ML22292A118
Text
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- - - MINIMUM OPERATING CPR LIMIT
... - - - - - - EVBllT MINIMUM OPER. LIMIT -
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I. IO lnq(Ta SCRAH SPCCO FIGURE 15.Q..1 MINIMUM OPERATING CPR LIMIT VS. SCRAM SPEED-CYCLE 1 NIAGARA MOHAWK POWER CORPORATION NOTE: Cycle-specific information is presented in NINE MILE POINT - UNIT 2 Appendix A, UPDATED SAFETY ANALYSIS REPORT USAR .REVISION 8 NOVEMBER 1995
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- fi 0 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
Cure Hun l!IBl111~hr) 0 10 2D ~() *It: so 61J iO <)() IC-0 IW l~O l~ll i:u 10~1 ::i'~ ~'-'**&1 JjJ:d f~tft
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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 40 I 80 I
I I
I I
I I
30 M I 60 I
I SCRAM I Position Reactivity I (percent)
(-$) I I
I 20 I 1 40 I 2 I
I I
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I 10 I 20 I
I I
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~
0 0 1 2 3 4 Time (seconds)
FIGURE 15.0-3
- Applicable to events analyzed with REDY Code ODYN Code SCRAM Reactivity is calculated internally during the transient event. SCRAM POSITION AND REACTIVITY
NINE MILE POINT - UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 14 FEBRUARY 2001
/ I NEUTRDN I LUX I VESSEL Pf 1=5 lllSE (PS II 2 llELlEF VI VE FLOW
.L 2 RVE SURFI CE tERT FLUX 3 CORE !NL T FLOW 125. 3 BTPASS VI LVE FLOH "s6 150.
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- -25.
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Tllif ISECI Til1E CSECJ I LEVEL IINC H-AEF-SEP-SKIRT l VOID .~ TIVITT 2 VESSEL S ERHFLDM 2 IJCPPLEA ERCTlVITT 150. 3 TURBINE TERHFLDW 1. 3 SCR!li AEJ CTlVITY
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TIHE ISECI THIE ISEC)
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
l VESSEL Pl ES RISE IPSII 2 RELIEF VI VE FLOW 125 3 Bl'PASS Vf VE FLCH q
5 6
75.
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- 20. 110.
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TIME CSECI
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i 8
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- 20. YO. 60.
TIHE ISECJ
- 20. °*
THIE CSECl 60. 80.
FIGURE :15.1-2 LOSS OF FEEDWATER HEATER, MANUAL FLOW CONTROL NOTE: THESE RESULTS ARE FOR CYCLE 1.CYCLE- NIAGARA MOHAWK POWER CORPORATION SPECIFIC RESULTS ARE PRESENTED lN APPENDIX A. NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S
- 25.~u...LJ..........U.---~---,J,---.i.....--~
B. 12. ~ ~ ~ ~. ~.
TIME ISECI TIME ISECl o.
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- 6. 12. 15.
T!HE ISECI T!HE lSECI FIG URE 15. l-.3 FEEDWATER CONTROLLER FAILURE, MAXIMUM DEMAND NOTE: THESE .RESULTS ARE FOR CYCLE J.CYCLE- NIAGARA MOHAWK POWER CORPORATION SPEClFIC RESULTS ARE PRESENTED IN APPENDIX A.
NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S
1 NEUTRON FLUX 1 VESSEL PRES RISE (p1il 2 AVE SURFACE HEAT FLUX 2 RELIEF VALVE FLOW 150 3 CORE INLET FLOW 150 3 BYPASS VALVE FLOW 4 CORE INLET SUB 0
w I-
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ct IL 0
I-z w
u 50 a:
w 3 2
0 0 10 20 JO 40 10 20 JO 40 50 TIME becl TIME (sec) 1 LEVEL linch-ref-leP-skirll 2 VESSELSTEAMFLOW 150 3 TURBINE STEAMFLOW 4 FEEDWATEA FLOW 2
ol--.1....l...l~i....::::t:=::::::J...__...1..J...---1.J - 2 0~~~-':-4~..1&.~~8~~~~12~~~~16 "'-~~_.20 0 W W 40 50 l lME lsecJ TIM E' lsecl FIGURE '15.1-4 PRESSURE REGULATOR FAILURE NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT SET REACTOR OPERATING LIMITS AND IS NOT REANALYZED NIAGARA MOHAWK POWER CORPORATION FOR POWER UPRATE OR FOR EACH RELOAD CYCLE. NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995
1 NEUTRON FLUX 2 PEAK FUEL CENTER TEMP JOO 1 VESSEL PRES RISE (ptil 150 J AVE SURFACE HEAT FLUX 2 5' LINE PRES l'llSE (p1il 4 FEEOWATEA FLOW J SAFETY VALVE FLOW lbl 5 VESSEL STEAM FLOW 4 RELIEF VALVE FLOW l*I 0
uJ 5 BYPASS VALVE FLOW l*I t- 6 TURBINE STEAM FLOW hU
~ 100 200
- u. 2 0
t-zw u
IC 50 w
a.
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4 CORE INLET FLOW ltl 5 DRIVE FLOW 1161
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a: - 1 f VOID REACTIVITY 2 DOPPLER REACTIVITY 3 SCRAM REACTIVITY 4 TOTALREACTIVITY
- 100 _ _ _........_ _ _....__ ___,..__ _ _ _ ____,
0 2 4 6 8 10 2 3 4 5 TIME tsccl FIGURE 15.2-1 GENERATOR LOAD REJECTION WITH BYPASS NOTE: THESE RESULTS ARE FOR CYCLE l. THIS EVENT rs LESS SEVERE THAN THE CASE WITH BYPASS FAILURE NIAGARA MOHAWK POWER CORPORATION ANO IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE. NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISlON 8 NOVEMBER 1995
- 1 NEUTRON FLUX 1 VESSEL PRES RISE (pall 2 PEAK FUEL CENTER TEMP 7 Sl'M LINE PRES RISE (pall 160 3 AVE SURFACE HEAT FLUX 300 3 SAF-ETY VALVE FLOW ltl 4 FEEOWATER FLOW 4 RELIEF VALVE FLOW l*I 5 VESSEL STEAM FLOW 5 BYPASS VALVE FLOW I*>
6 TURBINE STEAM FLOW l*I D
w
<(
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IL 0
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u 50 100 a:
w TIME lse<:I TIME l$0CI 1 LEVEL linch-<Vl-sep-skir1I 2 WR SENSED LEVEL l1nchell 200 J NR SENSED LEVEL !inches) 4 CORE INLET FLOW (fl 5 DRIVE FLOW 1 l*I 5
~
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w 0 a: - 1 1 VOID REACTIVITY 2 DOPPLER REACTIVITY 3 SCRAM REACTIVITY 4 TOTAL REACTIVITY 3 4 5 TIME lsecl TIME tsecl FIGURE 15.2-2 GENERATOR LOAD REJECTION WITHOUT BYPASS NIAGARA MOHAWK POWER CORPORATION NOTE: THESE RESULTS ARE FOR CYCLE 1.CYCLE-SPECIFIC RE5UL rs* ARE PRESENTED IN APPENDIX A. NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER i995
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TU£ l:UI 111£: ISECI FIGURE ~15.~-~
TURBINE TRIP, TRIP SCRAM, BYPASS AND APT - ON 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 B NOVEMBER 199S .
l!"IO.
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TllE ISEtl FIGURE 15.2-4 TURBINE TRIP WITHOUT BYPASS, TRIP SCRAM 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 -
- or. ,- --
I I STH LINE PRES RISE !PSll I Vf.55£L P ES RISE IPSJI 2
- ---- ---- 3 SRf TT Vf ~.Lf.l.QlLC*I II RfLlEF V VE FLOW !el
- s BTPF;SS V l/E FLOW [el Is TURBINE TE.AH FLOW 1.1 0 a-'-'--......J...-W..1~1LJ.l.--=~4~.~~~6*......_~---=~~""""'
Tli'IE ISECI I 1 LEVELi 1NM11-nff-SEI' - 5~lfiT l voio\nEA TIVliT 200
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TIME. ISfCl TJl'.E lSECl FIGURE 15.2-5 MSIV CLOSURE, POSITION SCRAM NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT NIAGARA MOHAWK POWER CORPORATION SET REACTOR OPERATING LIMITS AND IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE. NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S .
I NEUTRON LUX 2 PERK FUE CE~TER TEMP 150. 3 RVE SURF CE HEAT FLUX YFEEDWATE FLDH 5 VE5Sa 5 EAK FLOW
~ 100.~~'C"&,,.f---\,.-1----l-----l--
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- 12. o. 3. 6, 9. 12.
TIME ISECI E
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- a. 3. s. s. 12. 1.
TlME lSECI 2.
TIHE ISECI
..-3**----.....
FIGURE~----------------------------------.a 15.2-6 LOSS OF CONDENSER VACUUM NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT NIAGARA MOHAWK POWER CORPORATION SET REACTOR OPERATING LIMITS ANO IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE.
NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995
150 300 1 VESSEL PRES RISE (psil 1 NEUTRON FLUX 2 RELIEF VALVE FLOW 2 AVE SURFACE HEAT FLUX 3 BYPASS VALVE FLOW 3 CORE INLET f LOW 4 CORE INLET sue 200 IL 0
...uz 1-a: 100 20 JO 40 50 20 30 40 50 TIME (sec) TIME lsecl 200 1 LEVEL linc;h-rel*sep.,.kirtl 2 VESSELSTEAMFLOW 3 TURBINE STEAMFLOW ~
z"'
4 FEEDWATER FLOW I-w z
0 1 VOID REACTIVITY 0..
~ 2 DOPPLER REACTIVITY 0 J SCRAM REACTIVITY u 4 TOTAL REACTIVITY
~
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<t w
a:
-l000~~~~.~0~~~20~~~~30~~~~40~~---'50 -2 0 2 4 6 e 10 TIME lsccl TIME lsecl FIGURE 15.2-7 LOSS OF ALL RESERVE AND NORMAL TRANSFORMER NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT NIAGARA MOHAWK POWER CORPORATION SET REACTOR OPERATING LIMITS AND IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE.
NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S
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 G TllfiBIN( ! ffRH FUlfl 1.. 1
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- a. 3. s. s. 12. o. l. 2. 3. l!.
TIME CSECI TIHE !SECI FIGURE 15.2-8 LOSS OF ALL GRID CONNECTIONS NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT NIAGARA MOHAWK POWER CORPORATION SET REACTOR OPERATING LIMITS ANO IS NOT REANALYZED NINE MILE POINT-UNIT 2 FOR POWER UPRAT~ OR FOR EACH RELOAD CYCLE. 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-
!J
-JSO. r........u..Lu....u_L__ __i__ _~O---ll~Oc----...::1..
- a. 10. 20. 3 * -
Tll'IE ISECJ
-125 ...L.+..w..L......_._.,.J,__ _-::i=----+/-----;-;';:;--= ..
- 0. IO. 20. 30. ~O.
rIME. ISECI FIGURE 15.2-9 LOSS OF FEEDWATER FLOW NG TES:
- l. SEE ASTERISK NOTE IN TABLE 15.2-11. NIAGARA MOHAWK POWER CORPORATION
- 2. THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT SET REACTOR OPERATING LIMITS ANO IS NOT REANALYZED NINE MILE POINT-UNIT 2 FOR POWER UPRATE OR FOR EACH RELOAD CYCLE. UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S
l 625 575
\
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~
~
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v VI VI G.l 525 G.l 0
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475 0
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VI QI
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_,cu 425 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
470
-....Q) 0 N
a;
- !cu 450
~
v !--"
~
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_v 0
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VI Q) 430 u
- .§ '\..r--.....
a; Q)
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E 410 Nominal Lev I 0
u c
ill I
I 0
Cl
-t 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 ~
f-l* , . _ - - - - - - 1 0 4 5 ps1a, 560"f TO 100 psi, 330"F - - - - - - - _ . . , . ,..._.
_ _ 100 PS*. J3Q*F TO 14 7 PSI, 125"f ~
DEPRESSURIZE NORMAL SHUTDOWN VESSEL TO COOLING MAIN CONDENSER IOFFSITE POWER I w
...J m
<t
...J
<t
.q:
ffi CONDENSER DEPRESSURIZE VESSEL AOSIRELIEF VALVE S: NOT AVAILABLE VIA MANUAL RELIEF AL TERNA TE PATH
~ t - - - - - - - - - - i l - - t VALVE ACTUATION .. AHR w SUPPRESSION POOL
!: COOLING II!
u..
u..
0 A D NORMALSHUTDOVVN NORMAL COOLING COLO SHUTDOWN ION SITE POWER) SHUTDOWN INITIATED ACHIEVED P = 1055 psia tvESSEL HEAD T = 550"F REMOVED I wl- ADS/RELIEF VALVE 1-z
_w ALTERNATE PATH
~~
u.. <t 0 a:
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oa:
II> UJ II> 3:
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DEPRESSURIZE VESSEL FAILURE Of AUTOMATIC VIA MANUAL RELIEF DIVISION I DIESEL ADS/RELIEF VALVE RELIEF VALVE VALVE-ACTUATION* RHR SUPPRESSION POOL AL TEAlllATE PATH ACTUATION COOLING FIGURE 15.2-10
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 ------------+14---
- _. 115 psi, NO340°F POWER TO 14.7 OFFSITE psi, 125°F ---i
____J I
I c2*
ADS VALVE RHRLOOPA (DIVISIONS 1 AND 3)
AVAILABLE)
A* e*
NORMAL LOSS OF DEPRESSURIZE OFFSITE POWER DIVISION U FAILS SHUTDOWN VESSEL VIA TRANSIENT AUTOMATIC INITIATED ADS/RELIEF I RELIEF VALVE 1 ACTUATION VALVE ACTUATION "
P = 1055 psla RHR SUPPRESSION T; 550 °F POOL COOLING DIVISION I FAILS C1*
ADS VALVE RHR LOOPS B AND C (DIVISION 2 AND 3 AVAILABLE)
FIGURE 15.2-11 ADS/RHR COOLING LOOPS
- FOR DEFINITION OF A,B,C1, ANO C2, SEE NOTES ON NEXT 2 PAGES.
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 ALTERNATE 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
SIR MSL VALVE ORYWELL REACTOR VESSEL SUPPRESSION AREA RHA A r-H-;;T-1 EXCHANGER I
AHA SERVICE --L---....:r-"J;-l-IM...- ..... SERVICE WATER SYSTEM WATER IL ____ JI DISCHARGE 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 800 1100 1000 600 -
900
... 800 iL 400 o_
i w w a:
a:
- > 700 ~
II) <a:
a:
...w II) w a:
..J 600 300 ~
w II) 1-
"'w>
..J w
500 t:iw 400 200 JOO PRESSURE 200 100 100 CASE B 0
100 101 TIME hee l 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:
~
~
a: 140 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 iii 900 a.
800 I 700 iflJ
~ 600 a.
500 fl>>
Cl) 400 300 200 100 0
1 10 100 1000 10000 100000 1000000 TIME IS£Ct flGURE 15.2-18 VESSEL PRESSURE VS. TIME ALTERNATE SHUTDOWN COOLING ANALYSIS- POWER UPRATE NIAGARA MOHAWK POWER CORPORATION THIS DRAWING CREATED ELECTRONICALLY NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995
700 600 -
-I-
- u. 500 -
w
~ 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 a: 150 I ll i
UI D.
I_,
100 0
0 60 10 100 1000 10000 100000 1000000 FIGURE 15.2-20 SUPPRESSION POOL TEMPERATURE VS TIME ALTERNATE SHUTDOWN COOLING ANALYSIS- POWER UPRATE NIAGARA MOHAWK POWER CORPORATION THIS DRA\vING CREATED ELECTRONICALLY NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995
l Suppression Pool 2 Wei well Air space NMP2 EPU ASOC K*270 200. 2 u.. 2
!.!)
UJ c
QI 30 Q.
E Ill I-100.
- 0. I I I I I I I I I I I I I I I I I I I
- 0. 4. 8. 12. 16.
5~ 20A3CBBF 042908 1541.1 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 I VCSSEL P ES RISE IPSI I 2 AVE SURF CE HERT FLUX 2 RELIEF V LVE Fll'IH 3 CORE INL DTPA55 II L..'LE FLOW CCR INL + ~LgL-ISO. 125.
II OIFFUSEl'j Fll'JH l li:J II s 5 DIFFUSER FLOW 2 IY.l 6
Ci lOO. 75.
~
a:
a:
~
- z w 50. 25.
Ir UJ 110. llO.
5 FIGURE 15.3-1 NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT TRIP OF ONE RECIRCULATION SET REACTOR OPERATING LIMITS AND rs NOT REANALYZED PUMP MOTOR 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
125 1 VESSEL PRES RISE (p11I 1 NEUTRON FLU)(
2 AVE SURFACE HEAT FLUX 2 RELIEF VALVE FLOW 3 CORE INLET FLOW 3 BYPASS VALVE FLOW 4 CORE INLET SUB 4 DIFFUSER FLOW 1 lI 5 DIFFUSER FLOW 2 ("I a
w 75 a:
u.
a z
UI u 25 a:
w
- a. ]
2 10 20 JO 40 50 TIME bccl 150 I LEVEL (lnch*ref*sep*skirtl I VOID REACTIVITY 2 VESSEL STEAMFLOW 2 DOPPLER REACTIVITY 3 TURBINE STEAMFLOW 3 SCRAM REACTIVITY 4 FEEDWATER FLOW 4 TOTALREACTIVITY
- 2-~......~~~~.......~~--'~~~.......~~---
10 :10 JO so 0 10 20 JO 40 50 TIME lsccl TIME (secl FIGURE 15.3-2 TRIP OF BOTH RECIRCULATION PUMP MOTORS 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
I NEUTAOtl LUX 2 RVE SURF 'E HEAT FlUX 150. 3 CORE !NL T FIJ!!L_
II CORE !NL T SUB 5
~ 50.
5
~
~ o.W--JL---.-J.-!----+----+----+---
w z
0 a.
- c 8
~ -l. l-+-1-1--ll--!----+----+---+---
- 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 NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT NIAGARA MOHAWK POWER CORPORATION SET REACTOR OPERATING LIMITS ANO IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE. NINE MILE POINT-UNIT 2 UPDATED SAFETY . ANALYSIS REPORT USAR REVISION B NOVEMBER 1995
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
~ 100.~~-J.l---~.l----.l----..I---.
<r a:
~ ~.t---->,cM-:+->.o----1-'l'--+----1---
~
"o.
~
ffi"' 0.
~
- x:
Cl u
- -1. t - - - - > , r r - \ - U - - - - - - + - - - - -
it LJ
- 20. 30. 20. 30. , IJO.
TIHf ISECI TIHE ISECI NINE HILE POINT 2 FAST l:LDS!JlE llF BClTH RECIRCULRT Uli Vil.YES FIGURE 15.3-4 FAST CLOSURE OF BOTH MAIN RECIRCULATION VALVES AT 11% PER SECOND*'
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. NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 .
UPDATED SAFETY *ANAtYSIS REPORT USAR REVI SJON 8 NOVEMBER 1995
I NEUTRON LUX l VESSEL P ES RISE !PSII 2 AVE SURF E HEAT FLUX 2 HEUEF V LVE fLDW 3 COOE INL T F OM 3 BrPASS VI LVE FL~
150.t---t---!+----t------r.i"ll~CORE !NL T SUB 125. Hi---+--t-----t----t:',IHDIFFUSEll l*LOH I IZl 5 S OIFFUSER FLOH 2 11.l G
ffi 100.~ri--+-'t---+----+----+---
~
I!!
ffi 00.1-+----..,,..,..+--___.,_-+----1----+----
ffi l!O.
§ o.~""--+-------.~--+--r---+---
1 8
- -1. l--~--l----!*"4--.1---1'1-+----+--
~
UJ a:
FIGURE 15.3-5 1 SEIZURE OF ONE RECIRCULATION PUMP NOTE: THESE RESULTS ARE FOR CYCLE I.THIS EVENT DOES NOT SET REACTOR OPERATING LIMITS ANO IS NOT REANALYZED NIAGARA MOHAWK POWER CORPORATION FOR POWER UPRATE OR FOR EACH RELOAD CYCLE. 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 a
4 8
- 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 ARE PRESENTED IN APPENDIX A. NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S
1.6 .
1.S g
r-
<{
er er \ BUNDLE (25-34>
\
w
- i:
0 1.05 1.4
_J
\
\::!
r-er u
- ?
- > 1.3 POWER 1.04
~\
~
~
- z er
~,~,
w
~
0 0..
1.03 0 UJ
- 1. 2 r-
<{
er
' ........... -......_BUNDLE (21-JBI u..
~
0 en z
Q 1.02 ;-
1.1 u
~'~NOLE 123-361
<{
er u..
1.0 1.01 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 FIGURE 15.4-2 VARIATION OF CORE POWER -AND MCPR WITH THE DISTANCE ROD (26-35) WITHDRAWN DURING CONTINUOUS
- ROD-WITHDRAWAL ERROR NOTE: THESE RESULTS ARE FOR CYCLE 1. CYCLE- SPECIFIC RESULTS NIAGARA MOHAWK POWER CORPORATION ARE PRESENTED IN APPENDIX A. NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S
19 18 17
~
w I-
<{
a:. 16 z
0 j::
<t a: ,,,,,,--
w 2
w (
I
<.:J I- 15 w
- z:
a:
<(
w I
~ BUNDLE 121-381 /
/
-J
- e
/
14
~
x
- E
- ---=--- ..c::::::../ - - - -
BUNDLE 139-241 13 12 ROD BLOCK LINE 11L....------..L.------...,,jL....--J...--.J..--------.1....------...i.------__.
0 2 4 6 8 10 12 DISTANCE CONTROL ROD WITHDRAWN lfeetl FIGURE 15.4-3 MLHGRVS DISTANCE ROD (26,35)
WITHDRAWN NOTE: THESE RESULTS ARE FOR NIAGARA MOHAWK POWER CORPORATION CYCLE 1. CYCLE- SPECIFIC RESULTS ARE PRESENTED IN APPENDIX A. NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S
RBM RESPONSE TO CONTROL ROD MOTION 130 CHANNELA+C 125
,,...,. ~ """' B 124,331 L+/-.____J 132,331 120 I 115
- E m
a:
1 10 105 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 5 6 8 9 10 II 12 C.R FT WITHDRAWN FIGURE 15.4-4
. RSM RESPONSE TO CONTROL ROD MOTION, CHANNEL A & C NIAGARA MOHAWK POWER CORPORATION NOTE: THESE RESULTS ARE FOR CYCLE 1.CYCLE-SPECIFIC RESULTS ARE PRESENTED IN APPENDIX A. NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995
ABM RESPONSE TO CONTROL ROD MOTION 130 CHANNEL B
- D 12&
"""' ~ '"*'"
124.331 l+/-___J 132,331 120 115 110 105 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 7 B 9 10 11 12 C.R . FT WITHDRAWN FIGURE 15.4-5 ABM RESPONSE TO CONTROL ROD MOTION,
. CHANNEL B & D NIAGARA MOHAWK POWER CORPORATION NOTE: THESE RESULTS ARE FOR CYCLE 1.CYCLE-SPECIFJC RESULTS ARE PRESENTED IN APPENDIX A. NINE Mf LE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S
4 150 1 NEUTRON FLUX 2 AVE SURFACE HEAT FLUX a 3 CORE INLET FLOW 1 VESSEL PRES RISE (psil Ul 4 CORE INLET SUB
!;{ 2 RELIEF VALVE FLOW 3 BYPASS VALVE FLOW
...a:a 60 4 DIFFUSER FLOW fl%1
...z 2 5 DIFFUSER FLOW 2 (%)
Ul u
a:
Ul CL OOL~~~1L0~~--12~0~~--J3~0~~---'40..._~~50 - 50iL~~~,~~~~w~~~~3~0~~~4~0~~~50 0 0 TIME lsecl TIME laec) 150 t LEVEL lonch*nif.. ep*sk1<1) 2 FCV 1 POSITION 1%1 3 PUMP SPEED I I'll.)
~
FEEDWATER FLOW
"'....z 3 w 2 0 0
- e0 CL u
~ I VOID REACTIVITY
<t w
a:
0 2 -2 0 10 20 JO 4-0 50 0 2 4 6 8 10 TIME lsecl T IME (secl FIGURE 15.4-6 ABNORMAL STARTUP OF IDLE RECIRCULATION LOOP PUMP NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT NIAGARA MOHAWK POWER CORPORATION SET REACTOR OPERATING LIMITS AND IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE. NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT NOVEMBER 1995
I VESSEL P~tS RISE IPSll 2 RELIEF V* LVE FLOW 3 B'l'i'ASS V. LVE FLIJH 2 oo.i----1----+---i~'!OlffU-'illi-fUMl l'l.l 5 DIFFUSER FLO~ 2 lf.l
[j c; 100.H+---1----1-----l----1---
l::!
a:
a:
~
ffi ij:! so .,,
.. 't-t--'~-+-"'<----1----i~---+----
UJ n.
-IOO.~..w..w.....~---:;;1=--___,IL---..1----:I.
- 40. 0. 10. 20. 30. 40 .
TIME CSECI l~.r-----+----l----1----1----
E
-1.1-----+--+-+--+----lf-----1---
-50 . .!-..L..1..1..LJ..J...W._'::-----l----....L...--_L--..:I.
Q m. ~-
TIME ISECl
~- *40. ll.
TitlE !SECl
- 6. 8.
FIGURE 15.4-7 FAST OPENING OF ONE MAIN RECIRCULATION LOOP VALVE AT 30% PER SECOND NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT NIAGARA MOHAWK POWER CORPORATION SET REACTOR OPERATING LIMITS ANO IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE. NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995
/ 200.1----l-----+----+-H{~~}r.~ ~~,t~JL~:o I VE'SSEL P1ES Al5E IPSIJ 2 P.Ellff vw_VE FLOW 5 DIFFUSER FLIJW 2 tzl G
I so.
-100. W...Ul...L.1.J-LI...1.,l----..,,J,.---...,,.,__ ___.,_ _..:.i,.
- o. 10. 20. 30. 40 .
TIME CSECI 5
150.~--+-----+-----t----+----
FIGURE 15.4-8 FAST OPENING OF BOTH MAIN RECIRCULATION LOOP VALVES AT 11% PER SECOND NOTE: THESE RESULTS ARE FOR CYCLE 1. THIS EVENT DOES NOT NIAGARA MOHAWK POWER CORPORATION SET REACTOR OPERATING LIMITS AND IS NOT REANALYZED FOR POWER UPRATE OR FOR EACH RELOAD CYCLE. 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 3 TURBINE ' RES RISE IPSI I 150. 125. 11 lil'CS FLD I?. Of FKl
'11 f[EOH UH S VESSEL 5 FAM FLOH c;_ c < g ~~~.~~. 1rn!2 FRAC 1
" " l'IU lXl
!XI
-~
o.U ffi 1
_'I
...fl!
1 lob. 1 "
u 1 "- 7S.
11
~
so. 25.
~ ll ll ll ll
~ ... l!'.l"J'!
, " ., 'I "
o.o. ' 10. 20. 30. llO,
- -25.
- 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; u; ll ~
- 75. c 80.
LLJ t-
~
, " , 'I
" ~
u.
- ?'" 0 I-z
- 25. ,_,
w 40.
a:
- ~
-25.
0.
. 10. 20. 30. 40.
... 0.
o.
I
- 25. so. 75. 100.
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 FOR POWER UPRATE OR FOR EACH RELOAD CYCLE. NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT
- USAR REVISION 8 NOVEMBER 1995 -
\.l 'w4CCfnAIU AUUl n llru,; c.t.,fAA$.AS(l-.
'""'"' l'fSTIM$
AJ OfllQtlO C'J"(1UT ID"t&.1.
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&CCIDllirll U 1D(JITIPlt&1U)frifO* IAJITY AC110-I ftULllfCfll HrN11&l TD AVOIDING IJ'NACCtn"ll.1 l\llfiflfANA&.Ylll fllllUL fl llACH 11Afll
~to u,_D***CV ftlCUtlll(MlflrlT IDCHJtflCATtOff oP IYltffrtll AND 11.ac"*
1.ltr11 T' UH~fl&I.. '0" At; MtlV l"'C l4Jft'i 4CTIOAft IUCt4 SlATll IDU1Tff lCaf10-.0f 1.. M*t¥1'Tf"'
ACTtOlrlS ~ IC M W\llT t i "lDUUttO 0 44 Af1TA 1C f(O 11.a( .. IYl11M I 1otfrilfll tC*ttQl60' _, , ,. *.,...,...
S'r1ftM "'*"Ofll*lliU COlfQtt lCJ!rfl tO ACCOrW"'t 1SM
- Ct!Q'lrfl tf:a< .. J*SftVI IDt ..Tlf H;AflO-. c**14. . EMAAl Cl)lrraOIT IQ!lro TO U.T tlJ'f llll:fDuJrtDAlritC.,. flllQU ttllfr..t .. TS I &CMSYIT(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 A\fAI\ Al lt,.l fV co-.110Uu*.T10'4S 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...-t 1*1t& t1 0-.
FIGURE 1SA-1 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 IEVENT CATEGORY l SINGLE EQUIPMENT MALFUNCTION SINGLE OPERATOR ERROR I IST PROTECTION LEVEL I EVENT A:
I : EVENT 8 I SINGLE OPERATOR OPERATIONAL 2NO PROTECTION ERROR REQUIREMENT LEVEL PROTECTION PROTECTION LEVEL 1 LEVEL 1 3RO PROTECTION PROTECTION PROTECTION SINGLE OPERA TOR LEVEL OPERATIONAL LEVEL 2
- 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 IT IS INCONSISTENT TO PLACE OPERATIONAL REQUIREMENT LEVEL I I REQUIREMENTS ARBITRARILY ON SOME ACTION I BI (SCRAM) IN ALL CASES OF ONE EVENT CATEGORY, IT IS INCONSISTENT TO PLACE OPERATIONAL EVENT A BECAUSE THAT ACTION (SCRAM) MAY REPRESENT EVENT REQUIREMENTS ON SEPARATED LEVELS OF DIFFERENT LEVELS OF PROTECTION FOR THE PROTECTION FOR ANY ONE EVENT VARIOUS CASES. 1ST 1ST PROTECTION PROTECTION PANEL A LEVEL LEVEL PANEL 8 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 1SA-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 AELA TIONSHI PS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
NUMBER OF EV ENT EVENT EVENT TITLE STATES IN WHICH STATES THIS PROTECTION SEQUENCE IS APPLICABLE DIFFERENT PLANT CONDITION DIFFERENT PLAN CONDITION SAFETY SAFETY SAFETY SYSTEM SYSTEM SYSTEM 0 R u S F INDICATES THAT SYSTEMS QAND R SHARE AS A PAIR THE REQUIREMENT TO MEET THE SINGLE FAILURE CRITERION PERSONNEL
..-°"'
SAFETY (MANUAL I ~ SAFETY SYSTEM ACTION SYSTEM s REQUIRED FOR ( P JW SYSTEM W *'-"'-----
S F I '\
~
\ S F)
~
SYSTEMS MUST ITSELF
, MEET THE SINGLE FAILURE SAFETY CRITERION SYSTEM T INDICATES THAT ONE OR MORE OF THE KEY PROCESS PARAMETERS MUST BE LIMITED TO SATISFY NUCLEAR S F SAFETY OPERATIONAL CRITERIA SAFETY SAFETY ACTION ACTION A A EACH CONNECTED PROTECTION SEQUENCE IS FOR JUST ONE SAFETY ACTION FIGURE 15A-4 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 AUXILIARY B THE SAFETY RELATED 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
AUXILIARY SYSTEM A STATE EVENTS STATE EVENTS STATE EVENTS A u,v,w STATES AND EVENTS A - A -
B v.w FOR WHICH THE AUX*
B - B Q,A c u.v.w.x _ . ILIARY/SAFETY SYSTEM -
c Y,W c -
D u.v.w.x RELATIONSHIP APPLIES D v.w.z D Q,R,S s F s F I
SAFETY SYSTEM (3
SM7 SYSTEM E
SAFETY SYSTEM 1T SAFETY SYSTEM s
I SAFETY SAFETY INDICATES THAT SYSTEM IS SYSTEM SYSTEM INCLUDED IN COMBINATION BUT DOES NOT REQUIRE ~
THE AUXILIARY.
FIGURE 1SA-6 FORMAT FOR COMMONALITY OF AUXILIARY DIAGRAMS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
- D*
........ , .. l Mflllf VAlVt IPC* C*n
'Wt'.~
\>f'fAAflQft
,re:,
!ft*" VALVI A ... 1 atlrftJi"-SaftlJli ,.,..,. JIOWf"
'f'*I VI ....... VAlVf Btlft'fl If M. ...... t"\JWlP Or..-~"""
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CONJAQL CORE RfACTIVIT't' CO,,.TftOL FIGURE 1SA-9 SAFETY ACTION SEQUENCES FOR NORMAL OPERATION IN STATE A NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
STATE II NORMALiiP£RATIOfl EVENTS 2 ANO 5 EVENTS EVENTS EVENTS EVENTS EVENTS EVENTS EVENT EVENT 7AN0!. JANOS 1ANO!> JANOS 2AND5 2AND5 l JAND6 POSITIONING OFF-GAS VENT MINIMUM RATE OF CONTROL ROD OF CONTROL NEW FUEL RADIATION Y£1<T R[ACTOR POWER(SAN) REACTOR CHllNGE FUEL SPACING
~UEL DRIVE SYSTEM RODS DURING STORAGE MO*HTORING RELEASE MAXIMUM VESSEL TEMPERATURE CORE FACILITIES S"fSTEM POWPI (APllM) LIMIT L L Al.TERATION LIOUIO NUCLEAR WATER TEMPERATURE.
IOCFR 20 CORE POWER CORE SPENT FUEL RAOWASTE SYSTEM WATER LEVEL.
IOCFR 50 LEVEL REACTIVITY STORAGE SYSTEM TEMPERATURE FUEL SPACING. AND LIMIT CONTROL COMROL FACILITIES CONTROL FUEL HANDLING
"'INIMUMWATEA 10 CFR "lO LEVEL TO AVOID OH*GAS\IENT !OCFR ~O REACT DR WATER CHEMl&TRY SYSTCM REACTOR FUEL EXCESS l,.IJi.Or TEMPERA l\JRE COO~T L'IT L L L NUCLEAR SOLID RADWASTE 10 CFR 11 Lllo'IT REACTOR VESSEL CONTRDLROD SVSTE"' ROD PA TTEJlll S"STEM APPLIED TO WATER LEVEL DRIVE SHIPPING CASfC WATER DUALITY R2":5, RWM. RGM
':ONTROL CONTllOL SYSTEM L. L REACJDA GUii.DiNG VEHTILATIOH MONITOR ACTIVITY
~ADlATION RELEASE THROUGH RDDWOflTH lolOlllTOAING VENTILATION SYSTEM CONTROL iYSTEll AA0t04CTIVE M"-TEffl.ll FIGURE 15A-10 R~LEASE CONl~OL 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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f(WfAATIJAl COIURCh 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.~
REACTOR PROTECTION SYSTEM S 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 ANALYSlS REPORT
( .,
MSIV P<825 psig CLOSURE (RUN MODE)
PLANNED MSIV OPERATION CLOSURE HIGH PRESSURE SCRAM SIGNAL LIFTS VALVE PRESSURE REACTOR WHEN 3MAIN PROTECTION TRANSFERRING RELIEF STEAM LINES HEAT TO SUP- SYSTEM SYSTEM CLOSED >15% PRESSION POOL S F S F INSERT INCIDENT CONTROL ROD DETECTION ST ART HPCS , RCIC, PRESSURE CONTROL DRIVE SYSTEM CIRCUITRY ON LOW WATER LEVEL RELIEF RODS S F S F SCRAM RCICS MAINTAIN WATER LEVEL HPCS s F' CORE COOLING FIGURE 15A-14 PROTECTION SEQUENCE FOR LOSS OF PLANT INSTRUMENT /SERVICE AIR SYSTEM r
NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 28 MAY 19.87
EVENT9 INADVERTENT START-UP HPCSPUMP STATES A, 8, c ANO D
)
STATES B. D STATES B, D STATES A,C FEEDWATER PRESSURE REGULATOR CONTROLLER PLANNED OPERATE FAILURE OPERATION OPERATE FAILURE TO THE OPEN MAXIMUM POS ITION DEMAND PLANNED SEE PLANNED SEE OPERATION EVENT NO. 23 OPERATION 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
(
EVENTlO STARTUP OF IDl.E RECIRCULATION PUMPS STATES A, B, C, D STATE D STATE D STATES A, B, & C POWER 5-10%
l6 va: ~
APRM ~ APRM w 1 HIGH 3l: HIGH '
0 0..
FLUX ffi FLUX s-v SIGNAL ~ SIGNAL a..
PLANNED PLANNED OPERATION OPERATION NEUTRON NEUTRON MONITORING MONITORING SYSTEM SYSTEM REACTOR SCRAM SIGNAL ON PROTECTION NEUTRON MONITORING SYSTEM SYSTEM TRIP S F CONTROL ROD tNSERT CONTROL RODS DRIVE SVSTEM 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, STATEC POWER OPERATION STATED (MODE SWITCH NOT IN RUN)
PLANNED OPERATION NEUTRON HIGH NEUTRON FLUX MONITORING IAPRMl SIGNAL TO SYSTEM RPS S F SCRAM SIGNAL REACTOR ON NEUTRON PROTECTION MONITORING SYSTEM SYSTEM TRIP S F CONTROL ROD DRIVE INSERT CONTROL RODS SYSTEM S F SCRAM 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
(V(HY fl AltlRCULAltON ll)()IJ FlDW CONTROL f'.Al\,U'll DfC-'EASINfi StATUC.AffOO ONU\'WO V.alVE f A$t CLOSU~t 0-' OOl(nwD VALV( FASf CLOSllR(
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- f AU.CtOA YfDU tSOLAUOH t*MH!ATUC>tA.*GIUl 1RHAPVtilP s.rawcz"1ATEA*UMPS u.urtlAl MAJUMW VAL VU AtOUIACD Al[U!.JVALVH fOfl CONTROLLED Of:PfUUURIZATfOM MAlliinAINWAtl;R l£Vfl IH REACTOR "tflSSr:L untrtnrocOAt FIGURE 15A-18 COOUNG PROTECTION SEQUENCE FOR RECIRCULATION LOOP FLOW CONTROL FAILURE-DECREASING NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
iYll!!_!1 RECIR~ LOOI' PUMPT .. I' Qt.IE OR IOTH STATES CANO D ONEPWPTRIP 1WO PUMP TRIP SACF STATE C TWO Of\IE PUMP TR IP l'UMP TRIP 111..ANfllEO OPERATION ONE PUMP TRIP AT LOW POWER PRESSURE HEAT TO RELIEF &UPPRE$$10f<
SYSTEM POOL s
PRIMARY CONTAINMENT FIE ACTOR SCRAM SIGNAL AND REACTOR l'AOTECTION TURlllf\IE TR" VESSEL ISOLATION SYSTEM CONTROL SYSTEM l'AESSURE RELIEF S F S F M,t.lf.I STEAM INSERT ESF COf.ITAOLAOO 5TAFIT HPCS, RCIC, Llf.IE ISOLATION DRIVE SYSTEM CONTROL DETI:CTION ON LOW "'ATER LEVEL VALVES RODS CIRCUITRY S F $ F REACTOR SCRAM MAINTAIN 11£5SEL WATER LEVEL ISOLATION 5 F INITIAL CORE COOLING 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
{ EVENT 14 ISOLATION OF ALL MAIN STEAM LINES STATES C, D STATE C p < SETPOIN*T----C l'LANNED STATE 0 OPERATION p > SETPOINT REACTOR SCRAM SIGNAL WHEN PRESSURE HEAT TO SUP*
PROTECTION MAIN STEAM RELIEF PRESSION POOL SYSTEM LINES CLOSED>15% SYSTEM S F PRESSURE RELIEF CONTROi.ROD INSERT CONTROL DRIVE SYSTEM ROOS
&F ESF START HPCS, RCIC, DETECTION ON LOW WATER LEVEL CIRCUITRY RCICS MAINTAIN WATER LEVEL HPCS SCRAM s f INITIAL CORE COOLING FIGURE 1SA-20 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
EVENT1*
( ISOLATION OF ONE MAIN STEAM LINE STATES C, AND D LESS THAN GREATER THAN 90%POWER eo.POWER CONTINUE PLANNED NEUTRON OPERATION HIGH NEUTRON MONITORING FLUX SIGNAL SYSTEM S F SCRAM SIGNAL REACTOR ON NEUTRON PROTECTION MONITORING SYSTEM SYSTEM S F INSERT CONTROL ROD CONTROL RODS OAIVE SYSTEM S F SCRAM FIGURE 1 SA-21 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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( EVENT16 CONTROL ROD WITHDRAWAL ERROR START*UP ANO REFUELING OPERATION STATES A ANO B STATE A STATE B
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a; SCRAM SIGNAL REACTOR REACTOR ON PROTECT JON " REFUEL" PROTECTION NEUTRON SYSTEM SYSTEM MONITOR ING SYSTEM s F s F INSERT CONTROL ROD CONTROL ROD CONTROL DRIVE SYSTEM DRIVE SYSTEM RODS S F S F ROD BLOCK SC RAM FIGURE 1SA-23 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
STATE 0 llffERMEOIATE RANGE HONITCJ'l STATE D POWER RAMJE MCNITOR tEUTllON HIGH POWER BELO'li 301.
MONITORING IEUTRON SYSTEM R..UX SIGNAL S F NUCLEAR
~51.fiEMENT Ra> SEOlJ81CE ROO BLOO<
ANALYSIS ANO CCl.ITROl MONITOR IEACTOR CONffiOL SYSTEM PROTECTION ROD WORTH SYSTEM MINIHIZEJI UNAUTHORIZED ROD WlllUIAWAL cnlTROL ROO INSERT DRlV£ SYSTEM ClllilTR11.
ROOS STCf' RID HQT[ON SCRAH 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_
EVHH 18
"""'RHiiS tOSS Of. SHUT'DOW'ti COOLING STATES 4JJ.C AND 0 ISOLATION OF SHUTDOWN C:OOllNCi SUCTION LINE !---------------------------...
STATESC. D p>IJ5p,..
ALL OTHER ~INCLE FAILURES SlAfE.SA , 11 STATESA .11.C 1rc1 lPCI HPCS p p s r s r MA*frf sri~u.*11-.f ISULAftON VAl ve*
PLANNED OPERATION REESTABLISH RHR SHUTDOWN MANUAl 5 F RELIH \IALllE AUS AEOUIRlO COOLING MOOE WITH ALTERNATE VAL VU t>PEAATION EQUIPNIENT RE AC JOO
\IESSEl ISOLATtON AHA AHR HEAT EXCHANGER SU ...... ESSION RHRPUMP l'OOL COOL ING SERVICE WATER PUMP l>MOUE S F
£XTE,.OEO CORE COOLING FIGURE 15A-25 PROTECTION SEQUENCES FOR RHRS - 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 1SA-26 RHRS - SHUTDOWN COOLING FAILURE -
INCREASED COOLING
. NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
m.!11!.
LOU Of*\.\ HUJW&flM St*fUCAl'IDD
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.. , 11' ....
..,. lttlTIATf
.....1.. n1*11 HEAT TO rL&..... o L.ltr.11 tlO\.ATfOlil IUPl'MSStON O..*.t.flOlll
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.... Jf .. UVlL ..__ _ __ ,
Ullil'U. IT&llT...:llteCIC CDOllOG 0- LDIJWATlft l£Vll.
lfriQUtf COlflAOl 111.-HEAJPDI~
11tH111'\.fW SllMCI WAffR MllDi illlP"NafO!ffVO\ ftW'ff'ANi'I Ullff ITUT DIMUIUMZA1'10llf JHllffl"&lYI c.t,..Tl(Jlil
~fCIUllMOYM\ltlf'Ol COll'fllGLLIO Dl ...........IATIDll tllo\4'IT&nn1&HR Ll'dL lllllftt4'CTOl'VUIU Utl""WD FIGURE 15A-27 PROTECTION SEQUENCES FOR LOSS OF FEEDWATER FLOW NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
EVENT21 t...OSS OFA FEEDWATER HEATER STATED RECIRCULATION FLOW IN RECIRCULATION FLOW IN MANUAL FLUX CONTROL MODE PLANNED OPERATION NEUTRON HIGH FLUX MONITORING SCRAM SIGNAL SYSTEM tTHERMAL POWER MONITOR)
S F SCRAM SIGNAL REACTOR ON NEUTRON PROTECTION MONITORING SYSTEM SYSTEM S F CONTROL ROD DRIVE INSERT CONTROL RODS SYSTEM S F SCRAM FIGURE 15A-28 PROTECTION SEQUENCE FOR LOSS OF A FEEDWATER HEATER NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
EVENT 22 FEEOWATER CONTROLLER FAILURE
- MA><IMUM DEMAND STATES A. e.c. ANO D STATES A AND B STATED STATES CANO D
c OTHER OPERATING STATE 0 MOO ES '"RUN .. MOOE PRIMARY CON*
ESF TAINMENT AND DETECTION I REACTOR VESSEL CIRCUITRY ISOLATION CON
- TllOLSYSTEM HIGH FLUX NEUTRON SCRAM S F MONITORING SIGNAL SYSTEM llRMI PRESSURE MAIN STEAM l-IPCS RCICS RELIEF LINE ISOLATION SYSTEM VALVE S F S F SCRAM SIGNAL FROM TURBINE TRIP MAIN REACTOR IRUN MODEi OR TURBINE PROTECTION NEUTRON TRIP SYSTEM MONITORING PRESSURE SYSTEM RELIEF RECIRCULATION INSERT CONTROL ROD PUMP CONTROL DRIVE SYSTEM TRIP IRPTI ROOS S F PLANNED OPERATION REACTIVITY CONTROL FIGURE 1 SA-29 PROTECTION SEQUENCES FOR FEEOWATEA CONTROLLER FAILURE - MAXIMUM DEMAND NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
EVENT 23 PRESSURE REGULATOR FAILURE *OPEN STATES C, ANO 0 STATE 0 ONLY INITIATE SCRAM SIGNAL FROM ISOLATION ON*
_ _ __.__ _ _ 1. DEPRESSURI*
- - - - - - - *MAIN STEAM LINE ISOLATION START HPCS, PRIMARY Z4TION T0850 pug PRESSURE REACTOR
- TURBINE TRIP ESF CONTAINMENT IRUN MOOE RELIEF RCICON PROTECTION (RUN MODE: DETECTION AND REACTOR POWER 0-100%1 SYSTEM LOW WATER SYSTEM POWER 30*50%) CIRCUITRY VESSEL ISOLATION LEVEL
..__ _ _ _ __ .
- LOW WATER LEVEL ...__ _,.._ __ CONTROL SYSTEM S F s f (OTHER THAN S F RUN MODE:
POWER0*10%
CONTROL MAINTAIN MAIN STEAM PRESSURE ROD DRIVE HPCS CORE RCICS LINE ISOLATION RELIEF SYSTEM COOLING VALVES s F INSERT s F CONTROL RODS s F INITIAL REACTOR SCRAM CORE VESSEL COOLING ISOLATION PLANNED OPERATION RE*ESTABLISH COOLING FIGURE 1 SA-30 VIA MAIN CONDENSER PROTECTION SEQUENCES FOR PRESSURE REGULATOR FAILURE - OPEN NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 .
FINAL SAFETY ANALYSIS REPORT
EVENTl*
FIRST PRESSURE REGULATOR FAllURf - CLOSED
$TATlSC.&NDD
$ECOl'<D l'llESSU~E REGULA TD" OPERATE FAil URE HIGH E5F START HPCS, ACIC FlUX oETecnoN ON LOW WATER PRIMARY CIRCUITRY LEI/EL COl'ITAl11jl~£11jT PRESSURE AND REACTOR RELIEF VESSEL ISOLATION SYSTEM CONTROL SYSTEM s F s F MAINTAIN MAIN STEAM LINE CORE PRESSURE ISOLATION VALVES COOLING RELIEF s
s ,
PLANNED REACTOR VESSEL oPlllATIDN ISOLATION SCRAM RHA- I RHRHEAT SUPPllESSIOH EXCHANGER POOL 1 RHRPUMP
~COOLING MODE SERVICE WATER PUMPS 511,,RHSION l'OOl TEMPERATURE LIMIT START OEPRHSURIZATION nEOUIRED VALY!B
... os
- S F FOR CONTRDUED DEPREGBUAIZATION MAINTAIN WATER tN RE,.CTCIR VESSEL HPCS p
[llTENDEO CORE COOLING FIGURE 1SA-31 PROTECTION SEQUENCE FOR PRESSURE REGULATOR FAILURE- CLOSED NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
ill.!ilX!
MA IN TURBINE TRIP WITH BYPASS STATED POWER
> 30'x.
BYPASS ESF SYSTEM DETECTION PCRVICB OPERA HS Cl!IClllTRY S F RCICS s I' SCRAM SIGNALS.
MAIN REACTOR TURBINE PROTECTION I . TUR81Nf; TF!IP SYSTEM SToP VALVE CLOSURE s f S F RECIF!CULA TION CONTROL l'RESSURE MAIN STEAM INSERT PUMP ROOORIVE RELIEF LINE CONTROL ROOS TRIP IRPTI SYSTEM SYSTEM ISOLATION s r PLANNED OPERATION RESUME l'OWfR INITIAL PRIMARY Ol'ERATIO .. OR REACTIVITY PRESSURE CORE CONTAINMENT
... CHIEl/f SHUTDOWN CONTROL RELIEF COOLING ISOLATION FIGURE 15A.-32 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
'"ilsidl'
....,t.llM t.utltCOllDf'-$1" 11.t.TUC..&IC>O Elli' llll*td*IA or.ncnOH *""*"" ""Cl *ctC
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ACC1JICUl.&f1Dfrl ffCIC& ..... UAINST£AM LINE ISOLA TIDN I
- NIUTftOJf MOffl'TOltl'-0
$'ri1'UI PRIMARY CONTl.INMENT lSOlATION t RHllt H!A f !ICHANOlA SCRAM SIGNAL OH *""""'""
Sl!RYICt WATtR OUM'9 "IAC1GI' NEUTRON M09dT°"
MOttCftO'I llltEM OA TVflSIME IYlflr.t ITOf' VAL'fl PRUSUAE 9JlltfllllU10h '004.
TtWl*,lfU'lllf l.H11Hf Jt**n Dl"'IAiU-.te.ATIOf'I WIC)UUIJO\IAl'-fl
- DS 'OlltOfrf'*OulO D1**IHto1fl11*t10' FIGURE 1SA.-33 PROTECTION SEQUENCES FOR LOSS OF MAIN CONDENSER VACUUM NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
EVENT77 GENERAiiift"TRIP' WITH BYPASS STATED POWEii
>~
E6F BYPASS DETECTION PCRVICS SYSTEM CIRCUITRY Ol'ERATES 5 F MAIN SCRAM SIGNALS' REACTOR l'RESSURE TURBINE PROTECTION t . TURBINE RELIEF MAIN STEAM TRIP CONTROL VALVE LINE ISOLATION SYSTEM 8VSTE!lol IGENEAATORt FAST CLOSURE S F S F 5 F RECIRCULATION CONTROL l"ISERT P\JMf' RODDRlllE CONTROL ROOS TRIP' CAP'TI SYSTEM s f PLANNED Of'EAATION RESU"'E POWER INITIAL PRIMARY REACTIVITY PRESSURE CONTAINMENT OPE AA TION OR CORE CONTROL COOLING RELIEF ISOLATION ACHIEVE SHUTDOWN FIGURE 15A.-34 PROTECTION SEQUENCES FOR MAIN GENERATOR TRIP WITH BYPASS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
1.. fM,Tf
.,.,_,,u
\CM .. w U'"*stUM Uttt' l'SOlAt~
Sllt.Tr.JC. D., >IJt . . .
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..,.....,IWPff'()lll
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IX"'-flk.fllt1/Altt..,
UUtlOf;O
<ll'll FIGURE 15A-35 PROTECTION SEQUENCE FOR LOSS OF NORMAL AC POWER - AUXILIARY TRANSFORMER FAILURE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
EVDrf"21 LOsi'iifira'RMAL AC PDW!ff GfUD ccaoi:cc:TJOH LOU STAT!.S A. D.CAtrilDO Jf,-UI C. D HEA.t-TO at.tt'Pft~Off POO<
""""'lo9'Q-CtC D£1tCm>H D'lllO-*t.ttllUWI CIRCUURl 1 llHR HU f UOtANGl!.R I RHA PUMP SIJIYICt: *ATIJI PUllll'IJ DUl "lO LOSll OF MA.Dt~TfAM C4tdJfH1~ liN( iSOU,TfON
¥1.CUUM
_...., ..L
... Lllf "*tYI *GU'lllt.D\>~"'SfOl'I tJ9'111**~
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
.f.l!filil.1!!
GENERA TOR TRI?
WITH BYPASS FAILURE ST ATE 0 POWER POWER
<Jeno .. Jo,.
ESF DETECTION PCllVICS CIRC UITRY s F SCRAM SIGNALS I . HIGH PRESSURE
- ! HIGM FLUX S F REACTOR MAIN REACTOR PROTECIION TURBINE PROTECllON SCRAM SIGNAl.S:
SYSTEM TRIP SYSTEM 1. TURBINE CONTROL VALVE FA5T CLOSURE PRESSURE.
S F S F RELIEF MAIH STEAM SYSTEM LINE 180LA noN CONTROL RE CIRCULATION CONTROL INSERT 1'100 ORIVE PUMP ROD URIVE CONTROL ROOS 5 I F SVSTEM TRIP i RPTI SYSTEM S F s
- S F s
INITIAL PRIMARY REf,CTIVITY PRESSURE SCRAM CORE ' CONTAINMENT CONTROL RE L IEF COOLING ISOLATION FIGURE 1SA-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 ESf DETECTION PCRVICS CIRCUITRY s ,. * ,,
HPCS RCICS
$ F MAIN REACTOR SCRAM SIGNAL:
TURBINE PROTECTION TURBINE STOP TRIP SYSTEM VALVE CLOSURE PRESSURE s F s F RELIEF MAIN STEAM LINE ISOLATION SYSTEM RECIRCULATION CONTROL PUMP ROD DRIVE INSERT S F S F TRIP IRPTI SYSTEM CONTROL ROOS s F s F s F INITIAL PRIMARY REACTIVITY PRESSURE CORE CONTAINMENT CONTROL RELIEF COOLING ISOLATION FIGURE 1SA-38 PROTECTION SEQUENCES MAIN TURBINE TRIP - WITH BYPASS FAILURE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
(
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
.!Y1!UA RECIRCULATION looP P\Jloll' SEIZURE STATE DONlV ESF SENSES HIGH ESF SENS£$ 'RESSUR2 DETECTION REACTOR YESSlL DETECTION l0WWAT£R RELIEF CIRCUITRY WATER LEVEL CIRCUITRY LEVEL SYSTEM s F I , PRESSURE RELIEF 5 F REACT Of' stAAMSIClNAL
'ROTE CTI ON FROM PCRVICS SVSTEM TURBINE TRIP MAINTAIN WAT!A LEVEL I I S F CONTROL INHl'IT MAIN STEAM RODDl!IVI CONTROL IYJTIM LINE 180LATl ON RODS
', S F AHR PRIMARY SUPPRESSION CONTAINMENT POOL ISOLATION COOLING MODE SUPPRESSION POOL Tl!MPl!RATURE START DEPRESSURIZll TION ADS EXTENDED COflE COOLING FIGURE 15A-40 PROTECTION SEQUENCE FOR RECIRCULATION LOOP PUMP SEIZURE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 1
UPDATED SAFETY ANALYSIS REPORT USAR REVISION 4 OCTOBER 1~2
~
RECIRCULATION LOOI' PUMP SHAFT IREAK STATEOONLV ESF SENSES HIGH ESF SEN5e5 PRESSURE DETECTION REACTOll YHSiL DETECTION LOWW ...TER RELIEF CIRCUlmV WATER LEVEL CIRCUITRY LEVEL SVSTEM s ,
PRESSURE S F RELIEF S F.
REACT Oii SCRAM SI G"'AL PROTECTION FROM PCRVICS SYSTEM 'TURBINE TRIP MAINTAIN CORE s , COOLING 5 F CONTROL INSERT MAIN STEAM ROD DRIVE CONTROL LINE ISOUTION SYS'TEM RODS S F AHR PRIMARY SUPPRESSION CONTAINMENT SCA AM POOL ISOLATION COOLING MODI!
SUPPRESSION POOL TEMPERATURE START llEPRESSURIZATION ADI Ell'TENDED COllE COOLING FIGURE 15A -41 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
a HIGH "411t SlEAll' S1ARI HPa ESf
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MONllOA11tc; OETllCllOH llUVCllY ltl>OMtJt\1111~
FLU* MONrlORING LOW WAl flt flHIE, S'<UI ... ClllCUITRV ... .. f1(0 Ul1NTAL C:OO.TROl 51GNAl SYSTEM UllU l'flTfU fl'Alll\IEI SYS TE" S F S F SCRA" S F s f SIC-94.-L l'lllMARY
°"
91(.ACTOf1 CONTAINMENT COOtnie>t.
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"ftO!!C.ltO~ AHO AEACTOR M.-CflVl'IY l'YSffM MONlTOIUNG YliSSEl. lliOLATION llCSllHtOH DI lt'tftOOflOl .. f AL svsrer.1 CONl AOL SYSTEM C°"'fROL MAtNTAIN s f s r CORt COOLl"'<l INSERT MAIW 5TEAM COt41AOl.ftDD PRll.tAR'i' 0AtV£ SYSlEM CQOjT'flOl UNI< HEAT TO CONTAIHMEH1 ROD$
ISOLATION llUJ>J>RES&ION CPASSlllE)
POOL SF s r s r PRIMARY SCf'"'M ESTABLISH 1 AHR HEAT EXCHANGER I RHRPUMP SERVICE WATEl PUMPS p
SUPPRESSION POOL TEllPERATUR£ LIUIT ST ART OEPRESSURIZATION MANUAL 5RV REDU:REO V~VES FOR Pall\11014 CONTROLLED PR£SSuRIZATION M'llNT'llNWATER lfVCL IN n£1'1:101t VUSEL _ _ _..
p FIGURE 15A-42 t<OTio*
a MAIN STEAAI LU~E RADIATION MONITORINC TRIPS ARE R£MOVEO. tXffl*DEU PROTECTION SEQUENCES COftf CUOLIHQ FOR CONTROL ROD DROP ACCIDENT NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N. Y.
UPDATED SAFETY ANALYSIS REPORT USAR REVISION 15 OCTOBER 2002_
(
EVENT41 FUEL HANDLING ACCIDENT STATES A . 8 , C, ANO 0 REACTOR BUILDING MAIN CONTROL VENTILATION ROOM HEATING RADIATION RADIATION RADIATION VENTILATING ANO LEVEL MONITOR TRIP MONITOIUNG AIR CONDITIONING INDICATION SYSTEMS SYSTEM S F S F INITIATE MAIN CONTROL REACTOR BUILDING BUILDING ROOM ENVIRON*
ISOLATION VENT MENTAL CONTROL SYSTEM ISOLATION CONTROL S F STANDBY GAS TREATMENT SYSTEM S F REACTOR BUILDING IPASSIVEI FIGURE 15A-43 PROTECTION SEQUENCES FOR FUEL HANDLING ACCIDENT NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
1( . . . . . . -
- 'uJtt:L
~
e::.1**-.11'1
~.
.. ..'°"
--*~**
- I I
-U..l*:::.110
_..........,~
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
f\llfrfT *1. -.. 4S LOCA tttO\JHIO(
COtilTA ..... llilf SIAftS.C AAOD
.. , ** ,fl 110'1' lf~1UC.O
"""SHUTDOWN C'OOUND. MlAIC
- ,,.,(Ull"f At11tr ttf.41'TO IU,.,.Hltoft w*s1-.1c
... 1tH~S
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MltlJI #I A' 111 lOCA " l'f 8RfAC$.~SIOE"lO fttarUM\.,fto*V"'O'Sl(ftl '1111*wuu:10tu.crll A\f*r1t<OltM'.JwN COOt WAIHSU .... l.._{
ffif(,
- ~'""*"
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'* rtru111,N*1.1111ro~ St&IU
! , llfU tfWfW*lllAf Df"'ISSUllUH;flOf'f
- 1. ?*t.' I fl_.rt*a1u1111
- ll("'l"ll)lCA11~
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- nw*HA 'H"""'*r.a.t.1*L*'"'
OOl"'ffl\ lf\l'f'l a, VIJ.UAt l lirr~JrtlOfrf RfOUtRfO VAL \l'(S
" " ..... , , , *~" *llQN1 r Oft (Olf1ROtlfD Df..,,lSSln'fl/AlfO"il FIGURE 1 SA-45 PROTECTION SEQUENCES FOR LIQUID, STEAM, LARGE, SMALL PIPING BREAKS OUTSIDE CONTAINMENT NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
EVENT48 OFFGAS SYSTEM LEAK OR FAILURE STATES A, B, C, D
)
STATES A, B STATES C, D MANUAL OPERATOR MAIN CONDENSER ACTION LOW VACUUM OFF-GAS SYSTEM 1501.ATION PLANNED OPERATION 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
EVENT41 AUGMENTED OFF-OAS TREATMENT SYSTEM FAILURE STATES A, B, C, AND D STATES A,B STATESC.D SEE OTHER PLANNED LOSS OF OPERATION MANUAL MAIN CONDENSER OPERATION CONDENSER VACUUM ACTION HIGH PRESSURE EVENT2B ACTIONS MAIN TURBINE TRIP
~ F REACTOR PROTECTION SYSTEM S F CONTAOL ROD DRIVE SYSTEM OFF-OAS SYSTEM SCRAM ISOLATION FIGURE 15A-47 PROTECTION SEQUENCE FOR AUGMENTED OFF-GAS TREATMENT SYSTEM FAILURE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
EVENT 48 LIQUID RADWASTE SYSTEM l LEAK OR FAILURE f STATES A , B. C. D ~
GAS LEAK WATER LEAK HIGH RADIATION HIGHWATER PROCESS VENl'I
- FLOOR DRAIN LATION RADIATION MONITORING MONITORING SYSTEM SUBSYSTEM VENTILATION SUMP SYSTEM PUMP CONTROL SYSTEM ISOLATE PRIMARY BUILDING OR CONTAINMENT AREA LIQUID EFFLUENT FIGURE 1SA-48 PROTECTION SEQUENCE FOR LIQUID RADWASTE SYSTEM LEAK OR FAILURE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT
EVENT49 LIQUID RAOWASTE SYSTEM )
STORAGE TANK FAILURE STATES A, B. C, D ~
GAS LEAK WATER LEAK HIGH RADIATION HIGHWATER PROCESS VENTI*
FLOOR DRAIN LATION RADIATION MONITORING MONITORING SVSTEM SUBSYSTEM VENTILATION SUMP SYSTEM PUMP CONTROL SYSTEM ISOLATE CONTAIN BUILDING OR LIQUID AREA EFFLUENT FIGURE 1 SA-49 PROTECTION SEQUENCE FOR LIQUID RADWASTE SYSTEM STORAGE TANK FAILURE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
I l
REACTOR BUILDING OPERATOR VENTILATION SERVICE RADIATION MANUAL RADIATION WATER MONITOR TRIP INITIATION MONITORING SYSTEM SYSTEMS INITIATE REACTOR BUILD* rXTERNAL INTERNAL BUI LOI NG ING ISOLATION COOLING COOLING VENT CONTROL SYSTEMS SPRAY CONNECTION ISOLATION S F STANDBY GAS TREATMENT SYSTEM S F REACTOR BUILDING CPASSIVEI ESTABLISH SECONDARY CONTAINMENT RESTORE TEMPORARY CASI< CONTAINER COOLING FIGURE 1SA-50 PROTECTION SEQUENCE FOR SHIPPING CASK DROP NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
EVENT 51 REACTOR SHUTODWN FROM ANTICIPA TEO TRANSIENT WITI!DUT SCRAM STATES 11. C. 0 STATES B, D STATESC,D REACTOR ISOLATED FROM MAIN CONDENSER ESF STi\RTHPCS, PRESSURE REACTDR HEAT TO RCICSVSTEM PRDlECTIDN llPT ARI DETECTION SUPPRESSION RELIEF CIRCUITRY ON LOW WATER SYSTEM PDDL SYSTEM p LEVEL STANDBY LIQUID COHTRDL PRESSURE SYSTEM RELIEF C AD MAINTAIN ACIC5 WATER HPCS LEVEL CORE RE.ACTIVITY COKTRDL CORE REACTIVITY CONTRDL RHR SUPPRESSION REMOVE DECAY POOL COOLING HEAT FROM AHR SHUTDDWN MODE SUPPRESSION COOUNGMODE POOL PLANNED OPERA TIDNS CDNTIKUE SHUTDOWN COOLING CORE COOLING FIGURE 1SA-51 PROTECTION SEQUENCE FOR REACTOR SHUTDOWN - FROM ANTICIPATED TRANSIENT WITHOUT SCRAM NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT
EVENT st REACTOR SHUTDOWN FROM ANTICIPATED TRA"SIElfTwmtOUT SCRAM FROM O\ITSIOE MAIH CONTROL ROOll STATESA.B C D.
I I STATE A. STATES 8 , D llEACTOA l\IOT ISOLATED FROM MAIN COl\IOENSER A I REACTOR ISOLATED FF10M MAIN CONDENSER STATES C. 0 PLANNEll OPE RATIONS CONTINUE SHUTDOWN COOLING I STATESC . D I STATES B, c. D PLANNED OPEF1A TIOl\I CONTROL COOLOOWN I USING l\IORMAL SCRAM BY EOUtPMENT ESF STARTHPCS REACTOR OE *ENERGl?ING HEAT TO PRESSURE DETECTION SYSTEM 0111 PROTECTION SYSTEM
-SYSTEM CIRCU1mv r-- LOWWATER SUPPAE&SION - RELIEF SYSTEM MANUALLY POOL p LE\IEL I 5 F I I CONTROLllOO DRIVE SYSTEM RCICS I
- MAINTAIN
\IESSEl WATER LEVEL
- HP!;S I
PRESSURE RELIEF*
I SHUTDOWN RE RHR SUPPRESSION REa.t:OVE CECA Y ACTOll FR0"1 PODL ltEAT FROM OUTSIDE CON
- COOUNGMDDE -SUP!'AESSION TROl.AOOM p POOl I
I I
AHA SHUTIJDWN COOUNGNODE I
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
fVlf>fT.:I 911..C'IOR S>flllll(MN WITMOU'f ~T1'0l -
STAT£S9.-D SfUE$ ** O StATES8.D REACT°" HOT ISOl.AfEO RfACTOfl ISOLATED FROM FROM lolAIN CONOENSEA IWUN CONDENSER HEAT TO REACTOR SUPPRESSION PRESSURE
_ _ _.,sr_A_,rE;;s_._,a.,
. o_ _ _ _,. POOL l'ROf ECTION RELIEF SYSTEM ) 13S""' (!JS- SYSTEM p l'l.APNEO OPEftit.TION.
CONTROL COOL~
USING NORMAL ESF ST AR1 ..CS. ACIC s r
'$YSlE.U Ole L -
fQUfl"MENT DETECTION W... fER LEVEL STANDBY ClllCUITRY llQlUD COlllTR01..
.. SYSTEM RCICS WATEft lll'CS t£VEL CORE REACTIVITY CONTROL AHR SUPPRESSION REMOVE DECAY HEAT FROM POOL SUl'f'flESSION COOLING UOOE POOl.
p 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
CORE I
We = Total Core Flow WA = Active Loop Flow W, = Inactive Loop Flow
) 1----------------~---------------------------------------1 1N iagara Mohawk Illustration of Single Recirculation Loop Figure
'Power Corp. Operation Flows 158.2-1 USAR Revision 8 November 1995
1230r-----------------------------------~-----
1220
-l* 1210 Q) 1200 With Bypass Failure i
- _"' 11 "e
& 1180 l 1170 1160 70 80 90 100 110 lnitlal Power Levsl (% NBFU
- Nia.Gara Mohawk Peak Dome Pressure vs. lnltild Powsr level, LRBPF at EOC Figure Power Corpora* (TYP.tCAL) 151.3-1 USAR REVISION B NOVEMBER 199S
l:IO.D 1!>0.0 1(110 0
~ 100.0
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!IO.O o.o O. OQ,D 10.0 20.0 o.o ID.0 20 .0 TlllE (S£CCWS) TllE (SECCHlS) 1 EVEL( INCH-REr-SEP-SKRT) 2 SSEl STEAMFLOll J TlJlB If'£ STEAMrLOll 1!!0. 0 t--------....::4:_µ..!EE~Oll!!:!A~lEo!)..R.!.-'fl~0!...11- - - - - l I **f--="""'o*.l-~~~~~ftb(_----l
-1.ot--------+--41c------I 0 Oo~.0:--------~10.-0~~----i!i!----__J:Hl.O - 1
- 0 0~.0:--------~,o.-=-o_ _11..._ _ _ _ --120.0 TI !IE (SErnllS) 111£ (5£CQ'IOS)
FIGURE 15 B.3*2 FEEDWATER CONTROLLER FAILURE
- MAXIMUM DEMAND, 82% POWER, 60% FLOW NOTE: CYCLE- SPECIFIC INFORMATION NIAGARA MOHAWK POWER CORPORATION IS PRESENTED lN APPENDIX A. NINE MILE POINT* UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION B NOVEMBER 19%
1~.01--+-1----1------1---------1
~"' 100.01-.J--+----ll-------11-------i m .o l - - - - - + - - - - - - - 1 1 - - - - - - - i l5 l
- 2. 0 4. 0 .o mr (S£COM>S) TI IE (stC<HlS) 1 LEVEL( I 2 VESSEl S J TURBll'<E 200.0 i - - - - - - - - . . . . : . . 4.:....:FE=EO=VA""'T=E;...:...:.;=----___,
- .a 4.0 1.0 -2.C\i.o 2.a 4.0 1.0 TI ME (SECOl()S) 111£ (SEC!HlS)
FIGURE 15 B.3-3 GENERATOR LOAD REJECTION WITH BYPASS FAILURE, 82% POWER, 60% FLOW NIAGARA MOHAWK POWER CORPORATION NOTE: CYCLE- SPECIFIC INFORMATION NINE MILE POINT* UNIT 2 IS PRESENTED IN APPENDIX A.
UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1'3%
1sa.or--t-t---+------l-----~
a
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100.0 m .o l3 l :!Q,D 1 1ME (S!COMJS) 1 llE. (SECCHlS)
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- 2 *1\i~
11WE (SECCHJS) 111.£ (SEC(Jl!)S)
RGURE 15 B.3-4 GENERATOR LOAD REJECTION WITH BYPASS FAILURE, 82% POWER, 60% FLOW, EOC-RPTOOS NIAGARA MOHAWK POWER CORPORATION NOTE: CYCLE- SPECIFIC INFORMATION IS PRESENTED IN APPENDIX A. 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=-----1 100.01-----------+---l------I sIii 100.0 l
~
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~ .o o.o O.Og , Q 10,0 20. 0 o.o 10.0 20.0 TI W[ (SECOlflS) 111£ (X:CCJlOS) 1 EVEL( INCH-REF -SEP- Sl<RT) I VOID REA Vl1Y 2 SSEl STEAMFLOll 2 ;PLER CT IVITY J URBll'l: STEMIFLDll J CRAM RE C IVllY 1 ~. 0 1----------4-+"'EE=O=llA'"'"'TE=R~F=LO=ll-----i 4 OTAL RE C IVllY 1.0 I~ v 1.
u
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~ -1 0 o.oo.o 10.0 :!O.O 10. 0 20.0 1111£ (SECONJS) T11 (SEC~OS}
FIGURE 15 B.3*5 FEEDWATER CONTROLLER FAILURE
- MAXIMUM DEMAND, 82% POWER, 60% FLOW, EOC-RPTOOS NOTE: CYCLE- SPECIFIC INFORMATION IS PRESENTED tN APPENDIX A. NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT
- UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 1995
llO.O 1!>0 .0 100 0
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RGURE 15 B.3-6 FEEDWATER CONTROLLER FAILURE
- MAXIMUM DEMAND, 82°/o POWER, 60% Fl.OW, BPOOS NOTE: CYCLE- SPECIFIC INFORMATION NIAGARA MOHAWK POWER CORPORATION IS PRESENTED IN APPENDIX A.
NINE MILE POINT* UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION B NOVEMBER 19%
I I I I l I I I 1 I I l I I I I
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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.
Cycle-specific information is presented NINE MILE POINT in Appendix A" NUCLEAR STATION- UNIT2 SCRIBA, N.Y.
UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016
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NIAGARA MOHAWK POWER CORPORATION NOTE: Cycle-specific information is presented in NINE MILE POINT - UNIT 2 UPDATED SAFETY ANALYSIS REPORT Appendix A, Section A.5 USAR REVISION 7 OCTOBER 1994
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0 0 01 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 NOTE: "Results from initial LOCA analysis. NINE MILE POINT Cycle-specific information is presented NUCLEAR STATION - UNIT 2 in Appendix A" SCRIBA. N.Y.
UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016
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FIGURE: 15C-5 WATER LEVEL INSIDE THE SHROUD VERSUS TIME AFTER BREAK0.11 SQ.FT. HPCS LINE BREAK, LPCS DIESEL GENERATOR FAILURE WITH 2 ADS VALVES OUT-OF-SERVICE.
NINE MILE POINT NUCLEAR STATION - UNIT 2 NOTE: "Results from initial LOCA analysis. Cycle- SCRIBA, N.Y.
specific information is presented in Appendix A" UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016
' VESSEL PnEssu lPSIAl a:
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NINE MILE POINT NUCLEAR STATION - UNIT 2 NOTE: "Results from initial LOCA analysis. Cycle- SCRIBA, N.Y.
specific information is presented in Appendix A" UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016
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TIME ~FTER BREAK (SEC ) FIGURE: 15C-7 CONVECTIVE HEAT TRANSFER COEFFICIENT VERSUS TIME AFTER BREAK 0.11 SQ.FT. HPCS LINE BREAK, LPCS DIESEL GENERATOR FAILURE WITH 2 ADS VALVES OUT-OF-SERVICE.
NINE MILE POINT NOTE: "Results from initial LOCA analysis. Cycle-specific information is presented in Appendix A" I NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.
UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016
~ APPENDIX K LIHIT C.:J z::
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specific information is presented in Appendix A" UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016
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- FIGURE 15C-9 GENERATOR LOAD REJECTION WITH BYPASS FAILURE AND 2 SRV OUT-OF-SERVICE NIAGARA MOHAWK POWER CORPORATION NOTE: Cycle-specific Information is presented in NINE MILE POINT - UNIT 2 Appendix A UPDATED SAFETY ANALYSIS REPORT USAA REVISION 13 OCTOBER 2.000
Nine Mile Point Unit 2 FSAR Figure 15E.3 Core Offload Sequence Map 121~ 122 123 124 125 126 127 128 ~129
'515. 120=t 152 153 154 155 156 157 158 159 130 _.fg4 51 6~
+ 119 151 166 177 186 193 198 200 160 131 95 ~
92 118 150 167 178 187 194 199 201 161 132 96 66 134 47-43 - 63 91 117 149 168 179 188 195 196 197 162 133 97 67 35
- 62 90 116 148 169 180 189 190 191 192 163 134 98 68 36
- 61 89 115 147 170 181 182 183 184 185 164 135 99 69 37 31 - 60 88 114 146 171 172 173 174 175 176 165 136 100 70 38 27 - 59 87 113 145 144 143 142 141 140 139 138 137 101 71 39
- 58 86 112 111 110 109 108 107 106 105 104 103 102 72 40 19 - 57 85 84 83 82 Bl 55 54 53 52 51 BO 79 78 77 76 75 74 73 41 50 49 48 47 46 45 44 43 ..:t42 15 56""
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11 07 20'4 19 13 17 16 15 14 13 12 11 410 L
03 B 7 6 5 4 3 1 9-1 I I I I I I 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58
= SRM Detector Location I
USAlt Revision I Novembtt 199~
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 1' 50 49 48 47 46 45 44 43 72 -l-108 10~
51 83 51 36 25 16 9 4 2 42 71 107 m
~ 110 84 52 35 24 15 8 3 1 41 70 106 136 rtl6 8 43 - 139 111 85 53 34 23 14 7 6 5 40 69 105 135 167
- 140 112 86 54 33 22 13 12 11 10 39 68 104 134 166
- 141 113 87 55 32 21 20 19 18 17 38 67 103 133 165 31 - 142 114 88 56 31 30 29 28 27 26 37 66 102 132 164 21 - 143 115 89 57 58 59 60 61 62 63 64 65 101 131 163 23 - 144 116 90 91 92 93 94 95 96 97 98 99 100 130 162
- 145 117 118 119 120 121 122 123 124 125 126 127 128 129 161 J.-
147 148 149 150 151 152 153 154 155 156 157 158 159 Ld.16 0 l4b 11 -
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01 ()- 183 184 185 186 187 188 189 190 191 -~192 182 03 193 li4 liS li6 li7 liB li9 210 201 1
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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
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- a 1"'149 22 Zl 24 25 l.21 26
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= SRM Detector Location A = Alternate Source Location 1 = High e fuel assembly (8CIB219-4GDZ-100M-150) 2 s Medium e fuel assembly (8CIB176*4GDZ-100M-150)
USAR Revision 8 N<wembec 1995
\
Figure lSE.4-1 Adjacent Loaded Uncontrolled Cells in Different Batches 59 55 51 47-43-39-35-31-27-23-19-15-11 07 03 I I I I 02 06 10 14 18 22 26 30 3.. 38 '42 ..6 50 54 5B
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~ = Loaded Uncontrolled Fuel Cell
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USAR Reviskm 8 November 199S
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.. I FIGURE: 15G*1 A.ANT RESPONSE 10 FEEDWATER CONTROLLER FAl.URE AT 100~ POWE:R ~ FLOW*EOC NINE MILE POINT-UNIT 2 uPOAle:D Slf'E TY .,._Y9lS REPCRT USAR REVISION 22 OCTOBER 2016