Text

5 to Updated Final Safety Analysis Report, Chapter 5, Figures
	ML22292A089
Person / Time
Site:	Nine Mile Point
Issue date:	10/05/2022
From:	; Constellation Energy Generation
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML22292A107	List: ML22292A061; ML22292A062; ML22292A063; ML22292A064; ML22292A065; ML22292A066; ML22292A067; ML22292A068; ML22292A069; ML22292A070; ML22292A071; ML22292A072; ML22292A073; ML22292A074; ML22292A075; ML22292A076; ML22292A077; ML22292A078; ML22292A079; ML22292A080; ML22292A081; ML22292A082; ML22292A083; ML22292A084; ML22292A085; ML22292A086; ML22292A087; ML22292A088; ML22292A089; ML22292A090; ML22292A091; ML22292A092; ML22292A093; ML22292A094; ML22292A095; ML22292A096; ML22292A097; ML22292A098; ML22292A099; ML22292A100; ML22292A101; ML22292A102; ML22292A103; ML22292A104; ML22292A105; ML22292A106; ML22292A108; ML22292A109; ML22292A110; ML22292A111; ... further results
References
	NMP2L2821
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{{#Wiki_filter:STEAM DRYERS STEAM SEPERATORS DRIVING FLOW __

1. CORE INLET 2.CORE OUTLET

3. SEPARATOR OUTLET <STEAM OOMEl

4. STEAM LINE <2ND ISOLATION VALVEl

5. FEEDWATER INLET <INCLUDES RWCU RETURN FLOW) 6.RECIRCULATING PUMP SUCTION

7. RECIRCULATING PUMP DISCHARGE

~CHANNEL BYPASS-NOMINALLY 10% (Ref. ORF LI5-00719, Supp. ll <GE Letter NMP2-CJ4-051, 10/ll/94l SOURCE: DRF L15-00719 SUPP. 1 THIS OOA\\tlli'JIG CREATED ELECTRONICALLY JET PUMP PRESSURE FLOW TEMPERATURE ENTHALPY (ps1el <lb/hr) <"Fl <Btu/lbl 1071 108.5 x !12J6* 535 529.2 1047 108.5 x !12J6 550 636.2 1035 15.0 x 112J6 549 1191.0 1003 15.0 x 106 545 1191.0 1060 15.3 x 106 425.3 403.4 1037 32.84 x 112J6 534 521M 1325 32.5 x 106 535 530.3 FIGURE 5.1-lo RATED OPERATING CONDITIONS OF THE BOILING WATER REACTOR NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995

STEAM DRYERS ~ STEAM SEPERATORS DRIVING FLOW MAIN FEED 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 Dome) 1,035(a) 17.6(a) 549(c) 1,190.6(f)

4. Steam Line (2nd MSIV) 1,009(f) 17.6(a) 546(h) 1,190.6(f)

5. FW Inlet (includes RWCU flow) 1,069(i) 17.94(g) 440(g) 420.0(g)

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 WATER REACTOR NINE MILE POINT - UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 20 OCTOBER 2012

STEAM DRYERS STEAM SEPAAATORS A. LOWER PLEll<UM B COAE c UPPEFI PLEll<UM ANO SEP.. AATQRS

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I CA*J 1 2RSS 1 LEVEL I LOGIC I ii~ ~~E 19-------------- ~A-D_SIAl_._~_P_c_~_* -~ LEVEL B LOGIC RCIC [B_2_2_J ~ DIGITAL FEEDWATER ~ _______ -,- - _: __ ~ ~~~LA112 I I ~ ~ ~~-i22EI ~----~

~

LEVEL 2 LOGIC RCIC TITLE* NUCLEAR BOILER AND PROCESS INSTRUMENTATION A B c D E 2*1SC*750-217-21A*l 2*1SC*7!11*211*2<B*l -+--, \\ 2ee 0 \\ Nl2 }--I- -f---{Nl2 I F G H '*RO" 2311 1
HOSE2q VALVE CLOSED
@:CR I '- <B-J _, J ' _....;;;... i'H!*"P.,.0 ':v101e->
E:Fvta 3/4"FLEX HOSE ITYP OF 61 IB->
..l ** iii \\... ;::: I ~Y> -@_Yl ~ T ~ I I I I I I L LEVEL 1 LOGIC S AOSIB~ RIRB~ a-----------J"-
~~~~i- ~--R_HR<~c*--~
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~~.fiel ~ ~6~1 .------~ ~----~ LEVEL B LOGIC RCIC ________ J
________. LEYELRllcLOGIC J
K FIGURE 5.1-Zb NUCLEAR BOILER AND PROCESS INSTRUMENTATION NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N. Y.
o w
c-o z UPDATED SAFETY ANALYSIS REPORT 8 g 10 11 USAR REVISION 25 OCTOBER 2022 _j
1 2 3 4 5 7 8 9 10 11 A r ~ E9 B TO LOW PRESS CONN'S LOOP *o* JET PUMPS INSTRUMENT LOOPS FOR 2MSS*PI OND 2MSS*Pl0 SHOWN, 2MSS*P2,3,4,6, 7,8 AND 9 SIMILAR TO 2MSS*PI. NOTE 3 F *LT I " DIGITAL c VALVE CLOSED D I ORC -IRC E F N9 105 ° / G 285° H I LDSTC74 2MSS- ~ 601559

~_J

____ ~ \\!~l'!!IT 'CJ I IRC -ORC r**----. *-. *-* *-**-**-. *-....1 NOTE 6 (TYPl VALVE CLOSED J TO LOW PRESS CONN'S IN91 LOOP "B" JET PUMPS. INSTRUMENT LOOPS FOR 2MSS*Pll AND 2MSS*P2B SHOWN.2MSS*Pt2.13.14. 16,17,18, OND 19 SIMILAR TO 2MSS*Pll. NOTE 3 K I 130 r-- FEEDWATER ~AG>.J I rz:.)
RO
/r+-+-2-ISC-750-318-21A-> "*RO' ~ 25J 25K ) \\l_ .,!A-I, 2-ISC-750-311-21B-l-t-h. .,!B-I J./
HOSE37 T
T
HOSE33
~ DIGITAL FEEDWATER I
LT

L--* 13B

) IBYI r FT r---- 47J '-(A-) I )~-;~'fflliw+o[):::("*~~~~J1::::'.:=D-1~~~~~~~~~~~"-~+-i ~r-~"~~~~~~~~~~~~J1::::'.:=])-1~~~-{*p~*f-ffl';w.Jrl'~( I r I 1
EFVIBIA-l 2-ISC-750-368-21A-l -
.rFT " -E91 4BA 1----- <A-> .J
V181A-I

VlllB-1

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NSSFAl01 TOTAL FLOW i ~ 3 ~ 2-ISC-750-361-21B-l 'FT ' -E91 488 1----- ,<B-I,, i ~ CSLPC07 ~
~
~ SCRAM LOGIC 603401 RPS ~---,-~ PAH B2 Q ISCUCl2 1 ~ I i- - - -,- - -- - - -- l ~ C72-6500 ~ /*PT' -15ii-. UI ' g £ ' -.n '\\.CAB>,, ~ 7 HIGH PRESS LOGIC 1 LPCS. AHR<A>,RCJC 1 & VAL BRKR ISOL '.--------J r----~ I 6fll34fa2 I i !~22-1 i----i;::::::::T--~ 694E ~ ~22-1 I 6q4A I ~ ~
PT "
/*PT CSLPC08 1----~ -t7li-* -11c- <1!!1G>.1 '-<AG> ~ 1::W
EFV191A-I

HOSE3B LOOP INACTIVE FROM REC I RC PUMP 'A' RUNNING

-------..J ' '
r---------------~--------------~------------ RCSFC101 LOOP A ti~~ _ J_ ___ t-___ J 2MSS*REV1CZ-I LOOP B RCSFC102 Fl ,6_ L ___ t-___ _l_ _ LOOP INACTIVE FROM RECIRC PUMP 'B' RUNNING ISCBC07 ISCBC08 ~ HIGH PRESS LOGIC ~ L _ RHRIBJtCJ, RCIC _ J 1 ANO VAC BREAKER 1 ISOLATION L ______ @_ ___ "' __ : ' V'" ' ~ 601602 ~ I ~22-I 6q4F I ~ r,.,py '*PT" B -17ii-J , -17ii-) -.[BYI '(!IY I, GJ:1
HOSE34

EFVl21B-I SCRAM LOGIC Bl RPS 2-ISC-75B-36q-2(A-l -
- \\l_ '---~~~~-'---~~~~-'---~~~..,.; _l/ r-2-ISC-7511J-362-2lB-J "I I ~-----'---------'----------' ~ VALVE CLOSED
Vl91A-I 1

vi2c8-1
~ VALVE CLOSED v FT I 47K IB-1 )---, 1--, ~ 603401 1------'

4 1-----4 l----------------------L----------------------

>---@---~--~! ______________________ J _____________________ _ <-----------4 /FT " -47_A_ t-- <A-l FT <-----------4 ITYP OF 81 SEE CHART I ID-101 i -48c- }------, IA-> I I JET PUMP r--r--- 2MSS*Pl0 ~ ~ ],_ )!'..(,IQ..( b._ L r--r--- 1- © b._ L 2-ISC-75111-381-2(A-) MSSTC07 lii?2q"l 602235 ~ ~ @----J----@-: ~-e------4 ~w 1-------------------c e-9--] 2-ISC-750-340-21B-I -+-+-> .-++-2-ISC-750-331-21A-> 2-ISC-750-363-218-1 6~6~~01 L ~ ~~ 7
RO HIGH PRESSURE CONN 25R FOR CALIBR FLOW HIGH PRESSURE CONN r *RO
~ FOR CALIBR FLOW 25S ) V L---------; 1------1 1------1 1-- JET PUMP 2MSS*P l 2 3 4 5 6 7 8 q 10 1 Iii 5 11 12 13 14 15 16 17 18 l'l 20 15 20 SOURCE: PID-28C-12 < 11.B.3-lo IA-51 TO POST ACCIDENT SAMPING SYS ~ 1----- FC \\_
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Vl931A-I
'*sov 119 <AG> ~A-J,1 TRANSMITTER OF
EFV311A-I

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~ VALVE CLOSED TRANSMITTER OF ~B-l
EFV401B-I JET PUMP
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I ~ VALVE CLOSED
Vl941B-l
/*SOV 120 IBYI 1----- /'Fe TO POST ACCIDENT SAMPING SYS II.B.3-le tA-6> I 2-ISC-750-373-21A-I 2-ISC-750-324-21B-> -+--+-. .-++- 2-ISC-750-323-21A-I 2-ISC-750-374-21B-> ~ HIGH PRESSURE CONN r *RO 1l12 ) ~ § CL2-*NNS 2-ISC-500-401-2 ~ l 8 GD HIGH PRESSURE CONN C FOR CALIBR FLOW I TRANSMITTER OF
EFV231A->

HOS T
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'--~~~~~~ 1 ~~~~~~~~~~~~~~~~--L-~----E$~ 1 ~ T" I I
V231A-I I
TO HIGH PRESS CORE SPRAY SYSTEM l2CSH*P011091 6.3-S. IF* 31 TO CONTROL ROO DRIVE SYSTEM 12RDS-PDTll4,ll 71 4.6-5b IJ-51 TO REACTOR WATER CLEAN-UP SYSTEM 12WCS-FTl341 < 5.4-16" 11-8> NSSPAl01 ~---~---i f1~!- v IZ-1 ~ ~ ~ VALVE CLOSED 2-ISC-750-371-21A-I
EFV211A-I
~ VALVE CLOSED ~)
HOSE4111 \\l_
Ir-. I
V211A-I 2-ISC-750-372-21B->

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...!A-J..I T I I I r;\\3.!_3 I *Ro '
EFV221B-I 2-ISC-750-321-2107
( ' 7 FOR CALIBR FLOW 24D ) ~ TRANSMITTER OF .,!B-1 1 "--2-ISC-500-402-2 JET PUMP T _/
HOSE43

EFV241B-I
'f 2MSS*P20 ~....i..~~..;;.;;;,;.;.;;,;._~~-<I1::::'.::J1~..;;;.-~*(MTM*w-1""--<"'""~.--~---'~~~~~~~~~~~~~~~---' r I r ~* I ~ / /*RO 112 ) IA-l I
V241B-I
© VALVE CLOSED 2-ISC-750-364-2CA-J -z 15.1-2e IA-61 ~I ~ _,,_/
HOSE36 EF:'._14IA-I REMAINING 21SC-FT47'S 2-ISC-750-314-21A-I -~\\
~~~~~~~~~~~~.... ~~~~~~~~~~~ ' ~---.------'--------;: RECIRC LOOP A 1 NOTE 4 & 5 REMAINING 21SC-FT47'S RECIRC LOOP B NOTES 4 & 5 ~Bq-3) 20B 2-ISC-750-322-2<BB7> -\\l_ "B-J..I
HOSE41 T
._j__~~~~r--~~~*~*~-cLD-~~--'----JL.....,.:::-~ I I I i -- '*V22(8-J I '- 2-ISC-15111-400-JCZ-J ~ VALVE CLOSED i ~ i VALVE i CLOSED I CHART I I CALIBRATED JET PUMP INSTRUMENT NON-CALIBRATED JET PUMP INSTRUMENT LINE NUMBER LINE NUMBER EXCESS FLOW CONTAINMENT LOOP INSIDE CONTAINMENT OUTSIDE CONTAINMENT PENETRATION
HOSE ORIFICE RUN CHECK VALVE ISOLATION 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 CHART 111 I 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 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 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 JET JET 2CEC-PNL61'l IND SUMMER COMPUTER PUMP PUMP FLOW INPUT 2MSS*P TRANSMITTER GE !DENT NO, GE !DENT NO, 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 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 37
R025JIA-l

EFV18<A-I

Vl81A-l 0
0 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 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 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 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 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->
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 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 u
- u 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 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 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 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 B
21SC-FT48818-I 822-N033B 21SC-FT47KIB-I B22-N034K 2-ISC-750-311-218-l 2-ISC-750-361-218-l 1308-7 33
R025Kl8-I

EFV1118-I

V11<8-l 0
0 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 1
FT47A B22-R608 B22-K601A NSSFA102 2 FT47C B22-R608 B22-K601A NSSFA103 3 FT47E B22-R608 B22-K601A NSSFA104 4 FT47G B22-R608 822-K601A NSSFA105 5 FT47J B22-R608 B22-K601C NSSFA106 6 FT47L B22-R608 B22-K601C NSSFA107 7 FT47N B22-R608 B22-K601C NSSFA108 8 FT47R B22-R608 B22-K601C NSSFA10'l q FT47T B22-R608 B22-K607A NSSFA110 10 FT47V B22-R608 B22-K607A NSSFAlll 11 FT47B B22-R608 B22-K601B NSSFA112 12 FT470 B22-R608 B22-K601B NSSFA113 13 FT47F B22-R608 B22-K601B NSSFA114 14 FT47H B22-R608 B22-K6018 NSSFA115 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 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 B
21SC-FT47UIB-l B22-N034U 2-ISC-750-341-218-l 2-ISC-750-3'll-21B-l 1308-'l 60
RD25Ul8-l

EFV4118-l

V411B-l B
21SC-FT48Dl8-l B22-N033D 21SC-FT 4 7WIB-l B22-N034W ?-1cr_ 7<<a-:.4?-?(R-) ?- rcr-7r:.~-'la?-?(R-) 1308-8 61
RD25WIB-l

EFV4218-l

V421B-l 17 FT47P B22-R608 B22-K6010 NSSFA118 18 FT475 B22-R608 B22-K6010 NSSFAll'l 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 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 u
= u l'l FT47U B22-R608 B22-K607B NSSFA120 20 FT47W B22-R608 B22-K607B NSSFA121 TITLE:NUCLEAR BOILER AND PROCESS INSTRUMENTATION A B c D E F G H I J K M ISOLATION VALVE EFV INSTRUMENT TUBING N 3/4'FLEX HOSE ITYP OF 81 SEE CHART I ID-101 USAR NOTES: VA VB SC2 +NNS NOTE: DETAIL I TYPICAL TEST VALVE ARRANGEMENT 21SC*V81.83.B4.& 86 SHALL BE ORIENTATED WITH THEIR DIRECTION OF FLOW ARROWS OPPOSITE TO THAT SHOWN IN DETAIL 1
CHART II I EXCESS FLOW TEST VALVE NUMBERS CHECK VALVE NUMBER VA VB

EFVlllB-l

V1071B-l

V10'l!B-l

EFV181A-l

V1061A-l

V1081A-l

EFV251A-l

V'l01A-l

V'l21A-l

EFV26<A-I

V'l4!A-l

V'l61A-l

EFV271A-l

V'l81A-l

V100!A-l

EFV281A-l

V1021A-l

Vl041A-l

EFV2'l!A-l

Vlll'JtA-l

V1121A-l

EFV301A-l

V114tA-l

V1161A-l

EFVJl(A-1

V1181A-l

V1201A-l

EFV321A-1

Vl221A-l

Vl241A-l

EFV331A-l

Vl261A-l

Vl281A-l

EFV34!8-l

V'll!B-1

V'l31B-l

EFV35!8-l

V'l5!B-l

V'l71B-l

EFV36!8-l

V'l'l!B-l

V1011B-l

EFV3718-I

Vll9t8-l

Vl21t8-l

EFV3818-I

VllltB-l

Vll318->

EFV3'l!B-I

V115t8-l

V117t8-l

EFV401B-l

V831B-l

V811B-l

EFV4!1B-l

V1231B-l

V1251B-l

EFV421B-l

V1271B-l

V1291B-l

EFV121B-l

V751B-l

V771B-I

EFVl'l!A-l

V741A-l

V76!A-l

EFV201A-l

V801A-l

V821A-I

EFV231A-I

V861A-l

V841A-l

EFV131B-I

V103tB->

V10518-I

EFV241B-l

V851B-l

V871B-l

EFV141A-l

V1341A-l

V1361A-I

EFV211A-l

V1301A-l

V1321A-l

EFV2218-l

V1311B-l

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I.ALL INSTRUMENT & EQUIPMENT NUMBERS TO BE PREFIXED WITH '21SC-' EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN.
2. GENERAL ELECTRIC IDENTIFICATION NUMBERS ARE SHOWN IN SOUARES.

3. CONTAINMENT ISOLATION DATA !FOR LOW PRESSURE CONNECTION!
FOR JET PUMP INSTRUMENTATION OF NOZZLE N-9 ARE LISTED ON CHART hlSOLATION ARRANGEMENT SHOWN FOR FT47JIA-I IS TYPICAL. 4.HIGH PRESSURE CONNECTION FOR ALL NONCALIBRATEO FLOW TRANSMITTERS 21SC-FT47'S WILL BE FROM LINE NO. 21SC-750-372-21B-> FOR RECIRC LOOP "B" AND 215C-750-364-21A-> FOR RECIRC LOOP 'A'.
5. FOR S&W AND GE DESIGNATIONS SEE CHART I.

6. SEE DETAIL I FOR TYPICAL TEST VALVE ARRANGEMENT FOR EXCESS FLOW CHECK VALVES.EFV ANO CORRESPONDING TEST VALVE NUMBERS ARE LISTED IN CHART II.

7. SEE CHART III FOR INPUTS TO SUMMERS.
FIGURE 5,l-2c NUCLEAR BOILER AND PROCESS INSTRUMENTATION NINE MILE POINT NUCLEAR STATION UNIT 2 SCRIBA, N. Y. w 0 z UPDATED SAFETY ANALYSIS REPORT REVISION 25 OCTOBER 2022 1 2 3 4 5 6 7 8 9 10 11 _J
0 <[ a: LL 0 ... z u a: e, 1 NEUTRON FLUX 2 AVE SURFACE HEAT FLUX 3 CORE INLET FLOW 150.0L--...J-~~~--..,.---------"'"1 100.0 50.0 0.00.0 5.0 TIME (SECONDS> 1 LEVEL ClNCH-REF-SEP-SKRTl 2 VESSEL STEAMFLOW 3 TURBINE STEAMFLOW 4 FEEDWATER FLOW 200.0 100.0 0.0 2 -100.0L--------~5 ~0 --------~10.0 0.0 TIME (SECONDS>
Bosed on o representot1ve equ1brium fuel cycle.
NOTE: For c~le-apec1f1c re~lta see ~ix A, $1wt1on A.S.2.2.2.3 SOURCE: NEDC-31994P I THIS DRAWING CREATED Ei.ECTRONICALL y 0 "'... z z 0 Q.
c 0 u E
u <[ ~ 1 VESSEL PRESS RISE CPS!l 2 SAFETY VALVE FLOW 3 RELIEF VALVE FLOW 4 BYPASS VALVE FLOW 300.0l-_______ .::....:;:.;.:..:;:,;;:;;:...:.:;-.;.,:;;..:...-.;;.._ __ -t 200.0 100.lll 2 0.00.0 10.0 TIME (SECONDS> 1.0 0.lll 4 -1.0 -2.0L-----_;u...-~---------;: 111.0 TIME <SECONDS> FIGURE SAFETY RELIEF VALVE CAPACITY SIZING TRANSIENT "MSIV CLOSURE WITH HIGH FLUX TRIP" MOHAWK POWER CORPORATION NIAGARA NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995
MAIN STEAM FLOW RESTRICTOR SUPPRESSION POOL -~--~'-- FIGURE 5.2-2
SAFETY RELIEF VALVE SCHEMATIC ELEVATION
, NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
S/RV S/RV MAIN STEAM ISOLATION VALVES REACTOR VESSEL I. FIGURE 5.2-3 DRYWELL S/RV SAFETY RELIEF VALVE AND STEAM LINE SCHEMATIC NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
2 3 TAB.Et SAFETYAIELIEF VI.Lii[ surrix ASSIGNMENT Al'll ASSOCIATED EOLA.tENT SAFtTTnELD' 4 5 6 7 FO\\H rou-1 ro1l-$ rou-2 rou-2 rau-3 tOU*l rou-~ rou-2 ro13-4 rou-* rou-* rou-~ rou.. 3 O£ca r0l6 VALVE FC..OtMW 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 LOOP IPllO. rtNOl4 (~-~~ .,.-"600 A C l -i:--~lo--...... -+-__ ~i:--~--<>---+---+--+-
607A I
t<6078 I ~ 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 .lAll.E Vt EUllAlllN CORRELAlllN CHART 1'1IP ar IUD '>-1-~"'-'---l fUllC[ J S1[Mll U )>-+--'-"'----! MIZZlCIO J llilll.l<<NI l.KIOZlll- >-+----1 } {~~~E*c tlGHLC¥ll.ALMlf-NJRliW.WA1CRLf'<<l .f.:"rtr.'t::t,~.--
llKllllfj 511 nl-1Cll '°"1llQI. iTl'llll-DQC 31.
SiM.OOC.667
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2. FECOWA1CR CONTRO. SYS1CM IEO-----------------C.1JrllD
). NUCLEAR BOIL[R STST(M ftP-----------------822-tolO
4. ELCC [QP1 SEP SAfCCUARO STS----------------AH-4DM

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6. RtOUNOANT au.Cltvtl'Y COHtROL $YS1CM DCS. SPlC ----C22-4090

1. R!Dt.ltOANl ltC.ACltvtl'r CONTROi. $1'S1UI ELEM w _____ c21-~
FIGURE 5.2-4 GIVISIOHOR<<NUT.. fORVCSSCL..STRUMCNTATDf ISCCSUPPLOOCtl FIGURE II SOURCE: 761E445AF - 07 NUCLEAR BOILER SYSTEM P&ID SHEET 1OF2 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 !UPDATED SAFETY ANALYSIS REPORT USAR REVISION 13 OCTOBER 2000
2 3 ~* ) 1 2 3 5 MECH CLCC OIY OIY lQC 6 U:VCL lRIP POINT t-l-S_N~-o--84-o-! -+-N.,,...SI ___ -= : J LIS N6!UB,r AOSIBI / RHRl81 / RhR ICI 2 lSNH2B,( NS**NUCLU.RSTCAMSuPPLYSHUJOrrSYSltM AUi
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71
-+--1--+----1------~ PTN403C RRCSISUPPLDOC.6.tc11 PtN40lF' RRCSISUPPLDOC. 6*71 2 . PISN67$8 Pl ~nae l PIS NG7~C 1-----+----<-,-+-plS N67~0 l PISN618"'- POST ACCIDENT lritONITORINGIRHRIAll POStACCll)£Nl MONITORtHC. IRHR 1811 I r-;- ~ ... ----+--:NS-41A-l,...,,IRHR-:-'.:"ISOl:-I----! 2 PIS N6 l8B~-~7ff5-,--*- f----+--2-+-:-l--:-::-~-:--+-~-------I 1-----1---:-1--:-
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5 10 I 11 12 13 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:° USAR REVISION 3 OCTOBER 1991
PNEUMATIC ACTUATOR 0 PISTON LINER BODY SPINDLE PACKING GLAND INLET 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
1 w a: ~ <t a: w w I-171°C (340°F) 160°C (320°Fl SUPER HEATED STEAM WITH I --1 PRESSURE AT 3.1 BARS DIFF SATURATED STEAM ENVIRONMENT (45 PSIG) (.!)
i:z u-
<t Cl) w u w:::l I-0 a:W I-u
i...J z
0 OU w ~
i: ti iii 1--

<u
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i z

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i
--> ~~ u w a:~ ct. ...J ~
loo U(I) u u
o-- (.!) u z u 0 u> 0 u. > 00 <OM o- -(.!) <.!lz u z-8 -Cl) 0 Cl)::>
>Cl)
WW ~ ~ ...J...J uo (.!) (.!) z z uu Cii Cii Cii -N ~ w ...J u >-u I w w ...J ...J u u u
u TEMPERATURE WILL RISE FROM AMBIENT TEMP TO I 111°c (340°F) IN 5 MINUTES REMARK: THE MENTIONED TEMPERATURES ARE MIN TEMPERATURES TIME-___,~
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
RECIRCULATION PUMP CLEANUP PUMP STEAM 0h __ _::...l-, r-ROD 0 DR'"' REACTOR WATER CL,EANUP ~ I PRESSURE TURBINE FEEDWATER TO CONTROL ROD DRIVES 8 GENERATOR FIGURE 5.2-~ COOLING WATER TYPICAL BWR FLOW DIAGRAM NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
s 0.,, 5 I&. 0.... cC
E (J
0 ::c
E a
~ ui (J z cC.... (J Q z 0 (J (J ii: u w D. I/) 10 1.0 0.1 HYDROCHLORIC ACID (HCI) CHLORIDE (ppm) 0.03 0.01 E
c.
_g. UJ Cl a: 0 ..J I (.) SODIUM CHLORIDE (NaCl) --soDIUM HYDROXIDE (Na OH) 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
E
a.
.!!) LU 1- <I: ex: ~ <I: LU ...J 1000.-------------------------------, 800 600 400 200 100 80 60 40 20 15 10 8 6 4 2 4 in. LINE
20 ksi 30 ksi

AXIALLY ORIENTED CRACK

SATURATED WATER SYSTEM AT 1000 psig

ASTERISKS DENOTE CRACK OPENING OF 0.1 in.
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
Ln 0 - x ef - 12 11 10 9 8 7 6 5 4 3 DATA CORRELATION Le= CRITICAL CRACK LENGTH (in.) D =MEAN PIPE DIAMETER ah = Pl PE HOOP STA ESS MATERIAL* A1064 0 0 Do O o~ Q GE DATA (-60°F) 0 BMI DATA Lc/D = 15,000/crh 9 10 12 15 20 25 30 40 50 60 70 M I 0 x ~ c 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
j 1 3.41 MAX. 2 3 4 5 6 7 (J]

IS.38 Mlf.J --------t-----+-l.51i> MAX 2 PLACES B

I l]J2~iN 1.0~ I ~1 f--------------~~---DM~---------------1 ~IM'iA\\------'lr---fMIN--~~ LLLL>-------------\\,._:~~~~~~--~--~--:=---_-:...j~j~' 0 © APPROX. WT=6 UIS 2 3 4 5 6 7 B 9 10 g 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 0 ~:~:E~~:rl APPROX. WT' 5 lBS' =~~~*3 Al'l'ROll. WT
5La5.
FIGURE 5.3-1 BRACKET FOR HOLDING SURVEILLANCE CAPSULE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT 11 12 13
Nine Mile Point Unit 2 USAR USAR Revision 21 October 2014 FIGURE 5.3-2a HAS BEEN DELETED Now controlled per Pressure Temperature Limits Report (PTLR) PTLR-2, Revision 0
Nine Mile Point Unit 2 USAR USAR Revision 21 October 2014 FIGURE 5.3-2b HAS BEEN DELETED Now controlled per Pressure Temperature Limits Report (PTLR) PTLR-2, Revision 0
Nine Mile Point Unit 2 USAR USAR Revision 21 October 2014 FIGURE 5.3-2c HAS BEEN DELETED Now controlled per Pressure Temperature Limits Report (PTLR) PTLR-2, Revision 0
Nine Mile Point Unit 2 USAR USAR Revision 21 October 2014 FIGURE 5.3-2d HAS BEEN DELETED Now controlled per Pressure Temperature Limits Report (PTLR) PTLR-2, Revision 0
Nine Mile Point Unit 2 USAR USAR Revision 21 October 2014 FIGURE 5.3-2e HAS BEEN DELETED Now controlled per Pressure Temperature Limits Report (PTLR) PTLR-2, Revision 0
ii: - PRESSURE VESSEL EMBRITTLEMENT TREND 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 DRYER ASSEMBLY LIFTING LUGS STEAM DRYER ASSEMBLY ---- STEAM OUTLET NOZZLE SHROUD HEAD LIFTING LUGS FEEOWATER SPARGER SHROUD HEAD CORE SPRAv------t SUPPL Y HEADER SHROUD HEAD HOLD DOWN BOLTS CORE SPRAY SPARGER IN CORE FLUX MONITOR ASSEMBLY RECIRCULATING WATER INLET NOZZLE JET PUMP ASSEMBLY DIFFUSER SEAL RING AND SHROUD SUPPORT PLATE CONTROL ROD DRIVE HOUSING TOP HEAO COOLING SPRAY NOZZLE STEAM DRYER AND SHROUD HEAD ALIGNMENT AND GUIDE BARS STEAM SEPARATOR AND STANDPIPE ASSEMBLY FEEDWATER INLET NOZZLE TOP FUEL GUIDE FUEL ASSEMBLY CONTROL ROD FUEL SUPPORT PIECE 1.1------- FLOW INLET INTO FUEL BUNDLE CORE SHROUD CORE PLATE ASSEMBLY ~~f------- VELOCITY LIMITER FIGURE 5.3-4 RECIRCULATING WATER OUTLET NOZZLE CONTROL ROD GUIDE TUBE REACTOR VESSEL NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
HIGH WATER LEVEL \\ ALARM, L7
568.0
\\_ NORMAL WATER LEVEL= 563.55 LOW WATER LEVEL ALARM, L4 = 559.0 TOP OF ACTIVE FUEL ---- ZONE= 366.31 FIGURE 5.3-5 HIGH WATER LEVEL TRIP, L8 = 583.0 in. LOW WATER LEVEL SCRAM, L3 = 540.0 in. LOW WATER LEVEL, L2 = 489.5 in. LOW WATER LEVEL, L 1,;, 398.5 in. 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.
PLAN VIEW SELECTIJI SWITCH 'RESTRICTED MlllE" IN "IORM" PDSITIDN JSAR FIG 5-4.dgn 6/6!2016 7.20:35 AM o* PLAN VIEW II SELECTOR SWITCH 'flESTRICTED MODE" IN "CASK" POSITION SOURCE:0002410044006 FIGURE 5-4 CRANE RETRICTED AREA SHEET 1 OF 2 NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2Bl6 _J
CRANE OPERATION DATA BOTH THE CAB CONTRtl. CINiULE AND TH£ RADIO "BELLY aor HAVE A ICEY OPERATED 5n.ECTI>>t SWITCH UIBELED 'RESTRICTED HQ(E". THIS SVITOI tM5 Ttff:E POS(TJQHS LABELEOt II "tCJRH" - THIS POSITION 1S TtE ONLY PDSITJDN IN WHIOI THE ICEY MAY BE REMOVEQ 2J"CASIC" 3l"BYPASS" l SEL.ECJOR S\\tlTDt "RESlRIClEll HaF lH 'tG\\K' P051llft &RIDGE NCD TROLLEY TRAYEl. WJLL BE AS FCl.LDWS.tSEE PLAM VIEV 1U Bo-td9* T,...... RHV1otaon With \\hm Vall-.. *1. *tV.- mnd af bradgia...1d *Ith '"-limy prG***&\\y ***tch '" v.. tl'lpp.d ~1\\.1Dn19"'a1 br-1d,* MOtaon from *IV-d1,.*ataon ooh1ah "°"'ld pom1taon hook* er-..,. r-**tnct.md -... **II V1p V.. brufg. pr-o*1*1~ ***tah std 1n c:onpmtaan *nh V. W1dg* **at.ah. de-_,,.1.r* .u er.,. !90\\.IGn! s1d..,. brM... n.. br1dg! ** u OOIM '° ,...,, *Ith the D9"\\ar-h,,. *( hook* at. ~ ..,,,. af
a1raul.,....,...,u.1 !9C:'ta.., "-'-**11r.d by th. o... wr Gr
,.,ae1.0r *iauon u 11V-Inner" CDr'f\\er or V.. pool.,._._ All:JITJ[J'CAl.1.T+ Tt£ BRUX;E TRAVEL LIMIT SVITCH STATUS LIG-tT Wlll CDNTJP&JOUSL T FL"5H. Tr-oll!u T,.,_J Re1tr1cuon Vi\\h **Vt*r- *nd of Vt* brtdg* pcn1\\.lon!d a....- Vie 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* a-1hll.--v1awd _.,.,. *111 "'P W vall*w pr-a*1,.1\\t,I
\\di _,.. In DOnJwlO\\.l.., *1th tNi bridge... \\oho

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--a~Clf'\\'9..od.. t. brel'I-n.. "'a111y *all -
i.,...,, **th *1V-V.. c.n\\.!r hne
3 t-k 1-anJ or-V.. ctni.- hr. *1 hoak 1-....J ld!p*ndlt\\9...,an.h1ah..,d or "'* br1dg* ** pa*au-d 0- 1J'MI r!Hrlc\\!d -!I on th* I,._ -
hr. a( ! -9"""'1t.al *mi::~an d!t!nN,,.d.,,,. u... 11nn1-d1*W-.O* r.-- tha. _,w,. ar....,'°'" *Mlt.IAl"I tQ th.,..... t... or "- *tar'ap pool a-1e.ADIJJTIOHALLY. Tt£ IRIOOE TRAVEL LIMIT SlillTCH STATUS LIGHT WILL 11.LlJitlNATE. TO RESTORE THE CRNCE DPERATlCIH MCI RESl.K MOTi'" WITH THE SELECTOR SWtTOt '11ESTRICJED MCIE" JN Tt£ 'tCltM" POSIT!~ MOVE n£ TRO..L£'f AWAT FAQH Tt£ RES1RICT£D ZONE USING ffit£R 11UOOE OR TROLLEY l'CTICIN. NOTE THAT Mier.£ TRAVEL LIMIT STATUS LICHT VILL FLASH FOR 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. 11 SELECTat SWITCH "RESTRJCED MtXlE" IN "CASK' POSITUJJU BRIDGE AND TROLLEY TRAVEL WILL BE AS F(l..LOV5' ($[£ PL.AN VIEW Jiil. NOTE THAT AUX *1 AHO AUX *2 HOIST WILL BE INDl'EAABLE IN TtE CASK AREA. 9r1ds! Tro.*I RHtrlc\\lon "*th \\h* troll9\\,t 01. *1V-.,.... af br1dgll m-.d w1\\h irollq pf"'l;l*lllll'tl **ltlJ>I In,,..pt>9d pHlt.IDnf ~ brldgii -t.lan 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 10\\h v.. volley ***'Wlh. *-*..-,.1** operllbl* --
-t.aan mnd -'L tw..i.... lt*..... *Ill - ta,...., *l\\h UI* o9ft"9r hne of *3 1M1n hook et. eds!* of a cu.. o.ot... -~i.J..ct.Ian d*'-""""twd by th. aisntar af r*eo'-
1.ot&on 1.a a1v..r,,,,_ OOo"f'Wtr of V.. paol -**
HoGk has eccna ta Via CAM. lo*hng pool.,.... L1n11 i.1or. or \\h11 or-.o *all ta. d9\\el"1tl1rN1d bw a line fron "'- o.nt.- af __..,.. awu.. ta..._,,._ *-- of' the _. 1~1"'111 pool fpoinl. AJ,.'Id bw.., - tu-.......... nec1 boj \\he d1a\\.M!Ca from v,. 1:;itn'IM" or.... "°" s\\a\\lDn 10 V.. r.,. *dg* *t. '""'"" 8) or ""9 -a l!Nldang pooL ADIJJfUHU *.l.Y, THE BRIDGE TRAVEL LIHIT STATUS Ur.HJ WILL tnNTINUDUSLY FLASH wtEN TR.!J..LE'f TRAVEL HDJJDNS EXCEDl THE BDAROERS DF THE CASK PCXl. AREA. Trallty T,.,,.J Reur-1pt1an With ** u... mnd or v.. bra-'9-pa*a\\.loned ID-v..... v1at.d ...,., ru.l *tar-911* paal _... ond *1th "- br-1dg* pro*l**tw
'°' 1n "1pped pa.1\\.1- ~
1r-C1llew -t..lan.tu.d1 wcr.ild pout.Ion V.. *3 lfl!ln hack av~ U.. !\\or'"!f9 pool.,..,._
di vap the t1-alley P"'0*1*1'1.I... tatt !NI 1n aon,,..,a\\u*'

nth th. br1dgm **1~ de~I** apM"abJa -- -t.1-and Ht. br!lke.. The VDll9'1 *Ill C- \\a,...\\. *1"1 V.
C*nter hr19 of INlln hook *\\. U.. *dgt o( on.-0 hne .,..._..,n.d by "1* 1111n1....,.. d&!\\ancl! r,._, U. aen\\ar or.-.eotoi- *Mltlan ta...... ar th..,.... t. r.. 1 -~Iii* poal1 1n the Dl"!O or aw onk loading pool. V. hook ,.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 at. Cpcnnt. Bl ar V.. cuk lcuu:f1ng poc1L AODITICJIALLY, Tt£ BRIDGE TRAVEL LIHJT STAUS t.IGHT Will CONTIM.OJSL.Y Ft.ASH WHEN TJO.J..EY TM~ HOJJONS DCE'ED TIE BOMO£RS OF' Tt£ CASK LOADIM'.i POii.. AREA. 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. IJI SELECT[ll SWITCH "RESTRICTED MOOE" JN "BYPASS* PQSJTIDJti BAIOOE AND TRDL.LEY -TRAVEL WILL BE AS Fl1LDVS. THIS POS(Tl(Jol WILL ALLOW UH-RESTRICTED QPEJIATICl\\I OF #ILL HOIST IN All AREAS m:' TtE STATION. THIS llCLLOES lHDSE AREAS OF TtE S?EHT F\\EL STORAGE ANJ CASK LOADING POCL. SOURCE: lillillil24llillil441illil6 FIGURE 5-4 CRANE RESTRICTED ARtA SHEET 2 OF 2 NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016 _j
SUCTION FLOW CORE DRIVING FLOW 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
SOURCE 12177-PID* 2'1A*8 TITLE*REACTOR RECIRtlA.ATION SYSTEM
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a. fJ..l~~,w~msrs...,,.:-.i*.=**11 l.GPt~STlllf'WCllW'lMSft:11MIS-.....0*PLCL FIGURE 5.4-20 R£ACTOR COOLANT <REC! RCULATI ONl NIAGARA MOHAWK POWER CORPORATfON NINE MILE POINT - UNIT 2 UPDATED SAFETY ANALYSIS REPORT U5AR REV!5ION 1 3 OCTOBER 2000
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~-------------------------------~

RCSTC08 1 N0.2 SEAL CAVITY TEMP I ~ L'f-' LJ601 I I I I I I lr::9~.2~-~3b:-:(~C-~1~0~l--)>----~----------f~¥""1 NOTE 3 SEAL COOLER w~ u-I I *HOSE74_,\\.. A I I l:VS3B I ED48r214 2-RCS-7S0-190-2(B-, -...._, 602110 2-RCS-7S0-191-2( 8-J-....... ~-_,,, J =f"-'iJ:l ..:J----------i,,t-----[ r------, 2DER- ~SH 2-RCS-7S0 ~(B-l I -189-3(8-l c ~ Fi) I RCSFC04 ~~ N002B I 399 DER SYSTEM A
9. 3-9f (D-101 L'f-'
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( B-1
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( B-l 2-RCS-7S0-197-2CB-l VALVE CLOSE WcR I I 2-RCS-750-29-2(8-J I I I I I !_ ______.J I I PT 428 Pl 41B E9 I R 6 3 I RC~A03 I I I I r----------.J I PT 44B ~/"PI' LJ '103B) , ~ VS6B ~-----eRS ____ J I I I <~9~.12-jJ~b~(~c;-~10ITi::::::J---.... ---------U~§_~ NOTE 3 N0.1 SEAL CAVITY N~S t:C2 4;- ~ \\ 2-RCS-7S0- ~---~,, 'jHnW11111---------{)::*a-*-.l...---T'"--l<:'AJ------'L---;:~~/~¥':::.t-A-+111wr--,----,r--t'<AJ--_.J~~*-----...l..-----"'-----------<::::. '~RCSTA20 .. v61s(B-l -.. V60B(B-l .. v90B(B-l t~~fB-v58B 0 -;*):()-*------'--..... 1--(_.,.
5. 4-2b ( K-1 0) 602220
§---J RCSTA18 ..Iii:\\

~-------------- ~

C00(B J1.J2 N0.1 SEAL CAVITY TEMP 2-Rcs-024-19-1(B-1 7r-;R~E1-::.c~T:::oR;;----....1_1_-(~ " ___, NNs~c2 IF0'j IF013BI IF009BI IF011BI IF016BI <THIS DWG (I 4) I RECJRCULATION PUMP 4;:" 2RCSlfP1B(B-l C001 B T [ ""fb IC001BI I K1.K2 -Jl----fl---' '~~~~
i:V140

w;V1l0 l ___ \\... ~::::::::B~~GE::~J (8-J
( B-l THIS DWG (G 4l I 2-RCS-024- ( 8-1 ( B-1 ~ !RC....... ORC NNf>T SC2 v~
v7BB *v77B CB-l CB-J
---+ SC2-l NNS lfi ~Jr
V72B *V7SB (B-l (B-l DER SYSTEM 9.3-9b (F-81 NOTE 3 RO V2029B 1 8 ID001 ~
I l VS?B THIS DVG K-6 THIS DWG K-6 S.4-2b (K-101 S,4-20 (K-101 I FIGURE S.4-2c REACTOR RECIRCULATION SYSTEM NINE MILE POINT NUCLEAR STATION UNIT 2 SOURCE. PID-29C-33 SCRIBA, N.Y. UJ D z TITLE, FLOW DIAGRAM REACTOR COOLANT (RECIRCULATIONJ UPDATED SAFETY ANALYSIS REPORT A B c D E F G H I J K USAR REVISION 2S OCTOBER 2022 1 2 3 4 5 6 7 8 9 10 11 _J
8 N.O. E3&mb ELEC 1 ~2a~::~TOR ~ PIPE 0.TIIOOIA B(ill!fil) 18
SOURCE, PID-290-9 TITLE, REACTOR RECIRCULATION SYSTEM 11 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 FIGURE S. 4-2d REACTOR RECIRCULA TJON SYSTEM NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N. Y. UPDATED SAFETY ANALYSIS REPORT M USAR REVISION 16 OCTOBER 21illil4
1400 1200 H 1000 (.) z w ~ 800
u.

u.
w
I:
en
11. z a
<{ 600 w
r 400 200 N -
______________________________ _..u---- PUMP FLOW (gpm) - THOUSANDS H HEAD (feet) N NPSH (feet) E EFFICIENT (percent x 10) x RATED CONDITIONS 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
r THROAT OR MIXING SECTION SUCTOON --......... e.. - .--~~--...... ~ ~--..1...-------------~-------- DRIVING FLOW FLOW____, <Sr-------------- DRIVING NOZZLES SUCTION FLOW ---1 DRIVING FLOW 4P SUCTION. FLOW 4P ______ _l FIG URE 5.4-4 OPERATING PRINCIPLE OF JET PUMP NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
NORMAL WATER LEVEL TOP OF ACTIVE CORE 1 I I I I r I I I I I I l_~_) STEAM SEPARATORS STEAM SEPARATION DISTRIBUTION PLENUM WATER LEVEL AFTER BREAK IN RECIRCULATION LOOP ACTIVE CORE 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 (1 OF 2) DOWNSTREAM TAP (1 OF 2) I I tj MAIN STEAM PIPE FIGURE 5.4-6 INSERT MAIN STEAMLINE FLOW RESTRICTOR NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
I PILOT DISK.
PNEUMATIC COtfTROL ASSEMBLY SPRING YOKE ASSEMBLY 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 SOURCE, PI0-3SA-I 6 TITLE, REACTOR. CORE ISOLATION COOLING FIGURE S.4-9a REACTOR CORE ISOLATION COOLING NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N. Y. UPDATED SAFETY ANALYSIS REPORT 11 I USAR REVISION 19 OCTOBER 20I 0 _J
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L (SEE: llOTE:S 12. 13 ~ NJ LOCATIOIV Q 1-2 18-2 ',19-194 194-G ~-.a!>O.a!>O*I 18-11 ST.'H4T£0 LIA£ SIZE. IN. ..... NSATE 0 1,1 I I I I I I I I I I I

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~-i---------.c~** ~*~j ---*~I~~ THIS DRAWING CREATED ELECTRONICALLY MODE,4 sl.ICTIOIV FllOH COMJE:NSATE sTORAaE:. R£ACTtR AT HIGH PRE:sSU?E:. SIF'PR£ss1av ~ AT HIGH PRE:ss. 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 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 9.36 9.36 9.36 JG JG JG ?5 JG ?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 FL01'-S££ llOTE: 2 G8l6 GIG G8l6 G8l6 .>r *.llr~.llrf.>O *.llr JG JG JG ?5 IG MODE D SU:TIOIV FllOH SIF'PR£SSIOIV ~. R£ACTtR AT UN PRE:SSl.ii'E:. SIF'PR£SSIOIV ~ AT L01' PR£SS. LOCATIOIV Q I 2 3 <f 5 G ? 8 9 18 II 12 FL01'-S££/IOT£2 G8l6 GIG G8l6 G8l6 8.<f811."88.<fl1 JG JG JG ?5 /G 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. 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 SOURCE: 5.4-10-01 FIGURE 5.4-10 REACTOR CORE ISOLATION COOLANT SYSTEM PROCESS DIAGRAM SHEET 1 OF 2 NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 1 9 OCTOBER 2010 _J
THIS DRAWING CREATED ELECTRON!CALL Y 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 FDA HODES C l 0 ARE 9ASED ll'ON SUCTION PIPING DESIGN PERKITTING THE MINI-REQUIRED "'5H TO CONTINUE TD BE PROVIDED TO Tl£ RCIC PUMP WKEN Tl£ SlffRESSION POOL SUCTION STRAINER IS 59 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~ IFllJ>AND 21CS*HDV l4311'81~>. 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 DIAGRAM SHEET 2 OF 2 NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 18 OCTOBER 2008
a: J: iii co ...J I ~ 0 ...J u..
?
c( w I-U) 55000 50000 45000 40000 35000 30000 25000 20000 15000 10000 5000 2200 RPM 4700 RPM EXPECTED PERFORMANCE TRIP & THROTTLE SIZE: 4 INCHES RATED INLET STEAM : 1135 PSIG - 562°F LOW INLET STEAM: 135 PSIG - 358°F RATED EXHAUST PRESSURE: 10 PSIG 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 55000 50000 45000 a: 40000 J: <n ID ..J 35000 I ~ ..J LL. 30000
?;
<{ w I-(/) 25000 20000 15000 10000 EXPECTED PERFORMANCE TRIP & "FHROTTLE SIZE: 4 INCHES RATED INLET STEAM: 1135 PSIG-562°F LOW INLET STEAM: 135 PSIG - 358°F RATED EXHAUST PRESSURE: 10 PSIG STEAM RING INLET 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
550 MO e
2.* 400 Cl Q)
Q. i 350 200 150 100 ~ ~ ~\\ M \\ . \\ 0 2 \\ \\ 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
\\ 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 FIGURE: 5.4-11 VESSEL COOLANT TEMPERATURE VERSUS TfME CTWO HEAT EXCHANGERS AVAILABLE> NINE MILE POINT-UNIT 2 UPDATED S.Af"ETY ANAL YStS REPORT USAA REVISION 20 OCTOBER 2'012 ~
600 550 500 b 450 ill.a 400 0 t Q. ~ 3.50 !! 300 0 31: . gi 250 Q) 200 150 100 ~ ~ \\ -\\ \\ 0 2 4 eDRf: 0000-0071-6768 eDRF Section : 0000-0071-6783 Rev. 1 Nine M~e Point Unit 2 EPU RHR System Shutdown Cooling <SOC> Anolysis - Two SOC Loop$ .M"t Service Woter, ANS SJ 1979*20 ~ 6 8 10 12 14 16 18 20 22 24 Time After Control Rods Inserted <Hours> I-EPU-One Loop I 40 of 41 Plot-EPU Two Loops FIGUR£: 5.4-12 VESSEL COOLANT TEMPERATURE VERSUS TrME <TWO HEAT EXCHANGERS AVAILABLE> NINE MILE POlNT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 20 OCTOBER 2012 ~
A 8 B 10 II
SOURCE, PID-3\\A.* 22 TITLE,
RESIDUAL HEAT REMOVAL A 0 mI!l*-i 4 l! ~~~?-" r**-----T----e1ttill! i i @~ '~m::+-_r-=~~rl I
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r****r-**-****--~---r----, ll<Sa.. _,: tDl**-111 mtil:~~ou.. ~ 1 r.~.~,.~,~.,~~,-~ ibllil i i i-""' i lan~! I[~ LIJllll(£C.llllllL111. lllQICIR111£U.l'llU5 G H -N-~~-N-tD111..-111 Cl>>OIA_,.I n I\\_, ___,,,_,_,,,_, k.......,.,._,,,_, ~ M N FIGURE 5. 4-1 3o RESIDUAL HEAT REMOVAL NINE MILE POINT NUCLEAR STATION - UNIT SCRIBA, N. Y. UPDATED SAFETY ANALYSIS REPORT USAR REVISION 21 OCTOBER 2014 11 _J
a 5 2-RHS*l'i>S'-112*218*1 r:Z*llHS*llllll-111)*218*1 rri@1~
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RESIDUAL HEAT REMOVAL G M L ~~1=~ =~m:i;:-:~~~[.11 1~::1!~~ VITH .UlUIMI. 1*1 MILL ll£PUa: Tl.: DAs.H l*I Ill nc....ull FIJI ~~~~T 5oi:'M:':.S. 01111.11[Nl5 llHID4 t.11E l'ARI CF ND.EAR SAn:Tl I. ~~~~~~~l>>t::rf~~l~~~U 1111 8(
f. QFF-fOllUL 5U.TU$ lllSl'l.U HS.1[11 u;.talotClCN'.D IJt..... Ac:C.
FIGURE S. 4-1 3b RESIDUAL HEAT REMOVAL 2 1--~~~~-N-IN-E~M-IL_E_P_O_l_N_T~~~~--<ll NUCLEAR STATION
UNIT SCRIBA, N.Y.
UPDATED SAFETY ANALYSIS REPORT USAR REVISION 20 OCTOBER 2012_]
A 2 T... __.., ___, le\\1278 liiti ..., L!.J ~~~~ ! r~" tyj IQOI ;:;=:ND\\ I U Uo.l*l&t .,........,,..... \\.11A-l k 2--.l***-1n-:r1*-1 _..... 12-!JS*ll**I II ~QUACE,PID )IC IS TITLE, AESIOUAL HEAT REfotOVAl A H 2--***-r12-,.1-1 2--*U4*U**Jil*I-Ol'("IQ.Ql,£ r*-----mi-1 ~---+**: OH 11 MUUC-rD t?ii:\\':t Ol'1tvn.OW: ~-------~-. L '-°" !'!t!..a:' l.YL v '\\:J""" HJCMllllTVCU... ll i~---B *-1]~'*,~: 1 ,j _______ J !r---~ i jT~*-nii,E_,,,, l--"--<:I:i:"'1:mrn r---1 :tflrcnt 4 j ! ~l~'r.i~
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r. "
mlll11FIU11CN....... NIE: WCVM Ill ~Ii CTD 111: ~IJ(DH(l2Ul&.U.101ot:lhilW:f'111UJllG.I L CIULIED 4.Cl'F--IUMOlllUrSUTt.lllSl&UIDIMJlllll'l....O:. FIGURE S. 4 - 1 3c RESIDUAL HEAT REMOVAL NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y. UPDATED SAFETY ANALYSIS REPORT 5 6 6 II USAR REVISION 20 OCTOBER 2012_j
O --;.o:;;,:,...:r-;--1 2(A-I 2-RHS-7,._..._ I 2-RHS-7U-S87-2(A- ""'!.. ) SOlJRCE, PID-310-~.\\TREMOVAI. TITLE. RESIDUAL I ~ - - I *

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(f!:)tfil!i. EB+ [;)..... \\tf-1 It-I r ~I ~ ~@ 8t!!i!i SOURCE, PI0-31E-21 ~----- ,!;CJOlt*J TITLE, RESIDUAL HEAT REMOVAL lmTE 4 ~.'.:~ ::;1,.. llV;~.LJ !... ~~~LJ-! ...-'"-----~ GE!Uill::::r-i~::>---->-~l-1.:: ~ r i - -~~-~~J I C-41 L;~:-.~,:2~;'--- -- - --- --------------; L-,._L--'---""*"~~--.~L-,...-::u:*-~* ~**rn-*~ 2 21 +tt---------1~:' I I 2-""5-"8-,..-2**-> rm f!I !:.\\" El(U.l,. *A* 1 2--RHS*'1Sl*S89*218*1 i i 2-JMS-*1-212~1a -1 ~------; ~ - -- - - -fh:,:..:in
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FIGURE S.4-13e RESIDUAL HEAT REMOVAL NINE MILE POINT NUCLEAR ST A TION - UNIT 2 SCRIBA, N. Y. UPDATED SAFETY ANALYSIS REPORT 11 USAR REVISION 19 OCTOBER 20 l 0_j
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CSL SYSTEM SC2 ~ lo-SCJ NNS 6.3-70 <G-101 I SOURCE: PID-31F-17 TITLE: RESIDUAL HEAT REMOVAL N i'I (Xl -' "' -"' ' u (/} N NOTES: l ALL INSTRUMENT ANO EQUIPMENT NUMBERS TO BE PREFIXED WITH "2RHS" EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN. AN ASTERISK C*I WILL REPLACE THE DASH C-l IN THE PREFIX FOR EQUIPMENT OR INSTRUMENTS WHICH ARE PART OF NUCLEAR SAFETY FEATURES SYSTEM.
2.
GE IDENTIFICATIDN NUMBERS ARE SHOWN IN SQUARES CTO BE PREFIXED BY E12 UNLESS OTHERWISE PREFIXED.> J. NO FLAG SHOWN ON CORRESPONDING DOCUMENT. COORDINATES PROVIDE INTERFACE LOCATION. 4.2RHS*MOVl42 AND 2RHS*MOV149 SHALL BE DE-ENERGIZED AND DISCONNECTED FROM IT'S POWER SOURCE !BREAKER OPEN) DURING NORMAL PLANT OPERATION TO PRECLUDE THE POSSIBILITY OF SPURIOUS ACTUATION DURING A CONTROL ROOM FIRE !APPENDIX R). THIS IS NOT MEANT TO PRECLUDE USE OF THIS VALVE DURING NORMAL OPERATION, BUT TO ENSURE THAT THE VALVE REMAINS DE-ENERGIZED WHEN NOT IN USE. 5.0FF-NORMAL STATUS DISPLAY SYSTEM IS ABANDONED IN PLACE. FIGURE 5.4-13f RESIDUAL HEAT REMOVAL NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N. Y. w t-- 0 z UPDATED SAFETY ANALYSIS REPORT 1 2 3 4 5 6 7 8 g 10 11 A B c D E F G H I J K USAR REVISION 25 OCTOBER 2022_J
A a II SOURCE, PID-31 G-IS TITLE. RESIDUAL HEAT REMOVAL A B IVIJ6 lfll ~ D Hll ~ rn IM El ---~ l!!i!l ' iB ________________ J_-@-----~ D F ~ nn1 IM '---m-='"'~I d
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N I ALL LINES ANO EQUIPMENT INSIDE I I THIS BOUNDARY ARE DE-ENERGIZED ANO ABANDONED IN PLACE. I. ALL DCSIRLMENT MO £11.Jl'"ENT -.EA5 TD BE PIU:FUEII WITH J~~~.~~11.~:.t',fl~~~~.'l.JST~~Fl~Fml h~=TS~Tr:iS..TIUl£NU. llHlCH All[ PART DF ICl.C..EAA WEIT I. rol:IDCHTIFlC.\\TtDNN.teDISAllESICllNIN50JAllE51TDllE P'll£fU£D8'£1:ZLJL£UD1111'111£1"11£Fll£D.I J.~::._~....=mcca::1rc~uc::~t-
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~~- FIGURE 5. 4-t 3g RESIDUAL HEAT REMOVAL 2 6 1------N-IN_E_M-IL_E_P_O_l_NT-----lu NUCLEAR STATION - UNIT SCRIBA, N.Y. UPDATED SAFETY ANALYSIS REPORT USAR REVISION 20 OCTOBER 2012~
SIDE II TOSERvK:E WATER 0tS0tAAG£ RHRSERVJCE WATER SYSTEM JE---- RCICLINE I ,---------------------1 .... SJEAHFRDMRCtC I.IPL NO <E12*1020> NOTE:
1. FOR DATA PERTAINING TO NUl.lSERS WITHIN HEXAGONS REFER TO PROCESS DATA REF. 1.

2. TO REACTOR BUILDING EQUIPMENT DRAINS.
REFERENCE DOCUMENTS: MPL ITEM NO.
1. RESIDUAL HEAT REMOVAL SYSTEIA Pll<ID B12*1010 B21-1020/B22 -1020

2. NUCLEAR BOILER PROCESS DATA SIDE I TO SERVtCE WATER OISCtuac(
RtfiSERV1CE WATER SYSTEY FIGURE 5.4-14 RESIDUAL HEAT REMOVAL SYSTEM PROCESS DIAGRAM AND DATA SHEET 1 OF 3 NINE MILE POINT NUCLEAR STATrON
UNIT 2 SCRIBA, N. Y.
UPDATED SAFETY ANALYSIS REPORT USAR REVISION 19 OCTOBER 2010 _j
<SEE NOTE 3> MODE F POSITION Q 1 2 3 4 5 6 7 8 9 10 13 49 24 1 FLOW-GPM PRESS.-PSIA ,._, x x x x x l'Xl'X 'X 'X X [LOOP C \\._LOOPS A S. B R,PRESS. 135 PSIG MODE G POSITION Q 29 25 26 4 5 6 43 24 1 1 2 3 4 5 6 6.2 43 24 1 FLOW-GPM 1000 rz.rz. - PRESS.-PSIA IX"*' TEMP.
F
- '%' ~-l--+--+-~-~1'% - \\_SEE NOTE 22 \\_SEE NOTE 22 MODE S POSITION Q FLOW-GPM PRESS.-PSIA ,._,xx x x'x xx xx xx xx 1S.s'XIYIX1135X,X TEMP. "F MAX.PRESS. nRoP-FEET POSITION Q 54 55 !! FLOW*GPM PRESS.-PSIA XX X TEMP. "F MODE s <CONT.'Dl 'Xi'x x x x x x x x x x NOTE: Mode dote on this sheet wos used for original pipe and component sizing. Design requirements ore based on Mode specific analysis. <SEE NOTE 3 a. 4) MODE A-1 POSITION 0 1 2 3 4 5 I 6 7 B 9 I 10 16 11 29 FLOW-GPM PRESS.-PSIA '".;Y x x x x TEMP. "F l'X MAX.PRESS. DROP-FEET <SEE NOTE 14) MODE A-2 POSITION 0 1 2 3 4 5 I 6 7 B 9 10 16 11 29 FLOW*GPM PRESS.*PSIA "*' x x x xx xxxx,..1 TEMP. *F 18¥ [LOOP C \\_LOOPS A S. B MODE B JS11 Z/4 2e 2$8 I FCFi!3BXl84AF (/:12-1020) NOTESa A-l ~:J.SR~~jT~~p~~~~C£~1S HI~ A-2ACCIOENT WllHREtlRCU.. ATIOHLlNE8REAK !NEITl-ER SJOEAJrC>lfflEEPUHPO'ERATIOHMSTRA!HERPLIJGGEO 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 D HORMt.1..SHUJ'DCWfArTtRll!ll..OrlJCIWtTO""'lNtcHDDIS£R (SUNOTEU).. E ~r~+l~~f~~~mr~r KlOE 110* (ATOPSIG) G HINIKJHf'LDWBYPASSMODE. S SYSltMQH5TAHOIWDUTY 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 ~~~
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21.~~~~~~~~~~TtE 22.MU:lfll.INl"ELllMISSIUSHJTOfft£AD*IOof'T0 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 X1M.1XX1z4.1IXIX 1.RHJl'SUJ0.1"£1D--E1~1010 2.eflSTSTDIOESIGHSPCC-02-4010 s.ac1c.l"fl)----a1-102c 4 *.q[CIRCS't'STD4Pf1>----SD-!Q40 ,.1.rc.srro----01-1020 --+--+--l--+--+-~-+--+---+--+--4--+12&q - 72 MOD££ OPS/If PR£SS*PS/A /4.7 X X X X.,)<'l,.X Xj)< XI X.]i'x X l*.7 XIX SOURCE: 0016310001004 FIGURE 5.4-14 RESIDUAL HEAT REMOVAL SYSTEM PROCESS DIAGRAM AND DATA 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 TNlL<: I* VA.:.VF: FOSJrOI OIART >itltlA-1 OC O n 10{)[8 G 0 0 ()id 1:1"1£ DO() Tl/BL£ 3 LIMIT/I.I(, LIAJE l/IS5cS T o inioe.R-1 /0*11 PUMP O/SOWIG£ U!J! TO FIPV FIDOb!Al6 ftJJE.rlArtOJ/ IJomtA-Z I.JOME NOTE 25 ~.lo>J *** le D 1-c*_1tt11_7-+-- 1 _____ JJo_J.J..:..'l _____ ---i SEE NOTE 25 llfl){(*' 19*3f*3SfSTEAUUJ/[HiJIJEtltil/IE TPllrllll<fliZ) llt<<c-4 JS*/7 (~TWILi/i[ I/WU 7Qflr) 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 ~/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 NOfUJ ,. ts (PIJJ.JF 1.111/litllJl.I 8YPA:iS UNE') THIS DRAWING CREATED ELECTRONICALLY NOTE 25
25. STEAM CONDENSING MODE OF <C-1,2,3, & 4l OF RHR HAS BEEN RETIRED.
STEAM IS NO LONGER SUPPLIED TO RHR HEAT EXCHANGER. RHR HEAT EXCHANGER NO LONGER ACTS TO CONDENSE STEAM. SOURCE: 001631012Jl2J1012J4 FIGURE 5.4-14 .RESIDUAL HEAT REMOVAL SYSTEM PROCESS DIAGRAM ANO DATA SHEET 3 OF 3 NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 1 9 OCTOBER 2010
1200 r--------------------------------------- 1100 1000 ~ MINIMUM REQUIREMENTS 900 800 700 ~ 0 600 w
c
~ 500 ~ 400 300 200 100 0 1000 2000 NPSH-REOUIRED AT2 FT ABOVE PUMP MOUNTING FLANGE 3000 5000 GALLONS PER MINUTE Note: Pump cane r*presmts manufactur*r's l*sl curt1*. Installed performance and minimum acc*ptable Technical Seecitication p~r(ormanc* is below this cane. SOURCE: 73IE961AF 0 N 10 ::c ~
c fl) 5 II.
100 z 0 90 80 c 70
e

s 60
(,J z w Q LA. a: 50 LA. w w ~ w 40 fl) a: 0 ::c w 30
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a: ID BHP AT SPGR z 1.0 1000 20 6000 500 10 0 7000 8000 9000 FIGURE 5.4-15 RHR PUMP CHARACTERISTIC CURVES NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 13 OCTOBER 2000
q 10 11 A 2-wcs..... 1-211-1.,.. IH B <IEEJED--------: < \\:_~'~:~. j.... ____ J_ _ __, i l ..... Fl w B 0 i~ I !
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ru' El l!!.!!! ! ! [__~ j ~MJn1 1rn.....,.1 j ! i 0- ~---~' I;.'.'.',-;.::.',, >------------J ~ K M FIGURE ">.4-l&o REACTOR WATER CLEANUP SYSTEM NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N. Y. UPOATED SAFETY ANALYSIS REPORT 5 8 11 USAR REVISION 23 OCTOBER 2016 _j
D .: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 5 e 'I 10 II SOURCE, PJD-378-26 TITLE. REACTOR WATER CLEANuP !EliDC>****-, ~---**1 c::mL=>-***j ~-****: @8 i I i H 8@ El i 8: EJ! ~~.. I~* EJ r---&,m, EJ)!, ~ r'*~t*-~**_.. _,._. ________ _ IMllltC.c.LL m um l-f"W,*Ht~l*lta-1 1.... 2*WC'*~H-1 K* H rw~l._
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N FIGURE 5.4-16b REACTOR WATER CLEANUP SYSTEH NINE MILE POINT NUCLEAR STATION
UNIT SCRIBA, N. Y.
UPDATED SAFETY ANALYSIS REPORT 5 II USAR REVISION 2 3 OCTOBER 2018 _j
1 2 3 4 5 7 8 9 10 11 A SOURCE:PI0-37C-27 B IN006I TE 137 c

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IN001D I ~: sov Iv-I "~ f-Cl-FE ~ l/P A/S _.._..--\\160 ~v ~~ v206 160 , v201 !s1231e _;_so.... ~.I.~- fi04l ~@9* 1:~~1s :l_...!:=~*=~z;:1_~::;5. - J.b. VENT-,.. 58 lE_J NOTE 3 A- -= ~ O 1 WCS*IPNL188 ~ ---, I ~ WCSBC28 4:::;;df--" 1 1 ....__w_c_se_c_c 1-*'~e;,e
P.:.;IS;.,;;:*l~R ~..... _______...,.. a~tk'I--~
1EJ1-*s0*ei I"'" L-i 5.4-160 W-31 ) r\\ 2-WCS-01114-ql-3* f e-}_!-------------l:e~~r-~ sov 135 1F~3 1 2-WCS-006-3111-4 IFeJsl FV 160 f 76111 r:::::;:.:l::'._:::j -e;-- )--e---t:ll:J----H--{1-7( 1 IRsesl I MDV 1 V167 107 I ---L-:!., FY 135 [0331 2-WCS-006-24-3 o---2-wcs-1110s-2q-3 2-WCS-004-q6-3 2-WCS-1111114-26-3 2-WCS-004-41117-4 _...,_ __ -. 2-LWS-006-566-4 LWS SYSTEM 11.2-1.. !D-ll 2* WCS-006-164-4 NNS.l.scJ TITLE: REACTOR WATER CLEANUP A B c D E F G H I J K L NOTES. M TYPICAL AIR OPERATED VALVE ARRANGE~NT (SEE TABLE BELOW Aftl> NOTE 6> sov A/S EJ ADV I I I I I VENT I I _____ J TABLE AREA AOV m sov (J-q) 270.... 270 0 IH-1) 23A FG901 23A Oi-2) 238 F'1111!11 238 D-1-31 230 230 D IH-"41 23C cool 2JC c IJ-11 22A FG11i!12 22A IJ-21 228 cuu* 228 IJ-Jl 220 F002 220 0 (J-"41 22C F01Z12 22C c 11-81 27C 27C c IG-71 278 Flii!ICZl-4 278 LC KUC5B Kl.C5" KLC5" KUC5B KUL'.58 KLC5" Kl.C5" KUC5B KUC5B KUC5B Kl.C5" I. ALL INSTRUMENTS AND EQUIPMENT NUMBERS TO BE PREFIXED WITH *2wcs-* EXCEPT WHERE
DIFFERENT PREFIX IS SHOWN.
AN ASTERISK lol WILL REPLACE THE DASH !*I IN THE PREF IX FOR EQUIPMENT DR INSTRUMENTS WHICH ARE A PART OF NUCLEAR SAFETY FEATURE SYSTEMS.
2.
GENERAL ELECTRIC IDENTIFICATION NUMBERS ARE SHOWN IN SQUARES. !TO BE PREFIXED WITH G33 OR G361.
3. SEE TABLE FOR TYPICAL AIR OPERATED V ALVES ARRANGEMENT THIS DWG IM-51 *

4.
ND FLAG SHOWN DN CORRESPONDING DOCUMENT. COORDINATES PROVIDE INTERFACE LOCATION. ..... -** -.. - **-**-** -** -.. - **-**-** -** - **-**-.. -** -** - **-**-*1
5.
IALL LINES AND EDUIP~NT LOCATED INSIDE THIS BOUNDARY
ARE ABANDONED IN PLACE.
j
6. AOV23A,AOV23B,AOV23C,AOV23D,AOY27B,AOV27C AND AOV27D ARE BALL VALVES IN LIEU OF THE GLOBE VALVE SHOWN IN Tl-£ TYPICAL NJV ARRANGEMENT THESE VALVES ARE NOT SUPPLIED BY GE.
1-0WEVER THE GE IDENTIFICATION NUMBERS ARE MAINTAINED FOR CROSS REFERENCING TO OTHER DOCUMENTS. FIGURE 5.4-16c N REACTOR WATER CLEANUP SYSTEM NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y. UPDATED SAFETY ANALYSIS REPORT USAR REVISION 25 OCTOBER 2022 1 2 3 4 5 6 7 8 9 10 11 _J
1 2 3 4 5 7 8 9 10 11 A B 2-SAS-001-515-4 SAS SYSTEM q_3-1 * <0-3) c IF0:51 V79 D 2-WCS-001-39-4 THIS OWG !0-6) 2-WCS-001-36-4 [TI ADV 25A NOTE 3 E 2-WCS-002-37-3 2-WCS-001-175-3 rF0i5] ADV ~ 30A F NOTE 3 ADV IF013 I SC3lNNS 2-WCS-002-176-4 61A A G H 5.4-16f <B-Bl WCSBC05&------, 602317 8-1 WCSBC23&------~ I 2WCS-IPNL187 V208 NNS SC3 NOTE 3 !'!_ IR010 I 38A A rn < 5.4-16f <C-111 I ~ I 2-WCS-003-396-4 "_} ADV 2qA 5.4-16f IC-Bl 5.4-16f <E-9l 2-WCS-150-40-4 2* __ __....._,CLEANING r CONN ~ 2-WCS-008-509-4 2-WCS-002-44-4 NOTE 3 ~l5=._4-~16~c_<_K-~U~~>~-------- CHEMICAL CLEANING CONN ~-011J2-479-4 2 1
WCS-0~-~~
V76 RM V75 2-WCS-002-50-3 V74 IF0i71 2-WCS-002-51-4 ~ 2-WCS-002-172-4 THIS DWG <D-U 2-WCS-150-53-4 2-WCS-008-510-4 NNS iSC3 2-WCS-002-57-4 5.4-16c IA-71 2-WCS-002-481-4 NOTE 3 NOTE 3 2-WCS-008-203-3 IF0f91 ~V78 RM NOTE 3 IF0~01 ~V77 RM 2-WCS-006-486-3 2-WCS-150-517-3-- 2-WCS-002-46-3 2-WCS-004-3'l2-3 2-WCS-002-173-3\\ SC3 l NNS NNStSC3 lm6]V73~ ~ NNS 5.4-16f <8-91 2-WCS-001-39-4 IN~ 2 I l FILTER DEMINERALIZER DEMN 4A l--------- V171 V172 ~ ~ 5.4-16f IB-101 ) ~ NNS t007 I ADV 1---' A 52A 2-WCS-004-169-3 ADV t0051 54A A 2-WCS-002-35-3 NOTE 3 SC3 NOTE 3 I NNS ADV t0061 53A A 5.4-16f 11-41 ' ' ' v SHIELDED CUBICLE ~ 2-WCS-006-391-3 2WCS-IPNL187 1N0:21 ~---< FT ISA IF0~41 V173 ID~3 I RM STR5A IN015 I A ...
l, V174 Vl76 EB FE ISA V70 2-WCS-004-19-3 2-WCS-01116-487-3 2-WCS-002-168-3 RM 2-WCS-003-34-3 2-WCS-11101-45-3 Vl10 F041 m'--lefo-S-C3e:. /ffe)T PX A 1,-------~~---~ V358 g-T-V71 NOTE 3 2-WCS-150-389-3 NOTE 3 ADV 31A STRT8A ;r V254 I
~_j_ V359 F03q e "-----~ (----------, F041 B I F~31 I RM VIII l SC3 NNS DEMIN PRESSURIZATION 5.4-16e <K-71 KUC 2WCS-IPNL187 V72 IF0:91 NOTE 3 ADV 26A 5.4-16f (J-4) 2-WCS-001-185-3 5A ~F'--_::2_:-W:,:C~S-002-387-3 P6A lc0:1 I HOLDING PUMP 85 GPM 75 FT TOH 2-WCS-002-52-3 20FR-ED8402 DFR SYSTEM q.3-q. (J-41 NOTE 4 SC3 iNNS A V177 IF0:31 5.4-16f IK-21 A/S sov 16A NNS iSC3 2-WCS-002-184-4 rn ADV 29B NOTE 3 NOTE 3 NNS lscJ 2-WCS-008-54-3 2-WCS-006-488-3 5.4-16c IK-3! 2-WCS-002-61-3 NOTE 3 IN0J2 I LE (,,::~------ 2-WCS-150-186-3 2-WCS-006-385-3 FILTER OEMINERALIZER DEMN 4B L---------- RV 21B I I 5.4*!6f IE-Ill ) ~ \\_2-WCS-002-56-4 t-----"(.. scJ.LNNS 2-WCS-150-518-3 VIBZ ' ' v SHIELDED CUBICLE r---- 2-WCS-006-384-3 5.4-!6c !A-7) 2-WCS-006-489-3 2-WCS-003-59-3 V81 NOTE 3 J 2WCS-IPNL187 A ENT NOTE 3 2-WCS-004-21-3 5.4-16f !C-8! Fm41 c
J;?@
1--t:f-~i:.:;.~ I F039 c STRT8B J V256 I 0 V361 K DEM IN PRESSURIZATION 5.4-16e IK *6) II ~ 1:~~15-12102-386-3 j V86 2-WCS-150-382-3 V257~ F039 Fe41 RM V85 SOURCE: PI0-370-18 TITLE: REACTOR WATER CLEANUP A B c 2-WCS-002-64-3 IF0837 IV84 2-WCS-002-180-4 D FG 60B SC3 l NNS 2-WCS-002-65-4 5.4-16f <B-9> E 2-WCS-004-182-3 2-WCS-002-181-3 NNSrSC3 V83 IF0836 I SC3 l NNS 2-WCS-004-62-4 F ADV IF0051 54B B NOTE 3 NOTE 3 ADV IF0061 53B B 5.4-16f IJ-41 2-WCS-002-448-3 2-WCS-004-183-3 ~ SC3 N!s G H NOTE 3 ADV 26B NOTE 3 V82 IF0:91 2-WCS-004-63-4 5.4-16f IK-3! I r----? D O (---------* ' <IDC L__ KUC 2WCS-IPNLl87 5A
~~--.:2_-w:;,,c:.:s:.,-002-381-3 PSB 1ce:1 I HOLDING PUMP 85 GPM 75 FT TOH J
2DFR-E08401 OFR SYSTEM 9.3-9. 11-4) NOTE 4 K L NOTES: M N TYPICAL AIR OPERATED VALVE ARRANGEMENT (SEE TABLE BELOW ANO NOTE 5.1 EJ ADV I AREA <D-ll <D-21 <E-2> IF -ll (F-21 <D-3) <E-31 <G-4) <G-41 <E-5> <E-51 <G-51 <F-61 (H-6) (H-6) <E - 71 <F-71 <D-8) <F-8) (H-ql <H-101 <G-101 <G-10) 11-10) (J-3) A A/S VENT TABLE ADV m 25A F11114 A 2'lA F012 A 28A F011 A 30A F015 A SIA F013 A 51A F01B A 44A F00q A 52A F01a7 A 31A F016 A 54A F005 A 53A F006 A 26A F008 A 25B F11114 B 30B F0!5 8 618 FH13 B 2'lB F0!2 8 28B F011 B 518 F010 B 44B F1!10q B 529 F007 B 31B F016 8 54B F005 B 538 F01!16 8 2SB F01i!18 B 27A F11104 A 2WCS-IPNL187 sov 25A 2'lA 28A 30A SIA 5IA 44A 52A 31A 54A 53A 2SA 25B 308 SIB 2'l8 28B 51B 448 52B 318 54B 53B 26B 27A I. ALL INSTRUMENTS ANO EOUIPMENT NUMBERS TO BE PREFIXED WITH *2wcs-* EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN.
2. G.E. IDENTIFICATION NUMBERS ARE SHOWN IN SOUARES ITO BE PREFIXED WITH G36!.
3.SEE TABLE FOR TYPICAL AIR OPERATED VALVES ARRANGEMENT THIS OWG IM-3>. 4.ND FLAG SHOWN ON CORRESPONDING DOCUMENT. COORDINATES PROVIDE INTERFACE LOCATION.
5. AOV27A IS A BALL VALVE IN LIEU OF THE GLOBE VALVE SHOWN IN THE TYPICAL ADV ARRANGEMENT. THIS VALVE IS NOT SUPPLIED BY GE, HOWEVER THE GE IDENTIFICATION NUMBER IS MAINTAINED FOR CROSS REFERENCING TD OTHER DOCUMENTS.
FIGURE 5.4-16d REACTOR WATER CLEANUP SYSTEM NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N. Y. UPDATED SAFETY ANALYSIS REPORT 1 2 3 4 5 5 7 8 9 10 11 USAR REVISION 25 OCTOBER 2022 _j
1 2 3 4 5 7 8 9 10 11 A B 5.4-16f <F-8> c THIS DWG <E -6> NOTE 3 5.4-16c <D-8) EB AOV 2'lC 2-WCS-002-118-3 J IF0t51 1~1 ~~~=-~~---l-- V'l6 RM V'l5 < 5.4-!Sf <C-IU 2-WCS-002-119-3 RV 418 FG 60C D E NOTE 3 NNS ~SC3 [1J NOTE 3 ADV NOTE 3 28C 2-WCS-008-111-3 F 2-WCS-002-120-3 G ITTffil ADV L£_j 30C H NOTE 3 2-WCS-001-198-3 2-WCS-150-199-3 NOTE 3 LE 62~,,,_-_-__.__-_-~------------------------1 (,,, v SHIELDED CUBICLE FILTER DEMINERALIZER DEMN 4C zs 1N0c0s1 >-----< 66C I I r---- I 2-WCS-006-354-3 I I NOTE 3 PT 17C I I I I I I I I I I *----------- 1¥.?1

~ 2WCS-IPNL188

---J:Jlf-----'-----( POT }---------l:tif.--1 20C IN~041 I I 2-WCS-006-353-3 -~ 5.4-16c <D-8) 2-WCS-006-491-3 2-WCS-003-109-3 I 2-WCS-006-490-3 5.4-16c <K-5l 2-WCS-002-116-3 SC3 I NNS 5.4-16f CF-'ll 2-WCS-004-1'!5-3 2-WCS-002-194-3 NNSJSC3 V'l3 1F0c3s 1 SC3 I NNS RV 21C I F~81 I ~~f----{l]5.14-j1sfilr]<QG-]11[1::::::::::::> AOV IF0051 54C C 2-WCS-002-108-3 NOTE 3 AOV IF0061 53C C NOTE 3 5.4-16f (H-7) SC3 I NNS AOV IF0071 52C C NOTE 3 ~ 2WCS-IPNL188 ~ '-tJ ADV 31C V92 IF~691 2-WCS-004-196-3 2-WCS-150-452-3 ADV IF0081 26C C NOTE 3 5.4-16f CH-8l P6C I c~01 I HOLDING PUMP 85 GPM 75 FT TOH ~l9_.3_-~l>>~*<_E-_2_l ___ )~-----1r-------r----[)+---.....JL... ______ T'" ____ -[jT~HillISLQDW~G[Ji<Dt-TI11::::::::> 2-WCS-002-130-3 fFm5l ADV LQ_J 300 NOTE 3 10~061 5.4-16f CH-81 V223 Pl 388 V215 FG r--------------~--<140 1000071 NOTE 3 5.4-16c CA-101 NOTE 3 2-WCS-008-139-3 I F~I I AOV 280:...-----.__'f-' NOTE 3 NOTE 3 2-WCS-006-492-3 5.4-16c CK-4> NNS ~SC3 2-WCS-150-211-3 2-WCS-006-361-3 2-WCS-001-210-3 r;:::::-;:::::;--- '.1--------( is~ )--*-{J5[.4~-]16!frJcQG-]8[> :::::::::> ADV IF013 I l 610 D SC3 NNS NOTE 3 I N~l2 I 6~0 >---~ --------------------------1 (,,,',,,'_,,_'--------.... v SHIELDED CUBICLE PT 170 IN~ 6 1 i, FILTER DEMINERALIZER r---~ DEMN 40 I I I I I I I I I I *----------- 2-WCS-006-360-3 -~ 2WCS-IPNL188 5.4-16c CA-'ll 1----0J(J-__L------jPDT }-------~--I 200 V201 RV 210 IN~041 I F~81 I V202 2-WCS-006-493-3 2-WCS-003-135-3 F040 A J SC3 t NNS 0A42 V362 I--~~] V258 I~ V363 ~ F040 c V25~ 040 B F042 B 2-WCS-002-350-3 2DFR-ED8501 DFR SYSTEM NOTE 4 SC3 T NNS F0~2 V364 f.-.~~--{l]s.14-jt6filr~cfilGj-1fil01::::::::::::> t-----.t_JNNS 2-WCS-150-516-3 Vl01 1-i=f-~f-J T STRTBD V260 I SOURCE: PI0-37E-15 TITLE: REACTOR WATER CLEANUP A B IF! 0
1s-002-120-3 J I
f--1 -~------......__- v10s RM V105 2-WCS-002-129-3 c ~ - FG 600 2-WCS-002-126-3 SC3 I NNS 5.4-16f CG-'ll D 2-WCS-004-207-3 2-WCS-002-206-3 ADV IF0051 540 D NNS rSC3 2-WCS-002-134-3 NOTE 3 Vl03 IF~361 SC3 I ADV IFllJ06 I 530 D NNS NOTE 3 5.4-16f CJ-7) E F G NOTE 3 ~ ADV NOTE 3 310-,,~~ 2-WCS-150-359-3 2-WCS-11104-208-3 ADV IF011l8 I 260 D SC3 I NNS NOTE 3 5.4-16f IK-6) H 2WCS->PNL188 ~ '-tJ Vl02 IF0t91 P60 ICllJDllJI I HOLDING PUMP 85 GPM 75 FT TOH I V365 ~0 t---0:0--iP0----1 V261 ~_,, F040 F042 D D 2-WCS-002-356-3 2DFR-ED8502 J DFR SYSTEM 'l.3-'ld <E -6> NOTE 4 K V4780 V4 7'l0 V478C V4 7'lC K n V475 V474 V478B V479B V473 V472 V478A V47'lA L DEMIN PRESSURIZATION 5.4-16d CK-101 DEMIN PRESSURIZATION 5.4-16c ([-5) DEMIN PRESSURIZATION 5.4-16d Cl-4> M N TYPICAL AIR OPERATED VALVE ARRANGEMENT !SEE TABLE BELOW! EJ ADV ) TABLE AREA ADV Cl) CF -11 25C F014 c CH-ll 30C F12115 c (H-21 SIC F013 c <E-2l 29C F012 c CE-2> 28C F011 c C0-3) 51C F010 c CF-3> 44C Ffl)0CJ c (]-4) 52C F007 c (] -5) 31C F016 c CG-51 54C F005 c (] -6) 26C F008 c CG-51 53C F006 c Cl-6) 31110 F015 D CG-7> 250 F014 D CH-7) 610 F013 D CE-7> 290 F012 D CF-71 280 F011 D C0-8) 510 F010 D <F-81 440 F00CJ D (]-9) 520 F007 D Cl-10) 310 F016 D CG-10> 540 F005 D CG-Ill 530 F fl)fl)6 D ([-Ill 260 FIZl08 D 2WCS-IPNLIBB c 58 SDV 25C 30C SIC 29C 2BC 51C 44C 52C 31C 54C 26C 53C 300 250 610 290 280 510 440 520 310 540 530 260 V476 NOTES: V477
!: wu; I-
<fl w l-o: " a LL er Z o' "1 er 2DFR-ED851111 USAR REVISION
1.
ALL INSTRUMENTS AND EQUIPMENT NUMBERS TO BE PREFIXED WITH *2wcs-* EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN.
2.
G.E. IDENTIFICATION NUMBERS ARE SHOWN IN SQUARES no BE PREFIXED WITH G36l.
3. NO FLAG SHOWN ON CORRESPONDING DOCUMENT.
COORDINATES PROVIDE INTERFACE LOCATION. FIGURE 5,4-16e REACTOR WATER CLEANUP SYSTEM NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N. Y. w l-o z UPDATED SAFETY ANALYSIS REPORT 25 OCTOBER 2022 1 2 3 4 5 6 7 8 9 10 11 _J
1 2 3 4 5 7 8 9 10 11 A MILLIPORE FILTER HOLDER NOTE 5 FLTlA -~ MILLIPORE FILTER HOLDER NOTE 5 FL TIB 5.4-l6d CH-ll 5.4-16d IE-61 5.4-l6d IE-Ill SOURCE: PID-037F, REV.11 TITLE: REACTOR WATER CLEANUP A B ,,,__TYGON TUBING & CONNECTORS PRECOAT AGITATOR 'MIX100A Vll8 ~------jC}----i IF0A62 I Vll9 1rn;1 I c TKllA PRE COAT TANK FG 37A Vl22 IF~451 LT 56A IN0JB I D ,-----------j I A/S FY 55A V437A EDU4A PI 66A E ~-----------------1 VENT ' '==~~~ ________ J F RESIN AGITATOR
MIXl0lA RESIN FEED TANK
,----------------------------1 PCV434A ,---------J I I I PI 57A TK15A IA0A021 G V436A Vl78 Vl24 I , ______ J I NOTE 4 I I ~_J i [--l:t----, I I I Vl2l 2WCS-IPNLl87@ \\!A_) <!HIS DWG IK-101 I I Vl79 IF0A63 I Vl23 __________ I VI20 2WCS-IPNLl87 K~~- -----, 5A I I SQV I THIS DWG IG-91 46A S A/S f--{),'<f---ff----1 VENT ADV 46A I Vl39 PRECOAT AGITATOR
MIX100B FG 378 V435A I
I L _____ _ L--------------------------------------------- ,-----------------------------------------------------~ v433A: IF0A221 ADV NOTE 4 49A OFF/ON I L ___ _ I I RESIN METERING I PUMP I L _____________________________________________________________________________________ J
2wcs-IPNLl87K~~
5A ,>---.,,J kj f-Pl2A IC0A02 I STRT9An~ V276 0) L_ _________ ~ PRECOAT PUMP JT 255 GPM AT 85 FT TOH 20 FR-ED 85 04 L---jl_'9!_,;.3~9d!!_JllG,i_::!;611__) NOTE 3 100B041 r------------1 I A/S I I ',-"----~ I FY 55B V4368 _________ J 398 rn~ A/S~ ~----;~,.-~LOW l IF0B451 V132 VENT PI 66B RESIN AGITATOR
MIX10IB PI IR0Bl21 Vl89 IF0862 I 1-------~------1 Vl29 Vl30 PRECDAT TANK TK!l8 Vl3l 5B r-----1 r-g
\\_9 2WCS-IPNLIBB EDU4B V435B V437B TK15B RESJN FEED TANK f0~21 Vl34 r I PCV4348 ~ ' : <!HIS DWG IK 101 Vl98 PI 57B IF0:31 VI33 L ______ _ -1 V433B 1 NOTE 4 ~~~ IF0221 B ____ J ,-----------------------J NOTE 4
~---j -----
OFF/ON I L ___ _ ADV 508 RESIN METERING H PCV 63A NOTE 4 ADV 48A VlBB 5.4-l6d IE-61 5.4-16d IG-61 ~-, w IF0B201 PCV 63B NOTE 4 ADV 48B I I I I I I I ,------------J i I R~ll I PI 408 2WCS-IPNLIBB K~CC- -----, PUMP I Vl99 SQV I 468 I I s A/S f-~1§1_,l-iJ:t':+
2WCS-IPNLl8B KUC I
I I I 58 ~------------------------------------------------------------------------------------------J r;c=--;cc-,-;;--,;-;-=~ VENT THIS DWG IH-91 ADV 468 I I kjf-STRT9~-~ Pl2B IC0B02 I V277
0)
PRECOAT PUMP 255 GPM AT 85 FT TOH JTL_--{l}9.d3-39~dE1og-s[1===> NOTE 3 2DFR-ED8503 5.4-l6d IC-31 5.4-16d IB-81 5.4-l6e IB-31 5.4-16e IB-81 5.4-l6d IJ-61 5.4-l6e IJ-11 5.4-l6e IJ-61 5.4-lGe CE -Ill 5.4-l6e IE-61 THIS DWG. CB-81 THIS DWG. 18-41 5.4-lGd IF-41 5.4-l6e CG-61 5.4-16e IH-61 I NOTE 4 V128 NOTE 4 Vl38 THIS DWG IJ-31 5.4-l6e IG-91 THIS DWG IJ-61 THIS DWG IJ-41 THIS DWG CJ-71 5.4-16d IC-21 THIS DWG IJ-21 5.4-l6e IC-61 5.4-I6d IH-91 5.4-16e IG-41 THIS DWG CJ -61 B c D E F G H I J K THIS DWG lK-51 IF0:41 Vl25 --!' j-----------------'------1 f-------<( 9.2-I?b IJ-91 RV 45A V127 IF0A581 VI26 IF0~41 5.4-16d II-41 I THIS DWG ll-111 IF0A851 5.4-l6c IE-81 I THIS DWG IF-101 5.4-l6d lH-lll I THIS DWG IF-101 5.4-l6d IG-l0J ---KJi-----------_... ~( THIS DWG IJ-ll Vl35 Vl37 Vl36 1----{l]TH~IisJo~W~GJ1II]11[1::::::=> RV 43B r--1ILTCC:H1!;ISc.JJ.DWl!)G!__i!II~l~011___,) IF0~41 l----l[TITHillISLQDW~G[ijlij-1!0[1 ::::::> 5.4-16e IG-111 V268 J 5.4-l6c IH-91 5.4-I6c ID-101 5.4-l6e II-Ill ll.2-l
IB-11 ll.2-l

IC-21 Il.2-1

II-21 THIS DWG IE-61 K
1.

2.

3.

4.

5.
L M TYPICAL AIR OPERATED VALVE ARRANGEMENT (SEE TABLE BELOW> A/S s VENT B AOV TABLE AREA ADV (1) sov (J-3) 47A F02fl.I 47A A (l-6) 47B F020 47B B (H-3l 48A FIZl24 48A (H-7) 4BB F024 48B B (E -4l 49A Frzl22 49A CE-7l 49B F022 49B B CG-3) 50A F023 50A CG-6> 50B F023 508 B KUC 5A SB 5A SB 5A SB 5A 5B ALL INSTRUMENT AND EQUIPMENT NUMBERS TD BE PREFIXED WITH "2WCS-" EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN. G.E. IDENTIFICATION NUMBERS ARE SHOWN IN SQUARES ITO BE PREFIXED WITH G361. NO FLAG SHOWN ON CORRESPONDING DOCUMENT. COORDINATES PROVIDE INTERFACE LOCATION. SEE TABLE FOR TYPICAL AIR OPERATED VALVES ARRANGEMENT THIS DWG CM-4l. MILLIPORE FILTER HOLDER AND ASSOCIATED TYGON TUBING AND CONNECTORS ARE TEMPORARILY INSTALLED ONLY WHEN SAMPLING OF THE PRECOAT CONDENSATE RETURN IS DESIRED. FIGURE 5.4-16f N REACTOR WATER CLEANUP SYSTEM NINE MILE POINT NUCLEAR ST AT I 0 N - UN IT 2 SCRIBA, N.Y. UPDATED SAFETY ANALYSIS REPORT 1 2 3 4 5 6 7 8 9 10 11 USAR REVISION 25 OCTOBER 2022 _J
.I B c E F TOM:ACiOR. lll'ECIAC PuMP"' 2 REACTOR F"E.EDWATER RETVRN 4 RAOWA5TE,._~~~~~~~L-~~~~--. .... ~~~~--' 5'<STEM 2 3: 4 5 B I I ~! s ! NON-REGEN HEAT E'XC\\.I. r I "-.... RE!IC.C.W t.._ _______ __., I *** CLLto..1.1-UP F'"IL'T~Q.1 t C>E.t..tli..IE.A.Al..1 ZEQ.. UN17.. A" I I 'Fcv~ I I r- - I I 'i/ I I 11119-----t*****m~~')-******************j ~*-**.. --..... I \\. 13 I 13A @.J '--/ I
*~~}-- ------------omoj *---.... --......
FROt'I UN\\T "?." I I L_ I \\ I I CLH>.N-UP FILTH I ( 0£~~~:~~.~7._JE~ TYPICAL OF 2. SEE REF I 12 G33-1030 NOTES :
1.
POSITIONS 28 & 29 INOICATE CLE.foNUP C<N>ITIONS \\o/ITH VARIOUS R8CC\\ol INLET TEMPERATURES.
2.
fOR BACKWASH & PRECOAT fREQUENCY SEE !>UP 3. 3
fOR DET A I LS ON fl L TER & DEM I NERALI Z ER SYSTEI' SH PROCESS fLC)ol DIAGRAM flLTER/DEMINERALIZER REf. I DR 2.
4.
VALVES ARC SHOlot< IN THEIR NORMAL OPERATING POSITICJI.
5.
fOR DETAILS Of THE REACTOR VESSEL BOTlOM DRAIN C~ECTIONS SEC SUPZ.
6.
THE MAXI-ALLOWABLE PIPE fRICTION DROP fOR THC SIZING Of' THE CLEANUP RCClRCULATION PUMPS' SUCTION PIPING fROM POSITIONS I THROUGH 4 SHALL BE CONTROLLED l!'I' MOOE "I!" ANO THE NPSH SHALL NOT & BELOW THE MINI-AS -* MOOE "A" SHALL CONTllOL TH[ SIZING OT THE DISOIAllGE PIPING ANO THC MAXI-ALLOWAl!LE PIPE fRICTION.DROP AS SH<MN St40UlD NOT BE EXCEEOEO.
7.
fOR DATA PERTAINING TO -AS lllTHIN HEXA(OQNS, REfER TO PROCESS DATA
a.
MOOC "A" DCSlr.11 BASIS fOR HEAT EXCHANCOCRS ANO NO fLOW IS REQUIRED AT POSHION 16, 17, 21 'RI.I 27.
9.
l'CX>E "I!" DCSlr.11 BASIS fOR MAIN CLEllN-IJP PUMP (MAX. CAPACITY. AK> MIN. NPStl) ANO SIZING Of' MAIN ~ SUCTION PIPING. NO fLOW RCQ'O IN M0DC "I" POSITION 8 TIMU 15 l 21 THAU 29. 5ffERENCE DOCUMENTS
1.
Fl L TER/OEMI N SYST[l4 P&I O------------------G36-1010
2.
fl L TER/DEMI N SYSTEM P.O------------------G36-1020 SOURCE: 0016540001122E FIGURE 5.4-17 REACTOR WATER CLEANUP SYSTEM SHEET I OF 3 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT 5 7 B 9 : USAR REVISION 5 OCTOBER 1993
( ) MOOE A LOCATION 0 FLOW GPM TEMP. F* MAXIMUM PRESSURE DROP NORMAL OPERATION 63 420 "103 "103 "103 534 534 534 534 534 FOTEH~ 45I 451 534 535
-17'l**TOH 8
10 "103 715 715 687 535 233 233 120
10-*

--10--*
R.S.S. 1035 PSIA <SEE NOTES 1, 3 ANO 5 OF PROCESS DIAGRAM> 12 13 15 I6 I7 18 I'l 20 21 22 23 24 25 26 343 343 687 816 816 I20 120 120 438 438 438
--5'l--*

--10--*
ALLOWABLE PIPE FRICTION DROPS <SEE NOTE 6 OF PROCESS DIAGRAM> 27 28 2'l 1434 154 PSIO 30

- ---------------------------- - - - --- - ------ - --------- - --------------------- 10 --

MODE B HOT SHUTOOllN OPERATION IW!TH LOSS OF RPV RECIRC PUMPS> LC~ATION 0 FLOW GPM TEMP.F* MAXIMUM PRESSURE DROP 162 'l8 358 358 358 358 358 540 545 543 543 543 543 544
-1'10-*TOH JI)
R.S.S. 1003 PSIA <SEE NOTES I ANO 6 OF PROCESS DIAGRAM> IJ I~ 17 16 l'l ZI 26 (1<) 358 358 358 358 358 546 546 546
-162-*
ALLOWABLE PIPE FRICTION Of!OPS <SEE NOTE 6 OF PROCESS OlAGRAMl PSIO
.. --.. - --------------.............................. _........................................................................................... DELTA P...................................................................................................................................................................... i............................

A> PROCESS DIAGRAM 10505408 SHALL BE USED WITH & FORM PART OF THIS PROCESS DATA. IF THERE ARE ANY CONFLICTS BETWEEN THE PROCESS DIAGRAM ANO THIS PROCESS DATA. THE PROCESS DATA SHALL GOVERN.
Bl THE I INDICATES CONDITIONS FOR 0 FLOW RATE. C> SEE PARAGRAPH 4.2.3 OF 22A2816 FOR STARTUP PROCEDURE. E> DURING HOT STANDBY. WITH ONE CLEANUP PUMP ANO TWO FILTER OEM!NERAL!ZER UNITS IN OPERATI ON. SLOWDOWN RATE AT 545' F APPROX 126.0 GPM. Fl DURING MODE A. Two* CLEANUP PUMPS IN OPERATION. DURING MOOE B. ONE CLEANUP PUMP IN OPERATION. Gl POSl'TION 28-COOLING WATER FLOW TO NON-REGENERATIVE HEAT EXCHANGER NOT TO BE EXCEEOEO BY MORE THAN 67. OF THE V"LUE SHOWN. H> ALTERNATE OPERATING MOOE WILL INCREASE FLOW TO 700 G.P.M. AT THESE NODES. THIS DRAWING CREATED ELECTRONICALLY FIGURE SOURCE: OWG. NO. 001654000!l06 5.4-17 REACTOR WATER CLEANUP SYSTEM SHEET 2 OF 3 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR RE VISION 9 MAY 1997
c.. D E H J L I 1 2 3 5 6 7 I J1 B 9 10 I 1 1 I 1 2 1 2 DESIGN PRESSURE & TEMflERATURE Gl\\£N EELCW IS f"OR INFORMATION ON..Y AN> IS Tl£ BASIS f0R PIPING c£51Gfl. ESTIMATED LI~ SIZES ARE F"OR INFORMATION Olt.Y. ACTUAL Lit£ SIZES AS DETERMl~D BY Tl£ PIPING DESIGt-ER SHALL ~ET Tl£ PROCESS DATA HYDRAULIC REQUIRE~NTS. LOCATION 0 1:-1A* 1A-18.. 1C-1D 18-1E 2A-28 28-SA 5A-6 7-7A 7A-8 9-10 DESIGN PRESS, (PS IG} 1250 1250 1250 1250 1250 1250 1250 1410 1416 1410 DESIGN TEM,P. (DEG. Fo) 575. 575. 575. 575. 575. 575. 575. 575. 575. 575. ESTIMATED LINE 2.0 2.5 1.0 4.0 4.0 6.0 6.0 6. 0 6.0 6.0 SIZE (INCHES} LOCATION 0 13A-33A 27-338 15-21A 21A-20 DESIGN PRESS, (!'SIG) 1410 1410 1410 DESIGN TEMP. (DEG. r*J 1~. 150. 575. £ STI MA TED.LI t£ 8.0 8.0 8.0 8.0 SIZE ( INCt£S) ALL AUXILIARY PIPING IS DESICH:D TO 150° PSIG, 150. f 0 oLOCATION 1A IS Tl£ POINT Wl£RE Tl£ BOTTOM DRAIN Lit£ CONt-ECTION EXITS FROM Tl£ C.R.D. HOUSING AREA.
LOCATION 18 IS THE POINT Wt£RE Tl£ BOTTOM DRAIN Lit£ CONt-ECTION EXITS FROM THE REACTOR 1£S:E:L flEDESTAL.
ro SA.to£ CQN)ITIONS AS T1£ FEEIJWATER PIPING (BY OTHERS) 2 3
I 4 6 7 I T' I B 9 1 0 11-118 11A-1S8 11-B-13A 13A-14 1~10 1410 1410 1410 150. 150. 150. 150. 6.0 6.0 6.0 8.0 FIGURE 5.4-17 REACTOR WATER CLEANUP SYSTEM SHEET 3 OF 3 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT I 11 12 I
. _) THIS FIGURE HAS BEEN DELETED FIGURE 5.4 -18 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 0 APRIL 1~89
L VES')El HEAD DRAIN VENT' UNlT,.B' ~-i--~---~---~~-+-~c.e AIR. li!EAC.'lorl.V.V."1'52 t-------.,------r-1--t-,..._ ___ CONDENSATE 18 o..eAN-u>l=IU'ES2. oeMINE.IC!AU~ UNllA l='ILTEK /DEMllJEl:::AL17Et BACKWASH $ l'l!ECDATlhJb SEQIJHICE - SEE NOTE ~ rul'.J(TIOtJS SERVICE ISOLATE l HOLD 0£PR'ES5UKIZE DOME D~l..i AIR PRE.SSURIZ.£ I'" Alt BUHP t DJ:AllJ FILL t VHJT DOHE D~Al>J AIR PRESSVflZE 211DAl!t BUMP t l>iAlll BACrWASN / Dl!AUI F'ILL t VfAJT SOLKA fLOC fRHOAT RESlllJ rJ:ECOAT HOLD f"l'.HOltT HOLD UllTIL RETVRIJ TO,fr:VICE ~ERVICE {j)@ © r:!J (]) @ill ©@ ill G) (!) <D PRElDAT PUMP TA6L!: "I F/O AREA* ~7.FTa SERVICE ACT VE REACTOR WATER + kA RESIN RESIN WATER + c~ o.io~ WATER + F/O RA010* REACTOR ~S + CNOS + CONC REACTOR REACTOR CNOS AIR AIR WATER ~IDS sl: y SLURRY SLURRY sbe1os OR CNOS SOLIDS CNOS (NOS @ © ~ @ PRESSl.flE,PSIG ~~1<~ 110 80 80 80 100 ~ 100 0-100 ~ 40 0-100 ~ -40 ~~~~ 0-'lO 40 40 1-T-EHP_E_RA_Tu_R_E._*F--1* ~ - 111 - eo ea eo eo ~ oo 1i.o n.o eo eo eo uo eo ao ~10 eo eo Bo ~ ~ ~~~~~~~~~~v~~~~~~~~~ ~~~~~~~~~~~~~~ FLOW TIME, HIN. 3.15 l 0.7 2 5 Z. ?. O.' 10 30 30 OS 30 0.7 10 ~6Al..37S'&Al TOTAL LBS, SOLIDS l!fSID!IAl RESIDllAl TASL~Il © © @ ©@ ~ @ @ @ @ @ @ @ PRESSLflE.PSIO ~~ HO l!O 80 80 100 !I 100 0*100 40 40 OrlOO 40 40 fv~£M 0*20 (\\() 40 1-T-EHP_E_RA_T_UR_E._*F--i ao eo eo so oo "° no 120 ao eo ao so ao eo 'Wo't1:> eo ao eo 49 ~ 25 GPM 41il8 GPM 4119 GPM 54 SCF~ 52 SCF~ ~ GPH ~~GP> 138 GPM 290 GPH 1.5 GPH ~GP> 138 ~ 21!11 GPH 65 GPM 400 GPH 138 ~ 130 GPH FLOW TIME, HIN. 315 z 0.7 I.~ ~ 1.4 3 a.6 o 30 30 OS 5 30 o 1' 10 5 45 GAL 375 26 RESIDUAL RESIDUAi.
= '5EE. N.OT'E. 1.
TABLE m ~/O AREA
I" FT'I.
© © @ © @ @ ill @ @ @ @ @ @ @ @ @ I\\ K l\\... K 80 80 BO 80 IOO !I 100 0-100 40 40 0-100 40 40 ¥V~~H 0*1.0 40 40 TEMPERATURE. *F ~ ~ 60 80 so so G.O IOO 1'2.0 l'l..O 80 eo BO 80 eo 80 fro10 ao 80 ISO... 1-F-LO_W_R-AT-E __ _,.v; 1).... 40GPH 25 GPH 560 GPH 560 GPll 54 SCF~ 73 SCFM ~ GPH ~~:~ CP!o 179 GPH ~0 GPH 2 GPH ~~:~ CP~ 175 GPH 250 GPH 85 GPH 5~ GPM 170 GPH 175 GPH PRESSl.flE,PSlG FLOW TIHE,HIN. 315 'l.5 0.1 1.0 3 1.0 '3 0.5 10 Mill 30 HIN 31! HIN 0.5 ISOGAlGOGAL 350GALS50GAl "25Cf 73 5Cf 17SG"1.. 375G4l. 61 GAL 375 3f0GAL
~EE NOTE 2.
NOTES' I. f'OR THESE. \\IA.UJ£S I& REMAINDER Of S'ISTE.M VALUES: SEE. REACTOR ~ATER CLEANUP SYSTEM PD
2. DRY WE 1.GHT VALUES FOR 'RESIN,AS AS SHIPPED RESINS COHTAIN 50%
MOISTURE ( APPROXlllhA.TE) 3.NORMAL BACl<lt'llASH-PRECOA.T FREQUENC'I 15 EACH VESSEL C.\\IERY (g-1401'1'15. aEs!OllAl - SOURCE: 0016.540-01211-12127 REV. c FIGURE 5.4-19 FILTER DEMINERALIZER SYSTEM NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 15 OCTOBER 2002 _J
00 900 180° 270° 360° 428" I I I a AC
u.
UJ CD CD CD 366.31 '~ --- - SHELL 2 C3065-l C3121-2 C3147-1 ~ BELTLINE 277.25'_.' ---~-L--------.-----'--------.--__._ __ AB SHELL 1 216.31':_ - <{ CD C3066-2 CD CD C3065-2 u CD C3147-2 126.5'_.' ___ AA
FROM INSIDE BOTTOM OF RPV FIGURE, 5.A-1 lBELTLfNE WELD SEAM AND l
-Y' --- --~ - -- -~ ----------*-
1
, PLATE LOCATIONS*. NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
MTP-10 FINAL WELD PREP OR MTP-11 BACKGOUGE MTP10 FINAL WELD SURFACE MTP-10 AFTER PWHT RTP-8 AFTER UTP-50 FINALPWHT CENTERLINE SPECIMEN CODE NO (SEE SLAB DET FOR SPACING) CENTERLINE 1/8 SAW CUT (TYP) I.. 30° WELD DETAIL (WELD PER WPS 323 2F4F6) 6-7/16 3-25/32 ---~
w1t1J5":1-72.c102 2 1/
P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 L 8-5/8 .. I SUB-BLOCK ((WELD-1) FIGURE 5.A-2 w en o=> 01- -o z 15° 1/2 <D ----- 5/8 5/8 1/2 SURVEILLANCE SPECIMEN WELD JOINT DETAIL* AND WELD METAL CHARPY SPECIMEN LOCATIONSi NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 14 FEBRUARY 2001}}

ML22292A089

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