ML22292A118
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--- MINIMUM OPERATING CPR LIMIT
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ID 10 30 40 so 70 110 911 100 110 llO FIGURE 15.0-2 NMP 2 OPERATING POWER/FLOW MAP NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSJS REPORT USAR REVISION 19 OCTOBER 20'10
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50 I
100 1 -
Bounding Nuclear Core Data*
I 2 - SCRAM curve used in analysis" I
I c-678 CAD Tech Spec in percent**
I I
M-Mean CAD performance used in I
ODYN-GEMINI MCPR analysis I
80 40 I
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Time (seconds)
- Applicable to events analyzed with REDY Code ODYN Code SCRAM Reactivity is calculated internally during the transient event.
FIGURE 15.0-3 SCRAM POSITION AND REACTIVITY CHARACTERISTICS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT - UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 14 FEBRUARY 2001
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I NEUTRDN I LUX I VESSEL Pf 1=5 lllSE (PS II 2 RVE SURFI CE tERT FLUX 2 llELlEF VI VE FLOW 150.
3 CORE !NL T FLOW 125.
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FIGURE 15.1-1 LOSS OF FEEDWATER HEATER, NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT IS AUTO FLOW CONTROL LESS SEVERE THAN THE CASE WITH THE REACTOR IN MANUAL CONTROL.ANO IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE.
NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995
- 20.
YO.
- 60.
TIHE ISECJ NOTE: THESE RESULTS ARE FOR CYCLE 1.CYCLE-SPECIFIC RESULTS ARE PRESENTED lN APPENDIX A.
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- 25.
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l VESSEL Pl ES RISE I PSII 2 RELIEF VI VE FLOW 3 Bl'PASS Vf VE FLCH q
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TIME CSECI
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- 80.
THIE CSECl FIGURE :15.1-2 LOSS OF FEEDWATER HEATER, MANUAL FLOW CONTROL NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S
B.
- 12.
TIME ISECI o.~
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- 6.
- 12.
- 15.
T!HE ISECI NOTE: THESE.RESULTS ARE FOR CYCLE J.CYCLE-SPEClFIC RESULTS ARE PRESENTED IN APPENDIX A.
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T!HE lSECI FIG URE 15. l-.3 FEEDWATER CONTROLLER FAILURE, MAXIMUM DEMAND NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S
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150 10 1 VESSEL PRES RISE (p1il 2 RELIEF VALVE FLOW 3 BYPASS VALVE FLOW 20 JO 40 50 TIME (sec)
- 2 0~~~-':-4~..1&.~~8~~~~12~~~~16"'-~~_.20 TIM E' lsecl FIGURE '15.1-4 PRESSURE REGULATOR FAILURE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995
0 uJ t-150
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1 NEUTRON FLUX 2 PEAK FUEL CENTER TEMP J AVE SURFACE HEAT FLUX 4 FEEOWATEA FLOW 5 VESSEL STEAM FLOW TIME !>eel 1 LEVEL hnc:h-rel_.ep.. kort) 2 WR SENSED LEVEL hnchesl 3 NA SENSED LEVEL (inches!
4 CORE INLET FLOW ltl 5 DRIVE FLOW 1161
- 100 ___
0 2
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8 10 NOTE: THESE RESULTS ARE FOR CYCLE l. THIS EVENT rs LESS SEVERE THAN THE CASE WITH BYPASS FAILURE ANO IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE.
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TIME be<:I f VOID REACTIVITY 2 DOPPLER REACTIVITY 3 SCRAM REACTIVITY 4 TOTALREACTIVITY 3
4 2
TIME tsccl FIGURE 15.2-1 10 5
GENERATOR LOAD REJECTION WITH BYPASS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISlON 8 NOVEMBER 1995
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TIME lsecl NOTE: THESE RESULTS ARE FOR CYCLE 1.CYCLE-SPECIFIC RE5UL rs* ARE PRESENTED IN APPENDIX A.
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6 TURBINE STEAM FLOW l*I TIME l$0CI TIME tsecl 1 VOID REACTIVITY 2 DOPPLER REACTIVITY 3 SCRAM REACTIVITY 4 TOTAL REACTIVITY 3
4 FIGURE 15.2-2 5
GENERATOR LOAD REJECTION WITHOUT BYPASS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER i995
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-2.a.
- 2.
- 3.
111£: ISECI FIGURE ~15.~-~
TURBINE TRIP, TRIP SCRAM, BYPASS AND APT -
ON NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION B NOVEMBER 1 99S.
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- o.
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4t*.
- 3.
TllE ISEtl FIGURE 15.2-4 TURBINE TRIP WITHOUT BYPASS, TRIP SCRAM NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT
. USAR REVISION 8 NOVEMBER 1995 -
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NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT SET REACTOR OPERATING LIMITS AND IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE.
I I
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TJl'.E lSECl FIGURE 15.2-5 MSIV CLOSURE, POSITION SCRAM NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S.
150.
I NEUTRON LUX 2 PERK FUE CE~TER TEMP 3 RVE SURF CE HEAT FLUX Y FEEDWATE FLDH 5 VE5Sa 5 EAK FLOW
~ 100.~~'C"&,,.f---\\,.-1----l-----l--
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TIME ISECI E -1. t-----+-,,,.._-~--_,1-----1---
.... li UJ a:.
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..-3**----..... ~----------------------------------.a TIHE ISECI FIGURE 15.2-6 LOSS OF CONDENSER VACUUM NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT SET REACTOR OPERATING LIMITS ANO IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE.
NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995
IL 0
1-z...
u a:......
150 200 1 NEUTRON FLUX 2 AVE SURFACE HEAT FLUX 3 CORE INLET f LOW 4 CORE INLET sue 20 JO 40 TIME (sec) 1 LEVEL linc;h-rel*sep.,.kirtl 2 VESSELSTEAMFLOW 3 TURBINE STEAMFLOW 4 FEEDWATER FLOW 50
-l000~~~~.~0~~~20~~~~30~~~~40~~---'50 TIME lsccl NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT SET REACTOR OPERATING LIMITS AND IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE.
300 200 100
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6 e
10 TIME lsecl FIGURE 15.2-7 LOSS OF ALL RESERVE AND NORMAL TRANSFORMER NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S
@ 100.lt""'~:.'t-f--+--11-1.1'1,.,-,---l----l-----l---
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- 3.
- s.
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- 12.
TIME CSECI u a:
~
NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT SET REACTOR OPERATING LIMITS ANO IS NOT REANALYZED FOR POWER UPRAT~ OR FOR EACH RELOAD CYCLE.
I VESSEL PIES RISE tPSll 2 STM LINE FRF.5 RISE (PSI!
300.1------1----~----""3'-"'TlJllBH:E I HES !li.fil: CPSI J ti CUltElNfl i'SUB tBTD/LBI S REI fEF Vf I. VE FLOH Co J
- a.
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G TllfiBIN( ! ffRH FUlfl 1.. 1
- 2.
- 3.
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TIHE !SECI FIGURE 15.2-8 LOSS OF ALL GRID CONNECTIONS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995
I NEUTRON ~ux 2 AVE 5L~F
- _f. 11EAT FLUX 3 c:PfiE !NL* T fLOH tSO.l----+-----1----;qdJffc:INL fSUB-
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- 10.
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3 *
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- 0.
IO.
- 20.
- 30.
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rIME. ISECI NG TES:
- l. SEE ASTERISK NOTE IN TABLE 15.2-11.
- 2. THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT SET REACTOR OPERATING LIMITS ANO IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE.
Tll'IE ISECJ FIGURE 15.2-9 LOSS OF FEEDWATER FLOW NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S
l 625 575
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Top of Active Fuel 375 I
325 0
500 1000 1500 2000 2500 JOOO 3500 Time (secl FIGURE: 15.2-9A LOSS OF FEEDWATER FLOW EPU <3.988 MWt>
LEVEL INSIDE THE SHROUD NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT T
USAR REVISION 20 OCTOBER 2012
0....
Q)
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VI Q) u
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450
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__ v 410 Nominal Lev I I
I 390 350+--~~+-~~+--~~+-~~+-~~+-~~+-~~+-'
0 500 1000 1500 2000 2500 3000 3500 Time <sec>
FIGURE: 15.2-98 LOSS OF FEEDWATER FLOW EPU <3.988 MWD DOWNCOMER LEVEL RESPONSE NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT T
USAR REVISION 20 OCTOBER 2012
~
A NORMAL SHUTDOWN INITIATED P = 1055 psia T = 550"F f-l *,._------1045 ps1a, 560"f TO 100 psi, 330"F -------_..,.,
... _. __ 100 PS*. J3Q*F TO 14 7 PSI, 125"f ~
w
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DEPRESSURIZE VESSEL TO MAIN CONDENSER ffi CONDENSER DEPRESSURIZE VESSEL S:
NOT AVAILABLE VIA MANUAL RELIEF
~ t----------il--t VALVE ACTUATION.. AHR w
SUPPRESSION POOL COOLING II!
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AUTOMATIC RELIEF VALVE ACTUATION DEPRESSURIZE VESSEL VIA MANUAL RELIEF VALVE-ACTUATION* RHR SUPPRESSION POOL COOLING FAILURE Of DIVISION I DIESEL NORMAL SHUTDOWN COOLING IOFFSITE POWER I AOSIRELIEF VALVE AL TERNA TE PATH NORMALSHUTDOVVN COOLING ION SITE POWER)
ADS/RELIEF VALVE ALTERNATE PATH ADS/RELIEF VALVE AL TEAlllATE PATH FIGURE 15.2-10 D
COLO SHUTDOWN ACHIEVED tvESSEL HEAD REMOVED I
SUMMARY
OF PATHS AVAILABLE TO ACHIEVE COLD SHUTDOWN NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 22 NOVEMBER 1985
._,_..._ _________ 1055 pala, 550°F TO 115 psi, 340°F NO OFFSITE POWER
---i
+14--- 115 psi, 340°F TO 14.7 psi, 125°F ____J A*
NORMAL SHUTDOWN INITIATED P = 1055 psla T; 550 °F LOSS OF OFFSITE POWER TRANSIENT e*
AUTOMATIC RELIEF VALVE ACTUATION
- FOR DEFINITION OF A,B,C1, ANO C2, SEE NOTES ON NEXT 2 PAGES.
DEPRESSURIZE VESSEL VIA I
I DIVISION U FAILS c2*
ADS VALVE RHRLOOPA (DIVISIONS 1 AND 3)
AVAILABLE)
ADS/RELIEF I
VALVE ACTUATION 1
RHR SUPPRESSION POOL COOLING DIVISION I FAILS FIGURE 15.2-11 C1*
ADS VALVE RHR LOOPS B AND C (DIVISION 2 AND 3 AVAILABLE)
ADS/RHR COOLING LOOPS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 22 NOVEMBER 1985
S/R VALVE MSL REA CTOR VESSEL SUPPRESSION AREA FIGURE 15.2-12 ACTIVITY C1 AL TERNA TE SHUTDOWN COOLING PATH UTILIZING AHR LOOP 8 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
SIR VALVE MS!.
REACTOR VESSEL SUPPA ESSION AREA FIGURE 15.2-13 AHR LOOP C NIAGARA MOHAWK POWER CORPORATION NINE MILE POINi -UNIT 2 FINAL SAFETY ANALYSIS REPORT
$/R VALVE HSL REACTOR VESSEL
.SUPPRESSION AREA CSL Pl FIGURE l5o2-13a LOW PRESSURE CORE SPRAY (CSU IN ALTERNATE SHUTDOWN COOLING NIAGARA MOHAWK POWER CORPORATfON l\\JINE MILE POlf\\IT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REV g MAY igg7 _I
FIGURE,15.2-14 AHR LOOP 8 (SUPPRESSION POOL COOLING MODE)
NIAGARA MOHAWK POWER CORPORATION NINE MiLE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
r-H-;;T-1 EXCHANGER I
ORYWELL SUPPRESSION AREA RHA A REACTOR VESSEL SIR MSL VALVE AHA SERVICE --L---....:r-"J;-l-IM... -
..... SERVICE WATER SYSTEM WATER I
I DISCHARGE L ____ J FIGURE 15.2-15 ACTIVITY C2 ALTERNATE SHUTDOWN COOLING PATH UTILIZING RHR LOOP A NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
1300 1200 PRESSURE 1100 1000 900
... 800 i
w a:
- > 700 II)
II) w a:
.... 600
..J w
II) w > 500 400 JOO 200 100 0
100 101 TIME hee l PRESSURE CASE B 800 600 -
iL 400 o_
w a:
~
<a: a:
w...
300 ~
1-
..J w
200 100 t:i w >
FIGURE 15.2-16 VESSEL TEMPERATURE AND PRESSURE VS. TIME NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
2'40 220 200 180 ii:
160 w
a:
~
~ 140 a:
w
- a.
~ 120 0 0...
100 80 60 40 20 10 10 TIME!secl FIGURE 15.2-17 SUPPRESSION POOL TEMPERATURE VS. TIME NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
1300 1200 1100 1000 ct 900 iii
- a. -
800 I
700 i
flJ
~ 600
- a. _,
500 fl>>
Cl)..
400 300 200 100 0
1 10 THIS DRAWING CREATED ELECTRONICALLY 100 1000 TIME IS£Ct 10000 100000 1000000 flGURE 15.2-18 VESSEL PRESSURE VS. TIME ALTERNATE SHUTDOWN COOLING ANALYSIS-POWER UPRATE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995
700 600 -
- 500 -
- u. -
w I
~ 400 a:....
- a.
- E
~ 300.
CiO
.... 200 100 -
0 I
I I
I I 1
- I I
f 10 too 1000 10000 tOOOOO 1000000 TIME ISECJ FIGURE 15.2-1g VESSEL TEMPERATURE VS. TIME ALTERNATE SHUTDOWN COOLING ANALYSIS-POWER UPRATE NIAGARA MOHAWK POWER CORPORATION I THIS DRAW ING CREA TEO ELECTRONICALLY I
NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT U5AR REVISION 8 NOVEMBER 1995
200 Ill 150 a:
- >> i UI D. I 100 0
0..
60 10 100 THIS DRA\\vING CREATED ELECTRONICALLY 1000 10000 100000 1000000 FIGURE 15.2-20 SUPPRESSION POOL TEMPERATURE VS TIME ALTERNATE SHUTDOWN COOLING ANALYSIS-POWER UPRATE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995
200.
u..
!.!)
UJ c
QI 3
0...
Q.
E Ill I-100.
- 0.
5~
042908
- 0.
- 4.
20A3CBBF 1541.1 NMP2 EPU ASOC K*270 I I I I I I
- 8.
2 2
I I I I I I
- 12.
l Suppression Pool 2 Wei well Air space I I I
I I I I
- 16.
Time - HRS FIGURE: 15.2-20A EPU SUPPRESSION POOL TEMPERATURE RESPONSE TO ASDC EVENT NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 20 OCTOBER 2012
~
I NEUTRON LUX 2 AVE SURF CE HERT FLUX ISO.
3 CORE INL + ~LgL-II CCR INL s
Ci lOO.
~
a:
a:
~
- z
- 50.
w Ir UJ 110.
5 NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT SET REACTOR OPERATING LIMITS AND rs NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE.
125.
- 75.
- 25.
I VCSSEL P ES RISE IPSI I 2 RELIEF V LVE Fll'IH DTPA55 II L..'LE FLOW II OIFFUSEl'j Fll'JH l li:J 5 DIFFUSER FLOW 2 IY.l 6
llO.
FIGURE 15.3-1 TRIP OF ONE RECIRCULATION PUMP MOTOR NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT
~,. ________________________________________________________________.., ______________________________________ ~
USAR REVISION 8 NOVEMBER 1995
a w
a:
- u. a
>-z UI u a:
w
- a.
150 10 10 1 NEUTRON FLU)(
2 AVE SURFACE HEAT FLUX 3 CORE INLET FLOW 4 CORE INLET SUB
]
2 20 JO 40 TIME bccl I LEVEL (lnch*ref*sep*skirtl 2 VESSEL STEAMFLOW 3 TURBINE STEAMFLOW 4 FEEDWATER FLOW 50
- 10 JO so TIME lsccl NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT SET REACTOR OPERATING LIMITS ANO IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE.
125 75 25 1 VESSEL PRES RISE (p11I 2 RELIEF VALVE FLOW 3 BYPASS VALVE FLOW 4 DIFFUSER FLOW 1 lI 5 DIFFUSER FLOW 2 ("I I VOID REACTIVITY 2 DOPPLER REACTIVITY 3 SCRAM REACTIVITY 4 TOTALREACTIVITY
-2-~...... ~~~~
....... ~~--'~~~
....... ~~---
0 10 20 JO 40 50 TIME (secl FIGURE 15.3-2 TRIP OF BOTH RECIRCULATION PUMP MOTORS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995
150.
~ 50.
I NEUTAOtl LUX 2 RVE SURF 'E HEAT FlUX 3 CORE !NL T FIJ!!L_
II CORE !NL T SUB 5
5
~
~ o.W--JL---.-J.-!----+----+----+---
w z
0 a.
- c 8
~ -l. l-+-1-1--ll--!----+----+---+---
NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT SET REACTOR OPERATING LIMITS ANO IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE.
- 2*ar:.... ~l...u..~10-. --c:..1:200--. ---:;31,..0-.----;lJ:;';;O-. --=
TIHE ISECI FIG URE 15.3-3 FAST CLOSURE OF ONE MAIN RECIRCULATION VALVE AT 60% PER SECOND NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY.ANALYSIS REPORT USAR REVISION B NOVEMBER 1995
~ 100.~~-J.l---~.l----.l----..I---.
<r a:
~ ~.t---->,cM-:+->.o----1-'l'--+----1---
~
"o.
~
I VE~SEL ~ES RISE IPSll 2 RELIEF ~~LVE FLOW J25.l---l!---~-----l;J-m1~~i.:~ J,~~t7'~:!J 5 DIFFUSER FLCM 2 l/.J 6
"' ffi
- 0.
~
- x:
Cl u
- -1. t---->,rr-\\-U-----1---+----1---
LJ it
- 20.
- 30.
TIHf ISECI NINE HILE POINT 2 FAST l:LDS!JlE llF BClTH RECIRCULRT Uli Vil.YES NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT SET REACTOR OPERATING LIMITS AND IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE.
- 20.
- 30.
IJO.
TIHE ISECI FIGURE 15.3-4 FAST CLOSURE OF BOTH MAIN RECIRCULATION VALVES AT 11% PER SECOND*'
NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY *ANAtYSIS REPORT USAR REVI SJON 8 NOVEMBER 1995
I NEUTRON LUX 2 AVE SURF E HEAT FLUX 3 COOE INL T F OM 150.t---t---!+----t------r.i"ll~CORE !NL T SUB 5
ffi 100.~ri--+-'t---+----+----+---
~
I!!
ffi 00.1-+----..,,..,..+--___.,_-+----1----+----
ffi l!O.
NOTE: THESE RESULTS ARE FOR CYCLE I.THIS EVENT DOES NOT SET REACTOR OPERATING LIMITS ANO IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE.
l VESSEL P ES RISE !PSII 2 HEUEF V LVE fLDW 3 BrPASS VI LVE FL~
125.Hi---+--t-----t----t:',IHDIFFUSEll l*LOH I IZl S OIFFUSER FLOH 2 11.l G
§ o.~""--+-------.~--+--r---+---
1 8
- -1. l--~--l----!*"4--.1---1'1-+----+--
~
UJ a:
FIGURE 15.3-5 1:*
SEIZURE OF ONE RECIRCULATION PUMP NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION B NOVEMBER 199S
764 ASSEMBLIES t85 CONTROL ROOS I
r n
t6 16 t6 4 '
4 4
4 r
6 t6 16 16 6
i-i 4
4 8
8 4
4 16 16 42 44 42 16 16 4
8 a
0 8
4 16 16 44 48 44 18 16 4
8 0
0 B
4 16 16 42 44 42 16 16 4
4 8
8 4
4 L
6 16 16 16 6
LJ 4
4 4
4 16 16 16 I
L
-1
- ON LIMITS BUNDLE (21-38)
CONTROL ROD COORDINATES ARE SHOWN.
FIGURE 15.4-1 ROD PATTERN FOR RWE ANALYSIS NOTE: THIS ROD PATTERN IS FOR NIAGARA MOHAWK POWER CORPORATION CYCLE l.CYCLE-SPECIFIC RESULTS NINE MILE POINT -UNIT 2 ARE PRESENTED IN APPENDIX A.
UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S
1.6.
1.S g
\\
BUNDLE (25-34>
r-
<{
er er w
- i:
\\
0 1.05 1.4
_J
\\::!
\\
r-er u
- ?
1.3 ~\\
~
POWER 1.04
~
- z
~,~,
er w
~
0 0..
1.03 0
1.2 UJ r-
<{
er
~
u..
BUNDLE (21-JBI 0
en z
Q 1.1 1.02
~'~NOLE 123-361 u
<{
er u..
1.01 1.0 ROD BLOCK LINE 0.911---.....1---....i.-....i.-....i.---....L.----L.---...l 1.oo 0
2 4
6 a
10 12 DISTANCE CONTROL ROD WITHDRAWN (leetl NOTE: THESE RESULTS ARE FOR CYCLE 1. CYCLE-SPECIFIC RESULTS ARE PRESENTED IN APPENDIX A.
FIGURE 15.4-2 VARIATION OF CORE POWER-AND MCPR WITH THE DISTANCE ROD (26-35) WITHDRAWN DURING CONTINUOUS
- ROD-WITHDRAWAL ERROR NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S
19 18 17
~
w I-
<{
16 a:. z 0
j::
<t a:
w 2 w
<.:J I-15 w
- z:
a:
<(
w
~
-J
- e 14
~
x
- E 13 12 BUNDLE 121-381 /
/
/
(
I I
/
..c::::::..
- ---=---
BUNDLE 139-241 ROD BLOCK LINE 11L....------..L.------...,,jL....--J...--.J..--------.1....------...i.------__.
0 2
4 6
8 10 12 DISTANCE CONTROL ROD WITHDRAWN lfeetl NOTE: THESE RESULTS ARE FOR CYCLE 1. CYCLE-SPECIFIC RESULTS ARE PRESENTED IN APPENDIX A.
FIGURE 15.4-3 MLHGRVS DISTANCE ROD (26,35)
WITHDRAWN NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S
130 125 120 I
115
- E m
a:
110 105 RBM RESPONSE TO CONTROL ROD MOTION CHANNELA+C
,,...,. ~
124,331 L+/-.____J 132,331 B
A NONE FAILED B
3:2.41 c
24.41 D
24.33 E
24.33 AND 24.41 100L...-..
-=::::;;. __ 1..... ____ '------.L-..J.--.l....----.L-----.l....----.l....----.L...----.L...----.J-----I 0
2 J
4 NOTE: THESE RESULTS ARE FOR CYCLE 1.CYCLE-SPECIFIC RESULTS ARE PRESENTED IN APPENDIX A.
5 6
C.R FT WITHDRAWN 8
9 10 II 12 FIGURE 15.4-4
. RSM RESPONSE TO CONTROL ROD MOTION, CHANNEL A & C NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995
130 12&
120 115 110 105 ABM RESPONSE TO CONTROL ROD MOTION CHANNEL B
- D
"""' ~
124.331 l+/-___J 132,331 A
NONE FAILED B
32.41 c
24.41 D
24.JJ E
24.JJ ANO 24.41 100~----------i-.----.i....----------""-----.L....----.l....----.l....----J....----l....----.l....--....J 0
3 4
5 6
B 9
NOTE: THESE RESULTS ARE FOR CYCLE 1.CYCLE-SPECIFJC RESULTS ARE PRESENTED IN APPENDIX A.
C.R. FT WITHDRAWN 7
10 11 12 FIGURE 15.4-5 ABM RESPONSE TO CONTROL ROD MOTION,
. CHANNEL B & D NIAGARA MOHAWK POWER CORPORATION NINE Mf LE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S
a Ul
!;{
a:... a... z Ul u a:
Ul CL 4
150 1 NEUTRON FLUX 2 AVE SURFACE HEAT FLUX 3 CORE INLET FLOW 4 CORE INLET SUB 2
OOL~~~1L0~~--12~0~~--J3~0~~---'40..._~~50 TIME lsecl 150 t LEVEL lonch*nif.. ep*sk1<1) 2 FCV 1 POSITION 1%1 3 PUMP SPEED I I'll.)
FEEDWATER FLOW 3
0 2
0 10 20 JO 4-0 50 TIME lsecl NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT SET REACTOR OPERATING LIMITS AND IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE.
~
.... z w
2 0
CL :e 0 u
~
60 1 VESSEL PRES RISE (psil 2 RELIEF VALVE FLOW 3 BYPASS VALVE FLOW 4 DIFFUSER FLOW fl%1 5 DIFFUSER FLOW 2 (%)
-50iL 0 ~~~,~0~~~w~~~~3~0~~~4~0~~~50 TIME laec) 0 I VOID REACTIVITY
- - 1 2 DOPPLER REACTIVITY J SCRAM REACTIVITY j
u
<t w a:
-2 0 2
4 TOT AL REACTIVITY 4
6 8
10 T IME (secl FIGURE 15.4-6 ABNORMAL STARTUP OF IDLE RECIRCULATION LOOP PUMP NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT NOVEMBER 1995
c; 100.H+---1----1-----l----1---
l::!
a:
a:
~
ffi so.. 't-t--'~-+-"'<----1----i~---+----
ij:!
UJ
- n.
- 40.
l~.r-----+----l----1----1----
-50..!-..L..1..1..LJ..J...W._'::-----l----....L...--_L--..:I.
Q
- m.
~-
~-
- 40.
TIME ISECl NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT SET REACTOR OPERATING LIMITS ANO IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE.
I VESSEL P~tS RISE IPSll 2 RELIEF V* LVE FLOW 3 B'l'i'ASS V. L VE FLIJH 2oo.i----1----+---i~'!
OlffU-'illi-fUMl l'l.l 5 DIFFUSER FLO~ 2 lf.l
[j
-IOO.~..w..w.....~---:;;1=--___,IL---..1----:I.
0.
- 10.
- 20.
- 30.
- 40.
TIME CSECI E -1.1-----+--+-+--+----lf-----1---
ll.
- 6.
- 8.
TitlE !SECl FIGURE 15.4-7 FAST OPENING OF ONE MAIN RECIRCULATION LOOP VALVE AT 30% PER SECOND NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995
/
I so.
5 150.~--+-----+-----t----+----
NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT SET REACTOR OPERATING LIMITS AND IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE.
I VE'SSEL P1ES Al5E IPSIJ 2 P.Ellff vw_VE FLOW 200.1----l-----+----+-H{~~}r.~ ~~,t~JL~:o 5 DIFFUSER FLIJW 2 tzl G
-100. W...Ul...L.1.J-LI...1.,l----..,,J,.---...,,.,_ __
..:.i,.
- o.
- 10.
- 20.
- 30.
- 40.
TIME CSECI FIGURE 15.4-8 FAST OPENING OF BOTH MAIN RECIRCULATION LOOP VALVES AT 11% PER SECOND NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT U5AR REVISION 8 NOVEMBER 199S....
I NEUlRClN LUX I VESSEL Pl ES RISE IPSIJ 2 PERK FUE CENlER TEMr 2 STH LINE FAES RISE IPSll 3 AVE S HEAT FLUX 125.
3 TURBINE ' RES RISE IPSI I 150.
'11 f[EOH UH 11 lil'CS FLD I?. Of FKl S VESSEL 5 FAM FLOH c;_
c
< g ~~~.~~. 1rn!2 FRAC lXl
-~
""1 l'IU !XI 1
o.U 1 _'I 1
1 "-
ffi lob.
7S.
u 11 fl!
~
~ so.
- 25.
ll ll ll ll
~
l!'.l"J'!
'I
- o.
-25.
- o.
- 10.
- 20.
- 30.
- llO,
- a.
- 10.
- 20.
- 30.
L.10.
TIME ISECI TIME CSECI l LEVELllN H-REF-SEP-Sl<IRT I NEU RCN FLUX 2 H A SENS 0 LEVEL I INCHESJ 2 SUR ACE HEAT F ux 125.
3 N R SENS 0 LEVEL! INCHES!
120.
Ill LUMC !NL 11 FLllW I ~ ) :
S ORlVE FLI H 1 I 1. I u;
u; ll u;
~
- 75.
c
- 80.
LLJ t-
'I
~
~
- u.
- ?'"
0 I-
- 25.
z
- 40.
w,_,
a:
~
0.
I
-25.
- 20.
- 30.
- 40.
- o.
- 25.
so.
- 75.
100.
- 0.
- 10.
TIME ISECI CORE fLDH C?.I FIGURE 15.5-1 INADVERTENT STARTUP OF HPCS NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT NIAGARA MOHAWK POWER CORPORATION SET REACTOR OPERATING LIMITS AND IS NOT REANALYZED NINE MILE POINT-UNIT 2 FOR POWER UPRATE OR FOR EACH RELOAD CYCLE.
UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995 -
ftULllfCfll l\\llfiflfANA&.Ylll
\\.l'w4CCfnAIU AUUl n
'""'"' l'fSTIM$
AJ OfllQtlO
""D111il1Al\\(D DOJ.Q-.,1-.t*I
&CCIDllirllU 1D(JITIPlt&1U)frifO* IAJITY AC110-I HrN11&l TD AVOIDING IJ'NACCtn"ll.1 fllllUL fl llACH 11Afll IDCHJtflCATtOff oP IYltffrtll AND 1.ltr11T' UH~fl&I.. '0" At;MtlV l"'C l4Jft'i 4CTIOAft IUCt4 SlATll IDU1Tff lCaf10-.0f 1.. M*t¥1'Tf"'
ACTtOlrlS ~ ICM W\\llT ti "lDUUttO 0 44 Af1TA 1Cf(O 11.a(.. IYl11MI 1otfrilflltC*ttQl60' _,,,. *.,...,...
S'r1ftM "'*"Ofll*lliU COlfQttlCJ!rfl tO ACCOrW"'t 1SM
- Ct!Q'lrfl tf:a<.. J*SftVI IDt.. TlfH;AflO-. c** 14.. EMAAl Cl)lrraOITIQ!lro TO U.TtlJ'f llll:fDuJrtDAlritC.,. flllQUttllfr..t.. TS I &CM SYIT(W lo-t*Atl()llAfr. ~ll*fl IA*lTl' *l°'*" "l"l.. tl. l *litt!tfrrtCio
( 0-.t) tTIOfrrfl*O" Ol'l"AT tQlcl loti'-flfT' IUttVllLL.U.Cl fU'T fflllOUf"-Clll tO(frrft1*'f' AU.OW... U IRCU,t* t*"l!i fil'"tfll l'fltlt,ji l'tOl'lflAll.f ll lMlt ltrtC (Oti!OITt~ f'lA ~A4t t 0-. t i...-t1*1t&t10-.
FIGURE 1 SA-1
~to u,_D***CV ftlCUtlll(MlflrlT 11.ac"*
A\\fAI\\ Allt,.lfV co-.110Uu*.T10'4S llru,;c.t.,fAA$.AS(l-.
C'J"(1UT ID"t&.1.
CAlt[R1a BLOCK DIAGRAM OF METHOD USED TO DERIVE NUCLEAR SAFETY OPERATIONAL REQ. SYS.
LEVEL QUALITATIVE DESIGN BASIS CONFIRMATION AUDITS AND TECH. SPEC.
NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
I EVENT A I I
EVENT SINGLE EQUIPMENT SINGLE OPERATOR CATEGORY l MALFUNCTION ERROR I
IST PROTECTION I
LEVEL I EVENT A:
- EVENT 8 I SINGLE OPERATOR OPERATIONAL 2NO PROTECTION ERROR REQUIREMENT LEVEL PROTECTION PROTECTION LEVEL 1 LEVEL 1 3RO PROTECTION PROTECTION LEVEL OPERATIONAL LEVEL 2
- PROTECTION SINGLE OPERA TOR REQUIREMENT SCRAM LEVEL 2 ERROR 4TH PROTECTION LEVEL PROTECTION PROTECTION LEVEL 3 LEVEL 3 ADDITIONAL 5TH PROTECTION EQUIPMENT LEVEL PROTECTION OPERATIONAL PROTECTION MALFUNCTION LEVEL 4
- LEVEL 4 REQUIREMENT SCRAM OPERATIONAL 6TH PROTECTION REQUIREMENT LEVEL IT IS INCONSISTENT TO PLACE OPERATIONAL REQUIREMENTS ARBITRARILY ON SOME ACTION IT IS INCONSISTENT TO PLACE OPERATIONAL (SCRAM) IN ALL CASES OF ONE EVENT CATEGORY, I
EVENT A I I
EVENT BI REQUIREMENTS ON SEPARATED LEVELS OF BECAUSE THAT ACTION (SCRAM) MAY REPRESENT PROTECTION FOR ANY ONE EVENT DIFFERENT LEVELS OF PROTECTION FOR THE VARIOUS CASES.
1ST 1ST PANEL A PROTECTION PROTECTION PANEL 8 LEVEL LEVEL OPERATIONAL 2NO OPERATIONAL 2NO REQUIREMENT PROTECTION REQUIREMENT !PROTECTION LEVEL LEVEL JRO 3AD PROTECTION PROTECTION LEVEL LEVEL IT IS INCONSISTENT TO PLACE OPERATIONAL RE*
REQUIREMENTS ON EVEN THE SAME LEVELS OF PROTECTION. IF THE EVENTS ARE NOT OF THE SAME CATEGORY.
PANEL C FIGURE 1 SA-2 POSSIBLE INCONSISTENCIES IN THE SELECTION OF NUCLEAR SAFETY OPERATIONAL REQUIREMENTS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
e;'/ENT CLASS! FICATION ttOf\\MAL OPERATION 10 CFR 50, I DOSE LIMIT FIGURE 15A-3 SIMPLIFIED NSOA CLASSIFICATION INTER A ELA TIONSHI PS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
SAFETY SYSTEM 0
DIFFERENT PLANT CONDITION SAFETY SYSTEM s
I
'\\
\\ S F)
SAFETY SYSTEM R
EVENT EVENT TITLE STATES NUMBER OF EV ENT STATES IN WHICH THIS PROTECTION SEQUENCE IS APPLICABLE DIFFERENT PLAN CONDITION INDICATES THAT SYSTEMS QAND R SHARE AS A PAIR THE REQUIREMENT TO MEET THE SINGLE FAILURE CRITERION PERSONNEL SAFETY SYSTEM u
S F ACTION
..-°"' SYSTEM (MANUAL I ~
SAFETY REQUIRED FOR
( P J W SYSTEM W S F
~
SYSTEMS MUST ITSELF
~
MEET THE SINGLE FAILURE SAFETY SYSTEM T
S F SAFETY ACTION A
CRITERION INDICATES THAT ONE OR MORE OF THE KEY PROCESS PARAMETERS MUST BE LIMITED TO SATISFY NUCLEAR SAFETY OPERATIONAL CRITERIA EACH CONNECTED PROTECTION SEQUENCE IS FOR JUST ONE SAFETY ACTION FIGURE 15A-4 SAFETY ACTION A
FORMAT FOR PROTECTION SEQUENCE DIAGRAMS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
(
SAFETY RELATED SYSTEM x
I SAFETY SYSTEM AUXILIARY A DIAGRAM INDICATES THAT AUXILIARIES A, B, AND C ARE ESSENTIAL TO THE SAFETY SYSTEM OPERATION OF THE SAFETY RELATED AUXILIARY B SYSTEM X. NO CHRONOLOGY OR ORDl:R OF ACTION IS IMPLIED SAFETY SYSTEM AUXILIARY C FIGURE 15A-5 FORMAT FOR SAFETY SYSTEM AUXILIARY DIAGRAMS I
NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
INDICATES THAT SYSTEM IS INCLUDED IN COMBINATION BUT DOES NOT REQUIRE THE AUXILIARY.
STATE A
B c D
s EVENTS u,v,w AUXILIARY SYSTEM A STATES AND EVENTS STATE A
FOR WHICH THE AUX*
v.w
_. ILIARY/SAFETY SYSTEM -
B u.v.w.x c
u.v.w.x RELATIONSHIP APPLIES F
I SAFETY SYSTEM (3
I SAFETY SYSTEM
~
D SM7 SYSTEM E
s EVENTS Y,W v.w.z F
SAFETY SYSTEM 1T SAFETY SYSTEM FIGURE 1 SA-6 STATE EVENTS A
B Q,A c
D Q,R,S SAFETY SYSTEM s
FORMAT FOR COMMONALITY OF AUXILIARY DIAGRAMS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
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L EVENTS 7AN0!.
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CONTRDLROD DRIVE SYSTEM RDDWOflTH CONTROL ROD PA TTEJlll R2":5, RWM. RGM FIGURE 15A-10 SAFETY ACTION SEQUENCES FOR NORMAL OPERATION IN STATE 8 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
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L_.U FIGURE 15A-12 SAFETY ACTION SEQUENCES FOR NORMAL OPERATION IN STATED NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
(
EVENT7 MANUALOR
)
INADVERTENT SCRAM STATESA,B,C.~
F CONTROL ROD ORIVE SYSTEM S
F SCRAM FIGURE 15A-13 PROTECTION SEQUENCE FOR MANUAL OR INADVERTENT SCRAM NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANAL YSlS REPORT
(
r PLANNED OPERATION SCRAM SIGNAL WHEN 3MAIN STEAM LINES CLOSED >15%
INSERT CONTROL RODS REACTOR PROTECTION SYSTEM S
F CONTROL ROD DRIVE SYSTEM S
F SCRAM MSIV CLOSURE P<825 psig (RUN MODE)
INCIDENT DETECTION CIRCUITRY S
F RCICS MSIV CLOSURE HIGH PRESSURE LIFTS VALVE TRANSFERRING HEAT TO SUP-PRESSION POOL ST ART HPCS, RCIC, ON LOW WATER LEVEL MAINTAIN WATER LEVEL s F' CORE COOLING FIGURE 15A-14 PRESSURE RELIEF SYSTEM S
F PRESSURE RELIEF HPCS PROTECTION SEQUENCE FOR LOSS OF PLANT INSTRUMENT /SERVICE AIR SYSTEM NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 28 MAY 19.87
STATES B. D PRESSURE REGULATOR OPERATE FAILURE PLANNED SEE TO THE OPEN POSITION OPERATION EVENT NO. 23 EVENT9 INADVERTENT START-UP HPCSPUMP STATES A, 8, c ANO D STATES A,C PLANNED OPERATION
)
STATES B, D FEEDWATER CONTROLLER OPERATE PLANNED OPERATION FAILURE MAXIMUM DEMAND SEE EVENT N0.22 FIGURE 15A-15 PROTECTION SEQUENCE FOR INADVERTENT START-UP OF HPCS PUMPS
,NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNJT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 4 OCTOBER 1'1'12
(
STATE D EVENTlO STARTUP OF IDl.E RECIRCULATION PUMPS STATES A, B, C, D STATES A, B, & C STATE D POWER 5-10%
l6 v a:
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NEUTRON MONITORING SYSTEM
~
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FLUX ffi SIGNAL
~
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F NEUTRON MONITORING SYSTEM APRM HIGH FLUX SIGNAL SCRAM SIGNAL ON NEUTRON MONITORING SYSTEM TRIP PLANNED OPERATION PLANNED OPERATION CONTROL ROD DRIVE SVSTEM tNSERT CONTROL RODS S
F SCRAM FIGURE 1 SA-16 PROTECTION SEQUENCES FOR INADVERTENT STARTUP OF IDLE RECIRCULATION LOOP PUMP NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
(
EVENT 11 RECIRCULATION LOOP FLOW CONTROL FAILURE MAXIMUM DEMAND STATES C AND 0 STATE 0, MODE SWITCH IN AUN, POWER OPERATION STATEC STATED (MODE SWITCH NOT IN RUN)
NEUTRON MONITORING SYSTEM S
F CONTROL ROD DRIVE SYSTEM S
F SCRAM PLANNED OPERATION HIGH NEUTRON FLUX IAPRMl SIGNAL TO RPS SCRAM SIGNAL ON NEUTRON MONITORING SYSTEM TRIP INSERT CONTROL RODS FIGURE 15A-17 PROTECTION SEQUENCE FOR RECIRCULATION LOOP FLOW CONTROL FAILURE -
MAXIMUM DEMAND NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
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PROTECTION SEQUENCE FOR RECIRCULATION LOOP FLOW CONTROL FAILURE-DECREASING NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
111..ANfllEO OPERATION PRIMARY CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM S
F M,t.lf.I STEAM Llf.IE ISOLATION VALVES REACTOR 11£5SEL ISOLATION iYll!!_!1 RECIR~
LOOI' PUMPT.. I' Qt.IE OR IOTH STATES CANO D ONEPWPTRIP SACF 1WO PUMP TRIP STATE C Of\\IE PUMP TR IP FIE ACTOR l'AOTECTION SYSTEM S
F COf.ITAOLAOO DRIVE SYSTEM S
F SCRAM TWO l'UMP TRIP ONE PUMP TRIP AT LOW POWER SCRAM SIGNAL TURlllf\\IE TR" INSERT CONTROL RODS ESF DETI:CTION CIRCUITRY F
MAINTAIN WATER LEVEL 5
F INITIAL CORE COOLING PRESSURE RELIEF SYSTEM s
l'AESSURE RELIEF 5TAFIT HPCS, RCIC, ON LOW "'ATER LEVEL HEAT TO
&UPPRE$$10f<
POOL FIGURE 15A-19 PROTECTION SEQUENCE RECIRCULATION LOOP PUMP TRIP -
ONE OR BOTH NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
r
{
STATE C p < SETPOIN*T----C l'LANNED OPERATION STATE 0 p > SETPOINT REACTOR PROTECTION SYSTEM S F CONTROi.ROD DRIVE SYSTEM
& F SCRAM EVENT 14 ISOLATION OF ALL MAIN STEAM LINES STATES C, D SCRAM SIGNAL WHEN MAIN STEAM LINES CLOSED>15%
INSERT CONTROL ROOS RCICS PRESSURE RELIEF SYSTEM PRESSURE RELIEF ESF DETECTION CIRCUITRY MAINTAIN WATER LEVEL s f INITIAL CORE COOLING FIGURE 1 SA-20 HEAT TO SUP*
PRESSION POOL START HPCS, RCIC, ON LOW WATER LEVEL HPCS PROTECTION SEQUENCES FOR ISOLATION OF ALL MAIN STEAM LINES NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 28 MAY 1987
(
CONTINUE PLANNED OPERATION EVENT1*
ISOLATION OF ONE MAIN STEAM LINE STATES C, AND D LESS THAN 90%POWER GREATER THAN eo.POWER HIGH NEUTRON FLUX SIGNAL SCRAM SIGNAL ON NEUTRON MONITORING SYSTEM INSERT CONTROL RODS FIGURE 1 SA-21 NEUTRON MONITORING SYSTEM S
F CONTROL ROD OAIVE SYSTEM S F SCRAM PROTECTION SEQUENCES FOR ISOLATION OF ONE MAIN STEAM LINE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
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FIGURE 1 SA-22 PROTECTION SEQUENCES FOR INADVERTENT OPENING OF A RELIEF OR SAFETY VALVE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
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F ROD BLOCK STATE A EVENT16 CONTROL ROD WITHDRAWAL ERROR START*UP ANO REFUELING OPERATION STATES A ANO B STATE B STATE B INTERMEDIATE RANGE MONITOR NEUTRON MONITORING SYSTEM s
F REACTOR
" REFUEL" PROTECTION SYSTEM s
F CONTROL ROD DRIVE SYSTEM S
F SCRAM FIGURE 1 SA-23 HIGH NEUTRON FLU)(
SIGNAL SCRAM SIGNAL ON NEUTRON MONITOR ING SYSTEM INSERT CONTROL RODS PROTECTION SEQUENCE FOR CONTROL ROD WITHDRAWAL ERROR FOR START-UP AND REFUELING OPERATIONS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
tEUTllON MONITORING SYSTEM S F IEACTOR PROTECTION SYSTEM cnlTROL ROO DRlV£ SYSTEM SCRAH STATE 0 llffERMEOIATE RANGE HONITCJ'l HIGH IEUTRON R..UX SIGNAL INSERT ClllilTR11.
ROOS STATE D POWER RAMJE MCNITOR NUCLEAR
~51.fiEMENT ANALYSIS ANO CONffiOL ROD WORTH MINIHIZEJI POWER BELO'li 301.
Ra> SEOlJ81CE CCl.ITROl SYSTEM ROO BLOO<
MONITOR UNAUTHORIZED ROD WlllUIAWAL STCf' RID HQT[ON FIGURE 15A-2-&
PROTECTION SEQUENCE FOR CONTROL ROD WITHDRAWAL ERROR FOR POWER OPERATION NIAGARA MOHAWK POWER CORPORA T[QN NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVIS[ON 3 OCTOBER 1qcn_
1rc1 s r EVHH 18
"""'RHiiS tOSS Of. SHUT'DOW'ti COOLING STATES 4JJ.C AND 0 ISOLATION OF SHUTDOWN ALL OTHER ~INCLE FAILURES C:OOllNCi SUCTION LINE !---------------------------...
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s r AUS AHA SU...... ESSION l'OOL COOL ING l>MOUE S
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LOSS OF-SHUTDOWN COOLING FAILURE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
EVENT 19 AHR-SHUTDOWN COOLING INCREASED COOLING STATES A, B, C, ANO D AANOB CANDO PLANNED OPERATION PLANNED OPERATION FIGURE 1 SA-26 RHRS - SHUTDOWN COOLING FAILURE -
INCREASED COOLING NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
Ullil'U.
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EVENT21 t...OSS OFA FEEDWATER HEATER STATED RECIRCULATION FLOW IN MANUAL RECIRCULATION FLOW IN FLUX CONTROL MODE NEUTRON MONITORING SYSTEM S
F CONTROL ROD DRIVE SYSTEM S
F SCRAM HIGH FLUX SCRAM SIGNAL PLANNED OPERATION tTHERMAL POWER MONITOR)
SCRAM SIGNAL ON NEUTRON MONITORING SYSTEM INSERT CONTROL RODS FIGURE 15A-28 PROTECTION SEQUENCE FOR LOSS OF A FEEDWATER HEATER NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
PLANNED OPERATION STATES A AND B STATED EVENT 22 FEEOWATER CONTROLLER FAILURE
'"RUN.. MOOE NEUTRON MONITORING SYSTEM MAIN TURBINE TRIP RECIRCULATION PUMP TRIP IRPTI S F HIGH FLUX SCRAM SIGNAL llRMI REACTOR PROTECTION SYSTEM CONTROL ROD DRIVE SYSTEM REACTIVITY CONTROL l-IPCS SCRAM SIGNAL FROM TURBINE TRIP IRUN MODEi OR NEUTRON MONITORING SYSTEM INSERT CONTROL ROOS STATES CANO D ESF DETECTION I CIRCUITRY RCICS PRESSURE RELIEF SYSTEM S F PRESSURE RELIEF FIGURE 1 SA-29 PRIMARY CON*
TAINMENT AND REACTOR VESSEL ISOLATION CON
- TllOLSYSTEM S F MAIN STEAM LINE ISOLATION VALVE S F PROTECTION SEQUENCES FOR FEEOWATEA CONTROLLER FAILURE -
MAXIMUM DEMAND NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
PRESSURE RELIEF SYSTEM S F PRESSURE RELIEF EVENT 23 PRESSURE REGULATOR STATE 0 ONLY FAILURE *OPEN STATES C, ANO 0 SCRAM SIGNAL FROM
*MAIN STEAM LINE REACTOR PROTECTION SYSTEM ISOLATION
- TURBINE TRIP (RUN MODE:
POWER 30*50%)
ESF DETECTION CIRCUITRY LOW WATER LEVEL..._ __,.. __
(OTHER THAN s
f RUN MODE:
POWER0*10%
CONTROL ROD DRIVE SYSTEM s
F INSERT CONTROL RODS SCRAM HPCS MAINTAIN CORE COOLING s
F INITIAL CORE COOLING PLANNED OPERATION RE*ESTABLISH COOLING VIA MAIN CONDENSER INITIATE ISOLATION ON*
___ _._ ___ 1. DEPRESSURI*
START HPCS, RCICON LOW WATER LEVEL PRIMARY Z4TION T0850 pug CONTAINMENT IRUN MOOE AND REACTOR POWER 0-100%1 VESSEL ISOLATION CONTROL SYSTEM RCICS S
F MAIN STEAM LINE ISOLATION VALVES s
F REACTOR VESSEL ISOLATION FIGURE 1 SA-30 PROTECTION SEQUENCES FOR PRESSURE REGULATOR FAILURE -
OPEN NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
PLANNED oPlllATIDN E5F oETecnoN CIRCUITRY MAINTAIN CORE COOLING s,
RHA-SUPPllESSIOH POOL
~COOLING MODE
... os S
F HPCS p
[llTENDEO CORE COOLING EVENTl*
FIRST PRESSURE REGULATOR FAllURf - CLOSED
$TATlSC.&NDD
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F s
F MAIN STEAM LINE ISOLATION VALVES PRESSURE RELIEF s,
REACTOR VESSEL ISOLATION PROTECTION SEQUENCE FOR PRESSURE REGULATOR FAILURE-CLOSED NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
BYPASS SYSTEM OPERA HS PLANNED OPERATION RESUME l'OWfR Ol'ERATIO.. OR
... CHIEl/f SHUTDOWN POWER
> 30'x.
MAIN TURBINE TF!IP s f RECIF!CULA TION PUMP TRIP IRPTI s r REACTOR PROTECTION SYSTEM S F CONTROL ROOORIVE SYSTEM REACTIVITY CONTROL ill.!ilX!
MAIN TURBINE TRIP WITH BYPASS STATED SCRAM SIGNALS.
I. TUR81Nf; SToP VALVE CLOSURE INSERT CONTROL ROOS ESF DETECTION Cl!IClllTRY S
F s I' INITIAL CORE COOLING RCICS l'RESSURE RELIEF SYSTEM PRESSURE RELIEF FIGURE 15A.-32 PCRVICB MAIN STEAM LINE ISOLATION PRIMARY CONTAINMENT ISOLATION PROTECTION SEQUENCES FOR MAIN TURBINE TRIP WITH BYPASS NIAGARA MOHAWK POWER CORPORATION NINE MILE PO"INT-'UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAA REVISION 4 OCTOBER ~ 1992
TU-.lt"ill ACC1JICUl.&f1Dfrl I
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UAINST£AM LINE ISOLA TIDN PRIMARY CONTl.INMENT lSOlATION PROTECTION SEQUENCES FOR LOSS OF MAIN CONDENSER VACUUM NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
BYPASS SYSTEM Ol'ERATES PLANNED Of'EAATION RESU"'E POWER OPE AA TION OR ACHIEVE SHUTDOWN POWEii
>~
MAIN TURBINE TRIP IGENEAATORt S F RECIRCULATION P\\JMf' TRIP' CAP'TI s
f REACTOR PROTECTION SYSTEM S F CONTROL RODDRlllE SYSTEM REACTIVITY CONTROL EVENT77 GENERAiiift"TRIP' WITH BYPASS STATED SCRAM SIGNALS' E6F DETECTION CIRCUITRY 5 F
- t. TURBINE CONTROL VALVE FAST CLOSURE l"ISERT CONTROL ROOS INITIAL CORE COOLING l'RESSURE RELIEF 8VSTE!lol 5 F PRESSURE RELIEF PCRVICS MAIN STEAM LINE ISOLATION PRIMARY CONTAINMENT ISOLATION FIGURE 15A.-34 PROTECTION SEQUENCES FOR MAIN GENERATOR TRIP WITH BYPASS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
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AUXILIARY TRANSFORMER FAILURE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
DUl "lO LOSll OF C4tdJfH1~
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- GU'lllt.D\\>~"'SfOl'I CC..llaGl.Ll*.....,..l*f-FIGURE 1SA.-36 PROTECTION SEQUENCES FOR LOSS OF NORMAL AC POWER -
GRID CONNECTION LOSS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
POWER
<Jeno POWER
.. Jo,.
SCRAM SIGNALS I. HIGH PRESSURE
- ! HIGM FLUX REACTOR PROTECIION SYSTEM S
F CONTROL 1'100 ORIVE SVSTEM S
F SCRAM MAIN TURBINE TRIP S
F RECIRCULATION PUMP TRIP iRPTI s
REACTOR PROTECllON SYSTEM CONTROL ROD URIVE SYSTEM S
F s
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WITH BYPASS FAILURE STATE 0 ESF DETECTION CIRCUITRY S F SCRAM SIGNAl.S:
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RELIEF SYSTEM 5
PRESSURE RELIEF PCllVICS s F MAIH STEAM LINE 180LA noN I F PRIMARY
'CONTAINMENT ISOLATION FIGURE 1 SA-37 PROTECTION SEQUENCES MAIN GENERATOR TRIP-WITH BYPASS FAILURE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
POWER
< 30'lio MAIN TURBINE TRIP s F RECIRCULATION PUMP TRIP IRPTI s F REACTOR PROTECTION SYSTEM s
F CONTROL ROD DRIVE SYSTEM s F s
F REACTIVITY CONTROL ESf DETECTION PCRVICS CIRCUITRY s,.
HPCS RCICS
$ F SCRAM SIGNAL:
TURBINE STOP VALVE CLOSURE INSERT CONTROL ROOS INITIAL CORE COOLING PRESSURE RELIEF SYSTEM S F PRESSURE RELIEF MAIN STEAM LINE ISOLATION S F PRIMARY CONTAINMENT ISOLATION FIGURE 1 SA-38 PROTECTION SEQUENCES MAIN TURBINE TRIP - WITH BYPASS FAILURE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
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EVENT32 INADVERTENT LOADING AND OPERATION - FUEL ASSEMBLY IN IMPROPER POSITION STATES A, 8, C, 0 PLANNED OPERATION FIGURE 1 SA-39 PROTECTION SEQUENCE FOR INADVERTENT LOADING AND OPERATION OF FUEL ASSEMBLY IN IMPROPER POSITION NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
ESF DETECTION CIRCUITRY I
REACT Of'
'ROTE CTI ON SVSTEM I
I CONTROL RODDl!IVI IYJTIM SENSES HIGH REACTOR YESSlL WATER LEVEL stAAMSIClNAL FROM TURBINE TRIP INHl'IT CONTROL RODS
.!Y1!UA RECIRCULATION looP P\\Jloll' SEIZURE STATE DONlV ESF DETECTION CIRCUITRY 5
F AHR SUPPRESSION POOL COOLING MODE SENS£$
l0WWAT£R LEVEL
'RESSUR2 RELIEF SYSTEM s F PRESSURE RELIEF MAINTAIN WAT!A LEVEL SUPPRESSION POOL Tl!MPl!RATURE START DEPRESSURIZll TION ADS EXTENDED COflE COOLING FIGURE 15A-40 PCRVICS S F MAIN STEAM LINE 180LA Tl ON S F PRIMARY CONTAINMENT ISOLATION PROTECTION SEQUENCE FOR RECIRCULATION LOOP PUMP SEIZURE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 1UPDATED SAFETY ANALYSIS REPORT USAR REVISION 4 OCTOBER 1~2
ESF DETECTION CIRCUlmV S F REACT Oii PROTECTION SYSTEM s,
CONTROL ROD DRIVE SYS'TEM S
F SCA AM SENSES HIGH REACTOll YHSiL WATER LEVEL SCRAM SI G"'AL FROM
'TURBINE TRIP INSERT CONTROL RODS
~
RECIRCULATION LOOI' PUMP SHAFT IREAK STATEOONLV ESF DETECTION CIRCUITRY S F.
MAINTAIN CORE COOLING AHR SUPPRESSION POOL COOLING MODI!
ADI Ell'TENDED COllE COOLING SEN5e5 LOWW... TER LEVEL SUPPRESSION POOL TEMPERATURE START llEPRESSURIZATION PRESSURE RELIEF SVSTEM s,
PRESSURE RELIEF FIGURE 15A -41 PCRVICS 5
F MAIN STEAM LINE ISOUTION PRIMARY CONTAINMENT ISOLATION PROTECTION SEQUENCE FOR RECIRCULATION LOOP PUMP SHAFT BREAK NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 4 OCTOBER 1q~z
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a l'lllMARY CONTAINMENT AHO AEACTOR YliSSEl. lliOLATION CONl AOL SYSTEM s r PRll.tAR'i' CONTAIHMEH1 CPASSlllE) s r PRIMARY ESTABLISH MANUAL 5RV Pall\\11014 M'llNT'llNWATER lfVCL IN n£1'1:101t VUSEL ___..
p ESf OETllCllOH ClllCUITRV MAtNTAIN CORt COOLl"'<l tXffl*DEU COftf CUOLIHQ S1ARI HPa ftCtCUllf LOW WAl flt UllU toffTnOLltOO llUVCllY
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FIGURE 15A-42 PROTECTION SEQUENCES FOR CONTROL ROD DROP ACCIDENT NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N. Y.
UPDATED SAFETY ANALYSIS REPORT USAR REVISION 15 OCTOBER 2002_
(
REACTOR BUILDING VENTILATION RADIATION MONITOIUNG SYSTEMS S F REACTOR BUILDING ISOLATION CONTROL SYSTEM S F STANDBY GAS TREATMENT SYSTEM S F REACTOR BUILDING IPASSIVEI RADIATION MONITOR TRIP INITIATE BUILDING VENT ISOLATION EVENT41 FUEL HANDLING ACCIDENT STATES A. 8, C, ANO 0 MAIN CONTROL ROOM HEATING VENTILATING ANO AIR CONDITIONING SYSTEM S F MAIN CONTROL ROOM ENVIRON*
MENTAL CONTROL FIGURE 15A-43 RADIATION LEVEL INDICATION PROTECTION SEQUENCES FOR FUEL HANDLING ACCIDENT NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
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FIGURE 1 SA-44 PROTECTION SEQUENCES FOR LOSS-OF-COOLANT PIPING BREAKS IN RCPB-INSIOE CONTAINMENT NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
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PLANNED OPERATION STATES A, B EVENT48 OFFGAS SYSTEM LEAK OR FAILURE STATES A, B, C, D
)
STATES C, D MANUAL OPERATOR ACTION OFF-GAS SYSTEM 1501.ATION MAIN CONDENSER LOW VACUUM SEE 1.0SS OF CONDENSER VACUUM EVENT26 FIGURE 1 SA-46 PROTECTION SEQUENCE FOR GASEOUS RADWASTE SYSTEM LEAK OR FAILURE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
STATES A,B PLANNED OPERATION EVENT41 AUGMENTED OFF-OAS TREATMENT SYSTEM FAILURE STATES A, B, C, AND D STATESC.D MANUAL OPERATION ACTION OFF-OAS SYSTEM ISOLATION MAIN CONDENSER HIGH PRESSURE MAIN TURBINE TRIP
~
F CONTAOL ROD DRIVE SYSTEM SCRAM FIGURE 15A-47 SEE OTHER LOSS OF CONDENSER VACUUM EVENT2B ACTIONS PROTECTION SEQUENCE FOR AUGMENTED OFF-GAS TREATMENT SYSTEM FAILURE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
GAS LEAK HIGH RADIATION PROCESS VENl'I*
LATION RADIATION MONITORING SUBSYSTEM VENTILATION SYSTEM CONTROL ISOLATE BUILDING OR AREA EVENT 48 LIQUID RADWASTE SYSTEM l LEAK OR FAILURE f
STATES A, B. C. D
~
FIGURE 1 SA-48 WATER LEAK HIGHWATER FLOOR DRAIN MONITORING SYSTEM SUMP PUMP SYSTEM PRIMARY CONTAINMENT LIQUID EFFLUENT PROTECTION SEQUENCE FOR LIQUID RADWASTE SYSTEM LEAK OR FAILURE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
GAS LEAK HIGH RADIATION PROCESS VENTI*
LATION RADIATION MONITORING SUBSYSTEM VENTILATION SYSTEM CONTROL ISOLATE BUILDING OR AREA EVENT49 LIQUID RAOWASTE SYSTEM
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STORAGE TANK FAILURE STATES A, B. C, D
~
FIGURE 1 SA-49 WATER LEAK HIGHWATER FLOOR DRAIN MONITORING SVSTEM SUMP PUMP SYSTEM CONTAIN LIQUID EFFLUENT PROTECTION SEQUENCE FOR LIQUID RADWASTE SYSTEM STORAGE TANK FAILURE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
I l
OPERATOR MANUAL INITIATION REACTOR BUILDING VENTILATION RADIATION MONITORING SYSTEMS REACTOR BUILD*
ING ISOLATION CONTROL SYSTEMS S
F STANDBY GAS TREATMENT SYSTEM S
F REACTOR BUILDING CPASSIVEI ESTABLISH SECONDARY CONTAINMENT RADIATION MONITOR TRIP SERVICE WATER SYSTEM INITIATE BUI LOI NG VENT ISOLATION rXTERNAL COOLING SPRAY RESTORE CASI<
COOLING FIGURE 1 SA-50 INTERNAL COOLING CONNECTION TEMPORARY CONTAINER PROTECTION SEQUENCE FOR SHIPPING CASK DROP NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
STATES B, D REACTDR PRDlECTIDN SYSTEM p
STANDBY LIQUID COHTRDL SYSTEM CORE RE.ACTIVITY COKTRDL PLANNED OPERA TIDNS CDNTIKUE SHUTDOWN COOLING llPT ARI C AD ACIC5 CORE REACTIVITY CONTRDL EVENT 51 REACTOR SHUTODWN FROM ANTICIPA TEO TRANSIENT WITI!DUT SCRAM STATES 11. C. 0 REACTOR ISOLATED FROM MAIN CONDENSER STATESC,D ESF DETECTION CIRCUITRY MAINTAIN WATER LEVEL RHR SUPPRESSION POOL COOLING MODE STi\\RTHPCS, RCICSVSTEM ON LOW WATER LEVEL HPCS REMOVE DECAY HEAT FROM SUPPRESSION POOL HEAT TO SUPPRESSION PDDL AHR SHUTDDWN COOUNGMODE CORE COOLING FIGURE 1 SA-51 PRESSURE RELIEF SYSTEM PRESSURE RELIEF PROTECTION SEQUENCE FOR REACTOR SHUTDOWN -
FROM ANTICIPATED TRANSIENT WITHOUT SCRAM NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
I STATE A.
PLANNEll OPE RATIONS CONTINUE SHUTDOWN COOLING p
EVENT st REACTOR SHUTDOWN FROM ANTICIPATED TRA"SIElfTwmtOUT SCRAM FROM O\\ITSIOE MAIH CONTROL ROOll STATESA.B C D.
I STATES 8, D llEACTOA l\\IOT ISOLATED I REACTOR ISOLATED FF10M FROM MAIN COl\\IOENSER A MAIN CONDENSER STATES C. 0 REACTOR PROTECTION SYSTEM CONTROLllOO DRIVE SYSTEM SHUTDOWN RE ACTOll FR0"1 OUTSIDE CON*
TROl.AOOM SCRAM BY OE*ENERGl?ING
-SYSTEM MANUALLY I
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I PLANNED OPEF1A TIOl\\I CONTROL COOLOOWN USING l\\IORMAL EOUtPMENT MAINTAIN
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STATESC. D I STATES B, c. D I
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-SUP!'AESSION POOl p
I I
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COOL OOWN REACTOR FROM OUTSIDE MAIN CONTAOl llOOM FIGURE 15A*52 PROTECTION SEQUENCE FOR REACTOR SHUTDOWN -
FROM OUTSIDE MAIN CONTROL ROOM NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
p StATES8.D REACTOR l'ROf ECTION SYSTEM STANDBY llQlUD COlllTR01..
SYSTEM CORE REACTIVITY CONTROL fVlf>fT.:I 911..C'IOR S>flllll(MN WITMOU'f ~T1'0l -
STAT£S9.-D REACT°" HOT ISOl.AfEO FROM lolAIN CONOENSEA l'l.APNEO OPEftit.TION.
CONTROL COOL~
USING NORMAL fQUfl"MENT RCICS WATEft t£VEL SfUE$ ** O RfACTOfl ISOLATED FROM IWUN CONDENSER HEAT TO SUPPRESSION
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) 13S""'
ESF DETECTION ClllCUITRY lll'CS AHR SUPPRESSION POOL COOLING UOOE p
(!JS-ST AR1..CS. ACIC
'$YSlE.U Ole L-W... fER LEVEL REMOVE DECAY HEAT FROM SUl'f'flESSION POOl.
s r AHR.t;HlJTDOWN COot.INQ MODE p
FIGURE 1 SA-53 PROTECTION SEQUENCE FOR REACTOR SHUTDOWN -WITHOUT CONTROL RODS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 4 OCTOBER J~'i2
I CORE We = Total Core Flow WA
=
Active Loop Flow W,
= Inactive Loop Flow
) 1----------------~---------------------------------------1 1Niagara Mohawk Illustration of Single Recirculation Loop
'Power Corp.
Operation Flows USAR Revision 8 Figure 158.2-1 November 1995
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- Nia.Gara Mohawk Power Corpora*
With Bypass Failure 70 80 90 100 lnitlal Power Levsl (% NBFU Peak Dome Pressure vs. lnltild Powsr level, LRBPF at EOC (TYP.tCAL) 110 Figure 151.3-1 USAR REVISION B NOVEMBER 199S
0
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NOTE: CYCLE-SPECIFIC INFORMATION IS PRESENTED lN APPENDIX A.
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FIGURE 15 B.3*2 FEEDWATER CONTROLLER FAILURE
- MAXIMUM DEMAND, 82% POWER, 60% FLOW NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT* UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION B NOVEMBER 19%
1~.01--+-1----1------1---------1
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2.0 mr (S£COM>S) 1 LEVEL( I 2 VESSEl S J TURBll'<E 4.0 200.0 i--------....:..4
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NOTE: CYCLE-SPECIFIC INFORMATION IS PRESENTED IN APPENDIX A.
1.0 m.ol-----+-------11-------i
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FIGURE 15 B.3-3 GENERATOR LOAD REJECTION WITH BYPASS FAILURE, 82% POWER, 60% FLOW NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT* UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1'3%
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RGURE 15 B.3-4 GENERATOR LOAD REJECTION WITH BYPASS FAILURE, 82% POWER, 60% FLOW, EOC-RPTOOS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT* UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION B NOVEMBER 1CJ9S
FLUX FACE HEAl FLUX NI.El FLO\\/
150.0 f--------,-,,,.--'-!'=-;r:ll.=ET.:-=SUB=-----1 Iii s 100.0
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NOTE: CYCLE-SPECIFIC INFORMATION IS PRESENTED tN APPENDIX A.
- !O.O 100.01-----------+---l------I
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I VOID REA Vl1Y 2 ;PLER CT IVITY J
CRAM RE C IVllY 4 OTAL RE C IVllY I~ v 1.0 I
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FIGURE 15 B.3*5 FEEDWATER CONTROLLER FAILURE
- MAXIMUM DEMAND, 82% POWER, 60% FLOW, EOC-RPTOOS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT
- UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995
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RGURE 15 B.3-6 FEEDWATER CONTROLLER FAILURE
- MAXIMUM DEMAND, 82°/o POWER, 60% Fl.OW, BPOOS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT* UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION B NOVEMBER 19%
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FIGURE: 15.B.5-1 PEAK CLADDING TEMPERATURE VERSUS TIME AFTER BREAK (BP/P8X8R FUEL) 0.11 SQ.FT HPCS LINE BREAK, LPCS DIESEL GENERATOR FAILURE WITH 2 ADS VALVES OUT-OF-SERVICE NOTE: "Results from initial LOCA analysis.
NINE MILE POINT NUCLEAR STATION-UNIT2 SCRIBA, N.Y.
Cycle-specific information is presented in Appendix A" USAR UPDATED SAFETY ANALYSIS REPORT REVISION 22 OCTOBER 2016
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Cycle-specific information is presented in Appendix A" 0.1 1
Break Area (SQ FT.)
FIGURE: 15C-4 PEAK CLADDING TEMPERATURE VERSUS BREAK AREA HPCS LINE BREAK, LPCI DIESEL GENERATOR FAILURE WITH 2 ADS VALVES OUT OF SERVICE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA. N.Y.
UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016
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NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.
UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016
' VESSEL PnEssu lPSIAl a:
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NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.
UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016
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NOTE: "Results from initial LOCA analysis. Cycle-I specific information is presented in Appendix A" NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.
UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016
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UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016
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Nine Mile Point Unit 2 FSAR Figure 15E.3 Core Offload Sequence Map 121~ 122 123 124 125 126 127 128 ~129
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Nine Mile Point Unit 2 FSAR Figure lSE.3 Core Reload Sequence Map 8~ BO 79 78 77 76 75 74 i;t73 82'1 50 49 48 47 46 45 44 43 72 -l-108 1'
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143 115 89 57 58 59 60 61 62 63 64 65 101 131 163 23 -
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= SRM Detector Locations USAR Revision 8 November 199S
Nine Hile Poinc Unic 2 FSAR F11ur* lSE.l*l - tn1cial Core Fu*l Laadin1 Sequence I 1
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