-
Catawba Nuclear Station UFSAR Appendix 7B. Figures
Appendix 7B. Figures
-
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ure 7
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ure 7
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ystem
Blo
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PROCESS
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
!OD CON I KOl SY SI lM
Te.IP ;,i ;>tfoYFASS 1au: !
uv) . (v(
~) lY'ASS lKR A TRIP
,~ p •
ROD CON".ROL ·~ sns
(
-
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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i i I I
I I I I
I I I I
I I I I
L__ ----------- :f;'"' - _J
-------------1 I
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OEVELCPE• FR•MMANUFACTLRESIJWO. C'f'I 1J99.81-H24il8BREY, •es QA CONDIT ION I
VESTllOOIIE ELECTRIC CGll'GMTDI /W\
~ ~ : 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•
I I I I I I I I I I I I I I I L Lt_f __ -•--
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I I I I I I I I I I I I I I I I I I I I I I I I I I I I I
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I. ALLCl..:UITS •NTHISSHEETARENOTREDU~ANT.
OA CONDITION I
I
5. FOR UNIT IC~Tl"-JMltiF ....... lE(ITT
-
Catawba Nuclear Station UFSAR Figure 7-2 (Page 12 of 25)
(17 OCT 2013)
-
-
-
-
-
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,
I I 1· 1·-----·-1·---·-1-·-- 1 ·---·-·1 ---------------------1 - I --·1-·1 ·-1-·1 --·-1-·1 -
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j c~/f.,~,f'c1m ""'' ;kii~ m.11 1k1::a, lm'~::!W!I ""' ,,~:~ '"'"'~ A A A A A A &- A A f£N?ER'}i l~i~J j:l !~ii~ J~I 1s~5~~ ~,11 1~~6fJ j,Gl L•:o~i°i,L• L~!~~~ rL• L:t~~ ~~-L• L•;'J; rL•
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6, F!JlG[NT!NUIHI•N, SEENITTE60NSHT,1, 7,F0RC[NTINUAT!0N.SEEN0TE70NSHT,J.
a.F•RC[NTINUATl•N,SEEN•TEa •NSHT,1. 9,FaRC[NT!NUATI•N,5EEN•TElG •NSHT,l,
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l
OA CONDITION 1 :lSJi~JlECJl!LC!lff'A~!?..!.11
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
RID'"-""EllFIR,OtlFSl"llfflTEEFFl'CT.Mll-11 m:, ! POW 1 WEH ! V- -W-- -W-
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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
I
I
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I I I I 0--, I I I
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I
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I I I I I I I I I I j
I I I I I I I I I I j
I
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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®
t-AEDU~~T
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TURBINE POWER ITUABINEIMPULSECHAMBERPAESSUAEl
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' ~ij~i~i:f~~i~[FA\t0:ilh~Y;fJ!~1:&:11~iL\~~iif~~~~~~t~rJ!~1~~ t~ll" S. FDR UNIT I CC:tHIMJATION, SEE NOTE II ON SHT,l.
-
Catawba Nuclear Station UFSAR Figure 7-2 (Page 25 of 25)
(17 OCT 2013)
11 ,.
,,. I
BY BY
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f""~~" ""'''" I
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1 ~''.{rei1:0~ ;t:i1: I I
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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
OOHl."'"""'"'°'""'"""""'TE[FFB:1.l-21-]1 van - TLC
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ure
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Over
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Fig
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-4. T
yp
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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
-
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Fig
ure 7
-5 (P
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Fig
ure 7
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ngin
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afeg
ua
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est Cab
inet In
dex
, Notes, a
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end
0 Hl"l'1 ;z ;z
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-i
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TEST LIGHT OS'
~ ~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
-
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ure 7
-14
(Pa
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)
(22
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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.
-
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tatio
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U
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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