ML22292A089

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5 to Updated Final Safety Analysis Report, Chapter 5, Figures
ML22292A089
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 10/05/2022
From:
Constellation Energy Generation
To:
Office of Nuclear Reactor Regulation
Shared Package
ML22292A107 List: ... further results
References
NMP2L2821
Download: ML22292A089 (74)
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Text

STEAM DRYERS

STEAM SEPERATORS

DRIVING FLOW __..,._

JET PUMP

PRESSURE FLOW TEMPERATURE ENTHALPY (ps1el <lb/hr) <"Fl <Btu/lbl

1. CORE INLET 1071 108.5 x !12J6* 535 529.2

2.CORE OUTLET 1047 108.5 x !12J6 550 636.2

3. SEPARATOR OUTLET <STEAM OOMEl 1035 15.0 x 112J6 549 1191.0
4. STEAM LINE <2ND ISOLATION VALVEl 1003 15.0 x 106 545 1191.0
5. FEEDWATER INLET <INCLUDES RWCU 1060 15.3 x 106 425.3 403.4 RETURN FLOW) 6.RECIRCULATING PUMP SUCTION 1037 32.84 x 112J6 534 52 1M
7. RECIRCULATING PUMP DISCHARGE 1325 32.5 x 106 535 530.3

~CHANNEL BYPASS-NOMINALLY 10%

FIGURE 5.1-lo

(Ref. ORF LI5-00719, Supp. ll

<GE Letter NMP2-CJ4-051, 10/ll/94l RATED OPERATING CONDITIONS OF THE BOILING WATER REACTOR

SOURCE: DRF L15-00719 SUPP. 1 NIAGARA MOHAWK POWER CORPORATION

THIS OOA\\tlli'JIG CREATED ELECTRONICALLY NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT

USAR REVISION 8 NOVEMBER 1995 STEAM DRYERS ~

STEAM SEPERATORS

MAIN FEED FLOW DRIVING FLOW......

NMP2 EPU Figure 5.1-1a, Sheet 1

FIGURE: 5.1-1a, Sheet 1

RATED OPERATING CONDITIONS OF THE BOILING WATER REACTOR

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT

USAR REVISION 20 OCTOBER 2012 Press (psia) Flow (MLB/hr) Temp (deg F) Enthalpy (BTU/hr)

1. Core Inlet 1,080(a) 108.5(a) 534(a) 528.9(g)
2. Core Outlet 1,048(a) 108.5(a) 550(a) 656.2(b)
3. Separator Outlet (Steam 1,035(a) 17.6(a) 549(c) 1,190.6(f)

Dome)

4. Steam Line (2nd MSIV) 1,009(f) 17.6(a) 546(h) 1,190.6(f)
5. FW Inlet (includes RW CU 1,069(i) 17.94(g) 440(g) 420.0(g) flow)
6. Recirc Pump Suction 1,036(a) 33.12(a) 534(a) 529(a)
7. Recirc Pump Discharge 1,314(a) 33.12(a) 535(g) 530(g)

Table Source Documents

(a) BILBO Run NMP2EPUM+OUT+19.pdf: DRF file object 0000-0075-4740, Rev. 1 (b) Enthalpy = (1-x)*hf + x*hv (x=0.1659; hf = 549.9 btu/lbm; hv =1190.7 btu/lbm @ 1,048 psia);

BILBO Run NMP2EPUM+OUT+19.pdf; DRF file object 0000-0075-4740 and IF-97 Steam Tables (c) IF-97 Steam Tables @ 1,035 psia (d) IF-97 Steam Tables @ 1,036 psia and 533.9 deg-F (e) IF-97 Steam Tables @ 1,312 psia and 534.2 deg-F (f) NMP2 Task T2005; NeFile 0000-0134-0800; file MCO 0.10 Steamline Quality Task T2005.pdf (g) NMP2 EPU Task T0100 Figure 3-2; eDRFSection 0000-0069-2801-R0 (h) IF-97 Steam Tables @ 1,009 psia and 1,190.6 btu/lbm (i) 105% OLTP case 3 HB 23A6942 adjusted for 120% OLTP as defined in 22A2719 (access number 060030105), corrected sparger pressure drop 25psi x ratio of the square of the FW flow increase =

34.3 psid, 1035 + 34.3 = 1069 Note: FW temperature adjustment determined to be insignificant.

FIGURE: 5.1-1a, Sheet 2

RATED OPERATING CONDITIONS OF THE BOILING W ATER REACTOR

NINE MILE POINT - UNIT 2 UPDATED SAFETY ANALYSIS REPORT

USAR REVISION 20 OCTOBER 2012 STEAM DRYERS

STEAM SEPAAATORS

vOLUME CF ~LUIO 111 3 1

A. LOWER PLEll<UM ~10

B CO AE 1990 c UPPEFI PLEll<UM ANO SEP.. AATQRS 2290

J. DOME !ABOVE "ORM.AL '°"ATER LEVEL i 7160

E DOWNCOMEA REC <O "< 5210

F RECtRCUV.'rtNG LOOPS ANO JET PUMPS 1010

FIGURE 5.1-1b

COOLANT VOLUMES OF THE BOILING WATER REACTOR

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT

AMENDMENT 19 MAY 1985

A B c D E F G H I J K L M N

1 1

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FIGURE 5.1-Zb

NUCLEAR BOILER AND PROCESS INSTRUMENTATION

11 NINE MILE POINT 11 NUCLEAR STATION - UNIT 2 SDURCE1PID*2BB*q SCRIBA, N. Y.

TITLE* NUCLEAR BOILER AND PROCESS INSTRUMENTATION UPDATED SAFETY ANALYSIS REPORT A B c D E F G H I J K USAR REVISION 25 OCTOBER 2022 _j A B c D E F G H I J K L M N

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TO CONTROL ROO 20A I.ALL INSTRUMENT & EQUIPMENT NUMBERS TO BE PREFIXED DRIVE SYSTEM...!A-J..I WITH '21SC-' EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN.

12RDS-PDTll4,ll 71 *EFV211A-I *HOSE4111 \\l_ T 2. GENERAL ELECTRIC IDENTIFICATION NUMBERS ARE SHOWN 4.6-5b IJ-51 '.. I I ( IN SOUARES.

  • Ir-. I

' *V211A-I 3. CONTAINMENT ISOLATION DATA !FOR LOW PRESSURE CONNECTION!

' FOR JET PUMP INSTRUMENTATION OF NOZZLE N-9 ARE LISTED 2-ISC-750-364-2CA-J ON CHART hlSOLATION ARRANGEMENT SHOWN FOR FT47JIA-I NSSPAl01 ~ IS TYPICAL.

CLEAN-UP SYSTEM TO REACTOR WATER CLOSED VALVE -z 4.HIGH PRESSURE CONNECTION FOR ALL NONCALIBRATEO FLOW 12WCS-FTl341 ' 7 2-ISC-750-314-21A-I -~\\ /*RO 21SC-750-372-21B-> TRANSMITTERS 21SC-FT47'S FOR RECIRC LOOP WILL BE FROM LINE NO. "B" AND 215C-750-364-21A->

8 < 5.4-16" 11-8> ' ~---~---i f1~!- 2-ISC-750-372-21B- > 112 ) ~I ~ FOR RECIRC LOOP 'A'. 8 v IZ-1 ", IA-l I r;\\3.!_3 I *Ro ' I _,,_/ *HOSE36 EF:'._14 IA-I REMAINING 21SC-FT47'S 5. FOR S&W AND GE DESIGNATIONS SEE CHART I.

~Bq-3) 20 B 2-ISC-750-322-2<BB7> ~~~~~~~~~~~~.... ~~~~~~~~~~~ ' ' ~---.------'--------;: RECIRC LOOP A 6. SEE DETAIL EXCESS FLOW I FOR TYPICAL CHECK VALVES.EFV ANO TEST VALVE CORRESPONDING TEST ARRANGEMENT FOR

~ ~ -\\l_ "B-J..I - 1 NOTE 4 & 5 VALVE NUMBERS ARE LISTED IN CHART II.

REMAINING 21SC-FT47'S *EFV221B-I *HOSE41 T ' 7. SEE CHART III FOR INPUTS TO SUMMERS.

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~ i VALVE i **

CLOSED

9 9 I CHART I I JET CALIBRATED JET PUMP INSTRUMENT NON-CALIBRATED JET PUMP INSTRUMENT LINE NUMBER LINE NUMBER EXCESS FLOW CONTAINMENT PUMP LOOP INSIDE CONTAINMENT OUTSIDE CONTAINMENT PENETRATION *HOSE ORIFICE RUN CHECK VALVE ISOLATION CHART 111 I 2MSS*P S&W MARK NO. GE !DENT NO. S& W MARK NO. GE !DENT NO. !LOW/HIGH PRESSURE CONNI !LOW/HIGH PRESSURE CONNI NUMBER NO. NUMBER NUMBER VALVE NUMBER NOTE 4 NOTE 4 l A ------------ --------21SC-FT47AIA-l B22-N034A 2-ISC-750-327-21A-l 2-ISC-750-377-21A-l 1307-16 46 *R025E!A-l *EFV271A-l *V271A-l JET JET 2CEC-PNL61'l IND SUMMER COMPUTER 2 A ------------ --------21SC-FT47CIA-l B22-N034C 2-ISC-750-326-21A-l 2-ISC-750-376-21A-l 1307-11 45 *R025C!A-l *EFV261A-l *V261A-l PUMP PUMP FLOW INPUT 3 A ------------ --------21SC-FT47EIA-l B22-N034E 2-ISC-750-320-21A-l 2-ISC-750-370-21A-l 1307-13 3'l *R024AIA-l *EFV201A-l *V201A-l 2MSS*P TRANSMITTER GE !DENT NO, GE !DENT NO, 4 A ------------ --------21SC-FT47GIA-I 822-N034G 2-ISC-750-32'l-21A-I 2-ISC-750-37'l-21A-> 1307-10 48 *R025LIA-I *EFV2'l!A-I *V2~CA-l 1 FT47A B22-R608 B22-K601A NSSFA102 5 A 21SC-FT48A!A-I B22-N033A 21SC-FT47JIA-I B22-N034J 2-ISC-750-318-2<A-I,. 2-ISC-750-368-21A-l,. 1307-14 0 0 37 *R025JIA-l *EFV18<A-I *Vl81A-l 2 FT47C B22-R608 B22-K601A NSSFA103 6 A ------------ --------21SC-FT47LIA-I 822-N034L 2-ISC-750-325-21A-I...J 2-ISC-750-375-2!A-I...J 1307-'l 44 *R025A!A-I *EFV251A-l *V251A-l 3 FT47E B22-R608 B22-K601A NSSFA104 7 A ------------ --------21SC-FT47N( A-l B22-N034N 2-ISC-750-330-21A-l 2-ISC-750-380-21A-l 1307-8 4'l *R025NIA-l *EFV301A-I *V301A-l 4 FT47G B22-R608 822-K601A NSSFA105 8 A ------------ --------21SC-FT47RIA-I B22-N034R 2-ISC-750-328-2<A-l 2-ISC-750-378-21A-l 1307-12 47 *R025GIA-1 *EFV281A-l *V281A-I 5 FT47J B22-R608 B22-K601C NSSFA106 q A ------------ --------21SC-FT47TIA-I B22-N034T 2-ISC-750-332-21A-l 2-ISC-750-382-21A-l 1307-15 51 *R025TIA-1 *EFV321A-I *V321A-l 6 FT47L B22-R608 B22-K601C NSSFA107 10 A 21SC-FT48C!A-l B22-N033C 21SC-FT47VtA-> B22-N034V 2-ISC-750-333-2!A-l 2-ISC-750-383-2!A-I 1307-7 52 *R025V!A-l *EFV33!A-l *V331A-> 7 FT47N B22-R608 B22-K601C NSSFA108..

10 1 Iii A 21SC-FT48CIA-l B22-N033C ------------ ---------'2-ISC-750-323-21A-l :c _, 2-ISC-750-373-21A-l :c 1307-18 42 *R024CIA-I *EFV23tA-l *V231A-l w 10 5 A 21SC-FT48AIA-l B22-N033A ------------ --------"2-ISC-750-331-21A-l lJ "2-ISC-750-381-21A-l lJ 1307-17 50 *RD25RIA-l *EFV311A-l *V311A-l 8 FT47R B22-R608 B22-K601C NSSFA10'l >-

u - u - q FT47T B22-R608 B22-K607A 0 11 B ------------ --------21SC-FT47BIB-l B22-N034B 2-ISC-750-334-21B-l 2-ISC-750-384-21B-l 1308-10 53 *R025Bl8-l *EFV341B-l *V341B-l NSSFA110 z 12 B ------------ --------21SC-FT47DIB-l B22-N034D 2-ISC-750-335-21B-l 2-ISC-750-385-21B-l 1308-16 54 *R025Dl8-l *EFV351B-l *V351B-l 10 FT47V B22-R608 B22-K607A NSSFAlll 13 B ------------ --------21SC-FT47F!B-I B22-N034F 2-ISC-750-336-218-l 2-ISC-750-386-218-1 1306-13 55 *R025Fl8-l *EFV36!B-l *V3618-l 11 FT47B B22-R608 B22-K601B NSSFA112 14 B ------------ --------21SC-FT47Hl8-l B22-N034H 2-ISC-750-313-218-l 2-ISC-750-387-218-l 1306-16 56 *R024Bl8-I *EFV1318-l *V1318-l 12 FT470 B22-R608 B22-K601B NSSFA113 FIGURE 5,l-2c 15 B 21SC-FT48818-I 822-N033B 21SC-FT47KIB-I B22-N034K 2-ISC-750-311-218-l,. 2-ISC-750-361-218-l,. 0 0 1308-7 33 *R025Kl8-I *EFV1118-I *V11<8-l 13 FT47F B22-R608 B22-K601B NSSFA114 16 B ------------ --------21SC-FT47MIB-l B22-N034M 2-ISC-750-338-2tB-l...J 2-ISC-750-388-21B-l...J 1308-14 57 *R025MIB-l *EFV381B-> *V381B-l 14 FT47H B22-R608 B22-K6018 NSSFA115 17 B ------------ --------21SC-FT47PIB-l B22-N034P 2-ISC-750-33'l-21B-l 2-ISC-750-38'l-21B-l 1308-15 58 *RD25PIB-l *EFV3'l!B-l *VJ'l!B-l 15 FT47K B22-R608 B22-K6010 NSSFA116 18 B ------------ --------21SC-FT47SIB-l B22-N034S 2-ISC-750-337-21B-l 2-ISC-750-3'l0-21B-l 1308-11 5'l *RD25Hl8-l *EFV3718-l *V3718-l 16 FT47M B22-R608 B22-K6010 NSSFA117 l'l B ------------ --------21SC-FT47UIB-l B22-N034U 2-ISC-?- 1cr_ 7<<a-:.4?-?(R-) ?- rcr-7r:.~-'la?-?(R-) 750-341-218-l 2-ISC-750-3'll-21B-l 1308-'l 60 *RD25Ul8-l *EFV4118-l *V411B-l ' 1308-8 61 17 FT47P B22-R608 B22-K6010 NSSFA118 20 B 21SC-FT48Dl8-l B22-N033D 21SC-FT 4 7WIB-l B22-N034W *RD25WIB-l *EFV4218-l *V421B-l 18 FT475 B22-R608 B22-K6010 NSSFAll'l NUCLEAR BOILER AND 15 8 21SC-FT48B<8-l B22-N033B ------------ ----------'2-ISC-750-340-218-l :c _, 2-ISC-750-363-218-l :c 1308-17 35 *R025S<8-l *EFV4018-l *V4018-l l'l FT47U B22-R608 B22-K607B NSSFA120 20 B 21SC-FT48DIB-I B22-N033D ------------ ---------"2-ISC-750-324-21B-> lJ "2-ISC-750-374-2!B-l lJ 1308-12 43 *R02401B-l *EFV241B-l *V241B-l 20 FT47W B22-R608 B22-K607B NSSFA121 u = u - PROCESS INSTRUMENTATION

11 NINE MILE POINT 11 NUCLEAR STATION UNIT SCRIBA, N. Y. 2 SOURCE: PID-28C-12 TITLE:NUCLEAR BOILER AND PROCESS INSTRUMENTATION UPDATED SAFETY ANALYSIS REPORT A B c D E F G H I J K USAR REVISION 25 OCTOBER 2022 _J 1 NEUTRON FLUX 1 VESSEL PRESS RISE CPS!l 2 AVE SURFACE HEAT FLUX 2 SAFETY VALVE FLOW 3 CORE INLET FLOW 3 RELIEF VALVE FLOW 150.0L--...J-~~~--..,.---------"'"1 300.0l- _______.::....:;:.;.:..:;:,;;:;;:...:.:;-.;.,:;;..:...-.;;.._ 4 BYPASS VALVE FLOW __ -t

0

<[ 100.0 200.0 a:

LL 0

z u

a:

"' e,

50.0 100.lll

2 0.00.0 5.0 0.00.0 10.0

TIME (SECONDS> TIME (SECONDS>

2 VESSEL STEAMFLOW 1 LEVEL ClNCH-REF-SEP-SKRTl 3 TURBINE STEAMFLOW 200.0 4 FEEDWATER FLOW 1.0

0 z 0.lll 4 100.0 z 0

Q.

c 0

u E

u

<[

0.0 2 ~ -1.0

-100.0L--------~ 5 ~0 --------~10.0 -2.0L-----_;u...-~---------;:

0.0

  • 111.0 TIME (SECONDS> TIME <SECONDS>

FIGURE

TRANSIENT "MSIV CLOSURE WITH HIGH NOTE: For c~le-apec1f1c re~lta see FLUX TRIP"

~ix A, $1wt1on A.S.2.2.2.3 SOURCE: NEDC-31994P NIAGARA MOHAWK POWER CORPORATION I THIS DRAWING CREATED Ei.ECTRONICALL y NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT

USAR REVISION 8 NOVEMBER 1995 MAIN STEAM

FLOW RESTRICTOR

SUPPRESSION POOL -~--~'--

FIGURE 5.2-2

SAFETY RELIEF VALVE SCHEMATIC ELEVATION

, NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT MAIN STEAM ISOLATION VALVES

DRYWELL

S/RV S/RV

REACTOR VESSEL

S/RV

I. '

FIGURE 5.2-3

SAFETY RELIEF VALVE AND STEAM LINE SCHEMATIC

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT 2 3 4 5 6 7 B g 10 1 1 12 13

TAB.Et SAFETYAIELIEF VI.Lii[ surrix ASSIGNMENT Al'll ASSOCIATED EOLA.tENT SAFtTTnELD'

.... "' FO\\H rou-1 ro1l-$ rou-2 rou-2 rau-3 tOU*l rou-~ rou-2 ro13-4 rou-* rou-* rou-~ rou.. 3

O£ca r0l6 NOICS VALVE FC..OtMW tSUPPt. DOC. ' $HALL er USCD WITH AND roitw A PART°'

1KIS PAID DAU.. 'I' TH[R[ AR[ ANY CONf'l.M:15 8£lW([N TH[ PtlD 1,. WPt. NO.'S ARC PttHIX(O av 822 UNL{SS 01t1(RWfS( N01(0 A.NO lNS P*O OAU, THC P*JO DATA SHALL COVUIN

J. W.UUUV(l tt$UIUMCN1S fOR VARIDUSftAHGts AR( CAU8RAICO F013A F0138 1(.* AS SUTCO snow. AU WAlCA L(V(L SWHCH 5£1POIHJS AR( NOMmAL.; 1H[ AMAlYS£S ARC PCRfUfi;M(O WITH TH( !lttfllCH lRtP 1165 1165 ~~~IN 1T~ :c~~~

  • ACAC.lOR 8UUMNC fCMP[AAIURt:

A. f\\ICL lONC : THC INSTRUM£NTS Af![ CAUBU1(0fOR SA1utlA1[0 WAHR STCAM COMOIJIONS AT 0 PS.IC.. 111( VCSSCl ANO F013D 175 TH( ORYW[LL WITH NO J(.1 PUMP HOW

F013E rour 1175 1115 ADS-SAfUY,RCLICF VALV( FOfl AU10 0£PRCSSURIZA1K>N FOR 1H£ NUUBER or SRV'S WHICH SHIU BC CONTROLLABLE FROM lHC RUIOlC SNJ1DO*N S'rSlCM 18'r A[J - sec NOTE 4

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IPllO. E-~~~o:c~sl~.':':O~...! ~..[~~~wmo rOR 12o*r. w.nR,., o PS1C rtNOl4

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  • RlAClORDf.CATH(AJ

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-i:--~lo--...... -+-__ __,_ SUPPRCSStONPOOt.HCA1Uf'-ASSUMCR(AC10RISOlAfCOIWMCOIA1CLY

  • 607A t<6078 Ar1[R 5CAAllWl1H All H(At DlMP COtt~ lo It<< POOL RlACIOR I I OCPR£~SllR12A1tON RAt( MUSl 8C flAPIO (rfOUCH 10 AVOID SRV

~i:--~--<>---+---+--+- OtSCHARCC CONOCNSAllON OSCl.LAHON PROOlCMS.. !HE POOL

~ Al1$1 Al1$1 AIJ~ A17'4 All~ A.11$1 Al7$7 Al7$8 A11$1 A1110 At161 A.1762 A176l A1764 A.176$ A\\166 A1767 A1718 A111i9 Al170

suPPt.£..:NTAL DOClMNTS l.N](R Ttt: fCl.LOWN; O:Nllll:S Mf. 10 IE USEOWCON.UICTENWITHTHISDAA"91C; R£r£ACNC(

SAFETY/R(LICFVALVtLOCATION ~

  • SPAIMC SU PRESSURE t N.Kl.CAR BOUR SYSTEM PM> ------------------822-*D
2. FECOWA1CR CONTRO. SYS1CM IEO-----------------C.1JrllD

). NUCLEAR BOIL[R STST(M ftP-----------------822-tolO 4. ELCC [QP1 SEP SAfCCUARO STS----------------AH-4DM

.lAll.E Vt EUllAlllN CORRELAlllN CHART :.t. R[MOlf SHUTDOWN SYSTUI 1:0----------------ll'f AC

6. RtOUNOANT au.Cltvtl'Y COHtROL $YS1CM DCS. SPlC ----C22-4090 CONl'RQ. ROOM WAl[R l£ftt£L NllCATC>N IJ()TJIF LEVELS 1. R!Dt.ltOANl ltC.ACltvtl'r CONTROi. $1'S1UI ELEM w _____ c21-~

~'f[f---------~~*~~-l[-~~-------1 *~*~*~

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1'1IP ar IUD '>-1-~"'-'---l r fUllC[ J fEEDWATERPIPINGDETAl.

S1[Mll U )>-+--'-"'----!

MIZZlCIO J

llilll.l<<NI l.KIOZlll- >-+----1 }

{~~~E*c ~*t.: 2 -*- ------+----+----+---1

tlGHLC¥ll.ALMlf-

_1_ ------- --------- ----- ~

NJRliW.WA1CRLf'<<l - GIVISIOHOR<<NUT..

fORVCSSCL..STRUMCNTATDf ISCCSUPPLOOCtl

.f.:"rtr.'t::t,~.-- -*- ------- --------- ----- ~

FIGURE II

~~ 2 i--)- ------ ----------1--";.;;.o__+-=..;;...--l

,__2_ ------ ~

_JS_"_

....!............... ~,_...,!!__,,______-_,._ __ !__ ---~-- ___ a:_ ______ a:_ __ _

SOURCE: 761E445AF - 07

TOrT.IG>41 FIGURE 5.2-4

~

~- NUCLEAR BOILER SYSTEM P&ID SHEET 1OF2

  • llKllllfj 511 nl-1Cll '°"1llQI. iTl'llll-DQC 31.
    • SiM.OOC.667 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2

! UPDATED SAFETY ANALYSIS REPORT

--*** 1 2 3 4 5 6 7 B 9 10 USAR REVISION 13 OCTOBER 2000 2 3 5 6 7 I lr

  • B 9 10 I 11 12 13

MECH CLCC U:VCL M[CH ELEC OIY OIY lRIP OIV DIV lQC POINT lOC

PT N4038 RRCS l!.UF'f>L. OOC. 6

  • 71

PTN403C RRCSISUPPLDOC.6.tc11 -+--1--+----1------~

PtN40lF' RRCSISUPPLDOC. 6*71

POST ACCIDENT lritONITORINGIRHRIAll

POStACCll)£Nl MONITORtHC. IRHR 1811

2. PISN67$8 Pl ~nae l PIS NG7~C t-l-S_N~-o--84-o-! -+-N.,,...SI ___ -= : 1-----+----<-,-+-p lS N67~0

l PISN618"' -

I r-;- ~... ----+--:NS-41A-l,...,,IRHR-:-'.:"ISOl:-I----!

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2 lSNH2B,(

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NS**NUCLU.RSTCAMSuPPLYSHUJOrrSYSltM AUi

  • ANALOCTRIPWOOUL[
      • SUPPL OOC. 6 & )

FIGURE 5.2-4

NUCLEAR BOILER SYSTEM P&ID

~* ) SHEET 2 OF 2

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 F=tNAL SAFETY ANALYSIS REPOR1:°

      • . 1 2 3 I I ~ i 4 I 5 6 7 I fl.I B 5 10 USAR REVISION 3 OCTOBER 1991 SPINDLE

PNEUMATIC PACKING GLAND ACTUATOR

0

PISTON LINER

INLET

BODY

FIGURE. 5.2-5

SCHEMATIC OF SAFETY RELIEF VALVE WITH AUXILIARY ACTUATING DEVICE

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT SUPER HEATED STEAM WITH I --1 PRESSURE AT 3.1 BARS DIFF SATURATED STEAM ENVIRONMENT (45 PSIG) 1 w (.!) <>.

a: :i:z u- :;

~ <t Cl) w u u

<t w:::l I- 0 0 a: a:W I- > u u>

w ::i...J z 0 0 u.

<>. OU w >

"' > 00 w
i: ti iii "' ~ <OM I-1-- :<u (.!) ~ o-Cl) ** <tO z -(.!)

a: Cl) 1-> Cii (.!) <.!lz

-w z

u. I-w~ Cii <t"' ::i u u z--Cl)

(.!l:::lU w...J ::i 0 8 0 Cl)::>

zzO...J(.!l u w > > > ::>Cl) WW

--> ~~ >-...J...J...J a:~ ct. "' "' "'

loo U(I) u u >-~ ~ ~ uo >- >-

171°C (340°F) o-- -:::> u z (.!) (.!) (.!)

160°C (320°Fl z z uu Cii Cii Cii -N w w w

...J...J...J u u u u u *u

TEMPERATURE WILL RISE ~ I

FROM AMBIENT TEMP TO I 111°c (340°F) IN 5 MINUTES

TIME-___,~

REMARK: THE MENTIONED TEMPERATURES ARE MIN TEMPERATURES

FIGURE 5.2-Sa

ABNORMAL AMBIENT CONDITIONS FOR ACTUATOR QUALIFICATION TEST

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 7 DECEMBER 1983 STEAM 0h

__ _::...l-, r-

~ 8 GENERATOR PRESSURE I TURBINE

RECIRCULATION PUMP

ROD FEEDWATER COOLING CLEANUP 0 DR'"' WATER

PUMP

TO CONTROL ROD DRIVES REACTOR WATER CL,EANUP

FIGURE 5.2-~

TYPICAL BWR FLOW DIAGRAM

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT SODIUM CHLORIDE (NaCl)

HYDROCHLORIC ACID (HCI)

E c.

_g.

10 UJ Cl a:

0

..J I

(.)

s 0

5.,,

I&.

0 cC

E (J --soDIUM 0 HYDROXIDE
c (Na OH)
E a 1.0

~

ui (J

z cC (J

> CHLORIDE (ppm)

Q z 0.03 0

(J (J

ii:

u w D.

I/)

0.01

0.1

0.01.._....... __________...... ___....... ____________ _

4 5.0 5.8 6 7 8 8.6 9 10

pH

FIGURE 5.2-7

CONDUCTIVITY, pH, CHLORIDE CONCENTRATION OF AQUEOUS SOLUTIONS AT 77°F (25°C)

NIAGARA MOHAWK POWER CORPORATION N,INE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT 1000.-------------------------------,

800

  • 600

400

4 in. LINE

200

100 80

  • 60
  • 20 ksi

30 ksi E a. 40

.!!)

LU 1-

<I:

ex:

~

<I:

LU

...J 20

15 *AXIALLY ORIENTED CRACK

  • SATURATED WATER SYSTEM 10 AT 1000 psig
  • ASTERISKS DENOTE CRACK 8 OPENING OF 0.1 in.

6

4

2

1...,.._ ______________________________________....... ____..... ____...... __ ~

0 4 8 12 16 20 24 28 32 36 CRACK LENGTH (in.)

FIGURE 5.2-8

CALCULATED LEAK RATE VS CRACK LENGTH AS A FUNCTION OF APPLIED HOOP STRESS

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT 12

DATA CORRELATION 11 Le= CRITICAL CRACK LENGTH (in.) 9 D =MEAN PIPE DIAMETER ah = Pl PE HOOP STA ESS MATERIAL* A1064 10 10

9

12 8

0 Lc/D = 15,000/crh

7 M I Ln 0 0

-x 15 x

~

ef c

- 6

5 20

4 25 0 Q GE DATA (-60°F) 30

3 Do O 0 BMI DATA

40 o~

50

60 70

0... 0 0.2 0.4 0.6 0.8 1.0 ---------------------------------------------------1.2 1.4 1.6 1.8

FIGURE 5.2..;9

AXIAL THROUGHWALL CRACK LENGTH DATA CORRELATION

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT 2 3 4 5 6 7 B 9 10 11 12 13

NOTES I...... TL:.t.Ull'HUTIC STlj !ITI. UN~ ar-w12 INDICA~.

l1J 2.. At.L tlMlNl-1 All(. I~ INCHl.i Utl:.PT Ai NOTED ON Dll"W ING

[!) 3.AH"LVIATIONS Pf.It Allil YI.I

(J]

,__--- - - - ----IS.38 Mlf.J --------t-----+ -l.5 1i> MAX 2 PLACES

3.41 MAX.

I l]J2~iN 1.0~

I ~1 _.,_.. _______________ _

f-- ----- -------~~---DM~----- - ---------1

~IM'iA\\------'lr---fMIN--~~

LLLL>-------------\\,._:~~~~~~--~--~--:=--- _ -:...j~j~ '

0 © APPROX. WT=6 UIS

0 ~:~:E~~:rl APPROX. WT' 5 lBS'

=~~~*3 Al'l'ROll. WT

  • 5La5.

FIGURE 5.3-1

BRACKET FOR HOLDING SURVEILLANCE CAPSULE

j NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT

-**** 1 2 3 4 5 6 7 B g 10 11 12 13 Nine Mile Point Unit 2 USAR

FIGURE 5.3-2a HAS BEEN DELETED

Now controlled per

Pressure Temperature Limits Report (PTLR)

PTLR-2, Revision 0

USAR Revision 21 October 2014 Nine Mile Point Unit 2 USAR

FIGURE 5.3-2b HAS BEEN DELETED

Now controlled per

Pressure Temperature Limits Report (PTLR)

PTLR-2, Revision 0

USAR Revision 21 October 2014 Nine Mile Point Unit 2 USAR

FIGURE 5.3-2c HAS BEEN DELETED

Now controlled per

Pressure Temperature Limits Report (PTLR)

PTLR-2, Revision 0

USAR Revision 21 October 2014 Nine Mile Point Unit 2 USAR

FIGURE 5.3-2d HAS BEEN DELETED

Now controlled per

Pressure Temperature Limits Report (PTLR)

PTLR-2, Revision 0

USAR Revision 21 October 2014 Nine Mile Point Unit 2 USAR

FIGURE 5.3-2e HAS BEEN DELETED

Now controlled per

Pressure Temperature Limits Report (PTLR)

PTLR-2, Revision 0

USAR Revision 21 October 2014 PRESSURE VESSEL EMBRITTLEMENT TREND

ii:

- ---- SHIFT IN

RTndt ADJUSTED RTndt

10L-!&-..._..__............ __............._................ ____ __.

1e+17 1e+18 1e+19

FAST NEUTRON FLUENCE (E> 1.0 t.tev)

FIGURE 5.3*3

CALCULATED ADJUSTMENT OF RT Nor FOR NINE MILE POINT UNIT 2 LIMITING BELTLINE PLATE C3147 USING REVISION 2 TO REGULATORY GUIDE 1.99

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT* UNIT 2 UPDATED SAFETY ANALYSIS REPORT

USAR REVISION 3 OCTOBER 1991 REACTOR VESSEL HEAD TOP HEAO COOLING SPRAY NOZZLE DRYER ASSEMBLY LIFTING LUGS STEAM DRYER AND STEAM DRYER ASSEMBLY ---- SHROUD HEAD ALIGNMENT AND GUIDE BARS STEAM OUTLET NOZZLE

STEAM SEPARATOR AND SHROUD HEAD STANDPIPE ASSEMBLY LIFTING LUGS FEEDWATER INLET NOZZLE FEEOWATER SPARGER

SHROUD HEAD TOP FUEL GUIDE

CORE SPRAv------t SUPPL Y HEADER SHROUD HEAD FUEL ASSEMBLY HOLD DOWN BOLTS CONTROL ROD CORE SPRAY SPARGER FUEL SUPPORT PIECE

IN CORE FLUX 1.1------- FLOW INLET INTO FUEL BUNDLE MONITOR ASSEMBLY CORE SHROUD RECIRCULATING WATER CORE PLATE ASSEMBLY INLET NOZZLE ~~f------- VELOCITY LIMITER

JET PUMP ASSEMBLY RECIRCULATING WATER OUTLET NOZZLE

DIFFUSER SEAL RING CONTROL ROD GUIDE TUBE AND SHROUD SUPPORT PLATE

CONTROL ROD..

DRIVE HOUSING

FIGURE 5.3-4

REACTOR VESSEL

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT

HIGH WATER LEVEL \\

ALARM, L7

  • 568.0 \\_

HIGH WATER LEVEL NORMAL WATER. TRIP, L8 = 583.0 in.

LEVEL= 563.55 LOW WATER LEVEL SCRAM, L3 = 540.0 in.

LOW WATER LEVEL ALARM, L4 = 559.0

LOW WATER LEVEL, L2 = 489.5 in.

TOP OF ACTIVE FUEL ----

ZONE= 366.31

LOW WATER LEVEL, L 1,;, 398.5 in.

FIGURE 5.3-5

NOMINAL REACTOR VESSEL WATER LEVEL TRIP AND ALARM ELEVATION SETTINGS

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 24 FEBRUARY 1986 CUTui.ae. Of' u:ITNC:.Tt:D flR.1!Jlrl. Ofl SHk'T FUU..

5"TDRM,C.

  • CRSK L.0Atltt*U011 PocL.

o*

PLAN VIEW PLAN VIEW II SELECTIJI SWITCH 'RESTRICTED MlllE" IN "IORM" PDSITIDN SELECTOR SWITCH 'flESTRICTED MODE" IN "CASK" POSITION

SOURCE:0002410044006 FIGURE 5-4

CRANE RETRICTED SHEET 1 OF 2 AREA

UPDATED SAFETY ANALYSIS NINE MILE POINT-UNIT 2 REPORT

USAR REVISION 22 OCTOBER 2Bl6 _J

JSAR FIG 5-4.dgn 6/6!2016 7.20:35 AM CRANE OPERATION DATA

BOTH THE CAB CONTRtl. CINiULE AND TH£ RADIO "BELLY aor 11 SELECTat SWITCH "RESTRJCED MtXlE" IN "CASK' POSITUJJU BRIDGE AND TROLLEY IJI SELECT[ll SWITCH "RESTRICTED MOOE" JN "BYPASS* PQSJTIDJti BAIOOE AND TRDL.LEY HAVE A ICEY OPERATED 5n.ECTI>>t SWITCH UIBELED TRAVEL WILL BE AS F(l..LOV5' ($[£ PL.AN VIEW Jiil. NOTE THAT AUX *1 AHO -TRAVEL WILL BE AS Fl1LDVS.

'RESTRICTED HQ(E". THIS SVITOI tM5 Ttff:E POS(TJQHS LABELEOt AUX *2 HOIST WILL BE INDl'EAABLE IN TtE CASK AREA.

II "tCJRH" - THIS POSITION 1S TtE ONLY PDSITJDN IN WHIOI THE ICEY MAY BE REMOVEQ THIS POS(Tl(Jol WILL ALLOW UH-RESTRICTED QPEJIATICl\\I OF #ILL HOIST IN All 2J"CASIC" 9r1ds! Tro.*I RHtrlc\\lon AREAS m:' TtE STATION. THIS llCLLOES lHDSE AREAS OF TtE S?EHT F\\EL 3l"BYPASS" STORAGE ANJ CASK LOADING POCL.

"*th \\h* troll9\\,t 01. *1V-.,.... af br1dgll m-.d w1\\h irollq l SEL.ECJOR S\\tlTDt "RESlRIClEll HaF lH 'tG\\K' P051llft &RIDGE NCD TROLLEY pf"'l;l*lllll'tl **ltlJ>I In,,..pt>9d pHlt.IDnf ~ brldgii -t.lan TRAYEl. WJLL BE AS FCl.LDWS.tSEE PLAM VIEV 1U rr- *1V-dlr*iilnan.n1i:ih *Ill PG91llan *J 111*111 '-*

...... ""- r**tr1c\\ed 9P1'"1. r.. 1 *LDr-. pool -..

  • Ill "°lp the bfo1dg9 p!'"Oal,.1\\\\1 -ltQh,. 8'odi 1n oon,.-.iit.i'lln Bo-td9* T,...... RHV1otaon 10\\h v.. volley ***'Wlh. *-*..-,.1** operllbl* --

With \\hm Vall-.. *1. *tV.- mnd af bradgia...1d *Ith '"-limy -t.aan mnd -'L tw..i.... lt*..... *Ill - ta,...., *l\\h prG***&\\y ***tch '" v.. tl'lpp.d ~1\\.1Dn19"'a1 br-1d,* UI* o9ft"9r hne of *3 1M1n hook et. eds!* of a cu.. o.ot...

MOtaon from *IV-d1,.*ataon ooh1ah "°"'ld pom1taon hook* -~i.J..ct.Ian d*'-""""twd by th. aisntar af r*eo'-

er-..,. r-**tnct.md -... **II V1p V.. brufg. pr-o*1*1~ ***tah *1.ot&on 1.a a1v..r,,,,_ OOo"f'Wtr of V.. paol -**

std 1n c:onpmtaan *nh V. W1dg* **at.ah. de-_,,.1.r* HoGk has eccna ta Via CAM. lo*hng pool.,.... L1n11 i.1or.

.u er.,. !90\\.IGn! s1d..,. brM... n.. br1dg! ** u OOIM '° or \\h11 or-.o *all ta. d9\\el"1tl1rN1d bw a line fron "'-

,...,, *Ith the D9"\\ar-h,,. *( hook* at. ~..,,,. af

  • o.nt.- af __..,.. awu.. ta..._,,._ *-- of' the a1raul.,....,...,u.1 !9C:'ta.., "-'-**11r.d by th. o... wr Gr _. 1~1"'111 pool fpoinl. AJ,.'Id bw.., -tu-.......... nec1

,.,ae1.0r *iauon u 11V-Inner" CDr'f\\er or V.. pool.,._._ boj \\he d1a\\.M!Ca from v,. 1:;itn'IM" or.... "°" s\\a\\lDn 10 All:JITJ[J'CAl.1.T+ Tt£ BRUX;E TRAVEL LIMIT SVITCH STATUS LIG-tT V.. r.,. *dg* *t. '""'"" 8) or ""9 -a l!Nldang pooL Wlll CDNTJP&JOUSL T FL"5H. ADIJJfUHU *.l.Y, THE BRIDGE TRAVEL LIHIT STATUS Ur.HJ WILL tnNTINUDUSLY FLASH wtEN TR.!J..LE'f TRAVEL HDJJDNS EXCEDl Tr-oll!u T,.,_J Re1tr1cuon THE BDAROERS DF THE CASK PCXl. AREA.

Vi\\h **Vt*r- *nd of Vt* brtdg* pcn1\\.lon!d a....- Vie Trallty T,.,,.J Reur-1pt1an r'-trlO\\.!d..... and *IV> br1dg! prO*l*l\\y **It.ch 1n 1.r'lpp!d poa1taon. 9f'll ~llew -uan ooh1ch.,auJd pa11taon hook* With ** u... mnd or v.. bra-'9-pa*a\\.loned ID-v..... v1at.d a-1hll.--v1awd _.,.,. *111 "'P W vall*w pr-a*1,.1\\t,I...,., ru.l *tar-911* paal _... ond *1th "- br-1dg* pro*l**tw

      • \\di _,.. In DOnJwlO\\.l.., *1th tNi bridge... \\oho ***'°' 1n "1pped pa.1\\.1- ~ 1r-C1llew -t..lan.tu.d1
  • ~u* *II - --a~Clf'\\'9..od.. t. brel'I-n.. wcr.ild pout.Ion V.. *3 lfl!ln hack av~ U.. !\\or'"!f9 pool.,..,._

"'a111y *all - i.,...,, **th *1V-V.. c.n\\.!r hne *di vap the t1-alley P"'0*1*1'1.I... tatt !NI 1n aon,,..,a\\u*'

  • 3 t-k 1-anJ or-V.. ctni.- hr. *1 hoak 1-....J *nth th. br1dgm **1~ de~I** apM"abJa ---t.1-ld!p*ndlt\\9...,an.h1ah..,d or "'* br1dg* ** pa*au-d and Ht. br!lke.. The VDll9'1 *Ill C- \\a,...\\. *1"1 V.

0- 1J'MI r!Hrlc\\!d -!I on th* I,._ - hr. a( ! C*nter hr19 of INlln hook *\\. U.. *dgt o( on.-0 hne

-9"""'1t.al *mi::~an d!t!nN,,.d.,,,. u... 11nn1-d1*W-.O* r.--.,..._..,n.d by "1* 1111n1....,.. d&!\\ancl! r,._, U. aen\\ar tha. _,w,. ar....,'°'" *Mlt.IAl"I tQ th.,..... t... or "- *tar'ap or.-.eotoi- *Mltlan ta...... ar th..,.... t. r.. 1 -~Iii*

pool a-1e.ADIJJTIOHALLY. Tt£ IRIOOE TRAVEL LIMIT SlillTCH STATUS LIGHT poal1 1n the Dl"!O or aw onk loading pool. V. hook WILL 11.LlJitlNATE.,.JJ b* *\\ edge or.,,... o lane dllt!r-1111nad by U. dl*\\al'IO*

ff'_. U.. Cl!t\\\\er' of V..,...9121.Dr' Ua\\lan ta V.. f!I" -tgll TO RESTORE THE CRNCE DPERATlCIH MCI RESl.K MOTi'" WITH THE SELECTOR at. Cpcnnt. Bl ar V.. cuk lcuu:f1ng poc1L SWtTOt '11ESTRICJED MCIE" JN Tt£ 'tCltM" POSIT!~ MOVE n£ TRO..L£'f AODITICJIALLY, Tt£ BRIDGE TRAVEL LIHJT STAUS t.IGHT Will AWAT FAQH Tt£ RES1RICT£D ZONE USING ffit£R 11UOOE OR TROLLEY CONTIM.OJSL.Y Ft.ASH WHEN TJO.J..EY TM~ HOJJONS DCE'ED l'CTICIN. NOTE THAT Mier.£ TRAVEL LIMIT STATUS LICHT VILL FLASH FOR TIE BOMO£RS OF' Tt£ CASK LOADIM'.i POii.. AREA.

4 SECD>OS. 1T VIU. NOT BE POSSIBLE TD HOVE 1t£ TRDLL£Y 8ACX TDVMDS TtE ZDtE FCJ! THE l>>1UITIDN OF THE 4 SECDNlS. AFTER THE 4 5ECCHJS. THE BRlOOE TRAVEL LIMIT STATUS LIGHT WILL Tl.Bl DFF. TD RESTORE CRANE CPERATIDN AND RESUME MOTION VITM

THE SEL.£CTOR SWITOf "RESTRICTED HCIJE* JN THE i:ASIC" PQ5Jrl[J(. HOYE THE TRQ.LEY AVAY FRDH THE RESTRICTED ZONE USINli EITtER BAIDGE DA TREl..LET HDTIDH. NJTE THAT BRIDGE TRAVEl. LIMIT STATUS LIGHT WILL R.ASH FOR 4 SECCNJS. IT WILL HOT BE f"QSSlm.E TD HOVE TI£ TftCLLE't' BACK TOWARDS TtE ZONE FDR THE DJRAHQN CF THE 4 5EC(ICJ5. AF~ THE 4 GECDNDS. THE SRJDCZ TRAVEL SlATUS LUJtT WlLL T!..Hi CFF.

SOURCE: lillillil24llillil441illil6 FIGURE 5-4

CRANE RESTRICTED SHEET 2 OF 2 ARtA

UPDATED SAFETY ANALYSIS NINE MILE POINT-UNIT REPORT 2

USAR REVISION 22 OCTOBER 2016 _j SUCTION FLOW

... DRIVING FLOW

CORE

SIMPLIFIED SCHEMATIC

RECIRCULATION OUTLET

RECIRCULATION INLET

DISCHARGE SHUTOFF VALVE FLOW CONTROL VALVE

SUCTION SHUTOFF VALVE

FIGURE 5.4-1

RECIRCULATION SYSTEM ELEVATION AND ISOMETRIC

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT

c~i~* ;;.~UrJ:~-=....
a. fJ..l~~,w~msrs...,,.:-.i*.=**11

l.GPt~STlllf'WCllW'lMSft:11MIS-.....0*PLCL l.

FIGURE 5.4-20

R£ACTOR COOLANT <REC! RCULATI ONl

NIAGARA MOHAWK POWER CORPORATfON SOURCE 12177-PID

  • 2'1A*8 NINE MILE POINT - UNIT 2 TITLE*REACTOR RECIRtlA.ATION SYSTEM UPDATED SAFETY ANALYSIS REPORT U5AR REV!5ION 1 3 OCTOBER 2000

KEY-XMUSTBEENERGIZED t~~~;~~:~~~~~ BUT HAY

I *-.. *~ I~:- I*?~~=~* I~ --*- I

3A PILOT 3/'4"311!100PSI 1/2

4A ACT.OR. 1-301!1111PSI 3/'4

SA CJRCDR. 3/<t"'3008PSI 1/2

3. s~~~~i~ NOT PER s&w STANDARDS ARE PER ANSI

"'* ~~~~:&c... ~~~~o PR[~~~~~ ~~~H~1::-8~e.9~ STAUFFER

8 N.O. E3&mb ELEC 1~2a~::~TOR

~

PIPE 0.TIIOOIA B(ill!fil)

18

FIGURE S. 4-2d

REACTOR RECIRCULA TJON SYSTEM SOURCE, PID-290-9 TITLE, REACTOR RECIRCULATION SYSTEM 11 NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N. Y.

UPDATED SAFETY ANALYSIS REPORT M

USAR REVISION 16 OCTOBER 21illil4 1400

H HEAD (feet) 1200 N NPSH (feet)

E EFFICIENT (percent x 10) x RATED CONDITIONS

H 1000

(.)

z w

~ 800 u.

u.

w

I:

en 11.

z a

<{ 600 w

r

400

200

______________________________ _..u----

N -

PUMP FLOW (gpm) -THOUSANDS

FIGURE 5.4-3

RECIRCULATION PUMP HEAD, NPSH, FLOW AND EFFICIENCY CURVES

NIAGARA MOHAWK POWER CORPORATION NINE MrLE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT THROAT OR MIXING SECTION

SUCTOON --......... e.. -

. --~~-- r DRIVING FLOW.,._...... ~ ~--..1...-------------~------------ --

FLOW____, <Sr--------------._

DRIVING NOZZLES

---1

DRIVING FLOW 4P

SUCTION.

FLOW 4P

______ _l SUCTION FLOW

FIG URE 5.4-4

OPERATING PRINCIPLE OF JET PUMP

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT NORMAL STEAM WATER LEVEL SEPARATORS

TOP OF STEAM ACTIVE CORE SEPARATION DISTRIBUTION PLENUM

,,--- WATER LEVEL 1 AFTER BREAK IN RECIRCULATION I LOOP I ACTIVE CORE I

I r I I I I I I l_~_)

FIGURE 5.4-5

CORE FLOODING CAPABILITY OF RECIRCULATION SYSTEM

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT UPSTREAM TAP DOWNSTREAM TAP (1 OF 2) (1 OF 2)

I I tj INSERT

MAIN STEAM PIPE

FIGURE 5.4-6

MAIN STEAMLINE FLOW RESTRICTOR

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT

  • PNEUMATIC COtfTROL ASSEMBLY

SPRING YOKE ASSEMBLY

I PILOT DISK.

FIGURE 5.4-7

MAIN STEAM ISOLATION VALVE CUTAWAY VIEW

NIAGARA MOHAWK POWER CORPORATtON NINE MILE POINT -UNIT 2 FNAL SAFETY ANALYSIS REPORT

, AMENDMENT 28 MAY 1987' THIS FIGURE HAS BEEN DELETED

FIGURE 5.4-8

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT

AMENDMENT 28 MAY 1987 *

(

OUUIDE IMSIOE CONTAINMENT CONTAINMENT

~

2-RHS-eea-se-2ta->~

10

FIGURE S.4-9a

REACTOR CORE ISOLATION COOLING

SOURCE, PI0-3SA-I 6 NINE MILE POINT 11 TITLE, REACTOR. CORE ISOLATION COOLING NUCLEAR STATION - UNIT 2 SCRIBA, N. Y.

UPDATED SAFETY ANALYSIS REPORT I USAR REVISION 19 OCTOBER 20I 0 _J

£!?HU

I I I

~--~

~I ~'Al ** I "i:'.'.~-11::'"'

r.ia. ->J--OBL

~\\All I 1 _,.._ T -::...

'-'--~

FIGURE ~

  • 4-9c

REACTCA allE ISCLATIIll COCLUC

(SEE: llOTE:S 12. 13 ~ NJ MODE,4 sl.ICTIOIV FllOH COMJE:NSATE sTORAaE:. R£ACTtR AT HIGH PRE:sSU?E:. SIF'PR£ss1av ~ AT HIGH PRE:ss.

LOCATIOIV Q 1-2 18-2 ',19-194 194-G ~-.a!>O.a!>O*I 18-11 LOCATIOIV Q I 2 3 _, 5 G ? 8 9 18 II 12

FLOi'-SEE /\\OTE 2 - G8ll GIG &all - -e - IJ'l.N :n.N 31.N /6 JG 16 ?5 JG l;;;;}~:~A

  • 1225 18 -

LIA£ SIZE. IN. ST.'H4T£0 1,1

MODE B SU:TIOIV FllOH CCNJE:'NSATE: STORAaE:. R£ACT(Jq AT LOI.' PRE:SSl.ii'E:. SIF'PR£SSIOIV ~ AT HIGH PRE:S"S.

LOCATIOIV 0 I 2 3 <f

..... NSATE....... - 9.36 9.36 9.36 JG JG JG ?5 JG

0 ?tx#J,f:.,l-t.R£ o F 1811 /Jiii llJlll 11111 U8 -

MODE c SU:TIOIV FllOH SIF'PR£SSIOIV ~. R£ACTtR AT HIGH PRE:SSU?E:. SIF'PR£SSIOIV ~ AT L01' PRE:SS.

LOCATIOIV Q I 2 3 <f 5 G ? 8 9 18 II 12 I FL01'-S££ llOTE: 2 - G8l6 GIG G8l6 - -G8l6 -.>r *.llr~.llrf.>O *.llr JG JG JG ?5 IG I

I I

I I

I I

I MODE D SU:TIOIV FllOH SIF'PR£SSIOIV ~. R£ACTtR AT UN PRE:SSl.ii'E:. SIF'PR£SSIOIV ~ AT L01' PR£SS.

I LOCATIOIV Q I 2 3 <f 5 G ? 8 9 18 II 12 I

~ FL01'-S££/IOT£2 - G8l6 GIG G8l6 - -G8l6 -8.<f811."88.<fl1 JG JG JG ?5 /G MUNMY

OMINDlll:ING SJANO*BY10..DS£D OLRING£ffMTIDN v*r

I : MODE F TEST NOQE:, Sl.ICTIOIV FllOH COMJE:NSATE: STa;A(}E. R£ACTtR AT HIGH PR£SSl.ii'E:. SIF'PR£SSIOIV ~ AT LO/Y PRE:SS.

TOTALAl\\r--.-...J I LOCATIOIV 0 I 2 3

- 8 - V.M.?7.MV.M JG JG IG ?5 JG

l~~z~ o F 1811 18//!1 llilil - 5J/5 SAT SAT 218 11!.16 1811 186 333 Ille

=u

__ **~ ~-i---------.c~** ~*~j SOURCE: 5.4-10-01 FIGURE 5.4-10

---*~I~~ REACTOR CORE ISOLATION COOLANT SYSTEM PROCESS SHEET 1 OF 2 DIAGRAM

THIS DRAWING CREATED ELECTRONICALLY NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT

USAR REVISION 1 9 OCTOBER 2010 _J L

I.ATMOSPHERIC PRESSUAE OF 14.7 PSIA WAS USED IN COLCIA.ATIONS.

z. WATER FLOWS ARE SHlWN IN ClPH, STEAM FLOWS IN I-LB/HA. AND AIR FLOW IN SCFM 114.7 PSIA ANO 68" Fl.
3. THE MAXIHt.H POCI.. VATER TE~RATl.ftE FOR CONTINOUS SYSTEM CFERATION WILL HOl EXCEEO J4tr F. HOWEVER. 0t£ TO POTENTI-.,

SHORT TEAM OPERATION AT HIGt£R TEMPERATUA£S, PIPING EXPANSION SHOLi. BE BASED ON t7r F,

4. Tl£ IMECOYEREO FLOW NOZZLE PRESSURE DROP OF 4.5 PSI IS A FIXED LOSS BETWEEN LOCATIONS @ AND 0.
5. Tl£ LIU OIL COOLER PAESSUIE OAOP OF 5.8 PSI IS A FIXED LOSS &£TWEEN LOCATIONS@AND@.

SUCTION FROM CDNO ST()fljll;£ - - - - - - - - - - - - -HOOE A l 8 SUCTION FROM SlffRESSIONPODL ------------HOOE C & D PUMPOISCHARllt:--- ------------- -.HOOE C & 0 STEAM Slffl.Y _ - - - - - - - - _ - __ - __ - -HOOE A & B TIJlBINE EXHAUST-- --- ----------- - HOOE A & C TEST LINE ___ - - - - - - ______ - __ -HOOE F COOLING SYSTEM _ - - - - - - - - - - - - - __ -HOOE A 7.SYSTEM OPERATION IS POSSIBLE WITH INTERMEDIATE PRESSURES IN Tl£ REACTOR VESSEL AND Tl£ SlffRESSION PODL.HOWEVER.Tl£SE CONOITIONSOONOTCONTROl.PIPEOAVOLVESIZINGOASPECIFICATION.ANDNODATAISSHOWN.

8. PUMP MINI-FLOW REQUIREMENT HAY OCCUR OUAING ANY OPERATING HOOE. FLOW REQUIREMENT IS 75 ClPH MINllU-1.

'I. FDA VOi.YES AND FLOW INFOAHATION. REFER TO THE AHR SYSTEM P&IO HPL E12*1919 AND PROCESS OIAORAH HPL E12*1829.

... s~I: :~s::. ~'::°8:.0E::...~NT IS NOT OPERATING. INTERMITTENT FLOW OCCl..RS THROUGH THE STEAM SlJIPLY LINE DRAIN TRAP.

11. HEAO SPRAY NOZZLE PRESSURE DROP IS 11 PSI.

lot. DESIGN PRESSUIES ANO TEMPERATURES GIVEN ARE Tl£ BASIS FDA DESIGN OF BWRSO SUPPl.IEO EQUIPMENT. ESTIMATED LINE SIZES

=..~=~':""TION ONLY. ACTUOL LIHE SIZES AS DETERMINED BY PIPING DESIGt£R.5HOLL MEET Tl£ PROCESS DATA HYIJRAULIC

13. "PEAK PRESSURE" IS THE MAXI-PRESSURE ANTICIPATED OUAING A TRANSIENT PERl(X) WITH ALL OF THE CONTRIBUTING ELEMENTS AT AHAXIHUH.ITWOU.DBE EXPECTED TO OCCUR LESS T-11.0F SYSTEKOPERATING TIME.
14. FLOW VOLUES SHOWN CONTINUE TD BE PROVIDED TO Tl£ RCIC PUMP WKEN Tl£ SlffRESSION POOL SUCTION STRAINER IS 59 FDA HODES C l 0 ARE 9ASED ll'ON SUCTION PIPING DESIGN PERKITTING THE MINI-REQUIRED "'5H TO PERCENT PLUGGED.

15.HAXI-LINEAR LENGTH BETWEEN POSITIONS 5ANDZZEOUALS68FT.TME INTERNOL CRDSS*SECTIONOL AREA OF Tl£ VACIA.M BREAKER PIPING THAT IS SHARED BY RCIC AND AHR SHALL BE EOUAL TD DR OREATER THAN Tl£ COMBINED INTERNOL CRDSS*SECTIONOL AREASOFTt£1NOIVIOUALRCICANORHAYACUUHBAEAKERLINES.

11;. AEFER TD RCIC TIJlBINE VENOOAS DRAWING FDR LINE LENGTHS CONNECTING POINTS IS.23.24,25 ANO 26.

17.=*=r~~c SYSTEM STANDBY A FLOW t:E !.4 GPH OCCURS THROUGH TIE TUR81NE EXHAUST LINE DRAIN POT SYSTEM Al 25 PSIA

16. AIR fLOW fRIJ1 Ttf ll.1¥() Sfil. SYSTEM l'lf'IENTS STEat1 LEAICAOE ff l58 Ll!ftfl fll1J1 Tlflllltt:,
29. ll'ON RCIC SYSTEM INITl*TION. FLOW INJECTION TO THE REACTOR VESSEL IS STARTED AT 25.8 SECONDS AT A FLOW RATE OF 4*8 CPH. RATED DESlllH FLOW IS ESTABLISHED OT 36.* SECONDS ASSl.MING THE MAXI-OLLDWABLE VOi.VE STR(I([ TIMES FOR

~~/~~~i~ IFll J>AND 21CS*HDV l 4311'81~ >. THE FlJiCTIONOL REQUIREMENTS FDA REACTOR VESSEL WATER INVENTORY

LOCATION

@ MINl-NPSHATPUMPSUCTION

  • 22FEET
  • HOST LIMITING CONDITION WITH SUCTION

FROMSUPPRESSIONPODL, "'5H*23FEET

@ HAXIHLM PlW TOTAL DYNAMIC tEAO tAE.OUIA£0 BY SYSTEM>

S,3888FEETFOAMOOESAlt 6111 FEET FOR MODES 8 a. D

@AND@

  • 15PSl lSEENOT£6J

@ HAXl-PRESSUREOLLOWE0

  • 65PSIA

@ MAXIMUM PRESSURE OLLOWED

  • 125 PSIA PRESSUREISSPSILESST-POSITIOll@

@ HAXl-PRESSUREREQUIRE0

  • 65PSIA

@ SUFFICIENTPRESSURETORET-TDSUPPRESSIONPDDL

FIGURE 5.4-10 REACTOR CORE ISOLATION COOLANT SYSTEM PROCESS SHEET 2 OF 2 DIAGRAM

THIS DRAWING CREATED ELECTRON!CALL Y NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT

USAR REVISION 18 OCTOBER 2008 2200 RPM 4700 RPM

55000

50000

45000

40000 a:

J:

iii co 35000

...J I

~

0 30000

...J u..

? c(

I-w 25000

U)

20000

EXPECTED PERFORMANCE 15000 TRIP & THROTTLE SIZE: 4 INCHES RATED INLET STEAM : 1135 PSIG - 562°F 10000 LOW INLET STEAM: 135 PSIG - 358°F RATED EXHAUST PRESSURE: 10 PSIG

5000

o...... ~..._~....... ~--'~~....... ~--~...... ~~..._~...... ~....... ~--'~~....... ~--~...... ~~"'-~~

0 100 200 300 400 500 600 700 800 900 1000 1100 1200 1 300 1400 1500

BRAKEHORSEPOWER

FIGURE 5.4-1 Oa

RCIC TURBINE CHARACTERISTIC CURVES-STEAM FLOW VS. POWER

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 24 FEBRUARY 1986 60000 STEAM RING INLET

55000 EXPECTED PERFORMANCE TRIP & "FHROTTLE SIZE: 4 INCHES RATED INLET STEAM: 1135 PSIG-562°F 50000 LOW INLET STEAM: 135 PSIG - 358°F RATED EXHAUST PRESSURE: 10 PSIG

45000

a: 40000 J:

<n ID

..J 35000 I

~

..J LL. 30000

?;

<{

w I-(/)

25000

20000

15000

10000

0 100 200 300 400 500 600 700 800 900 1000

PRESSURE - PSIG

FIGURE 5.4-10b

RCIC TURBINE CHARACTERISTIC CURVES STEAM FLOW VS. PRESSURE

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 7 DECEMBER 1983 eDRF: 0000-0071-6768 eORF Seetion : 0000*0071-6783 Rev. l

Nine Mile Polrtt Unit ? EPO RHR. S.ystem Shutdown Coormg CSOC> Niolysi&

  • Two SD.C Loops 61* F Service Wo.ter, ANS 5.11979t2a

~

550 MO ~

~\\

M e,..

2.* 400 - \\

Cl

  • '-Q).

Q. \\

.,.... i 350 '

-. \\

- \\

200 - \\

150 ~

100...... '

0 2 4 6 8 12 14 16 18 20 Time After Control Rods Inserted !Hours>

I-EPJJ* Two Loops - - - 125 Deg.FI

20 of 41 Plot* EPU Two L.oops

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USAA REVISION 20 OCTOBER 2'012 ~

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USAR REVISION 20 OCTOBER 2012 ~

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A B c D E F G H I J K USAR REVISION 25 OCTOBER 2022_J A a D F M N

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UPDATED SAFETY ANALYSIS REPORT A B D G H USAR REVISION 20 OCTOBER 2012~

I.IPL NO <E12*1020>

NOTE:

1. FOR DATA PERTAINING TO NUl.lSERS WITHIN HEXAGONS REFER TO PROCESS DATA REF. 1.

RCICLINE 2. TO REACTOR BUILDING EQUIPMENT DRAINS.

,---------------------1 I

REFERENCE DOCUMENTS: MPL ITEM NO.

1. RESIDUAL HEAT REMOVAL SYSTEIA Pll<ID B12*1010
2. NUCLEAR BOILER PROCESS DATA B21-1020/B22 -1020

SIDE II SIDE I

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  • UNIT NINE MILE POINT 2 SCRIBA, N. Y.

UPDATED SAFETY ANALYSIS REPORT

USAR REVISION 19 OCTOBER 2010 _j

<SEE NOTE 3> MODE F <SEE NOTE 3 a. 4) MODE A-1 POSITION Q 1 2 3 4 5 6 7 8 9 10 13 49 24 1 POSITION 0 1 2 3 4 5 I 6 7 B 9 I 10 16 11 29 FLOW-GPM FLOW-GPM FCFi!3BXl84AF (/:12-1020)

PRESS.-PSIA,._, x x x x x l'Xl'X 'X 'X X PRESS.-PSIA '".;Y x x x x NOTESa TEMP. "F l'X A-l ~:J.SR~~jT~~p~~~~C£~1S HI~

MAX.PRESS. A-2ACCIOENT WllHREtlRCU.. ATIOHLlNE8REAK !NEITl-ER DROP-FEET SJOEAJrC>lfflEEPUHPO'ERATIOHMSTRA!HERPLIJGGEO

[LOOP C \\._LOOPS A S. B WITH t. PLAHT SPECIFIC DEBRIS HIX.OB HIM>

8 POST ACCIDENT COtHAIHHEHT SPRAY WITH HEAT A£JECTJC>>f WITH ff. PUHP OPEAATIOH ANO STRAINIER Pt.UGGEDVITH A Pl.NH SPECIFIC DEBRIS HJX.CPEAIC SUPPRESSIC>>i POfl. TEfoPERATUREt R,PRESS. 135 PSIG MODE G <SEE NOTE 14) MODE A-2

POSITION Q 29 25 26 4 5 6 43 24 1 1 2 3 4 5 6 6.2 43 24 1 POSITION 0 1 2 3 4 5 I 6 7 B 9 10 16 11 29 FLOW-GPM 1000 rz.rz. -FLOW*GPM D HORMt.1..SHUJ'DCWfArTtRll!ll..OrlJCIWtTO""'lNtcHDDIS£R (SUNOTEU)..

110* (ATOPSIG)

PRESS.-PSIA IX"*' PRESS.*PSIA "*' x x x xx xxxx,..1 E ~r~+l~~f~~~mr~r KlOE

TEMP.

  • F -'%' ~-l--+--+-~-~1'% -TEMP. *F 18¥ G HINIKJHf'LDWBYPASSMODE.

S SYSltMQH5TAHOIWDUTY

\\_SEE NOTE 22 \\_SEE NOTE 22 [LOOP C \\_LOOPS A S. B

MODE S MODE B POSITION Q JS11 Z/ 4 2e 2$8 I

FLOW-GPM t-----+.,=-X~~~":::.t-=.-:t-=--=i':=--:::,t-=-t-=-~f;=_~t_-:::,t.-=-~-=--::.,f;=_-:::,t-:::,t-:..~-=-~*~-Ot-7'-'!iQ-i=:---,t-14-50-t-o-c-:;f---i<-7f.()(.--?40<l,....-:>I ~~~ :*~1:3t~= t,~JEJ:~t~~~.: ~ THtS PRESS.-PSIA,._,xx x x'x xx xx xx xx 1S.s'XIYIX1135X,X 1-V>R_'E._ss_-1'6_1"'...J.'~%"1:iZI~ --l-..+--ll~'X!Lx~::.;,.i.x<:..x*-x~y~ *o:..:x* ~~'XIL,v~:x~rxq_1---1<:~l!;-'-r+--1l>'a;Z(.*1!J.. l--¥X~1Xq.,......,. *"" '"" _,_.,..,., "" """"....,.... " GOYCJlll.

TEMP. "F i-~-"-"-+---+-4-+--+=~-+--+--+-21_2_,a_2 ::=t=:t==l==t:=t=::t==1~=t:~+---+--+--+--+----l 2. WrS~FJL~,~~Tri~~r~ID~~r~~s.

MAX.PRESS.

nRoP-FEET ~~~.' *7DH-lZ"* -,;-- -~ ~... IJrrl)ICATOTHtCi\\T.llSNOTSlc.NIFICAJCT.

HEAT REMt>VAl PER HX 120.sx ID'° BTU/HRCIHX OPERATING) 5~U't~ %~w£ffe:+:ffove -$EE AIOT£7{TYP) :: ~~::~:::~=~ :::~.::¥/,~::~:.::*

MODE s <CONT.'Dl s. W~~~k~~Mrt ~~'vf'i.ru*,~~~ 1 ~

POSITION Q 54 55 !! s. ~Wf~~TtS MUIMJM IXJ AK> lotlNltuc !"/) vAt.utS tt1t 'TIL FLOW*GPM 1.-&.SHE:DLJICS INDICATtnowocc:SNOTPASSTtfl:UTl-£SEl'O(HTS.

PRESS. -PSIA XX X 'Xi'x x x x x x x x x x l..TlENP9WAY.U~CIN IJIOYE TK l\\N>MCUffl.t5fE.f.T.THE TEMP. "F - - - TMl.SVM..UC1'1.USTI£01 t£~

&.OtlTICH.l.HDTIC

t 0 ~G£WlTDlat:l!IOT~trPROV I DCD.S~il£SlztDT011..!MlOO

10. ~ =:l~Jf,l'~~Jg*lli SlltQ 11.StD ON fl.CM Stt.Mf CH

11.TA!!L.E.I lfCllc.tlt3VALVEr'OSITIOHSEUUtf6VAIUOJSM:)l)[SOP£N.TION.

~: f~ LINC LQS.S[S fRa4 POIHl'@TO l"lllf@sa: RU 3.

i<f.~Jj=~NC>OHMl:fTI~I:~~=*

1S.1iM.7iRf1.0W5AAtlHCiPM 1 51'£AMRCJlirl$AREIN:!,000L~.

15. HX W1Y IMIQ:I W'CfC 11 410 roPH S>EU. SID£ Fl.OW.

17.F'Cl'tLINE.$1ZlllCl~TJOHXEQEf.5 0

11. I~:='r: ~URJ~~~su.:rg~11*1w..

~oet= ~~~v:,r:; 1 ~wrJ:.r~~fn' uQJ10 CIJ'R7tU.

20. ~:~1:i~~~~~OT~~

21.~~~~~~~~~~TtE

22.MU:lfll.INl"ELllMISSIUSHJTOfft£AD*IOof'T 0 2!. Tl!E I()( STEAM INLET PRESSURE SHALL 11E GREATER TMAN 60 PSIA TO MINIMIZE THE POSSIBILITY OF

FLOW INDUCED YIBRATIOI!.

24.Tl£tEATREMOVAL.RATESHOVNISBASEDONTHEHEATAEMOVALCAPA81LIT't' OFTHEHEATEXCHANCERIHXl.ACTUALDPERATINGHEATREMOVALRATEHUSTBE

~mrfxAE!i~:!k:c~z~~vfiL~\\~1UEi:~~:~J'~,1~

MODED SE:E: Nor£,, RX PRE:M //0 Pa/G

1.RHJl'SUJ0.1"£1D--E1~1010 2.eflSTSTDIOESIGHSPCC-02-4010 s.ac1c.l"fl)----a1-102c X1M.1XX1z4.1IXIX 4 *.q[CIRCS't'STD4Pf1>----SD-!Q40

,.1.rc.srro----01-1020

--+--+--l--+--+-~-+--+---+--+--4--+12&q - 72

MOD££ OPS/If SOURCE: 0016310001004

NOTE : Mode dote on this sheet wos used for FIGURE 5.4-14 original pipe and component sizing. Design PR£SS*PS/A /4.7 X X X X.,)<'l,.X Xj)< XI X.]i'x X l*.7 XIX requirements ore based on Mode specific RESIDUAL HEAT REMOVAL SYSTEM PROCESS DIAGRAM AND DATA analysis. SHEET 2 OF 3

NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N. Y.

UPDATED SAFETY ANALYSIS REPORT

USAR REVISION 19 OCTOBER 2010

-SEE NOTE 20 POSITION Q DESIGN PRESS.

IN P I

£SIGN TEMP.

IN "F ES IMATED LINE SIZE

NOTE 25 NOTE 25 NOTE 25

TNlL<: I* VA.:.VF: FOSJrOI OIART

>itltlA-1 OC O n

10{)[8 G 0 0 ()id ~.lo>J ***

T o 1:1"1£ le D

DO()

Tl/BL£ 3 LIMIT/I.I(, LIAJE l/IS5cS 25. STEAM CONDENSING MODE OF <C-1,2,3, & 4l OF RHR HAS BEEN RETIRED.

inioe.R-1 /0*11 PUMP O/SOWIG£ U!J! TO FIPV FIDOb!Al6 ftJJE.rlArtOJ/ STEAM IS NO LONGER SUPPLIED TO RHR HEAT EXCHANGER.

IJomtA-Z I.JOME RHR HEAT EXCHANGER NO LONGER ACTS TO CONDENSE STEAM.

1-c*_1tt11_7-+--1 _____ JJo_J.J..:..'l _____ ---i SEE NOTE 25 llfl){( *' 19*3f*3SfSTEAUUJ/[HiJIJEtltil/IE TPllrllll<fliZ) SOURCE: 001631012Jl2J1012J4

llt<<c-4 JS*/7 (~TWILi/i[ I/WU 7Qflr) FIGURE 5.4-14

IHH~*29(V(S5EL l/CAD(.f SFllAYl.llJEJ M#l D lHH iSIJIJ!mMI 5/KuntJ!J tJll[ ~PY 7ol'WI')

'51. *4 (SllfJl!J()Jl,IJl51X/JllOllUll! TET8WJt'lllTJf!JJll'7. RESIDUAL HEAT REMOVAL SYSTEM

~/J(Jfl l&-27 (SlilJ]/JtJ'f/llDl5(/IAlatllJ{ lPL/8fJJJtJITOlltlltltU)

IJtJP! f ~(Nf.111'1-ff {T{ST UJJl Tll S/Jl'PHS5/0!J lrXXJ PROCESS DIAGRAM ANO DATA NOfUJ,. ts (PIJJ.JF 1.111/litllJl.I 8YPA:iS UNE') SHEET 3 OF 3

UPDATED NINE MILE POINT-UNIT 2 SAFETY ANALYSIS REPORT THIS DRAWING CREATED ELECTRONICALLY

USAR REVISION 1 9 OCTOBER 2010 1200 r---------------------------------------

1100 0 N 1000 ~ MINIMUM REQUIREMENTS 10 ::c

~

fl) ::c 5 II. 100 900 z NPSH-REOUIRED AT2 FT ABOVE PUMP MOUNTING FLANGE 800 0 90

700 80..

~ 70

  • c 0 600 e w s
c >-

~ 500 60 (,J z w

~ Q 400 a: 50 LA. LA.

w w

~

300 w 40 fl) a:

0

c 200 w 30
.£ a:

ID 100 BHP AT SPGR z 1.0 1000 20

0 500 10

0 1000 2000 3000 5000 6000 7000 8000 9000

GALLONS PER MINUTE FIGURE 5.4-15

Note: Pump cane r*presmts manufactur*r's l*sl curt1*. RHR PUMP CHARACTERISTIC CURVES Installed performance and minimum acc*ptable Technical Seecitication p~r(ormanc* is below this cane.

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 SOURCE: 73IE961AF UPDATED SAFETY ANALYSIS REPORT

USAR REVISION 13 OCTOBER 2000 B 0 H M

,-@ 5 i~

I !

t.

<IEEJED--------:

< \\:_~'~:~. j.... ____ J_ _ __,

i l

2-wcs..... 1-211-1.,..

I i

i

..... Fl ! 8

... o~

-IH w 1 a----:--------

~ --, r-----e ~

~!!:Ii m' ! rn 1 r*el--L----eBij q ___ ! j ! isg !..,.,,

! I I ITTFle/---ow El l!!.!!! : I : ru' ! ! [__~

j : ~MJn1 1rn.....,.1 j ! i 0-

~---~' '

10 I;.'.'.',-;.::.',, >------------J ~

FIGURE ">.4-l&o

REACTOR WATER CLEANUP SYSTEM

11 NINE MILE POINT 11 NUCLEAR STATION - UNIT 2 SCRIBA, N. Y.

UPOATED SAFETY ANALYSIS REPORT A B 0 E G H K USAR REVISION 23 OCTOBER 2016 _j D H N

.:ric1C1111Wlf11C:U_,""'.

W(.llllA!Dlfllttl

~-**** r--~----~ I

11111'/.. ll)I! J& ~:

SIMl!~--4>-~

.. ____ ~ l*~-Ml*l i l*Cl*i:r~I

, ** /,~ ! ~ \\4......

UH 1*..0*~-J

2

!EliDC>****-,

~---**1 c::mL=>-***j

~-****:

@8 i I i 8@

8: EJ! El i

~~.. I~* EJ rw~l._

r---&,m, EJ)!, *.. :~-~_::~::!

5 5

~ r'*~t*-~**_.. _,._. ________ _

1.... "" 2*WC'*~H-1

- K*

e

'I

10

IMllltC.c.LL m FIGURE 5.4-16b um l-f"W,*Ht~l*lta-1

REACTOR WATER CLEANUP SYSTEH

II SOURCE, PJD-378-26 NINE MILE POINT II TITLE. REACTOR WATER CLEANuP NUCLEAR STATION

  • UNIT SCRIBA, N. Y.

UPDATED SAFETY ANALYSIS REPORT

H USAR REVISION 2 3 OCTOBER 2018 _j A B c D E F G H I J K L M N

1 ~ 2-WCS-11104-17-3 1

\\ 2-WCS-006-486-3

1rn:1 I : IN017 I 1F0:21

~NOTE 3 *

  • IN006I L._._. -*-*-*-*-*-.I ~NOTE 3

-.... -,Ej3 5.4-16d !C-41 TE ------1 5.4-16b !G-31 >. ' >

137

2-WCS-008-13-3 \\ CCP SYSTEM

' 7 -

" :.. V160 - 9.2-Jo <L-BJ, 2-WCS-1111116-456-3 2 I 5.4-16b IJ-ql NOTE 4 - 2

SCJ, r V387 j ** --::JNNS '

T: ~ V388 "16 L!.JD ~f---.;._~~~---+~~

IN0!7 I
  • B L*-*-. -*-*-*-*-*-*I IF041 I 2-WCS-11104-18-3 V52 Y51 J V5~

3 2-WCS-750-416-3 3 NNS iSC3 I 2-WCS-11104-106-3 -TYPICAL AIR OPERATED (SEE TABLE BELOW Aftl> NOTE VALVE ARRANGE~NT 6>

-- -- -- IFl~I I

NOTE 3 2-WCS-006-4q2-3

-- @JTE3 : IN017 I

  • 0 sov A/S I

-- ---- E3 L ____. -*-*-*-*-*-.I ~~.... Ej3_ I I

. 5.4-l6e <E-91, I

. ' I VENT :

-- ~- I 2-WCS-01111-411-3 ~ NON-REGENERATIVE - _____ J I WCSTClllS y_ HEAT EXCHANGER 2-WCS-006-202-3 NNStSCJ ' ' 602322

~ ~54 ~5~ &---" TS i::::l \\. -----*---------*-* EJ ADV 4.----1-----<. 120 ~

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