l,
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CArnwBA NUCLEAR STATION UNIT 2 FUNCTIDNAL •IAGRAMS
AODCDNTAOLS&.AODBI..OCKS
7244045 l "'-™EllFIR,Ot2F!""ll'D'ITeEFFl'CT.l-M> -...:, TLC """ > W-- -W-- V V • IMENSIONSINl~>-ES
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Catawba Nuclear Station UFSAR Figure 7-2 (Page 13 of 25)
(17 OCT 2013)
- ~----------,.~ri ..
S1EsfLE!f,1i1)~"aCK Cll~lEtJ..
I'""""''"~• ,c"',rcm,,'"'"' "':'~1\'IP LllEEN•TE!l TRAllEFllREOc:>i1""1N,
7. LIC>
Catawba Nuclear Station UFSAR Figure 7-2 (Page 14 of 25)
(17 OCT 2013)
! ,::lll!ll~'!lli. I ,si~~l~r~' Ill SEET 21
I I I I I I I I I I I I
_____ L ___ -----~-------L _______ L ___ _ 1,-''"•"'"" I "Tllrl/i,>;:'· '"If/'~,,>;:'·
STEAMOUMPC•NTROL MOOESELECTORSWITt:H
=•.1·-l·=•I
-·:'-i •~~~~cj
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:~~~ti i¥iW!~!1a Ri\•!.i k3w~ta& ----------:;p·~~ --------
1, iTEAM OOM•l61LOCICEll8YILCOl]t(;A1" TCTtt, •U'4'VALVE6 ... DYE!
Catawba Nuclear Station UFSAR Figure 7-2 (Page 15 of 25)
(17 OCT 2013)
CONTRCI. MOOE SELECTOR SWITCH
PRESSURIZER PRESSURE CH~NELS III II I
I I I
I I I I I I I I I t _______ L ______ j, _______ ,L ___________________________________ ..,i __________________________ ..,i _________ t _________ t I
L _______ ~_:;~~,~:; _________________________ ':~.::~::~ ____ -------~~t·:-: ____ ___:
1. 111.L Cl~CUITS (Jj THIS S1£ET ARE r«JT ~EllJNOANT,
2.LOCALCONTROLOVERRIDESALLOTHERSiliNALS. L.llCALOYERRIOEACTIJATESIILAlfollNCONTRCI.ROOi'I.
4.rPEN/Sft.lTHll!CATIDNINCONTROLROOM.
5. A L!(Jjl SHOL1-D BE PROYICED ™ THE CONTROL ROCl'i FCR EIICH SPRAV YIILYE TO lr«l!CATEWHENITISl«JTFULLVCLOSEO,
-----T·----r·-----r·------r-----------1 I I I I I I I I I I I
~ ,]~\~!::, ,::~~['., AUTO--MA~AL
CONTROL
(LCX:111.)
I
""':: "' ,)~~' ·;~~· ·~~1~t :~i:
CLOSE
ISOLATION
TLIIN-ON
HEATERS 191-EET 12)
1 IOLH!El,.,,.,,,..,u-o,n1nm.1+1'""' TLC i WEH i RIG.,.LEM,OFllllllt,...UP!IIT;IFF_,,.,.,,._'1 Vll1
-D•TEC>l
Catawba Nuclear Station UFSAR Figure 7-2 (Page 16 of 25)
(17 OCT 2013)
Pressurizer Heater Control
POWERAELIEFVALVE
SELECTOAS\IITCH
I I I I
PRESSURIZERLEYELCflANNELS
I UI ll
I I I I I I I
( ~;;;:;:;:.-' ..I. ':,:;;:t~;:'. I c:;;~:;,~ ..I. i 111.LORIFICE
VALVES CLOSED --------------------7---,----7----,-------
~----+---I--------~ I I I
P•WERIELIEFVALVE SELECTOOSWITCH
l.ALLCIRCUITSONTHISSHEET/lflENOTRE•UNIJANT. 2. L•CPL C•NTACJ.. •VERIUIES ALL •H£A SHlNALS.
L0CAL0VEIJl!0EACTUATESIILAllMINC0NTA0LllOC,,,.
POWEAAELIEFVAL.VE
SELECTOR SWITCH
4. OP~/SHUTIN• ICATIONINCt»JTRCJ..ROOM. 5.ALIGHTSH•ULOBEPROVIDEDINIBEC•NTR•LROOMFIJ'lEACHSPRAVVALVETO
IN•ICATEWfENITISNOTFULLYCJ..OSEO.
"' HEATERS (Sft:ET121
I I I I I I I I I I I I
CONTROL CONTROL CONTROL STATl•N STAT!~ STATION
IC•NTR•LROOMI (C~TRCl_llODl'II ICONTR•LR•CJ-1!
. TO HOOUI.Ji!E
VARIABLESPRAYVALVE >t:ATER N0.1
CONTIIOL l'CV-455B SIGNAL NC27
ISHEET121 (N•fE5l
. MODI.LATE
SPRAYVAL.VE
PCV-~55C
AUTO-MAI-UL
!LOCAL.I
IS•LATIDN (NOTE oil
TURN-ON
BACl(-UP fEATERS
~~E~S~~S·~~sf:!~~~!~ ® ~~TAI/IA UNIT fNY
Catawba Nuclear Station UFSAR Figure 7-2 (Page 17 of 25)
(17 OCT 2013)
REMOTE CONTROL ST~TION
!SELECTORSWITl:f
Catawba Nuclear Station UFSAR Figure 7-2 (Page 18 of 25)
(17 OCT 2013)
Pressurizer Heater Control
REMOTE COIITROL STAT!~
(SELECTOR SWITC>i
REl>()TE CONTROL STAT!~
ISELECTORSWITCHI
Vlll!lo'IBLEHEATER HEATERINTEFD..OCK
CHl'IRGING FLOW ISELECTOR SIIITCHI
--------;:~u::,:•;;;;;,;-·-- I FOR GROUP A fi::ATERS OH£::
1;
I LOCALlllNTR[l_STATION 7 j F~~~~g~~l~1~~~rs OTHE:j@
I _,j,,_ i
GROUPA HEATERS
@~T~~-
INOTE2l INOTE4l
QRCJJPD HEATERS
2. GROLf'AA~QROLf'DHEATERSMLllT DEONSEPERATE VITAL POWER 51.f'PLIES W'.ITH THE LOCAL CONTROL SEPERATE• SOTHATA~Sl"'LEFAILUREOCESNOTOEFEATBOTH.
~- THE NUMBER OF RACK-UP HEATER CJ10UPS IS TYPIC/11.. If£ ACT~L NJMDER OF GROUPS MAY DIFFER IEPENOINQ ON ELECTRICAL LIYIOING RECJJIREMENTS.
0. PRECAUTIONS 5HIJJLO BETAKEN TO AVOl• M'INJALHEATEROPERATWN,WHICHWIJJLO CAUSE HEATEROAMAGE. IF THE WATER LEVEL LNCO~ERS IBE HEATERS.
GROUPC fEATERS
___ _.i ___ ,
I CONTROLF:OOR!Tffl I i A~rtl~lr~oiic, ! ---r---
I I I I I I I I I
Ylll[All.E
FORCillOUPC
REMOTE CONTROL STATION
(SELECTORSWITCHI
GROUP • HEATERS
llE~TEC~IROLSTATl~
ISELECTOR SIIITCHI
GROUPE fEATERS
~~~l~!~~TS~·~~ ®
__ ,._ ~TA\IB~ UNIT lNY
PREJ~~1}1f~A.!i-Eff~R"~~~TR•L 7244045
Catawba Nuclear Station UFSAR Figure 7-2 (Page 19 of 25)
(17 OCT 2013)
________________ "_'.'_~'~'.'._\. ____________ _
~ ! i i i i i
r-------------------------------i r-------------------------------
! STEAMllENERAT•A"A i i STEAMGENERAT•R"B" ! CONTR•L:~~G•RITHM i i CONTR•L:~~G•RITHM ! AC~~tt~~T~o~,rc, j i AC~~tt~;Mo~,ic,
i ,,,,;;:1:b·"' , ••"i,I':trr • i i "''"ti:::1""' , •"i':::If, :...-------:--------------:-------' L..-------:--------------:-------
1 I I I
l--------------------~--------------~------------------=7-----~---------------:---' i I '
F11s~ftfR (SHJ~f p lBl Lll~E4°ft CLfl~LB~fr8ill~~~~ER '--IJ>(f---1 '--IJ>(f---1 '--11,(f---l '--l)>(f---1 ! IN•TES5&6) (N•TE3) I
,_ _____ NOTES, ~ MODULATE MODULATE ~ MODULATE MO•U=-T~ FEEDWATER FEE•WATER FEE• \1/ATER FEEDWATER
!.ANALOGGATECONSISTSOFTWOSOLENOIDVENTVALVESINSERIES BYPASS VALVE A MAIN VALVE A BVPASSVALVEB MAINVALVEB TD REDUNDANTLY INTERLOCK THE AIR LINE BETWEEN EACH VALVE FCV-5 !Iii (CF28) FCV-511i1A (CFJl'll FCV-521i1A (CF371 FCV-52~ ICF3SI DIAPHRAGMANDITSASSOCIATEDPOSITIDNER, THE SOLENOID VALVES !NDTE3l (N•TE3) INDTE3J (NDTE3) ~~EFl~t\~~iiIJf TO VENT, CAUSING THE FEEDWATER VALVE TO CLOSE
2. ~~lilJff&I!~Eg~Nl~~\ .. ~HEET ARE NOT REDUNDANT. EXCEPT WHERE
3. •PEN/SHUT INDICATION FOR EACH FEEDWATER VALVE IN CONTROL ROOM. 4. THE REDUNDANT MANUAL RESET CONSISTS OF TWO MOMENTARY CONTROLS
DNTHECDNTROLBOARD.ONEFDREACHTRAIN.
5. 6~J~~~~iE•~liL_~\~~ATER PUMPS CAUSES CLOSURE OF ASSOCIATED PUMP 6.THEFEE• WATERPUMPSAN• PUMP •ISCHARGEVALVESARESUPPLIE• BY
OTHERS.
7. HID l
Catawba Nuclear Station UFSAR Figure 7-2 (Page 20 of 25)
(17 OCT 2013)
-
LOOPCEk • INTERLOCK (SHEET 131
! ! ! ! ! STEAM •:::RATDR" C ! ! STEAM •:::RAT•R" • ! ! CONTROLA~~G•RITHM ! ! CONTROL ll~~GORITHM ! ! ACisutt~~T~o~,rc, ! ! AC~~tt~1fo~IIC, ! ! MrfJ0v~1Vtc BY;::~wv~I\i c ! ! M~fJ0v~1\1:Ro svt!l~wlA1L\i o ! i OEMIIND DEMAND i i DEMAND •EMANO i l,_ ______ _I _____________ _! ________ , L.. ______ _I _____________ _I-------·
I I I I I I I I
-•• -~ •-••-•• -•• -~---•-••-••-•• -~- -••-••-••-•• -•• ____ ==:"\ ____ -~- -••-••-••-••-~- I
I ,,..,t"',, I .,..,/"",, I .,..,/"",, I ....,:"",,: i ~ IC....ll IC....ll ~ :
-------------------------~ --··-r-·-----------·-r-·---------------- =----_J"-----r--------------r-_l REDUNDANT MODULATE MODULATE REDUNDANT MODULATE MODULATE
I. ANALOG GATE CONSISTS OF nm SOLENOID VENT VALVES IN SERIES TO REDUNDANTLY HflERLDCK THE AIR LINE BET\iEEN EACH VALVE DIAF'HRAGMANOITSASS•CIATEOPOSITIONER.THESOLENDIOVALVES f~EFi°vt~i~it;IJf TO VENT, CAUSING THE FEEDWATER VALVE TO CLOSE
FEEOWATER FEEDWATER FEE• 'NATER FEEDWATER Mll!N VALVE C BYPASS VALVE C MAIN VALVED BYPASS VALVED
FCV-530 ICF46l FCV-SJ~A ICF481 FCV-54il ICF55) FCV-S4~A ICFS7l (NOTEJl CNOTE31 !N• TEJl INOTE3l
2. f~~ICCAlff~r:~Eg~Nb~~~ ~HEET ARE N•T REDuN•ANT. EXCEPT WHERE
3.0PEN/SHUTINDICATIDNFOREACHFEE•WATERVALVEINCONTROLROOM. DA COIIJITI ON I
WESTIN:;HDUSE ELECTRIC CCR"ORATION ®
FEED'w'ATER CONTROL & ISOLATION
"' """""'"°"''"""-""'""",..,"""'""' ,.44 4
I I I I I I I I I I
Catawba Nuclear Station UFSAR Figure 7-2 (Page 21 of 25)
(17 OCT 2013)
r----------------~-------------
()ift{) 39!!.01-0""281l,REv. • 11
- I llll!!IIIF!llll!F!Wll'll!T[EIJECI.IMTEL¼1!
- '""-'""""""''""'""T(EFJECl.'"1EMt-ll -DA CONOITIDN I
11111 ...... ILICTIIIC CQIIIDIIIIDII @
Catawba Nuclear Station UFSAR Figure 7-2 (Page 22 of 25)
(17 OCT 2013)
Feedwater Control & Isolation
LOOPC!.O INTERLOCK (SHEET lJI
! ! r·----------------------------- ! ! STEAM G:::RATOR" C ! STEAM G:::RATOR" 0 ! ! CONTRDLA~~GDRITHM ! CONTRU.. A~~GORITHM ! ! ACisUtt~~Tf•~i1c, ! ACr~tt~Tf•ilIC, ! ! M~fJ 0v~iti:R C svf!°f~Wv";,,I\i C ! MnJ0v~iti:R D BYfl!fWvAAl~i D ! i DEMAND DEMAND i DEMAND DEMAND i : I I I I I I --------1 --------------i--------· -----·-·1 -----------·-·1 -------·
I I I I
----~ •-••-••-••-~---•-••-••-••-~---•-••-••-••-••-••-~-----~---•-••-••-••-~- I
I .,.,:'"'" I .,.,:'""" .,.,:""" I =:'""": i ~ ~ ~ ~ :
---------------------------~-----1--------------1--------------------;;,;;;;;,;;;.., -----r--------------r-.1 MODULATE MOOULATE MODULATE MODULATE
I. ANALOG GATE CONSISTS OF nm SOLENOID VENT VALVES IN SERIES TORE•UNDANTLYINTERL•CKTHEAIRLINEBETWEENEACHVALVE OIAPHRAGMANOITSASSOCIATEOPOSITIONER.THESOLENOIDVALVES ~~EFi°vtEs~~it;JJf TO VENT. CAUSING THE FEEDWATER VALVE TD CLOSE
2.ALLCIRCUITSONTHISSHEETARENOTREOUNOANT,E)(CEPTWHERE INOICATEO'"REDUNOANT".
3.0PEN/SHUTINO!Cllll•NFOREACHFEEDWATERVALVEINC•NTR•LROOM. 4.FORCONTINUATION, SEENOTESONSHT.l.
I I I I
FEEOWATER FEEOWATER FEEOWATER FEEOWATER MAIN VALVE C BYPASS VALVE C MAIN VALVE D BYPASS VALVE D
FCV-53il ICF46l FCV-53~A ICF4BI FCV-54il ICF55) FCV-54ilA ICF57l !NDTE3l (NOTE JI !NOTEJl INOTEJl
OA CONDITION I
FEED~•TER C~TIIOL & IS•L.ATI~ D..,.W'EDF-l21l
Catawba Nuclear Station UFSAR Figure 7-2 (Page 23 of 25)
(17 OCT 2013)
, ...
¾
"'t ® ---- --------------------- "'l ® ·~ ® ---------------------------------- --------------- -------------------------------------------- ------------BY OTHERS
l.TRAINACONTR•LSMAFPl1BREAKERNUMBER TRAINBC0NTR0LSMAFP21BREAKERNUMBER
8.THETURlllNESPEEDCONTROLJSTYPICAL,ACTUAL IMPLEMENTATJ0NMAYN0TINCLU•ESPEE• C~TRDL,
TRIP OF MMN FEED PUMPS BY OTHERS BY OTHERS
~ ----------------------~
•EVEL•PEDFROM CNM 1399. 0 l-0~24.015. REV. D6 LFSAR F1c:,,re 7-2 [Page 23 of 25) QA CONDIT JON 1
0 0 0 VESTlrt:;IGJSE ELECTRIC CIR'IIIATl()I @
: : : l]~~~LEAR PA USA
Catawba Nuclear Station UFSAR Figure 7-2 (Page 24 of 25)
(17 OCT 2013)
11 10
BVBY
OTHERS®
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Catawba Nuclear Station UFSAR Figure 7-2 (Page 25 of 25)
(17 OCT 2013)
11 ,.
,,. I
BY BY
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4.THESESIGNALSINDICATETHEFULLCLOSEDPOSITIONOFTHESTOPVALVES.POSITION ~~p:m~~ ~Mi?1Nm.E~o~ 1~gl~~r~i~ PER 5Tt»' VALVE. ONE F•A EACH TRAIN.
5. THIS FLINCTiaN IS usm TO BVP~55 THE REOucm TEMPEllATL.iE RETURN TO POWER
~~t/}lgfAflJ:C~t'r" J0 .. itiweiu~~lt~Rrns~1i1r2'~ ~L~h%8[tigL, H£ C- IS 6, FOR C•NTINUOTION, SEE NOTE lm ON SHT. \,
OA CONDITION 1
7244045 l "'"""'"'°'"'''""""°""'FFB:1.1..,._L> "oH: > TLC
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SF
Test C
ircuits
11.NALOG TESTING MASTER RELAY TESTING • ~ l LOGIC TESTING I
Bl STABLE I NPUTI ILO GI C C I R cu I T ~--M-A_S_T_E_R _R_E_L-AY-
FINAL DEVICE OR ACTUATOR TESTING
SOLENOID SLAVE RELAYl--r--------...,..!I VALVES
SLAVE RELAY
[E I RELAY' •~
....
MOTOR OPER, VALVES
SOLENOID VALVES
MOTOR OPER, VALVES
~I PUMP MOTORS
SLAVE RELAY 1--------------- ACTUATORS
I SLAVE RELAY I • ACTUATORS
Ca
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ure 7
-5 (P
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ure 7
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afeg
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est Cab
inet In
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, Notes, a
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end
0 Hl"l'1 ;z ;z
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-i
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~ ~I J & I
ILLIJIIINITED l'IISlttlUTTON ,WI TOI NI TH 28V LAMP NO. 327 i (EKCEPT AS IIOTED) J:
REAi OF P.lNIE
i s I ~
~
SYMIOL KEY l t'.:=n
DETAIL C CU11RENT MONITOR OS' LEO WITH INTEHAL RESISTOR CONTACT LDCUIIIN SljftEME
(I) !
t SPS 11 I I ~ - TYP. TEAMINlL IIIIIIBERS I I I
; LqCr 1••-r• r 1·-r1 ~:x.:~r" I u SPS g SPS ALL YIRISTORS I STC ~ IK' ~ IK' HE STC
JIIDI JII02 ~ SPS ; :PS Gl:Vl30LUOA JBOI JB02 ---r J. ~Tr. ,., fu\ STC t71 (BJ l 1 SPS • • .,
OEIIERll IIOTES: I. CIRCUITRY AIIO HAR~HE FOR REDUNDANT PROTECTION TRAINS
"A' AND "I' TEST CIBINETS ARE Dllt'LICATE EXCEPT AS NOTED
A - TRAIN •A- ONLY
B - TRAIN •r OILY 2, IN DETAILS l' I TNE SYNIIIL • IIEPRESEIITS THE SUFFIX
NUMSERS OF TNE DEVICE REFERENCED.
EXAMPLE: K' - SPS RELAY, IC601, KS02, ETC, K(O) - OPERATING COIL K(R) - RESET COIL S' - STC TEST SWITCH, 9802, san. ETC, H' - STC REUY, HI I, K817, HC. DI' - STC LIGHT, DS800S, 0911077. ETC.
I 3, "DETAIL l', •r Tl!'E CIRCUITS ARE DETAILED ON TNE
SCHEMATICS, '"DETAIL I" CIRCUITS WILL IE SUISTITIJTEO AIR "DfJAIL A" CIIQJITS WHERE REQUIRED.
UCATIDN LEGEND SPS - SOLID STATE PIIJTECTIIIN SYSTEM STC - UF£GUIIIOS TEST CAB I NET X - SlfGI, NCC, AUXILIARY RELAY RAC!, ETC,
ASC - lUXIL1AIY SAFEOOlRDS CABINET
:1 µ-SEE DETAIL
• ·c" ~
~ N
DETAIL A rtPICAL PROTECTION ACTUATION CIRQJIT a.acme SCHEMES (CONTACT CLDS~RE FOR AC111ATION)
DETAIL 8 TYPICAL .PRDTECTI011 ACTIJATION CIRCUIT SLDCIING SCHEMES (CONTACT DP£NIIIG FOi ACTUATION)
Catawba Nuclear Station UFSAR Figure 7-6 (Page 1 of 1)
(22 OCT 2001)
Figure 7-6. Motor-Driven Auxiliary Feedwater Pump Alignment to NSW Logic Diagram
AFWPUMP RUNNING
LOSS OF CONDENSATE SOURCE (213 LOW DP)
BLACKOUT (SEQUENCER)
SAFETY INJECTION
LOSS OF BOTH MAIN FEEDWA TER
PUMPS
214LOW-LOW LEVEL IN ANY
STEAM GENERA TOR
FROM TURBINE DRIVEN AFWPUMP LOGIC
(FIGURE 7-7)
NS\A/SUPPLY VAL VE RN250A
CLOSE
OPEN
AUTO
5 SEC DELAY
AUTO
OPEN
CLOSE
AFWPUMPA NS\A/ SUCTION VALVECA15A
SSECDELAY
NOTE: TRAIN 8 IS SIMILAR
STOP MOTOR DRIVEN AFW PUMP DO NOT ALIGN W!TH NS\A/
OPEN NS\A/ SUPPLY VALVE
RN250A
OPENAFW PUMP A NS\A/ SUCTIONVLV
CA15A
Catawba Nuclear Station UFSAR Figure 7-7 (Page 1 of 1)
(22 OCT 2001)
Figure 7-7. Turbine-Driven Auxiliary Feedwater Pump Alignment to NSW Logic Diagram
aJDIIJI" 111E11E1GR1 __ _..,.
2 14 UIIHJlV Lall IN ---ti.-Mr TIii 11B111 IEN,
-
11511 Sl'ft.Y YIUE CAIIM
IBI IIJIPLY WILE -
• _,__,__
Ill, IEVl• Imlll -
ll'EN 1111 UPLY VII.IE CAIIM
DIIITml.llllEFII! 11!111 UPLY VIUES -11111111• FIIIIE 7.lil
ll'EN 11!111 UPLY '1111.E Dlllill
1111' 111mE 1111& IIFV PIN' Ill 111T UII IIIIH N5V
2 1111Y 1111 111111£--1:11,._ NJClEM STATION 11'11T 112 Flllll-1IHl'IER1llaB-FllllEII
Filll!E .,..., N 1\IIIIIE-IIIIVEN IIIIL FEEllllM'ER PUP
..__ 111 - ,UIIIC DI-
-I
Catawba Nuclear Station UFSAR Figure 7-8 (Page 1 of 1)
(22 OCT 2001)
Figure 7-8. Component Cooling Water System Logic Diagram
BLACKOUT SIGNAL
SAFETY INJECTION LOW LOW FWST LE
LOW SURGE TANK T.EVEL
INDIVIDUAL EQUIP. S UENCER MANUAL CONTROLS
TRAIN A COMPONENT
COOLING PUMPS SAFETY MODE
INITIATION
(TRAIN B SIMILAR)
TRAIN A AUXILIARY BLDG NON ESSENTIAL
ISOLATION VALVES SAFETY MODE
ALIGNMENT
NOTE: A separate manual control switch is provided for each pump and valve which receives a safety injection or containment isolation signal. Each such device is controlled independently of any other in the manual mode. Capability for simultaneous manual actuation o[ all devices by a single control switch is not provided or implied.
OR
TRAIN A VALVES
SAFETY MODE ALIG!\'MENT
CONTAINMENT ISOI.ATION SIGNAL
EQUIP,
TRAIN A REACTOR BLDG
NON ESSENTIAL ISOLATION VALVES
SAFETY MODE ALIGNMENT
Catawba Nuclear Station UFSAR Figure 7-9 (Page 1 of 1)
(22 OCT 2001)
Figure 7-9. Chemical and Volume Control System Logic Diagram
B 1 ackout Signal
Safety Injection Signal
-1 nd i vi dua 1 Equ i p. Sequencer Manual Controls
Train A Centrifugal
Charging Pump Safety Mode
Initiation
(T ra i n B S i mi 1 a r)
Train A Valves
Safety Mode Alignment
NOTE: A separate manua 1 cont ro 1 switch is provided for each pump and valve which receives a safety injection or containment isolation signal. Each such device is control led independently of any others in the manual mode. Capability for simultaneous manual actuation of all devices by a single control switch is not provided or imp! ied.
Containment Isolation Signal
Train A Reactor BI dg •
I so lat ion Valves
Safety Mode Alignment
Catawba Nuclear Station UFSAR Figure 7-10 (Page 1 of 1)
(22 OCT 2001)
Figure 7-10. Residual Heat Removal Pump Logic Diagram
SAFETY INJECTION SIGNAL
SEOU NCER
AHR PUMP MANUAL CONTROLS
VALVE MANUAL CONTROLS
TRAIN A RHR PUMPS SAFETY MOOE INITIATION
TRAIN A AHR HEAT EXCHANGER BYPASS AND OUTLET VALVES SAFETY MODE INITIATION
Catawba Nuclear Station UFSAR Figure 7-11 - 7-12 (Page 1 of 1)
(22 OCT 2001)
Figure 7-11. Deleted Per 1991 Update
Figure 7-12. Deleted Per 1993 Update
Catawba Nuclear Station UFSAR Figure 7-13 (Page 1 of 1)
(22 OCT 2001)
Figure 7-13. Cold Leg Accumulator Isolation Valves Control and Alarm Logic
. NC·HlGH PRESSURE ·" .(Al!lOVE 0P,11 SETPOINT)
MANUALOPEN ;(~·ROOM)
, SAFETY INJECTION --,,--SIGNAL
SAFaY1NJECTION -----l SIGNAL
MANUAL
Ca
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ure 7
-14
(Pa
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)
(22
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00
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Fig
ure 7
-14. C
on
tain
men
t Pressu
re Co
ntro
l System
Logic
TRAN A CONTAIINENT PRESSURE
ONO'f
AR RfTlftN
FAN
OPEN
AR RETlBI DAMPER
Q.OSE
l
NE DELAY
TIME DELAY
MANUAL CONTROL
HIGH HIOH CONTAINMENT PRESSURE
2/4 LOGIC
NOTE: TRAIN B LOGIC SIMILAR
l TRAIN 8 CONTAINMENT PRESSURE
AND
START
CONTAINMENT SPRAY PUMP
STOP
OPEN
CONTAINMENT SPRAY DISCHARGE
CONTAINMENT ISOLATION VALVES
CLOSE
Catawba Nuclear Station UFSAR Figure 7-15 (Page 1 of 1)
(17 APR 2012)
Figure 7-15. RWST Level Signal for Safety Injection System Recirculation Sump Isolation Valves
RWST WIDE RANGE LEVEL CHANNEL BISTABLES 1! NORMALLY OE,ENERGIZED 2) OE-ENERGIZED ON LOSS OF POWER 31 TRIPS!GNALf'flOl/!DED WllEN ENERGlZEO 41 tNERGiZEO ON LOSETPOINT
~-"-
( !.B ~ I LO
0 II LO
7/4
' TRIPSlGNAl. TO AUTOMATICALLY OPEN SUMP ISOLATION VALVE
Nl185A (COt,fT ON FIG, 7-161
Ill
LO /"~ PROCESS
I LB \ CONTROL ~CABINETS
IV ,:o
SOUOIHATL PROTECTlm~ CABINETS
~ l e TRIP SIGNAL TO
AUiOMATICALLY OPE:N SUMP ISOLATION VALVE
N11849 (CON'i ON FIG. 7-16)
~ -·--- +- 1--
fflH!lllfJl2ft2f:,'tl\ltlll[OTH',)!l(llll'.J!I 111'-: 'ii
NO, REV I SlONS
DUKE POWER C!Jt,PANY CATAWBA NUCL:J,H c_;Tl'ITION
RWST LEVEL SIGf/A'... FOR SAFETY
INJECTION S'fSTEM REClRCULAT!ON
SUMP ISOLATION VALVES
APPENDIX 7 CHPT, 7 TABLES & FIG,
Catawba Nuclear Station UFSAR Figure 7-16 (Page 1 of 1)
(22 OCT 2001)
Figure 7-16. Safety Injection System Recirculation Sump Isolation Valves
SUMP VALVE AUTOMATIC OPEN CIRCUIT
RHR OUTER ISO. VALVE CLOSED
MANUAL RESET
SPRING RETURN
TON
RESET · ---------------. SWITCH
OPEN AUTO CLOSED
RHR INNER ISO. VALVE CLOSED
N (NOTE1) MCB
RWST/RHR SUCTION ISO.
VALVE CLOSED
INTERLOCK TABLE
NI 185A NI 1848
RWSTfR.HR PUMP SUCTION ISO. FW27A FW66B VALVE LMTSW#1 LMTSW#l
AHR INNER 'ND 1B ND368 ISO. VALVE L.MTSw#2 LMT S¥$1
AHA OUTER ND2A ND37A ISO. VALVE LMT SW#I LMTSW#'l
TRAIN A 8
OPEN VALVE
] ____ ~ TRIP SIGNAL 1
FROM 2/4 I RWSTLO LEVEL SIGNAL II
I (CON'T PROM I . FIG. 7.6.6·11 I L _______ _J
CLOSE VALVE
APPLICABLE VALVE
DESCRIPTION VALVE
SUMP TO #1 AHA PUMP NI 185 A
SUMP TO #2 AHR PUMP NI t84 8
'LIMIT SWITCH #1 13 THE NORMAL POSITION StGNA LAND IS USED FOR POSITION SIGNALS BETWEEN VALVES A;SSIGNED TO THE SAME TRAIN. LIMIT SWITCH #J. IS THE STEM MOUNTED POSITION SWITCH AND IT IS USED FOR POSITION SIGNALS BETWEEN VALVES ASSIGNED TO OPPOSITE TAAINS.
TB - TEST BUTTON (LOCATE.D ON WES'TINGHOOSE 'SAFEGUARDS TEST CABINET) S - SAFETY INJECTION SIGNAL
NOTE 1: THIS IS A TWO POSITION CUTLER-HAMMER(E30JY5) MO-MENTARY OPEN/CLOSE PUstlBUTTOtl. THERE IS NOT AN AUTO BUTTON, BUT WHEN THE SWITCH IS NOT IN THE OPEN OR CLOSE STATE IT IS IN THE AUTO MOOE.
Catawba Nuclear Station UFSAR Figure 7-17 (Page 1 of 1)
(22 OCT 2001)
Figure 7-17. Reactor Coolant System Overpressure Protection System for Low
Pressure/Temperature Water Solid Conditions Logic Diagram
RCS WIDE RANGE RCS WIDE RANGE PRESSURE TEMPERATURE MCB SWITCH
ENABLE/DlSABLE TRANSMITTER TRANSMITTER
PT
PB~
( T RA I N B I S S I H I LA R)
TT NORM LOW PRESS
TB L
Nl438A,Nlli39B Open (Assured Air Supply, N2} A
LOW PRESSURE MODE OPE RAT l ON ALERT
PORV ACTIVATED A
ACTIVATE TO OPEN PORV
(TRAIN A}
MCB PORV MODE SELECTOR SWITCH
OPEN AUTO
A RETURN TO
NORMAL MODE
r- -7 I EXISTING I I PORV I L ~OGI:_ .J
CLSD
Catawba Nuclear Station UFSAR Figure 7-18 (Page 1 of 1)
(05 APR 2015)
Figure 7-18. Rod Control System Block Diagram
TAVG LOOP TAVG LOOP TAVG LOOP TAVG LOOP A B C o
I ~ ~ I I SELECTED TAVG I ROO CONTROL
REFER TO UFSAR FIG. 7-2
IP.,ges 11 & of 251
12
ROD DRIVE POWER REDUNDANT TRIP SIGNAL
I REACTOR TRIP BREAKER I
I REACTOR TRIP i BREAKER 2
DRIVE ROD CONTROL ROD POWER ACTUATOR
CONTROL ROD MECHANISM
/TT
DIJCE EIIERGY CATAWBA NUCLEAR STATION
ROD CONTROL SYSTEM BLOCK DI AGRAM
I IIEl.fAlfD FIJI 2114 FSM ll'IMIE EFFECT,IMIE &-•14 1K 11;;11 -11;;11 ... r.;12 -w- -w- -w- IDlmER.lll..J:ILa_Ml'Ell:ll:llltllP: .. ,. IIIMIN!IIMillll ;:;m::.!U!!!m.-::.u:az:m .. , .. lllWSED FIJI at FSM ll'IMIE EFFECT,IMIE 11·2Hl l"£CIEDAnlF 1111. REVISIONS DllN DOTE CIICD DOTE - IMTE CIWb. ..... - CN-FSAR-F IO. 7-lB I ~Y-1..-ECTED DWO. IID.
Catawba Nuclear Station UFSAR Figure 7-19 (Page 1 of 2)
(17 APR 2012)
Figure 7-19. Control Bank Rod Insertion Monitor Block Diagram
(t.T) SEL COMPARATOR
z-----OEMAND BANK SIGNAL TYPICAL OF ONE CONTROL BANK
LOW ALARM
LOW-LOW ALARM
t-+-------'
COt4tON FOR ALL FOUR CONTROL BANKS
NOTE: I. DIGITAL CR A~ALOG SIGl-!ALS MAY BE USED FOR THE COMPARATOR CIRCUITS.
2. COMPARISON IS DONE FOR ALL CONTROL BANKS
0
D
•
•
Catawba Nuclear Station UFSAR Figure 7-19 (Page 2 of 2)
(17 APR 2012)
Deleted Per 2012 Update.
Ca
taw
ba
Nu
clear S
tatio
n
U
FS
AR
Fig
ure 7
-20
(Pa
ge 1
of 1
)
(22
OC
T 2
00
1)
Fig
ure 7
-20. R
od
Dev
iatio
n C
om
pa
rato
r
DEMAND BANK SIGNAL {ROD CONTROL) >I
INDIVIDUAL ROD POSITION READING OF THOSE RODS CLASSIFIED AS MEMBERS OF THAT BANK
ALARM
COMPARATOR
NOTE: I. DIGITAL OR ANALOG SIGNALS MAY BE USED FOR THE COMPARATOR COMPUTER INPUTS.
2. THE COMPARATOR WILL ENERGIZE lliE ALARM IF THERE EXISTS A POSITION DIFFERENCE GREATER THAN A PRESET LIMIT BETWEEN ANY INDIVIDUAL ROD AND THE DEMAND BANK SIGNAL.
3. COMPARISON IS INDIVIDUALLY DONE FOR ALL CONTROL BANKS.
Catawba Nuclear Station UFSAR Figure 7-21 (Page 1 of 2)
(17 APR 2012)
Figure 7-21. Pressurizer Pressure Control
PRlPRES3t;;;tE MEASUREMENT
ffi T --- ----- ---------- -- ----------------- ---r ~
,~ -------~:a-----~E~~
~-------f::!S--7-----:-------: ' ' ' ' ' ' ' '
LO PRESS O!:V!i>a.'!101-JIT'J!!;"!
-----c!)
L-~_J __ _ t-----------r-1, ---------t-,----+i'.'......,~,ii\Jef---------+1----' ,
~ ~ -;------- I-~----
'
lflxJI
T 6
TOVAmASL[
HEATERS LOGIC
L_J-----,. l ,_,_ _____ l M/A STAnmi ~]✓ ,".;,,T'. I ':i:Vs~~~11; .. : 1 ~1✓ '~~~
(COl,fTROL ROOM) [COtlTJWI ROD~) T
,[ ,[ MODuUIH
SPRA\IV/l.l\11'#1
DEVELOPED FROM
fflVLJOJL"I~
SPRAVVALYEf2
' 6
I ooLMOLn~ Lu,.,nuL
' ' 6
l __________________ _,
DUKE ENERGY CATAWBA NUCLEAR STATION UNITS 1 & 2
PRESSURIZER PRESSURE CONTROL
OCP & •OP PRESSURIZER PRESSURE CONTROL SYSTEM FUNCTIONAL DIAGRAMS
CNM 1399.03-0660,001, SHT, A-7 2 RELElloEDFlll2112FSMll'llAIEEFFECT, •ATE!1/!S/11 WMC 11,,16 CG/\ ",.'7 WEH 11,,2" -W- -W- -W-I RELEA!E• FIii 2111 FSM ll'•ATE EFFECT.IYITE 2-28-!t VDR I";-~• TLC 3;-i!~ WEH 3;-;l~ W W ii ~~N~~:~,;,.:"' ~:~ :: :::::::~: ::::~ :~-=---
•Rm. IUB'l!BIF1Jl211HF5Mitro'llEEFFECI.D!TE 111-21-111 Cl
Catawba Nuclear Station UFSAR Figure 7-21 (Page 2 of 2)
(17 APR 2012)
Deleted Per 2012 Update
Catawba Nuclear Station UFSAR Figure 7-22 (Page 1 of 2)
(17 APR 2012)
Figure 7-22. Pressurizer Level Control System Block Diagram
14EA31lREIIIUIJ F.O.ll!ll'"
G• LB uD~)'!• l ~ ~~-=-ll~ GD--..! t: "": • ·: ----------- -------- _ -~ · 1----------------1~;1
L-~~ -- - 1 : " :-----ffi
~~~~~,~ =~~--E' : j •.• ,e, ·~- ~L~'~..,'s··"'··· E.l "'.:'.:'.~:•''~
~-~------·--_··_···-_-_·-_-···_· ~l~I -1~7, -f-=---"8----------------~ •i ! ' l~i ,
NtiA ~lAIIUN !COMTROLRDOM!
~-,,...SWITCHTO
L----f
1-...,,;;. Si-A,10N ! !LUCCA.l)
t----.+j-\\L --f-=---L ---------- ----.../...2)
DUKE ENERGY CATAWBA NUCLEAR STATION UNITS 1 & 2
•EYELCPED FROM CI\N 1399,03-0660,001. SHY, A-6
2 IELEASE• FllllllllFr,IRl.l'l)IITEEFFEt:T. •AlEll-l6-l1 WMC 11,,16 CG/\ ",.'7 WEH 11,,2" -W- -W- -W-
PRESSURIZER LEVEL CONTROL
OCP & •DP PRESSURE LEVEL CONTROL SYSTEM FUNCTIONAL DIAGRAM
I IEL!!SED FllR
Catawba Nuclear Station UFSAR Figure 7-22 (Page 2 of 2)
(17 APR 2012)
Deleted Per 2012 Update.
Catawba Nuclear Station UFSAR Figure 7-23 (Page 1 of 3)
(17 APR 2012)
Figure 7-23. Steam Generator Level Control
II
\IAUOATED NUCLEAR POWER
Er !
' ~-' LEVEL
VALIDATED FEEDWATER TEMPERATURE
VALIOATC:D STEAM FEEDWATER
FLOW
' I : : I I I
-- ----- - - ---- ------ -~----- - ----- - - ---- - l::' '
' ~--~ \
"
I ?ROPORTIOHAL I !
i- LOAOINOX ----- --------- ------ -- - -- - -- -+-------- -- ------------------__________ l N ,' I
TOTAL FEEDWATER
FLOW DEMAND
DEVELOPED FRO"I CN'I 1399.13-11662.NI. SHY. A-6
1 llLEASEllHJl21112FSl!lUllJAT[EFFECl,!!-l!Hl
RIG,llEI.EIISEDHl!21l!lFSNl~lEEFFECI.Z-2lt-!!
NO. REVISIONS
i
DUKE ENERGY CATAWBA UNITS 1 & 2
FEEOWATER FLOW DEMAND CALCULATION DCP&DDPFEE•l,/ATER
CONTROL SYSTEM FUNCTIO~LOII\ORAMS
CN-FSAR-FIG. 7-23.01 REV. 1
Catawba Nuclear Station UFSAR Figure 7-23 (Page 2 of 3)
(17 APR 2012)
Steam Generator Level Control
II
MEASURED MAINlfALVE
POSITION
E&----- ------------,
"
MAINF[EDWAT[R FLOW CONTROL
VALVE Ni/A INTERFACE
MAIN VALVE POSITIOI-!
11~1 !(~]
DEVELIPED FID4
SWITCl1.TO· MANUAL
lj)---
CNM 1399.113-8662.IJllll. SHT. A-7
,-'~~ 0
BYP/1.SSFEEDWATER FLOW CONTROL
VALVE M/A INTFRFACE
MEA.SUREO BYPASS VALVE
POSITION
FEEDWATER FLOW DEMAND
TRACKING
'------..f>~C -------
Catawba Nuclear Station UFSAR Figure 7-23 (Page 3 of 3)
(17 APR 2012)
Deleted Per 2012 Update
Catawba Nuclear Station UFSAR Figure 7-24 (Page 1 of 2)
(17 APR 2012)
Figure 7-24. Main Feedwater Pump Speed Control System Block Diagram
ROLLBACK flOLD ON Rll;foR
(ByOthero)
FWflEI\OER PRES.SUR[
=-----------------
FPO----------------
' ' ' ' ' ' ' . :
FEEDWATER FLOW FEEDWA TER FLOW Ul:~ANU SG A DEMAND SG B
FEEDWATER fLOVI' f~EDWAlER fLDW DEIIIIAND SG C DEMAND SG D
y REMOVE
FEEOPUMP
' I ~
' ' ------------------- - ~
VALIDATED FEEDPUMP A
SPHcll FEEDPUIIIIPBIAS
A '
.l TO FEEOWATER PUMP TURBINE B M/A BIAS AND SPEED DEMAND
LOGIC
~---'---~,_ _______ T _____ ------------- ----.\ I All~~~~TE
' b------00
IJEVEUJ'EO FRCM 014 1399.13-IBR.111, SHY. A-B
II "
FEEDWATERPUIIIIPTUABINE A SPEED DEMAND
Nil
V•R\'i .. PAWi', .. WEHi'i"' REVISIONS •RN •ATE CHK• •ATE APPR •ATE CIYIL ELEC. i'EOl
DUKE ENERGY CATAWBA UNITS 1 & 2
FEEDWATER PUMP TURBINE SPEED DEMAND CALCULATION
•CPFEE•WATER CONTROL SYSTEM FUNCTIO~LOIAORAMS
CN-FSAR-FIG, 7-24
Catawba Nuclear Station UFSAR Figure 7-24 (Page 2 of 2)
(17 APR 2012)
Deleted Per 2012 Update.
Catawba Nuclear Station UFSAR Figure 7-25 (Page 1 of 2)
(17 APR 2012)
Figure 7-25. Steam Dump Control System
REACTOR
'"'' y
OPERATOR ENTERED
COASTDOWN TFMP
I I
STEAM DUMP I CONTROL MODE I
SELECTOR :
TAVG COASTOO\MII
I URBINE TAVG PRE:SSURE VALIDA TEO TURBINE
FAILURE SIGNAL FAILURE IMPULSE PRESSURE
q) ® TAVGD
(NOLOAD)
fovg Pl¥11Trlp Conlrollcr
STEAMPRESURE FAILURE-SWITCH
TOllftAMUAL
$ ' I ' ' I ' I I I
' '
STEAM PRESSURE
M/A STATION
t----------~---- -1----~----~- --;--------------+---~---;----~--- -~==8-/ ,1 I RESET •_ : : : : : : : : : : 1 1 I
• ,:~;;,, ~==~ -----~-:_-:_--r-------r-------r-~-:_=r----:--r----_-_-_-_-:_-_-_-_-_-~:_--r----r---r_-:_-_-:_-::-_-_-_-_-_--r--:a- ------_, --- -- ____ / 4 I I ! I I I I I I I I 1 ' TRIPOPEN
~--- •~·l1ttE' 1 5 ;::1 n.;e;,:::r.: .. ~ =,. ""1" : L : '-s---, : : ----;a---~-:-- Q_) s~~~B~~ti:~4
II
L _ -- - -~--~ -:::::::_~~--~-- ------ -- -- -- ____ ·:::~:::::Js=~~~-==S--§, r s~~:l&i,
"
§- ~-§ ~---- ~---~
TRIPOPl.'N ATMOSPHERIC
~v~~[,~~L~-~ I DEVELOPED FRIJ4
Clf4 1399,113-11661,llllll, SHY, A-6
I RELEA5EDFIJl2112FSIIILJ'IMIEEFFECl.11-1&-t1 111M: ,,- CliA 11" WEH RIG. IEI.IASEllF~21111F!iARIAlolTEEFFECT.MEHI VDR 2< PAW 24 WEH j'i2'
ND. REVISIONS
DUKE ENERGY CATAWBA UNITS 1 & 2
STEAM DUMP CONTROL •CPl •• PSTEAMDUMP
CONTROL SYSTEM FUNCTIO~LOIAORAMS
CN-FSAR-FIG, 7-25
Catawba Nuclear Station UFSAR Figure 7-25 (Page 2 of 2)
(17 APR 2012)
Deleted Per 2012 Update.
Ca
taw
ba
Nu
clea
r S
tati
on
UF
SA
R F
igu
re 7
-26
(P
ag
e 1 o
f 1
)
(15
NO
V 2
00
7)
Fig
ure
7-2
6. B
asi
c F
lux-M
ap
pin
g S
yst
em
NOTE1
JSOLAT!ON l'Al_VES ARE ~ON SAFETY-RELAED ANJARENOTCONS:JERE[)INOESJGNBASiS PC~ID~NT A\,A- Y -IS.
ERN:'.:N009/Sl
I=---------------+-1 llfrnSED /DR ?tlll7 '~R ffilE mm.OOT[ 11-IHl
ORIG. RELEASED fQ~ 2000 FSAR UPDATE
NO. REVISIONS
DUKE POWER COt-PANY CATAWBA ,UC!_EAR STATION UNITS 1&2
BAS1C FLUX--MAPPING SYSTEM
APPENDIX 7
REV.
1
Catawba Nuclear Station UFSAR Figure 7-27 - 7-30 (Page 1 of 1)
(22 OCT 2001)
Figure 7-27. Deleted Per 1990 Update
Figure 7-28. Deleted Per 1990 Update
Figure 7-29. Deleted Per 1990 Update
Figure 7-30. Deleted Per 2000 Update
Ca
taw
ba
Nu
clea
r S
tati
on
UF
SA
R F
igu
re 7
-31
(P
ag
e 1 o
f 1
)
(22
OC
T 2
00
1)
Fig
ure
7-3
1. R
od
Co
ntr
ol
Sy
stem
Sim
pli
fied
Blo
ck D
iagra
m
575
' BUS ' A·
'\:_;- REACTOR TRIP BREAKERS
,e,10-1 20flHP .---.. _,----..
INDUCTION [ J l++-----t-----t-----,------+--:-+--,-----.,-----r-MOTOR .---.. _ _.-.._
0.Q_lJ_U
10-438KYA
SYNCHRmJ•US GENERATOR
IZIG-ZAG\IYEI
1=8341-15@725/ MlN 1-HH'l00 MS ~6 S/MIN
TIME FOR r-E STEP=780
=l. ·~ ----i_ - -
~VARIABLE CEf'iJTir£
~~~~~~
__ f SI-UTDO\IN SHUTDO\m SHUTOOWII SHUTDO~N SHUT[)J\,N CONTROL [WJ
Ca
taw
ba
Nu
clear S
tatio
n
U
FS
AR
Fig
ure 7
-32
(Pa
ge 1
of 1
)
(22
OC
T 2
00
1)
Fig
ure 7
-32. C
on
trol B
an
k D
Pow
er Ca
bin
ets 1B
D a
nd
2B
D P
artia
l Sch
ematic D
iagra
m
cpA rpB cpC
STATIONARY GRIPPER
COILS
cpA rpB q:,C
MOVABLE GRIPPER
COILS
CONTROL BANK D GROUP I POWER CAB I NET I BD
rpA rp B cp C
120 YAC ' I • I • I I 'I ([ 1 LIFT COIL DISCONNECT SWITCHES
120 YAC
CONTROL BANK D GROUP 2 POWER CABINET 2 BO
LIFT COILS
2-----------------___. LI FT COi LS
MULTIPLEX THYRISTORS
Catawba Nuclear Station UFSAR Figure 7-33 (Page 1 of 1)
(22 OCT 2001)
Figure 7-33. Deleted Per 1995 Update
Back to Title PageC07C000C07C001Figure 7-1. Protection System Block Diagram
C07C002Figure 7-2. Instrumentation and Control System Diagrams - Index and SymbolsInstrumentation and Control System Diagrams - Index and Symbols
C07C003Figure 7-3. Setpoint Reduction Function for Overpower and Overtemperature T Trips
C07C004Figure 7-4. Typical ESF Test Circuits
C07C005Figure 7-5. Engineered Safeguards Test Cabinet Index, Notes, and Legend
C07C006Figure 7-6. Motor-Driven Auxiliary Feedwater Pump Alignment to NSW Logic Diagram
C07C007Figure 7-7. Turbine-Driven Auxiliary Feedwater Pump Alignment to NSW Logic Diagram
C07C008Figure 7-8. Component Cooling Water System Logic Diagram
C07C009Figure 7-9. Chemical and Volume Control System Logic Diagram
C07C010Figure 7-10. Residual Heat Removal Pump Logic Diagram
C07C011Figure 7-11. Deleted Per 1991 UpdateFigure 7-12. Deleted Per 1993 Update
C07C013Figure 7-13. Cold Leg Accumulator Isolation Valves Control and Alarm Logic
C07C014Figure 7-14. Containment Pressure Control System Logic
C07C015Figure 7-15. RWST Level Signal for Safety Injection System Recirculation Sump Isolation Valves
C07C016Figure 7-16. Safety Injection System Recirculation Sump Isolation Valves
C07C017Figure 7-17. Reactor Coolant System Overpressure Protection System for Low Pressure/Temperature Water Solid Conditions Logic D
C07C018Figure 7-18. Rod Control System Block Diagram
C07C019Figure 7-19. Control Bank Rod Insertion Monitor Block Diagram
C07C020Figure 7-20. Rod Deviation Comparator
C07C021Figure 7-21. Pressurizer Pressure Control
C07C022Figure 7-22. Pressurizer Level Control System Block Diagram
C07C023Figure 7-23. Steam Generator Level ControlSteam Generator Level Control
C07C024Figure 7-24. Main Feedwater Pump Speed Control System Block Diagram
C07C025Figure 7-25. Steam Dump Control System
C07C026Figure 7-26. Basic Flux-Mapping System
C07C027Figure 7-27. Deleted Per 1990 UpdateFigure 7-28. Deleted Per 1990 UpdateFigure 7-29. Deleted Per 1990 UpdateFigure 7-30. Deleted Per 2000 Update
C07C031Figure 7-31. Rod Control System Simplified Block Diagram
C07C032Figure 7-32. Control Bank D Power Cabinets 1BD and 2BD Partial Schematic Diagram
C07C033Figure 7-33. Deleted Per 1995 Update