ML17054B964

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P&Id:Residual Heat Removal Sys. Sheet 1 of 2
ML17054B964
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 10/11/1985
From:
GENERAL ELECTRIC CO.
To:
NIAGARA MOHAWK POWER CORP.
Shared Package
ML17054B965 List:
References
731E961AF, NUDOCS 8511010308
Download: ML17054B964 (1)


Text

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RMS F LU5H I N G WATE R SUPP Ly TO RCAC TOP BU JE 0 lN 'C)

E QUJ @'HE4 T DRA,LN5 10 yi 1 I

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LIRN.CIS Otl%%%t%

$PC58%0 IAE 794E lOLLOMRRNC.

III~aa1, CueV~JC t3lE 9G the a e~8 ITLC ~,s PPID.

RESIDLIAL He%,T REMOVAL 5+5 I

IL R

Y F

PRIMARY CON.TAJNMEhlT 7.

PROCESS RADIATION MONITORING SYSTEM OI3/DI4/DI7/DIB I0IO K6OS HIGH/ LOW SELECTOR I

STATION TFIEPMAL RELI EF VALVE FO'J5 KEVLOCIC I

KOOt B A/4 P

POT 8.

DE LE TED KEYLOCK R RL45 MO F093 VMS HE A T HNII M

Qc wo 9.

PROCESS I NS TR -------- A62-4070 I BOOI B COt05 B 10.

RHR SYSTEM PROCESS DATA-----------------EI2-I020 F003 I

I.

RHR SYS DESIGN SPEC----E i 2-4010 PS A

I654 F097 I

DRW R hit 8

CIT WO3O B

l2.

EMERGENCY EQUIPMENT COOLING WATER----------A62-4230

+AH PT N053 B

I IVI0 FO'l~

KEY LOCK rO r

NC I 3.

RCIC SYS FCD----------ESI IO 30 REAC RECIRC SYS P&ID'B33/35 IOI0 RM5 N005 b

NOOt b Q,;,

PI 5 A

IN65 3 8

Pl RMS BA-B I 5.

NUCLEAR BOILER SYS P&IO------------821/822-IDIO I

MO FO/0B B TO MO RMS ~,qlD ra EACTOR DRAJ'At 16 LOW PRESSURE CORE SPRAY P& ID ------.-------E21 I 0 t 0 F0608 TO SERV ICE WATER DISCHA'RGE I 7.

POST ACCIDENT SANPLI NC SYSTEM P&I9-D24.-IOIO I B.

RHR SYS EDDL-EI2 3050 I9.

REACTOR PLANT SAIs/IPLING SYS-B ( A/E.

SUPPORTING DOC UMEJRITS MPL I TEM NO.

RCoo2 b ERE FT FOBOB p

X-F07/) tR F 07N*5 THE/I hh At RELIEF P073B I Fo FOB I B FE NOOb 5

FO758 r-REACTOR

>'ECOILJDAR.Y OklTA14 ts/IE 4 T SEE REF t~

NQTE. 5 N007 B I

P IP ING INSTRUMENT SYM3'MLS------------------A42-IOIO OVERALL F" F 2.58%I54I/JlE RfYIQJON AEV NOTES:

j

/

INSTRUMENT LINE DESIGN E V'LYING MUST COMPt Y WITH INS 1 RLIMENT P IP ING SPEC IF ICATION REFERENCE 9.

THE METHOf:

OF MOUNT INC LO( AL INSTRUMENTS I 5 TO

.3E DETEPMI NEf'Y P IP I NG DESIGNER.

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

SEE NOTE 2I CrEERPF fYIPl NQ F l'IJ-IGLOO NOTES:

15.

DELETED Pt 694 S I

PT DCC K007 B

le.

LINE FROM RELIEF VALVES TO SLOPE DO l.4RD CONTINUOUSLY TO SLJPPRESSIOV POOL

~

MAC KDD5 8 B-f SPR K009 B

FLU5HING CONNECT IONS SHALL.

BE PROVIDED I N ACCORDANCE WITH REF 2.

TEMPORARY S T R A I Ist ~ R SCREENS

~ H AL L BE PROV I D E D O N THE SUCT ION 5Il'E OF ALL PUMPS IN ACCORDANCE WITH REF 2.

I 8.

ALLOW ADEQUATE PIP IP c c JFtFACE AREA FOR COOL I QG OF PUMP COC) 9.

F'I Rt 92 8

I 9.

FOR LOCA T ION AND I CI EN T I C I CA T IOhJ PF I NS l R tJMEN TS 5 EE INSTRIUI)PIEN T DATA SFIEE I REF.

'IB.

DI SCHARGE Lf NES FOR COOLING WATER TO BE ROUTED UP5TREAM OF SERVICE WATER RAD I AT ION MON I TORS.

E-IO

~0.

EXCEPT AT POINTS OF CONNECTION WITH GE 5UPPL JEO Ef)tlt1PMEJN T OR P IP l NG.

THE P I P ING CESI GI)JER SHALL 5 I ZE ALL PIPES IN CONFORMANCE WITH THE SYSTEM OES I GN SPEC AND PROCESS C I AGRAM.

2 I.

THE EMEPGENCY

RESPONSE

F'ACILITv (ERF)

INFORMATION SYSTEM INTERFACE I 5 PROVIDED BY OTHERS.

? 2.

A FIT TINC JS PROVIDED FOR TEh1PORIJRY HOOKVP OF AIR SUPPLY TO AJR OPERATOR WHEN FUNCTIONAL TESTING OF CHECK VALVE JS TO BE PERFORMED.

)HP H-fo e.

EQUIPMENT INSTRUMENTS ARE PRE-FIXED BY SYSTEM NO.

(EI?)

UNLESS OTH=RWISE NOTED FI Rfolh FT 093 7.

ALL MOTOR OPe.RATED VALVES ARE AC OPERATED UNLE55 OTHERWISE NOTED.

REACTOR HEAD SPRAY LINE CONN-ECTION TO MAIN LINE SHALL BE AS CLOSE AS PRACTI C IBLE TO VALVE FO I 6.

DELETEO VALVE SHOULD BE IN STALLED WI TH PACKING GLAILD(5), UPSTREAI'1 5IDE OF DISK.

FIS FT lt/If 52 IVC5Z PIC R6D RMS H-B 9.

I I

I TIS 03 pier M0 d'W FOZ6) B TO REACTOR F lg3 E BUILDING DRAINS C /7 /9 lp.

F/

T Rb03 8 A

NOI5 C

BA"8 PT 02 TO SUPPRESSION O

VALVES F005 9 F025ABICR FO30&FO88 SHALL BE I" REL I EF VALVES ~

REF; 5 2,C-I FU548 T DOO9E D020E RMS F2J5 E

rp MQ FQI I B

5H 2,E-4 H

RMS ptc KO03 I

I 2.

RCO(

B p

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LS I

N65/

DMIN DIST PT RMS O

I 8

rp PIS I 4, I

F05I8 ',C N650 I

MO MO PT F081 8

a)

F052 NO?.ro B

cQ F/62 E FI07E RELIEF VALVE F 23I IS PROVIDED TO ACCOUNT FOR THE THERMAL EXPANSION OF CONTAINED WATER BETWEEN VALVE5 MO F008 AND ft/IO F009.

yp RME FOR ADDITIONAL CONTROL ROOM L IGHTS9 SY5TEM ALARMS REMOTE MANUAL SWITCHES SEE REF TO RAOWASTE SYSTEM RMS I /0 RMS ct iC FJ E

Jrl 0 F049 hhD F040 C r PROV I 5 I ONS FOR CONTAINMENT ISOLATION SHALL BE IN ACCORDANCE WIT H CURRENT LICEN-SING REQUIREMENTS.

0 O PT 050 SH.2 F-2 SEE NOTE Zl BA-B QEIIF SYSTEM SELECTION OPT IOIV~ ARE I ND I CATED B Y MULTIPLE MF'L I TEM NO.

WE@ERE/s/CE DOCUMENTS MPL ITEM NO ~

NUCLEAR BOILER SY5 FCD-82I/822 I030 TE TO REMOTE N 03I SHU TDOWN RECORDER SH-2 F -2 I

DM 5 IIII O I

I I

F'IDIOM 5W-Z.

I TE FIO2>a R'l:

I TE 'OC%

IE NODS A TE tst03 I SH 2, 4-I FIO~BI FIO4B AC TQ SPPPRESSIQN POC L

~LP 4I MQ RIIIS F2058 I

F 07 3 8

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RPAS FO7+

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Chen RECOR DE Rt tY)O Klvlb I c,O; FQ47 IS KE /LOCK F070 NO27 5 SH. I,C-8 2.

CLEANING OF P IP I NG EQUIPMENT------------

462 4

I 40 3;

RESIDUAL HEAT REMOVAL FCD- ------------------EI2-I030 4

NO04 B)~

I n

TO REMOTE SHUTDOWN RECORfJE R HIGH PRESSURE CORE SPRAY P&ID-------------E22-I 0 I 0 ILIJ0 R ISrt 5 c,,

F04 B

5.

RCIC SYSTEM P&ID-------ESI-lolo BA-8 e.

DELETED Pol NOTE 22 AO FOB 9 5H2 tC-i3 C

REACTok YE.SSC I RMS MO Fcl 99 8

d; A

H TCI SUPP POOL FQBBC PJ5 N4 0/I FZO 4C L.O.

MO PIS PIG BA-B F064 C

F2048 L.O.

N65 5 I

N656 C

LC RIVt5 C /7/6 PI ROO PT N055 PT N05i P/

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LC FO72C REF.

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e RMS ROOK BA-B MO PJS P/5 N7 56 Nb55 F064 B

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R008 TYP FQR 3 PUIVIPS C" 2 A THRU CQQ2C E.XCE.F'T FOR BLUFF IX LETTERS I

FQi2B FP'IBI3 LO FQI3E FO318 CQQ2 E L.C.

F0728

F084, LC EE 0003 6 oi MO C re F023 E2LSB EIO2.01 MJN DIST.L FOI9 E. A-A F II2: L2)

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Ft FT HOt 3 dPIS A!660 8 dPS T

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TO SUPPRE 55IOtst 9OO L ocr t

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FOAL)/J LO F05/ 8 FOSSES IIO FOR 2.

B ERF

't M 5 AO RM5 It.'M5 FZZ3 FOSO BI

-0255 LP FE.

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F224 C

F2078 TO SUPPRESSION t'00 L F Z l(06 FQ5BB F059 B ~,, F053 B

o~

F20 L.O.

T TD FUEL

~ POOL COOLING AND CiEANUP SYSTEM AA-B F2088 MIN. DISTANCE RMS 0638 MIN DJSTANCE I

L.C+

IRHIR QVSTENI TEST LILIE-A 8-B L.

FT N052 C

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CE.

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F2258 1Mt0 F 105 8, -

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I COCJ 3 F202 RO 9002 CJOOI C

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RMS FI 5 N652 5

PF)RESSJOKJ POOL C /720 PS N654 C

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PIS N653 C

PT 0)3 re yC~ ERP C

IC E'TLOCK fYI0 RMS FCJOW r @~4 ERFr r

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C KE'/LOCK P'. Ivt5 NI Q FOD4 ~

PT O62 P

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+TO REACTOR BUILDING EQUIPMENT DRAINS FQIB C SEE Nprf ta F082 L.

F 203 F069 FDBAC F084B F044C L O4 CQ LR N)

A.X F085L T OS5 8 REF.

I TQ E ME.RC LNCY LCJUIPMF NT CQQLINC WATLR AS REQ D REF l2 AA-C PROCESS SAIYIPLE.

PROCESS SAMPLE TO REACTOR PLANT TO POST ACCIDEITIT SAMPLINCI SYSTEfslt SAMPLINCI SYSTEM (Rf F. I9

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CFIEP.J7 SH.Z E-Icl )

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g A. NIAL.T Nf INCORP.

FOYER.

r)Fr% MN: R. S t)tll CWK CL f: P. BLITTNCNS24)LI

,~ JJ,'A X 10 RHR SERvtgg 2.

PRESSURE INTEGRI TY OF wATER SYSTEM P I I I NG CEQU I Pf'iENT PRESSURE PARTS-----------A62-4030 REVISIONS C

PRINTS T0 g

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