ML22292A089
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{{#Wiki_filter: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 10 6 425.3 403.4 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 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) (a) (a) (a) (g)
- 1. Core Inlet 1,080 108.5 534 528.9 (a) (a) (a) (b)
- 2. Core Outlet 1,048 108.5 550 656.2
- 3. Separator Outlet (Steam (a) (a) (c) (f) 1,035 17.6 549 1,190.6 Dome) nd (f) (a) (h) (f)
- 4. Steam Line (2 MSIV) 1,009 17.6 546 1,190.6
- 5. FW Inlet (includes RWCU (i) (g) (g) (g) 1,069 17.94 440 420.0 flow)
(a) (a) (a) (a)
- 6. Recirc Pump Suction 1,036 33.12 534 529 (a) (a) (g) (g)
- 7. Recirc Pump Discharge 1,314 33.12 535 530 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 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
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* *LT 112 )--, 2. GENERAL ELECTRIC IDENTIFICATION NUMBERS ARE SHOWN AB> , l.IAG> \JAG> 8Y1 IN SOUARES.
7 ;;i Jl* IBY>
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--- 101 ) . ---------' qe
~---- .... -- 118
~---- 1--- (8Y) ""
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~ ~
- 2*1SC*750-217-21A*l VALVE CLOSED I 11~3 '*RO' 2*1SC*7!11*211*2<B*l -+--,\ '*RO" VALVE CLOSED
@:CR '---'< I'<",~:i/' , I 2311
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- *HOSE32 \. *HOSE2q I I ___________......
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~6~1 DIGITAL FEEDWATER I ITYP OF 61
~ :--------i
~ _______ -,- - _: __ ~ ~~~LA112
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.------~
LEVEL B LOGIC ________ J :________ . LEYELRllcLOGIC
~----~
[B_2_2_J RCIC
~ ~ ~ ~~-i22EI ~----~
g --------~' '
*-------- g LEVEL B LOGIC LEVEL 2 LOGIC RCIC RCIC 10 10
*o w
c-o z FIGURE 5.1-Zb NUCLEAR BOILER AND PROCESS INSTRUMENTATION 11 11 NINE MILE POINT 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 TO LOW PRESS CONN'S TO LOW PRESS CONN'S LOOP *o* JET PUMPS IN91 LOOP "B" JET PUMPS. INSTRUMENT LOOPS FOR 2MSS*PI INSTRUMENT LOOPS FOR 2MSS*Pll OND 2MSS*Pl0 SHOWN, 2MSS*P2,3,4,6, AND 2MSS*P2B SHOWN.2MSS*Pt2.13.14. 7,8 AND 9 SIMILAR TO 2MSS*PI. 16,17,18, OND 19 SIMILAR -
- LDSTC74 TO 2MSS*Pll.
I NOTE 3 IRC -ORC NOTE 3 2MSS- ~ 601559 1 I ---- ~_J ____ ~ 1 ORC - I R C
\!~l'!!IT 'CJ
~
N9 E9
° 285° r
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/
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*RO /r+-+-2-ISC-750-318-21A-> "*RO' VALVE
'I I
CLOSED J./ 130 " DIGITAL ~ 25J 25K ) I *LT r-- ----- FEEDWATER DIGITAL
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.,!A-I ,
T 2-ISC-750-311-21B-l-t-h.
.,!B-I T *HOSE33
~ FEEDWATER IBYI
)~-;~'fflliw+o[):::("*~~~~J1::::'.:=D-1~~~~~~~~~~~"-~+-i
' ...... I r~r-~"~~~~~~~~~~~~J1::::'.:=])-1~~~-{*p~*f-ffl';w.Jrl'~( I """' 1
*EFVIBIA-l *V181A-I *VlllB-1 *EFVlllB->
2-ISC-750-368-21A-l - i NSSFAl01 TOTAL FLOW 2 .rFT4BA "1----- -E91 2 r FT
',<B-I F488 T ',, 1----- -E91
~: ~
FT r---- 47J ~ 2-ISC- 750-361-21B-l I 47K )---,
- '-(A-) <A-> IB-1
.J
- -------..J 3
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CSLPC07 i ~ r---------------~--------------~------------ Q SCRAM LOGIC 603401 7 HIGH PRESS LOGIC RCSFC101 :' LOOP A LOOP B : RCSFC102 ISCBC07 ISCBC08 RPS 1 LPCS. AHR<A>,RCJC LOOP
,6_ LOOP
~L_ ~
ti~~ 1 & VAL BRKR ISOL CSLPC08 INACTIVE Fl : INACTIVE HIGH PRESS LOGIC PAH ' .r----~ RHRIBJtCJ, RCIC _J SCRAM t-___ J B2
.--------J t-___ _l_ _
~---,-~
ISCUCl2 1----~ 1 ANO VAC BREAKER 1 LOGIC L___ ' ' 1 FROM FROM 6fll34fa2 REC I RC _J_ ___ RECIRC ' ISOLATION ' Bl RPS
~
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I i _@_ !~22-1 PUMP 'A' RUNNING PUMP 'B' RUNNING ' ______ @_ ___ "' __ :' L 1--,
' V'" '
l ~ i----i;::::::::T--~ 694E 3 ' ' ' 3
~ ~
~ 2MSS*REV1CZ-I 601602
~
' C72-6500 :I ~22-1 6q4A :I I I
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- I 603401
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/*PT' *PT " /*PT r,.,py '*PT" UI -15ii-. -t7li-* -11c- B -17ii-J , -17ii-)
g' -.[BYI '(!IY I , 1::W\l_ GJ:1
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2-ISC-75B-36q-2(A-l -
*EFV191A-I *HOSE3B
_l/ *HOSE34 r-2-ISC-7511J-362-2lB-J
*EFVl21B-I ISOLATION
'---~~~~-'---~~~~-'---~~~..,.; ~-----'---------'----------' VALVE INSTRUMENT
-" EFV
" "I I -
*Vl91A-I 1 *vi2c8-1
TUBING 4 4
~ ~
VALVE VALVE 3/4'FLEX HOSE CLOSED CLOSED 1------' VA VB SC2 +NNS
------; >---@---~--~!
______________________ J _____________________ _
----4 1-----4 l----------------------L---------------------- <-----------4 DETAIL I MSSTC07 lii?2q"l ITYP OF 81 TYPICAL TEST VALVE ARRANGEMENT 602235 ~ ~ SEE CHART I
@----J----@-:
ID-101
<-----------4 NOTE:
5 ITYP OF 81
.---- 21SC*V81.83.B4.& 86 SHALL BE ORIENTATED WITH THEIR DIRECTION OF FLOW ARROWS 5
~w OPPOSITE TO THAT SHOWN IN DETAIL 1
- SEE CHART I '
ID-101
I JET PUMP r--r--- r--r--- ~-e------4 1-------------------c
CHART II 1- ©
/FT " FT 2MSS*Pl0 ~ ~
L L
-47_A_ i -48c- }------,
t--
EXCESS FLOW TEST VALVE NUMBERS e-9--]
],_ )!'..( ,IQ..( b._ b._ CHECK VALVE 6~6~~01
<A-l IA-> I I 2- ISC- 75111- 381-2(A-) 2-ISC-750-340-21B-I -+-+-> 2-ISC- 750-363-218-1 NUMBER VA VB
~ ~~
.-++-2-ISC-750-331-21A-> *EFVlllB-l *V1071B-l *V10'l!B-l
- ' - ' 7 *RO HIGH PRESSURE CONN HIGH PRESSURE CONN r *RO ~
V L---------; 1------1 1------1 1-- *EFV181A-l *V1061A-l *V1081A-l
' ' 25R FOR CALIBR FLOW FOR CALIBR FLOW TRANSMITTER OF 25S )
TO POST
*EFV251A-l
*EFV26<A-I
*V'l01A-l
*V'l4!A-l
*V'l21A-l
*V'l61A-l
~ Il ~A-J ,1 TRANSMITTER OF ~B-l ACCIDENT
. 1----- .
r----- *EFV311A-I *HOS T JET PUMP JET PUMP T _/ *EFV401B-I 1----- ----- SAMPING SYS
*EFV271A-l *V'l81A-l *V100!A-l 2MSS*Pl5 *HOSE35
.FC .. .. . -
*EFV281A-l *V1021A-l *Vl041A-l
< 11.B.3-lo IA-51
.FC \ _ *Vl931A-I
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, ,.,,, I
*V311A-I I I f-ir-..l..~~~..;;;,;;;,;;..;.;;;.,~~~~~J1::::'.:=])-1~~~~-i:P~:f-ffl,;w.J.""~(]!ii():~~~
1 *Vl941B-l /'Fe II.B.3-le tA-6> > *EFV2'l!A-l
*EFV301A-l
*Vlll'JtA-l
*V114tA-l
*V1121A-l
*V1161A-l TO POST ACCIDENT '*sov ' *V40CB-> I I *EFVJl(A-1 *V1181A-l *V1201A-l 6
SAMPING SYS
*SOV' 123 119
<AG>
~ ~ /*SOV
*EFV321A-1
*EFV331A-l
*Vl221A-l
*Vl261A-l
*Vl241A-l
*Vl281A-l lAY> VALVE VALVE 120
~
*EFV34!8-l *V'll!B-1 *V'l31B-l
§ CLOSED CLOSED IBYI
*EFV35!8-l *V'l5!B-l *V'l71B-l 2-ISC-750-324-21B-> -+--+-. *EFV36!8-l *V'l'l!B-l *V1011B-l GD 2-ISC- 750-373-21A- I 2-ISC-750-374-21B-> ~
CL2-*NNS *EFV3718-I *Vll9t8-l *Vl21t8-l
.-++- 2-ISC-750-323-21A-I *EFV3818-I *VllltB-l *Vll318->
~l 8 HIGH PRESSURE CONN HIGH PRESSURE CONN FOR CALIBR FLOW r *RO 24D )
1l12 )
, ~ '-
~ *EFV3'l!B-I
*EFV401B-l
*V115t8-l
*V831B-l
*V117t8-l
*V811B-l
'f 2-ISC-500-401-2 C FOR CALIBR FLOW I TRANSMITTER OF TRANSMITTER OF .,!B-1 ,....._, 1 "--2-ISC-500-402-2 *EFV4!1B-l *V1231B-l *V1251B-l
*EFV231A-> *HOS T JET PUMP JET PUMP 2MSS*P20 T _/ *HOSE43 *EFV241B-I *EFV421B-l *V1271B-l *V1291B-l
*EFV121B-l *V751B-l *V771B-I
- i:::-:>-_;:""'f-/H/,'fjo~~~~-Cr::'.:JD-~~~2M~S~S~*~Pl:0~~~~~....I~-+.,
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1 1
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- T" I I r~....i..~~..;;.;;;,;.;.;;,;._~~-<I1::::'.::J1~..;;;.-~*(MTM*w-1""--<"'""~.--~---'~~~~~~~~~~~~~~~---' *EFVl'l!A-l *V741A-l *V76!A-l
© I r ~* I ~ -
*EFV201A-l *V801A-l *V821A-I
*V231A-I I *V241B-I *EFV231A-I *V861A-l *V841A-l
~ VALVE
*EFV131B-I
*EFV241B-l
*V103tB->
*V851B-l
*V10518-I
*V871B-l VALVE
/ CLOSED *EFV141A-l *V1341A-l *V1361A-I 7 CLOSED *EFV211A-l *V1301A-l *V1321A-l 7 TO HIGH PRESS CORE *EFV2218-l *V1311B-l *V13318->
SPRAY SYSTEM l2CSH*P011091 2-ISC-750-371-21A-I 6.3-S. IF*31 TO CONTROL ROO
~) *RO 20A 2-ISC-750-321-2107 1 5.1-2e IA-61 > NOTES:
..\l_
...!A-J I.ALL INSTRUMENT & EQUIPMENT NUMBERS TO BE PREFIXED DRIVE SYSTEM ..I WITH '21SC-' EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN.
12RDS-PDTll4,ll 71 *EFV211A-I *HOSE4111
' T ( 2. GENERAL ELECTRIC IDENTIFICATION NUMBERS ARE SHOWN 4.6-5b IJ-51
- Ir-. I I I IN SOUARES.
*V211A-I 3. CONTAINMENT ISOLATION DATA !FOR LOW PRESSURE CONNECTION!
FOR JET PUMP INSTRUMENTATION OF NOZZLE N-9 ARE LISTED NSSPAl01 ~ 2-ISC- 750-364-2CA-J ON CHART hlSOLATION ARRANGEMENT SHOWN FOR FT47JIA-I IS TYPICAL. TO REACTOR WATER VALVE -z 4.HIGH PRESSURE CONNECTION FOR ALL NONCALIBRATEO FLOW v~---~---i f1~!- CLEAN-UP SYSTEM CLOSED ' 7 TRANSMITTERS 21SC-FT47'S WILL BE FROM LINE NO. 8 12WCS-FTl341
' 2-ISC- 750-372-21B- >
2-ISC-750-314-21A-I -~\ /*RO 112 ) ~I ~ 21SC-750-372-21B-> FOR RECIRC LOOP "B" AND 215C-750-364-21A-> 8
< 5.4-16" 11-8>
IZ-1 " IA-l FOR RECIRC LOOP 'A'. Ir;\3.!_3 *Ro ' .... I _,,_/ *HOSE36 EF:'._1 4 IA-I REMAINING 21SC-FT47'S 5. FOR S&W AND GE DESIGNATIONS SEE CHART I.
~ ~ -\l_
~Bq-3) I 20B 2-ISC-750-322-2<BB7> ~~~~~~~~~~~~ ~~~~~~~~~~~ ' ' ~---.------'--------;: RECIRC LOOP A 6. SEE DETAIL I FOR TYPICAL TEST VALVE ARRANGEMENT FOR
- 1 NOTE 4 & 5 EXCESS FLOW CHECK VALVES.EFV ANO CORRESPONDING TEST "B-J ..I VALVE NUMBERS ARE LISTED IN CHART II.
*EFV221B-I *HOSE41 T ' 7. SEE CHART III FOR INPUTS TO SUMMERS.
REMAINING 21SC-FT47'S RECIRC LOOP B ._j__~~~~r--~~~*~*~-cLD-~~--'----JL.....,.:::-~ I I I ~ NOTES 4 & 5 i -- '*V22(8-J I ' ISC-15111-400-JCZ-J VALVE CLOSED
' i
~ i VALVE CLOSED i **
9 9 I CHART I I JET CALIBRATED JET PUMP INSTRUMENT NON-CALIBRATED JET PUMP INSTRUMENT LINE NUMBER LINE NUMBER EXCESS FLOW CONTAINMENT I PUMP LOOP INSIDE CONTAINMENT OUTSIDE CONTAINMENT PENETRATION *HOSE ORIFICE RUN CHECK VALVE ISOLATION
!LOW/HIGH PRESSURE CONNI !LOW/HIGH PRESSURE CONNI NUMBER NO. NUMBER CHART 111 2MSS*P S&W MARK NO. GE !DENT NO. S& W MARK NO. GE !DENT NO. 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
------------ -------- 2MSS*P TRANSMITTER GE !DENT NO, GE !DENT NO, 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 4
5 A A 21SC-FT48A!A-I B22-N033A 21SC-FT47GIA-I 21SC-FT47JIA-I 822-N034G B22-N034J 2-ISC-750-32'l-21A-I 2-ISC-750-318-2<A-I 2-ISC-750-37'l-21A-> 2-ISC-750-368-21A-l
,. 1307-10 1307-14 48 37
*R025LIA-I
*R025JIA-l
*EFV2'l!A-I
*EFV18<A-I
*V2~CA-l
*Vl81A-l 1 FT47A B22-R608 B22-K601A NSSFA102 6 A ------------ -------- 21SC-FT47LIA-I 822-N034L 2-ISC-750-325-21A-I 0
...J 2-ISC-750-375-2!A-I 0
...J 1307-'l 44 *R025A!A-I *EFV251A-l *V251A-l 2 FT47C B22-R608 B22-K601A NSSFA103 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 3 FT47E B22-R608 B22-K601A NSSFA104 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 4 FT47G B22-R608 822-K601A NSSFA105 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 5 FT47J B22-R608 B22-K601C NSSFA106 10 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-> 6 7 FT47L FT47N B22-R608 B22-R608 B22-K601C B22-K601C NSSFA107 NSSFA108 .. 10 1Iii 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 5 A 21SC-FT48AIA-l B22-N033A
------------ -------- "2-ISC-750-331-21A-l u
lJ "2-ISC-750-381-21A-l u - lJ 1307-17 50 *RD25RIA-l *EFV311A-l *V311A-l 8 q FT47R FT47T B22-R608 B22-R608 B22-K601C B22-K607A NSSFA10'l NSSFA110 0 z 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 10 FT47V B22-R608 B22-K607A NSSFAlll 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
------------ -------- 11 FT47B B22-R608 B22-K601B NSSFA112
,. 5,l-2c 21SC-FT47F!B-I B22-N034F 2-ISC- 750-336-218-l 2-ISC-750-386-218-1 1306-13 *R025Fl8-l *EFV36!B-l *V3618-l 13 B 55 14 15 B
B 21SC-FT48818-I 822-N033B 21SC-FT47Hl8-l 21SC-FT47KIB-I B22-N034H B22-N034K 2-ISC- 750-313-218-l 2-ISC-750-311-218-l 2-ISC-750-387-218-l 2-ISC-750-361-218-l 1306-16 1308-7 56 33
*R024Bl8-I
*R025Kl8-I
*EFV1318-l
*EFV1118-I
*V1318-l
*V11<8-l 12 13 FT470 FT47F B22-R608 B22-R608 B22-K601B B22-K601B NSSFA113 NSSFA114 FIGURE 16 B ------------ -------- 21SC-FT47MIB-l B22-N034M 2-ISC-750-338-2tB-l 0
...J 2-ISC-750-388-21B-l 0
...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- 750-341-218-l 2-ISC-750-3'll-21B-l 1308-'l 60 *RD25Ul8-l *EFV4118-l *V411B-l 17 FT47P B22-R608 B22-K6010 NSSFA118 20 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 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 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 l'l FT47U B22-R608 B22-K607B NSSFA120 u u 20 FT47W B22-R608 B22-K607B NSSFA121 PROCESS INSTRUMENTATION 11 11 NINE MILE POINT NUCLEAR STATION UNIT 2 SOURCE: PID-28C-12 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
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 4 BYPASS VALVE FLOW _ _-t 300.0l-_ _ _ _ _ _ _.::....:;:.;.:..:;:,;;:;;:...:.:;-.;.,:;;..:...-.;;.._ 0 <[ 100.0 200.0 a: LL ...z 0 "'ua: "'e, 50.0 100.lll 2 0.00.0 5.0 0.00.0 10.0 TIME (SECONDS> TIME (SECONDS> 1 LEVEL ClNCH-REF-SEP-SKRTl 2 VESSEL STEAMFLOW 3 TURBINE STEAMFLOW 4 FEEDWATER FLOW 200.0 1.0 0
"'...z 4 100.0 "'0z Q.
0.lll
- c 0
u E u
<[
~ -1.0 0.0 2
-2.0L-----_;u...-~---------;:
-100.0L--------~
0.0 5*~0 --------~10.0 111.0 TIME (SECONDS> TIME <SECONDS> FIGURE
- Bosed on o representot1ve equ1brium fuel cycle.
SAFETY RELIEF VALVE CAPACITY SIZING TRANSIENT "MSIV CLOSURE WITH HIGH FLUX TRIP" NOTE: For c~le-apec1f1c re~lta see
~ix A, $1wt1on A.S.2.2.2.3 NIAGARA MOHAWK POWER CORPORATION I
SOURCE: NEDC-31994P THIS DRAWING CREATED Ei.ECTRONICALL y NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995
MAIN STEAM FLOW RESTRICTOR SUPPRESSION
-~--~'--
POOL FIGURE 5.2-2
- SAFETY RELIEF VALVE SCHEMATIC ELEVATION
, NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
MAIN STEAM ISOLATION VALVES DRYWELL S/RV S/RV REACTOR VESSEL S/RV I' . FIGURE 5.2-3 SAFETY RELIEF VALVE AND STEAM LINE SCHEMATIC NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
2 3 4 5 6 7 B g 10 1 1 12 13 TAB.Et SAFETYAIELIEF VI.Lii[ surrix ASSIGNMENT Al'll ASSOCIATED EOLA.tENT SAFtTTnELD' FO\H rou-1 ro1l-$ rou-2 rou-2 rau-3 tOU*l rou-~ rou-2 ro13-4 rou-* rou-* rou-~ rou .. 3 1 O£ca r0l6 NOICS VALVE FC..OtMW tSUPPt. DOC . ' $HALL er USCD WITH AND roitw A PART°' 1KIS PAID DAU. . 'I' TH[R[ AR[ ANY CONf'l.M:15 8£lW([N TH[ PtlD A.NO lNS P*O OAU, THC P*JO DATA SHALL COVUIN
, . WPt. NO.'S ARC PttHIX(O av 822 UNL{SS 01t1(RWfS( N01(0 J . W.UUUV(l tt$UIUMCN1S fOR VARIDUSftAHGts AR( CAU8RAICO AS SUTCO snow. AU WAlCA L(V(L SWHCH 5£1POIHJS AR( NOMmAL.;
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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
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~~ 2 i--)- ------ ----------1--";.;;.o__+-=..;;...--l
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SOURCE: 761E445AF - 07
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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 -+--1--+----1------~ RRCSISUPPLDOC.6.tc11 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 - - - - - + - - - - < - , - + - plS N67~0 l PISN618"'- I r-;- ~. ----+--:NS-41A-l,...,,IRHR-:-'.:"ISOl:-I----! J LIS N6!UB,r AOSIBI / RHRl81 / RhR ICI 2 PIS N6 l 8B~-~7ff5-,--*- 2 lSNH2B,( f----+--2-+-:-l--:-::-~-:--+-~-------I 1-----1---:-1--:-*-+>---:.;-~--::~ ~~:;: ::R ISOLI 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 PRESSURE AT 3.1 BARS DIFF (45 PSIG) I SATURATED STEAM ENVIRONMENT
--1 1
w a: :i:z (.!) u- :;
~ <t Cl) w u u
<t w:::l I-0 0 a:
w a:W I-z > u u>
- i...J 0
"'~
w 0 u.
<>. OU > > 00 w :i: ti iii
- <u "' <OM o-I- 1--
Cl) ** <tO (.!) z ~ -(.!) a:
-w Cl) 1-> Cii (.!)
z <.!lz z-
<t"' ::i u u
- u. I-(.!l:::lU w~ w Cii
- i 0 8 0
-Cl)
Cl)::> zzO
...J(.!l ...J u w > > ::>Cl)
WW a:~ ct.
- loo
~~
U(I) u
...J u "'
~ "'
~ "'
~
...J ...J uo o-- -:::> >-
u >- >- 171°C (340°F) (.!) z (.!) z (.!) z uu
-N 160°C (320°Fl Cii Cii Cii w w w
~
...J ...J ...J u u u u >- >-
*u u
I TEMPERATURE WILL RISE FROM AMBIENT TEMP TO 111°c (340°F) IN 5 MINUTES I 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 I PRESSURE TURBINE RECIRCULATION PUMP CLEANUP PUMP 0 ROD DR'"'
FEEDWATER COOLING WATER 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) Ec. _g. UJ 10 Cl a: 0
..J s.,,
I (.) 0 5 I&. 0
....cC
- E (J --soDIUM 0 HYDROXIDE
- c
- E (Na OH) a
~
1.0 ui (J z
....(JcC
- > CHLORIDE (ppm)
Q z 0.03 0 (J (J ii: uw 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 Ea.
.!!) 40 LU 1- <I: ex: ~ <I: LU ...J 20 15
*AXIALLY ORIENTED CRACK
*SATURATED WATER SYSTEM AT 1000 psig 10
*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 Le= CRITICAL CRACK LENGTH (in .) 9 11 D =MEAN PIPE DIAMETER ah = Pl PE HOOP STA ESS MATERIAL* A1064 10 10 9 12 8 0 Lc/D =15,000/crh Ln 7 M I 0 0 15 x x ef c
~
6 5 20 4 25 0 Q GE DATA (-60°F) 30 3 Do O 0 BMI DATA o~ 40 50 60 70 0 .0 . .- - - .2 - - - - -0.4
------ - - - - - 0.8 0.6 - - - - - -1.2
- - - - - -1.0 - - - - - -1.4
------ - - - - -1.8 1.6 -
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]
, _ _ - - -- - - - - - - I S . 3 8 Mlf.J - - - - - - - - t - - - - - +- l . 51i> MAX 2 PLACES 3 .41 MAX .
I l]J2~iN 1.0~ I ~1_ . , _ . . _______________ _ f--------------~~---DM~---------------1
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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 RTNor 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 TOP FUEL GUIDE SHROUD HEAD CORE S P R A v - - - - - - t SUPPLY HEADER FUEL ASSEMBLY SHROUD HEAD 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 TRIP, L8 = 583.0 in . NORMAL WATER . 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, L1 ,;, 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" SELECTOR SWITCH 'flESTRICTED MODE" IN "IORM" PDSITIDN 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 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 2J"CASIC" THIS POS(Tl(Jol WILL ALLOW UH-RESTRICTED QPEJIATICl\I OF #ILL HOIST IN All 3l"BYPASS" 9r1ds! Tro.*I RHtrlc\lon AREAS m:' TtE STATION. THIS llCLLOES lHDSE AREAS OF TtE S?EHT F\EL
"*th \h* troll9\,t 01. *1V- .,.... af br1dgll m-.d w1\h irollq STORAGE ANJ CASK LOADING POCL.
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 r r - *1V- dlr*iilnan .n1i:ih *Ill PG91llan *J 111*111 '-* TRAYEl. WJLL BE AS FCl.LDWS.tSEE PLAM VIEV 1U
...... ""- 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 "'-
o.nt.- af _ _ ..,.. awu . . ta ..._ , , . _ * - - of' the
,...,, *Ith the D9"\ar- h,,. *( hook* at. ~ ..,,,. af
- 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 r'-trlO\.!d . . . . . and *IV> br1dg! prO*l*l\y **It.ch 1n 1.r'lpp!d Trallty T,.,,.J Reur-1pt1an 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 _,.. ***'°'
-t.1-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 - -
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 at. Cpcnnt. Bl ar V.. cuk lcuu:f1ng poc1L TO RESTORE THE CRNCE DPERATlCIH MCI RESl.K MOTi'" WITH THE SELECTOR 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 ARtA SHEET 2 OF 2 NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT 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
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-I 1--~ 1. ALL INSTRUMENT & EQUIPMENT NUMBERS TO BE PREFIXED 2RCS-TKSB I I 602220 I L. 0. ~"~~~~--~~----~ 86B ~ITH "2RCS-" EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN.
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REACTOR 3. NO FLAG SHOWN ON CORRESPONDJNG DOCUMENT. I I RECIRCULATION C001 B NBE 87B ,__ _ _ __ NBEX NBEY COOROINATES PROVJDE INTERFACE LOCATION, I _.1.. RCSLA0* I 9.2-3b !C-71 "'"'w MOTOR c 1 .c2 86B 86B
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TITLE, FLOW DIAGRAM REACTOR COOLANT (RECIRCULATIONJ UPDATED SAFETY ANALYSIS REPORT 029-C and CNs.dgn 9/1/2022 1:38:05 PM A B c D E F G H I J K USAR REVISION 2S OCTOBER 2022 _J
KEY-XMUSTBEENERGIZED t~~~;~~:~~~~~ BUT HAY I *-..--*- I
*~ I~:- I*?~~=~* I~
3A 4A PILOT ACT.OR. 3/'4"311!100PSI 1-301!1111PSI 1/2 3/'4 SA CJRCDR. 3/<t"'3008PSI 1/2
- 3. s~~~~i~ NOT PER s&w STANDARDS ARE PER ANSI
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B(ill!fil) PIPE 0.TIIOOIA 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) N NPSH (feet) 1200 E EFFICIENT (percent x 10) x RATED CONDITIONS H 1000 (.) zw
~
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w
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- 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
e..---- --r-THROAT OR MIXING SECTION SUCTOON --.........
<Sr--------------
.--~~--......~ ~--..1...-------------~-------- DRIVING FLOW .,._ FLOW____, DRIVING NOZZLES
---1 DRIVING FLOW 4P SUCTION.
_ _ _ _ _ _ _l FLOW 4P 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
STEAM NORMAL SEPARATORS WATER LEVEL STEAM TOP OF SEPARATION ACTIVE CORE DISTRIBUTION PLENUM WATER LEVEL AFTER BREAK IN 1 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 11 TITLE, REACTOR . CORE ISOLATION COOLING NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N. Y. UPDATED SAFETY ANALYSIS REPORT I USAR REVISION 19 OCTOBER 20I 0 _J
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---*~I~~
FIGURE 5.4-10 REACTOR CORE ISOLATION COOLANT SYSTEM PROCESS DIAGRAM SHEET 1 OF 2 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 Al 8 SUCTION FROM SlffRESSIONPODL - - - - - - - - - - - - H O O E 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 PERKITT ING 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:,
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2200 RPM 4700 RPM 55000 50000 45000 40000 a: J: iii co 35000 ...J I ~ 0 30000 ...J u..
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c( w 25000 I-U) 20000 EXPECTED PERFORMANCE 15000 TRIP & THROTTLE SIZE: 4 INCHES RATED INLET STEAM : 1135 PSIG - 562°F LOW INLET STEAM: 135 PSIG - 358°F 10000 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
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eDRF: 0000-0071-6768 eORF Seetion : 0000*0071-6783 Rev. l Nine Mile Polrtt Unit ? EPO RHR . S.ystem Shutdown Coormg CSOC> Niolysi&
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UPDATED SAFETY ANALYSIS REPORT A USAR REVISION 20 OCTOBER 2012_j
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- FIGURE 5.4-13f RESIDUAL HEAT REMOVAL 11 11 NINE MILE POINT NUCLEAR STATION - UNIT 2 SOURCE: PID-31F-17 SCRIBA, N. Y.
TITLE: RESIDUAL HEAT REMOVAL UPDATED SAFETY ANALYSIS REPORT A B c D E F G H I J K USAR REVISION 25 OCTOBER 2022_J
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TITLE. RESIDUAL HEAT REMOVAL 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. I
,---------------------1
' REFERENCE DOCUMENTS:
- 1. RESIDUAL HEAT REMOVAL SYSTEIA Pll<ID MPL ITEM NO.
B12*1010
- 2. NUCLEAR BOILER PROCESS DATA B21-1020/B22 -1020 SIDE II SIDE I JE----
TOSERvK:E WATER 0tS0tAAG£ TO SERVtCE WATER OISCtuac( RHRSERVJCE WATER SYSTEM RtfiSERV1CE WATER SYSTEY
- - ... - - - ... - . . . . SJEAHFRDMRCtC 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 <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 I6 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. DROP-FEET A-2ACCIOENT WllHREtlRCU.. ATIOHLlNE8REAK !NEITl-ER SJOEAJrC>lfflEEPUHPO'ERATIOHMSTRA!HERPLIJGGEO WITH t. PLAHT SPECIFIC DEBRIS HIX.OB HIM> [LOOP C \._LOOPS A S. B 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 I6 7 B 9 10 16 11 29 FLOW-GPM 1000 rz.rz. - FLOW*GPM D HORMt.1..SHUJ'DCWfArTtRll!ll..OrlJCIWtTO""'lNtcHDDIS£R (SUNOTEU) .. PRESS.-PSIA IX"*' PRESS.*PSIA "*' x x x xx xxxx,..1 E ~r~+l~~f~~~mr~r KlOE 0* (ATOPSIG) 11 TEMP.
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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 XX X 1.-&.SHE:DLJICS INDICATtnowocc:SNOTPASSTtfl:UTl-£SEl'O(HTS. PRESS. -PSIA 'Xi'x x x x x x x x x x l..TlENP9WAY.U~CIN IJIOYE TK l\N>MCUffl .t5fE.f.T.THE TMl.SVM..UC1'1.USTI£01 TEMP. "F - - - &.OtlTICH.l.HDTIC t£~ 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.
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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
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--+--+--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 RESIDUAL HEAT REMOVAL SYSTEM requirements ore based on Mode specific 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
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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
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. RESIDUAL HEAT REMOVAL SYSTEM 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 NINE MILE POINT-UNIT 2 THIS DRAWING CREATED ELECTRONICALLY UPDATED SAFETY ANALYSIS REPORT USAR REVISION 19 OCTOBER 2010
1200 r--------------------------------------- 1100 0N 1000 ~ MINIMUM REQUIREMENTS 10 ::c
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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
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- 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 2-WCS-11104-17-3 1 ~ 1
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RM \ _ 2-WCS-004-137-3 FV 2-WCS-01114-ql-3* 1F~ 3 1 r:::::;:.:l::'._:::j 2-WCS-001-136-3 SC3 NNS 160 2-WCS-003-587-4 9 NNStC3 vns vn1 5.4-16f !K-61 RHS SYSTEM 5.4-13f 11-51 2-WCS-006-3111-4 f 111 )--e---t:ll:J----H--{1-7( 9
< 5.4-16e !C-9l I ~Yl0B ~Vte7
... 1rl" t0~21 RM IF~l I RM 2-WCS-006-163-4 IFeJsl FY 135 1F0~q1 RM 1F0030I RM CONDENSER MDV 1
1I V167 IRsesl
\_ 2-WCS-11102-214-3 CONNECTION 107 I [0331
---L-:!.,
2-WCS-006-24-3 2-WCS-004-q6-3 o---2-wcs-1110s-2q-3 2-WCS-1111114-26-3 2-WCS-004-41117-4 _...,__ _-. 2-LWS-006-566-4 LWS SYSTEM 10 11.2-1 .. !D-ll 10 2*WCS-006-164-4 NNS .l.scJ FIGURE 5.4-16c REACTOR WATER CLEANUP SYSTEM 11 11 NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y. SOURCE:PI0-37C-27 TITLE: REACTOR WATER CLEANUP 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 1 1 8-1 WCSBC05&------, 2-WCS-001-39-4 [TI 2-WCS-002-37-3 602317 THIS OWG !0-6) rF0i5] ADV NOTE 3
~ 30A WCSBC23&------~
2-WCS-001-36-4 IF0:51 ADV NOTE 3 5.4-16f <B-Bl 2-SAS-001-515-4 25A 2-WCS-001-175-3 SAS SYSTEM V79 q_3-1 * <0-3) ADV IF013 I SC3lNNS 2-WCS-002-176-4 61A A
' 2WCS-IPNL187 V208 NNS SC3 NOTE 3 rn I A
2 !'!_ IR010 I 38A A IN~2 l 2
< 5.4-16f <C-111 I ~ I ADV 2qA NOTE 3 NOTE 3 v' SHIELDED CUBICLE FILTER 2-WCS-003-396-4 "_} DEMINERALIZER DEMN 4A 2WCS-IPNL187 1N0:21 TYPICAL AIR OPERATED VALVE ARRANGEMENT
~ 2-WCS-006-391-3 (SEE TABLE BELOW ANO NOTE 5.1 2-WCS-150-40-4 ~---< FT ISA A/S 2WCS-IPNL187 EB IN015 I A A 2* 2-WCS-008-203-3 ' '
...
- l, 2WCS-IPNL187
_ ___....._,CLEANING ,' ' sov A 3 r CONN NOTE 3 NOTE 3 l--------- _____ _, FE 16A 3
~ ISA A/S 5.4-16f IC-Bl V173 V174 ENT Vl76 V177 IF0~41 ID~3 I NOTE 3 VENT IF0:31 2-WCS-008-509-4 RM STR5A V70 2-WCS-004-19-3 V171 V172 EJ 2-WCS-002-44-4 2-WCS-004-21-3 ADV IF0~01 2-WCS-01116-487-3 I F~31 I I l
IF0f91 2-WCS-002-168-3 RM RM
~V78 ~V77 5.4-16f IK-21 RM RM 2-WCS-11101-45-3 Vl10 F041
~~
4 2-WCS-003-34-3 VIII 4
~l5=._4-~16~c_<_K-~U~~>~-------- TABLE
~-011J2-479-4 2-WCS-006-486-3 5.4-16f IB-101 ) m'--lefo-S-C3e:. /ffe)T PXA m 2-WCS-150-517-3-- 1,-------~~---~ V71 V358 g-T-SC3 NNS AREA ADV sov
~
<D-ll F11114 25A A 25A NNS t007 I ADV STRT8A ;r V254 I DEMIN <D-21 F012 2 ;WCS-0~-~~
1 NOTE 3 2'lA A 2'lA 2-WCS-002-46-3 1---' A 52A ~_j_ V359 PRESSURIZATION
<E-2> 28A F011 28A 5.4-16e <K-71 A 2-WCS-004-169-3 IF -ll F015 30A 2-WCS-150-389-3 30A A V76 F03q CHEMICAL ADV e F041 B (F-21 SIA F013 SIA
(----------, A CLEANING NOTE 3 "-----~ 31A CONN 2-WCS-004-3'l2-3 ' <D-3) 51A F01B A 5IA RM ' "--- KUC 2WCS-IPNL187 <E-31 44A F00q 44A 5 V75 ADV t0051 V72 5A
<G-4) 52A A
F01a7 52A 5 2-WCS-002-173-3\ 54A A 2-WCS-002-35-3 A 2-WCS-002-50-3 SC3 IF0:91 ~F'--_::2_:-W:,:C~S-002-387-3 P6A <G-41 31A F016 31A V74 l A NNS NOTE 3 lc0:1 I <E-5> 54A F005 A 54A IF0i71 NNStSC3
<E-51 53A F006 53A HOLDING PUMP A SC3 NOTE 3 85 GPM <G-51 26A F008 2SA lm6]V73~ NOTE 3 I 75 FT TOH A 2-WCS-002-51-4 ~
~ NNS NNS 20FR-ED8402 <F-61 25B F11114 B
25B DFR SYSTEM F0!5 q.3-q. (J-41 (H-6) 30B 8 308 ADV ADV t0061 26A NOTE 4 (H-6) FH13 53A A 618 B SIB
<E - 71 F0!2 2'l8 2-WCS-002-172-4 2'lB 8 5.4-16f <8-91 5.4-16f 11-41
<F-71 28B F011 B
28B 5
<D-8) 518 F010 51B B
5.4-16f (J-4) F1!10q
<F-8) 44B 448 B
2-WCS-002-52-3 (H-ql F007 2-WCS-001-39-4 529 B 52B 5.4-16f !C-8! 2-WCS-001-185-3 <H-101 31B F016 318 8
<G-101 54B F005 54B THIS DWG <D-U SC3 iNNS B 2-WCS-002-184-4 F01!16
<G-10) 538 53B 8
NNS iSC3 NOTE 3 F01i!18 v 11-10) 2SB 26B rn B IN0J2 I LE -------------------------, (J-3) 27A F11104 (,,::~------ 27A
NOTES:
A 7 SHIELDED CUBICLE I. ALL INSTRUMENTS ANO EOUIPMENT NUMBERS TO BE PREFIXED 7 2-WCS-150-53-4 NOTE 3 NOTE 3 2-WCS-150-186-3 ADV WITH *2wcs-* EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN. 29B 2. G.E. IDENTIFICATION NUMBERS ARE SHOWN IN SOUARES FILTER OEMINERALIZER ITO BE PREFIXED WITH G36!. r---- DEMN 4B 3.SEE TABLE FOR TYPICAL AIR OPERATED VALVES NNS lscJ 2-WCS-006-385-3 ARRANGEMENT THIS OWG IM-3>.
' 2-WCS-006-384-3 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 2-WCS-008-510-4 2-WCS-008-54-3 BY GE , HOWEVER THE GE IDENTIFICATION NUMBER IS
MAINTAINED FOR CROSS REFERENCING TD OTHER DOCUMENTS.
L---------- 8 5.4-16f <E-9l 8 NNS iSC3 5.4-!6c !A-7) 2-WCS-002-57-4 VIBZ 2-WCS-006-489-3 2-WCS-006-488-3 5.4-16c IA-71 RV Fm41 2-WCS-002-481-4 2-WCS-003-59-3 c
- J;?@
5.4-16c IK-3! 21B F039 9 c 9 I I 5.4*!6f IE-Ill )
~ \_2-WCS-002-56-4 j
2-WCS-002-61-3 J V81 1--t:f-~i:.:;.~ I 0 STRT8B V256 I
~ 1:~~15-12102-386-3 t-----"(.. scJ.LNNS DEM IN V361 PRESSURIZATION 2-WCS-150-518-3 5.4-16e IK *6)
NOTE 3 II V86 2-WCS-150-382-3 V257~ F039 Fe41 NOTE 3 D O 2-WCS-004-182-3 r----? (---------* RM ' <IDC L__ KUC 2WCS-IPNLl87 V85 V82 5A ADV IF0051 2-WCS-002-448-3 10 2-WCS-002-64-3 SC3 54B B ADV IF0:91 *~~--.:2_-w:;,,c:.:s:.,-002-381-3 10 PSB IF0837 IV84 l NNS 2-WCS-002-181-3 2-WCS-004-183-3 ~SC3 26B 1ce:1 I NNSrSC3 NOTE 3 N!s NOTE 3 HOLDING PUMP 85 GPM FIGURE 5.4-16d 2-WCS-002-180-4 SC3 2DFR-E08401 V83 NOTE 3 2-WCS-002-65-4 l NNS 75 FT TOH OFR SYSTEM IF0836 I 9.3-9. 11-4) FG 60B NOTE 4 ADV 53B IF0061 B 2-WCS-004-63-4 REACTOR WATER CLEANUP SYSTEM 2-WCS-004-62-4 5.4-16f <B-9> 5.4-16f IJ-41 5.4-16f IK-3! 11 11 NINE MILE POINT NUCLEAR STATION - UNIT 2 SOURCE: PI0-370-18 SCRIBA, N. Y. TITLE: REACTOR WATER CLEANUP 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 2-WCS-002-120-3 ITTffil ADV NOTE 3 L£_j 30C NOTE 3 2-WCS-001-198-3 1 THIS DWG <E -6> 1 NNS ~SC3 NOTE 3 (,, ' v LE EB AOV NOTE 3 [1J ADV NOTE 3 2-WCS-150-199-3 62~,,,_-_-__.__-_-~------------------------1 SHIELDED CUBICLE 2'lC 28C
>-----< 66Czs 1N0c0s1 :*
FILTER I DEMINERALIZER r----I DEMN 4C I 2-WCS-006-354-3 I I 2 I I 2-WCS-006-353-3 2 I I I TYPICAL AIR OPERATED VALVE ARRANGEMENT I I
!SEE TABLE BELOW!
2-WCS-008-111-3 I I NOTE 3 I NOTE 3 I I
-~
2WCS-IPNLIBB 5.4-16f <F-8> c 58 PT 17C -----~ 1¥.?1 2WCS-IPNL188 5.4-16c <D-8)
- - - J:Jlf-----'-----( POT }---------l:tif.--1 3 20C 3 2-WCS-006-491-3 IN~041 t EJ 2-WCS-003-109-3 2-WCS-006-490-3 5.4-16c <D-8) F040 ADV IF~81 I A )
RV SC3 NNS 0A42 5.4-16c <K-5l 21C V362 TABLE AOV IF0071 J
~~f----{l]5.14-j1sfilr]<QG-]11[1::::::::::::> 52C C I--~~]
V258 I~ AREA ADV Cl) SDV V363 ~ F014 2-WCS-002-118-3 2-WCS-002-116-3 NOTE 3 CF -11 25C c 25C CH-ll F12115 4 IF0t51 V25~ F042 30C F013 c 30C 4
~
040 1~1~~~=-~~---l-- 2WCS-IPNL188 ~ B B (H-21 SIC c SIC
'-tJ V'l6 <E-2l F012 ADV 29C c 29C CE-2> 28C F011 2-WCS-004-1'!5-3 31C c 2BC RM C0-3) F010 2-WCS-002-350-3 51C c 51C V'l5 V92 CF-3> Ffl)0CJ 44C c 44C AOV IF0051 n 2-WCS-002-119-3 SC3 54C C IF~691 P6C (]-4) 52C F007 52C c
I 2-WCS-002-194-3 V475 NNS NNSJSC3 NOTE 3 2-WCS-002-108-3 2-WCS-004-196-3 I c~01 I (] -5) 31C F016 c 31C CG-51 54C F005 54C 2-WCS-150-452-3 HOLDING PUMP 2DFR-ED8501 c 5 85 GPM V474 (] -6) 26C F008 26C 5 V'l3 AOV IF0061 ADV IF0081 75 FT TOH DFR SYSTEM c 53C C 26C C F006 SC3 SC3 CG-51 53C c 53C 1F0c3s 1 NOTE 4 RV 418 FG 60C I I Cl-6) 31110 F015 D 300 NNS NOTE 3 NNS DEMIN NOTE 3 V478B F014 PRESSURIZATION CG-7> 250 250 D 5.4-16d CK-101
< 5.4-!Sf <C-IU 5.4-16f CF-'ll 5.4-16f (H-7) 5.4-16f CH-8l V4780 V479B CH-7) 610 F013 F012 D
610 CE-7> 290 290 DEMIN D V473 PRESSURIZATION CF-71 280 F011 280 V4 7'l0 D 5.4-16c ([-5) F010 C0-8) 510 510 ______T'"____-[jT~HillISLQDW~G[Ji<Dt-TI11::::::::> V478C
~l9_.3_-~l>>~*<_E-_2_l_ _ _)~-----1r-------r----[)+---.....JL... 2-WCS-002-130-3 fFm5l ADV NOTE 3 10~061 V472 D F00CJ V215 LQ_J 300 V4 7'lC DEMIN
<F-81 440 D
440 6 r;:::::-;:::::;--- '.1--------( is~ )--*-{J5[.4~-]16!frJcQG-]8[>:::::::::> V478A PRESSURIZATION (]-9) F007 l V223 520 D 520 I 2-WCS-001-210-3 5.4-16d Cl-4> F016 Cl-10) 310 310 ADV IF013 V47'lA D 610 D SC3 NNS F005 Pl CG-10> 540 540 D 388
~SC3 CG-Ill 530 F fl)fl)6
(, ,', ,'_, _'- - ' - - . . v NNS NOTE 3 D 530 IN~l2 I 6~0 >---~ --------------------------1 ([-Ill 260 FIZl08 D 260 IF~I I SHIELDED CUBICLE 2-WCS-150-211-3 NOTE 3 NOTE 3 AOV NOTES: 7 FG 280:...-----.__'f-' :, FILTER IN~6 1 i, V476
- 1. ALL INSTRUMENTS AND EQUIPMENT NUMBERS TO BE PREFIXED 7 r--------------~--<140 DEMINERALIZER r---~ WITH *2wcs-* EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN.
DEMN 40 2. G.E. IDENTIFICATION NUMBERS ARE SHOWN IN SQUARES 2-WCS-006-361-3 V477 no BE PREFIXED WITH G36l. 1000071 2-WCS-006-360-3 3. NO FLAG SHOWN ON CORRESPONDING DOCUMENT. I I COORDINATES PROVIDE INTERFACE LOCATION. I I I 2-WCS-008-139-3 I 2DFR-ED851111 I NOTE 3 NOTE 3 I I I
-~
5.4-16f CH-81 wu; I-8 PT 170 2WCS-IPNL188 <fl w l- 8 o: " a LL er Z o' 5.4-16c CA-'ll "1 1----0J(J-__L------jPDT }-------~--I er 200 V201 V202 2-WCS-006-493-3 IN~041 5.4-16c CA-101 2-WCS-006-492-3 5.4-16c CK-4> RV 210 I F~81 I 2-WCS-003-135-3 F040 c SC3 T NNS F0~2 V364 f.-.~~--{l]s.14-jt6filr~cfilGj-1fil01::::::::::::> 1-i=f-~f-J I Vl01 J STRTBD T 9 V260 9 2-WCS-002-126-3 t-----.t_JNNS
~0t---0:0--iP0----1 V365 IF!;;1s-002-120-3 NOTE 3 V261~_,,
0 2-WCS-150-516-3 I -~------......__- F040 F042 f--1 v10s ~ 2WCS->PNL188 ~
'-tJ D D ADV NOTE 3 310-,,~~
RM 2-WCS-004-207-3 2-WCS-002-356-3 V105 Vl02 ADV IF0051 2-WCS-002-129-3 540 D SC3 IF0t91 2-WCS-002-206-3 P60 10 I 2-WCS-150-359-3 10 w
~ NNS 2-WCS-002-134-3 l-2-WCS-11104-208-3 ICllJDllJI I o
> NNS rSC3 NOTE 3 z HOLDING PUMP 2DFR-ED8502 Vl03 ADV 530 IFllJ06 I D
ADV 260 IF011l8 I D 85 GPM 75 FT TOH FIGURE 5,4-16e IF~361 SC3 SC3 DFR SYSTEM FG 600 I I NNS
'l.3-'ld <E -6>
NNS NOTE 3 NOTE 3 NOTE 4 REACTOR WATER CLEANUP SYSTEM 5.4-16f CG-'ll 5.4-16f CJ-7) 5.4-16f IK-6) 11 11 NINE MILE POINT SOURCE: PI0-37E-15 NUCLEAR STATION - UNIT 2 TITLE: REACTOR WATER CLEANUP SCRIBA, N. Y. 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 1 Vll8 1 THIS DWG lK-51 MILLIPORE IF0:41 FILTER HOLDER ,,,__TYGON TUBING
& CONNECTORS FG 37A
,-----------j ~-----------------1 NOTE 5 I A/S Vl25
' --!' j-----------------'------1 f-------<( 9.2-I?b IJ-91 FLTlA -~ '
V436A PRECOAT FY ==~~~ 5.4-16d II-41 AGITATOR 55A
'MIX100A
' ________ J' RESIN AGITATOR
- MIXl0lA 2 Vl22 IF~451 PI VENT Vl78 2
~------jC}----i 66A TK15A TKllA Vl24 IA0A021 V437A .------------------ I THIS DWG ll-111 >
RESIN FEED TANK , ______ J I 5.4-l6c IE-81 IF0A62 I Vll9 LT ,----------------------------1 I NOTE 4 TYPICAL AIR OPERATED VALVE ARRANGEMENT NOTE 4 RV IF0A851 (SEE TABLE BELOW> 56A ' I
'I 45A IN0JB I EDU4A
, - - - - - - - - - J'
~_J i[--l:t----, PCV 63A I THIS DWG IF-101 >
I I PRE COAT I I PI I TANK PCV434A I -----, 5.4-l6d lH-lll 1rn;1
- <!HIS DWG IK-101 57A IF0A63 I _ _ _ _ _ _ _ _ _ _I I NOTE 4 Vl2l 2WCS-IPNLl87@ I A/S
'I Vl79
\!A_) --
Vl23 3 I I L _____ _ ADV s 3 L--------------------------------------------- 48A
VENT
OFF/ON I L ___ _
,-----------------------------------------------------~
B V435A v433 A: IF0A221 ADV NOTE 4
V127 I I THIS DWG IF-101 >
49A
I AOV VI20 2WCS-IPNLl87 K~~- -----, ,--------------------------* ------*
IF0A581 5A I
,------------------------ ------, RESIN METERING PUMP VlBB
- 2wcs-IPNLl87K~~
I I I
- L _____________________________________________________________________________________ J SQV I :
46A S : ' 5A
' V128 VI26 A/S f--{),'<f---ff----1 I
,>---.,,J 5.4-l6d IE-61 5.4-l6d IG-l0J TABLE VENT 4 THIS DWG IG-91 : kj f- Pl2A IC0A02 I 5.4-16d IG-61 AREA ADV (1) sov KUC 4 ADV STRT9An~ (J-3) 47A F02fl.I 47A 5A 46A V276 0) L __ _ _ _ _ _ _ _ _~
A F020 PRECOAT PUMP JT (l-6) 47B B 47B SB 255 GPM AT 85 FT TOH 48A FIZl24 48A (H-3l 5A 20 FR-ED 85 04 L---jl_'9!_,;.3~9d!!_JllG,i_::!;611__) (H-7) 4BB F024 48B SB NOTE 3 B Frzl22 (E -4l 49A 49A 5A Vl39 CE- 7l F022 SB MILLIPORE 49B B 49B 100B041 FILTER CG-3) 50A F023 50A 5A HOLDER NOTE 5 FG r------------1 IF0~41 CG-6> 50B F023 508 5B 378 I A/S B I
---KJi-----------_....... ,..__ _ _ _~( THIS DWG IJ-ll
'I I
5 FL TIB ,-"----~ V4368 Vl35 5 5.4-l6c IH-91 PRECOAT _____ rn~ A/S~ AGITATOR FY
*MIX100B ' 55B _________ J' RESIN PI 398 IR0Bl21 AGITATOR l
~----;~,.-~LOW
- MIX10IB IF0B451 V132 VENT PI Vl89 66B TK15B IF0862 I TK!l8 V437B RESJN FEED f0~21 Vl34 r
I
~-, 1----{l]TH~IisJo~W~GJ1II]11[1::::::=>
TANK w 1-------~------1 ,-----------------------J RV 5.4-I6c ID-101 Vl29 ,---------------------------- NOTE 4 IF0B201
ADV NOTE 4 43B r-----1 r - g
508 6 PRECDAT
\_9 EDU4B
PCV r--1ILTCC:H1!;ISc.JJ.DWl!)G!__i!II~l~011___,)
TANK 2WCS-IPNLIBB 63B PCV4348
,----- ~
PI NOTE 4 5.4-l6e II-Ill
' 57B Vl3l : <!HIS DWG IK 101 IF0:31 ,--------- -------, 1. ALL INSTRUMENT AND EQUIPMENT NUMBERS TD BE PREFIXED
' Vl98 WITH "2WCS-" EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN.
L VI33
~---j - - - - - ADV I
'I 2. G.E. IDENTIFICATION NUMBERS ARE SHOWN IN SQUARES 48B I
------------------------------------------ -1 I ITO BE PREFIXED WITH G361.
'I 3. NO FLAG SHOWN ON CORRESPONDING DOCUMENT.
IF0~41 COORDINATES PROVIDE INTERFACE LOCATION. I V433B : OFF/ON I V435B 1 NOTE 4 IL ___ _
,------------J 4. SEE TABLE FOR TYPICAL AIR OPERATED VALVES ARRANGEMENT THIS DWG CM-4l.
' Vl37
____ J'
- ~~~ IF0221 B i I R~ll I PI 408 l----l[TITHillISLQDW~G[ijlij-1!0[1::::::> 5. MILLIPORE FILTER HOLDER AND ASSOCIATED TYGON TUBING AND CONNECTORS ARE TEMPORARILY INSTALLED ONLY WHEN 7 Vl30 2WCS-IPNLIBB K~CC- -----, ,-------------------------------- SAMPLING OF THE PRECOAT CONDENSATE RETURN IS DESIRED.
7 5B , RESIN METERING
,----------------------------- -, PUMP I' Vl99 SQV I : : 2WCS-IPNLl8B KUC ~------------------------------------------------------------------------------------------J 468 I I I s ' 'I 58 Vl38 Vl36
' I A/S f-~1§1_,l-iJ:t':+ I 5.4-l6e CG-61 5.4-16e IG-111
'I r;c=--;cc-,-;;--,;-;-=~ VENT THIS DWG IH-91 I kjf- Pl2B IC0B02 I 5.4-16e IH-61 ADV 468 STRT9~-~
V277 0) PRECOAT PUMP 255 GPM AT 85 FT TOH 2DFR-ED8503 JTL_--{l}9.d3-39~dE1og-s[1===> NOTE 3 8 8 5.4-l6d IC-31 5.4-16d IB-81 5.4-l6e IB-31 5.4-16e IB-81 5.4-l6d CH-ll 5.4-l6d IJ-61 5.4-l6e IJ-11 5.4-l6e IJ-61 5.4-16d IE-61 5.4-lGe CE -Ill 5.4-l6d IE-Ill 5.4-l6e IE-61 THIS DWG. CB-81 9 9 ll.2-l
- IB-11 THIS DWG. 18-41 5.4-lGd IF-41 ll.2-l
- IC-21 V268 Il.2-1
- II-21 10 THIS DWG IJ-31 5.4-l6e IG-91 THIS DWG IJ-61 10 THIS DWG CJ-71 THIS DWG IJ-41 THIS DWG IE-61 FIGURE 5.4-16f 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 REACTOR WATER CLEANUP SYSTEM 11 SOURCE: PID-037F, REV.11 11 NINE MILE POINT TITLE: REACTOR WATER CLEANUP NUCLEAR ST AT I0 N - UN IT 2 SCRIBA, N.Y.
UPDATED SAFETY ANALYSIS REPORT A B c D E F G H I J K USAR REVISION 25 OCTOBER 2022 _J
2 4 5 B I I ~! s ! .I G33-1030 NON-REGEN HEAT E'XC\.I. NOTES : TOM:ACiOR. 1. POSITIONS 28 & 29 INOICATE CLE.foNUP C<N>ITIONS \o/ITH VARIOUS R8CC\ol lll'ECIAC PuMP"' INLET TEMPERATURES.
- 2. fOR BACKWASH & PRECOAT fREQUENCY SEE !>UP 3.
B r 3* fOR DET AI LS ON fl LTER & DEM I NERALI ZER 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 t.._ _______ __.,
I "-.... RE!IC.C.W 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 DATA
-AS lllTHIN HEXA(OQNS, REfER TO PROCESS
- a. MOOC "A" DCSlr.11 BASIS fOR HEAT EXCHANCOCRS ANO NO fLOW IS c REQUIRED AT POSHION 16, 17, 21 'RI.I 27.
I **
- 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. REACTOR F"E.EDWATER t CLLto..1.1-UP F'"IL'T~Q.1 C>E.t..tli..IE.A.Al..1 ZEQ.. RETVRN UN17.. A"
,,.-, I
'Fcv~ II 'I r- - I I
'i/ I I 5ffERENCE DOCUMENTS 11119-----t*****m~~')-******************j ~*-** . .- -..... 1. Fl LTER/OEMI N SYST[l4 P&I O------------------G36-1010
- 2. fl LTER/DEMI N SYSTEM P.O------------------G36-1020 I :
\.
13 I 13A
@.J E
,...____..,.. _____ '--/
* *~~}-- - -- ---- -----omoj I I *---.... ......
(
\
..._ _,,I I FROt'I I SEE REF I CLH>.N-UP FILTH I 12 UN\T "?."
I 0£~~~:~~.~7._JE~ L_ -------- TYPICAL OF 2. F RAOWA5TE,._~~~~~~~L-~~~~--.....~~~~--' 5'<STEM 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 2 3: 4 5 7 B 9 : USAR REVISION 5 OCTOBER 1993
MOOE A NORMAL OPERATION R.S.S. 1035 PSIA
<SEE NOTES 1, 3 ANO 5 OF PROCESS DIAGRAM>
LOCATION 0 FOTEH~ 8 10 12 13 15 I6 I7 18 I'l 20 21 22 23 24 25 26 27 28 2'l FLOW GPM 63 420 "103 "103 "103 45I 451 "103 715 715 687 343 343 687 816 816 1434 TEMP. F* 534 534 534 534 534 534 535 535 233 233 120 I20 120 120 438 438 438 154 MAXIMUM *10-* *--10--* *--5'l--* *--10--* PRESSURE *-17'l**TOH DROP ALLOWABLE PIPE FRICTION DROPS <SEE NOTE 6 OF PROCESS DIAGRAM> PSIO * ----------------------------------------------------------------------- - ----- 30 -------------- - ---------------------------- - - - --- - ------ - --------- - --------------------- 10 --
- MODE B HOT SHUTOOllN OPERATION IW!TH LOSS OF RPV RECIRC PUMPS> R.S.S. 1003 PSIA
<SEE NOTES I ANO 6 OF PROCESS DIAGRAM>
0 LC~ATION JI) IJ I~ 17 16 l'l ZI 26 (1<) FLOW GPM 162 'l8 358 358 358 358 358 358 358 358 358 358 TEMP.F* 540 545 543 543 543 543 544 546 546 546 MAXIMUM *-162-* PRESSURE *-1'10-*TOH DROP ( ) 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. SOURCE: OWG. NO. 001654000!l06 FIGURE 5.4-17 REACTOR WATER CLEANUP SYSTEM SHEET 2 OF 3 NIAGARA MOHAWK POWER CORPORATION TH IS DRAWING CREATED ELE CTRO NICALLY NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USA R RE VISION 9 MAY 1997
2 3 5 6 7 I J1 ; B 9 10 I 1 1 I 12 12 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 c Olt.Y. ACTUAL Lit£ SIZES AS DETERMl~D BY Tl£ PIPING DESIGt-ER SHALL ~ET Tl£ PROCESS DATA HYDRAULIC REQUIRE~NTS. 0 LOCATION 1:-1A* 1A-18.. 1C-1D 18-1E 2A-28 28-SA 5A-6 7-7A 7A-8 9-10 11-118 11A-1S8 11-B-13A 13A-14 DESIGN PRESS, (PS IG} 1250 1250 1250 1250 1250 1250 1250 1410 1416 1410 1~10 1410 1410 1410 D DESIGN TEM,P. (DEG . Fo) 575. 575. 575. 575. 575. 575. 575. 575. 575. 575. 150. 150. 150. 150.
- ESTIMATED LINE 2.0 2.5 1.0 4.0 4.0 6.0 6.0 6 .0 6.0 6.0 6.0 6.0 6.0 SIZE (INCHES} 8.0 E
LOCATION 0 DESIGN PRESS, (!'SIG) 13A-33A 1410 27-338 1410 15-21A 1410 21A-20
"- DESIGN TEMP. (DEG. r*J 1~. 150. 575.
- £ STI MATED .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. H
**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)
J FIGURE 5.4-17 L REACTOR WATER CLEANUP SYSTEM
-- SHEET 3 OF 3 I
NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
*.*. 1 2 3 I , ' 4 6 7 I T' I B 9 10 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 _
TA6L!: "I F/O AREA* ~7.FTa RA010* REACTOR ~S + CNOS + CONC REACTOR REACTOR CNOS SERVICE ACT VE REACTOR WATER + AIR AIR WATER ~IDS sl: kAy RESIN SLURRY RESIN WATER + c~ o.io~ WATER SLURRY sbe1os
+ F/O 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 VENT' UNlT,.B' ~ ~ ~~~~~~~~~~v~~~~~~~~~ ~~~~~~~~~~~~~~
FLOW TIME, HIN. 3.15 l 0.7 2 5 Z. ?. O.' 10 30 30 OS 30 0.7 10
~6Al..37S'&Al
~-i--~---~---~~-+-~c.e AIR. TOTAL LBS, SOLIDS l!fSID!IAl RESIDllAl VES')El HEAD li!EAC.'lorl.V.V."1'52 t-------.,------r-1--t-,...__ _ _ CONDENSATE TASL~Il DRAIN o..eAN-u>l=IU'ES2.
oeMINE.IC!AU~ UNllA
© © @ ©@ @ ~ @ @ @ @ @ @ @
HO l!O 80 80 100 100 0*100 40 40 - OrlOO 40 40 fv~£M 0*20 (\() 40
~~
PRESSLflE.PSIO !I 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 18 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.
K~K
© © @ © @ @ ill @ @ @ @ @ @ @ @ @
l='ILTEK /DEMllJEl:::AL17Et PRESSl.flE,PSlG I\ l\... 80 80 BO 80 IOO !I 100 0-100 40 40 - 0-100 40 40 ¥V~~H 0*1.0 40 40 BACKWASH $ l'l!ECDATlhJb SEQIJHICE - SEE NOTE ~ ~ 60 80 so so G.O IOO l'l..O 80 eo BO 80 eo 80 fro10 ao 80 ISO ... _,.v; 1) . . TEMPERATURE. *F 1'2.0 rul'.J(TIOtJS PRElDAT PUMP 1-F-LO_W_R-AT-E_ _ 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 SERVICE {j)@ FLOW TIHE,HIN. - - 315 'l.5 0.1 1.0 3 1.0 '3 0.5 10 Mill 30 HIN 31! HIN 0.5 ISOLATE l HOLD @
- - ISOGAlGOGAL 350GALS50GAl "25Cf 73 5Cf 17SG"1.. 375G4l. - - 61 GAL 375 - - - 3f0GAL - -
0£PR'ES5UKIZE © - aEs!OllAl - DOME D~l..i r:!J **~EE NOTE 2. AIR PRE.SSURIZ.£ (]) I'" Alt BUHP t DJ:AllJ @ill NOTES' FILL t VHJT ©@ I. f'OR THESE. \IA.UJ£S I& REMAINDER Of S'ISTE.M SOURCE: 0016.540-01211-12127 REV. c VALUES: SEE. REACTOR ~ATER CLEANUP DOHE D~Al>J ill G) SYSTEM PD FIGURE 5.4-19 AIR PRESSVflZE (!) 2. DRY WE 1.GHT VALUES FOR 'RESIN ,AS AS SHIPPED RESINS COHTAIN 50% 211DAl!t BUMP t l>iAlll MOISTURE ( APPROXlllhA.TE) BACrWASN / Dl!AUI @@ 3.NORMAL BACl<lt'llASH- PRECOA.T FREQUENC'I FILTER DEMINERALIZER F'ILL t VfAJT @@ 15 EACH VESSEL C.\IERY (g-1401'1'15. SYSTEM SOLKA fLOC fRHOAT @ RESlllJ rJ:ECOAT @ HOLD f"l'.HOltT @@ NINE MILE POINT-UNIT 2 HOLD UllTIL RETVRIJ TO ,fr:VICE @ UPDATED SAFETY ANALYSIS REPORT
~ERVICE <D USAR REVISION 15 OCTOBER 2002 _J L
00 900 180° 270° 360° 428" I I I a AC UJ u. CD CD CD 366.31 '~ SHELL 2 C3065-l C3121-2 C3147-1
~ BELTLINE 277.25'_.'---~-L--------.-----'--------.--__._ __
AB SHELL 1 216.31':_ - -- - ---* C3066-2 C3065-2 C3147-2
<{ CD u CD CD CD 126.5'_.'_ _ ___.__ _ _ _ _ _ __..___ _ _ _ _ _ _ _ __
AA FIGURE , 5.A-1 lBELTLfNE WELD SEAM AND l --~ - -- -~ ----------*- **1
,PLATE LOCATIONS* .
-Y ' --- ----- --- *---*-*:*-
NIAGARA MOHAWK POWER CORPORATION
- FROM INSIDE BOTTOM OF RPV NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
FINAL WELD PREP MTP-10 OR MTP-11 MTP10 I.. 6-7/16 BACKGOUGE 3-25/32 FINAL WELD SURFACE MTP-10 AFTER PWHT RTP-8 AFTER UTP-50 30° 15° FINALPWHT WELD DETAIL (WELD PER WPS 323 2F4F6)
- - *w1t1J5":1- ---~
CENTERLINE 72.c102 2 1/ SPECIMEN CODE NO (SEE SLAB DET FOR SPACING) 1/2 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 w en o=> ----
<D 01-
-o z
P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 5/8 CENTERLINE P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 P2 5/8 1/8 SAW CUT (TYP) 1/2 L SUB-BLOCK ((WELD-1) 8-5/8
..I FIGURE 5.A-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}}