ML22278A241

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Rev. 21 to Updated Final Safety Analysis Report, Chapter 7, Figures
ML22278A241
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 09/19/2022
From:
Constellation Energy Generation
To:
Office of Nuclear Reactor Regulation
Shared Package
ML22278A223 List: ... further results
References
Download: ML22278A241 (67)


Text

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LPRMS

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LOGIIIC OUI'PUTS -

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SCRAM GRClPFtLL BOX OR DllVALENTI L:----r----.J r:.------

L SCIVdit G'IIOUPI!IU5WAYOR EQUIVAlaT I

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..... -----"r""----....I-PROT'IeTJON TERMlNALBOJt ON HCU RPS SENSORS A&B MAY BE CONNECTED TO A COMMON PROCESS TAP. C&D MAY ALSO SHARE ONE TAP.

RPS SENSORS A&C OR B&D MUST NOT BE CONNECTED TO A COMMON PROCESS TAP.

WIREWAYS NA, NB, etc. MAY BE ASSIGNED TO AND ROUTED WITH SEPARATED DIVISIONS AS APPROPRIATE TO PLANT LAYOUT.

TRIP LOGICS A AND B OUTPUTS FOR EACH SCRAM GROUP MAY BE COMBINED IN A SINGLE CONDUIT AS DESIRED AFTER LEAVING THE RPS CABINETS NOTE: Per NEI 98-03, this Figure in it's entirety, is classified as HISTORICAL.

LIMERICK GENERATING STATION UNITS 1 & 2 UPDATED FINAL SAFETY ANALYSIS REPORT RPS SEPARATION CONCEPT FIGURE 7.1-1 Rev. 11 9/02

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'SOLATION VALVES NSS$S SEPAAATtON CONCEPT PER NEr 98..Q3, THIS FfGURE IN ITS ENTIRETY IS CLASSIFIED AS HISTORICAL LIMERICK GENERATING Station UNITS 1 & 2 UPDATED FINAL SAFETY ANALYSIS REPORT PCRVICS SEPARATION CONCEPT FIGURE 7.1-2 Rev. 11 9/02 M."'~' _______

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LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT TYPICAL ISOLATION SIGNAL RESET SCHEMATIC FIGURE 7.1-5

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LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT TYPICAL DRYWELL PURGE FAN INLET ISOLATION VALVE SCHEMATIC FIGURE 7.1-6

LGS UFSAR Figures 7.2-1 Deleted

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MODE SWITCH IN SHUTDOWN NEUTRON MONITORING IRM TRIP I

MAIN STEAM LINES ISOLATED

"'.untON MON'T~I"G OPRM TfU, MODISWITCM I..... UN MODE SWITCH NOT IN RUN MODE SWITCH IN RUN TURBINE CONTROL VALVE FAST CLOSURE NUCLEAR SYSTEM PRESSURE HIGH DRVWELL PRESSURE HIGH REACTOR VESSEL WATER LEVEL LOW DISCH VOL SCRAM DISCHARGE VOLUME WA TER lEVEL HIGH HIGH lEVEL I""-

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MODE SWITCH II MODE SWITCH IN REFUEL OR IN STARTUP SHUTDOWN OR RUN I

I NEUTRON I MONITORING APRM TRIP I

SCRAM I TURBINE STOP VALVE CLOSURE LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR PROTECTION SYSTEM SCRAM FUNCTIONS FIGURE 7.2-2 REV. 13 09/06

TAIPSYSTEM A POWER aus NOTE; CONTACTS SHOWN IN NORMAL. CONDiTt ON o

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TRANSMfTTERS TRIP SYSTEM a POWER BUS REACTOR PROT~CT10N SYSTEM LOGICS COHFIGURAT10N FOR:

SCRAM DtSCHARGE VOL.UME HIGH WAl"ER L.EVEL TURBINE CONTROL VALVE FAST CLOSURE REACTOR VESSEL LOW WATER L.EVEL PER NEI 98-03. THIS FIGURE IN ITS ENTIRETY IS CLASSIFIED AS HISTORICAL DAYWEL.l HIGH PRESSORE REACTOR VESSEL HfGH PRESSURE LIMERICK GENERATING Station UNITS 1 & 2 UPDATED FINAL SAFETY ANALYSIS REPORT ARRAGEMENT OF RPS CHANNELS AND LOGICS FIGURE 7.2-3 Rev. 11 9/02

TR"'IVSTIM A ------....------- TtlU.. aYS"nM' TAIP LOCtC A1 TRIP LOGIC A2 SCRAM CONTACTORS E

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SCRAM CONTACTOR LOGICSASSOCrATED WITH TAIP SYSTEM A PtlOT SOLENOIDS

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TAIP lOGIC 112 SCRAM CONTACTOR LOGICS ASSOC.ATED wrTH TRrp SYSTEM 8 PILOT SOLENOIDS

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H GROUP 10 GROUP 2S GROUP 38 GROUP 4S IeRAM PILOT *=RAM,.1l.OT SCRA.. "LOT acAAM P'LOT SOLENOIDS SOLENOIOS SOUNOIOS SOl£NOlbS NOTE:COHTACTSSHOWNIN NORMAL COHDtTJON PER NEt 98-03. THJS FIGURE IN ITS ENTIRETY IS CLASSIFIED AS HISTORICAL LIMERICK GENERATING Station UNITS 1 &2 H

UPDATED FINAL SAFETY ANALYSIS REPORT SCRAM CONTACTORS AND SCRAM CONTACTOR ACTUATOR LOGICS (SCHEMATIC)

FIGURE 7.2-4 Rev. 11 9/02

A SCRAM CONTACTORS TRIP '"OGle At TURBlNE STOP VALVE CLOSURE A TUABtNE CONTROl..

VALVE FAST CLOSURE OAYWEU.

HIGH PRESSURE NUCLEAR SYSTEM HIGH PRESSURE REACTOR LOW WATER L.eV£L EJ NEUTRON MON\\T01=tING SYSTeM A

A MANUAL SCRAM NOTE~ CONTACTS SHOWN eN NORMAL CONOITION A CONTACTS ARE RESET S CONTACTS ME SEAUNG PER NEI 98-03, THIS FIGURE 1N ITS ENTIRETY IS CLASSIFIED AS HISTORICAL MANUAL SCRAM C

C C

R G

LIMERICK GENERATING Station UNITS 1 & 2 UPDATED FINAL SAFETY ANALYSIS REPORT LOGICS FOR TRIP SYSTEM A (SCHEMA TIC)

FIGURE 7.2-5 Rev. 11 9/02

NEUTRON MONITORING SYSTEM TRIP CHANNELS IRM DETECTOR LPRM DETECTOR (OTHER DETECTORS)

LPRM DETECTOR AMPLIFIER AMPLIFIER (LPRM)

AMPLIFIER (LPRM)

NEUTRON MONITORING SYSTEM A

BYPASS A

UPSCALE TRIP IRM CHANNEL A (ONE OF EIGHT)

A IRM BYPASS A

IRM INOP A

IRM UPSCALE TRIP A

MODE SW IN RUN AMPLIFIER-SUMMER APRM CHANNEL (ONE OF FOUR)

OTHER APRM CHANNELS TWQ-OUT-OF-FOUR VOTER A1 (ONE OF FOUR)

E APRM Neutron Flux - Upscale E

Q[ APRM Simulated Thermal A

Power - Upscale Q[ APRM lnop)

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E REACTION PROTECTION SYSTEM (OPMR Upscale Trip) gnQ E

A l (OPRMN:::NITORING SYSTEM LOGICS o ~

(TWO OF EIGHT)

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CD NOTE: CONTACTS SHOWN IN NORMAL CONDITION. ~

NEUTRON MONITORING SYSTEM TRIP SYSTEM A 1 LOGIC (ONE OF FOUR)

(APRM Neutron Flux - Upscale QJ: APRM Simulated Thermal Power -

Upscale Q[ APRM Inop) smQ (APRM Not Bypassed)

    • (OPRM Upscale Trip) and (OPRM Not Bypassed)

NOTE: PER NEI 98-03, THIS FIGURE, IN IT'S ENTIRETY, IS CLASSIFIED AS HISTORICAL.

LIMERICK GENERATING STATION UNITS 1 &2 UPDATED FINAL SAFETY ANALYSIS REPORT RELATIONSHIP BETWEEN NEUTRON MONITORING SYSTEM AND REACTOR PROTECTION SYSTEM FIGURE 7.2-6 Rev. 13 09/06

TRIP SYSTEM A POWER BUS I

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TURBINE STOP VALVE CLOSURE CHANNELS C

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r--3 UPDATED FINAL SAFETY ANALYSIS REPORT NOTE: Per NEI 98-03, this Figure, in it's entirety, is classified as HISTORICAL.

CONFIGURATION FOR TURBINE STOP VALVE CLOSURE INPUT TO RPS FIGURE 7.2-7 Rev. 11 9/02

At

,"Ufl SYSTEM A

. STUM, LilliE 8 ITeAM LINE C MAIN:ItIAM UNE ISOLATiON CW_NEU CSWlTCH CONTACtS SHOWN 'N POSITIONS WHEN ISOLATION VALVES &..ISS 'ntANt.- C:LO$EOI TR'PSVSTf.'

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  • tTlAM Ll_D. tNaoAR'O VALVE Foal)
  • STEAM LtHEI),OU11IOAROVALV£ NOTE:

ISOLATtOH OF THREE Oft MORE stEAM. UNfS WILL CAuse A SCRAM.

T,,'fI'VSTIM

  • flOWeR IIU.

LIMERICK GENERATING Station UNITS 1 &2 PER NEI 98-03, TH,IS FIGURE IN ITS ENnRETYtSCLASSIFIEDAS HISTORICAL UPDATED FINAL SAFETY ANALYSIS REPORT CONFIGURATION FOR STEAMLINE ISOLATION TRIP FIGURE 7.2-8 Rev. 11 9/02

00 02 04 06 08 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 50 52 54 56 58 60 LPRM STRING UPPER LEFT LETTER -INPUT FOR APRM CHANNEL 1 LOWER LEFT LETTER -INPUT FOR APRM CHANNEL 2 LOWER RIGHT LETTER -INPUT FOR APRM CHANNEL 3 UPPER RIGHT LETTER - INPUT FOR APRM CHANNEL 4 APRM SYSTEM LIMERICK GENERATING STATION UNITS 1 & 2 UPDATED FINAL SAFETY ANALYSIS REPORT LPRM CHANNEL ARRANGEMENT IN THE CORE AND APRM CHANNEL ASSIGNMENTS FIGURE 7.2-9 Rev. 10 10/00

LGS UFSAR Figures 7.2-10 and 7.2-11 Deleted

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LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT OUTLINE DRAWING: 26" WELD END MAIN STEAM ISOLATION VALVE FIGURE 7.2-12

REFERENCE DRAWl NGS DWG.

UFSAR NO.

FIG. NO.

M-188 M-198 M-211 1.2-61 M-215 I. 2-71 M-217 I. 2-72 M-221 1.2-54 M-236 I. 2-70 M-240 I. 2-56 I M-198

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SECTION C-C LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PIPING AND MECHANICAL:

REACTOR ENCLOSURE, UNIT 1.

DRYWELL EL. 272'-9" FIGURE 7.2* 13

LGS UFSAR Figures 7.2-14 through 7.2-16 Deleted

LIMERICK GENERATING STATION UNITS 1 &2 UPDATED FINAL SAFETY ANALYSIS REPORT OPRM Cell Assignments (Channel 1)

FIGURE 7.2-17 (Sheet 1 of 4) Rev. 13 09/06

LIMERICK GENERATING STATION UNITS 1 & 2 UPDATED FINAL SAFETY ANALYSIS REPORT OPRM Cell Assignments (Channel 2)

FIGURE 7.2-17 (Sheet 2 of 4) Rev. 13 09/06

LIMERICK GENERATING STATION UNITS 1 &2 UPDATED FINAL SAFETY ANALYSIS REPORT OPRM Cell Assignments (Channel 3)

FIGURE 7.2-17 (Sheet 3 of 4) Rev. 13 09/06

LIMERICK GENERATING STATION UNITS 1 &2 UPDATED FINAL SAFETY ANALYSIS REPORT OPRM Cell Assignments (Channel 4)

FIGURE 7.2-17 (Sheet 4 of 4) Rev. 13 09/06 L..-______

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OUTBOARD VALVES (DIV 2)

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT ISOLATION CONTROL SYSTEM FOR MAIN STEAM LINE ISOLATION VALVES FIGURE 7.3-1

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MOTOR CONTROLLER DIVISION I ESSENTIAL DIVISION" ESSENTIAL VALVE CLOSING POWER VALVE CLOSING POWER K1..L K2 -L

---I~_I---------------_I~~I-LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT ISOLATION CONTROL SYSTEM USING MOTOR-OPERATED VALVES FIGURE 7.3-2

AIR AIR SUPPLY EXH SPRING LOADED AIR OPER SLAVE CYL SPRING AND, AIR WILL CLOSE VALVE LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT MAIN STEAM LINE ISOLATION VALVE CONTROL DIAGRAM FIGURE 7.3*3 Rev. 5, 4/96

Q -LOW REACTOR WATER LEVEL (LEVEL 1)

G -LOW REACTOR WATER LEVEL (LEVEL 3)

@ -HIGH DRYWELL PRESSURE (S) -REACTOR LOW PRESSURE PERMISSIVE e -

ADS TIME DELAY e

-CS OR RHR PUMP RUNNING PERMISSIVE HIGH DRYWELL PRESSURE BYPASS TIME DELAY START ADS START CS CS, RHR START RHR A LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SYSTEM LEVEL AUTOMATIC INITIATION LOGIC-ADS, CS, RHR FIGURE 7.3-4

HPCI START HPCI o

-REACTOR VESSEL WATER LEVEL 8

-HIGH DRYWELL PRESSURE LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT AUTOMATIC INITIATION LOGIC-HPCI FIGURE 7.3-5

VESSEL LEVEL SENSORS DRYWELL PRESSURE SENSORS TRIP LOGIC ACTUATOR EQUIPMENT MANUAL CONTROL ELECTRICAL DIVISION DIV..

o SEE FIGURE 7.1-4 00 PUMP ONLY DIV..

90 0 TO 180 0

DIV 3 DIV 3 180 0 TO 270*

DIV 2 0° TO 90"

'DIV 2 DIV 1 270 0 TO 0" DIV 1 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT EMERGENCY CORE COOLING SYSTEM (ECCS) SEPARATION SCHEME FIGURE 7.3-6

LGS UFSAR Figures 7.3-7 and 7.3-8 Deleted

MANUAL RESET MANUAL INITIATION PB CR SEAL-IN AUX DEVICE CR SEE NOTE 10 CONTROL SWITCH IN 'OPEN' POSITION RMS CR L!

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[L-__________________________________ ~AI~R~C~IR~C~U~IT~8~R=E=A~KE~R~(~5~2~l_=__. __________________________________ ~1 CORE SPRAY PUMPS COOIA,CODlB,COOIC,COOIO NOTE 2 iii 3

.. c..

  • Z"'8)(IZ~AD <71 (GZ (E.<'\\-\\O~o)

I.

~~~E~et,:[~~t ~~I~i:;" 5o'i:~~CL ~~rs~~rJ. 'SI~i.!'i.R.isr!~~D~LE~E.Nc.£ AFTER LOW CO"lOITIC): A.

WIT~ PLANT or~ tWRHAL AIJ'llIARY PQI-J'ER ACTIVE

?Ufl?I.A~C STAR"rSAFTER IOSEe DEI-"'

F004A F0048 FOOs F037 FOISA FOISB F03lA F0318

~

ACT I VE PUMP COOlA & C COOl8 & 0 S (0 STAIl;T5 AI'TElO. IS 5EC. DE.L.... '(

OPE.s A<l£R PEAC L!7W PREIS. PERM.

I OP(Ns AFlEE REAC LOW PRESS. P[RM.

OP[~S AfTER REAC lCW PRESS. P[IU*I.

I ()P(NS AFTER REAC lO" PRESS. PERM.

CLOSES IF DP£,

  • NO DELAY I CLOSES IF OPE'
  • NO DELAY CI DSES AFT£~ flOW ESU6liSHEO I CLOSES AFTER FLew ESTABLISHED WITH PLANT Of< STANDBY DIEsn POW£R

.sT)lr.R\\~ AF"TER. i 5.E..C C~l-A.Y START!:>.... nE....,

~E.C DE.'-.........

~

SAME SEQUENCE AS CONDITIO; A

2.

OIV 2 CIRCUIT IDENTICAL TO CIRCUIT FOR OIV I. DIV 3 & 4 PARTS IDENTIFIED AS FOLLOWS

!UU DIV 2 QJ.L1 DIV 4 PLt1P COOlA COO1B COOIC COOIO MIN fLOW BYPASS VALVES f03lA F031B OUTBOARD I SOL. VALVE fOO4A F004B INWARD ISOl. VALVES f005 F037 TESTA8LE CHECK VALVES fDQ6.\\

F006B PUHP sueT ION VALVES fOOlA fOOlB fOOIC fOOl" TEST BYPASS VALVES fOl51 FOISB HltH ORYWEll PRESS 821-.694A, E N694B.r NE94C. t N6940.1""

REACTOR VESSEL LEVEL 821-16914,E N6918, f NE91C,t N691D.h REACTOR PRESSl:;lE 8ZI-.690A, E, N690B,F,I<.,P N600C,G N600D."

J,N

3.

PUHPMOTOR CIRCUITS SHAll PROV!IE fOR OVERLOAD PROTECTI(JO;. OVERLOAO RELAYS TO BE APPLIED SO AS TO MAINTAIN POWER AS LONG AS POSSIBLE WITHOUT II"I'1EDIATE DAHAGE TO MOTOIi 0Ii HARM TO ENERGIZED PNR SYSTEM. VALVE MOTORS SHALL BE PROVIDED WITl".

OVERLDAD TRIP AND BREAKER SHORT CIRCUIT PROTECTIVE TRIPS.

4.

MOTIVE POW£R FOR OIV. 1.2.l & 4 PUMPS SHALL ORIGINATE FROM A DiffERENT EMERGENCY AC BUS. POWER FOR VALVES IN EACH DIV SHAll ORIGINATE FROM THE SAME BUS SUPPLVlNG PUHP POWER. CONTROl POWER fOR PUMPS & VALVES or OIV 1.2.3. & 4 SHAll 8E FROM A OlfFER[Nl SOURCE..

5. *. SWITCHGEAR DEVICE FUNCTION NUMBERS AISI SPEC. C37.2.
6.

ALL EQUIPMENT AND INSTRUI1ENTS AIlE PREFIXED BY SYSTEM NO. EZI UNLESS OTHERWISE NOT"

7.

FOR LOCATION AND IDENTIFICATION Of INSTRl!1ENTS SEE INSTRLt1EHT DATA SHEET REF. 11.

8.

SEE REFERENCE P&IO'S HI! ADDITlIJ'AL INFORJIATION ON ALARMS. VALVE INDICATING LI GHTS AND PROCESS INSTRLt1ENTA TlOII.

9.

OIV I-A,E,J.N, DIV 2*8.F,K.P, OIV l-C,G, DIV 4-D,H.

10.

UNLESS OTHERWISE NOTED ALL CONT!OL SWITCHES SHALL BE TYPE, 3 POSITION SWITCH "CLOSE" *. "AUTO" * "OPEN" SPRING RETURN TO "AUTO" fROM "CLOSE" OR "OPEN" POSITION, PULL TO STDP IN ALL POSITICJlS.

12, THE CORE SPRAY SYSTEM SHAll BE DESIGNED IN ACCOROANCE WITH REF. 10.

13.

LAMPS TO BE LOCATED BEL!7W RECULAR CORE SPRAY ANNUNCIATORS. LECENO AS SHOWN.

14.

SWITCH TO SE LOCATED BELOW LAM/S. SIoIITCH TO BE 2 POSI1ION "NORMAL" _ "INOP".

15.

IU:PRt:'CNT,r.T1\\1t ~

PllRAU.EL TORQUE 5Wrn:H CD1rl6INATIDN Rt:FER TO RtFl:RE:NCC I~

I/o

~.r,:~~~ ~G~~Ltu'lfP~,r6"~ ~~L~~':-16~vrd'E. PUMP RUIIINIt.!G REFERENCE DOCUMENTS*

I. NUCLEAR 80 ILER SYS TEM P& 1 D

2. NUCLEAR BOILER SYSTEM FCD
3. RESIDUAL HEAT REHOVAL SYSTEM FCD
4. CORE SPRAY SYSTEM P&ID
5. CORE SPRAY SYSTEM DES. SPEC
6. HPCI SYSTEM rCD
7. RC IC SYSTEM FCD
8. LOGIC SYMBOLS
9. RHR SYSTEH P&IO
10. ELECTRICAL EQUI P SEPARATION fOR IAfEGUARD SYS II. INSTRUMENT DATA SHEET It. CORE 5PRAY 5YSTE.M I:LEM. 01"'-

MPL ITEM NO.

B21-IOIO 821-1030 ElI-1030 EZI*IOIO E21-4010 E41*1030

£SI-IOlO A41-1030 EII*IOIO A61-4050 E21-30S0 UI-1040 729E613AD, SHT.1, REV. 10 Per NEI 98-03, this Figure in it's entirety is classified as HISTORICAL.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CORE SPRAY SYSTEM FCD (SHEET 1 OF 2)

FIGURE 7,3-9 Rev. 11 9/02

LGS UFSAR Figure 7.3-10 Deleted

LGS UFSAR Figures 7.3-12 through 7.3-25 Deleted

~FLHS mANS INOfJoA INOSOS INOSOC INO~OD INOS/A I"'OSI B INOBle INoel D

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Lf!".. 1 3 AOS(~)

A 0 s (C)

J.~vel 2.

II I.~vel ~

II II Acre

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~RCS 1/

I LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT LEVEL SENSOR CONNECTIONS FIGURE 7.3*26 REV. 7 12/97

BOTTOM OF TOP GUIDE7~

II LOCATION OF DETECTOR DURING NORMAL REACTORl STARTUP It~!::-E 120.00 STROKE LOCATION OF DETECTOR DURING NORMAL REACTOR OPERATION

...J UJ

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MOTOR & SWITCH LEADS j IN*CORE HOUSING AND GUIDE TUBE WASHER NUT SEAL ADAPTER GEAR BOX DRIVE MOUNT BEARING LOAD ADJUSTMENT DRIVE TUBE CABLE GUARD CONNECTION POINT OF DETECTOR CABLE CORD GRIP LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SRM/IRM NEUTRON MONITORING UNIT FIGURE 7.&,2

MOTOR FLEXIBLE CABLE POSITION SWITCHES DRIVE CONTROL MONITOR CIRCUITRY LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DETECTOR DRIVE SYSTEM SCHEMATIC FIGURE 7.6-3

FISSION CHAMBER DETECTOR DETECTOR DRIVE t

FLEXIBLE DRIVE BIOLOGICAL SHAFT SHIELD= __

""'"1 L..J" MOTOR MODULE VOLTAGE AMPLIFIER &

PRE-

~TTENUATOR~--~

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~JMIt-115' ILOW LEVEL

~15v HIGH LEVEL I

CALIBRATE

& DIODE LOGIC UNIT RANGE SWITCH INVERTER MEAN SQUARE ANALOG OPERATE &

CAL.IBRATE I---REF SWITCH TRIP RESET OPERATIONAL AMPLIFIER

~

r-£ZJ-J OPE RATE & 1 _ I I--.... :.---t CALIBRATE J W'

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SWITCH LOCAL METER COM

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.~ REMOTE

>RECORDER

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TRIP I------t (HI-HI)TRIP ON LEVEL

~

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~

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_ (HI) ALARM ON LEVEL TRIP SET -----.....

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~~=-I_~ _____ ~

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TRIP ALARM ON LEVEL l+.;:;:!

I-----il TRIP SET 1------......

...---------,LOCAL, LAMP MU~

U MODULE INTERLOCKS TRIP

~ }TR IP OUTPUT INSTRUMENT INOPERATIVE 1------1

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Per NEJ 98-03, this Figure in it's entirety is classified as HISTORICAL.

LIMERICK GiCNERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT FUNCTIONAL BLOCK DIAGRAM OF IRM CHANNEL FIGURE 7.6-5 Rev. 11 9/02

TIP CALIBRATION TUBE LPRM DETECTOR

~~~-- DETECTOR THIMBLE

--:....-.-- FUEL BUNDLE CONTROL ROD BLADE I,,,

I TIP CALIBRATION TUBE---r'--.tr LPRM DETECTOR (TYP.I--'_.......

PRESSURE VESSEL

___ } CABLES TO CONTROL ROOM LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT POWER RANGE DETECTOR ASSEMBLY LOCATION FIGURE 7.8-6

~

I

~

APRM 120 Vac Bus A APRM 2-out-of-4 Voter A1

~

K1A I

K4A

~

K1E K4E APRM 2-out-of-4 Voter A2

~

I K1C

~

K4C

~

I K1G

~

K4G To RPS Logic A1 To RPS Logic A2 NOTE:

Contacts are shown in normal operation position.

APRM 120 Vac Bus B

~

I

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APRM 2-out-of-4 Voter B1 K1B K4B

~

I K1F

~

K4F To RPS Logic B1 APRM 2-out-of-4 Voter B2

~

I K1D

~

K4D

~

I K1H

~

K4H To RPS Logic 82 LEGEND: K1 A, K1 B, K1 C, K1D, K1 E, K1 F, K1 G, K1 H = (APAM Neutron Flux - Upscale Q[ APAM Simulated Thermal Power - Upscale Q[

APAM Inop) and (APAM Not Bypasses)

K4A, K4B, K4C, K4D, K4E, K4F, K4G, K4H = (OPAM Upscale Trip) and (OPAM Not Bypassed)

S3 = APAM Bypass Switch LIMERICK GENERATING STATION UNITS 1 &2 UPDATED FINAL SAFETY ANALYSIS REPORT APRM CIRCUIT ARRANGEMENT FOR REACTOR PROTECTION SYSTEM INPUT FIGURE 7.6-7 Rev. 13 09/06

SRM IRM LPRM APRM OPERATION

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HIGH DOME PRESSURE (NOT SEALED IN)

LOW WATER LEVEL 2 TRIP TYPICAL OF LOGIC CHANNELS RRCS ARI READY FOR RESET (NOTSEA_LE_~..

IN.), ~ __________________======================:;~~ __ ~~ __ ;-_________________

R_R_C_S_A_R_'_'N_'_T_'A_T_'_O_N~~

R RCS MANU AL I N \\T~I~A~T.:.:.'O:.:N4-____ -!:.A~R~1.!!M~A~N~U:.:;A~L:..:'.:..:N.:..;'T:..:.':..:A..;..,;.;

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(SEALED IN)

TO

~

9 SEC LOW WATER LEVEL TRIP 2 (SEALED IN)

RRCS MANUAL INITIATION (SEALED IN)

RRCS RESET TO 25 SEC RRCS POTENTIAL ATWS ANNUNCIATION 118SEC APRM NOT*DOWNSCALE TRIP TRIP RECIRC PUMPS RRCS FW RUNBACK INITIATION SLCS INITIATION RRCS RWCU ISOLATION RRCS CONFIRMED ATWS (ANNUNCIATION)

RRCS RESET RRCS READY FOR RESET Note: This figure is based on GE Drawing Number 944E194TR.

Per NEI 98-03, this Figure in it's entirety is classified as HISTORICAL.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT RRCS INITIATION LOGIC FIGURE 7.6-10 Rev. 11 9/02

BACKUP SCRAM VALVES-ENERGIZE TO VENT LINE INSTRUMENT AIR FllOB FllOA RPS SIGNAL C

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~-----II TO F180 & F18l RPSA TO HCU BANK B TO HCU BANK A F009 *.,..

I EXH RPS B EXH EXH ND~

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LEVEL 8 NORMAL WATER LEVEL 7 LEVEL 5 EL. 310' - 2 %"

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LGS UFSAR Figure 7.7-2 Deleted

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.. ---:....----oor---_.....

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~!ESf'o!'m'NC O'i'~H~TiCN TAKING PLA<::F.

LIMERICK GENERATING STATION UNITS 1 & 2 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR MANUAL CONTROL SYSTEM OPERATION FIGURE 7.7-3 Rev. 11 9/02

START

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LIMERICK GENERATING STATION UNITS 1 & 2 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR MANUAL CONTROL SELF-TEST PROVISIONS FIGURE 7.7-4 Rev. 11 9/02

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Rev. 17 09/14 Adjustable Speed Drive (ASD)

FIGURE 7.7-7A Rev. 16 09/12

t TYPICAL FOR EACH LOOP TURBINE CON*

TROLMECH ADMISSION VALVE INITIAL PRESSURE REGULATOR TURBINE BYPASS VALVES M -INDUCTION MOTOR G - AC GENERATOR C - AOJUST ABLE SPEeD COUPLING

~

RECIRCULATION FLOW CONTROL COMPONENTS LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT RECIRCULATION FLOW CONTROL FIGURE 7.7-7 Rev 08 1V98 FIGURE 7.7-7A Rev. 16 09/12 UNIT 2 MG Set Unit 2 FIGURE 7.7-7A Rev. 17 09/14 Figure 7.7-7A Deleted LGS UFSAR

LGS UFSAR Figure 7.7-8 Deleted

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TO 'tliE GATt eu~ewr

\\JNe~A NORMAL OPIRATJNG OONOt"10NS.

LIMERICK GENERATING STATION UNITS 1 & 2 UPDATED FINAL SAFETY ANALYSIS REPORT SIMPLIFIED DIAGRAM TURBINE PRESSURE & SPEED LOAD CONTROL REQUIREMENTS FIGURE 7.7-9 Rev. 11 9/02

INTENTIONALLY LEFT BLANK LIMERICK GENERATING STATION

~ITS I AND 2 LPOATED FINAL SAFETY ANAlYSIS REPORT TRAVERSING INCORE PROBE ASSEMBLY (UNIT 1)

(SHEET 1 OF 2)

FIGURE 7.7-10 Rev. 1 July/en

~Outer Sheath (Ground)

~Center Conductor Guard Sheath OAL 130-170 ft.

DIA 0.2581~

(MAX) orA 0.213 11 (REF)

SENSITIVE LENGTH 1.00 11 REF 0.6g" LIMERICK GENERATlttJ STATIa.

lftlTS 1 AND 2 UPDATED FlNAL SAFETY ANALYSIS REPORT TRAVERSlNG INCORE PROBE ASSEMBLY (SHEET 2 OF 2)

FIGURE 7.7-10 Rev. 1 Jul /gt

LGS UFSAR Figure 7.7-11 Deleted

INTENTIONALLY LEFT BLANK LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT RPV CONTROL DISPLAY (SHEET 1 OF 6)

FIGURE 7.7-12 Rev.2 July/Q2

INTENTIONALLY LEFT BLANK LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAl SAFETY ANAlYSIS REPORT CONTAINMENT CONTROL DISPLAY (St£ET 2 OF 6)

FIGURE 7.7-12 Rev.2 July/Q2

INTENTIONALLY LEFT BLANK LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CRITICAL PLANTS VARIABLES DISPLAY (St£E T 3 OF S)

FIGURE 7.7-12 Rev.2 July/g2

INTENTIONALLY LEFT BLANK LIMERICK GENERATING STATION

~ITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT TREND PLOT DISPLAY (SHEET -1 OF 6)

FIGURE 7.7-12 Rev. 2 J uly/g2

INTENTIONALLY LEFT BLANK LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT TWO-DIMENSIONAL PLOT DISPLAY (9£ET 5 OF 6>

FIGURE 7.7-12 Rev.2 July/C)2

INTENTIONALLY LEFT BLANK LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT VALIOATION OISPLAY (SHEET 6 OF 6)

FIGURE 7.7-12 Rev. 2 J uly/g2

PE.R NEI'9f4J~03t TfifS.FfGURE It~ ITS ENTlR.ETY* IS CLASSJF1ED AS HtSTO:RJCAL LIMERICK GENERATING STATION UNITS 1 & 2 UPDATED FINAL SAFETY ANALYSIS REPORT FUNCTIONAL BLOCK DIAGRAM OF SRM CHANNEL FIGURE 7.7-13 Rev. 11 9/02

00 02 04 06 08 10 12 14 16 18 20 22 2426 28 30 32 34 36 38 40 42 44 46 48 50 52 54 56 58 60

  • TYPICAL ROD YIELDING FOUR STRING INPUT TYPICAL ROD YIELDING THREE STRING INPUT TYPICAL ROD YIELDING TWO STRING INPUT ffi TYPICAL ROD YIELDING ONE STRING INPUT

~ LPRM INPUT UPON ROD SELECTION A

RBM ODA 'A' B

RBM ODA 'B' LIMERICK GENERATING STATION UNITS 1 & 2 UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 7.7-14 RBM ROD SELECTION COMBINATIONS Rev. 10 10/00

120 118 116 114

~

w en

z 0 c...

112 en w

a::

w

~

w a::

....J 110 w

z z <<
r:

<.)

.:2:

OJ a::

108 106 104 102 100 o

BCCD1 CHANNEL BCCD2 CHANNEL 2

4 6

CONTROL ROD POSITION (FT WITHDRAWN) 8 10 12 14 LIMERICK GENERATING STATION UNITS 1 &2 UPDATED FINAL SAFETY ANALYSIS REPORT TYPICAL RBM CHANNEL RESPONSE TO CONTROL ROD MOTION (NO FAILED LPRMS)

FIGURE 7.7-15 Rev. 10 10/00

o c

8 A

LPRM 1 LEVELS CRUCIFORM CONTROL BLADE

&.PRM DETECTOR

~

BCCO, CHANNEL

~

BCC02CHANNEL o NOT IN SYSTEM


BOTTOMOFCORE LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT NEW RBM BCCD1/BCCD2 LPRM ASSIGNMENT FIGURE 7.7-16 Rev. 5, 4/96

0\\° E-i

z H o

~

E-i

~

Cf) 130 NOMENCLATURE ILLUSTRATION ONLY NOT TO SCALE 125 120 115 110 105 100 94

~ :z o

H t9

~

LTSP

          • ~

Cf}

H

r::

E-i

z H

ITPS Cl

    • .* ~.***.*.********* ~...*******..***********.************************* J.,...-______

~

H

()I

~

~

HTSP E-i

        • 0*************************************************...................................................
z 30 45 I

LPSP RBM PERCENT DOWNSCALE 60 IPSP POWER 70 90 HPSP LIMERICK GENERATING STATION UNITS 1 & 2 10 UPDATED FINAL SAFETY ANALYSIS REPORT POWER DEPENDENT RBM TRIP NOMENCLATURE FIGURE 7.7-17 Rev. 10 10/00