ML17216A792
| ML17216A792 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 09/19/2016 |
| From: | Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML16357A167 | List:
|
| References | |
| Download: ML17216A792 (67) | |
Text
LPRMS A1 81
....._ .... TJ1IIP5 TRFS ....._ ....
J.OGIC LOGIIIC OU'IPUTA.
OUI'PUTS
- - - GIRO&.P 1 c--- --- --,
SCRAM GRClPFtLL BOX OR DllVALENTI L:----r----.J r:.------ -. ..... .--.I SCIVdit G'IIOUPI!IU5WAYOR EQUIVAlaT L .-~-.~~---.I
.....-----"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 LIMERICK GENERATING STATION UNITS 1 & 2
- NOTE: Per NEI 98-03, this UPDATED FINAL SAFETY ANALYSIS REPORT Figure in it's entirety, is RPS SEPARATION CONCEPT classified as HISTORICAL.
FIGURE 7.1-1 Rev. 11 9/02
MTtONAL QltTtONAL COMMOfif C~
""oeESS ,."oeESS TAft TA' TAt' TAitt TAl'
- TP LOGtC ..OGle: ... OGtC LOGIC tAU flU .1" fA2.
1, ......- ........------I AUXft.LAYS ""'."fLAYS t! DlV I tN80..AO
...."'VAL I MoUtUAI.
OUTIO.. lltO
,"VII VALVES SWitCHES t SWJ1"CHES VALVIS WI",WAY I
- I I
OJV, MOTO" STARTeA' POW 'DC NORMALLY
- ACA/OR
'1010 I
I Me I
MO HOfltMAU.. Y SOL I SOL NOIitMALLV DE*ENERGIZED I D£*INlfIIGtZIO I
I
,,.'OA.RD I OVTlOAfilO
.SOLAT'ON t 'SOLATION V4\.VES VALVES NSS$S SEPAAATtON CONCEPT PER NEr 98..Q3, THIS FfGURE IN ITS ENTIRETY IS CLASSIFIED AS HISTORICAL LIMERICK GENERATING Station
.- UNITS 1 & 2 UPDATED FINAL SAFETY ANALYSIS REPORT PCRVICS SEPARATION CONCEPT FIGURE 7.1-2 Rev. 11 9/02
_ _ _ _ M."'~' _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ "~_,,* _ _
- _ _ _' _ _ _ _
eOMMO~ COMMON PROCesS PROCESS TAP" '. TAP' tHY 1 CONDUIT ..
~'$
fAA'£tS.
FAft$A*n~ . --,
. lOGIC
- ... Tl'Ill>I.OGtc 01 'mIl' UiGIC C ....
I~_~
AUX1L.fARYRE LAYS .
lN80ARP VAt.V~$
MANUAL SWITCH II *M.At\~UAL SWtrefl AUXn;JARY RELAYS QtJnlt)A.flO VAlV~$
- 2 JHl)JV.~ OUAt,..
CA.at:~ fNA
. 1'. ~-~-~-::!MJsrw-.l-t
. ...;-.'-'.........- .....--._......__ ,J SlNGLE $..JNGl~
RAC£WAY I
.' AAC!WAV I
I
'COMMON RAC!'WAV I
I I
LIMERICK GENERATING Station PER 'NE19$-03; THtS FIGUREfN. rrs UNITS 1 & 2 ENTIRETYJS CLASSIFIED AS UPDATED FINAL SAFETY ANALYSIS REPORT
'HfSTORJCAl MAIN STEAM LINE ISOLATION SEPARATION CONCEPT FIGURE 7.1-3 Rev. 11 9/02
e MUl T I~l f C ,ReUI T IH "CTon IIf <;SI l
-L -L l f liE l Sf NSOJ1<; T
,../,,~__-,I
+
OTHER
+
OTHfR 1'"'=t:=:t=::t:=======:-1~1 po '-
!HII III WIIlfWAY OIV I (lIV I 0111 III I,"~' JT INPUT TERMINAL 80)(
COllI TAINING Dill I RetC CONTROL 1
TO
+....L~
0111 III WI~~~~Y I~~____
_--I'--_ __ -_ - -_- -_ -'_ ____,IO<.Ie elRe7'1T EOUIP r-RCte CONTROL lor.K Dill III PANEL CABINET Dill I NOTE CIRCUITS FOR RCIC INITIATIONS UTILIZE CONTACTS ElfCTRICAll Y SEPARATE FADM THOSf USE D ~OH OTHER 0111 III INPUTS LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT RCIC SENSOR SEPARATION SCHEME FIGURE .7.14'
~
ZW O~f-z ...J -<<U
'-r--- 0 !::f-<< 0
'-..or-
~...J 0 oozf-wa: IU
>f-o-z 0..<<0 wO
...Jz >z
...Jz!:: N~U ...JW 0t9 <t:0~ <<...J 00-
_00 >UOO ~ >~
- I I:
'-'~ ------------,
I
,-100--
I I
I U
~
0 I
f-
~oo w
00 I oo~
...JU oozg f--UZ I
00 Wa:...J ~QwQ f-W>f-I
>f-a:
...JZW Z~...JU5 O...J<<O I
<t:0f-
>U~ UU>o.. I
~
I'.
I
~~
\.
I LO I
0)
I II ~
I
" " I I
I f-U Wf- I 00-
'-'r' w~
a: en LO
- 0) I '-~
I Jr---i l I I 1 1__ ..,
zl 0
~I...J
~-
<t:1<t:
...J z z o t9 enl-
- en Qu f--
<t:t9
...JO
'-~
0...J
~
1 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT TYPICAL ISOLATION SIGNAL RESET SCHEMATIC FIGURE 7.1-5
\ ~
I ~~
- r- -040A "RUN" I ~~
- r- -030A CLOSE I
-r- 95-2 SGTS OPEN ON
-" l UNIT 1
~r-ISOLATION SIGNAL HS
-r-
-76
-030A OPEN OPEN ON k:-
- ..- UNIT 2 ISOLATION SIGNAL
- ~ 95-1
--; ~
4~
SV L:.~ OF 95-1 95-2 I""~ HV-76-030
( .(
J )
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
"'.untON MON'T~I"G OPRM TfU, MODISWITCM I..... UN NEUTRON MAIN STEAM MONITORING LINES ISOLATED IRM TRIP I
TURBINE MODE SWITCH MODE SWITCH CONTROL NOT IN RUN IN RUN VALVE FAST CLOSURE I TURBINE STOP VALVE CLOSURE
[ MANU",
NUCLEAR SYSTEM PRESSURE HIGH SCRAM DISCHARGE VOLUME WA TER lEVEL HIGH NEUTRON MONITORING APRM TRIP I
- REACTOR DISCH VOL MODE SWITCH DRVWELL PRESSURE HIGH VESSEL WATER HIGH lEVEL I""-
IN SHUTDOWN LEVEL LOW NOT BYPASS II I
MODE SWITCH MODE SWITCH IN REFUEL OR IN STARTUP
[ SHUTDOWN OR RUN I
I SCRAM I
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
TRANSMfTTERS c D 8
o 0*
TAIPSYSTEM A TRIP SYSTEM a POWER aus CHANNELS POWER BUS TA'PSYSTEM /It. TRIP SYSTEM a I_---A'--_\
,..._--J!\.\o.._ _\.
I "'
o NOTE; CONTACTS SHOWN IN NORMAL. CONDiTt ON At 81 82 REACTOR PROT~CT10N SYSTEM LOGICS COHFIGURAT10N FOR:
SCRAM DtSCHARGE VOL.UME HIGH WAl"ER L.EVEL TURBINE CONTROL VALVE FAST CLOSURE DAYWEL.l HIGH PRESSORE REACTOR VESSEL LOW WATER L.EVEL REACTOR VESSEL HfGH PRESSURE PER NEI 98-03. THIS FIGURE IN ITS ENTIRETY IS CLASSIFIED AS LIMERICK GENERATING Station HISTORICAL
.- 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 TRIP TRIP TAIP LOCtC LOGIC LCOle lOGIC A1 A2 8t 112 SCRAM CONTACTORS E C G s H SCRAM CONTACTOR LOGICSASSOCrATED SCRAM CONTACTOR LOGICS ASSOC.ATED
~~ ___________
WITH TAIP SYSTEM A PtlOT SOLENOIDS A~----------_,
wrTH TRrp SYSTEM 8 PILOT SOLENOIDS
,r-----------~~---------- __,
A r a ,
c o I H GROUP 1A GROUP 2A GROUP 3A GROUP 4A GROUP 10 GROUP 2S GROUP 38 GROUP 4S IC"AM "LOT SCRAM "'LOT ecAAM PILOT ICRAM "LOT IeRAM PILOT *=RAM ,.1l.OT SCRA.. "LOT acAAM P'LOT
'OI..£NO'OS SOUNO.OS 1Ot.£NOIOS: S01.£NOtOS SOLENOIDS SOLENOIOS SOUNOIOS SOl£NOlbS NOTE:COHTACTSSHOWNIN NORMAL COHDtTJON PER NEt 98-03. THJS FIGURE IN ITS ENTIRETY IS CLASSIFIED AS HISTORICAL c H o
LIMERICK GENERATING Station
- SCRAM CONTACTOR LOGIC FOR SCRAM CONTACTOR LOGIC FOR UNITS 1 &2 UPDATED FINAL SAFETY ANALYSIS REPORT BACKUPSCAAM BACKUP SCRAM SCRAM CONTACTORS AND VALVE A VALVE B SCRAM CONTACTOR ACTUATOR LOGICS (SCHEMATIC)
FIGURE 7.2-4 Rev. 11 9/02
TRIP '"OGle At TURBlN E STOP VALVE CLOSURE A TUABtN E CONTROl..
VALVE FAST C CLOSURE C
A C
OAYWEU.
HIGH PRESSURE NUCLEAR SYSTEM HIGH PRESSURE REACTO R LOW WATER L.eV£L EJ MON\T01=tING NEUTRO N SYSTeM .
A A MANUAL MANUAL SCRAM SCRAM R
G SCRAM CONTACTORS NOTE~ CONTA CTS SHOWN eN NORMA L CONOITION A CONTAC TS ARE RESET LIMERICK GENERATING Station S CONTACTS ME SEAUN G UNITS 1 & 2 UPDATED FINAL SAFETY ANALYSIS REPORT PER NEI 98-03, THIS FIGURE 1N ITS LOGIC S FOR TRIP SYSTE M A ENTIR ETY IS CLASSIFIED AS (SCHE MA TIC)
HISTORICAL FIGURE 7.2-5 Rev. 11 9/02
NEUTRON MONITORING SYSTEM TRIP CHANNELS IRM DETECTOR LPRM DETECTOR (OTHER LPRM DETECTOR DETECTORS)
AMPLIFIER AMPLIFIER (LPRM) AMPLIFIER (LPRM)
NEUTRON MONITORING SYSTEM AMPLIFIER-SUMMER A A BYPASS UPSCALE APRM CHANNEL TRIP (ONE OF FOUR)
OTHER APRM CHANNELS IRM CHANNEL A (ONE OF EIGHT)
TWQ-OUT-OF-FOUR VOTER A1 (ONE OF FOUR)
A IRM UPSCALE MODE SW A IN RUN TRIP APRM Neutron Flux - Upscale E Q[ APRM Simulated Thermal A Power - Upscale Q[ APRM lnop) E smQ (APRM Not Bypassed)
REACTION PROTECTION SYSTEM Il (OPMR Upscale Trip) gnQ E o~
A (OPRMN:::NITORING SYSTEM LOGICS (TWO OF EIGHT)
E i
~
NEUTRON MONITORING o NOTE: CONTACTS SHOWN IN NORMAL CONDITION.
SYSTEM CD LIMERICK GENERATING STATION TRIP SYSTEM A 1 UNITS 1 &2 LOGIC (ONE OF FOUR)
UPDATED FINAL SAFETY ANALYSIS REPORT
Upscale Q[ APRM Inop) smQ (APRM Not Bypassed)
RELATIONSHIP BETWEEN NEUTRON
MONITORING SYSTEM AND REACTOR PROTECTION SYSTEM NOTE: PER NEI 98-03, THIS FIGURE, IN IT'S ENTIRETY, IS CLASSIFIED AS HISTORICAL. FIGURE 7.2-6 Rev. 13 09/06
TRIP SYSTEM A POWER BUS I TRIP SYSTEM BPOWERBUS I I I
I 1 ..J~ 1 -.J~ 1 .-J~ 1 --.J~
"" ~
-,I- -,I-
-,I- ~5 r--3 r--3 -5 -/- - 3 -/- - 5 -5 r--3 MSV-3 MSV-4 MSV-1 MSV-2
~ ~' c I I TURBINE STOP VALVE CLOSURE CHANNELS A C B D A1 I I B1 I
B1 REACTOR PROJECT SYSTEM LOGICS NOTE: CONTACTS SHOWN IN NORMAL CONDITION NOTE: THREE OUT OF FOUR STOP VALVES MUST CLOSE TO CAUSE A SCRAM LIMERICK GENERATING STATION UNITS 1 & 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONFIGURATION FOR TURBINE STOP VALVE CLOSURE INPUT TO RPS NOTE: Per NEI 98-03, this Figure, in it's entirety, is classified as HISTORICAL. FIGURE 7.2-7 Rev. 11 9/02
T,,'fI'VSTIM
- flOWeR IIU.
. STUM, LilliE 8 ITeAM LINE C ITIAMt..tNED MAIN:ItIAM UNE ISOLATiON CW_NEU CSWlTCH CONTACtS SHOWN 'N POSITIONS WHEN ISOLATION VALVES &..ISS 'ntANt.- C:LO$EOI
,"Ufl SYSTEM A TR'PSVSTf.'
-- }u !if CG lf~
/E~ E~
l:{' SF' At A2 at fII£ACTORftflOTECTION SY$TEM LOG,es fCOH'tACD SHOWN .... NORMAL.CONOIT1OM qy::
F022A. $TUMUNE4.NeoN'tDVALYE F022C .* :1T*AMU"'~C'.r~ VALve FoaA
- SUAM LINE ~OU'f1IOAROVALVE FG2IC .* ..,..AM U_C.. ,~"O*YALVE
'0228
- STEAM'UN! a..ttIOARD VALVE FO:22O
- tTlAM Ll_D. tNaoAR'O VALVE to.a
- IIt1!AM UNI .. OUTIOAAO VALVE Foal)
- STEAM LtHEI),OU11IOAROVALV£ NOTE: ISOLATtOH OF THREE Oft MORE stEAM. UNfS WILL CAuse A SCRAM.
LIMERICK GENERATING Station UNITS 1 &2 UPDATED FINAL SAFETY ANALYSIS REPORT PER NEI 98-03, TH,IS FIGURE IN ITS ENnRETYtSCLASSIFIEDAS CONFIGURATION FOR HISTORICAL 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 LIMER ICK GENER ATING STATION UNITS 1 & 2 UPDATED FINAL SAFET Y ANALY SIS REPORT LPRM CHAN NEL ARRANGEMENT IN THE CORE AND APRM CHAN NEL ASSIGNMENTS FIGURE 7.2-9 Rev. 10 10/00
LGS UFSAR Figures 7.2-10 and 7.2-11 Deleted
I.: ""' ..I."............ T_
~~
~-----------------------------------------------------------,~~~~-~.------------------------------- ----------------------/--~
~----------------------------------------I~l~~------------------------~----------------------------------/
-~---~~ -~---_11--__,_-
---~~----- .. -
1====-*--=--_-_
LIl ....cw-s.c.-"w.~
~.C'T ....-
c..... ....
_l. sc ..... 10 11' ....
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
IM-198
- REFERENCE DRAWl NGS DWG. UFSAR NO. FIG. NO. - I
~ M~r~*~~~IN~~~~~~o~~~~E:S~~*~:~.5~E~~~~~i~~U~~~~~~~n~~:~*~:~u~;~~~n~~~r~~~
M-188 - UNIT 2 f
M-198 - KEY PLAN 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 .1 M-240 I. 2-56 fJ01f,:
i,Jl.II.~I .. TO"U4IIIP lIQIIl~f~"
~.", OOQIL ...-... ,.,... . . . ~,..~ " "
- 2. !If 1ft __ ** ." .... 412 FOR (LINE 'I\" ~ 'D" MA'~ STEAM VAlVE ""'ENTATION)
/
(
..' "~ I~~ F[£O"'ATER(~fF.)
t~,dJ, - '"
--.~.
o*
i ' I
,.-1.- . ." "
'M,:J-~M~'
SECTION C-C LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT
~~
~1"'ZI1 PIPING AND MECHANICAL:
REACTOR ENCLOSURE, UNIT 1.
SECTII)N C,* C. ~I I DRYWELL EL. 272'-9" M-230 , M-240 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..-_ _ _ _ _ _ "~, .. ,~ __ ~ ___ ~ _ _ _ _ _ _ _ _ ___'__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____I
ISOLATION TRIP SYSTEM A ISOLATION TRIP SYSTEM 8 ei~I ~!~ eT~ ;<:i so A I I C 8 I )
I I I r --,'J I , r .JJ I
I
'r_ -,
L I I INSTRUMENT I 8 I 1 C I L
AI
~ L ~ CHANNELS L .J L ...J CHANNEL A CHANNEL C CHANNEL 8 CHANNEL D AC POWER (REACTOR AC POWER (REACTOR PROTECT ION SYSTEM BUS A PROTECTION SYSTEM BUS 8 OR OR INSTRUMENT AC BUS A INSTRUMENT AC BUS B I 1.8
-:r::- - -:r:- -
1.D INPUTS FROM OTHER { I I
} . INSTRUMENT CHANNELS I I I
I A C I B D I
TRIP LOGICS FROM DC POWER FROM DC POWER FROM AC POWER BUS A BUS B FROM AC PCWVER A1. 1.8 A l l B J[ ][
( TRIP C I ID ACTUATOR f f C D LOGICS SOLENOIO ~ SOLENOIO ~
INBOARD VALVES OUTBOARD VALVES (DIV 1) (DIV 2)
ACTUATOR LOG ICS 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
ISOLATION TRI' SYSTEM A ISOLA TION TR IP SYSTEM I e~I A I I re I C ~ I~ I I I
r .., I 'r
_,J -, r l' 'r
_ ..J L_ l I
L_
, I CHANNELS I B 1 I 1
~ 0 C
L L .....J L :.J L :..J CHANNEL A CHANNEL C CHANNEL B CHANNEL 0 AC POWER (REACTOR AC POWER (REACTOR PROTECTION SYSTEM BUS A PROTECTION SYSTEM IUS I OR OR AC POWER AC POWER
.LA lC 1
-!---II---
B Y 0
--~---+/--} INPUTS FROM OTHER ...L.
- r: I TRIP CHANNELS { I I A C B o TRIP LOGICS AyB A .2:-~.----
T INBOARD VALVES (LEAK DETECTION INPUTS)
ACTUATOR LOG ICS
t.
c l__
. ~ B T
= ~T23= 0 OUTBOARD VALVES 1-:;1 1
L ___
K1 t ---,
VALVE CONTROL POWER
---J
,I MOTOR CONTROLLERS VALVE CONTROL POWER I
1~2f-1 L ___
K2 ~
~
I MOTOR CONTROLLER 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
SPRING LOADED AIR OPER SLAVE CYL SPRING AND, AIR WILL CLOSE VALVE AIR AIR SUPPLY EXH 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
START ADS Q -LOW REACTOR WATER LEVEL (LEVEL 1)
G -LOW REACTOR WATER LEVEL (LEVEL 3)
@ -HIGH DRYWELL PRESSURE CS, RHR (S) -REACTOR LOW PRESSURE PERMISSIVE e- ADS TIME DELAY e -CS OR RHR PUMP RUNNING PERMISSIVE HIGH DRYWELL PRESSURE BYPASS TIME DELAY START START CS 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
DIV .. DIV 3 DIV 2 DIV 1 0
900 TO 1800 180 TO 270* 0° TO 90" 0
270 TO 0" VESSEL LEVEL SENSORS DRYWELL PRESSURE SENSORS TRIP LOGIC ACTUATOR EQUIPMENT MANUAL CONTROL ELECTRICAL DIV .. DIV 3 'DIV 2 DIV 1 DIVISION o SEE FIGURE 7.1- 4 00 PUMP ONLY 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
o fii ReACTOR HIGH V~S5EL D~Y\"ELL LEVEL I TRIP PRESSURE LIS B21-CR PIS 621-CR ..c ..
- Z"'8)(IZ~AD <71 (GZ (E.<'\-\O~o)
N691A N694A
- ~/"
lIOTE. ~
START W W CR
/ , CR
/
PERMISSIVE WH,EN \
REACTOR
( PRUSUR[ 15
!\[LDW SETPOIIIIT J
~
PIS-OZI- cR N"90A 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-"'
S (0 STAIl;T5 AI'TElO. IS 5EC. DE.L ....'(
F004A OPE.s A<l£R PEAC L!7W PREIS. PERM.
HIGH F0048 I OP(Ns AFlEE REAC LOW PRESS. P[RM.
REACTOR VESSEL DRYIoIELL FOOs OP[~S AfTER REAC lCW PRESS. P[IU*I.
PRESSURE F037 I ()P(NS AFTER REAC lO" PRESS. PERM.
LEVEL I TRIP FOISA CLOSES IF DP£,
- NO DELAY MANUAL MANUAL PIS 621- FOISB I CLOSES IF OPE'
- NO DELAY LIS B21- CR RESET INITIATION N691E CR N694E F03lA CI DSES AFT£~ flOW ESU6liSHEO F0318 I CLOSES AFTER FLew ESTABLISHED W
PB CR ARMEO P&
CR
/:0,W CR /~CR P(RMI~SIV[ WHtN \
~
ACT I VE PUMP COOlA & C COOl8 & 0 WITH PLANT Of< STANDBY DIEsn POW£R
.sT)lr.R\~ AF"TER. i 5.E..C C~l-A.Y Rt:ACTOR START!:> ....nE.... , ~E.C DE.'-.........
( PRt55URt: 15 ~ SAME SEQUENCE AS CONDITIO; A SEAL-IN &ELOW !>tTPOINT
- 2. OIV 2 CIRCUIT IDENTICAL TO CIRCUIT FOR OIV I. DIV 3 & 4 PARTS IDENTIFIED PIS* !ilIA CR / AS FOLLOWS
" / ,-N~':.:.9..:..0£=-+-_ _-,
AUX DEVICE CR / W ,C.R j PLt1P
!UU COOlA DIV 2 COO1B QJ.L1 COOIC DIV 4 COOIO MIN fLOW BYPASS VALVES f03lA F031B OUTBOARD I SOL. VALVE fOO4A F004B 1 INWARD ISOl. VALVES TESTA8LE CHECK VALVES PUHP sueT ION VALVES f005 fDQ6.\
fOOlA F037 F006B fOOlB fOOIC fOOl" TEST BYPASS VALVES fOl51 FOISB HltH ORYWEll PRESS 821-.694A, E N694B .r NE94C. t N6940.1""
REACTOR VESSEL LEVEL i
821-16914,E N6918, f NE91C ,t N691D.h PERMI5$E WHEN \
SEE NOTE 10 J
(EQUIPME.t.lT PoWER ~~ AVAILAeLE PUMP HOT DR SUS REACTOR PRESSl:;lE 8ZI-.690A, E, J,N N690B,F ,I<.,P N600C ,G N600D ."
SY At:) 3. PUHPMOTOR CIRCUITS SHAll PROV!IE fOR OVERLOAD PROTECTI(JO;. OVERLOAO RELAYS TO CONTROL SWITCH IN 'OPEN' POSITION
\ BY AE LP J 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 RMS CR CQO.IT"DL SWITCH AC BUS. POWER FOR VALVES IN EACH DIV SHAll ORIGINATE FROM THE SAME BUS SUPPLVlNG IN CLOSE PUHP POWER. CONTROl POWER fOR PUMPS & VALVES or OIV 1.2.3. & 4 SHAll 8E FROM A PO-SITION OlfFER[Nl SOURCE..
IUAS , E-I 5. *. SWITCHGEAR DEVICE FUNCTION NUMBERS AISI SPEC. C37.2.
j ! I PERMISSIVE AFTER \
10 SECONDS TIME DELAY rOR PUMP A4 C
(
PERMISSIVE WHEN )
DIESEL WENERI<TOR
!IA£AKEA ('u)sED 6.
7.
ALL EQUIPMENT AND INSTRUI1ENTS AIlE FOR LOCATION AND IDENTIFICATION Of PREFIXED BY SYSTEM NO. EZI UNLESS OTHERWISE NOT" INSTRl!1ENTS SEE INSTRLt1EHT DATA SHEET REF. 11.
POIMI~IVE.
L! PERMISSIVE UNLESS INITIATION 0
( IN PULL TO STOP UNLE.55 \
j \ Dt~I~E CR / \I!II'AE I LI' /
INFORJIATION ON ALARMS. VALVE INDICATING SIGNAL PRESENT POSITION
\ D:~~E CR J \ RMS E-I J PERMISS'VE UNU:~ IN PUL L TO 15 R:>R
~EC OE.\...A"C" pu......,ps l 9. OIV I-A,E,J.N, DIV 2*8.F,K.P, OIV l-C,G, DIV 4-D,H.
! -.--,---Ij STOP POSITION sf( 0 10. UNLESS OTHERWISE NOTED ALL CONT!OL SWITCHES SHALL BE TYPE, 3 POSITION SWITCH t
- NOT!: IS \ RMS , E -I j PERMISSIVE AFTER 7 SEC. SEAL-IN "CLOSE" *. "AUTO" * "OPEN" SPRING RETURN TO "AUTO" fROM "CLOSE" OR "OPEN" POSITION, PULL TO STDP IN ALL POSITICJlS.
(
PERMISSIVE UNLESS
\
t TIME DELAY I
ovERTORO\IED WHILt: OPElIIUG
\--\A-U-X DEVICE CR j AUX DEVICE LP 12, THE CORE SPRAY SYSTEM SHAll BE DESIGNED IN ACCOROANCE WITH REF. 10.
'I TORQUE ON /
\ SWITCH VALVE
! 13. LAMPS TO BE LOCATED BEL!7W RECULAR CORE SPRAY ANNUNCIATORS. LECENO AS SHOWN.
! I PERMISSIVE UNI...ES5 VAL VE IS FULLY CLOSED
.~
(
l PERMISSIVE WHILE VALVE IS CLOSING
\
! PERMISSIVE IoIHEN \ . CONTROL SWITCH
- 14. SWITCH TO SE LOCATED BELOW LAM/S. SIoIITCH TO BE 2 POSI1ION "NORMAL" _ "INOP".
\
'INITIATION SIGNAL' IN 'STOP' PERMISSIVE WHEN VALVE 15 FULLY CLOSED \
LIMIT SWITCH ON VALVE J 3 POSITION S .... ,TCH "STOP' "AUTO' 'START' SPRING RETURN TO "AUTO' 15 PRESENT POSITION 15. IU:PRt:'CNT,r.T1\1t ~ PllRAU.EL TORQUE 5Wrn:H CD1rl6INATIDN Rt:FER TO RtFl:RE:NCC I~ ,
LIMIT
\ SWITCH ON VALVE J rROM 'STOP' 'START' PERMISSIVE RMS 1-4-5 I/o ~.r,:~~~ ~G~~Ltu'lfP~,r6"~ ~~L~~':-16~vrd'E. PUMP RUIIINIt.!G CONTROL SIoIITCH UNUSS STOP IN 'START" SI.HAL IS NOTE 15
- POSITION PReSENT
- /c:, '0 RMS CR AUX DEVICE CR / "
~.~~ LIGHT ON WHEN IN IoIANUAL OVERRIDE REFERENCE DOCUMENTS*
/1' I. NUCLEAR 80 ILER SYS TEM P& 1D
- 2. NUCLEAR BOILER SYSTEM FCD
- 3. RESIDUAL HEAT REHOVAL SYSTEM FCD MPL ITEM NO.
B21-IOIO 821-1030 I OPEN CLOSE J I START I STOP I 4. CORE SPRAY SYSTEM P&ID
- 5. CORE SPRAY SYSTEM DES. SPEC ElI-1030 EZI*IOIO E21-4010 1L-_~R=E..:..VE~R~S..:..'"..:..G..:..C..:..0_"_T_A_CT_0_R_(_4_2l_*_ _-J1
[L-__________________________________~AI~R~C~IR~C~U~IT~8~R=E=A~KE~R~(~5~2~l_=__. __________________________________~1 6. HPCI SYSTEM rCD
- 7. RC IC SYSTEM FCD E41*1030
£SI-IOlO
- 8. LOGIC SYMBOLS A41-1030 CORE SPRAY PUMPS COOIA,CODlB,COOIC,COOIO 9. RHR SYSTEH P&IO EII*IOIO TEST BYPASS VALVE MO FOl5A,8 10. ELECTRICAL EQUI P SEPARATION fOR IAfEGUARD SYS A61-4050 NOTE 2 iii 3 THROTTLING TYPE (NOTE 2 iii 3l II. INSTRUMENT DATA SHEET E21-30S0 It. CORE 5PRAY 5YSTE.M I:LEM. 01"'- UI-1040 729E613AD, SHT.1, REV. 10 Per NEI 98-03, this Figure in it's LIMERICK GENERATING STATION UNITS 1 AND 2 entirety is classified as HISTORICAL.
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 S'~Y/cE Lcv~1 .3 NSSSS INOfJoA n INOSOS n
1/
11 INOSOC "
INO~OD If II Ltlvel ',.2 NS.sSS~ ~PS INOS/A I"'OSI B .'
If IC I-INOBle ,. It II INoel D I. .. vc.1 '/..2.; a CSCA),RH,qGq),ADSC~), Rerc
..-+-'..-+--- IN091 A CS(8)~ IlHIl(B), HA;Z tp-;--t---- (NO 918
...........---INOfY'/C
.---/N09/lJ
~~~~----INO~/E
....- t - - + - - - - I NO 91 F c s ("c), ~ HIJ("c), ADS (c)
...--+----IAl09/G
..----INoctIH Lf!" .. 1 3 AOS(~)
1-+-+--+---1NO Y SA A 0 s (C)
- + - - - I N O 9sc J.~vel 2. Acre
.-+-~~---IN09~A /I
" II
,-~~I----IIVO 97 e I.~vel ~ ~RCS IN40.2rf
/ N4-0.2.. lJ " " "
IN4<:J:2 E " II
/#40.2 f#'
II
" 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 ...J UJ LOCATION OF DETECTOR DURING NORMAL REACTORl ~
STARTUP u..
o J:
It~!::-E f-(:J Z
UJ
...J UJ 120.00 >
STROKE ~
u t
FLEXIBLE SHAFT 7
/
LOCATION OF DETECTOR DURING NORMAL REACTOR OPERATION 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
POSITION SWITCHES DRIVE CONTROL MOTOR MONITOR CIRCUITRY FLEXIBLE CABLE LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DETECTOR DRIVE SYSTEM SCHEMATIC FIGURE 7.6-3
OPERATIONAL AMPLIFIER
~
r-£ZJ-FISSION CHAMBER VOLTAGE PRE-AMPLIFIER &
~TTENUATOR~--~ INVERTER MEAN SQUARE :.---t I - -....
J OPE RATE &
CALIBRATE J1 _
W' I ...._
"11 DETECTOR AMPLIFIER ANALOG I SWITCH
~JMIt-115' ILOW LEVEL
~15v HIGH LEVEL LOCAL METER
.~ REMOTE
>RECORDER I COM CALIBRATE DETECTOR & DIODE LOGIC UNIT COM DRIVE BIOLOGICAL t
SHIELD=_ _""'"1
- L..J" FLEXIBLE DRIVE SHAFT OPERATE &
CAL.IBRATE I---REF SWITCH RANGE MOTOR SWITCH MODULE
~-------,LOCAL LAMP TRIP RESET - }TRIP.OUTPUT UPSCALE r--I-, TRIP I - - - - - - t....... (HI-HI)TRIP ON LEVEL
~ IP SET 1 - - - - - - - - - '
REMOTE DRIVE CONTROL r-- ctJ TRIP
~
t------'-jLOCAL TR IP SET -----.. .
I. 0:_LAMP
}TRIP OUTPUT UPSCALE (HI) ALARM ON LEVEL
...---------,LOCAL LAMP
+1t ",5 r-J-, TRIP
.. }TR IP OUTPUT DOWNSCALE ALARM ON LEVEL
+20v +15v l+.;:;:!
PO~~R I-----il ....
+24v-----i PRE- -20v VOLTAGE -15v TRIP SET 1------.. . .
-24v----IREGULATOR J--~ItL-----tREGULATOR COM SUPPLY ...---------,LOCAL, LAMP COM COM
~~=----L _________J ~~=-I_~_____~
OPERATE & TRIP ~ }TR IP OUTPUT REF INSTRUMENT INOPERATIVE UMU~
CALIBRATE 1 - - - - - - 1...~
SWITCH MODULE INTERLOCKS 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
APRM 120 Vac Bus A APRM 120 Vac Bus B APRM APRM APRM APRM 2-out-of-4 2-out-of-4 2-out-of-4 2-out-of-4 Voter A1 Voter A2 Voter B1 Voter B2
~ ~ K1E
~ ~ ~ ~ ~ K1D
~ K1H K1A K1C K1G K1B K1F I K4A I K4E I K4C I K4G I K4B I K4F I K4D I K4H
~ ~
To RPS Logic A1
~ ~
To RPS Logic A2
~ ~
To RPS Logic B1
~ ~
To RPS Logic 82 NOTE: Contacts are shown in normal operation position.
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
'4 i""'- II ~
'0 Z 0
I-
-,..- - 100 U
0::
I-w 0:: a:
'0 '3 i""'-
-r-
- ~
~
w 0
Q.
- 10 10 '2 ~
_L-
- 1 Z 0 0 w I- ~
> '1
~
u a: Z
.5 '0 ~
w ~
CI)
X
~
a:
I-w z
w J: - 0.1 U- a: ~
z ~
0 ::>
a: u..
I-a:
w
- > 10 '0 ~ ~
w Z
~
- r- - 0.01 0
Q.
I-
<: Z
~ w a: u w a:
J: w I- Q.
w l:) 109 ~ - ~
3 a:
w 1\)n ~ - -
Q.
- 4 0
w ~
I- a:
a: <:
w ~
(/)
(/)
107 ~ ~
~
~
5 u..
106 ~
6 105 SOURCE LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT RANGES OF NEUTRON MONITORING SYSTEM FIGURE 7.8-8
TYPICAL OF LOGIC CHANNELS HIGH DOME PRESSURE (NOT SEALED IN)
RRCS ARI READY FOR RESET LOW WATER LEVEL 2 TRIP (NOTSEA_LE_~ ..IN.), ~__________________======================:;~~ __~~__;-_________________R_R_C_S_A_R_'_'N_'_T_'A_T_'_O_N~~ Note: This figure is based on GE Drawing Number 944E194TR.
RRCS MANU AL I N \T~I~A~T.:.:.'O:.:N4-____-!:.A~R~1.!!M~A~N~U:.:;A~L:..:'.:..:N.:..;'T:..:.':..:A..;..,;.;
TIO:.;.N;.....__________
ARI RESET HIGHDOMEPR:ES:S;U~R~E~________________, -____ ===-__________________-,
(SEALED IN)
TO 9 SEC TRIP RECIRC PUMPS
~
TO RRCS FW RUNBACK INITIATION 25 SEC RRCS POTENTIAL ATWS ANNUNCIATION SLCS INITIATION LOW WATER LEVEL TRIP 2 RRCS RWCU ISOLATION (SEALED IN) 118SEC RRCS CONFIRMED ATWS (ANNUNCIATION)
Per NEI 98-03, this Figure in it's RRCS MANUAL INITIATION entirety is classified as HISTORICAL.
(SEALED IN)
RRCS RESET LIMERICK GENERATING STATION RRCS RESET UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT APRM NOT*DOWNSCALE TRIP RRCS READY FOR RESET RRCS INITIATION LOGIC FIGURE 7.6-10 Rev. 11 9/02
B m RRCS DIV 1 EXH RRCS DIV 2 BACKUP SCRAM ARI VALVES ..... - ~ EXH VALVES-ENERGIZE ENERGIZE TO VENT TO VENT LINE LINE FllOB FllOA F160B F160A TO HCU BANK B INSTRUMENT TO HCU BANK A AIR RRCS DIV 2 EXH RPS SIGNAL RRCS DIV 1 EXH F162A
." C "0
- C F094 C
C) ~
la! r-II m i:
m C m ~-----II TO F180 & F18l
...... "n II
<in
~
- lJ Z n
~
~
- lJ>>
r-c:C)
(') (I)!m C/) >> -4 z
>>:lJ "n m~ll en m RPSA
-4 :. F009 * .,.. I
< <:'-4
-z_ EXH r-Z0 Z
>>NC)
RPS B m
~ en C/)
(I)
- zJ 0 qJ Z o
~ ND~
F163B II ND F163A r lTO F010& FOll
&AI
~
z Z
a::
&AI
~ ...,
~
~
z z 0 0 <
a:: 0 0 N
~ ...,
~ a::
a:: w ~
- , en 0 w J
- Q. < :;:,
en :;:, Z ~ u..
LEVEL 8 NORMAL LEVEL 7 WATER - LEVEL 5 LEVEL ~
LEVEL 3 ZERO EL. 310' - 2 %" BOTTOM OF (zero ref.) DRYER SKIRT I REFERENCE LEVEL 2 LEVEL 1 TOP OF ACTIVE FUEL
+I I
t ACTIVE RANGE
- - - -- INACTIVE RANGE PECO ENERGY COMPANY LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT WATER LEVEL RANGE DEFINITION FIGURE 7.7-1 Rev. 09 11/99
LGS UFSAR Figure 7.7-2 Deleted
~oo r-H)t] WtniooA'NAl WnHt)RAWAl, MOTOR t~OO ~oo ~10rtON EllOCK SI.OC-K COf'>rROlS $£;t.~cnol\t Seltf;:rIO~~ CON'H!OLS i __L 8
t t t __ t Ac.l'lV~'rY ;s.CH~TPt CONn~OL COtHROt A ~
.CO~PA~e }-~--------------------____~~~__________
r-----------~----------_
ADDRESS OF 01l'H3AT3,ON
."ClJ SE'l£C1'EP ACT~ON COOt Sl'CP~M:~?~
\-
~-------------------------~(\-----------------
~. ."'-....- ..---:....----oor---_.....
,f.O'OI={ESS OF O'i'~H~TiCN HCU TAKING
~!ESf'o!'m'NC PLA<::F.
~-----------------,
f"Afl4.;..tH...--~ OUTPtlr
'OUTPUT O/~rA DA;T.s. FCH=f LIMERICK GENERATING STATION UNITS 1 & 2 UPDATED FINAL SAFETY ANALYSIS REPORT P:E.R. NEt 98-0S THfSFIG*URE IN ITS t
ENTIRETYfS eLAS*SIFtED AS REACTOR MANUAL CONTROL H1STO*RICAL SYSTEM OPERATION FIGURE 7.7-3 Rev. 11 9/02
. AeTtON lOOP START FOA
.... SEL.ECTEO ROO
~,,-
SERV!C~ OPERA-lOA se ...ecn 0 ~~OO MONf'!'O~ lOO~ f:O~
NOt~-S£leCT£O AOO$
~
Cf:n.-.tN $TATUS OF t~f::>t.T ROO
~
NO
" t.~S" ROO t YU r*-..,...****
SelF~TEst NOI.T ROO LIMERICK GENERATING STATION UNITS 1 & 2
- P:E.R NEI 98..03 t THI,S *FtGtJRE IN ITS ENTIRETYfS CLAS*$IF1ED AS UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR MANUAL CONTROL H1STO:FUCAl SELF-TEST PROVISIONS FIGURE 7.7-4 Rev. 11 9/02
r- SWITCH NO. - - ~~
~,SOO ~
_~ l S01 I
r-----t-------~~
I ) .
, - -_ _ _ _---.J..., L S03 L S02
-) >,"
r---+-----~..,
~ _ _ _ _----l., L S06 L S04
) >I'"
4~~ . ,-
I ~ L S07 -)}
l S08 J*
r I" I
I I ~ ~ S09
,. - \}
M-t-+-++----.---J' , rL S10 m
~
- 0 1\ ~
r-~--r-1---~-----~~ ~S12 ~
,,-_ _ _ _ _ _.-J1 L 511
§
, -_ _ _ _ _ _--.J1 I IL513 (")
r~--t-+------~,,~~---~-+--L-1 r
L S14 ....... m
, _ _ _ _ _.-J, t 515 I r---t--t---------J
. . -. 'rs.i7-----+-~~--l-J.
1 L 516
~7 I
I
'""""--t--------.-J~ L.!
1 8
S19
~ -----------~~
L-I ,-_______~' ,S20 C~5~2~1------~-l-1 r-~-i---t--+------------~~~-------~-~-J-~
. . ;; 522L
~--------JI ~523 rl--t--+------~"1
~_ _ _ _ _ _ _~' L~5~2~5~---------+--~~~-L--j 524
~
~' ~
r-~r-~----------l~ L
,,-_ _ _ _ _ _ _ _---1, 526 S27
- II ~j r--t---------l., ~ 528 0Z
,,-_ _ _ _ _ _.-J L
~r 529 n-l~
o r-~--t-t--t--+------~I ~ .- ~530 ~
~
i-~-1r--t--+---------~'
r - - - - - -......... 531 0 II ~: ~S3;3-------+--+--+--l--j ' 1532
'---_ m m
1 :. ~~--------~--~
534 I ,. Lr~-------J.
I ",S36 I
, L~6 I
,,-_ _ _ _ _ _---J, l537 I
~ ~ L5~ I
, -_ _ _ _ _ _ _ ~I, rl~53-9-----------1--~
r--r~--t--+-~------.-J1 Lr5~47°----~~-+--L~
. -_ _ _ _ _ _ ~I l541 r-~--r-i--~------~;1r------~ ~542 r--t-t--+-----~~ 1~5~~~----~~
""""_ _ _ _ _ _ _- i L 543 1 r------~~ Lr5~4=7----~--~ L 545 II 1 ~,S'6 I I -1 Lr-S4_B_ _ _ _ _ + __--l.._J.
ROD WITHDRAWN t 549 OV ER TRA VE L ' rt-=:55:-:0::--------4iIJ
" Lr;~--------~--J.
~ 551
' l~5=5:::-2--..T----~...
j _ I 1
~o ROO .., r
~ INSERTED Z
I )~
~
!! c: )(10
!iii m
- ... ,)-1 r m
... < m m!:
O:t: I I '1-1°
~
n'T1
>C~
-. Z .,,"' )1-en 1 Z
_ : I_I 1- - N N
~
I
- e_ )}- - S
_m en-"
'-Z N
~ ~HROMEL 1M
!!l-~
,.. -t m 11K. I~
)\:....
~ -< ~ ~
-n '" Z r_
o .')}-
~.J.
ri AlUMEl
__ >0_ -,r
~ =
z .. z o....
Z
>" --- --- I N
- ~ ~ t !:1MB oOJ m "Z
0 m 0
~
LGS UFSAR Figure 7.7-6 Deleted
Security Related Information Figure Withheld Under 10 CFR 2.390 Rev. 17 09/14
TROLMECH ADMISSION VALVE INITIAL PRESSURE REGULATOR Figure 7.7-7A Deleted t
TURBINE BYPASS VALVES TYPICAL FOR EACH LOOP M -INDUCTION MOTOR MG Set G - AC GENERATOR Unit 2 C - AOJUSTABLE SPEeD COUPLING
~ RECIRCULATION FLOW CONTROL COMPONENTS LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT RECIRCULATION FLOW CONTROL UNIT 2 FIGURE FIGURE 7.7-7A 7.7-7 Rev.08 Rev 16 09/12 1V98 FIGURE 7.7-7A Rev. 17 09/14
LGS UFSAR Figure 7.7-8 Deleted
- T0~lHr<f~
I'):tESS'W~E PF.ESS $T£AM AMP ltNE NO.1 COM' flAE~UAe REGUlATOR
~UGH SET 'OfNT I + etAS VAlO~
GA1'E ro.,e'N! (JRCWT TO e-V'A$$
PR£SSUA~ OEMAND lOW VAlO! -n'IC~
GATE LtMfl'" . t - -. .- - - -
cmcOtT 1'0 Tu~e'Ne AOM1S!~ON VAc..VES OEMANO "R~$SUR~
REGULATOR SET
'OINT' ... !UAS TVRatNE
$!t£J:O LOAO COt.l"'ttllOt..$
o
.8IAS t~STA~H.JSH£O
~lOM 1~ OFFS~"
B~E.~~ GOV~RNOA CVTPUT ANO LOAO C-EMANO 'R£SSV ft!
REGUf..A'fO~ Otfrpun C51'O 15" RANG~l STtA.~~t..OW lE-QV'VAL£NT LC<AOf
~OTr~
THIi HiGH ANO "'-OW VAl.VE GA T~
T!RMlr~Ol.OG,,( ~EF£RS
'TO THE MAC~froO~
O~ TH£ INPVT $tGP~A'"
TO 'tliE GATt eu~ewr
\JNe~A NORMAL OPIRATJNG OONOt"10NS.
LIMERICK GENERATING STATION UNITS 1 & 2 UPDATED FINAL SAFETY ANALYSIS REPORT PER- NEI9S*03 TH1.SFfGURE IN ITS t
ENTIRETY.S CLAS-SJF1EO AS SIMPLIFIED DIAGRAM TURBINE HtSTO-RICAL PRESSURE & SPEED LOAD CONT ROL REQUIREMENTS FIGUR E 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 0.21311 (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 LIMERICK GENERATING STATION UNITS 1 & 2 ENTlR.ETY* IS CLASSJF1ED AS UPDATED FINAL SAFETY ANALYSIS REPORT HtSTO:RJCAL 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' LIMERICK GENERATING STATION B RBM ODA 'B' UNITS 1 & 2 UPDATED FINAL SAFETY ANALYSIS REPORT RBM ROD SELECTION COMBINATIONS FIGURE 7.7-14 Rev. 10 10/00
120 BCCD 1 CHANNEL 118 116 BCCD 2 CHANNEL 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 2 4 6 8 10 12 14 CONTROL ROD POSITION (FT WITHDRAWN)
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
CRUCIFORM o CONTROL BLADE c
&.PRM DETECTOR 8
~ BCCO, CHANNEL
~ BCC02CHANNEL A
LPRM LEVELS 1 o NOT IN SYSTEM
BOTTOMOFCORE LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT NEW RBM BCCD 1 /BCCD 2 LPRM ASSIGNMENT FIGURE 7.7-16 Rev. 5, 4/96
130 NOMENCLATURE ILLUSTRATION ONLY NOT TO SCALE 125 -
120 ~
o:z H
t9
~ LTSP
- ~ * * * * * * * * * * * * * * * * ! - ; .- - - - - - - - - - - -
Cf}
H 115 _ ::r::
E-i
- z H
Cl : ITPS
- .* ~ .***.*.********* ~ ...*******..***********.************************* J.,...-_ _ _ _ _ _- . . ,
0\° ~
_ H 110 E-i ()I
- z ~
H ~
o HTSP
~ E-i :
- 0************************************************* .................................................. .
E-i
~
Cf)
- z 105 100 30 45 60 70 90 10 LPSP I IPSP HPSP 94 RBM PERCENT POWER DOWNSCALE LIMERICK GENERATING STATION UNITS 1 & 2 UPDATED FINAL SAFETY ANALYSIS REPORT POWER DEPENDENT RBM TRIP NOMENCLATURE FIGURE 7.7-17 Rev. 10 10/00