ML22292A081

5 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.3-1 Through 4.6-9

ML22292A081
Person / Time
Site:	Nine Mile Point
Issue date:	10/05/2022
From:	Constellation Energy Generation
To:	Office of Nuclear Reactor Regulation
Shared Package
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References
NMP2L2821
Download: ML22292A081 (24)

Text

....

1 REACTOR CORE 4WATER

2 WATER___/'/. 5 VESSEL 3SHROUD~.

MATERIAL MATERIAL MATERIAL DENSITY

RADIUS INCHES NO. NAME WATER 0.274 g/cm3

U02 2.642 g/cm3

1 REACTOR CORE 93.56 ZIRCONIUM 0.896 g/cm3

2 WATER 101.4 WATER 0.74 g/cm3

3 SHROUD 103.4 304L STA I NLESS STEEL FROM ASME SA 240

4 WATER 125.5 WATER 0.74 g/ cm3

-J 5 VESSEL 131.68 CARBON STEEL FROM ASME 533 ~

6 AIR AIR

• 1.3 x 103 g/cc

FIG. 4.3-1 MODEL FOR ORIGINAL ONE DIMENSIONAL TRANSPORT ANALYSIS OF VESSEL FLUENCE NINE MILE POINT NUCLEAR STATION-UNIT 2 SCRIBA, NY UPDATED SAFETY ANALYSIS REPORT L T _J USAR REVISION 16 OCTOBER 2004 1.4

1.3

1.2

1.1

1.0

a: 0.9 w

3r; 0 0.8 fl.

..J c(

i5 0.7 c(

a:

w

> j:: 0.6

c(

..J w

a: 0.5

0.4

0.3

0.2

0.1

0 0 10 20 30 40 50 60 70 80 90 100

PERCENT OF CORE RADIUS

FIG. 4.3-2

RADIAL POWER DISTRIBUTIONS USED IN THE ORIGINAL VESSEL FLUENCE CALC.

NINE MILE POINT NUCLEAR STATION-UNIT SCRIBA, NY 2

UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 16 OCTOBER 2.0.04 _J A. NATURAL CIRCULATION 100 B. LOW REC!RC. PUMP SPEED VALVE MINIMUM POSITION F C. LOW REC!RC. PUMP SPEED VALVE MAXIMUM POSITION D. RATED RECIRC. PUMP SPEED VALVE MINIMUM POSITION E.MID-RANGE CHARACTERISTIC, PARTIAL FCV OPENING

'10 F.UPPER LIMIT OF CORE FLOW

80

70

a:

LlJ

ir:

0 60 0..

I-REGION IV z

LlJ

(..) 50 a:

LlJ 0..

40

30 CAVITATION REGION REGION Ill

20

TYPICAL STARTUP PATH 10

10 20 30 40 50 60 70 80 '10 100 110 120

PERCENT CORE FLOW FIGURE 4.4-1

TYPICAL POWER-FLOW OPERA TING MAP

NIAGARA MOHAWK POWER CORPORATION THIS DRAWING CREATED ELECTRONICALLY NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT

USAR REVISION 8 NOVEMBER 199S 1.2------------------------,

1.01----------------------------1 ULTIMATE PERFORMANCE LIMIT

0.8 x 0 "N

x 0

~

a: 0.6 c( 105% ROD LINE 0 w 0

0.4

0.2

0 0~----2-0 ___ __.40'-----~60-~--~80:-----~

PERCENT POWER

FIGURE 4.4-2 I

TOTAL CORE STABILITY (CYCLE 1)

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

[ __

1 NEUTRON FLUX 1 VESSEL PRES RISE (psi) 2 PEAK FUEL CENTER TEMP 3 2 STM LINE PRES RISE (psi) 3 AVE SURFACE HEAT FLUX TURBINE PRES RISE (psi) 4 FEEDWATER FLOW 125 5 4 CORE INLET SUB (Btu/lb) 150 5 VESSEL STEAM FLOW CORE AVE VOID FRAC (%)

6 TURBINE STEAM FLOW (%)

. Cl w 75

~ 100 0:

u.

0.,/-.. A " ll I- /}, /'-' *-

z w -"

• Q -

u 50===-==' ' 25 0: ~ -

w..

• 0.. v -

~

0 0 10 20 30 40 0 10 20 30 40 I... -25 I -...

TIME (sec) TIME (sec)

1 LEVEL (inch-ref-sap-skirt) 1 NEUTRON FLUX 2 WR SENSED LEVEL (inches) 2 SURFACE HEAT FLUX 150 4 3 NA CORE INLET SENSED LEVEL (inches) FLOW(%) - 4 120 3 FLOW VAR SCRAM SP 5 DRIVE FLOW 1 (%) ESTIMATED THERMAL POWER

Cl 100 I-80 w

<(

0:

u.

0 I-j z

,.,

• Q " u 40 w 50 ~~ 0: - w

,;=-- ll ll l - 0..

>- < 5 " ~ t-.

0 I -.. 0 I...

0 10 20 30 40 0 25 50 75 100 -

TIME (sec) CORE FLOW(%)

FIGURE 4.4-a.J 10 PSI PRESSURE REGULATOR SET POINT STEP AT 51.5% RATED POWER *- - * - ---- -- ---*

(NATURAL CIRCULATION)

... NIAGARA MOHAWK POWER CORPORATION

, :~ NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT 1 VESSEL PRES RISE (psi) 1 NEUTRON FLUX 2 STM LINE PRES RISE (psi).

2 PEAK FUEL CENTER TEMP 3 TURBINE PRES RISE (psi) 3 AVE SURFACE HEAT FLUX 125 5 4 CORE INLET SUB (Btu/lb) 150 4 FEEDWATER FLOW CORE AVE VOID FRAC (%)

5 VESSEL STEAM FLOW 6 TURBINE STEAM FLOW(%)

- c " <

0 75

~ 100

<(

a: ~ ~

u. - H u 0 --:;

I- ~...,

z,

w 50 ' 25

(.) -

a:

w Q.. - *

• 0 I ~ -25 t.. II I II II Ill 1 0 10 20 30 40 0 10 20 30 40 TIME (sec) TIME (sec)

1 LEVEL (inch-ref -sep*skirt) 1 NEUTRON FLUX 2 WR SENSED LEVEL (inches) 2 SURFACE HEAT FLUX 3 NR SENSED LEVEL (inches) - - 4 120 3 FLOW VAR SCRAM SP 150 4 CORE INLET FLOW(%) ESTIMATED THERMAL POWER 5 DRIVE FLOW 1 (%)

0 w

100 I-80 <(

, a:

u.

0 ~

I-z w

.. (.)

50. -a: 40

- ~ 7 w Q..

H R

- c c r -

0 I *-.. 0 I --

0 10 20 30 40 'O 25 50 75 100 TIME (sec) CORE FLOW(%)

FIGURE 4.4-4

• 10 CENT ROD REACTIVITY STEP.

AT 51.5% RATED POWER (NATURAL CIRCULATION)

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

- * - -- - - - -- --- - -~

1 VESSEL PRES RISE (psi) 2 STM LINE PRES RISE (psi) 1 NEUTRON FLUX 3 TURBINE PRES RISE (psi) 2 PEAK FUEL CENTER TEMP 4 CORE INLET SUB (Btu/lb) 3 AVE SURFACE HEAT FLUX 1251----+----+--- 5 CORE AVE VOID FRAC (%)

1501------1-----+--- 4 FEEDWATER FLOW 6 TURBINE STEAM FLOW(%)

5 VESSEL STEAM FLOW c c

c.

• OW-L~J....L..1'1-1...1.-'-----L------,-'----~-~u~~* -2st1 I I I I 1 I I I. 1 0 10 20 30 40 0 10 20 30 40 -

TIME (sec) TIME (sec) 1 LEVEL (inch -ref-sep-skirt) 1. NEUTRON FLUX 2 WR SENSED LEVEL (inches) 2 SURFACE HEAT FLUX 3 NR SENSED LEVEL (inches) 3 FLOW VAR SCRAM SP 1501------+-----1---- 4 CORE INLET FLOW(%) 120.__ 4 ESTIMATED THERMAL POWER ------1----

5 DRIVE FLOW 1 (%)

0 I-w

<( 80 a:

0 "-

I-j

. z w

7 (.)

50 * " a: 40

~ w u a.

L. c c c c ~

0 I H... 0 I...

0 10 20 30 40 0 25 -50 75 100 TIME (sec) CORE FLOW(%)

FIGURE 4.4-5

6-INCH WATER LEVEL SET POINT STEP AT 51.5% RATED POWER' (NATURAL CIR~U~TION)

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

l

.* (THIS FIGURE HAS

• BEEN DELETED}

FIGURE 4.4-6

LOOSE PARTS DETECTION SYSTEM SCHEMATIC DIAGRAM

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

AMENDMENT16 DECEMBER 1984 LOOSE PART ALARM MONITOR GO TO PANEL LPEAC

MAKE A COPY OF HARO FROM LPEAC ALARM LOG

ARRIVE ORDER CIECK ALARM

YES DIAGNOSTIC GO TO PROCEDURES

RESET SYSTEM LOCAL ALARM

ALL. LISTEN TO CHANNELS

SCHEDULE EVAL.UA SPECTRAL TION OF ALL CHANNELS

MONITORING RETURN TO

FI GURE 4.4-7

LOOSE PART ALARM LOGIC

NIAGARA MOHAWK POWER CORP.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAA REVISION 3 EXAMINE AUAM MRIVAL OADERS

NO INJTIATE llMPL ITlllE MJDIFIEO CFAEE PMT> PROBABILITY CALCU..ATION OW>

Tl£ LEADING EXAMINE COMPONENT CONSlLT EDGE OF FIRST OVGS FOR Al.ARM CHANEL POSSIBLE LOOSE PART SERVICE

NO EVALUATE USING PORTABLE MONITOR

CC>>4PARE WAVE FORM WITH GATl£R DATA OTl£R SENSOR PLANT SYSTEM FROM OT1£R JN ZONE

SPECTRAL. OF PERFORM ASSESS Tl£ EVENT DAMAGE OF POTENTIAL NMl.YSJS COMPARE SENSOR LOOSE PMT

---

111111 INTERCHANNEL DELAY TIMES

SPECTRAL OF COMPARE DEVELOP BACKGRCUiO ACTION PLAN VJTH EVENT EVALUATE LOOSE PMTS LOCATION

NO

FIGURE 4.4-8

PLATE THICKNESS..._. CC>>4PUTE IMPACT __ _ LOOSE PART FROM LPEAC DIAGNOSTIC PROCEDURES LOGIC NIAGARA MOHAWK POWER CORP.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 3 SENSOR OK SELECT LPM CHANNEL

LPEAC FALSE EXAMINE YES ALARM LOG

NO ACCEPTABLE VERIFY NOISE LEVEL BACKGROUND

PERFORM LPEAC MAINTENANCE MODE CALCS

YES

MODIFIED VERIFY APO

CHANNEL CHECK/TEST SENSOR,~---.

CABLE AND AMPLIFIER YES CHANNEL OK

>-------t~EARL Y INDICATION OF IMPACT

PERFORM CHECK SIGNAL SPECTRAL r-----11~ VALIDATE OTHER EVALUATION SENSOR IN ZONE

NO F IGURE 4.4-9 VALIDATION PROCEDURES LOGIC LOOSE PART SIGNAL

NIAGARA MOHAWK POWER CORP.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT

USAR REVISION 14 FEBRUARY 2001 in Spbere Diameter

01 ' 3 in z. '

D

10 1 1 in Q

'. - V=lO w

..J V=B w

u u

D Impact Velocity 1-w u \\

w \\

1-w 10° D

~ '

CL w

10- 1 L-~~~~~-'-~~~~~~_._~~~~~---t.~~~~~~....,j

0. 0 5. 0 10. 0 15. 0 20. 0 FREQUENCY. kHz

FI GURE 4.4-10 NOTE: THIS MAP FURNISHED BY EPRI.

MAP AT THREE FEET TYPICAL METAL SPHERE IMPACT FROM SENSOR

NIAGARA MOHAWK POWER CORP.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT

. t __ _ USAR REVISION 3

I /CONTROL ROD UNLOCKING HANDLE *~ ASSEMBLY ISHOWN RAISED AGAINST SPRING FORCE)

UNLOCKING ROD

, / INDEX TUBE -DRIVE

ACTUATING SHAFT

VELOCITY LIMITER

LOCK PLUG SOCKET RETURN SPRINGS

FIGURE 4.6-1

CONTROL ROD TO CONTROL ROD DRIVE COUPLING

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT BOTTOM OF REACTOR VESSEL

HOUSING

CYLINDER--+---+--!

MOVING PISTON (MAIN DRIVE PISTON)

DRIVE WITHDRAW DRIVE INSERT LINE -------. LINE

• ARROWS SHOW WATER FLOW WHEN THE DRIVE IS IN THE WITHDRAWAL MQDE OF OPERAJION.

BALL CHECK VALVE

PR= REACTOR PRESSURE

FIGURE 4.6-2

CONTROL ROD DRIVE UNIT

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT VELOCITY LIMITER CONTROL ROD

CONTROL ROD TO GUIDE DRIVE TUBE COUPLING

HOUSING TO VESSEL "J" WELD

REACTOR

VESSEL BOTTOM HEAD UNCOUPLING ROD THERMAL SLEEVE

OUTER FILTER

DRIVE HOUSING INNER FILTER (THIMBLE)

STOP PISTON AND INDEX TUBE SEALS

COLLET -FINGERS COTIER PIN

COLLET-SPRING SPRING WASHERS BUFFER COLLET-PISTON HOLES AND RINGS

DRIVE HOUSING TO PISTON AND FLANGE WELD SEALS

PRESSURE FLANGE OVER HUB POAT PRESSURE HOUSING UNDER PORT FLANGE BALL CHECK VALVE DRIVE CAGE MAIN FLANGE WELDED PISTON TUBE PLUG TO PISTON TUBE HEAD WELDED WELD PLUG MAIN POSITION INDICATOR FLANGE BOLTS WELL PISTON-TUBE-HEAD RING FLANGE RING FLANGE BOLT

POSITION INDICATOR TUBE TO PISTON TUBE HEAD WELD POSITION INDICATOR HOUSING

FIGURE 4.6-3

CONTROL ROD DRIVE SCHEMATIC

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 19 MAY 1985 BWR 5

2 RING FLANGE 3 SOCl(ET HEAD Fl LUSTER HEAD CAP SCREW !POSITION INDICATOR PROBE MOUNTING I SCREW IRING FLANGE MOUNTING) 4 s ;~~-=~~BEER CFOR PART 4) 8.75 9 O*RING ~PISTON TUBE) 10 NUT lPISTON TUBE!

12 STOP PISTON 1J SPUT BUSHING ISTOP PISTON)

SEAL RING (STOP PISTON) 15 SPRING WASHERS 16 COTTER PIN CSTOP PISTON)

INDEX TUBE 18 SANO 19 COLLET AND PISTON 20 SEAL RING iCOLLET PISTON -INTERNAL) 21 SEAL RING lCOLLET PISTON - EXTERNAL) 2J Fl LUSTER HEAD SCREW !GUIDE CAP PLUG MOUNTING!

25 DRILLED Fl LISTER HEAD SCREW COUTER FILTER MOUNTING) 28 SEAL RING !INNER FILTER*

29 SANO 34 DRIVE SCREW (NAMEPLATE MOUNTING) 35 BALL RETAINER 36 BALL (CHECK VALVE) 37 0-AING (BALL RETAINER)

OWG. 38 41 ~~~~~ 1~ffu~oR PROBE SEE NOTE 2 761E387 50 0-RING {INSERT ANO WITHDRAW PORTS) 51 0-RING ICRO FLANGE FACEI SS SET SCREW PLUG !COOLING WATER ORIFICE}

57 ~6~~~;~~~ SPACER MOUNTING I INOT SHOYVNJ 59 60 BAAR EL 61 GUIOECAP 63.74 NAMEPLATE 64 FLAT ME.AO SCREW.(STRA.INER MOUNTINGI 66 STRAINER 66 OUTER FJLTER 69 ORIVE PISTON 70 SPUn DWG. 71 ~~~EIUNCOUPLING) SEE NOTE I 761E387 72 73 CYLINDER. TUBE. AND l'l.AflGt 77 DOWEL !ALIGNMENT) PIN 7B COLLET HOUSING !PORTION OF OUTER TUBE) 19 !::~~~:~~~~OF CYLINDER, TUBE, ANO FLANGE*

80 81 POSITION INDICATOR SWITCHES 82 INDEX TUBE NOTCH 83 OUTER TUBE (PART OF CYLIND£A, TUllE, AND fLAlllGEl 84 INNER CYLINDER (PART OF CYLINDER, TUBE, AND FLANGE) as THERMOCOUPLE {PART OF POSl"tlON INOICATOR PR08E, 86 STUD IPOFITION OF PISTOlll TUBE) 87 COLLET FINGER (PART OF COLLET AND PlSTONI 88 INDICATOR TUBE !PART OF PISTON TUBE) 89 INNER SEALS (DRIVE PISTON - BUFFER SEALS, 90 INTERNAL BUSHING !DRIVE PISTON) 91 EXTERNAL BUSHING {()RIVE PISTON) 92 OUTER SEALS IORIVE PISTON!

83 INSERT PORT !INSERT AND SCAAM llllLET/WITHDRAW OUTLET) 94 RING MAGNET IPART OF DRIVE PISTONI 95 CABl.E CPOSITJON iNOICATORI 116 POAT TO COLLET PISTON !WITHDRAW PRESSURE TO COLLET PISTON) 97 ~~~:~::"H~:Gi::ITHDRAW INLET/INSERT OUTLET AND 116 INNER SEALS !DRIVE PISTON -DRIVE*OOWN SEALS!

INNER SEALS (DRIVE PISTON -DRIVE-UP SEALSJ 100 - WATER PORTS IN COLLET HOUSING 101 BUfFER ORIFICES IN PISTON TUBE (TYPICAL)

NOTES:

I. FOR MODEL 7 ROB144E ITEMS 71 AND 72 ARE MADE OF A SINGLE P1ECE. FIGURE 4.6-4

2. THE POSITION INDICATOR PROBE (ITEM 41} IS SUPPLIED SEPARATELY FOR MODEL 7RDB144E.

3. MODEL 7RDB144FG007 IS AN ACCEPT ABLE MODEL 7RDB144C OR E CONTROL ROD REPLACEMENT FOR BWR/2-5 MODELS. DRIVE CCUTAWAY)

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

UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 15 OCTOBER 2002 _j

~

. r:J LJ LJ e_ LI

-:. ~

di" 11' [TI

~: I ~ Ll e_ LJ......

I 0 _J

!lllitMl""'l!QI,

.*. ___ Cf~~E]

________ El El___,-,., El~:

• • ~EJ~EJ L __._ __ _,

El

TRUCNTNl/O,QUIPMENTl'UtlERSTOBEPAEF'IXEO

"'UCCl'.'1VHIMAOlll='F£A£NTPR£FIXISSHOVN. l*I VIL.l..M:Pt.AC&: JHEOASH(-J ININSTR\\MENT TENS. NUMeli'.ASWHICMAAIPARTOFNUCLEARSAFETY

FIGURE 4. 6-0Sb

CONTROL ROD DRIVE HYDRAULIC SYS TEH

NINE MILE POINT NUCLEAR STATION - UNIT 2 SOUACE.PI0-388-14 SCRIBA, N. Y.

TITLE.CONTROl..AOOORIYEHYORAULIC$YSTEH UPDATED SAFETY ANALYSIS REPORT

USAR REVISION 18 OCTOBER 2008 _j NOT;:

SYSl£M S£L!CTIOO Off{Cf'S *If: ll'(JIC4lt0 BY ~LTIPL£ MflL ITCM Nw.tl£RS

REF£RENCE DOCUMENTS MPL ITEM No.

1 CONTROL ROO ORIVE tlYO SYS P&ID - - --- - - - -C11/C12*1010 2 CONTROL ROO ORIVE HYO SYS FCO - - - --- - - -Cll/C12*t030 3 OEStGN SPECtFICA TION - - - - - - - --- - - - - -Cl1/C12*4010

4. HYDRAULIC CONTROL UNIT - - - - - - --- - - - - -c11;c12-0001 5 PIPING&. INSTRUMENT SYMBOLS - - - - - --- - ----A42.-1010

6. PROCESS DATA - - - - - - - - - - - - - - - -- --Cll/ C12-1020 7 REACTOR WATER CLE'..AN UP SY5 P&lD - - - - -- -- --G 31/G33-10 IO 8 REACTOR R£.CIRC 5YS P&ID- ~ - - - ---- - --- G33/83S-1010 NOTES:

I, FOR DATA PERTAINING TO NUMBERS WITHIN HEXAGONS REFER TO PROCESS DATA. FIG. 4.b"'7

2. SOURCE OF CRD SYSTEM WATER SHALL BE NORM~LLY FROM CONDENSATE TREATMENT L __ INSERT __ J SYSTEM. CONOENSATE STORAGE TANK IS THE ALTERNATE SOURCE IF CONO£NSATE TREATMENT

@-1r 15 SYSTEM IS NOT IN OPERATION. FOR DETAILED DESIGN REQUIREMENTS FOR SOURCE ANO ~UALITY REACTOR Of WATER) *SEE REF 3.

VESSEL 3. DELETED

4. PUMP SUCTION RELIEF VALVES SET AT 150 PSIG.

RECIRCULATION SYSTEM SEAL PURGE LINE -il

F03~ CONTROL DRIVE DRIVE ROD WATER OPEN AT 2 gpm & 80pt(d a:

FILTER 0003 OTHER HCU'S OTHER Hcu*s WITHDRAWAL INSERT a

TO HCU'~ Lt.I < rCONTAINMENT l: _.._..............-.--~-.---.....

.... II) WITHDRAWAL INSERT

~-___.,_~---J ::>

TO HCU'5 <

I x

w

COOLING HEADER

0001

DRIVE HEADER

USAR REVISION 23 OCTOBER 2018 CHARGING HEADER

DR'IV£ WA.TE.R. FIGURE 4.6-6 PUMP COOl SEE N01E 4 WCS PUMPS HYDRAULIC SEAL/PURGE FLOW CONTROL CONTROL ROD DRIVE UNIT SCRAM HYDRAULIC SYSTEM DISCHARGE HEADER AND INSTRUMENT VOLUME NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N. Y.

UPDATED SAFETY ANALYSIS REPORT L _J J,

MODE A NORMAL OPtRAHON

LtJCAilDN 0 lA l 2 2A 3 4 s 5A s 7 a 9 1'2l ti 12 l'.3 COND1TJONS.

FLOW, GFIM "l3. "J3 93 2ril n n 10 63 2x I, ORI\\1~$ LATt;H£;D, G3 57 lj7 ~3 0 0 2 2. REACTOR STEAM OOME PRESSURE PIT l0~~ fSIO.

PRESSURE PSlG 21 lq 1487 1487 1487 1476 1462 l4GC! PR +-30 PR FLCJW ro DRIVES. MINIMtJt-1 REOUCREO l455 PR+262 PR+2Gl2 PR+30 3. MAX!MUM COOL.ING PR PRt-30 PRESSURE AT POSITION lA IS 21il FEET Of WATER AT 200 GPM.

• - - HOOE A SIZES THE COOLl~D WATER HEADERS.

LOCATlON 0 M l5 16 17 18 20 2t 22 23 24 2~ 2s 27 LlNE LOSS FROM LOCATION rn ro LOCArION 2:el SH~LL NOT EXCEED 3 f'SU:l.

FLOW, GFIM. 4 6 rlJ QJ 0 34MAX.J4MA>< J4MAX,34MAX 0 0 ~ 0

PRESSURE PSIG PRt-30 PRt-30 1-455 SEE NOTE 3C PR PR PR 0

MOOE 6 ROD lriSERTlON CfDfl NOTf.S St:E Stlt.ET 2.l

LOC#\\TION 0 lA l 2 :ZA 3 4 s 5A 6 7 a q lri9 H 12 13 CONOITIONS.

FLO\\l,GPM G3 ~3 qJ 2* 2e 73 73 L0 63 63 57 57 sci 0.7 2 1-OR l IJES ENS ~fl nNO..

2. REACTOR 5T£AM DOME PRESSUflE AT rn'20 PS!G.

f'Rf.SSUR£ PSlG ;;'l l? MS7 H87 M67 H76 !462 HG.2 H55 DR-rZG~ PJl+26~ PR+'J0 PA+-~0 <PR+6 {PFJ+a PR t-:lla J. MA:<fMUM DRIVING FLOW TO DRIVES.

MOOE B SrZES THE DRIVE WATEA HEADERS.

LOCATIOl'i 0 t4 1~ !G 17 ta i~ 21 22 2:3 ~4 2-:; i~ 27 FLO'W.CPM 0 2 0 4 ~ 0 4 4 1.~,7.7.7 0 PRESSURE PSlC PR+'.JCi' PfH3r.!l 1-455 PR+26~ PR+25'2 PR+L5 P:fl+~I PR+'lla PR PJ'\\1'21/J F'R+2© P1h8 0 MA~ MAX MA'X

MODE C SCRAM

LOCATION 0 lA l 2 21+ 3 4 5 5A s 7 a 9 1~ l\\ 12 13 CONDITIONS:

Fl..OW', C#lM 45 45 45 2* 20 25 25 11§ 15 15 J5 J5 !5 JS H~t3 " 1. ORl'IES SCAAMMlNCl.

2. REAC:!OR STEAM DOME: PR5.SSURE AT 102B PSlO.

PRESSIJRE PSICl 21 21 t55'3 1487 1550 SEE SEE J. FLOWS BAS~O ON l'o!~)(lMUM ROD \\IElOCIT'f OF 85 INC-HES PEA SECOND tiOTE, NOTf~ MODE C S~ZES THE INSERT AND WITHDRAW l..1NES,

~

---

LOCATION 0 H 15 l6 17 16 28 21 22 23 24 2S -2G 27 FLOW,GPM 0 fC1 ' 0 0.l,S£~ ~PFflO); ~ 0 ~ 'HJ Cl0 -3..6 38 30 !'IOTE.'9 5565 PRESSOOE P'SIG UGI' 73Z PR 256 ~'4 G5 MIN MIN MA:;( MA)( SEE MOOE D SCRAM COMPLETED NOTE10

LOCATION 0 1A l 2 2tl 3 4 5 5A G 7 6 ~ rn 11 l2 l3 CCJNDITlONS.

FLOW,CPM 200 20e 2B0 12 l0 iea 190 ta 15 15 l5 15 15 15 14.~ " 1. SCRAMMING OF DRllJES COMPLETED-

2. REGICTDR STEAM DOME PRESSURE AT I'll PSIG.

Pl11::".S5\\JRE P-SlG 21 l~ 12l0 121~ ) FR ) F'A ) PA ) PR )PR ) Pfi 3.MA~lMUM CRU SUP~LV PUMP FLOW~

MODE D srzE'.s !HE PUMP' SUCTION LINE.

Nori::: MlN !MUM ~CCiJMUUHOR !"RECHARGE PRESSURE IS 56'!i FStO.

LOCATION 0 l4 15 16 17 18 20 21 22 23 2f 25 2G 27 FLOW,(jPM ~ 0 t55 0 0 121 ~-q2 r21_q2 0.".!2 SEE SEE liLl ~ NOTE:~ NOTE:9

P~ESSURE PSIG '168 1$ 76 PR 65 65 65 MA~ MAJ( MAX

• SEE NOfE 10.

USAR REVISION 23 OCTOBER 2018

FIGURE 4.6-7 CONTROL ROD DRIVE HYDRAULIC I THIS DRAWING CREATE_Q ELECTRONICALLY ] SYSTEM PROCESS DATA SHEET 1 OF 3

NINE MILE POINT -

NUCLEAR STATION UNIT 2 SCRIBA, N. Y.

UPDATED SAFETY ANALYSIS REPORT L T _J NOTES:

1. DEFINITION OF SYMBOLS 7. PUMP SUCTION RELIEF VALVES SET AT 150 PSIG.

PR-INDICATES PRESSURE OF THE REACTOR MEASURED IMMEDIATELY ABOVE THE CORE PLATE. 8. PROCESS DIAGRAM 11201448 SHALL BE USED WITH ANO FORM PART OF

2. MAXIMUM OPERATING TEMPERATURES THIS PROCESS DATA. IF THERE ARE ANY CONFLICTS BETWEEN THE THE MAXIMUM SYSTEM OPERATING TEMPERATURE WILL NOT EXCEED 150 DEG. F. PROCESS DIAGRAM ANO THIS PROCESS DATA, THE PROCESS DATA SHALL GOVERN.

FROM LOCATION I THROUGH 27 WITH THE FOLLOWING EXCEPTIONS. 9. DURING SCRAM, THIS FLOW WILL BE DIRECTED INTO THE SCRAM DISCHARGE VOLUME.

FOLLOWING SCRAM, THIS FLOW WILL DECLINE AS VALVE F002 CLOSES AND AS THE SCRAM DISCHARGE VOLUME PRESSURIZES TO EQUAL THE REACTOR PRESSURE.

AFTER THE SCRAM DISCHARGE VOLUME ANO THE REACTOR VESSEL PRESSURE HAVE EQUALIZED, FLOW WILL BE DIVERTED TO THE REACTOR VESSEL VIA THE CRD MODE A- <LEAKING SCRAM WITHDRAW LINES AT A FLOW RATE DEPENDENT ON THE REACTOR PRESSURE, DISCHARGE VALVE> I.E. IA.l APPROX. 15 GPM AT '0' PSIG. REACTOR PRESSURE.

IB.l APPROX. 6 GPM AT '1000 " PSIG. REACTOR PRESSURE.

10. THIS VALUE APPLIES IMMEDIATELY FOLLOWING COMPLETION OF SCRAM.

PRESSURE WILL SUBSEOUENTL Y EQUALIZE WITH REACTOR PRESSURE.

24 11. DESIGN PRESSURE AND TEMPERATURE SHOWN IN "TABLE I" IS FOR INFORMATION 25 ONLY ANO IS THE BASIS FOR DESIGN OF BWRS SUPPLIED EQUIPMENT. ESTIMATED LINE ESTIMATED LINE SIZES ARE FOR INFORMATION ONLY. ACTUAL LINE SIZES AS DETERMINED BY THE SIZE !INCHES> PIPING DESIGNER SHALL MEET THE PROCESS DATA HYDRAULIC REQUIREMENTS.

A. MAXIMUM CHARGING WATER PRESSURE SHALL BE 1600 PSIG NOMINAL. 12. ALL VALUES SHOWN IN MODES A, B, C, ANO 0 ARE NOMINAL UNLESS OTHERWISE NOTED, 21-22 24-25 27A-27B 27B-27 27 27C-270 ACCUMULATOR PRECHARGE PRESSURE SHALL BE 575 PSIG NOMINAL, 13. INSERT ANO WITHORAWL PIPING SHALL BE DESIGNED FOR HYDRODYNAMIC LOADS AS LOCATION 580 PSIG MAXIMUM, AT 70" F. A RESULT OF A NORMAL SCRAM AT ZERO AND NORMAL REACTOR PRESSURES. SHORT ISEE NOTE 13> ISEE NOTE 13> ISEE NOTE 13! <SEE NOTE 13: llSEE NOTE 14> <SEE NOTE 14l B. DELETED STROKE AND FULL STROKE SCRAM ANO A SCRAM WITH FAILED CRD BUFFER. PLANT

C. LOCATION 20, 21 ANO 22-THE ANTICIPATED RANGE OF COOLING WATER LOAD COMBINATIONS SHOULD INCLUDE CONSIDERATION OF THOSE SYSTEM DIFFERENTIAL PRESSURE IS FROM APPROXIMATELY 6 PSI TO A MAXIMUM HYDRODYNAMIC LOADS.

DESIGN TEMP. OF 30 PSI. REDUCED DIFFERENTIAL PRESSURE rs ACCEPTABLE SUBJECT TO 14. THE SCRAM DISCHARGE VOLUMES <SDV> AND ITS VENT AND DRAIN PIPING DESIGN SHALL MAINTA1NING THE REQUIRED COOLING WATER FLOW TO THE DEVICES. CONSIDER THE HYDRODYNAMIC LOADS WHICH MAY OCCUR DUE TO ([) SDV ISOLATION AND

0. LOCATION 23-MAXIMUM DRIVE COOLING REQUIREMENTS WlLL NOT EXCEED 12> SOV VENHNG AND DRAINING FOLLOWING A SCRAM COMPLETION AT REACTOR 0.34 GPM/ORlVE FOR THE CONDITIONS LISTED. MINlMUM DRIVE COOLING OPERATING PRESSURE.

REQUIREMENTS WILL NOT BE LESS THAN 0.20 GPM/ORIVE.

• SEE CRO SYSTEM DESIGN SPECIFICATION.

• • 2 [NCH HEADER TO EACH HALF OF THE TOTAL QUANTITY OF HCU'S. 4. MODE B-A. l,,r;JCf\\TION 13 ANQ 14-INSERT VAi-VE F'i]'i]7-A 1;~0$!;$ ON 0f1!VE !NS1"RT SIGNAL. WITHDRAW VALVE F007-B ON DRIVE WITHDRAW SIGNAL BUT DOES NOT STAY CLOSED DURING SETTLING.

B. LOCATION 18-THE CRO DRIVE WATER PRESSURE SHALL NOT BE LESS THAN PR+250 PSIG, FDR THE CONDITIONS 1ND!CATED.

5. MODE C-A. DELETED

B. THE TEMPERATURES LISTED lN NOTE 2 FOR POSITION 24, 25 ANO 27 MAY BE ASSUMED TO OCCUR LESS THAN l PERCENT OF THE OPERATING LIFE OF THE SYSTEM.

C. LOCATION 21 TO 22-THE PRESSURE DROP FROM LOCATION 21 TO 22 SHALL

0. LOCATION 23-A NEGATIVE FLOW RATE lNDICATES FLOW FROM THE REACTOR THROUGH THE DRlVE SEAL, lNTO THE CRD. THE MAXIMUM LEAK RATE FROM THE REACTOR CAN REACH 10 GPM PER DRIVE.

E. LOCATlON 24 TO 25-THE PRESSURE DROP FROM LOCATION 24 TO 25 SHALL NOT EXCEED 162 PSl AT 30 GPM FOR ANY CRO.

F. RESPONSE TIME OF FCV-F002 IS SUCH THAT SCRAM IS COMPLETED BEFORE FCV-F002 STARTS TO CLOSE.

G. SCRAM DRAlN VALVE F0ll ANO VENT VALVE F0l0 CLOSE WITH A SCRAM SIGNAL.

6. MODE 0-

B. LOCATION 27-THE SCRAM 01SCHARGE VOLUME SHALL BE SIZED SO THAT THE RE SUL TlNG PRESSURE AFTER llil0 PERCENT STROKE IS LESS THAN 65 PSIG.

FIGURE 406-7 CONTROL ROD DRIVE HYDRAULIC SYSTEM PROCESS DATA SHEET 2 OF 3 NINE MILE POINT THIS DRAWING CREATED ELECTRONICALLY NUCLEAR STATION-UNIT 2 SCR IBA9 NY UPDATED SAFETY ANALYSIS REPORT USAR REVISION 1 6 OCTOBER 2004 I TABLE2: THERMAL CYCLES FOR SAFETY RELATED PIPES AND PIPE SUPPORTS TABLEZ.: !CONTINUED>

A. ~~6R~~i~o~o:+~~~~~~~)L LINES 131, 15) & 161, ICRD FLANGE TO 16 ~o~~~i ~EYr?f~~LriCDRAlN VAL VESl B. ~'6~Ti~~T~N~Tl\\RoA~H~IS~~~:3Eol~~~~~~E EXPECTED EXPECTED PRfSSURE TEMPERATURE FREQUENCY DURATION PRESSURE TEMPERATURE FREQUENCY DURATION

!psigl i*n PERPlANT PER EVENT lpsigl 1*F1 PERPLANT PEREVENT LIFE !91 LIFE 191

1. STANDBY OPERATION 1250 121 CONSTANTTEt.1P

!ALLLINESAFHCTEDI 45hitlt$7)/150t.1AX 2.SCRAM !ALL OR SINGLE 1250 121 AMBIENT TO 280 121 1250 121 AMBIENT TO LINES AFFECTED> 2BOl2)

3.SCRAM-COLD !All OR SINGLE LINE AFFECTED) 4.INSERT AND WITHDRAWAL MOTIONISINGLELJNE IPR+300l CONSTANT TEMP AFFECTEDI 45 ~.nN7!/150 MAX

~EUVRECNHTA::o OTN~t' :r:~l~~B~~T~gNlHOSE PROJECTS WHICH IA) AMBIENT TO 45 18)

!Bl AMBIENT TO 150 TABLE 2. ICONTINUEDI

c. ~1~5R~~iT~o~o~Nr5REcf~ J~~f,s (5) & 13), ICRO FLANGE TO

6.ABNORMAL SYSTEM 1510 MAX CONDITIONS 110l PRESSURE TEMPERATURE

!S1NGLELINESAFFECTEDll4) lpsi9l 1*F1

AMB1ENTTQ <25 clO ~OURS 500(1JMAX

8.ANTICIPATEOTRANSIENT 1500 2.A8NORMAL SYSTEM WITHOUT SCRAM lALl !PASSIVE) CONDITIONS!ALL LINES AFFECTED> LINESAFFECTEDllBJ

3.SCRAM !All OR SINGLE 1510MAX 110)

LINES AFFECTED) 4.INSERT ANO WITHDRAWAL CONSTANT TEMP MOTION !SINGLE LINE 45 MINlJJ/150 MAX NOTES FOR TABLE 2. AFFECT EDI

11) PIPE SUPPORT INTEGRITY SHOULD BE MAINT AINEO FOR THERMAL EXPANSION 5.ABNORllAAL SYSTEM CONDITIONS CONDITIONS lALL OR 1510 MAX THIS MAY BE DEMONSTRATED BY VISUALLY INSPECTING THE PIPE SUPPORTS RANDOM SINGLE LINES 1101

~~~c%~Ag~~?T~~~~:ING ANY or THE FOLLOWING RARE EVENTS AT HOT M"FEClED1<41

~f t~~;:~~~;:~R~!g~~$~r~~;~~ pi~;;~ :~T:,:: TIME

12) g~~gl~l6~~Si~~~M~~-D TEMPERATURE CONDITIONS. HOT REACTOR

IJ) ~~~E~01L~ S~~OULO BE SIZED AS A MINIMUM TO

14)rn~T~~ENJA1~;fuglE6Su~l~CK CRD MAINTENANCE, AND PRESSURE t51~Jl!~~ :~DA w~~~E~~Wtrl :1~~~u~ro~~~A~E A~E~l~~DA~gRN~~~:~-rPE~Nc~~~

PRESSURES, SHORT STROKE AND FULL STROKE SCRAMS, ANO A SCRAM

~gNHSID~:A~ll<fJ> ~FR~~Eu;[Es~s~'E~N~YLD°to°-~~~f~~tT~g~~s~HOULD INCLUDE

16lTHE SCRAW DISCHARGE VOLUME ISDV> AND WITHDRAWAL PIPING DESIGN SHOULD CONSIDER THE HYDRO-DYNAMIC LOADS WHICH MAY OCCUR DUE TO 11 SDV ISOLATION AND 21 SDV VENTING ANO DRAINING FOLLOWING Sc.RAM COMPLETION.

171FOR DESIGN OF CRD PIPING 45 *F MIN. 15 REFLECTIVE OF THE MINIMUM CONDENSATE STORAGE TANK !CSTl TEMPERATURE AND CAN BE REVISED TO AGREE WITH CST ENVIRONMENTAL CONDITIONS OR

~llW¥i~~- CRD PIPING AMBIENT CONDITIONS, WHICHEVER IS

(8) ~:~/~~p H~¥c~b°~:~2~\\~1\\~~~ TA..,f~f Ds{~rNJ'JNSATE STORAGE

191 THE EVENT FREQUENCIES GIVEN ARE NOT REFLECTIVE OF THE NUMBER OF STRESS CYCLES ASSOCIATED WITH EACH EVENT.

110> g6~1g 1~ 1 6:~s;~~JtJ.~~-D TEMPERATURE CONDITIONS. HOT ANO COLD REACTOR

FIGURE 4.6-7 CONTROL ROD DRIVE HYDRAULIC SYSTEM PROCESS DATA

sHEET-3 OF3

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 23 DECEMBER 1985 SCRAM VALVE PILOT AIR Ill!. ISOLATION VALVE --------..-.~l(wa1...------CHARGING WATER RISER

ISOLATION VALVE...{jD&J----- ISOLATION VALVE WITHDRAWAL RISER EXHAUST WATER RISER ISOLATION VALVE ISOLATION VALVE DRIVE WATER RISER INSERT RISER ~-------SCRAM PILOT VALVE ASSEMBLY

ISOLATION VALVE ----4-lCll:a:.tl COOLING WATER RISER JUNCTION BOX

ISOLATION VALVE WIRING TROUGH ASSEMBLY SCRAM DISCHARGE RISER

OUTLET SCRAM VALVE UNIT INTERCONNECTING INLET SCRAM VALVE CABLE

MANIFOLD

DIRECTIONAL CONTROL VALVE (WITHDRAW AND SETTLE) SHUTOFF VALVE

WATER ACCUMULATOR DRAIN

SCRAM ACCUMULATOR N 2 CYLINDER SCRAM WATER ACCUMULATOR

ACCUMULATOR N2 PRESSURE FRAME INDICATOR

CARTRIDGE VALVE ACCUMULATOR N2 CHARGING

~h.,,~~-~- ACCUMULATOR INSTRUMENTATION ASSEMBLY

FIGURE 4.6-8

CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT

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

-STEEL FORM LINER

- CRO HOUSING l..

1--++------'-- HANGER ROD

PEDESTAL VESSEL SU"'ORT

GRID CLAMP SUPPORT BAR

FIGURE 4.6-9

CONTROL ROD DRIVE HOUSING SUPPORT

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