ML17054B964

P&Id:Residual Heat Removal Sys. Sheet 1 of 2

ML17054B964
Person / Time
Site:	Nine Mile Point
Issue date:	10/11/1985
From:	GENERAL ELECTRIC CO.
To:	NIAGARA MOHAWK POWER CORP.
Shared Package
ML17054B965	List: ML17054B964 ML18038A074
References
731E961AF, NUDOCS 8511010308
Download: ML17054B964 (1)

Text

10 yi 1 the

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12'--.-I III~aa1, CueV~JC t3lE TO RCAC TOP ~,s a RMS LIRN.CIS Otl%%%t% $ PC58%0 IAE 794E lOLLOMRRNC. ITLC PPID.

B U JE 0 l N 'C) 5+5 u

T E QUJ @'HE4 T RESIDLIAL He%,T REMOVAL F L U5H I N G WATE R SUPP Ly F DRA,LN 5 I IL R Y Z

PRIMARY CON.TAJNMEhlT 0003 6 F084, SEE NOTE 2I OVERALL Pt AEV oi > MO LC fYIPl NQ F l'IJ-IGLOO F" F 2.58%I54I/JlE RfYIQJON C

re F023 EE 694 I

S CrEERPF NOTES:

NOTES: j /

E2LSB EIO2.01 FOI9 MJN 15. DELETED INSTRUMENT LINE DESIGN E V'LYING MUST A-A DIST.L PT COMPt Y WITH INS RLIMENT P IP ING SPEC IF E. DCC 1

K007 B F II2: L2) ICATION REFERENCE 9.

dPIS FOC I FT Ft le. LINE FROM RELIEF VALVES TO SLOPE THE METHOf: OF MOUNT INC LO( AL F22IC HOt 3 N 659 B-f MAC DO l.4RD CONTINUOUSLY TO SLJPPRESSIOV INSTRUMENTS I 5 TO .3E DETEPMI NEf'Y A!660 8 kH=

dPS T LU LS N69O t CIO78 KDD5 8 POOL ~

P IP I NG DESIGNER.

PIPING HIGH POINT VENT' LOW POINT dpr SPR DRAINS ARE TO BE ADDED 45 NECE SARY.

J)060 oC F 222C RMS t F I06 8 K009 B

I 8. ALLOW ADEQUATE PIP IP c c JFtFACE AREA FLU5HING CONNECT IONS SHALL. BE PROVIDED I N ACCORDANCE WITH REF 2. TEMPORARY F'I FOR COOL I QG OF PUMP COC) 9. ~R I S TR A I Ist SCREENS ~ H A L L BE PROV I D E D ON THE SUCT ION 5Il'E OF ALL PUMPS IN

~0 g. IAO tx I

rO Rt 92 8 I 9. FOR LOCA T ION AND I CI EN T I C I CA T IOhJ PF ACCORDANCE WITH REF 2.

FOt7 FOJ4, A,B- 9 I NS l R tJMEN TS 5 EE INSTRIUI)PIEN T DATA SFIEE I MIN. DISTANCE- b ERF 8 REF. 'IB.

Foist BA-8 E-IO

~0. DI SCHARGE Lf NES FOR COOLING WATER EXCEPT AT POINTS OF CONNECTION WITH TO BE ROUTED UP5TREAM OF SERVICE ITCF GE 5UPPL JEO Ef)tlt1PMEJN T OR P IP l NG.

ctPIS dPT

( RO WATER RAD I AT ION MON I TORS.

C REACTok THE P I P ING CESI GI)JER SHALL 5 I ZE ALL N@SW NOR

) LOOOA X PIPES IN CONFORMANCE WITH THE SYSTEM e.

YE.SSC I c,Q, 7 FQ 'I 2 C E.A-A C C EQUIPMENT & INSTRUMENTS ARE PRE-REF 15 I OES I GN SPEC AND PROCESS C I AGRAM. FIXED BY SYSTEM NO. (EI?) UNLESS I

I MN DIST+

FOrc)3C 2 I. THE EMEPGENCY RESPONSE F'ACILITv (ERF) INFORMATION OTH=RWISE NOTED J056C I5 AO o hh0 F LU SNJNC WAT F R FI FT SYSTEM INTERFACE I 5 PROVIDED BY OTHERS.

2)Q . 'P928 P 05'K 'r L F2008 L.O.

SUPPLY'EF.

Rfol h

? 2. A FIT TINC JS PROVIDED FOR TEh1PORIJRY HOOKVP OF AIR SUPPLY TO 7. ALL MOTOR OPe.RATED VALVES ARE AC C

< T' i FOIZ. C 093 AJR OPERATOR WHEN FUNCTIONAL TESTING OF CHECK OPERATED UNLE55 OTHERWISE NOTED.

FOAL)/J E.t-IFV VALVE JS TO BE PERFORMED. )HP H-fo LS F22l I RM5 REACTOR HEAD SPRAY LINE CONN-

'FO2. S C 690 FIS FT ECTION TO MAIN LINE SHALL BE FE REF. 15 SH.2 A- S I lt/If 52 IVC5Z RMS PIC AS CLOSE AS PRACTI C IBLE TO 2 208 NO90 S I H-B L RIV15 SH.2, C-10 I

I R6D VAL VE FO I 6.

4PIS dPT Ro QEE NOTE iO I TO SUPPRE 55IOtst 9. DELETEO RMS N658 N058 9OO L C /7 /9 p < e oo0 B ocr ,O,c I MIJJ. DIST+

t MO MO /VJO I

lp. VALVE SHOULD BE IN STALLED WI TH LO l

B F CJ24 I

PACKING GLAIL D(5), UPSTREAI'1 5IDE FD2I F/ T TIS OF DISK.

pier

/

I SEE 03 M0 PT F05/ 8 I NOI5 d'W TO MO M 5 AO NQTL Rb03 8 A FOZ6) B 02 SUPPRESSION IIO RM5 'M 5 TO REACTOR O Fcl 99 FOSSES It.

FZZ3 C FOSO BUILDING DRAINS 8

't FOR B Ba-8 F lg3 E VAL VES F005 F025ABICR FO30&FO88 BI 2.

-0255 BA"8 REF; 5 I"

9 LP 2,C- SHALL BE REL I EF VALVES ~

d; ERF F224 T DOO9E FU548 I

FE. RMS F2J5 E F Z l(0 6 FQ5BB F2078 . C IVQI4 C MQ rp D020E TO SUPPRESSION T FQI I B 5H 2,E-4

~

H F059 t'00 L yp F/62 E KO03 RMS B

~ TD FUEL ptc 2.

o~,,

F053 B  !

AA-B RME I I RELIEF VALVE F 23I IS PROVIDED TO ACCOUNT FOR THE POOL COOLING F20 AND CiEANUP FI07E RCO( B p .~ THERMAL EXPANSION OF CONTAINED WATER L.O. F2088 I I SYSTEM BETWEEN VALVE5 MO F008 AND ft/IO F009.

LS I N65/

RMS MIN. DISTANCE TO RAOWAS TE SYSTEM 0638 RMS DMIN DIST PT FOR ADDITIONAL CONTROL ROOM E

MIN DJSTANCE I I FJ RMS O I L IGHTS9 SY5TEM ALARMS & REMOTE L. L.C+ IRHIR QVSTENI TEST LILIE- /0 8 MANUAL SWITCHES SEE REF

',C FT A 8-B N052 Ct I CE. hhD Jrl 0 RMS iC PIS F229 B C J 0 O

ct rp I 4, PROV I 5 I ONS FOR CONTAINMENT I

ROOt0 NO25 F040 F049 I F05I8 N650 ISOLATION SHALL BE IN F2258 1Mt 0 I MO LICEN-5 PF)RESSJOKJ F 105 8, - FI 5 C r BA-B SEE NOTE Zl PT MO PT ACCORDANCE WIT H CURRENT SING REQUIREMENTS.

POOL N652 F081 8 a) F052 050 QEIIF NO?.ro B 3

RIVI'68 I TE cQ SH.2 F- 2 SYSTEM SELECTION OPT IOIV~ ARE TO rO REMOTE N 03I I ND I CATED B Y MULTI PLE MF'L I TEM NO.

~C PS C /720 PT SHU TDOWN SH-2 F -2 DM 5 IIII O I WE@ERE/s/CE DOCUMENTS RECORDER Klvlb I MPL ITEM NO ~

r @~4 re I N654 C

0)3 F070 c,O; tY)O NO27 5 ERFr r iC I-) yC~ ERP FJMS I

I I

FQ47 IS NUCLEAR BOILER SY5 FCD-82I/822 I030 C C KE /LOCK I SH. I,C-8 KE'/LOCK IC E'T LOCK PIS I

PT I

2. CLEANING OF P IP I NG &

5 fYI0 RMS S' R696 N653 I I

F'IDIOM 5W-Z.

EQUIPMENT------------ 462 P'. Ivt NI Q FOD4

~ FCJOW .

.Ci + I O62 C

P 'I R'l: I TE FIO2>a TE 'OC%

4 I 40 I R&t3 IE NODS A 3; RESIDUAL HEAT REMOVAL I

+TO REACTOR NO04 B)~ SH 2, 4-I TE tst03 I FCD- ------------------EI2-I030 F082 BUILDING F069 0 FIO~BI FIO4B SEE Nprf ta I ILIJ R ISrt 5 n L. COCJ 3 EQUIPMENT DRAINS c,, F04 B

I AC TQ SPPPRESSIQN POC L 4 HIGH PRESSURE SPRAY CORE P&ID-------------E22- 0 0 F 203 F202 FQIB C FDBAC F084B TO REMOTE

~LP 4I MQ RIIIS I I BA-8 SHUTDOWN F2058 I F 07 3 5. RCIC SYSTEM P&ID-------ESI-lolo RO F044C L O4 LR CQ RECORfJE R 8

9002 CJOOI C Pol e. DELETED I

F085L OS5 8 N) NOTE 22 L REF. I T

-X I

A. AO g) @60 5 A RMS X K6OS HIGH/ LOW FOB 9 H FZO 4C L.O. SELECTOR TFIEPMAL o 7. PROCESS RADIATION STATION RELI EF tYt RPAS TCI SUPP POOL MO I

VALVE I

MONITORING BA-B FQBBC F064 PIG PIS I FO'J5 KEVLOCIC FO7+ I SYSTEM OI3/DI4/DI7/DIB I0IO 5H2 tC-i3 C N656 N65 5 F2048 L.O. KOOt B ,B POT Po?

PJ5 KEYLOCK I

LC C A/4 P VMS I

I -X- ~u~ B

8. DE LE TED RIVt 5 N4 0/I R RL45 MO PI C /7/6 I HE A T F093 ROO P PS P/ PT PT ;Qc HNII M I

H-8 9. PROCESS I NS TR -------- A62-4070 A 008 N05i N055 wo BOOI B NOO RM4 COt05 B I B b NC) IJI5 10. RHR SYSTEM PROCESS DATA-----------------EI2-I020 MO I~NRCR O

SEE PUIVIP b F09BC F003 I

'r i FOQCD B L,O.

'"~

PS F097 CX I654 A I

~llnauL I I . RHR SYS DESIGN SPEC----E 2-4010 i COO2 C DRW CIT pr FQIB R hit 8 'HIJ Tb/OWN Chen T0 SUPR POOL 'I B

WO3O B RECOR DE Rt I

l2. EMERGENCY EQUIPMENT tt63 p t I F0468 L.C)

PT IVI 0 COOLING WATER----------A62-4230 N053 +AH REF. LC FO'l~

RCIC SYS FCD----------ESI IO 30 I B I Q,;,

FOSBB PS PJS OOOJ B FO72C RM5 I 3.

ROOK KEY LOCK ki664 Nr 63 RMS PI 5 rO NOOt b BA-B A r NC N005 REAC RECIRC SYS P&ID'B33/35 IOI0

, B e IN65 3 8 BA-B MO Pl b F064 P/5 PJS I I 5. NUCLEAR BOILER B N7 56 Nb55 MO SYS P&IO------------821/822-IDIO H TO FO/0B B I

c C /7/5 RMS F0608 MO RMS ~,qlD ra EACTOR 16 LOW PRESSURE CORE TYP FQR 3 PUIVIPS C" 2 A FO7t 8 LC

.Q iC P/ PT PT DRAJ'At TO SERV ICE SPRAY P& ID ------.-------E21 0 I t 0 WATER DISCHA'RGE THRU CQQ2C FQi2B E.XCE.F'T FOR R008 N05J N05 RCoo2 b FOBOB X-I 7. POST ACCIDENT SANPLI NC SYSTEM P& 9- I D24.-IOIO BLUFF IX LETTERS I FQI3E FP'IBI3 FO758 p THE/I hh At F07/) tR F 07N*5 I B. RHR SYS EDDL -EI2 3050 CQQ2 E FO318 LO ERE FOB I B RELIEF P073B I Fo r-REACTOR >'ECOILJDAR.Y I9. REACTOR PLANT SAIs/IPLING SYS-B ( A/E.

FT FE Okl TA14 ts/IE 4 T N007 B NOOb 5 SUPPORTING DOC UMEJRITS MPL I TEM NO.

L.C.

F0728 SEE REF t~ I P IP ING & INSTRUMENT TQ E ME.RC LNCY AA-C NQTE. 5 SYM3'MLS------------------A42-IOIO LCJUIPMF NT PROCESS SAIYIPLE. PROCESS SAMPLE FOIMF B 2. PRESSURE CQQLINC WATLR TO REACTOR PLANT TO POST ACCIDEITIT RHR SERvtgg INTEGRI TY OF AS REQ D SAMPLINCI SYSTEfslt SAMPLINCI SYSTEM wATER SYSTEM P I I NG I CEQU I Pf'iENT REF l2 (Rf F. I9 ) SH.Z E-Icl CFIEP.J7 ) PRESSURE PARTS-----------A62-4030 g I C7/ t t/IRR)%

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NIAL.T Nf L.PIUI /Ic I'Q. L JF CHU.NGUYEN A~ g L.T E

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REVISIONS C 4EL PRINTS T0 FEVV G.FAULKAifp, IN CORP. CHK BY 'J LAG//IRRE CATEC ORY ZC CH tst 6 t-)ENL DOC CHNG FOYER. NHPP789 RETRACE MJCHbtst.

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