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
ML22292A107	List: ML22292A061 ML22292A062 ML22292A063 ML22292A064 ML22292A065 ML22292A066 ML22292A067 ML22292A068 ML22292A069 ML22292A070 ML22292A071 ML22292A072 ML22292A073 ML22292A074 ML22292A075 ML22292A076 ML22292A077 ML22292A078 ML22292A079 ML22292A080 ML22292A081 ML22292A082 ML22292A083 ML22292A084 ML22292A085 ML22292A086 ML22292A087 ML22292A088 ML22292A089 ML22292A090 ML22292A091 ML22292A092 ML22292A093 ML22292A094 ML22292A095 ML22292A096 ML22292A097 ML22292A098 ML22292A099 ML22292A100 ML22292A101 ML22292A102 ML22292A103 ML22292A104 ML22292A105 ML22292A106 ML22292A108 ML22292A109 ML22292A110 ML22292A111 ... further results
References
NMP2L2821
Download: ML22292A081 (24)

Text

{{#Wiki_filter:1 REACTOR CORE MATERIAL RADIUS INCHES NO. NAME 1 REACTOR CORE 93.56 2 WATER 101.4 3 SHROUD 103.4 4 WATER 125.5 -J 5 VESSEL 131.68 6 AIR L 4WATER 2 WATER___/'/. 5 VESSEL 3SHROUD~ MATERIAL MATERIAL DENSITY WATER 0.274 g/cm3 U02 2.642 g/cm3 ZIRCONIUM 0.896 g/cm3 WATER 0.74 g/cm3 304L STAINLESS STEEL FROM ASME SA 240 WATER 0.74 g/cm3 CARBON STEEL FROM ASME 533 AIR

• 1.3 x 103 g/cc FIG. 4.3-1 MODEL FOR ORIGINAL ONE DIMENSIONAL TRANSPORT ANALYSIS OF VESSEL FLUENCE T

NINE MILE POINT NUCLEAR STATION-UNIT 2 SCRIBA, NY UPDATED SAFETY ANALYSIS REPORT USAR REVISION 16 OCTOBER 2004 ~ _J

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 L 40 50 60 PERCENT OF CORE RADIUS 70 80 90 100 FIG. 4.3-2 RADIAL POWER DISTRIBUTIONS USED IN THE ORIGINAL VESSEL FLUENCE CALC. NINE MILE POINT NUCLEAR STATION-UNIT 2 SCRIBA, NY UPDATED SAFETY ANALYSIS REPORT USAR REVISION 16 OCTOBER 2.0.04 _J

100 '10 80 70 a: LlJ

ir:

60 0 0.. I-z LlJ (..) 50 a: LlJ 0.. 40 30 20 10 A. NATURAL CIRCULATION B. LOW REC!RC. PUMP SPEED VALVE MINIMUM POSITION C. LOW REC!RC. PUMP SPEED VALVE MAXIMUM POSITION D. RATED RECIRC. PUMP SPEED VALVE MINIMUM POSITION E.MID-RANGE CHARACTERISTIC, PARTIAL FCV OPENING F.UPPER LIMIT OF CORE FLOW TYPICAL STARTUP PATH 10 20 30 40 50 60 PERCENT CORE FLOW THIS DRAWING CREATED ELECTRONICALLY 70 80 F REGION IV CAVITATION REGION REGION Ill '10 100 FIGURE 4.4-1 110 120 TYPICAL POWER-FLOW OPERA TING MAP NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S

0 x "N x 0 ~ a: c( 0 w 0 1.2------------------------, ULTIMATE PERFORMANCE LIMIT 1.01----------------------------1 0.8 0.6 105% ROD LINE 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 STM LINE PRES RISE (psi) 2 PEAK FUEL CENTER TEMP 3 TURBINE PRES RISE (psi) 3 AVE SURFACE HEAT FLUX 4 CORE INLET SUB (Btu/lb) 150 4 FEEDWATER FLOW 125 5 CORE AVE VOID FRAC (%) 5 VESSEL STEAM FLOW 6 TURBINE STEAM FLOW (%) .Cl w 75 ~ 100 0:

u.

,/- A 0 ll I- /}, /'-' z w Q u 50

===-==' 25 0: ~ w 0.. v ~ I -25 I 0 0 10 20 30 40 0 10 20 30 40 TIME (sec) TIME (sec) 1 LEVEL (inch-ref-sap-skirt) 1 NEUTRON FLUX 2 WR SENSED LEVEL (inches) 2 SURFACE HEAT FLUX 3 NA SENSED LEVEL (inches) 120 3 FLOW VAR SCRAM SP 150 4 CORE INLET FLOW(%) 4 ESTIMATED THERMAL POWER 5 DRIVE FLOW 1 (%) Cl w 100 I-80 <( 0:

u.

j 0 I-z w Q u 40 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 4 CORE INLET SUB (Btu/lb) 150 4 FEEDWATER FLOW 125 5 CORE AVE VOID FRAC (%) 5 VESSEL STEAM FLOW 6 TURBINE STEAM FLOW(%) c 0 75 ~ 100 <( a: ~ ~

u.

0 H u 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) 120 3 FLOW VAR SCRAM SP 150 4 CORE INLET FLOW(%) 4 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 NEUTRON FLUX 2 PEAK FUEL CENTER TEMP 3 AVE SURFACE HEAT FLUX 1501------1-----+--- 4 FEEDWATER FLOW 5 VESSEL STEAM FLOW OW-L~J....L..1'1-1...1.-'-----L------,-'----~-~u~~* 0 10 20 30 40 TIME (sec) 1 LEVEL (inch-ref-sep-skirt) 2 WR SENSED LEVEL (inches) 3 NR SENSED LEVEL (inches) 1501------+-----1---- 4 CORE INLET FLOW(%) 5 DRIVE FLOW 1 (%) 50 7 ~ u L. c c c c 0 I H 0 10 20 30 40 TIME (sec) 0 w I- <( a: "-0 I-z w (.) a: w

a.

1 VESSEL PRES RISE (psi) 2 STM LINE PRES RISE (psi) 3 TURBINE PRES RISE (psi) 4 CORE INLET SUB (Btu/lb) 1251----+----+--- 5 CORE AVE VOID FRAC (%) 6 TURBINE STEAM FLOW(%) c -2st1 I I I I 1 I I I 0 10 c c

1. NEUTRON FLUX 20 30 TIME (sec) 2 SURFACE HEAT FLUX 3 FLOW VAR SCRAM SP 40 -

1 120.__ 4 ESTIMATED THERMAL POWER ------1---- 80 j 40 ~ 0 I 0 25 50 75 100 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 GO TO MONITOR PANEL LPEAC MAKE A HARO COPY OF ALARM LOG FROM LPEAC CIECK ALARM ARRIVE ORDER RESET SYSTEM LOCAL ALARM . LISTEN TO ALL CHANNELS SCHEDULE SPECTRAL EVAL.UA TION OF ALL CHANNELS RETURN TO MONITORING YES FI GURE 4.4-7 GO TO DIAGNOSTIC PROCEDURES LOOSE PART ALARM LOGIC NIAGARA MOHAWK POWER CORP. NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAA REVISION 3

EXAMINE AUAM MRIVAL OADERS EXAMINE Tl£ LEADING EDGE OF FIRST Al.ARM CHANEL CC>>4PARE WAVE FORM WITH OTl£R SENSOR JN ZONE PERFORM SPECTRAL. OF EVENT NMl.YSJS COMPARE SPECTRAL OF BACKGRCUiO VJTH EVENT CC>>4PUTE IMPACT NO CFAEE PMT> INJTIATE MJDIFIEO llMPL ITlllE PROBABILITY OW> CALCU..ATION NO NO COMPARE SENSOR

---

111111 INTERCHANNEL DELAY TIMES EVALUATE LOOSE PMTS LOCATION FIGURE 4.4-8 CONSlLT COMPONENT OVGS FOR POSSIBLE LOOSE PART SERVICE EVALUATE USING PORTABLE MONITOR GATl£R DATA FROM OT1£R PLANT SYSTEM ASSESS Tl£ POTENTIAL DAMAGE OF LOOSE PMT DEVELOP ACTION PLAN PLATE THICKNESS..._. __

LOOSE PART DIAGNOSTIC PROCEDURES LOGIC FROM LPEAC NIAGARA MOHAWK POWER CORP. NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 3

SELECT LPM CHANNEL EXAMINE LPEAC FALSE ALARM LOG PERFORM LPEAC MAINTENANCE MODE CALCS VERIFY MODIFIED APO PERFORM SPECTRAL EVALUATION NO YES SENSOR OK VERIFY ACCEPTABLE BACKGROUND NOISE LEVEL YES CHECK/TEST CHANNEL SENSOR,~---. YES CHANNEL OK >-------t~EARL Y INDICATION CABLE AND AMPLIFIER NO OF IMPACT CHECK SIGNAL r-----11~ VALIDATE OTHER SENSOR IN ZONE F IGURE 4.4-9 LOOSE PART SIGNAL VALIDATION PROCEDURES LOGIC NIAGARA MOHAWK POWER CORP. NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 14 FEBRUARY 2001

. t __ _ 01. z D

10 1 Q

'. w

..J w u u < D w 1-u w 1-w 10° D ~ w CL \\ \\ in 3 in Spbere Diameter 1 in V=lO V=B Impact Velocity 10- 1 L-~~~~~-'-~~~~~~_._~~~~~---t.~~~~~~....,j

0. 0

5. 0

10. 0

15. 0

20. 0 NOTE: THIS MAP FURNISHED BY EPRI.

FREQUENCY. kHz FI GURE 4.4-10 TYPICAL METAL SPHERE IMPACT MAP AT THREE FEET FROM SENSOR NIAGARA MOHAWK POWER CORP. NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 3

UNLOCKING HANDLE ISHOWN RAISED AGAINST SPRING FORCE) VELOCITY LIMITER SOCKET I /CONTROL ROD

• ~

ASSEMBLY UNLOCKING ROD / INDEX TUBE - DRIVE ACTUATING SHAFT LOCK PLUG 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--+---+--! DRIVE INSERT LINE -------. BALL CHECK VALVE MOVING PISTON (MAIN DRIVE PISTON) FIGURE 4.6-2 DRIVE WITHDRAW LINE

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

PR= REACTOR PRESSURE CONTROL ROD DRIVE UNIT NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT

VELOCITY LIMITER CONTROL ROD TO DRIVE COUPLING UNCOUPLING ROD OUTER FILTER DRIVE HOUSING (THIMBLE) INDEX TUBE COLLET-FINGERS SPRING WASHERS BUFFER HOLES HOUSING TO FLANGE WELD PRESSURE OVER POAT HOUSING FLANGE DRIVE MAIN FLANGE PISTON TUBE TO PISTON TUBE HEAD WELD MAIN FLANGE BOLTS PISTON-TUBE-HEAD RING FLANGE BOLT POSITION INDICATOR TUBE TO PISTON TUBE HEAD WELD CONTROL ROD GUIDE TUBE HOUSING TO VESSEL "J" WELD REACTOR

VESSEL BOTTOM HEAD THERMAL SLEEVE INNER FILTER STOP PISTON AND SEALS COTIER PIN COLLET-SPRING COLLET-PISTON AND RINGS DRIVE PISTON AND SEALS FLANGE HUB PRESSURE UNDER PORT BALL CHECK VALVE CAGE WELDED PLUG WELDED PLUG POSITION INDICATOR WELL RING FLANGE 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

L BWR 5 OWG. 761E387 DWG. 761E387 2 3 4 s 8.75 9 10 12 1J 15 16 18 19 20 21 2J 25 28 29 34 35 36 37 38 41 50 51 SS 57 59 60 61 63.74 64 66 66 69 70 71 72 73 77 7B 19 80 81 82 83 84 as 86 87 88 89 90 91 92 83 94 95 116 97 116 - 100 101 RING FLANGE SOCl(ET HEAD CAP SCREW IRING FLANGE MOUNTING) Fl LUSTER HEAD SCREW !POSITION INDICATOR PROBE MOUNTING I

~~-=~~BEER CFOR PART 4)

O*RING ~PISTON TUBE) NUT lPISTON TUBE! STOP PISTON SPUT BUSHING ISTOP PISTON) SEAL RING (STOP PISTON) SPRING WASHERS COTTER PIN CSTOP PISTON) INDEX TUBE SANO COLLET AND PISTON SEAL RING iCOLLET PISTON - INTERNAL) SEAL RING lCOLLET PISTON - EXTERNAL) Fl LUSTER HEAD SCREW !GUIDE CAP PLUG MOUNTING! DRILLED Fl LISTER HEAD SCREW COUTER FILTER MOUNTING) SEAL RING !INNER FILTER* SANO DRIVE SCREW (NAMEPLATE MOUNTING) BALL RETAINER BALL (CHECK VALVE) 0-AING (BALL RETAINER) ~~~~~ 1~ffu~oR PROBE SEE NOTE 2 0-RING {INSERT ANO WITHDRAW PORTS) 0-RING ICRO FLANGE FACEI SET SCREW PLUG !COOLING WATER ORIFICE} ~6~~~;~~~ SPACER MOUNTING I INOT SHOYVNJ BAAR EL GUIOECAP NAMEPLATE FLAT ME.AO SCREW.(STRA.INER MOUNTINGI STRAINER OUTER FJLTER ORIVE PISTON SPUn ~~~EIUNCOUPLING) SEE NOTE I CYLINDER. TUBE. AND l'l.AflGt DOWEL !ALIGNMENT) PIN COLLET HOUSING !PORTION OF OUTER TUBE) !::~~~:~~~~OF CYLINDER, TUBE, ANO FLANGE* POSITION INDICATOR SWITCHES INDEX TUBE NOTCH OUTER TUBE (PART OF CYLIND£A, TUllE, AND fLAlllGEl INNER CYLINDER (PART OF CYLINDER, TUBE, AND FLANGE) THERMOCOUPLE {PART OF POSl"tlON INOICATOR PR08E, STUD IPOFITION OF PISTOlll TUBE) COLLET FINGER (PART OF COLLET AND PlSTONI INDICATOR TUBE !PART OF PISTON TUBE) INNER SEALS (DRIVE PISTON - BUFFER SEALS, INTERNAL BUSHING !DRIVE PISTON) EXTERNAL BUSHING {()RIVE PISTON) OUTER SEALS IORIVE PISTON! INSERT PORT !INSERT AND SCAAM llllLET/WITHDRAW OUTLET) RING MAGNET IPART OF DRIVE PISTONI CABl.E CPOSITJON iNOICATORI POAT TO COLLET PISTON !WITHDRAW PRESSURE TO COLLET PISTON) ~~~:~::"H~:Gi::ITHDRAW INLET/INSERT OUTLET AND INNER SEALS !DRIVE PISTON - DRIVE*OOWN SEALS! INNER SEALS (DRIVE PISTON - DRIVE-UP SEALSJ WATER PORTS IN COLLET HOUSING BUfFER ORIFICES IN PISTON TUBE (TYPICAL) NOTES: I. FOR MODEL 7 ROB144E ITEMS 71 AND 72 ARE MADE OF A SINGLE P1ECE.

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

3. MODEL 7RDB144FG007 IS AN ACCEPT ABLE REPLACEMENT FOR BWR/2-5 MODELS.

FIGURE 4.6-4 MODEL 7RDB144C OR E CONTROL ROD DRIVE CCUTAWAY) NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y. UPDATED SAFETY ANALYSIS REPORT USAR REVISION 15 OCTOBER 2002 _j

030-A.dgn 8/31/2022 1:03:28 PM 1 2 3 4 5 7 8 g 10 11 A CNS SYSTEM 9.2-17a fF-3l CONDENSATE STORAGE BLDG CNS SYSTEM l9.217a(H91 CNS SYSTEM 19.2 17a {J SJ B c I ~ TUNNEL BOUNDARY ______ _L".: __________________ ! ~-1 V///?//fi'~ J 1-- I I ' I ' I REACTOR BLDG ________ _J D 603318 ~ v !.). RDSPC06 VB

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--2-RDS-750-5902-4 IF0A13 I 9.3-9b (E-91 1----J

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V6B I I 2DER-ED3303 9.3-9b CF-91 NOTE 3 ~V1S7 © eJ w w 0 0 z z /\\ r------------------------------~ I I © LTI _1..1r-----~ I I I I I l--- IF1:91 I F~l 31 V7B x v I V~l 4._B L-----* -- 1 ~-Mf--~ 9.3 9b CF 9l 1---J ~ 1 ' r..,. r11T NOTE 3 T r11>--_} 2DER-ED3302 I v120'" '"v130 1 ~ STRT 28 ~ I I RDSPC03Lfu, 1 C I I 'y ' 7 Vl 0B * :::.. PIB lc0:1 I ~-1~ v---~ 60331 s I N0:1 I 2DFR-ED3302 DFR SYSTEM <-.,.__,_9~*~3~9~b'--'-(~F_9~1'--~~ NOTE 3 I 7 V16B \\_ 2-RDS-750-5901-4 PID 378 CK 5) > V20S2B' 7 ~ s r ~ 14B RDSPC12f.\\ 1 I ~---------------------\\ 106 >----------------------, 1 ___.J I 8603446 I F~20 I V23A V154 THIS DWG fK-4l I F~201 V23B SOURCE, PID-30A-30 TITLE, CONTROL ROD DRIVE HYDRAULIC SYSTEM A B ID~03 I FLT2A v F V207SA DRIVE WATER FILTERS F V207SB IF0:31 c IF~22 I V2f/J74A I F:22 I -V2074B 2-DER-ED530B DER SYSTEM 9.3-9b (E-91 NOTE 3 I F~21 I V26A I F:21 I V26B D (AS SYSTEM 4.6-0Sc CL-31 I D005 I PCV I BA FLT4A AIR FILTER V21210S FLT4B AIR FILTER V2007 IR600l V2008 IR606 I LJ IF039 I V53B V539 V2009 V2010 ~ ~ EJ 1 I I I l/P o--~ 107 I D008 I I K001 I (Ro\\_ ~ I I I I ~-L ___ i _____ i I VIS5 Al711& I N004 I,,.--..__ V29 FT 107 FE 107 E 603311 RDSPC01~ v I I IN6001 ~ I I EJ(;;\\_ ____ j ~ V73 RCS SYSTEM S.4-2b IK-91 NOTE 3 F I w "' m. PT 108 V93 V32 4.6-05b (A-51 V27 '----1]0:~--{ P( 111 fl II IR016 I _c:---CHARGING WATER HEADER V540A VS40B V31A V31B G / 1------------ ---------------------, / I ' I ' I AUTO LOAD(NG A/M 6A Pl MANUAL LOADING 1 MAN/AUTO STATION D009A L _________________________________ _ MAN/AUTO 5TATION D009B I I I ' I A/M 6B AUTO LOADING Pl MANUAL LOAD(NG L-----------

---

~

I F:461 V33B I F~46 I V33A FV 6B FV 6A H © '. I I L_l _ _J I I I I I I I '---- ~~ L_""i _ _J I I I I I I I FLOW CONTROL STATION 8 'I I ISC SYSTEM V2077*r S.12o(H9l ISC SYSTEM v2000 L.Jo ~--~-~--(:J5~.~1~2~a~(H~1~0~1::::::)> ~ I p ISC SYSTEM TH($ DWG (A 81 ' 7Vl 9B

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v2001*.. 2DER-ED3309 D ~ t0 ~ IL ___ ~--(::I~~ffi:J]~J r--.,.r te..,. 5.1 2a{H 10) re.... ~.II * >LJD>L.JD DER SYSTEM 9.3-9bCG-101 NOTE:11:3 IF0~ s I --~ I D:07 I V21B .T, - ' I PCV INSTRUMENT AIR SUPPLY ,_..1 __ _,,/,1--' -----;/,I-'--<( 4.6 05c CH 1) (NSTRUMENT AIR SUPPLY

4. -

C H-1 V34B J 4.6-0Sb IC-SI K L M

NOTES,

1. ALL S&W INSTRUMENT AND EQUIPMENT NUMBERS TO BE PREFIXED WITH "2RDS-" EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN.

2. GE-NES.D IDENTIFICATION NUMBERS ARE 5HOWN IN SQUARES tTO BE PREFIXED W(TH C 12 l *

3. NO FLAG SHOWN ON CORRESPONDING DOCUMENT.

COORDINATES PROVIDE INTERFACE LOCATION.

4. 2RD5-PCV14121 IS. TO BE OPERATED AS A MANUAL PRES.SURE CONTROL VALVE.

THE AIR SUPPLY TO REGULATOR ISOLATION VALVE IS MAINTA(NED (N THE SHUT PQS(TION. FIGURE 4. 6-0So N CONTROL ROD DRIVE HYDRAULIC SYSTEM NINE MILE POINT NUCLEAR STATION UNIT 2 SCRIBA, N.Y. UJ D z UPDATED SAFETY ANALYSIS REPORT 1 2 3 4 5 6 7 8 g 10 11 USAR REVISION 2S OCTOBER 2022 _J

SOUACE.PI0-388-14 TITLE.CONTROl..AOOORIYEHYORAULIC$YSTEH ~ LJ e_ LI ~ .r:J LJ [TI Ll e_ LJ di" 11' ~: I ~ 0 I _J !lllitMl""'l!QI, El ___ Cf~~E] 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 NUMeli'.ASWHICMAAIPARTOFNUCLEARSAFETY TENS. FIGURE 4. 6-0Sb CONTROL ROD DRIVE HYDRAULIC SYS TEH NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y. UPDATED SAFETY ANALYSIS REPORT USAR REVISION 18 OCTOBER 2008 _j

L 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 RECIRCULATION SYSTEM SEAL PURGE LINE -il DRIVE WATER FILTER 0003 DR'IV£ WA.TE.R. PUMP COOl SEE N01E 4 F03~ OTHER HCU'S OTHER Hcu*s WCS PUMPS SEAL/PURGE FLOW L __ INSERT __ J @-1r 15 OPEN AT 2 gpm & 80pt(d a: a TO HCU'~ Lt.I l: II) ~-___.,_~---J ::> TO HCU'5 COOLING HEADER DRIVE HEADER I x w CHARGING HEADER SCRAM DISCHARGE HEADER AND INSTRUMENT VOLUME WITHDRAWAL REACTOR VESSEL CONTROL ROD DRIVE 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 SYSTEM. CONOENSATE STORAGE TANK IS THE ALTERNATE SOURCE IF CONO£NSATE TREATMENT SYSTEM IS NOT IN OPERATION. FOR DETAILED DESIGN REQUIREMENTS FOR SOURCE ANO ~UALITY Of WATER) *SEE REF 3.

3. DELETED

4. PUMP SUCTION RELIEF VALVES SET AT 150 PSIG.

INSERT rCONTAINMENT _.._..............-.--~-.---..... WITHDRAWAL 0001 HYDRAULIC CONTROL UNIT INSERT USAR REVISION 23 OCTOBER 2018 FIGURE 4.6-6 CONTROL ROD DRIVE SYSTEM HYDRAULIC NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N. Y. UPDATED SAFETY ANALYSIS REPORT _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. 2x I, ORI\\1~$ LATt;H£;D, FLOW, GFIM "l3. "J3 93 2ril n n 10 63 G3 57 lj7 ~3 0 0 2

2. REACTOR STEAM OOME PRESSURE PIT l0~~ fSIO.

21 PR+2Gl2 PR+30

3. MAX!MUM COOL.ING FLCJW ro DRIVES. MINIMtJt-1 REOUCREO PRESSURE PSlG lq 1487 1487 1487 1476 1462 l4GC!

l455 PR+262 PR +-30 PR 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 NOTE10 MOOE D SCRAM COMPLETED 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. LOCATION 0 l4 15 16 17 18 20 Nori::: MlN !MUM ~CCiJMUUHOR !"RECHARGE PRESSURE IS 56'!i FStO. 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 CREATE_Q I THIS DRAWING 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

ESTIMATED LINE SIZE !INCHES> LOCATION DESIGN TEMP. 21-22 24-25 27A-27B 27B-27 27 27C-270 ISEE NOTE 13> ISEE NOTE 13> ISEE NOTE 13! <SEE NOTE 13: llSEE NOTE 14> <SEE NOTE 14l

• SEE CRO SYSTEM DESIGN SPECIFICATION.
  • 2 [NCH HEADER TO EACH HALF OF THE TOTAL QUANTITY OF HCU'S.

THIS DRAWING CREATED ELECTRONICALLY NOTES:

1. DEFINITION OF SYMBOLS PR-INDICATES PRESSURE OF THE REACTOR MEASURED IMMEDIATELY ABOVE THE CORE PLATE.

2. MAXIMUM OPERATING TEMPERATURES THE MAXIMUM SYSTEM OPERATING TEMPERATURE WILL NOT EXCEED 150 DEG. F.

FROM LOCATION I THROUGH 27 WITH THE FOLLOWING EXCEPTIONS. MODE A- <LEAKING SCRAM DISCHARGE VALVE> 24 25 A. MAXIMUM CHARGING WATER PRESSURE SHALL BE 1600 PSIG NOMINAL. ACCUMULATOR PRECHARGE PRESSURE SHALL BE 575 PSIG NOMINAL, 580 PSIG MAXIMUM, AT 70" F. B. DELETED C. LOCATION 20, 21 ANO 22-THE ANTICIPATED RANGE OF COOLING WATER DIFFERENTIAL PRESSURE IS FROM APPROXIMATELY 6 PSI TO A MAXIMUM OF 30 PSI. REDUCED DIFFERENTIAL PRESSURE rs ACCEPTABLE SUBJECT TO MAINTA1NING THE REQUIRED COOLING WATER FLOW TO THE DEVICES.

0. LOCATION 23-MAXIMUM DRIVE COOLING REQUIREMENTS WlLL NOT EXCEED 0.34 GPM/ORlVE FOR THE CONDITIONS LISTED. MINlMUM DRIVE COOLING REQUIREMENTS WILL NOT BE LESS THAN 0.20 GPM/ORIVE.

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.

7. PUMP SUCTION RELIEF VALVES SET AT 150 PSIG.

8. PROCESS DIAGRAM 11201448 SHALL BE USED WITH ANO FORM PART OF THIS PROCESS DATA. IF THERE ARE ANY CONFLICTS BETWEEN THE PROCESS DIAGRAM ANO THIS PROCESS DATA, THE PROCESS DATA SHALL GOVERN.

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 WITHDRAW LINES AT A FLOW RATE DEPENDENT ON THE REACTOR PRESSURE, 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.

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

12. ALL VALUES SHOWN IN MODES A, B, C, ANO 0 ARE NOMINAL UNLESS OTHERWISE NOTED,

13. INSERT ANO WITHORAWL PIPING SHALL BE DESIGNED FOR HYDRODYNAMIC LOADS AS A RESULT OF A NORMAL SCRAM AT ZERO AND NORMAL REACTOR PRESSURES. SHORT STROKE AND FULL STROKE SCRAM ANO A SCRAM WITH FAILED CRD BUFFER. PLANT LOAD COMBINATIONS SHOULD INCLUDE CONSIDERATION OF THOSE SYSTEM HYDRODYNAMIC LOADS.

14. THE SCRAM DISCHARGE VOLUMES <SDV> AND ITS VENT AND DRAIN PIPING DESIGN SHALL CONSIDER THE HYDRODYNAMIC LOADS WHICH MAY OCCUR DUE TO ([) SDV ISOLATION AND 12> SOV VENHNG AND DRAINING FOLLOWING A SCRAM COMPLETION AT REACTOR OPERATING PRESSURE.

FIGURE 406-7 CONTROL ROD DRIVE HYDRAULIC SYSTEM PROCESS DATA SHEET 2 OF 3 NINE MILE POINT 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 A. ~~6R~~i~o~o:+~~~~~~~)L LINES 131, 15) & 161, ICRD FLANGE TO TABLEZ.: !CONTINUED> B. ~'6~Ti~~T~N~Tl\\RoA~H~IS~~~:3Eol~~~~~~E 16 ~o~~~i ~EYr?f~~LriCDRAlN VAL VESl

1. STANDBY OPERATION

!ALLLINESAFHCTEDI 2.SCRAM !ALL OR SINGLE LINES AFFECTED> 3.SCRAM-COLD !All OR SINGLE LINE AFFECTED) 4.INSERT AND WITHDRAWAL MOTIONISINGLELJNE AFFECTEDI 6.ABNORMAL SYSTEM CONDITIONS !S1NGLELINESAFFECTEDll4) 8.ANTICIPATEOTRANSIENT WITHOUT SCRAM lALl LINES AFFECTED> EXPECTED PRfSSURE TEMPERATURE FREQUENCY DURATION !psigl i*n PERPlANT PER EVENT LIFE !91 1250 121 CONSTANTTEt.1P 45hitlt$7)/150t.1AX 1250 121 AMBIENT TO 280 121 IPR+300l CONSTANT TEMP 45 ~.nN7!/150 MAX IA) AMBIENT TO 45 18) !Bl AMBIENT TO 150 1510 MAX 110l AMB1ENTTQ <25 clO ~OURS 500(1JMAX 1500 !PASSIVE) NOTES FOR TABLE 2.

11) PIPE SUPPORT INTEGRITY SHOULD BE MAINT AINEO FOR THERMAL EXPANSION CONDITIONS THIS MAY BE DEMONSTRATED BY VISUALLY INSPECTING THE PIPE SUPPORTS

~~~c%~Ag~~?T~~~~:ING ANY or THE FOLLOWING RARE EVENTS AT HOT ~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 PRESSURE lpsigl 1250 121 EXPECTED TEMPERATURE FREQUENCY DURATION 1*F1 PERPLANT PEREVENT LIFE 191 AMBIENT TO 2BOl2) ~EUVRECNHTA::o OTN~t' :r:~l~~B~~T~gNlHOSE PROJECTS WHICH TABLE 2. ICONTINUEDI

c. ~1~5R~~iT~o~o~Nr5REcf~ J~~f,s (5) & 13), ICRO FLANGE TO 2.A8NORMAL SYSTEM CONDITIONS!ALL LINESAFFECTEDllBJ 3.SCRAM !All OR SINGLE LINES AFFECTED) 4.INSERT ANO WITHDRAWAL MOTION !SINGLE LINE AFFECT EDI 5.ABNORllAAL SYSTEM CONDITIONS lALL OR RANDOM SINGLE LINES M"FEClED1<41 PRESSURE lpsi9l 1510MAX 110) 1510 MAX 1101 TEMPERATURE 1*F1 CONSTANT TEMP 45 MINlJJ/150 MAX 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

ISOLATION VALVE --------..-.~l(wa1...------ SCRAM VALVE PILOT AIR Ill!. CHARGING WATER RISER ...{jD&J----- ISOLATION VALVE ISOLATION VALVE WITHDRAWAL RISER EXHAUST WATER RISER ISOLATION VALVE INSERT RISER ISOLATION VALVE ----4-lCll:a:.tl COOLING WATER RISER ISOLATION VALVE SCRAM DISCHARGE RISER OUTLET SCRAM VALVE INLET SCRAM VALVE MANIFOLD DIRECTIONAL CONTROL VALVE (WITHDRAW AND SETTLE) SCRAM WATER ACCUMULATOR FRAME ISOLATION VALVE DRIVE WATER RISER ~-------SCRAM PILOT VALVE ASSEMBLY JUNCTION BOX WIRING TROUGH ASSEMBLY UNIT INTERCONNECTING CABLE SHUTOFF VALVE WATER ACCUMULATOR DRAIN SCRAM ACCUMULATOR N2 CYLINDER ACCUMULATOR N2 PRESSURE INDICATOR CARTRIDGE VALVE ACCUMULATOR N2 CHARGING ~h.,,~~-~- ACCUMULATOR FIGURE 4.6-8 INSTRUMENTATION ASSEMBLY CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT

GRID CLAMP -STEEL FORM LINER CRO HOUSING l.. VESSEL SU"'ORT 1--++------'-- HANGER ROD PEDESTAL SUPPORT BAR FIGURE 4.6-9 CONTROL ROD DRIVE HOUSING SUPPORT NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT}}