ML22292A102

5 to Updated Final Safety Analysis Report, Chapter 6, Appendix 6D, Figures 6.2.1 Through 6C-1

ML22292A102
Person / Time
Site:	Nine Mile Point
Issue date:	10/05/2022
From:	Constellation Energy Generation
To:	Office of Nuclear Reactor Regulation
Shared Package
ML22292A107	List: ML22292A061 ML22292A062 ML22292A063 ML22292A064 ML22292A065 ML22292A066 ML22292A067 ML22292A068 ML22292A069 ML22292A070 ML22292A071 ML22292A072 ML22292A073 ML22292A074 ML22292A075 ML22292A076 ML22292A077 ML22292A078 ML22292A079 ML22292A080 ML22292A081 ML22292A082 ML22292A083 ML22292A084 ML22292A085 ML22292A086 ML22292A087 ML22292A088 ML22292A089 ML22292A090 ML22292A091 ML22292A092 ML22292A093 ML22292A094 ML22292A095 ML22292A096 ML22292A097 ML22292A098 ML22292A099 ML22292A100 ML22292A101 ML22292A102 ML22292A103 ML22292A104 ML22292A105 ML22292A106 ML22292A108 ML22292A109 ML22292A110 ML22292A111 ... further results
References
NMP2L2821
Download: ML22292A102 (432)

Text

POINT OF CRITICAL FLOW BREAK AREA (FT2)

A. RECIRCULATION PUMP SUCTION LINE 2.598 B. REACTOR WATER CLEANUP LINE 0.088 C. COMBINED AREA OF ALL 0.4609 JET PUMP NOZZLES ASSOCIATED WITH THE BROKEN LOOP 50*

TOTAL EFFECTIVE BREAK AREA= 3.147 REACTOR VESSEL RECIRCULATION RECIRCULATION LOOP LOOP c

PUMP TO REACTOR WATER CLEANUP SYSTEM FIGURE 6.2-1 NOTE:

• 5 NOZZLES PER JET PUMP RECIRCULATION PUMP SUCTION LINE BREAK SCHEMATIC NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT US.A.R REVISION 0 A DDt I ft.ft ob

~

c;;

-a::

a..

w 20

)

(/)

rn w

a:

a..

10 TIME AFTER BREAK (SECOND)

FIGURE: 6.2-2 NOTE: THIS FIGURE IS DERIVED BASED ON OLTP CONDITIONS. THE OLTP PRIMARY CONTAINMENT PRESSURE RESULTS REMAIN VALID FOR EPU RECIRCULATION PUMP SUCTION CONDITIONS ON A RELATIVE BASIS. LINE BREAK WITHOUT FEEDWATER, CASE C NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 2.0 OCTOBER 2.012

CONTT. SPRAY ON - - - - - -

• TIME AFTER BREAK (SECOND)

FIGURE: 6.2-3 NOTE: THIS FIGURE IS DERIVED BASED PRIMARY CONTAINMENT PRESSURE ON OLTP CONDITIONS. THE OLTP RECIRCULATION PUMP SUCTION RESULTS REMAIN VALID FOR EPU LINE BREAK WITH FEEDWATER, CASE B CONDITIONS ON A RELATIVE BASIS.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 2.0 OCTOBER 2.012

40a---------;---------+-----------+---.-----+----------i~...........----.....+---------'

DRYWELL ii a..

§ 2or----------r=---:J,_.~~---------+-------. . . . . . +------~ir--11-------~-l..--------..-J fJw a: SUPP.

Q.. CHAMBER o~~~~------4------+------+-------l.------_J_ _____j 103 105 106 TIME AFTER BREAK (SECOND}

FIGURE: 6.2-4 NOTE: THIS FIGURE IS DERIVED BASED ON OLTP CONDITIONS. THE OLTP PRIMARY CONTAINMENT PRESSURE RESULTS REMAIN VALID FOR EPU RECIRCULATION PUMP SUCTION CONDITIONS ON A RELATIVE BASIS. LINE BREAK WITH FEEDWATER, CASE C LIMITING CASE REVISED FOR EPU, SEE FIGURE 6.2-4A ANO 6.2-4B.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT

a.

CJ 6000

....c(

w a:

~

9 LI.

U) u 4000 a.

c o.________........._________._________...________..______________________________

0 200 400 600 800 1000 1200 1400 SOURCE: ES- I 2 I REACTOR -VENT DISCHARGE DIFFERENTIAL PRESSURE (PSI)

FIGURE 6.2-48 .

HIGH PRESSURE CORE SPRAY Nolt: Tlds curve applicable lo Pre-Power Vprale FLOW RATE containment response 1val11alion in Section 6.2.1.1.J" For reco11ciled perfor1na11ce c11rve see NIAGARA MOHAWK POWER CORPORATION Figure 6.J.JA.

NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 13 OCTOBER 2000

45 40

, """" ' '\

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0 0.1 1.0 10.0 100.0 TIME AFTER BREAK (SECOND)

FIGURE: 6.2-4A EPU PRIMARY CONTAINMENT PRESSURE NOTE:EPU GOTHIC OBA SHORT TERM PRESSURE RECIRCULATION PUMP SUCTION RESPONSE.CORYWELL 105°F,ORYWELL RH 40% LINE BREAK WITH FEEDWATER, AND WETWELL q0°F> CASE C - SHORT TERM RESPONSE NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L r USAR REVISION 20 OCTOBER 2012

40

- ,,_ DRYWELL

~

c..111"""

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- SUPP. CHAMBER llAI

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FIGURE: 6.2-48 NOTE:EPU SHEX OBA LONGTERM RESPONSE. EPU PRIMARY CONTAINMENT PRESSURE RECIRCULATION PUMP SUCTION LINE BREAK WITH FEEDWATER, CASE C - LONG TERM RESPONSE NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 2.0 OCTOBER 2.012

DRYWEll 1"1111---- CONTT. SPRAY ON---..-....;a..JI SUPP. CHAMBER TIME AFTER BREAK (SECONDS)

FIGURE: 6.2-5 NOTE: THIS FIGURE IS DERIVED BASED PRIMARY CONTAINMENT PRESSURE RECIRCULATION PUMP SUCTION ON OLTP CONDITIONS. THE OLTP LINE BREAK WITH FEEDWATER, CASE A RESULTS REMAIN VALID FOR EPU CONDITIONS ON A RELATIVE BASIS.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 20 OCTOBER 2012

DRYWELL CONTT*

...,___ _ _-'- SPRAY ON --+----;;aa.a u..

0 100 r:::=::::::=:::J::::=:=:::;;;;;--t'~--------t---\------1-----~--+------~--l-----~__J SUPP.

CHAMBER 103 108 TIME AFTER BREAK (SECOND)

FIGURE: 6.2-6 NOTE: THIS FIGURE IS DERIVED BASED PRIMARY CONTAINMENT TEMPERATURE ON OLTP CONDITIONS. THE OLTP RECIRCULATION PUMP SUCTION RESULTS REMAIN VALID FOR EPU LINE BREAK WITH FEEDWATER, CASE A CONDITIONS ON A RELATIVE BASIS.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L_'"-----------------------------------------------------,~~U~SA~R;:::-;:R~E~V~IS~I~O~N~2~0~-----0-C-T-O-B-E-R--20-1~2

DRYWELL CONTT.

1-'-----t-- SPRAY ON aooL--------1-~--~---1-----~r--f---------+-t--------+---------r-------~

SUPP.

CHAMBER 0L..-L..LJLI.!Jlil..........J_LJ..J..llilL--L..l..J.JUJJJ.L............J.......J...J...J..U.UJ..........J.....L.IU..L.U..U--....1-.&...&..J...U..LY..--.L.......1-'-lr...w..I~

10*1 10° 101 102 103 104 105 108 TIME AFTER BREAK (SECOND)

FIGURE: 6.2-7 NOTE: THIS FIGURE IS DERIVED BASED PRIMARY CONTAINMENT TEMPERATURE ON OLTP CONDITIONS. THE OLTP RECIRCULATION PUMP SUCTION RESULTS REMAIN VALID FOR EPU LINE BREAK WITH FEEDWATER, CASE B CONDITIONS ON A RELATIVE BASIS.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 20 OCTOBER 2012

,,.....__ DRYWEll 300L...--~-----i-----~---l--------~+-------"".f-J.i!-------~--r----------r~-------,

u.

0 w

a:

> 200 a:

lU a..

eIJJ I-SUPP.

CHAMBER 100 101 10 2 TIME AFTER BREAK (SECOND)

FIGURE: 6.2-8 NOTE: THIS FIGURE IS DERIVED BASED PRIMARY CONTAINMENT TEMPERATURE ON OLTP CONDITIONS. THE OLTP RECIRCULATION PUMP SUCTION RESULTS REMAIN VALID FOR EPU LINE BREAK WITH FEEDWATER, CASE C CONDITIONS ON A RELATIVE BASIS.

LIMITING CASE REVISED, SEE FIGURE 6.2-SA ANO FIGURE 6.2-SB.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 20 OCTOBER 2012

300 I

I 275 '

... IOI"'

- DRYWELL 250

~

J' 225

,., Iii"

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w a; 200 A' "

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100 I ........ I I I I

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- POOL 75 I

50  !

0.1 1.0 10.0 100.0 TIME AFTER BREAK (SECOND)

FIGURE: 6.2-8A EPU PRIMARY CONTAINMENT TEMPERATURE NOTE:EPU GOTHIC OBA SHORT TERM TEMPERATURE RECIRCULATION PUMP SUCTION RESPONSE.DRYWELL 105°F,ORYWELL RH 40% LINE BREAK WITH FEEDWATER, AND WETWELL q0°F. CASE C - SHORT TERM RESPONSE NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L r USAR REVISION 20 OCTOBER 2012

350 f j

I 300 .

I I

I I

i I

DRYWELl LL.

~ 250 .....

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SUPP. CHAMBER: --- 1--

I I

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100 i 100 1000 10000 100000 TIME AFTER BREAK (SECOND)

FIGURE: 6.2-88 EPU PRIMARY CONTAINMENT TEMPERATURE NOTE:EPU SHEX OBA LONG TERM TEMPERATURE RESPONSE. RECIRCULATION PUMP SUCTION LINE BREAK WITH FEEDWATER, CASE C - LONG TERM RESPONSE NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L r USAR REVISION 20 OCTOBER 2012

DRYWELL SUPP.

CHAMBER 101 102 103 104 105 10*

TIME AFTER BREAK (SECOND)

FIGURE: 6.2-9 PRIMARY CONTAINMENT TEMPERATURE NOTE: THIS FIGURE IS DERIVED BASED RECIRCULATION PUMP SUCTION ON OLTP CONDITIONS. THE OLTP LINE BREAK WITHOUT FEEDWATER, CASE C RESULTS REMAIN VALID FOR EPU CONDIT IONS ON A REL AT IVE BASIS.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT

0w (I) m

..J

~ 50001----------------~--.........~---------~...........----_._......................................--1-~-----------------a

<t a:

0

..J I&.

10-1 2 3 4 5 6 1 8 91 oo 2 3 4 5 6 1 8 9101 2 3. 4 5 6 1 89102 TIME AFTER BREAK (SECOND) FIGURE: 6.2-10 NOTE: DERIVED BASED ON OL TP AND IS VERIFIED VENT SYSTEM MASS FLOW TO BE APPLICABLE TO EPU CONDITIONS. RECIRCULATION PUMP SUCTION LINE BREAK WITH FEEDWATER, CASE C NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 20 OCTOBER 2012

300 ...----------t---------;---~~---t-----~---1----------+--------~----~~~

u...

• 0 CASE A TIME AFTER BREAK (SECOND)

FIGURE: 6.2-11 NOTE: THIS FIGURE IS DERIVED BASED ON OLTP CONDITIONS. THE OLTP SUPPRESSION POOL TEMPERATURE RESULTS REMAIN VALID FOR EPU RECIRCULATION PUMP SUCTION CONDITIONS ON A RELATIVE BASIS. LINE BREAK WITH FEEDWATER LIMITING CASE REVISED FOR EPU, SEE FIGURE 6.2-llA.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L_'"---------------------------------------------------------------------------,~~U~SA7,R~R~E~V~IS~l~O~N~2~0~-------0-C-T-O-B-E-R-2-0-1J2

250 I

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50 l

l

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I l 10 100 1000 10000 100000 TIME AFTER BREAK (SECOND)

FIGURE: 6.2-11A NOTE:EPU SHEX OBA LONG TERM TEMPERATURE RESPONSE. EPU SUPPRESSION POOL TEMPERATURE RECIRCULATION PUMP SUCTION LINE BREAK WITH FEEDWATER NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 20 OCTOBER 2012

50,000 0UI en e.

30,000

....ill(w a:

...J CASE B

§ 0

e 20,000 1-----ir------t-----+-----11:-----"::lll~-+------+-------1 w

c:

~

w

c CASEC 10,000 TIME AFTER BREAK (SECOND)

FIGURE: 6.2-12 NOTE: THIS FIGURE IS DERIVED BASED ON OLTP CONDITIONS. THE OLTP RHR HEAT EXCHANGER HEAT REMOVAL RESULTS REMAIN VALID FOR EPU RECIRCULATION PUMP SUCTION LINE CONDITIONS ON A RELATIVE BASIS. BREAK WITH FEEDWATER LIMITING CASE REVISED FOR EPU, SEE FIGURE 6.2-12A.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 2.0 OCTOBER 2.012

50,000 I f f i  !

! i I ' l i  !

I I I I l I i  ! I I I 40,000 l  !

u  ! I I I

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r f i I I 30,000 I I

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c j l I i

I I 14-l I 10,000 I l

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0 I I  !

10 100 1000 10000 100000 TIME AFTER BREAK {SECOND)

FIGURE: 6.2-12A NOTE:EPU SHEX OBA LONG TERM HEAT REMOVAL. EPU RHR HEAT EXCHANGER REMOVAL RECIRCULATION PUMP SUCTION LINE BREAK WITH FEEDWATER, CASE C NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L r USAR REVISION 20 OCTOBER 2012

FLOW RESTRICTORS TURBINE BREAK INBOARD OUTBOARD BYPASS

--B MSIV MSIV A

c REACTOR

- TURBINE PRESSURE VESSEL

-- STOP VALVES DRYWELL CONTAINMENT POINT OF CRITICAL FLOW AREA (FP)

A. STEAM LINE NOZZLE 3.05 B. STEAM LINE RESTRICTOR 0.913 C. MAIN STEAM ISOLATION VALVE 0.913-0.0 FIGURE 6.2-13 MAIN STEAM LINE BREAK SCHEMATIC

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

6.0 .. STEAM INVENTORY AREA : 2.233 FT 2 FLOW RESTRICTOR AREA: 0.913 FT2 STEAM NOZZLE AREA: 3.05 FT2 STEAM LINE AREA: 2.977 FT2 5.283 FP j:!..

5.0 "'

<(

w a:

<(

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<( 3.963 FP

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al w

t:=

(.)

w

u. (.) (.)

3.05 FT2

u. w w w 3.0 .. en en N

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I CJ? (.)

d M w en I.I) 2.0 0

,H 0.1 0.2

~ 2 I 3

1. 4 I

5

~ I 6

22 I 106 TIME AFTER ACCIDENT (SECONDS)

FIGURE 6.2-14 MAIN STEAM LINE BREAK AREA VS TIME NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT

40 DRYWEll CONTT.

SPRAY ON 30

-us CJ Q.

UJ a:: 20 fl) fl)

LI.I a: SUPP.

Q.. CHAMBER 10

.. 10' L-..J-.J...J..J..1.JJ.U............L.....J.....L.J.JJUJ.L-..L.-11......L.LL.LUJ....__....!l...-.l.....Ul...l...L.l.L&.-_,...,l,_...&....l...l...&..L.a.IU...-_ _...........~.............._................._ _

10-1 10° 101 102 103 104 105 TIME AFTER BREAK (SECOND)

FIGURE: 6.2-15 NOTE: THIS FIGURE IS DERIVED BASED PRIMARY CONTAINMENT PRESSURE ON OLTP CONDITIONS AND REMAINS MAIN STEAM LINE BREAK APPLICABLE TO EPU CONDITIONS BASED WITH FEEDWATER, CASE A ON REFERENCE 12, 18,AND 1q.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 20 OCTOBER 2012

CONTT.

DRYWELL SPRAY ON SUPP.

CHAMBER TIME AFTER BREAK (SECOND)

FIGURE: 6.2-16 PRIMARY CONTAINMENT PRESSURE NOTE: THIS FIGURE IS DERIVED BASED MAIN STEAM LINE BREAK ON OLTP CONDITIONS AND REMAINS WITH FEEDWATER, CASE B APPLICABLE TO EPU CONDITIONS BASED ON REFERENCE 12, 18, AND 1C3.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 20 OCTOBER 2012

II.I

~ 201---~~~-;-----.,_--,.r-+-+----~-t---~-----1-~--~~-+-~~----~---------1 (I) en w

a:

Q..

-10..._................a-.di....&...&..u.&d---'--..............U..UJ.l.--..L-A-&...l...a..&.LU..--.i.........a....a...JL..U.1u.&.............A-L......L...L..u..&.U......-L.......L...L..LLU..1~......J....-L-u.JU..W 10*1 101 102 103 10 4 TIME AFTER BREAK (SECOND)

FIGURE: 6.2-17 NOTE: THIS FIGURE IS DERIVED BASED ON OLTP CONDITIONS AND REMAINS PRIMARY CONTAINMENT PRESSURE APPLICABLE TO EPU CONDITIONS BASED MAIN STEAM LINE BREAK ON REFERENCE 12, 18,AND 1g. WITH FEEDWATER, CASE C NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 20 OCTOBER 2012

40 DRYWELL 30 CJ 0

a..

w a: 20 CJ) fl)

UJ a: SUPP.

a..

CHAMBER 10 0

-10 ......................L.-d~..s.J,J..l--..r.................-.,,....a.L.&.&......---..a-a..a.-1.1~............- - - -.......................- -............................................~............~--..........- -........................

10-1 101 103 104 105 TIME AFTER BREAK (SECOND)

FIGURE: 6.2-18 NOTE: THIS FIGURE IS DERIVED BASED PRIMARY CONTAINMENT PRESSURE ON OLTP CONDITIONS ANO REMAINS MAIN STEAM LINE BREAK APPLICABLE TO EPU CONDITIONS BASED WITHOUT FEEDWATER, CASE C ON REFERENCE 12, 18,ANO 1q.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 20 OCTOBER 2012

DRYWELL CONTT. _.,_ _ _ _..,...

SPRAY ON u..

0 SUPP.

CHAMBER OL-....J.....-L-.ih....L.J..u.u---1....J....J....L..uu..u................_.._,_.i-u..w.a---......_.....'-d......,..i..w-....-1.......-.............a..w.u-_...-...........,...--.....__,__.___._........

10.. 1 101 102 104 105 TIME AFTER BREAK (SECOND)

FIGURE: 6.2-19 PRIMARY CONTAINMENT TEMPERATURE NOTE: THIS FIGURE IS DERIVED BASED MAIN STEAM LINE BREAK ON OLTP CONDITIONS ANO REMAINS WITH FEEDWATER, CASE A APPLICABLE TO EPU CONDITIONS BASED ON REFERENCE 12, 18,ANO 1q.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 20 OCTOBER 2012

DRYWELL Hlllf-----" CONTAINMENT SPRAY ON +------~

ii:'

Q w

a:

~ 200.-~-----t----------t-----------1---------1-l---------l.-

u:

UJ a.

w t-SUPP.

100r::=:=::::::::t==-:=:=::=;;;ii;.,-.~----;----------f--~C~H~AM:.:.:=BE=R:......t--------4-------__J TIME AFTER BREAK (SECONDS) FIGURE: 6.2-20 PRIMARY CONTAINMENT TEMPERATURE NOTE: THIS FIGURE IS DERIVED BASED MAIN STEAM LINE BREAK ON OLTP CONDITIONS AND REMAINS WITH FEEDWATER, CASE B APPLICABLE TO EPU CONDITIONS' BASED ON REFERENCE 12, 18,AND 1g.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 2.0 OCTOBER 2.012

u..

0 w

a:

---

1-----------+--.. . . . . .------+---------+---------I

)

~ 200 a---1-----~a----------11--..........

0:

w A.

s w

SUPP.

CHAMBER:

1oor-===:::t=::=:::::;;;;::~~------r----~~1------1---------1------1 0 ...__..__,_~~...............---..a....a....a...1.1.1.n--_........~i.....&..J..J..UJ~.....J-......._.....L.J..U..U--.............L-.l.....U.1.U.L.--......_J.....L...U..U.U.--...l-.J.-L....L.J.,,JU..U 10*1 101 102 103 104 101 10' TIME AFTER BREAK (SECONDS)

FIGURE: 6.2-21 NOTE: THIS FIGURE IS DERIVED BASED PRIMARY CONTAINMENT TEMPERATURE ON OL TP CONDITIONS AND REMAINS MAIN STEAM LINE BREAK APPLICABLE TO EPU CONDITIONS BASED WITH FEEDWATER, CASE C ON REFERENCE 12, 18,AND 1q.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 2.eJ OCTOBER 2012

SUPP.

CHAMBER 101 102 10' 10 4 105 10*

TIME AFTER BREAK (SECOND)

FIGURE: 6.2-22 NOTE: THIS FIGURE IS DERIVED BASED PRIMARY CONTAINMENT TEMPERATURE ON OL TP CONDITIONS ANO REMAINS MAIN STEAM LINE BREAK APPLICABLE TO EPU CONDITIONS BASED WITHOUT FEEDWATER, CASE C ON REFERENCE 12, 18,AND 19.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 20 OCTOBER 2012

ii:'

0 w

a:

!( 200 a:

w A.

~

w 10-1 10° 101 102 103 10*

TIME AFTER BREAK (SECONDS)

FIGURE: 6.2-23 NOTE: THIS FIGURE IS DERIVED BASED SUPPRESSION POOL TEMPERATURE ON OLTP CONDITIONS AND REMAINS MAIN STEAM LINE BREAK APPLICABLE TO EPU CONDITIONS BASED WITH FEEDWATER ON REFERENCE 12, 18, AND 1q.

TEMPERATURE COMPARISON BASED ON OLTP ASSUMED RHR HEAT EXCHANGER K-FACTOR=1qq BTU/SEC PER °F.EPU ASSUMED K-FACTOR WILL NINE MILE POINT-UNIT 2 CONTINUE TO REDUCE POOL TEMPERATURE UPDATED SAFETY ANALYSIS REPORT BELOW ITS MAXIMUM LIMIT.

L USAR REVISION 20 OCTOBER 2012

THIS FIGURE HAS BEEN DELETED

---

~ .. - ----------.

.. FIGURE 6.2-24

\. NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT 1 uua REVISION 13 OCTOBER 21*>

~

THIS FIGURE HAS BEEN DELETED

! '- -** ~ *- ---- :::. ____

FIGURE 6.2-25 I I

I I

r f*

NIAGARA MOHAWK POWER CORPORATION I

~ NINE MILE POINT-UNIT 2  :

-~

UPDATED SAFETY ANALYSIS.REPORT j I

U5AR REVISION 13 OCTOBIA 2lllG

THIS FIGURE HAS BEEN DELETED FIGURE 6.2-26 NIAGARA MOHAWK POWER CORPORATION i NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT OCTOBER :IBl

THIS FIGURE HAS BEEN DELETED iiiiiiim~**

.....FIGURE

________ 6.2-27

~111111111111----------1

\

, NIAGARA MOHAWK POWER CORPORATION  !

NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USM't &VISION 13 OCTOll&l 2119

vs.

STEAM LINE BREAK AREA (PRE-EPU ANALYSIS) 0.08 N

¢::'.

en

{/)

0 0..

0.07

£ (JJ JS c

3:

0 0.06 0.05 0 0.4 0.8 1.2 1.6 2 2.4 2.8 Break Area (ft2)

FIGURE: 6.2-28 MAXIMUM ALLOWABLE BYPASS CAPACITY (A/ { k} VERSUS STEAM LINE BREAK AREA NOTE: THE ABOVE PLOT IS FOR THE PRE-EPU ANALYSIS, WHICH ASSUMED SPRAY INITIATION AT 30 MINUTES.

FOR EPU, SPRAY INITIATION IS AT 20 MINUTES. NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 20 OCTOBER 2012

1 o-.. 1 0-'

0

(.{)

SPRAYS ~SHUTDOWN LING ON

°"

...... 0 It)

{/)

a..

w a::: 0

J

(/)

CJ) lJJ Q::

0...

I-

z 0 w

r:

z I-z 0 0 u N TI ME CSECONOSl FIGURE: 6.2-28A LONG TERM STEAM BYPASS ANALYSIS:

2 BREAK AREA = 0.3 FT ;

BYPASS AREA = 0.05 FT 2

• NOTE: THE ABOVE PLOT IS FOR THE PRE-EPU ANALYSIS, WHICH ASSUMED SPRAY INITIATION AT 30 MINUTES.

FOR EPU, SPRAY INITIATION IS AT 20 MINUTES.

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 20 OCTOBER 2012

I '

,~

I P1 irr ari ' ( Of! ta1 nn 1er t\ Va Iii l c: ry NEii 100 J

u.

.....f II N'

~... - -

~

i--

~

.a 0

J-

c 10 I

v

.A I

A r I

IP' 1~rlr na ~\J r

"'n "!ti 1in "l"U:I n+ \Al :lJL. fl_ w~ *tv rel

)

1 0 200 400 600 800 1000 1200 1400 1600 1800 Time (secJ FIGURE: 6.2-288 HEAT SINK SURFACE HEAT SINK SURFACE HEAT TRANSFER COEFFICIENCY FOR HEAT TRANSFER COEFFICIENT LIMITING STEAM BYPASS CONDITION Break = 0.3 ft2 Bypass = 0.05 ft2 NOTE: THIS IS A PRE-EPU ANALYSIS NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L r USAR REVISION 20 OCTOBER 2012

50 ~--=---=--=----=--=------------------------------------------------------------...-.

Design Pressure = 45 psig 4-0 30 20 90% SPRAY EFFICIENCY Drywall and Wetwell Sprays Initiated at 1800 seconds 10 0 '----.....a-..--__..____ ~--------------------------~----...._ ______________________________

0 o.4 o.a 1.2 1.6 2 2.4 (Thousands)

TIME (sec)

<> OW-Spray @ 501' A WW-Spray @ 50.% X OW-Sproy @ 90" V WW-Spray @ 90" CONTAINMENT PRESSURE SENSTIVITY TO FIGURE: 6.2-28C SPRAY THERMAL EFFICIENCY CONTAINMENT PRESSURE SENSITIVITY TO SPRAY THERMAL EFFICIENCY FOR Break= 0. 3 ft2 Bypass= 0.05 ft2 LIMITING STEAM BYPASS CONDITION NOTE: THE ABOVE PLOT IS FOR THE PRE-EPU ANALYSIS, WHICH ASSUMED SPRAY INITIATION AT 30 MINUTES. NINE MILE POINT-UNIT 2 FOR EPU, SPRAY INITIATION IS AT 20 MINUTES.

UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 20 OCTOBER 2012

---

+-------.. . . . . . . . . . . . . . .~ r CONTAINIVJENT WALL. (DRYWEL.L)

HEATSINK#7 TIME AFTER BREAK (SECOND)

FIGURE: 6.2-29 NOTE: THIS FIGURE IS DERIVED BASED HEAT TRANSFER COEFFICIENT ON OLTP CONDITIONS.FOR EPU, RECIRCULATION PUMP SUCTION LINE REFER TO REFERENCES 7 AND 16. BREAK WITH FEEDWATER, CASE C NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L_'----~--~~----------------------~--------~-------,~~U~S~A~R~R~E~V~IS~I~07N~2~0=-------0--CT-O-B-E-R--20-1_J2

25.00 tn A.

u..

20.00 0

0

..J w

> 15.00 w

(.)

ill(

u..

a:

tn 10.00

..J 0

0 A.

5.00 0.00-f-...........-------4~------

• o.oo 2.00

. . . . --------.6.00 4.00

... ---------4~------

8.00

. . . .--------.12.00 10.00

. . . ----.. . . . 14.00 POOL SWELL HEIGHT (FEET) FIGURE 6.2-29A 11------------------------------......

LOCTVS COMPARISON TO PSTF RESULTS POOL SURFACE VELOCITY VS SWELL HEIGHT LIQUID SLOWDOWN NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT JUNE f984

38

\

LOCTVS-36

~

~PSTF

/r IL DATA

...I 34 0

0 a.

IL 0 32

E 0

I= j

/

0 30 m

E

/ l 0

a: 28 IL z

O*

V/

~

oc( 26 w

...I w

v

_/

24

- ~

22 0.00 0.20 0.40 0.60 0.80 1.00 1.20 1.40 1.60 TIME (SECONDS) FIGURE 6.2-298 LOCTVS COMPARISON TO PSTF RESULTS POOL SURFACE ELEVATION VS TIME LIQUID SLOWDOWN NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

.II INF 1QR4

24 U) a.. 20 LL

~

u 0

...I 16 w

w 0

c(

LL 12 a:

U) 0 8 0

a..

o-'-----......j~---==::::t:::=::-.._ __..J-______J.--____.......J.______...J-______J-__--l--J o.oo 0.20 0.40 . 0.60 0.80 1.00 1.20 1.40 . 1.60 TIME (SECONDS) FIGURE 6.2-29C LOCTVS COMPARISON TO PSTF RESULTS POOL SURFACE VELOCITY VS TIME LIQUID SLOWDOWN NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMFNDMENT 11

v 30 LOCTVS--..

/,

28

"/-PSTF DATA II 26 v

~

en

-w 24 A.

a:

I

~ 22 en w

a:

A.

/v

20 18 16 ~

---

~

14 0.00 0.20 0.40 0.60 0.80 1.00 1.20 1.40 1.60 TIME (SECONDS) FIGURE 6.2-29D LOCTVS COMPARISON TO PSTF RESULTS WW AIR SPACE PRESSURE VS TIME LIQUID SLOWDOWN NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMl=NnMFNT 11 JUNE 1984

~

34 U)

D.

w a: 30

> PSTF U) tn DATA w

a:

D.

26

....m w

m m 22 14 ........--'6'--.........-------+-------+------+-------+-------+------t-------~--------

o.oo 0.20 0.40 0.60 0.80 1.00 1.20 1.40 1.60 1.80 TIME (SECONDS) FIGURE 6.2-29E LOCTVS COMPARISON TO PSTF RESULTS BUBBLE PRESSURE VS TIME LIQUID SLOWDOWN NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT JUNE 1984

25.00 en a.

u.

20.00 0

0

..I w

> 15.00 w

0 c(

u.

a:

en 10.00

..I 0

0 a.

5.00 o.oo_.,_______...,...______...,...._______...______-..._______,..______._..________._________.

0.00 2.00 4.00 6.00 8.00 10.00 12.00 14.00 16.00 POOL SWELL HEIGHT (FEET) FIGURE 6.2-29F LOCTVS COMPARISON TO PSTF RESULTS POOL SURFACE VELOCITY VS SWELL HEIGHT STEAM SLOWDOWN NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMFNDMENi 11 JUNE 1984

/

36 i.--

rf 34 LOCTVS--t i='

LL I

//

~-

..... 32

~STF 0

0

£L DATA II LL 0 30 s

==

0 I '/

28 m

0==

//'

e: 26 z

v 0

!c> 24 w

/

w 22

/

20 0.00 0.20 0.40 0.60 0.80 1.00 1.20 1.40 1.60 TIME (SECONDS) FIGURE 6.2-29G LOCTVS COMPARISON TO PSTF RESULTS POOL SURFACE ELEVATION VS TIME STEAM SLOWDOWN NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AUCl\lnl\ACl\IT 11 .ll INF 1QR4

- 24 U) a.

LL 20 u0 w 16 w

0 c(

LL a: 12 U) 0 8 0

Q.

4 0-l-----~1-=====~------~------.{......-----+------....+.------+-------'

0.00 0.20 0.40 0.60 0.80 1.00 1.20 1.40 1.60 TIME (SECONDS) FIGURE 6.2-29H LOCTVS COMPARISON TO PSTF RESULTS POOL SURFACE VELOCITY VS TIME STEAM SLOWDOWN NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

.11 INI= 1 QA.4

32 v

v

/

30 LOCTVS ---

I 28 I v /"

26 I"'"

cc PSTF u; - DATA

//

~ 24 w

a:

I/

~ 22 w

a:

v D..

20

~

/

18 16

___.,e;. v 14 I

0.00 0.20 0.40 0.60 0.80 1.00 1.20 1.40 1.60 TIME (SECONDS} FIGURE 6.2-29 I LOCTVS COMPARISON TO PSTF RESULTS WW AIR SPACE PRESSURE VS TIME STEAM SLOWDOWN NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT

34

./ \

32 I \

30 LOCTvs,

- y I\

./L ~ /

A 28 PSTF v

c(

• oATA u; 26

\~

D.

w a: /

/

> 24

,I I\

0 ~

0 w

a:

/

D. 22 v w

...I m / ~ _/

m 20

~~

~-

m

/

18 16 /

14 0.00 0.20 0.40 0.60 0.80 1.00 1.20 1.40 1.60 TIME (SECONDS) FIGURE 6.2-29J LOCTVS COMPARISON TO PSTF RESULTS BUBBLE PRESSURE VS TIME STEAM SLOWDOWN NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT

345 -l l~s' REF TOP 1

OF DRYWELL HEAD iREACTOR FIGURE *6.2-30 :

DRYWELL HEAD-REFUELING BULKHEAD SKETCH .

(/.

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 .

.,. FINAL SAFETY ANALYSIS REPORT

105° oo ______._ _ ..,a__

CL REACTOR 345° NOTE:

THE SHADED AREAS ARE AIR DUCTS PENETRATING THE VENT. THESE SHADED AREAS ARE NOT AVAILABLE FOR 285° VENT FLOW.

SECTION 1-1 SOURCE: EV-001T-7 FIGURE 6.2-30A REFUELING BULKHEAD VENT AREA NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR RFVISION 1~ or.TORFR ?nn?

DRYWEli...

HEAD I  :

-* I DRYWELL BELOW REFUELING BULKHEAD FIGURE *a.2~31 NODA.LIZATION DIAGRAM

• 4 * ... ~

RCIC HEAD SPRAY LINE BREAK DRYWELL .

HEAD-DRYWELLSUBCOMPARTMENT'.S

• NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2

• FINAL SAFETY ANALYSIS REPORT

30.0 25.0 r DRYWELL HI EAD (pt)

NODAL PRESSURES: RCIC HEAD SPRAY LINE BREAK. DRYWELL HEAD

- DRYWELL SUBCOMPARTMENTS.

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT - UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAA REVISION 0 APRIL 1989

~

)

1f2UJQJ

/ P1 - Pz 0.......

U) 8.00

~

e:

~-

/

6.QJ0

/

La.I a:

J

(/)

(/)

IJJ I

tr:

0.. 4.11

_J

([

I-z I

La.I a: 2.1210 UJ LL LL 0

iUJ0

-2.0m e.00 la.SB 1.0121 1.se 2.00 2.50 FIGURE 6.2-318 TIME AFTER BREAK <SECONDS>

NODAL PRESSURE DIFFERENTIALS:

RCIC HEAD SPRAY LINE BREAK. DRYWELL

- DRYWELL HEAD SUBCOMPARTMENTS.

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT - UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 0 APRIL 1989

-~*~--*--~-. *-~* .. -*-

© DRYWELL HEAD I J  :

i _ _ _ _...,__......__._.....,__......_--"""_ _ _ _...,....

© DRYWELL BELOW REFUELING BULKHEAD FIGURE 6.2-32 NODALIZATION DIAGBAM RECIRCULATION SUCTIQN LINE BREAK DRYWELL HEAD-DRYWELL SUBCOMPARTMENTS NIAGARA MOHAWK POWER CORPORATION NINE MILE POIN_T~UNIT 2 FINAL SAFETY ANALYSIS REPORT

60.0 DRYWELL CP2> - -

DRYWELL HEAD

21.e 0.50 U!J0 1.50 2.1210 2.50 FIGURE 6.2-33A TIME AFTER BREAK <SECONDS> NODAL PRESSURES: RECIRCULATION SUCTION LINE BREAK. DRYWELL HEAD - DRYWELL SUBCOMPARTMENTS. NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT - UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAA REVISION 0 APRIL 1989 ISl tSl IS\ aex) Cl (/) a.. ISl '5il IJJ CD a: Cl) (/) L1J 0:: a.. ISi tSl,. -z _J <I: IJJ ~ 0:: N w LL LL Cl ~ tSl FIGURE 6.2-338 TIME AFTER BREAK <SECONDS> NODAL PRESSURE DIFFERENTIALS: RECIRCULATION SUCTION LINE BREAK. DRYWELL - DRYWELL HEAD SUBCOMPARTMENTS. NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT - UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 0 APRIL 1989 40000 32000 0w en -~ !l 24000 a: ~ 3r: 0_. u.. 16000 en UJ \ 8000 ~r r----1 I 1111111 I 1111111 I I 111111 I I 11111 I 1111111 I 1111111 I I 111111 0 10..1 101 102 103 104 105 101 TIME AFTER BREAK (SECOND) FIGURE: 6.2-34 NOTE: THE MASS RELEASE IS FOR THE OLTP CONDITIONS. REACTOR VESSEL SLOWDOWN EPU LIMITING CASE MASS RELEASE PROVIDED RECIRCULATION PUMP SUCTION IN FIGURE 6.2-34A. LINE BREAK WITH FEEDWATER, CASE C NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 20 OCTOBER 2012 40,000 --------,.-------.--------....----------.-------~---------, 32,000 ....---------1---1-*- - - - - - - , r - - - - - - - - - - - - - - - t - - LONG-TERM (SHEX)

• • * * *

• EXTENDED-SHORT-TERM (M3CPT)

I - - SHORT-TERM {M3CPT} u '-*-*.... ~1*.-*flllll!. ........, ~ 24,000 " t - - - - - - - - + - - - - - - - + - - - + - ** - - - - + - - - - - - - - i - - - - - - - - ; - - - - - - - - - i ~ ~ .I ~ I " 16,000 -i--------+--------!----1-!-----+--------+---------t--------i s \ ~ \ ~ \ ..*......... 19**** ~ 8,000 + - - - - - - - - - + - - - - - - - t - - - - 4 \ . . . - - - - - + - - - - - - - - + - - - - - - - J - - - - - - - - i

• • - - - - - - - *.........-..._ _ _ _ _ _ _ _ _ t - _ _ _ _ _ _ _ _ _ _

• • -*~~-*~*~*1--...........*........~*-*Lo..lm*~*~**~*+--;_:~._.,-..........~*~*~*~**a.t-........-*.......-*..........*-*-*-*-*mlmf-*---*---*-*---**~**--i*

0 -r---~-..........*..........*~*~*~*~*-a+-*--~*--........ 0.1 1 10 100 1000 10000 100000 TIME AFTER BREAK (SECOND) FIGURE: 6.2-34A NOTE:EPU DBA-LOCA SLOWDOWN DATA. EPU REACTOR VESSEL SLOWDOWN RECIRCULATION PUMP SUCTION LINE BREAK WITH FEEDWATER, CASE C NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L r USAR REVISION 20 OCTOBER 2012 600..,________--t~---- ...... --a................ ...----+---------+-----------f----------1----------t 200t--------...........~--------+----------t-----~IR--+----------+---------~---------1 o ...........-.............................................................w.w-...................................&,W,l._ _.......................,...1..1.du.u................a-...............,..&.A&..........~_._1..U.L.U............di......J.-.t-1....u..u.1 10-1 .10' 101 101 TIME AFTER BREAK (SECOND) FIGURE: 6.2-35 REACTOR VESSEL SLOWDOWN ENTHALPY NOTE: THE ENERGY RELEASE IS FOR THE OLTP CONDITIONS. RECIRCULATION PUMP SUCTION EPU LIMITING CASE ENERGY RELEASE PROVIDESD IN LINE BREAK WITH FEEDWATER, CASE C FIGURE 6.2-35A. NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 20 OCTOBER 2012 800 -EXTENDED-SHORT-TERM {M3CPT) 600 ~.. - - LONG-TERM (SHEX} . * * * * ** SHORT-TERM (M3CPT} f-- II .__,,,, m-..J I-co \ 400 Q.

c t-

~ __ zId.I 200 0 - . . . . . ... - - - ... .. - .... . - - - .. ... -- - - - .. - ..... - - - . - - - . . . . . .. - - 0.1 1 10 100 1000 10000 100000 TIME AFTER BREAK (SECOND) FIGURE: 6.2-35A EPU REACTOR VESSEL SLOWDOWN NOTE:EPU DBA-LOCA SLOWDOWN DATA. ENTHALPY RECIRCULATION PUMP SUCTION LINE BREAK WITH FEEDWATER, CASE C NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 20 OCTOBER 2012 TIME AFTER BREAK (SECOND) FIGURE: 6.2-36 REACTOR VESSEL SLOWDOWN NOTE: THE MASS RELEASE IS FOR THE OLTP CONDITIONS MAIN STEAM LINE BREAK WITH AND IS VERIFIED APPLICABLE TO EPU CONDITIONS FEEDWATER CASE C PER REFERENCES 12, 18 AND 19. NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L_'----------------------------------------------------------------------------------p:--+.usnA~R~R~E~V~IS~IO~N~2~0-----------0-C-T_O_B_ER__2_0_J12 12oor;;;;;;;;;--===~ir----------t---------+----._...---+---------...+---------...l---------J m ....a -aoor----------......,ra---.. . . . .---;-----------+---------+.----------1----------1-------__J

')

I-m Q. ....a ct i!:z w 400 r------t-------1---.....: TIME AFTER BREAK (SECOND) FIGURE: 6.2-37 REACTOR VESSEL SLOWDOWN ENTHALPY NOTE: THE ENERGY RELEASE IS FOR THE OLTP MAIN STEAM BREAK CONDITIONS AND IS VERIFIED APPLICABLE WITH FEEDWATER, CASE C TO EPU CONDITIONS PER REFERENCE 12, 18 AND 19. NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT SOURCE MONITOR CONDITION CONTROL ACTION RESULTANT MONITOR SW-SR H2/02 ANALYZER PUMP *P2A RUN NOTE 10 MAIN POWER TO H2/02 ANALYZER SYSTEM-ON NOTE II SW-SR # H2/02 ANALYZER PUMP *P2A START H2/02 ANALYZER PUMP *P2A NOT MOTOR OVERLOAD SW-MAINTAIN H2/02 ANALYZER H2/02 ANALYZER MODE SWITCH INLET ISOLATION PUMP *P2A ANALYZE VAL VE *SOV64A OPEN H2/02 ANALYZER SW-PB CMS PR! CONTMT H2/02 ANALYZER NOTE 5 PUMP *P2A OUTLET ISOLATION DIV I MANUAL ISOLATION VAL VE *SOV65A OPEN RESET P873 START P873 NOTE 5 SW-PB CMS PR! CONTMT ORYWELL HUMIDITY DIV I MANUAL ISOLATION EL 265' ISOLATE P873 <RANGE 0 TO 100% RH) NOTE 6 SW- !KEYLOCKl LOCA OVERRIDE OVERRIDE LOSS OF COOLANT ACCIDENT ISOLATION SIGNAL DIV I H2/D2 ANALYZER PUMP llP2A G STOP NOTE 6 SW- <KEYLOCKl P873 H2/02 ANALYZER SAMPLE LOCA OVERRIDE LOW FLOW RESET NOTES: SW-MAINTAIN I. ALL INSTRUMENT ANO EQUIPMENT NUMBERS TO BE PREFIXED WITH "2CMS-" EXCEPT H2/02 ANALYZER MOOE SWITCH PUMP *P2A STANDBY WHERE A DIFFERENT PREFIX IS SHOWN. AN ASTERISK<*l WILL REPLACE THE OASHH IN THE PREFIX FOR INSTRUMENT ANO EQUIPMENT WHICH ARE PART OF NUCLEAR SAFETY FEATURES SYSTEM.

2. SEE LSK-27-!'l FOR LOSS OF COOLANT ACCIDENT ISOLATION SIGNAL LOGIC DEVELOPMENT.

3. LOGIC FOR H2/02 ANALYZER PUMP *P2A !S SHOWN. LOGIC FOR PUMP *P2B IS SIMILAR.

4. ASSOCIATED EQUIPMENT NUMBERS:

DIV! I DIV !I

• P2A *P2B

• SOV64A *SOV648 SW-SR

• SOV65A *SOV65B H2/02 ANALYZER

• FS1001A *FS1001B PUMP *P2A STOP

~~

• PNL66A ~

!.E.!:il...U0 !flll.Lill

5. ADDITIONAL LOGIC FOR MANUAL ISOLATION SWITCH SHOWN ON LSK-33-2H. SOURCE:LSK-33-2A REV. 16

6. ADDITIONAL LOGIC FOR LOCA OVERRIDE SWITCH SHOWN ON LSK-33-2H.

7. LOGIC FOR MOISTURE ANAL YZER-MIT72A IS SHOWN. LOGIC FOR MOISTURE ANALYZERS

• PNL73A FIGURE 6.2-38 MIT72B,C.D,E & F IS SIMILAR.

CONTAINMENT ATMOSPHERE

8. MOISTURE ANAL YZERS-MIT72A,C & E ARE RECORDED ON A THREE PEN RECORDER ON PANEL HJ3-P873. ANAL YZERS-MIT72B,D & F SHARE A THREE PEN RECORDER ON PANEL H13-P875. MONITORING SYSTEM LOGIC DIAGRAM SHEET 1 OF 12

'l. #SUPPLIED BY MEGGITT SAFETY SYSTEMS INC. SETPOINTS SHOWN ON LOGIC DIAGRAMS ARE FOR LOGIC

10. DIV II SWITCH LOCATED AT *PNL73B. CLARIFICATION ONLY ANO MAY BE ONLY APPROXIMATIONS NINE MILE POINT-UNIT 2

11. LOCAL PUMP SWITCH MUST BE HELD IN THE START" POSITION TO MAINTAIN PUMP OPERATION. OF THE ACTUAL PROCESS SETPOINT. REFER TO SETPOINT DATA SHEETS FOR ACTUAL PROCESS SETPOINTS.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 15 OCTOBER 2002 SOURCE MONITOR CONDITION CONTROL ACT! OH RESULTANT llONI TOR SUPPRESS I ON POOL WATER LEVEL SW-SR Cliff All 'MrlilTUllMi INSTR ISOL V >------------t..,.___"' '-*s_o'(__ f;.W -so_w_SA_DPEN _ _, PBJl SW-SR Cliff All MONITUllHG INSTR 1511. Y ,__ _ _ _ _ _ _ _ _ _,___ __,""1 '-*_suvs_m_"SOV6 __5A_a.tJSE _ _, PB73 NOTES: I. ALL mu I PIENT ANO INSTRUMENT NUMBERS TO BE PREF I XEO llTH *2c1s-* EXCEPT WHERE A 0 I FFERENT PREFIX IS SHOWN. AN ASTER I SK (*) II LL REPLACE THE DASH (*) IN THE PREFIX FOR INSTRUMENTS ANO EQUIPMENT WHICH ARE A PART OF NUCLEAR SAFETY FEATURES SYSTEMS.

2. LOGIC FOR DIV I CONTAINMENT ATMOSPHERE MONITORING INSTRUMENT ISOLATION VALVES *SOV&4A AHO 0 SOY65A ARE SHDWJ(, *LOGIC FOR OIY II CDllTAINllENT ATMOSPHERE MOH fl OR IHG INSTRUMENT ISOLA Tl ON VALVES *!ovs*e AND *sovsse.

IS SllllLAR.

3. ASSOCIATED EQUIPMENT NARK" NUMBER'S: (ANO RELATED CONTROL ROOM PANEL HO.)

DIV I (P873) DIV IT (P875)

• sovs*A *sovs*e

• SOY65A *SOV658 SOURCE: 121 77-LSK-33-2B REV.12 FI GURE 6. 2- 38 CONTAINMENT ATMOSPHERE MONITORING SYSTEM LOGIC DIAGRAM SHEET 2 OF 12

) NOTE: NIAGARA MOHAWK POWER CORP. FOR LATEST SET POINT INFORMATION SEE SET POINT DATA SHEET NINE MILE POINT-UNIT 2 ~UPDATED SAFETY ANALYSIS REPORT U AR REVISION 0 APRIL 1989 SOURCE MONITOR CONOITION PRIMARY CONTAINMENT OXYGEN CONCENTRATION HIGH CONTAINMENT OXYGEN <RANGE 0 TO 10%1 PRIMARY CONTAINMENT OXYGEN CONCENTRATION HIGH CONTAINMENT OXYGEN <RANGE 0 TO 10%1 PRIMARY CONTAINMENT HYDROGEN CONCENTRATION HIGH CONTAINMENT HYDROGEN !RANGE 0 TO 30%1 PRIMARY CONTAINMENT HYDROGEN CONCENTRATION HIGH CONTAINMENT HYDROGEN <RANGE 0 TO 30%! NOTES: !. ALL INSTRUMENT ANO EQUIPMENT NUMBERS TO BE PREFIXED WITH "2CMS-" EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN. AN ASTERISK<*I WILL REPLACE THE DASHH JN THE PREFIX FOR INSTRUMENT AND EQUIPMENT WHICH ARE PART OF NUCLEAR SAFETY FEATURES SYSTEM.

2. THREE PEN RECORDER SHARED WITH *PR2B & *PR!B SHOWN ON LSK-33-20 & 33-2E.

3. #-SUPPLIED BY MEGGITT SAFETY SYSTEM INC.

4. COMMON ANNUNCIATOR FOR DIV I PRIMARY CONTAINMENT OXYGEN/HYDROGEN CONCENTRATION HIGH.

5. COMMON ANNUNCIATOR FOR DIV II PRIMARY CONTAINMENT OXYGEN/HYDROGEN CONCENTRATION HIGH.

6. THREE PEN RECORDER WITH TWO SPARES.

SOURCE:LSK-33-2C REV. 16 FIGURE 6.2-38 CONTAINMENT ATMOSPHERE MONITORING SYSTEM LOGIC DIAGRAM SHEET 3 OF 12 SETPOINTS SHOWN ON LOGIC DIAGRAMS ARE FOR LOGIC CLARIFICATION ONLY ANO MAY BE ONLY APPROXIMATIONS NINE MILE POINT-UNIT 2 OF THE ACTUAL PROCESS SETPOINT. REFER TO SETPOINT DATA SHEETS FOR ACTUAL PROCESS SETPO!NTS. UPDATED SAFETY ANALYSIS REPORT USAR REVISION 15 OCTOBER 2002 SOURCE MONITOR CONOIT!ON CONTROL ACTION RESULTANT CONTAINMENT ORYWELL LOOP A PRESSURE <RANGE 0 TO 150 PSIG> NOTE 7 CONTAINMENT ORYWELL LOOP A PRESSURE CRANGE 0 TO 150 PSIGl NOTE 5 NOTE 7 CYCLE Tl MER CMS SAMPL! NG 6 SYSTEM STEP # l SUPPRESSION CHAMBER SW CMS DIV I LSK-33-2J PRESSURE SAMPLE PATH SELECTOR <RANGE 0 TO 150 PSIGl AUTO NOTE 7 NOTE 6 SW CMS DIV I SAMPLE PATH SELECTOR SUPPRESSION CHAMBER OFF PRESSURE CYCLE Tl MER <RANGE 0 TO 150 PSIG> CMS SAMPL! NG NOTE 7 SYSTEM STEP # 2 SUPPRESSION CHAMBER PRESSURE <RANGE 0-5 PS!Gl CYCLE Tl MER SUPPRESSION POOL CMS SAMPL! NG WIDE RANGE LEVEL SYSTEM STEP # 3 <RANGE 192' TO 217'l SUPPRESSION POOL WIDE RANGE LEVEL <RANGE 192' TO 217') NOTES:

1. ALL INSTRUMENT ANO EQUIPMENT NUMBERS TO BE PREFIXED WITH '2CMS-' EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN. AN ASTERISK<-> WILL REPLACE THE OASHH IN THE PREFIX FOR INSTRUMENTS AND EQUIPMENT WHICH ARE PART OF NUCLEAR SAFETY FEATURES SYSTEM.

2. THREE PEN RECORDER SHARED WITH *ARGB & *PRlB SHOWN ON LSK-33-2C & 33-2E.

3. THREE PEN RECORDER SHARED BY *PT7B, *L T9B AND *TR70B ON LSK-33-2K.

4. LOGIC SHOWN FOR CMS DIV I SAMPLE PATH SELECTOR.

LOGIC FOR CMS DIV lI SAMPLE PATH SELECTOR SIMILAR.

5. STEP l SHOWN. OTHER STEPS SIMILAR.

6. SEE NOTE 2 ON LSK-33-2J FOR FURTHER EXPLANATION OF SWITCH FUNCTION.

7. A RED LINE ON RECORDERS & INDICATORS WILL BE PROVIDED AT 45 PSIG.

SOURCE: LSK-33-20 REV.16 FIGURE 6.2-38 CONTAINMENT ATMOSPHERE MONITORING SYSTEM LOGIC DIAGRAM SHEET 4 OF 12 SETPOINTS SHOWN ON LOGIC DIAGRAMS ARE FOR LOGIC NIAGARA MOHAWK POWER CORP. CLARIFICATION ONLY ANO MAY BE ONLY APPROXIMATIONS OF THE ACTUAL PROCESS SETPOINT. REFER TO SETPOINT NINE MILE POINT-UNIT 2 DATA SHEETS FOR ACTUAL PROCESS SETPOINTS. UPDATED SAFETY ANALYSIS REPORT USAA REVISION 5 SOUflCE MONITOR CONOITJON SUPPRESSION POOL A LEVEL CONTAINMENT DRYWELL LOOP A PRESS EL zq3' H5 TO C+l5 PSlG DRYWELL PRESSl..RE HIGH I HlGH CONTAINMENT DRYWELL LOOP B PRESS EL zq3' M5 TO (+l5 PSlG DRYWELL PRESSURE HIGH I HlGH CONTMT OW PRESSURE ANG 12.S TO 17 PSJA 5UPPR Cf'llllM0ER PffESSURE RI<<> 12.5 TO 17 PSIA NlTES1

1. ALL l..STRUHENT AHO EQUIPl'ENT NUMBERS TO BE PftfflXED WlTH "2CHS-' EXCEPT wt£flE A DfFFEl¥HJ PJiEFIX IS SH0WH. AN ASTEftlSI<<*) WH.L flEPLACE THE DASH<-> JN THE MFIX FDA JNS1'1'U£NTS AND EClUfPMENT WHICH ARE PAAT OF NUCLEAR SAFETY FEATI.R;:S SYSTEM.

2. THREE PEN RECORDER SHARED WITH *ARSB & *PR2B SHOWN ON LSK-33-2C &. 33-20.

3. ALL EOOlf'MENT LOCATED ON DIV I PAl£L ~ ANO DIV JI PAl£L ~ UNLESS OTHERWISE SPECIFIED.

SOURCE: LSK-33-2E REV.l FIGURE 6.2-38 CONTAINMENT ATMOSPHERE MONITORING SYSTEM LOGIC DIAGRAM SHEET 5 OF 12 SETPOINTS SHOWN ON LOGIC DIAGRAMS ARE FDR LOGlC NIAGARA t<lHAWK POWER CORP. CLAfUFICATION ONLY ANO MAY BE ONLY APPROXIMATIONS OF THE ACTUAL PROCESS SETPOlNT. REFER TO SETPOINT NINE MILE POINT-UNIT 2 DATA SHEETS FOR ACTUAL PROCESS SETPOINTS. UPDATED SAFETY ANALYSIS REPORT USM REVISION 3 COtGlllON MCltlTOR NOTE 4 Pl13 cP8'15> OAYWELL ARE:A TEMPE:RAll.N: NOTIES '5 & 6 173314 '87Sl<<M> P813 1813315! CP875S HIGIESI HEASURf:Q t87S115S OAYWELL IE:MP NOTE 1 CMSICl3 HIGIESI HEASUAE:O tCHSTCl41

• ISi<< <<CMSICl5>

OAYWELL TEMP 151 ptqe HIGH <<CMSICI&> d 'jJqlJ P873 CP875S LOW:SI MEASUAE:Q OAYWELL 1£MP NOllE'St 1.. ALL INSTRUMENT AIG EQUIPMENT N.t&:RS 10 1£ PflEFIX£0 VllH "2CMS*-£XCEIPI WHEAE: A OIJJA£NT IPA£JIX IS SHOWN.. M ASlRISIC f*I VIU. A£Pl.AC£ IHE GASH C*J IN THE PRE:FIX FOR EQUIPMErtl OR INSIRllJMENIS MHICH Mf: A PMI 06 NUCLEAR SAF'EIY FEATURES SYSTEM.. 2.AOOITIONAL INPulS ~ROH ALL OllER OflYVEU. 1MPt:RAll.llA£ LEHENTS IN EACH AE:SH:CllVE: OIYISION. &.. ASSOCIATED EClUIPMENI MAflC IU&RSt: ORYVILL - OIY..I

• Tl191 80P CHPIA Pl ERF'

~IA PT 01¥..11

• 11153 CHPIA PT EAF' C. .TA Pl

3. UIGIC FOR OIY..I ORWELL TE~RAIURE: IOtllORING IS SIGWN+ LOGIC FOR 01¥.11 *TUR *1115*

OAYWILL. OIY..I & II ~SSION OllAl&A IE.... tOtlTOAING IS SIMILAR. *TSHXl51 CMSICIJ *ISHX15J CMSTtl*

4. IE:MP A£COAOE:AS M£ THAt:E: PE:rt At:COAOEflS VI TH lftPUIS A$ '°'-'-OVS; *Tlt3' *111*5

• Tl131 *Tll46 OIY+I 01v~11 *TSHXlll CMSICl5 *ISHXl*! CMSTCll

• IAX131 *llAY131 *IAZ131 *IAX1~8 ellAYl41 *IAZ14'8 ORYVILL *T£111 CHSIAll CMSIAI* *1£111 CMSTAll CMSIAU1 elEllt *l1<<M *IEll1 *IEU6 *1UCI *IE122 *T1U CMSl"82 CMSIAIM *lU7 CMSTAU CMSIAUI

• IE1R *llElft *IE1R *IE111 *TIEla *IE123 *T113 CM51"93 CMSIAlll *1118 CMSTAlt tMSTAUq

• 11113 *IElll *TEI" *IEU8 *11111 *IEl241 *TEl<<M CHSI,_.. OISIAlll *1£114' CMSTA13 CMSIA121 5.. THE AVERMlE VALUES Of' YMIOUS TEMP£RATURE POINTS - c~o 8Y THE PPC CCM'UTER *T115 CMSIA85 CMSIAU1 *1128 CMSTA14 CMSIAt21 AS F'OLLOVSi *TUI& CMSl.AI& OISIAl13 *1111 CMSTA1'5 tMSTAIZl 01v..1 OIY+ll OIY..I & II *T117 CMS1ae1 CM$1All* *1111 CM$TAl6 CMSIA123

• T£111 CMSlaea CMSIAl1'5 *1£123 CMSTA11 CMSIAIZ*

OAYVIELL CMST.-1 CMST"82 CMSIUl5 *TEIM CMSI AM CMSI AU& *1£124 CMSTAJI CMSIAIH ..,...SSION CIW&R CMSIUl3 CMSTUl4 SOURCE: LSK-33*02-F REV+18 FIGURE 6.2*38 CONTAINMENT ATMOSPHERE MONI TORINO SYSTEM LOGIC DIAGRAM SHEET 6 OF 12 SETPOINTS SHOWN ON LOGIC DIAGRAMS ARE FOR LOGIC CLARIFICATION ONLY ANO MAY BE ONLY APPROXIMATIONS OF THE ACTUAL PROCESS SETPOINT.REFER TO SETPOINT NINE MILE POINT-UNIT 2 DATA SHEETS FOR ACTUAL PROCESS SETPOINTS. UPDATED SAFETY ANALYSIS REPORT OCTOIER L USM REVISION 25 282~ 33-02-F.dgn 9/27/2022 10:11 :32 AM SOURCE MONITOR CONDITION CONTROL ACTION MONITOR P873 IP875) CONT ATM MONITORING H2/02 ANALYZER 2CMS*P2A !NOP NOTE 3 PB73 CPB75l CONT ATM MONITORING INSTR !SOL V

• SOV64A INOPERABLE LOGIC FOR *SOV65A PB73 CPB75l CONT ATM MONITORING ORYWELL SAMPLE V

• SOV23A INOPERABLE LOGIC FOR

• SOV23C,E PB73 CP875l CONT ATM MONITORING ORYWELL SAMPLE V

• SOV24A INOPERABLE LOGIC FOR

• SOV24C B7330!

187510!) NOTE 2 CMSBC05 CONT ATM MONITORING CCMSBC06l DRYWELL SAMPLE V

• SOV26A LOGIC FOR

• SOV26C CONT ATM MONITORING DRYWELL SAMPLE V

• SOV32A LOGIC FOR

• SOV33A CONT ATM MONITORING DRYWELL SAMPLE V

• SDV34A CONTAINMENT ATMOSPHERE PRIMARY CONTAINMENT ATM MONITORING DIVISIDN I LOGIC FOR MON DIV.I

• SOV35A BYPASS/INOPERABLE MANUALLY OUT OF SERVICE P873 A PB73 LOSS OF COOLANT CP875l ACCIDENT ISOLATION SIGNAL DIV.I .....  !!75)~

w NOTE 5 ' P602 CONT ATM MONITORING OW !SOL VLV *SOV24A ~ NOT FULLY CLOSED SEE NOTE 7 NOTES: !. ALL INSTRUMENT ANO EQUIPMENT NUMBERS TO BE PREFIXED WITH "2CMS-" EXCEPT 6. ASSOCIATED EQUIPMENT MARK NUMBERS: WHERE A DIFFERENT PREFIX IS SHOWN. AN ASTERISK <*>WILL REPLACE THE DASH DIV.I DIV.II H IN THE PREFIX FOR EQUIPMENT OR INSTRUMENTS WHICH ARE A PART OF NUCLEAR SAFETY FEATURES SYSTEM. *P2A *SOV26A *P2B *SOV268

• SOV23A *SOV26C *SOV23B *SOV26D

2. COMMON BYPASS INOPERABLE ANNUNCIATION FDR ALL DIV.I CONTAINMENT ATMOSPHERE *SOV23C *SOV32A *SOV23D *SOV328 MONITORING H2/02 ANALYZER, PUMPS, SAMPLING VALVES AND PRIMARY CONTAINMENT *SOV23E *SOV33A *SOV23F *SOV33B ISOLATION VALVES. SEE ASSOCIATED EQUIPMENT MARK NUMBERS. *SOV24A *SOV34A *SOV24B *SOV34B

3. DIVISION I INOPERABLE LOGIC IS SHOWN. DIV.II IS SIMILAR. SEE NOTE 6. *SOV24C *SOV35A *SOV24D *SOV35B

4. SEE LSK-27-19 FOR LOSS OF COOLANT ACCIDENT ISOLATION SIGNAL LOGIC DEVELOPMENT. *SOV64A *SOV64B

• SOV65A *SOV65B

5. LOGIC FOR CONTAINMENT ATMOSPHERE MONITORING ORYWELL ISOLATION VALVE *SOV24A OFF-NORMAL STATUS IS DESCRIBED. LOGIC FOR ALL CONTAINMENT ATMOSPHERE 7. THE OFF-NORMAL STATUS DISPLAY SYSTEM HAS BEEN MONITORING ORYWELL AND SUPPRESSION CHAMBER ISOLATION VALVES OFF NORMAL ABANDONED IN PLACE. SOURCE: LSK- 33-2G STATUS IS SIMILAR. SEE NOTE 3 ON LSK-33-2M AND NOTE 4 ON LSK-33-2H FOR ASSOCIATED VALVE NUMBERS. FIGURE 6.2-38 CONTAINMENT ATMOSPHERE MONITORING SYSTEM LOGIC DIAGRAM SHEET 7 OF 12 SETPOINTS SHOWN ON LOGIC DIAGRAMS ARE FOR LOGIC NIAGARA MOHAWK POWER CORP.

CLARIFICATION ONLY ANO MAY BE ONLY APPROXIMATIONS OF THE ACTUAL PROCESS SETPOINT. REFER TO SETPOINT NINE MILE POINT-UNIT 2 DATA SHEETS FOR ACTUAL PROCESS SETPOINTS. UPDATED SAFETY ANALYSIS REPORT USAR REVISION 13 OCTOBER 2000 SOURCE CONDITION CONTROL ACTION RESULTANT MONITOR SW-SR CMS PR! CONTMT !SOL VALVE *SOV32A OPEN CMS SAMPLING SYSTEM STEP # 1 LSK-33-2J STEP # 3 OR STEP # 5 CMS PR! CONTMT SW-SR CMS PR! CONTMT !SOL VLV *SOV32A !SOL VALVE *SOV32A ENERGIZE TO OPEN AUTO SW-SR CMS PR! CONTMT !SOL VAL VE *SOV32A CLOSE SW-PB CMS PR! CONTMT OIV I MANUAL ISOLATION RESET P602 SW-PB CMS PR! CONTMT OIV I MANUAL ISOLATION ISOLATE CMS OIV I SW- lKEYLOCKl LOCA OVERRIDE LOCA OVERRIDE ACTUATED OVERRIDE LOSS OF COOLANT ACCIDENT ISOLATION SrGNAL DIV I CMS PR! CONTMT SW- lKEYLOCKl !SOL VLV *SOV32A LOCA OVERRIDE OE -ENERGIZE TO CLOSE RESET P873 ~0 LSK-33-2M ~0 LSK-33-2M NOTES:

1. ALL INSTRUMENT AND EQUIPMENT NUMBERS TO BE PREFIXED WITH '2CMS-' EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN. AN ASTERISKl-> WILL REPLACE THE DASH<-> IN THE PREFIX FOR INSTRUMENTS ANO EQUIPMENT WHICH ARE PART OF NUCLEAR SAFETY FEATURES SYSTEM.

2. SEE LSK-27-19 FOR LOSS OF COOLANT ACCIDENT ISOLATION SIGNAL LOGIC DEVELOPMENT.

3. LOGIC FOR CMS DRYWELL ISOLATION VALVE *SOV32A rs SHOWN. LOGIC FOR *SOV32B, *SOV35A ANO *SOV35B IS SIMILAR.

4. ASSOCIATED EQUIPMENT NUMBERS:

ERF ERF OPERATING DIV I CMPTR PT DIV II CMPTR PT ~

• SOV32A CMSZC114 *SOV32B CMSZCl15 1,2 OR 3

• SOV35A CMSZC122 *SOV35B CMSZC123 4 SOURCE: LSK-33-2H REV.15 FIGURE 6.2-38 CONTAINMENT ATMOSPHERE MONITORING SYSTEM LOGIC DIAGRAM SHEET 8 OF 12 SETPOINTS SHOWN ON LOGIC DIAGRAMS ARE FOR LOGIC NIAGARA MOHAWK POWER CORP.

CLARIFICATION ONLY AND MAY BE ONLY APPROXIMATIONS OF THE ACTUAL PROCESS SETPOINT. REFER TO SETPOINT NINE MILE POINT-UNIT 2 DATA SHEETS FOR ACTUAL PROCESS SETPOINTS. UPDATED SAFETY ANALYSIS REPORT USAR REVISION 5 SOURCE CONDITION CONTROL ACTION RESULTANT MONITOR SW-SR CMS DRYWELL SAMPLING VALVE *SOV23A OPEN P873 (P875J CMS DRYWELL SW-SR CMS DRYWELL SAMPLING VALVE *SOV23A SAMPLING VALVE *SOV23A ENERGIZE TO OPEN AUTO P873 P873 <P875> <P875l NOTE 5 CYCLE TIMER 6 LSK-33-2D CMS SAMPLING SYSTEM STEP # 1 2 LSK-33-2H CMS DRYWELL SAMPLING VALVE *SOV23A SW-SR CMS DRYWELL DE-ENERGIZE TO CLOSE SAMPLING VALVE *SOV23A P873 CLOSE P873 (P875J (P875J SW- CMS DIV I SAMPLE PATH SELECTOR CMSBC07 STEP 1 P873 (P875J NOTE 4 NOTE 6 NOTE 2 NOTES:

1. ALL INSTRUMENT AND EQUIPMENT NUMBERS TO BE PREFIXED WITH '2CMS-' EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN. AN ASTERISK(*) WILL REPLACE THE DASHH IN THE PREFIX FOR INSTRUMENTS AND EQUIPMENT WHICH ARE PART OF NUCLEAR SAFETY FEATURES SYSTEM.

2. SEVEN POS!TlON SELECTOR SWITCH. LOGIC FOR STEP 1 IS SHOWN. LOGIC FOR STEP 2 ANO 3 IS SIMILAR. ADDITIONAL LOGICS FOR THIS SWITCH SHOWN ON LSK-33-2D & 33-2H.

3. LOGIC FOR CMS DRYWELL SAMPLING VALVE *SOV23A IS SHOWN. LOGIC FOR OTHER ORYWELL SAMPLING VALVES LISTED BELOW IS SIMILAR.

4. COMPUTER POINT FOR DIV I STEP ONE IS SHOWN. SEE ASSOCIATED EQUIPMENT LIST FOR CORRESPONDING STEPS AND COMPUTER POINTS,

5. ASSOCIATED EQUIPMENT NUMBERS:

SAMPLING VALVES COMPUTER POINTS STEP DIV I DIV II DIV I DIV II

• SOV23A *SOV23B CMSBC07 CMSBCl2 2 *SOV23C *SOV230 CMSBC0CJ CMSBC14

• SOV23E *SOV23F CMSBCll CMSBCl6

6. STEP 4 IS NOT USED IN THE AUTOMATIC MOOE. STEP 4 IS USED IN THE MANUAL SELECTION MODE, BUT ONLY OPERATES 2CMS*SOV35A, B.

SOURCE: LSK-33-2J REV.16 FIGURE 6.2-38 CONTAINMENT ATMOSPHERE MONITORING SYSTEM LOGIC DIAGRAM SHEET q OF 12 SETPOINTS SHOWN ON LOGIC DIAGRAMS ARE FOR LOGIC NIAGARA MOHAWK POWER CORP. CLARIFICATION ONLY AND MAY BE ONLY APPROXIMATIONS OF THE ACTUAL PROCESS SETPOINT. REFER TO SETPOINT NINE MILE POINT-UNIT 2 DATA SHEETS FOR ACTUAL PROCESS SETPOINTS. UPDATED SAFETY ANALYSIS REPORT USAR REVISION 5 OCTOBER 199: SOURCE MONITOR CONOITJON CONTROL ACTION MONITOR SW-SELECTOR NOTES 5,9,10 DISPLAY SUPPRESSION POOL *TE53B 2CES*PNL405 WATER TEMPERATURE HIGH > 85°F SW-SELECTOR DISPLAY SUPPRESSION POOL *TE55B 2CES*PNL405 WATER TEMPERATURE RANGE 50° F TO 250° F SW-SELECTOR NOTE 2 DISPLAY *HJS172

• TE54B P601 SW-SELECTOR DISPLAY *HJS!72

• TE55B P601 601550 SUPPRESSION POOL NOTE 7 WATER TEMPERATURE RANGE 50° F TO 250° F SUPPRESSION POOL CMSTC22 WATER TEMPERATURE NOTE 7 HIGH/HIGH > 10!°F SUPPRESSION POOL WATER TEMPERATURE RANGE 50° F TO 250° F SW-SELECTOR NOTE 4 DISPLAY *HJS174 NOTE 8 HE678 P601 SW-SELECTOR DISPLAY *HJS174

• TE688 P601

9. *TE50A THRU *TE598 ARE DUAL ELEMENTS ANO THE SPARE ELEMENTS OF THE FOLLOWING *TE'S WILL BE USED FOR REMOTE SHUTDOWN INDICATION.

ASSOCIATED EQUIPMENT LIST: OIV.I OIV.II DIV.I DIV.II NOTES: 2RSS*Tl103 2RSS*Tl104 2RSSlllTll03 2RSS*Tll04 I. ALL INSTRUMENT AND EQUIPMENT NUMBERS TO BE PREFIXED WITH 2CMS-" EXCEPT 7. ASSOCIATED EQUIPMENT LIST <COMPUTER POINTS IN PARENTHESIS>: lllTE50A *TE51B-NOTE 12 HE56A lllTE578 WHERE A DIFFERENT PREFIX IS SHOWN. AN ASTERISK <*>WILL REPLACE THE DASH NORMAL OPERATION *TE52A *TE538 *TE58A l!tTE5'lB H IN THE PREFIX FOR EQUIPMENT OR INSTRUMENTS WHICH ARE A PART OF *TE54A *TE558 NUCLEAR SAFETY FEATURES SYSTEM. DIV.I DIV.II WINDOW NO. INSTALLED SPARES

10. SEL SW SELECTS ONE OF FIVE TEMP ELEMENTS FOR COMMON DSPL ON HE50A CCMSTC07> *TE508 CCMSTCl7) 601560 *TE50C *TE500 2RSS*Tll04. LOGIC IS SHOWN FOR *TE53B AND *TE55B.LOGIC FOR

2. SELECTOR SWITCH SELECTS ONE OF TEN TEMPERATURE ELEMENTS FOR COMMON DISPLAY ON *TE51A <CMSTC08> HE51D ICMSTCl8) 601550 *TE51C *TE51D-NOTE 12 lllTE518, *TE578 ANO *TE5'l8 IS SIMILAR.

• Tl172. LOGIC FOR *TE54B AND *TE55B POSITIONS IS SHOWN. LOGIC FOR *TE508, *TE52A <CMSTC09> *TE528 <CMSTC19) 601560 *TE52C *TE520

• TE510, *TE52B, lllTE538 AND HE56B THROUGH *TE59B INCLUSIVE IS SIMILAR. *TE53A CCMSTC101 *TE538 ICMSTC201 601550 HE53C *TE530 11. CMSTU100 IS THE CMPTR COMPOSED AVG SUPPRESSION POOL HE54A <CMSTClll *TE548 ICMSTC2!) 601560 *TE54C HE540 WATER TEMPERATURE.

HE55A <CMSTC!2> *TE558 ICMSTC22l 601550 *TE55C *TE550 12. THE <+>SIDE OF DUAL ELEMENT 2CMS*TE518 HAS FAILED. HE56A <CMSTC!3l HE568 ICMSTC23l 601560 *TE56C *TE560 THE H SIDE OF DUAL ELEMENT 2CMS*TE51B IS USEO FOR

3. TEMPERATURE RECORDER APPLICABLE TO *TE67B, HE688, HE698 AND *TE708 ONLY. *TR67B

• TE57A <CMSTC14> HE57B CCMSTC241 601550 *TE57C HE570 REMOTE SHUTDOWN INDICATION ONLY. THE ( + l SIDE OF DUAL lllTR68B ANO *TR698 SHARE ONE 3 PEN RECORDER, *TR70B SHARES WITH *LR98 & *PR7B ON LSK-33-20.

LOGIC FOR *TE67B IS SHOWN. LOGIC FOR BAL OF POST ACCIDENT MONITORING TEMPERATURE *TE58A CCMSTC151 *TE5BB <CMSTC25l 601560 HE58C *TE580 ELEMENT 2CMSHE51D IS USED FOR CONTROL ROOM INDICATION CHANNELS IS SIMILAR. SEE NOTE 8. *TE5'lA CCMSTC16) HE5'l8 ICMSTC26> 601550 *TE5'lC *TE5'l0 AND ALARM. THE H SIDE OF DUAL ELEMENT 2CMSlllTE51D IS

• Tl!71 *Tl!72 SPARE.

4. SELECTOR SWITCH SELECTS ONE OF FOUR TEMPERATURE ELEMENTS FOR COMMON DISPLAY ON *HJS171 *HJS172

• Tll74, DIV.II IS SHOWN. LOGIC FOR *TE67B AND HE68B ARE SHOWN. LOGIC FOR

• TE69B AND *TE708 IS SIMILAR. 8. POST ACCIOENT MONITORING:

ERF ERF

5. LOGIC FOR DIV.!! INSTRUMENTS IS SHOWN. LOGIC FOR DIV.I IS SIMILAR.

OIV.I CMPTR PT DIV.II CMPTRPT

6. TEMPERATURE RECORDERS APPLICABLE TD DIV.!! TEMPERATURE ELEMENTS ONLY.

• TE67A CMSTA100 *TE67B CMSTA101 *TR678 ASSOCIATED EQUIPMENT LIST: *TE68A CMSTA102 *TE68B CMSTA103 lllTR68B

• TRW170 *TRX170 *TRY170 *TRZ170 *TE69A CMSTA104 *TE698 CMSTA105 lllTR698

• TE50B HE538 lllTE56B lllTE59B HE70A CMSTA106 *TE70B CMSTA107 lllTR708

• TE5!0 <NOTE 12) *TE54B HE57B SPARE *Tl175 HI!74 SPARE *HJS175 11tHJS174

• TE52B *TE558 HE58B SOURCE:LSK-33-2K REV. 16 FIGURE 6.2-38 CONTAINMENT ATMOSPHERE MONITORING SYSTEM LOGIC DIAGRAM SHEET 1121 OF 12 SETPOINTS SHOWN ON LOGIC DIAGRAMS ARE FOR LOGIC CLARIFICATION ONLY AND MAY BE ONLY APPROXIMATIONS OF THE ACTUAL PROCESS SETPOINT. REFER TO SETPOINT NINE MILE POINT-UNIT 2 DATA SHEETS FOR ACTUAL PROCESS SETPOINTS. UPDATED SAFETY ANALYSIS REPORT USAA REVISION 15 OCTOBER 2002

SOl.RCE MONITOR CONDITION MONITOR RADIATION MONITOR TROUBLE/MANUAL OUT OF SVCE/RAl)-l ST ATUS ORYWELL ATMOSPHERE TRAIN A LEAKAGE RADN-RAOO At() MONITOR STATUS DRYWELL ATMOSPHERE

• RUZ10A TRAIN A LEAKAGE

.___<AG_>_, PB80 GASEOUS RADIATION LEVEL MICRO-PROCESSOR ORYWELL ATMOSPHERE TRAIN A LEAKAGE PARTICULATE RADN LEVEL DRYWELL ATMOSPHERE A TRAIN A LEAKAGE PARTICULATE RADN ALERT DRYWELL ATMOSPHERE NJTES1 TRAIN A LEAKAGE PARTICULATE RADN HIGH NOTE 4

1. ALL INSTRUMENl AND EQUIPMENT NUMBERS TO BE PREFIXED WITH '2CMS-' PROCESS AIRBORNE EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN. A RADN MON ACTIVATED

2. # SIJ>PLIED BY DIGITAL RADN MON VENDOR. ORYWELL ATMOSPHERE

3. RMS COMPUTER GENERATED SIGNAL. TRAIN A LEAKAGE

4. SEE THE FOLLOWING LSK'S FtR ADDITIONAL INPUTS1 GASEOOS RADIATION ALERT 22-30, 22-55,. 22-IN,S, 22-q,,JH,27-15G 851254

!5. LOGIC FOR 2CMS*RE19A lS SHOWN. LOGIC FOR 2CMS*RE111JB IS SIMlLAR. ORYWELL ATMOSPHERE c RMsRC76

6. 2 PEN RECORDER. TRAIN A LEAKAGE NOTE 4 7, LOOP COMHl.MICATION. GASEOUS RADIATION HIGH

8. RMS COMPUTER GEl£RATEO SIGNAL LOCATED ON CONSOLES. COMMOO FOR ALL RADIATION MONITORS.

q,, ASSOCIATED EQUIPMENT NUM3ERS1 DETECTOR FIELD COOROL ROOM INDICATORS RECORDERS ERF COMPUTER SERVICE GAS PARTICULATE MICRO-PROCESSOR MICRO-PROCESSOR GAS PART GAS PART GAS PART TRAIN A RfxiSA REY10A RUW19A RUZ10A RIXl0A RIYlBA RRX10A RRY10A CMSRA100 CMSRA1B2 TRAIN B REXlllJB REYIBB RUWlllJB RUZ10B RIXll!IB RIY10B RRX10B RRYlBB CMSRAlBI CMSRA103

10. RADIATil)-l MONITOR TROUBLE/MANUAL OUT OF SERVICEIRADN STATUS Cl)-lSISTS OF THE FOLLOWll'{; CONDITIONS:

I. TROt.BLE II. MANUAL OUT OF SERVICE III. RADN STATUS

1. DETECTOR FAlLURE/SATURATil)-l l. TEST MOOE I. HIGH RAOO LEVEL

2. LOSS OF SIGNAL COMl'IJNJCATION 2. CALIBRATE MOOE 2. ALERT RADN LEVEL

3. POWER FAILURE !HIGH & LOW VOL TAGEI 3. MONITOR OFF 3. HIGH RATE CF

.C. CHECK SOl.RCE FAILmE RADN INCREASE

5. BACKGROOND CHECK FAILlflE

6. PUMP FAILURE

7. FILTER t£CHANISM STEP FAILURE

8. HIGH/LOW FLOW q, HEAT TRACE FAILURE SOURCE: LSK-33-2L REV.14

n. 2CMS*CA810BIBY> lS LOCATION FOR 2CMS*REX/REY /RUWIBBIBYl.

FIGURE 6.2-38 CONTAINMENT ATMOSPHERE MONITORING SYSTEM LOGIC DIAGRAM SHEET 11 OF 12 SETPOINTS SHOWN ON LOGIC DIAGRAMS ARE FOR LOGIC NIAGARA 1'1JHAWK POWER CORP. CLARIFICATION ONLY AND MAY BE ONLY APPROXIMATIONS OF THE ACTUAL PROCESS SETPOINT. REFER TO SETPOINT NINE MILE POINT-UNIT 2 DATA SHEETS FOR ACTUAL PROCESS SETPOINTS. UPDATED SAFETY ANALYSIS REPORT USAR REVlSION 3 OCTOBER 19 1 Slllllt:t COllDITlllll Clllff'llDL ACTION RESUCTA!IT IOIUTOR ERF CllSZCI 00 LOCA SIGNAL NOTE 3 RESET OR LSK*33-2H OVERRIDDEN SI-SR CMS PRI CllS PRI CONTIIT CONTIIT ISOL V

• SOY24A OPEN I SOL VAL VE 0 SOV24A fm CMS PR I CONTMT ENERGIZE TO OPEN Cffil)

DIV I MANUAL ISOLATION LSK-33-ZH I SOLA TE LDCA SIGNAL PRESENT ANO NOT CMS PR I CONTJCT LSK-33-ZH OVERRI ODEN ISOL VALVE *SOV24A DE-ENERGIZE TO CLOSE SI-SR CJCS PRI P873 COHTMT ISOL VALVE (~)

• SDV24A CLOSE NOTE 4 NOTES CONTD:

NOTES: 4. KEYLOCK.SllTtH. I. ALL EQUIPMENT AND INSTRUMENT NUMBERS TO BE PREFIXED llTH *2c11s-* EXCEPT 5. LOGIC FOR POST Act I DENT .SAMPLE LOOP ISOLATION VALVE (CONTMT SIDE) IHERE A DIFFERENT PREF I l IS SHOIN. AN ASTER I SK (*) 11 LL REPLACE THE .*SOV74A IS SHOWN. LOGIC FOR THE FOLLOWING VALVES IS SIMILAR. DASH(*) IN THE PREFIX FOR INSTRUMENTS' EllUIPllENT WHICH ARE PART OF *'*SDV74B TRAIN B POST ACCIDENT SAMPLE LOOP SUCTION 'TSOLATION (CONTMT SIDE) NUCLEAR SAFETY FEATURES SYSTEIS. *SDY75A TRAIN A POST ACCIDENT SAMPLE LOOP RETURN ISOLATION (COHTMT SIDE)

2. LOGIC FDR CllS PRIMARY CONTAINMENT ISOLATION VALVE *SDY24A IS SHOIH. *SOV75B TRAIN B POST ACCIDENT SAMPLE LOOP RETURN ISOLATION (CONTllT SIDE)

LOGIC FOR PRIMARY CONTAINMENT ISOLATION VALVES LISTED BELDI IS SlllLAR. *SOY76A TRAIN A POST ACCIDENT SAMPLE LOOP SUCTION I SOLA Tl ON (SAMPLE SIDE)

3. ASSOCIATED EOUIPllENT LIST: *SOV76B TRAIN B POST ACCIDENT SAMPLE LOOP SUCTION ISOLATION (SAMPLE SIOE)

ERF ERF *SOV77A TRAIN A POST ACCIDENT SAMPLE LOOP RETURN ISOLATION (SAMPLE SIDE) DI Y I CMPTR PT DIV JI cliPT'il PT *sovne TRAIN e POST ACCIDENT SAMPLE LOOP RETURN ISOLATION (SAMPL,E SIDE)

• sov 2*A CiiTICiOii *SOV248 CillCfiiT

• SOY24C CMSZC102 *SOV240 CMSZCl 03

• SOV26A CllSZCI08 *SOV26B CMSZCI 09

• sov2&c CllSZCI 10 *SOV26D CMSZCl 11

• SDV33A CMSZC112 *SDY3JB CMSZ&l 13

• SOV34A CMSZC120 *SOVJ4B CllSZ.Cl21

• soVSDA CMSZC104 *SOY61A CllUC105

• sov&oe CMSZC118 *SOY&lB CllSZC107 *SOURCE: 121 77-LSK-33-2M REV.12

• sOV62A CMSZCl 16 *SOV63A CllSZCl 17

• SOV628 CMSZCI 06 *SOV638 CMSZC119 FIGURE 6.2-38 CONTAINMENT ATMOSPHERE MONITORING SYSTEM LOGIC DIAGRAM SHEET 12 OF 12 NOTE:

) NIAGARA MOHAWK POWER CORP. FOR LATEST SET POINT INFORMATION SEE SET POINT DATA SHEET NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 0 APRIL 1989 EL. 303' *O" TO 297'*0" DRYWELL EL. 240' SUPPRESSION CHAMBER. FIGURE'.6.2-39. SCHEMATIC OF CONTAINMENT SPRAY. NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT STACKED PERFORATED PLATE HOLES 0.0~37' +/-0.010' t SUCTION FLOW STACKED-DISK STRAINER WITH A* QUARTER SEGMENT REMOVED TO ILLUSTRATE THE INTERNAL DESIGN FIGURE 6.2-39a ECCS SUCTION STRAINER NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORt LOOP A SPRAY RING EL.: 301'6" DRYWELL WALL BIOLOGICAL SHIELD SPRAY DISTRIBUTION SHOWN AT ELEVATION OF 291'*6" (% AREA SHOWN) DRYWELL WALL SIDE NOZZLE ORIENTATION FIGURE 6.2-40 TYPICAL LOOP A SPRAY COVERAGE IN DRYWELL NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 27 JULY 1986 LOOPB SPRAY RING' 303' ! f .Si'.'RAY DISTRIBUTIO.N

• VERTICAL. SHOWN AT ELEVATIONj293'

~,.DO WNW A.RD (1A AREA SHOWN)

EXTERIOR PEDESTAL .WALL*

SIDE " SIDE i . NOZZLE ORIENTATION FIGURE 6.2"-41 TYPICAL LOOP B SPRAY COVERAGE IN DRYWELL NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT A I. Ar-a..11"'\I. Al"" .. I T n"7 11 11 v -1 no~ ( SECTION AB REPRESENTS A 1A AREA OF SUPPRESSION SUPPRESSION POOL WITH SPRAY COVERAGE POOL OUTER WALL SHOWN AT ELEVATION 199.5' ELEVATION 199.5 SPRAY RING ---'---+-1t--1,__. ELEVATION 231' B SECTION CC SPRAY RING .....,_ OUTER WALL PEDESTAL NOZZLE ORIENTATION PEDESTAL WALL ELEVATION 199.5 FIGURE 6.2-42 APPROXIMATE SPRAY COVERAGE IN SUPPRESSION CHAMBER NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 28 MAY 1987 ri REACTOR SPRAY RING LOOP-B EL. 303'-0" .I ~- BIOLOGICAL Q SHIELD WALL ,.. PLATF EL. 288'-3V4' i~~r~ ~~ ~ SPRAY RING EL. 231'-0" i---------1:s. SUPPRESSION POOL SPRAY COVERAGE FIGURE 6.2-43 APPROXIMATE VOLUME COVERAGE BY CONTAINMENT SPRAYS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED FIGURE 6.2-44 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT - UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S 0 0 (\I --t CONTAINMENT SPRAY ON ~ RHR SHUTDOWN COOLING ON l() r..... lJ... (.!) lJ.J Q 0 lO w a::: <( a::: Ll.J II) 0.. 0.1 L.: l1J I- _J 0 0 a.. 0 0 ~""t---r--r....,.-r"T"M-rt-~--,.~r-T"'T"T'Tl-~T-l""""r'T"T'T'"M-t----r-........,..-r-i-T"TTf'---~-r-r--r-r"M'"H~-r----.-.-.~ ~1~ 1 1if TI ME (SECONDS) FIGURE: 6.2-45 LONG TERM STEAM BYPASS ANALYSIS: BREAK = 0.30 FT 2 BYPASS = 0.05 FT 2 . NOTE: THE ABOVE PLOT IS FOR THE PRE-EPU ANALYSIS, NMP2 POWER UPRATE - 3536 MWT WHICH ASSUMED SPRAY INITIATION AT 30 MINUTES. SUPPRESSION POOL TEMPERATURE VS TIME FOR EPU, SPRAY INITIATION IS AT 20 MINUTES. THE POOL TEMPERATURE WILL REMAIN BELOW THE DESIGN LIMIT OF 212°F. NINE MILE POINT-UNIT 2 GROSS VOi l04 UPDATED SAFETY ANALYSIS REPORT 85.JOS 14.35.59 L USAR REVISION 20 OCTOBER 2012 1.80E+08 -'r I ~ u I 1.60E+08 ~ \ .... 'J... t,I. 1.40E+08 --.:c... '\ ~ 11.ill**U.; r*- ~ l!..d.-...1- - -r -1. ~ j I I\.

> 1 .. 20E+08 - 'D

--tia > 1 ..00E+OS ..... 'u 1"111 ll"'ll 0 -- ....1.......- E t a: 8.00E+07 -- G)

• tf ***  !' .........

11 ~ _,,,,.,,,... x" f ....... 11' a:

c 6.00E+07 ____.,,.."'

a: l......ollllll' ~ 4.00E+07 - ............. 2.00E+07 O.OOE+OO ~ I I 1000 10000 100000 Tama After Accident ~sec) FIGURE: 6.2-46 RHR HEAT EXCHANGER HEAT REMOVAL RATES LONG TERM STEAM BYPASS ANALYSIS: NOTE: THE ABOVE PLOT IS FOR THE PRE-EPU ANALYSIS, BREAK = 0.3 FT 2 BYPASS = 0.05 FT 2 . WHICH ASSUMED SPRAY INITIATION AT 30 MINUTES. FOR EPU, SPRAY INITIATION IS AT 20 MINUTES. NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L r USAR REVISION 20 OCTOBER 2012 THIS FIGURE HAS BEEN DELETED. FIGURE: 6.2-46A NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L r USAR REVISION 20 OCTOBER 2012 8000 -== A. 95% FLOW TO DRYWELL CJ So/o FLOW TO WETWELL A. == A. I 6000 a:: w A. Wi c(; a:' CC I a:: 4000 A. fl) ...I ~ ...0 2000 o .......__........_________________________________________________.........._______________ -10 0 20 40 60 80 100 120 SOURCE: ES-121 DRYWELL-WETWELL PRESSURE DIFFERANCE (PSI) FIGURE 6.2-47 Nole: Th& cu"'e aeplicable to Pre-Power Uprate containment response eraluation in Section 6.2. l. I .3. CONTAINMENT SPRAY FLOW RATE The Containment Sprar Pow rate used as input lo the Power Uorale containment response eraluation has been reconciled usi11g the Technical Specification performance curres for the. NIAGARA MOHAWK POWER CORPORATION RHRpumps. NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 13 OCTOBER 2000

a. 6000 CJ w

<C a:

=

g u. (/) 4000 0 a. -I 0:---------:::--------=--------1---------L------__JL,.._______L________. 0 40 80 120 160  ! 200 240 280 SOURCE: ES-121 REACTOR -WETWELL DIFFERENTIAL PRESSURE (PSI) FIGURE 6.2-49 LOW PRESSURE CORE SPRAY Note: This curve applicable lo Pre-Power Uprate containment response e1talualion in Section 6.2.1.1.J. FLOW RATE For reconciled performance curve see Figure 6.J-4A. NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 13 OCTOBER 2000 8000

E a.

CJ a.

E 6000

')

a. a: w a. ...cc w a: it: 4000 0 IL. u a. 2000 0 0:---------:.40:--------~a~o--------1~2-0________1ieo--------2~0Lo--------2~40------~2wao SOURCE: ES-121 REACTOR -WETWELL DIFFERENTIAL PRESSURE (PSI) FIGURE 6.2-50 LOW PRESSURE COOLANT Note: This curve applicable to Pre-Power Uprate INJECTION FLOW RATE containment response evaluation in Section 6.2.1.1.J. For reconciled performance cune see Figure 6.J-SA. NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 13 OCTOBER 2000 ) REFERENCE CALCULATION ES-052-5 4.0 - 3.897 fTz ft t-c w a: c cw ... ~ 3.0 3.147 FT2 a: m j t w ~ (.) w I.I. I.I. w ... Q) 0 &l> p I ~~ I I I 2.0 0 1.0 2.0 108 TIME AFTER ACCIDENT (SECOND) FIGURE 6.2-51 RECIRCULATION PUMP SUCTION LINE BREAK AREA VS. TIME NIAGARA MOHAWK POWER CORPORATIO~ NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 0 APRIL 1989 N12B EL. 299.04' 1--+.+--1---+--+--t"-:'""""N12B......-~1--~.....--+---+---1---1---+~M---I 1-t!r.J J N12C N12B 7 9 15.96' 12 EL.283.08'1 4'-t--l-___.."7"'4~1--+---ir-+-+--+--+-+-l-l-~..,__~"'4--l--~~+--l---&...1 N2f"' 1 2 EL. 266.54' .,___ _ _ _ _ _ _ _ _ _ _ _ 3 /.NODE NUMBER (TYP) 6 116.54' 210° 180° 150° 120° 90° 60° 30° PIPE DESIGNATION NOTES: 1.~)INDICATES THE ASSUMED N1A-B: RECIRCULATION SUCTION (24") LOCATION OF THE PIPE NOZZLE. N2A-F: RECIRCULATION INLET (12") 2. THE FEEDWATER LINE BREAK N4A-D: FEEDWATER INLET (12") IS ASSUMED TO OCCUR IN NODE 19 NS: LPCS (1 O") N6A-B: RHR/LPCI MODE (12") N9A: JET PUMP INSTRUMENTATION (4") N10: CRD HYDRAULIC SYSTEM RETURN (3") N12B-C: INSTRUMENTATION - WATER LEVEL (2") N13B: INSTRUMENTATION -WATER LEVEL (2") FIGURE 6.2-52 NODALIZATION DIAGRAM FEEDWATER LINE BREAK 21-NODE MODEL RPV-BSW ANNULUS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT ........................ i .......... BREAK NODE 19! <( u; 351 a. w £C 301 en en w £C

a. 251 I

1o:'i"* 101 ~--~-----------.-...-. ------.-.~~--~..._.--+-~--.----.-.-....------~ 2 3 4 5 6~ 7 8-9 10- 2 2 3 4 *5 ..-6 7 8 9 10- c 2 3 4 10° I TIME AFTER BREAK (SECONDS) FIGURE 6.2-53 NODAL PRESSURES FEEDWATER LINE BREAK 21-NODE MODEL RPV*BSW ANNULUS SHEET 1 OF e NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984 -c( 35[ -a: en D.. w 30! en en w a: 25 I 1 D.. .-__.._.;.'NODE 3 10!'~-~~--~-------..,.._---~~~~-------.~--,.....,..___,~,.~~---~-----...----..,......,-.-.~ 10 .. 3 2 3 4 5 6 7 8 9 10- 2 2 3 4 5 6 7 8 9 *.10- 1 2 3 4 5 6 7 8 9 1o0 TIME AFTER BREAK (SECONDS) FIGURE 6.2-53 NODAL PRESSURES FEEDWATER LINE BREAK 21-NODE MODEL RPV-BSW ANNULUS SHEET 2 OF 6 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984 so~,-----------------,-~----------~-------,---------~~--~~- 451-.------------t----------1------------1 ~ 351I (/) a. w a: 30 1

> I

(/) (/) w a: 251I a. 10l-+------------------__,,_______________.........,__,~---------.-----_-.-r--w___,~ 10- 3 2 3 4 5 6 7 8 9 ' 1 o 2 3 4 5 6 7 8 9 10-1 2 3 4 5 6 7 8 9 1 o0 I

_ .. ~.!.

TIME AFTER BREAK (SECONDS)_ FIGURE 6.2-53 NODAL PRESSURES FEEDWATER LINE BREAK 21-NODE MODEL RPV-BSW ANNULUS SHEET 3 OF 6 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 <( c;; 35 a. w 1%: 30 en en

• w 1%:

a. 25 NODE9 20 10+'------------~---..-.,_.~--~-----.--......~.-.-...+-~~-.----.--..--r--r-r-1-T""'f 1 o- 3 2 3 4 5 & 1 as 10-2 2 3 4 5 & 1 a s 1 o-:r f s s 3 4~

• 6 i 9 1**0° TIME AFTER BREAK (SECONDS);

FIGURE 6.2-53 NODAL PRESSURES FEEDWATER LINE BREAK 21-NODE MODEL RPV-BSW ANNULUS SHEET 4- OF - 6 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984 40~'~~---------------+---~----~--------+------~~~~--~~ - 35 ~ en a. w a: 30 en en w ' a: 25 a. 10+---------------.._...,.__,_______~----.---...............,.....,.+-...------------;r--.-.-.._...__.

• 1o-3 2 3 4 s & 1 s 9 1o.:z 2 3 4 s & 1 a9 1 o- f'" 2 3 4 s a1 8 9 1o0 TIME AFTER BREAK (SECONDS) FIGURE .6.2-53 NODAL PRESSURES FEEDWATER LINE BREAK 21-NODE MODEL RPV-BSW ANNULUS SHEET 5 OF 6 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT

45 ; - - - - - - - - - - - - - - - - - - - + - - - - - - - - -...... 1 BREAK NODE 19 <( 35 en a. w a: 30: en en w a: 25 a. NODE17 NOD.E21-- 1o-3 2 3 4 s &1 a 9 *; 10-2 2 a 4 5 &1 a 9 1o~r 2 3 4 s &1 a9 10° TIM*E AFTER BREAK (SECONDS) FIGURE 6.2-53 NODAL PRESSlJRES FEEDWATER LINE BREAK 2*1-NODE MODEL RPV-BSW ANNULUS SHEET 6 OF 6 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT 40,~:----~---------------r------~------------..--------------~---- Q iii Q. w £C 0 0 w a: Q. cc t:= z w a: w u. u. i5 5 -s'.~---------------------+-~~---~-------~---- 10- 3 2 3 4 5 6 7 8 9 1 (j~2 2 .....~~---~-----------1 3 4 5 6 7 8 9 10- 1 2 3 4 5 618 9 100 TIME AFTER BREAK (SECONDS) FIGURE 6.2-54 \NOTE: _ NODAL PRESSURE DIFFERENTIALS

11. DIFFERENTIALS ARE RELATIVE TO NODE 21 FEEDWATER LINE BREAK 21-NODE MODEL RPV-BSW ANNULUS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT A l\.ACl\lnl\ACl\IT ')~

1 EL 314'*1 * '2" ~.....~~~---11--.....,.~~~----+---1i----~~~~~---1----1111~~ I \ EL 309.094' \ J 16 17 10 11 12 13 14 15 18 19 N2F EL 283.073' 1 2 3 8 9 LODE NUMBER 1 (TYP) EL 266*6* '2" _ _ _ _ _ _ _ _ _ _...___ _ _- - ' - - - L - - - " " - - - - - - - 1 . . - - - - - ' 210° 180° 150° 120° 90° 60° 30° PIPE DESIGNATION NOTES:

1. C>> INDICATES THE ASSUMED N1B: RECIRCULATION SUCTION (24") LOCATION OF THE PIPE NOZZLE.

N2A-F: RECIRCULATION INLET (12") 2. THE FEEDWATER LINE BREAK N4A-D: FEEDWATER INLET (12") IS ASSUMED TO OCCUR IN NODE 29 NS: LPCS (1 O") N&A-B: RHR/LPCI MODE (12") N9A: JET PUMP INSTRUMENTATION (4") N10: CRD HYDRAULIC SYSTEM RETURN (3") N12B-C: INSTRUMENTATION - WATER LEVEL (2") N13B: INSTRUMENTATION - WATER LEVEL (2") FIGURE 6.2-55 NODALIZATION DIAGRAM FEEDWATER LINE BREAK 37-NODE MODEL RPV-BSW ANNULUS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT . w ~ 30~~-------------1---+.--1--~~.___._-1----~~--'--~~~------~------' Ul Ul w ~ 25r-.-----~--------_,_---+-t~--~_,_-------------+---~------~-------t 201----------#---#----#---+---------.....__-------.... I NODE #37* TIME AFTER BREAK (SECONDS) FIGURE 6.2-56 NODAL P'RESSURES. FEEDWATER LINE BREAK 37-NOOE MODEL RPV-BSW ANNULUS - .SHE.ET 1OF10 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT so, 45. 40/I <C iii 0. 351 I w a: 30( (/) (/) w a:

0. 251 201 NODE4 NODE3

• NODl(4 *-* -- - -

NODE 1. NODE37 10-3 2 a 4 s s ta 9 10.:r - 2 3 TIME AFTER BREAK (SECONDS), FIGURE 6.2-56 NODAL-PRESSURES FEEDWATER LINE BREAK 37-NODE MODEL RPV-BSW ANNULUS SHEET 2OF10 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT DECEMBER *19g5 c 35 -~ U) D.. 30-+-----------------~-------------+---~-~----,,,,-;-----1 U) U) NODES-- w ~ 25"+----------~---t----~-------~~-t-~-f----;o---------1 NODE7 2011-1------------------------Jlll!l'---flllll!ll-------------1 NODE 5 -- NODES 10*~----..--..--~..................,.......____........__................................~..........----...-~...-..-....................... 10- 3 2 3 4 5 6 7 8 9 1 o-:2 2 3 4* 5 6 7 8 gi_f~ o.1 2 TIME AFTER BREAK (SECONDS)i FIGURE 6.2-56

---

....-.~~~~

r\fObAL PRESSURES ......----------.....

FEEDWATER LINE BREAK 37-NODE MODEL RPV-BSW ANNULUS SHEET 3 OF 10 .

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

• AMENDMENT ~f3 DECEMBER 1985

-cc 35 a.

w a:

t/J t/J w

a:

a. 25~

NODE 11*

NODE37 10~*-----.---...;-................-...........-----...---.--~.............~-----.---....-.........,.........~~

3 4 5 6 7 8 9!110-1* 2 3 4 5 6 7 8 9 .,1 o0 TIME AFTER ~REAK (SEC_ONDS)

..._.FIGURE 6.2-56

~ ......... ......--------11111111111

~

NODAL PRESSURES FEEDWATER LINE BREAK 37-NODE MODEL RPV-BSW ANNULUS SttEET 4 OF 10 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 ,

FINAL SAFETY ANALYSIS REPORT DECEMBER 1985

so~------------~----------------------------~------------

~

35.

UJ a..

w a: 30 UJ UJ w

a: 25 a..

NODE13 20.

-NODE 37 10~----------~-----~--------------------.......~------------------.-.r-.-t

' 1o-r 2 3 4 s s ta 9 110~2 I:

2 3 4 s 6 1 8 9.Jlo-1 2 3 4 s s 1 a 9"10° TIME AFTER BREAK (SECONDS) FIGURE 6.2-56 NODAL PRESSURES FEEDWATER LINE BREAK 37-NODE MODEL RPV-BSW ANNULUS SHEET 5OF10 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAF~TY ANALYSIS REPORT DECE:MErER 1985 .

so~.--~~~-----------,-----------------~~------------------

-cc 35

-a:w iii a.

30

> I tn tn w

a:

a. 25~

NODE~7*-.-

10......----........--.~....-.....-.-.-.........-----..-.......--.~.........................- -.....- -....................................

3 4 5 6 7 8 ~1 Q.. c s: 2

!IME__ AFTER BREAK (SECONDS)t

._...FIGURE . 6.2-56 .

NODAL PRESSURES FEEDWATER LINE BREAK 37-NODE MODEL RPV-BSW ANNULUS SHEET 6 OF 10 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT

50----~------------~------~----~--------------------------

40~*-------------------+--------------------+---~---------------t

<C (ii c.

35

........ NODE 21 w

a: 30*

UJ UJ w

a: 25 c..

NODE.37.

3 4 s s 1 s9 :1o~ 1

... ~*....::.:r.)? ,.

2 3 4 5 6 7 8 9 10° TIME AFTER BREAK (SECONDS)! FIGURE 6.2-56 NODAL PRESSURES FEEDWATER LINE BREAK 37-NODE MODEL RPV-BSW ANNULUS SHEET 7OF10 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT nFCEMBER 1985

so~*------~--------~-w---~~--------------~~-----~--------

c u;

35 Q.

w a: 30 1 en en w

a:

Q. 25 1 0 ' ~ , - - - - - - ~ - - - - - - - - - - _ , _

.NODE37

__________________,..._______________ ~ ...........

1o.:3. 2 3 4 5 6 7 8 9 I 1 o:a* 2 3 4 56 7 8 9 *10.1-: 2 3 4 5 6 7 8 9 1 OO TIME AFTER BREAK (SECONDS) FIGURE ._6.2-56 NODAL PREs*s*uRES FEEDWATER LINE BREAK 37-NODE MODEL RPV-BSW ANNULUS SHEET 8OF10 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT

50-.---------~--~-------------~----~~~--------~~~~~~~_,

BREAK NODE 29

-< 35

-a:w flJ Q.

30 0

(/)

w a:

Q. 25 NODE37 10..,._------~------.._.~_._.--------------------_._~~---~-------------'

10- 3 2 3 4 5 6 7 8 9 10- 2 2 3 4 5 6 7 8 9 10*1 2 3 4 s a1 a9 1 oo TIME AFTER BREAK (SECONDS) FIGURE 6.2-56 NODAL PRESSURES FEEDWATER LINE BREAK 37-NODE MODEL RPV-BSW ANNULUS SHEET 9 OF 10 NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

SOURCE: CALC ES-157 UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 15 OCTOBER 2002 ~

50~1---------------------r---------------~---.-------------------

45~;--~---------------1-------------------J~----------------~

-<C

-c..

iii 201..,.._----------+~~~~~~t.--~_..;;;.i~---------1

.:N()-p~ 3;f TIME AFTER BREAK (SECONDS) *'); FIGURE 6.2-56

....---------------~--~--------

NODAL PRESSURES FEEDWATER LINE BREAK 37-NODE MODEL RPV-BSW ANNULUS SHEET 10 OF 10 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT

' Al\Al=NnMFNT 23

40' 1

35 B~EAK1 NODE.29:

30 c

u; A.

._. 25 w

a:

U)

U) 20 w

a:

A.

cc 15' i==

z

• W a: 10 w

u.

u.

Q 51 1 o.:r

.5......--~-------------...-.---------------------4----~----------~_....

2 3 4 5 & 1 s 9 10-2 2 3 4 s & 1 s g 1 oY 2 3 4 s 6 1 s *s 1 oo TIME AFTER BREAK {SECONDS) I' FIGURE ,6.2-57 NODAL PRESSURE DIFFERENTIALS FEEDWATER LINE BREAK 37-NODE MODEL NOTE: RPV-BSW ANNULUS

1. PIFFERENTIALS ARE RELATIVE TO NODE 37 ,

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT JUNE 1984

19 RPV STABILIZER 87 87 l EL. 314.125' GT" I"'

~

~/.

x-0

"'\ "'\ I I

I I

--~ / --~ / _J(

L __

14 15 16 15.085' 17 '

EL. 301.04' 18 20 EL. 299.04' EL. 297.04' 11 12 15.96' 7

EL. 283.07' 1 2 3 4 5 6 16.53' EL 266.54' 45° 15° 345° 315° 285° 255° 225° NOTES: f' PIPE DESIGNATION 1.\.. ../INDICATES THE ASSUMED A: FEEDWATER INLET (12") LOCATION OF THE PIPE NOZZLE.

B: RECIRCULATION SUCTION (24") 2. THE LPCI BREAK IS ASSUMED TO C: RECIRCULATION INLET (12") OCCUR IN NODE 20.

D: LPCS (1 O")

E: RHR/LPCI MODE (12")

F: CRD HYDRAULIC SYSTEM RETURN (3")

G: JET PUMP INSTRUMENTATION (4")

H: WATER LEVEL INSTRUMENTATION (2"}

FIGURE 6.2-58 NODALIZATION DIAGRAM LOW PRESSURE COOLANT INJECTION LINE BREAK RPv-s;;w ANNULUS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

50 NODE BREAK 20 40

c u;

a..

~ 30 ---~----~~~-+-~--....._~~----+_...~~~~~~..._~~~~~~~

en en w

a:

a..

10*4 10-3 10*2 10- 1 10° TIME (SEC)

FIGURE 6.2-59 NODAL PRESSURES LOW PRESSURE COOLANT INJECTION LINE BREAK RPV-BSW ANNULUS SHEET 1OF5 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

- 50

~ 30 1--~~~~~~-f-~--~~~~-;-~~~~~~--t--~~~--~--~

fl) fl) w a:

Q.

TIME (SEC)

FIGURE 6.2-59 NODAL PRESSURES LOW PRESSURE COOLANT INJECTION LINE BREAK RPV-BSW ANNULUS SHEET 2 OF 5 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

TIME (SEC)

FIGURE 6.2-59 NODAL PRESSURES LOW PRESSURE COOLANT INJECTION LINE BREAK RPV-BSW ANNULUS SHEETS OF 5 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

\

50 - - - - - - - - - - - - - - - - , - - - - - - - - - - - - - - . - - - - - - - - - - - - - - . - - - - - - - - - - - - - ,

c iii D..

w a: 30 U)

U) w a:

A.

NODE17 20 TIME (SEC)

FIGURE 6.2-59 NODAL PRESSURES LOW PRESSURE COOLANT INJECTION LINE BREAK RPV-BSW ANNULUS SHEET 4 OF 5 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

c iii

~ 30 ~~~~~--~-+-~~~~~----t-~~~~~~~t--~~~~~----1

(/)

(/)

w a:

A.

20 10 10-3 10- 2 10- 1 TIME (SEC)

FIGURE 6.2-59 NODAL PRESSURES LOW PRESSURE COOLANT INJECTION LINE BREAK RPV-BSW ANNULUS SHEET 5 OF 5 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

35 ----------------..----------------.----------------,r--------------...,

BREAK NODE 20 25 c

(ii e:.

w a:

"'"'w a:

Q.

...I 15 j::

z w

a:

w LL LL c

5 10*4 10*3 10-2 10- 1 100 TIME (SEC)

FIGURE 6.2-60 NODAL PRESSURE DIFFERENTIALS NOTE: LOW PRESSURE COOLANT INJECTION LINE

1. DIFFERENTIALS ARE RELATIVE TO NODE 19 BREAK RPV-BSW ANNULUS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 23 DECEMBER 1985

19 RPV STABILIZER l

EL 314.125' EL. 309.93' EL 307.93' 14 15 18 15.085' EL. 305.93' v~ rx /_ __ E

~--

t)

EL. 299.04' E GJ.-

-~

NODE  : I NUMBER H (TY~

7 8 9 10 11 12 15.96' EL 283.07' 16.53' EL 266.54'

_____1_________2________3_________ 4 ________5__________s__ __.__l 120° goo 60° 30° 330° 300° NOTES:/"'"\

PIPE DESIGNATION 1.\._ /INDICATES THE ASSUMED A: FEEDWATER INLET (12") LOCATION OF THE PIPE NOZZLE.

B: RECIRCULATION SUCTION (24") 2. THE LPCS BREAK IS ASSUMED TO C: RECIRCULATION INLET (12") OCCUR IN NODE 20.

D: LPCS (1 O")

E: RHR/LPCI MODE (12")

F: CRD HYDRAULIC SYSTEM RETURN (3")

G: JET PUMP INSTRUMENTATION (4")

H: WATER LEVEL INSTRUMENTATION (2")

FIGURE 6.2-61 NODALIZATION DIAGRAM LOW PRESSURE CORE SPRAY LINE BREAK RPV-BSW ANNULUS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

............ ,.. ... ~

50 ....--------------r-------------~--------------,.-------------,

NODE BREAK 20*

40 I

c a.

~ 30 1--~~~~--~-1-~~---#--~---4+-___;===F=:lllrir-~~----1--~----~----~

(/.)

(/.)

w a:

A.

20 10 10*4 10- 3 10-2 10- 1 TIME (SEC)

FIGURE 6.2-62 NODAL PRESSURES LOW PRESSURE CORE SPRAY LINE BREAK RPV-BSW ANNULUS SHEET 1OF5 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

TIME (SEC)

FIGURE 6.2-62 NODAL PRESSURES LOW PRESSURE CORE SPRAY LINE BREAK RPV-BSW ANNULUS SHEET 2 OF 5 I NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 .

FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

50 --------------.....--------------,---------------r--------------~

~ 30 1---------------1---~--~~---t-~~~~------t------~~~--~

fl) fl) w a:

A.

20 NODE15 10 10*4 10*' 10- 2 10- 1 100 TIME (SEC)

FIGURE 6.2-62 NODAL PRESSURES LOW PRESSURE CORE SPRAY LINE BREAK RPV-BSW ANNULUS SHEET 3 OF 5 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

50 _______________....,.....____________-r--------------..--------------~

40 c

iii 0.

II.I a:

30 en en II.I a:

A.

NODES 20 10*" 10-3 10- 2 10- 1 100 TIME (SEC)

FIGURE 6.2-62 NODAL PRESSURES LOW PRESSURE CORE SPRAY LINE BREAK RPV-BSW ANNULUS SHEET 4 OF 5 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

c c;;

a.

~

30 1--~----~--~-t-------~~---1-~~~~------.------~~~--~

Cl)

Cl) w cc a.

20 10-3 10-2 10*1 TIME (SEC)

FIGURE 6.2-62 NODAL PRESSURES LOW PRESSURE CORE SPRAY LINE BREAK RPV-BSW ANNULUS SHEET 5 OF 5 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

\

35..--------------,.--------------....,---------------....-------------.. . . .

30 BREAK NODE 20

-a; 25 Q

e:.

w 20 a:

(/)

(/)

w a:

&:l. 15

..J cC

~

z w

a: 10 w

u..

u..

s 5

TIME (SEC)

FIGURE 6.2-62A NODAL PRESSURE DIFFERENTIALS NOTE:

1. DIFFERENTIALS ARE RELATIVE TO NODE 19 LOW PRESSURE CORE SPRAY LINE BREAK RPV-BSW ANNULUS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

19 RPV STABILIZER 1

EL 314.125' 15.085' 13 14 15 18 EL. 299.04' 7

15.96' EL. 285.07' 10 11 12 EL 283.07' NODE NUMBER EL 281.07' (TY/7 16.53' EL. 266.54'

....___1__ ~------2--------3---------4---------5----------6----__J_

goo 330° 120° 60° 30° 300° NOTES:

PIPE DESIGNATION I'""'

1. \..,/INDICATES THE ASSUMED A: FEEDWATER INLET (12") LOCATION OF THE PIPE NOZZLE.

B: RECIRCULATION SUCTION (24") 2. THE RECIRCULATION INLET BREAK C: RECIRCULATION INLET (12") IS ASSUMED TO OCCUR IN NODE 20.

D: LPCS (10")

E: RHR/LPCI MODE (12")

• F: CRD HYDRAULIC SYSTEM RETURN (3")

G: JET PUMP INSTRUMENTATION (4")

H: INSTRUMENTATION - WATER LEVEL (2")

FIGURE 6.2-63 NODALIZATION DIAGRAM RECIRCULATION INLET LINE BREAK RPV-BSW ANNULUS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT II lt\.IC -t no A

50 . . - - - - - - - - - - - - -........---------------,----------------,----------------,

40 BREAK NODE 20 NODE7 20 10 10*4 10-3 10- 2 10- 1 TIME (SEC)

FIGURE 6.2-64 NODAL PRESSURES RECIRCULATION INLET LINE BREAK RPV-BSW ANNULUS SHEET 1OF5 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

10*4 10-3 10*2 10-1 100 TIME (SEC)

FIGURE 6.2-64 NODAL PRESSURES RECIRCULATION INLET LINE BREAK RPV-BSW ANNULUS SHEET 2 OF 5 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

10* 4 10- 3 10*2 10*1 101 TIME (SEC)

FIGURE 6.2-64 NODAL PRESSURES RECIRCULATION INLET LINE BREAK RPV-BSW ANNULUS SHEET 3 OF 5 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

50 .....--------------,--------------r--------------..--------------i 40

~ 30 t----~~~~~-+---~~~~~--+-~--~~~--~.-------~--~---1 U>

U>

w a:

a.

20 NODE17 10-3 10*2 10*1 10° TIME (SEC)

FIGURE 6.2-64 NODAL PRESSURES RECIRCULATION INLET LINE BREAK RPV-BSW ANNULUS SHEET 4 OF 5 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

50 ---------------.--------------,..--------------..---------------,

40 10*4 10*3 10*2 10- 1 10° TIME (SEC)

FIGURE 6.2-64 NODAL PRESSURES RECIRCULATION INLET LINE BREAK RPV-BSW ANNULUS SHEET 5 OF 5 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

35..---------------,----------------r---------------,----------------,

30 25 c

ti)

a. 20 w

a: BREAK

> NODE 20

(/)

r.n w

a: 15 a.

....I

<t

~

z 10 w NODE 1 a:

w LL LL i5 5

0

.5......___ ....._-.!.-.!....d...L...L..~-----'--'--'-..i.....l....i...i..........---__.__________............._____________......_.......

1Q.;4 10-3 10- 2 10- 1 10° TIME (SEC)

FIGURE 6.2-64A

'.:~ J.\NODAL PRESSUR:E'.-DIFFERENTIALS l  !

• NOTE: 1

• _ (1 RECIRCULATION INLET LINE BREAK t A~,

1: DIFFERENTIALS ARE RELATIVE TO NODE 19 . ___8PY~~l)..W~~~~b~~ _ .,_.- '--"~-*

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

• 19 RPV STABILIZER f

EL. 314125' "N13A 1' I

~

N13A 13 14 15 16 17 18 N4C N4B N4A 15.083' N12A EL. 299.04' N6B N12B 8 9 10 11 12 15.96'

..!_NODE NUMBER (TYP) 13.54' 1 ....................._ 2 .......-+-.- 3 ---+--- 4 ....................._

EL. 266.54' ......,_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.....,.

5 ..................._ 6 l 16.54' 180° 150° 120° goo 60° 30° PIPE DESIGNATION NOTES:

1.()INDICATES THE ASSUMED NIA-B: RECIRCULATION SUCTION (24") LOCATION OF THE PIPE NOZZLE.

N2A-E: RECIRCULATION INLET (12") 2. THE RECIRCULATION SUCTION N4A-C: FEEDWATER INLET (12") LINE BREAK IS ASSUMED TO NS: LPCS (1 O") OCCUR IN NODE 20 N6A-B: RHR/LPCI MODE (12")

N9A: JET PUMP INSTRUMENTATION (4")

N10: CRD HYDRAULIC SYSTEM RETURN (3")

N12A-B: INSTRUMENTATION - WATER LEVEL (2")

N13A: INSTRUMENTATION - WATER LEVEL (2")

FIGURE 6.2-65 NODALIZATION DIAGRAM RECIRCULATION SUCTION LINE BREAK RPV-BSW ANNULUS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AlUICt..11"'\lACt..IT of of II llr.11'"" .. """".II

• -t:'

so-----------------~..------------------.------------------r-----------------i

- 35 tC iii BREAK NODE #20 a.

w a: 30

=

w a:

a.

25 10- 4 2 3 4 5 6 7 8 9 10-3 2 3 4 5 6 7 8 9 10- 2 2 3 4 5 6 7 8 910- 1 2 3 4 5 6 7 8910° TIME (SEC)

FIGURE 6.2-66 NODAL PRESSURES RECIRCULATION SUCTION LINE BREAK RPV-BSW ANNULUS SHEET 1OF6 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

c 35 i.i A.

w a: 30

(/)

(/)

w a:

A.

25 10 _________________________________~-------------------------------"--------.......

10*4 2 3 4 5 6 7 8 9 10- 3 2 3 4 5 6 7 8 910-2 2 3 4 5 6 7 8 9 1 Q.1 TIME (SEC)

FIGURE 6.2-66 NODAL PRESSURES RECIRCULATION SUCTION LINE BREAK RPV-BSW ANNULUS SHEET 2 OF 6 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

c 35 (i)

A.

w a: 30 (t)

(t) w a:

A.

25 10- 4 2 3 4 5 6 7 8 9 10-3 2 3 4 5 6 7 8 9 10- 2 2 3 4 5 6 7 8 9 10- 1 TIME (SEC)

FIGURE 6.2-66 NODAL PRESSURES RECIRCULATION SUCTION LINE BREAK RPV-BSW ANNULUS SHEET 3 OF 6 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

so----;..._-------------------.......------------------------.-----------------------w

- 35 c(

ii D..

w a: 30 en en w

a:

D..

25 9 12 20 10- 4 2 3 4 5 6 7 8 9 10-3 2 3 4 5 6 7 8 9 10-2 2 3 4 5 6 7 8 9 10- 1 TIME (SEC)

FIGURE 6.2-66 NODAL PRESSURES RECIRCULATION SUCTION LINE BREAK RPV-BSW ANNULUS SHEET 4 OF 6 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

<(

35 iii a.

w a: 30 fl) fl) w a:

a.

25 10 __________________________________________________________________________

10- 4 2 3 4 5 6 7 8 9 10- 3 2 3 4 5 6 7 8 9 10-2 2 3 4 5 6 7 8 9 10-1 TIME (SEC)

FIGURE 6.2-66 NODAL PRESSURES RECIRCULATION SUCTION LINE BREAK RPV-BSW ANNULUS SHEET 5 OF 6 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

50 45 40

-c;;

c 35 a.

LU IC 30 en en LU IC a.

25 18 20 J 15

~

~_.,,,.

19 10 I I I I I I I I I I I I I I I I I I I I I I I I 10- 4 2 3 4 5 6 7 8 9 10-3 2 3 4 5 6 7 8 9 10- 2 2 3 4 5 6 7 8 9 1 Q.1 TIME (SEC)

FIGURE 6.2-66 NODAL PRESSURES RECIRCULATION SUCTION LINE BREAK RPV-BSW ANNULUS SHEET 6 OF 6 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

30------------~-----.------------------r-------------------,.-------------------,

25 BREAK NODE #20 c 20 CJ) e:.

w a:

> 15 CJ)

CJ) w a:

D..

..J

<(

j:: 10 z

w a:

w u.

u.

Ci 5

-s---------------.

10-:4 2 3 . . . . --------------------------~~------------------------------------

4 5 6 789 10- 3 2 3 4 5 6 789 10- 2 2 3 4 5 6 78 910- 1 2 3 4 5 6 7 8 9 1o0 TIME, SEC.

FIGURE 6.2-66A 1

"~~~NODAL PRESSURE UiFFERENTIALS NOTE: *-*. 'iRECIRCULATION\ISUCTION LINE BREAK.

1: DIFFERENTIALS ARE RELATIVE TO NODE 19 RPV-BSW ANNULUS

~-*-*,,t NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 11 JUNE 1984

NODEI y MOMENT ARM 210°

~/; FEEDWATER~ EL 2_6_6_*5_ 42-'----_._~......,,---&...____..__

NOZZLE z 270 0 SEC. A*A 81 AND 92 ARE BOUNDARY AZIMUTHS FOR NODE I.*

SPAN = 82-81 NODAL HEIGHT= h2-h1 RPV OR= 11.167 FT BSW IR= 14.063 FT= r PROJECTED X*AREA = r(h2-h1) (SIN (82-210°)-SIN (81-210°))

PROJECTED Z*AREA = r(h2-h1) (COS (81-210°)-COS (lb-210°))

MOM ENT ARM = 1/2 (h1 +h2) - 266.542 ft *

. THE X-AXIS IS THE BREAK AXIS FIGURE 6.2-67 ANNULUS PRESSURIZATION GEOMETRY.

FOR FORCE AND MOMENT CALCULATIONS FEEDWATER LINE BREAKS RPV-BSW ANNULUS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

3500-------------------------------------------

- ~

",~

/v---

- asoo...,_____..,..______.....,____...,_____,..____ ----4 i)200_0-+----....._~ _ _ _...,.___ _...___..___ _ _.,.____ __,

D..

i2 w

u a:

0 U.; 150J)...,_______,.~_....,_ _ _ _...,___ _ _,....__ _ _.,..__ _----a

[

• 1000 (

soo~-------+--------t-------....-------...--------.

00......0_ _ _ _0. . .2._____o. . .4_ _ _ _o.....e____o. . e-L . _ _____.*1.0 1 TIME AfTER ~REAK {SECONDS~

.....--------1,I

__:. r

- -FIGURE

---

- - - - - - - - - - - - - - - - - - - - - -...... i 6.2-68 1 ~~mlli!llllllll----~--

VEcfOR SUM OF HALF-ANNULUS FORCES ACTING ON BSW .

FEEDWATER LINE BREAK 21-NODE MODEL RPV-BSW ANNULUS I i

i NIAGARA MOHAWK POWER CORPORATION \

i NINE MILE POINT-UNIT 2  :

FINAL SAFETY ANALYSIS REPORT

3500-*- - - - - - - . - - - - - - - - - - - - - - - - - - -

25QQ_-+-----+------+------+-----+---~

' /~

fl 2ogg-+------+-/--+-----1-------1-------1------1 i

iU..

I 150Q-+.- - < # - - - + - - - - - - + - - - - - + - - - - - + - - - - - 1

• o.o 0-+----~~+-~~-"------i.----~---&----------

0.4 0.6 0.8 0.2 1.0 TIME AFTER BREAK (SECONDS)

FIGURE 6~2-68A VECTOR SUM OF HALF-ANNULUS FORCES

" ACTING ON BSW

. FEEDWATER LINE BREAK 37-NODE MODEL

.RPV-E3SW A~NULUS ..

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

8.0'~X1g~--------------------

7.0:1-P------+-----+----+----+--------t 2~0....,,_ _ _ _..,.___ _ _+ - - - - - - - - - - t - - - - - - t 1.0~' ..___ _--+------t-----+----....,._-----1 o.o.....______._____.....,____-+-_ _ _ - t -_ _----4

--,0.0 0.2 0.4 0.8. 1.0 TIME AFTER BREAK (SECONDS)

FIGURE* 6.2-69 VECTOR SUM OF HALF-ANNULUS MOMENTS ACTING ON BSW FEEDWATER LINE BREAK 21-NODE MODEL RPV-BSW ANNULUS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

s.ox1cr....----------------------

~ ~

C*

7.0-+-----+------+------+-----+--------f 8.0.,...._----+------+------+------+-------I

--r----_

/~

5.0------+---v+------t-----+----+--------.!

~I a..

52 /

I i=' 4.0-+-----l'----+------+-----+-----1-------1 I* 3.0 I

, ----+-----+-----+-----t-------1 2.0.........

1.0 .........----+-----+------+------------------

0.0-+------+-----1-----+----+-------1 10.0 - 0.2 0.4 ~ 0.8 0.8 1.0 TIME AFTER Bf!EA_!<..(S~CONDS)

FIGURE ~.2-69A .*

VECTOR SUM OF HALF-ANNULUS MOMENTS ACTING ON BSW FEEDWATER LINE BREAK 37-NODE MODEL RPV-BSW ANNULUS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

2NMS*SOV1A 2NMS*SOV1B 2NMS*SOV1C 2NMS*SOV10 IPC-.......-opc 2NMS*SOV1E TIP BALL VALVE s

TIP EXPLOSIVE SHEAR VALVE 2NMS*VEX1-A Z31A, B, C, 0 1 E 2NMS*VEX1B 2NMS*VEX1C 2NMS*VEX10 2NMS VEXlE 111 TEST CONNECTION TIP INDEXING MECHANISM Z-31A, B, C, D, E TIP DRIVE GUIDE VALVE TO RPV SOURCE: EM-38A-5 FIGURE 6.2-70 ISOLATION VALVE ARRANGEMENT FOR PENETRATION Z-31A, 8, C, D, E

...______________.....______________NIAGARA* MOHAWK POWER CORPORATION NINE MILE POINT-,UNIT 2 UPDATED SAFETY ANALYSIS REPORT- - -**- ..

INSTRUMENT INSTRUMENT LINES FROM RPV /PRIMARY CONTAINMENT NOTE~ THIS FIGURE REPRESENTS THE GENERAL ISOLATION VALVE ARRANGEMENT OF NUMEROUS INSTRUMENT LINES.

ALTHOUGH PHYSICAL DETAILS MAY DIFFER FOR INDIVIDUAL LINES, THE SAFETY FUNCTION AND TESTING CAPABILITIES REMAIN UNCHANGED.

SOURCE: NIA FIGURE 6.2- 70a..

ISOLATION VALVE ARRANGEMENT

'.FOR INSTRUMENT LINES NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT

I

\---~

\g__

L-1--J,~---------,

!---------"-'-* -~ I

• ~~UCITlll'Ml:CllCTAIMllM...._..SUIPIO lt.~&~:"!L 11.°".......... SfAl\ll...._..,l'tSTDtl'l~-flUCl".

FIGURE 6.2-71a CONT A!NMENT ATMOSPHERE MONITORING SYSTEM NINE MILE POINT NUCLEAR STATION - UNIT 2 SOURCE, PlD-62A-16 SCRIBA, N.Y.

TITLE, CONTA!Nl1NT ATMOSPHERE MONITORING UPOATEO SAFETY ANALYSIS REPORT USAR REVISION 1 S OCTOBER 2002

I I

I I

• ---~

• • ~W-;'J

    ~~~~"*

1t.lltf*IOIMl.Lr.tATUID""'-A'USTDllllJWDCll&lNl't.1.t£.

~- ~l- @- @- ..

r---1----: r---1----: r---1----: ! FIGURE 6.2-71b

~@ ~@ ~@ ~ CONTAINMENT ATMOSPHERE MONITORING SYSTEM NIAGARA MOHAWK POWER CORPORATION SOURCE, Pf0-B29-19 NINE MILE POINT-UNIT 2 TJTLE. CONTAINMENT ATHOSPHERE MONITORING SYSTEM UPDATED SAFETY ANALYSIS REPORT USAR REVISION 1S OCTOBER 201212

A c G M

l. l.

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

\1----i

-,--~

~~~11 Q"""q.11n:

~

-\'.*

111 FIGURE 6.2-720 OBA HYDROGEN RECOMBINER SYSTEM 11 r--~~~-NIN~E-M-~-E-P-01-NT~~~---t, 1 SOURCE, PID~62A-1S. NUCLEAR STATION - UNIT 2 TJT1.. £, OBA HYOROGEN RECcmBtNER SYSTEM SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT A D G M N USAR REVISION 16 OCTOBER 2004

FIGURE 6, 2- 72b DBA HYDROGEN RECOMBINER SYSTEM NINE MILE POINT NUCLEAR STATION-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 0 APRIL 1989

l THIS FIGURE

'-~

HAS BEEN DELETED

-*--- - -** --* - . -. . - -- .. - .. ~. --* -* --- *-

FIGURE 6~2- 72C I I

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AP.Al""'IUl"'\.l.Ar-11..1,.. ""7

1.05*3 ---------_...._,.----.....----------r--------,

1.05-6-l-----__,._---..,.......J------------.-L---.--------...-.-L----....--.-..,....,.......-....1 0.01 0.1 10 100 Time After LOCA <days)

FIGURE: 6.2-720 HYDROGEN GENERATION RATES FOLLOWING A DESIGN BASfS ACCIDENT CDBA>

NINE MILE POINT ... UNIT 2 UPOATEO SAFETY ANALYSIS REPORT USAR REVISION 20 OCTOBER 2012 ~

180 160 i,.....--

IOrywell Rodiolysis I~

~

g 140

,/-

.2 0

c:

120

/

v

/

~

c:: 100 Q) v

(.!)

cQ)

~ 80

/ IWetwell Radiolysis I v ----

is

x:

60 /

~

0 cu ~

£ 40 ~

I I

~ ~ ~ Corrosion

___..--- ~

20 ,,

~

~

I Metal-Water Reaction I 0 .

0 0.1 10 100 Time After LOCA <days>

FIGURE: 6.2-72E INTEGRATED HYDROGEN GENERATION FOLLOWING OBA NINE MILE POINT-UNIT 2 UPOATEO SAFETY ANALYSIS REPORT USAR REVISION 20 OCTO&ER 2012 ~

THIS FIGURE HAS BEEN DELETED FIGURE: 6.2-72F NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L T USAR REVISION 20 OCTOBER 2012

J, THIS FIGURE HAS BEEN DELETED

-ti FIGURE: 6.2-72G NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L T USAR REVISION 20 OCTOBER 2012 _J

10 J

I l

I Dryw~ll I /

j I ~

II~

~I/

c:

8i 5

/ J Wetwen 0

)(

I Recombiner Start

~~

c:a.> r'-.

• ~*

~ t:: """""'

'1 r:.;.

(,,)

_.,,,,,,- e::::: ~~

\,..

a.>

"""' ~

0..

Q)

§ I .-- ~ ~

f'..

- r--..... '"" f'...

15 ~" [lo"'

~ r--..

~

0 0 10 100 1000 Time After LOCA <days>

FIGURE: 6.2-72H OXYGEN CONCENTRATIONS FOLLOWING A DESIGN BASIS ACCIDENT <OBA>

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANAL. YSIS REPORT USAR REVISION 20 OCiOBER 2012 ~

Il 10 I

I 1/ v v J .

I Orywell J

I IJ f; Wetwell I Recombiner Start I II ll r.t ...

~

1/

v

\ .... ~

v L-P"'

'~

r\

~ ~

,,.,,..,,,. ~ ..-""' ...... ~V \ ..... ~

... Ji,

-- ~

\ Ii..

~

~

I"--. .....

~"

~

0 0 10 100 1000 Time After LOCA Cdcys>

FIGURE: 6.2-721 HYDROGEN CONCENTRATIONS FOLLOWING A DESIGN BASIS ACCIDENT <OBA>

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 20 OCTOBER 2012 ~

THIS FIGURE HAS BEEN DELETED

~

• - _.J.....__ --

FIGURE 6.. 2- 7~J NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT I

t\.l("\\/J:l\A RJ:R 1 QR.4

SOURCE MONITOR CONDITION CONTROL ACTION RESULTANT MONITOR SW-SR DRYWELL RECOM*

BINER INLET OUTBOARD

!SOL V *MOV3A CLOSE P873 LOSS OF COOLANT NOTE 2 1 - - - - - - - - - - - - 1 ACCIDENT - ISOLATION DRYWELL RECOMBINER SIGNAL DIV.I 1-------13"! INLET OUTBOARD !SOL G SW- CKEYLOCKl NOTE 6 LOCA OVERRIDE V *MOV3A CLOSE RESET P873 DRYWELL RECOMBINER l LSK-27-13B DIV .I MANUAL

"'"'"'~

ISOLATION DRYWELL RECOMBINER INLET SW* CKEYLOCKJ 33 ...... - OUTBOARD !SOL VAL VE *MOV:¥\ LOCA OVERRIDE- NOTE 8 NOT FULLY CLOSED OVERRIDE DIV I PRIM CONTMT !SOL VL VS LOCA OVERRIDE DRYWELL RECOMBINER DRYWELL RECOMBINER INLET OUTBOARD !SOL INLET OUTBOARD !SOL V *MOV3A OPEN SW-SR DRYWELL RECOM- P873 V.MOV3A OPEN BINER INLET OUTBOARD

!SOL V *MOV3A OPEN DRYWELL RECOMBINER INLET OUTBOARD !SOL VAL VE 873413 4'l

• MOV3A MOTOR OVERLOAD (875213)

SW RECOMBINER CLG RECOMBINER CLG WATER BLOCK VALVE WATER BLOCK VALVE R 74 MDV LOSS OF POWER *SOV!f/JA OPEN *SOV!f/JA OPEN P873 SW RECOMBINER CLG WATER BLOCK VALVE RECOMBINER CLG ORYWELL RECOMBINER *SOVlf/JA CLOSE WATER BLOCK VALVE G 33 OUTLET OUTBOARD !SOL *SOVlf/JA CLOSE FAILS OPEN ON SW-SR RECOMBINER CLG LOSS OF POWER P873 VAL VE *MOVlA CLOSE WATER DRAIN VALVE

• SOVllA OPEN RECOMBINER CLG WATER DRAIN VALVE DRYWELL RECOMBINER *SOVllA OPEN 33 OUTLET INBOARD !SOL PB73 VALVE *MOV4A CLOSE SW RECDMBINER CLG WATER DRAIN VALVE

• SOVllA AUTO P873 NOTES: RECOMBJNER CLG I. ALL INSTRUMENT AND EQUIPMENT NUMBERS TO BE PREFIXED WITH "2HCS-" EXCEPT WHERE A WATER DRAIN VALVE G DIFFERENT PREFIX IS SHOWN. AN ASTERISK C*l WILL REPLACE THE DASH H IN THE SW RECOMBINER CLG *SOVllA CLOSE PREFIX FOR INSTRUMENTS AND EQUIPMENT WHICH ARE PART OF NUCLEAR SAFETY FEATURE SYSTEMS. WATER DRAIN VALVE PB73

2. SEE LSK-27-l'l FOR LOSS OF COOLANT ACCIDENT- ISOLATION SIGNAL LOGIC DEVELOPMENT. *SOVllA CLOSE P873 FAILS CLOSED ON

3. LOGIC FOR DRYWELL RECOMBINER INLET OUTBOARD ISOLATION VALVE *MOV3A JS SHOWN. LOGIC LOSS OF POWER FOR ALL RECOMBINER ISOLATION VALVES IS SIMILAR CSEE ASSOCIATED EQUIPMENT MARK NUMBERS, NOTE 4l

4. ASSOCIATED EQUIPMENT MARK NUMBERS:

DIV.I CMPTR NO. DIV.II CMPTR NO.

• MOVIA HCSTC21 *MOVIB HCSTC22

• MDV2A HCSTC21 *MOV2B HCSTC22

• MOV3A HCSTC21 *MOV3B HCSTC22

• MOV4A HCSTC21 *MOV4B HCSTC22

• MOV5A HCSTC21 *MOV5B HCSTC22

• MOV6A HCSTC21 *MOV6B HCSTC22

• P873 *P875 SOURCE: LSK- 27-13A

5. LOGIC FOR RECOMBINER COOLING WATER BLOCK VALVE *SOV10A ANO DRAIN VALVE *SOVllA IS SHOWN. LOGIC FOR RECOMBINER COOLING WATER BLOCK VALVE *SOVlf/JB AND DRAIN F IGURE 6.2- 72K VAL VE *SOVllB IS SIMILAR.

6. ONE SWITCH PER DIVISION. COMBUSTIBLE GAS

7. OFF NORMAL STATUS INDICATING LIGHT, ONE LIGHT PER ISOLATION VALVE.

8. COMMON ANNUNCIATOR FDR BOTH SYSTEMS HCS AND CPS IN EACH DIVISION.

CONTROL SYSTEM

'l. OFF-NORMAL STATUS DISPLAY SYSTEM JS ABANDONED IN PLACE. LOGIC DIAGRAM SHEET 1 OF 5 SETPOINTS SHOWN ON LOGIC DIAGRAMS ARE FOR LOGIC NIAGARA MOHAWK POWER CORP.

CLARIFICATION ONLY ANO MAY BE ONLY APPROXIMATIONS OF THE ACTUAL PROCESS SETPOINT. REFER TO SETPOINT NINE MILE POINT-UNIT 2 DATA SHEETS FOR ACTUAL PROCESS SETPOINTS. UPDATED SAFETY ANALYSIS REPORT USAR REVISION 13 OCTOBER 2000

SOIR:E MfllflTOO Cot<<lJTION CONTROL ACTION RESll.TANT MONITOR

~ ORYWELL RECOl-81 NER INLET OUTBD I SOL V

• MOY3A I NOl"EMl!lt..E

~ ORYIELL RECCHI HER INLET INSO ISOL V

• MOVSA INOPERA81..E Pl73 ~CMt:fWilll!f't RECOM:I INLET OUTBD I SOL V

• H>V2A I NOP P873 ~SSl ON CtWtlER RECOl'B I Nl..ET I NID l SOL Y

• MlV5A I HOP

~ SUPPRESSI !>>I CHAPeER RECOMI OUTLET OUTSO ISOL Y *H>YlA INOP DJV I H2 RECOMBINER 873-491 1------------s_vs_TE_M_I_NOP_. -----+--ti., A 1875281>

~ SUPPRESSI ON CHHeER RECOte OUTLET I NBD l SOL V *MlY-4A I NOP PB73 RECDMl CLG llTR BLOCK VALVE

• SOVllfA INOPERABLE P873 AECIHl CLG WTR Dftil\lN VALVE

• SO'lll A INOPERABLE

~ RECOMill NER UNI T

• NllRIA J ltOPERML.E DIV.I SYSTEM ~LY ~

__DF_S£A_._m_E

'-OUT ____, (NOTE 3l LSK-"l-~

DIV.I 7 S!ftY1 CE WATER I MOf'EJWM.E t<<JTESc !Tl.Bil

1. ALL :INSTRUMENT AND EQUIPMENT !UflERS TO BE PREFIXED WJTtt '2HCS-' &

o.t£llT WHERE A DIFFBlrzffT PREFIX IS 9HIMI.. AN AITERHlK C*l WILL <PUSHl lliftJICE THE DASH <->JM THE l'MFlX FtlR 1"SlRUMENTS AND EOOIPMENT A WlCtt AflE PMT OF IULEM WETY FEl\TUftE SYSTEM. <Tl.R-0

2. LilmC FtlR DIVISDI I FECaaNER ~ITY t<<NTtJmiG IS SKlWN. LSK-27-13A

~ Ftl't mY1$DI II ~R lNOl'ERllllILITY f'IOf!Tt:l\JNG IS SIMILAR.

3.. ALlERNATE ilCTQf SWITCH.

4. Ul6'IC F£lft DIVIUJN I REC9MlillHER HANt.w.. ISOLATION IS Stf)WN.

LOGIC FOR DlV1SION II RECtl8.'lllER MANlJilltl.. ISOLATION IS SIMILAR.

SOURCE*

5. DIV.I EOOlf'fEKT LOCATEO AS 9H6VN ON P873. FI GURE 6.2-72K lllY.II EllMIENT LOCATED ON 1"875. --

COMBUSTIBLE GAS CONTROL SYSTEM LOGIC DIAGRAM SHEET 2 OF 5 SETPOINTS SHCNN ON LOGIC DIAGfWo!S AR£ FOR LOGIC NI A&!\flA t-OiAWK PO\lER CORP.

CLARlFltATION ONI.. Y AN) MAY BE ONLY Af'PFtOXlMAllONS Of THE ACTIJAL PROCESS SETPOINT. REFER TO SETPOINT NI HE Ml LE POI NT- UNIT 2 DATA SHEETS FOR ACTUAL f'AOCESS SETl"OlHTS. UPDATED SAFETY ANALYSIS REPORT OCTOM:R 1~

SOURCE MONITOR CONTROL ACTION RESULTANT MONITOR Ol V I RECOf.Bl NER 1 A BLOWER INLET TEW OJ V I RECOtfSl NER l A BLOWER INLET TEW HIGH DIV I RECOtel NER 1 A t£ATEA W.L l'Eiffii!Afl.lftE DI V I RECC>>-BJ NER l A HEATER \#ILL TEM>

HIGH DI V J RECOMn NER l A HEATER WALL TEM>

HIGH/HIGH DIV l REC~NER lA REACTl ON CH#HIER SHELL TEW JV I IA LSK-27-130 REACTIOH CfilllliER SHELL TE1'P HIGH/HI GH DI V I RECOtel NER l A IETURN Gl'IS TEM"EMTUAE 01 V 1 REt:OMll NER l A RETURN GAS TEW HIGH DIV I RECOMU NER 1 A I NLET Pl'IESSl.A;:

Ol V I REctlMU NER 1A I NLET PRESSURE HIGH OOTES1

1. ALL INSTRUMENT & ECIUIPMENT MMBERS TO BE PREFIXED WITH "2HCS-* EXCEPT WHERE A DllFFEl'EH PREFIX lS SHINN. AN AST£R1SK <*> Wll..L REf'LACE THE Dl'ISH H JN Tl£

!'MFIX FOR Blll!l'mlJMENTS AND EQUIPMENT WHICH ARE PAAT OF THE NUCLEAR WETY FEATUM: SYS'l'Qt;.

2. LQllC FOR ~ RECOMeHR *RIMl1A IS SHOWN. LOGIC FOR HYDROGEN RECOHBlNER

-AllMltB lS SMl..AR.

3. ASSOCIATED Eaull"MENT MARK NUMBERS1 FI GURE 6.2-72K OllV.l DlV.ll COMBuSTIBLE GAS

• TT13A

• TTlSA

• TTiGA *P873

• PT1':1A *P896

• TTlflB

• PTl"lB CONTROL SYSTEM

• TTl7A LOGIC DIAGRAM SHEET 3 OF 5 SETPOiNTS SiHOWN ON LOGIC DIAGRAMS ARE FOR LOGIC Nl AGARA ltil)HAWK P01<<ER CORP.

CLAAFJCATION ONl. Y At<<> MAY BE OHL Y APPRClXIMATIDNS Of THE ACTUAL PAOCESS SETPOZNT. REFER TO SETPOINT NINE MILE POINT-UNIT 2 DATA SHEETS FQlll ACTUAL f'NJCESS SETPOJNTS. UPDATED SAFETY ANALYSIS REPORT USM AEVISJON 3 OCT R1

SLUlCE MONITOR CONOJTJON CONTROL ACTlON RESULTANT MONlTOR OI V l RECOM3 I A ...----... ~

REACTION K -t J H/A CHAl"BER TEH" DIV I RECOM3 lA REACTl ON CHAH:IER TEMi' Hl GH

.----.PB'*>

OI V l RECOH3 lA

• TSL20A t-------------------1 REACTl ON CHAM:IER TEMP LOW HCSTClq CHCSTC20l TO c 120 MIN HYDROGEN RECOM3I NER w START UP

• RBNRl A AI R I NLET VALVE *MlV25A ~

NOT FULLY CLOSED OPERATE OI V I RECOH3 1 A ~

THRU GAS FLOW HCSFC01 CHCSFC02l

.....----. PB'!B DI V l RECOl43 1A c

• FSL21A - - - - - - - - - - - - - - - - - - - - ; THRU GAS FLOW LOW LSK-27-13E HYDROGEN RECOM3I NER 2 *RBt.Rl A I-EATER CONTROL INTERLOCKS DIV I RECIM3INER lA T~ GAS SW- HYDROGEN HYDROGEN RECOl431 NER FLOW LOW RECOt-B UNI T GAS HEATER *HI A

• RBNRl A OPERATE EtERGI ZE TO MlDULATE ON SCR CONTROL HYDROGEN RECOMBl NER HYDROGEN RECOM3I NER . - - - - - - GAS HEATER *HI A LSK-27-13C DE-ENERGl ZE

• RBt.Rl A Hl GH TEMP &

PRESSURE l NTERLOCKS S'd- HYDROGEN HYDROGEN RECOl-BI NER RECCJM:l UNIT GAS BLO\ER

~*-RBt.Rl_A_ _ ___, ~ *FNJ A ON NlTES1

---

offOI GAS

1. ALL INSTRUMENT & EClJJPMENT NUMBERS TO BE PREFIXED WITH "2HCS-* EXCEPT WHERE A HYDROGEN RECOt-BI NER DlFFERENT PREFlX IS SHOWN. AN ASTERISK C*l 'WJLL REPLACE THE DASH C-l JN THE BLO\ER PREFIX FOR INSTRUMENTS ANO EOOlPr-ENT VHICH ARE PART OF THE NUCLEAR SAFETY *FNJ A OFF FEATURE SYSTEMS.

2. LOGIC FOR HYDROGEN RECOf.'BltER *RBNRIA IS SHOWN.

LOGJC FOR HYDROGEN RECOMBlNER *RBNRlB JS SIMILAR.

3. ASSOClATED EDUlPMENT MARK NUMBERS:

DIV.I OJVJI DIV.I DlVJI

~  ;:fl'2is  ;;:fSHzeA  ;;:s.:jilllB

• FT21A *FT2lB *TSL20A *TSL20B SOURCE: LSK-27-130 REV.11

• HIA *HIB *TI2"A *TI20B

• FNJA *FNlB *Fl21A *Fl21B FI GURE 6.2-72K

• PNL873 *PNL875 *FSL2JA *FSL21B

• PNLf3qS *PNLeq7 COMBUSTIBLE GAS

• MOV2!5A *MOV2!5B CONTROL SYSTEM LOGIC DIAGRAM SHEET 4 OF 5 SETPOINTS SHOWN ON LOGIC DIAGRAMS ARE FOR LOGIC NIAGARA MOHAWK POWER CORP.

CLARlFlCATION ONLY ANO MAY BE ONLY APPROXIMATIONS OF THE ACTUAL PROCESS SETPOINT. REFER 10 SETPOINT NINE MILE POINT-UNIT 2 DAT A SHEETS FDR ACTUAL PROCESS SET POINTS. UPDATED SAFETY ANALYSIS REPORT USAR REVISION 3 OCTOBER 1qq1

SO!R:E MONITOR CONDITJON CONTROL ACTION RESULTANT MONITOR SW-SR HYDROGEN RECOMBINER AIR INLET VALVE HYDROGEN RECCM31 NER

• MOV25A CLOSE AIR INLET VALVE G

• MOV25A CLOSE P873 SW- HYDROGEN RECOl-l!INER AIR INLET VALVE HYDROGEN RECCM31 NER

• MOV25A STOP AIR INLET VALVE R

• MOV25A OPEN SW-SR HYDROGEN PS73 HYDROGEN RECOM3I NER RECOMBINER AIR GAS BLOW1::R FAN INLET VALVE HYDROGEN RECOH3I NER

• FNl A RUNNl NG *MOV25A OPEN COOLING WATER l NLET VALVE G

• MOV26A CLOSE 01 V I HCS RECOM:ll NER ~

I A lNLET HYDROGEN RECOM:ll NER TEl-P COOL! NG WATER I NLET R VALVE *t<IV26A OPEN

~

HYDROGEN REC!Jt.BI NER

• RBNRIA AlR INLET w VALVE *MlV25A FULL C OSEO P873 HYDROGEN RECOM31 NER READY

• RBNRl A COOLI NG WATER INLET VALVE FULL OPEN MJV26A HYDROGEN RECOM31 NER COOLING WATER BLOCK VALVE FULL EN SOVl 0A DI V I HCS RECOM:II NER 1 A HEATER GAS TEW DJ V I RECOMBI NER I A HEATER LSK-27-130 2

GAS TEW HIGH DI V I HCS RECOM:ll NER lA HEATER OUTLET GAS TEl-f OJ V I RECOMBI NER I A HEATER OUTLET GAS TEM" HI GH tllTES:

I. ALL lNSTRUHENT St EQUIPMENT tu1BERS TO BE PREFIXED WlTH "2HCS-' EXCEPT WtERE A DIFFERENT PREFIX lS SHCNN. AN ASTERlSK (*) WlLL REPLACE THE DASH <->JN THE PREFIX FOR INSTRl.MENTS ANO EQUIPMENT WHICH ARE PART OF THE NI.CLEAR SAFETY FEATURE SYSTEMS.

2. LOGIC FOR HYDROGEN RECOMBJNER *RBNRlA IS SHOWN. LOGIC FOR HYDROGEN RECOMBINER

• RBNRlB IS SIMILAR.

3. ASSOCIATED EClUIPMENT HARK MJMBERS1 OlVJ OIV,IJ OIV,J OIVJI SOURCE1 LSK-27-13E REV.11

• fi'i4A *Til'4B *TI'i2A *Tii2B FI GURE 6.2-72K

• TT15A *TT15B *Tll2A *Tll2B

• HDV25A *MOV25B *Tl1'4A *TU4B COMBUSTIBLE GAS

• HOV2SA *HOV2SB *TSH1"4A *TSHHB

• P873 *P875 *Tll5A *TI15B CONTROL SYSIEM

• P~ *Psq7 *TSH15A 4,# DENOTES Slffl.IED BY RECOMBltER VEfflOR.

• TSHl5B LOGIC DIAGRAM SHEET 5 OF 5 SETPOINTS SHOWN ON LOGIC DIAGRAMS ARE FOR LOGIC NIAGARA MJHAWK POWER CORP.

CLARIFICATION ONLY AND MAY BE ONLY APPROXIMATIONS OF THE ACTUAL PROCESS SET POINT. REFER TO SETPOINT NINE MILE POINT-UNIT 2 DATA SHEETS FOR ACTUAL PROCESS SETPOlNTS. UPDATED SAFETY ANALYSIS REPORT USAR REVISION 3 OCTOBER 1~~1

r--::::::-::i---~;~-- 1 1---~::::::::r--~~-~-- 1 1 1 t.,_ ~

_ _ _ _ _ _ _ _j i ~--..~-+f1""""-e1 i i e7~~-+t"'"-.i<-e1 i L----T ____ J r---t2~::~-:

l__:~Jr=-

I ' '

i- - - --- ---- - - - - - - - -- - - - - ----- - - .J

[__ :-:":'.:'::::-~T----< ~v... I

' ' r--r--------.,

~ r------------r---::~~~--~~

!  ! H  ! l:  : iii~  : t- Etf L--~-------------~-~~ i ~----r---"

l_, *----------- ------b=i;;.::--~_________ j i t--lil:-=*

i i ~~--:! ,_,.

I -..-

1

~-----------------J

=-t~:*. *~*---M2

"=?-

'------------- I~~

I

.w. 'T l<**t.. .. ::.

2-4.llS*M--.._Ul'*l:> J"H ~ M llOfl" J

'-r.r.~

FIGURE 6.2-730 CONTAINMENT LEAKAGE MONITORING SYSTEM NIAGARA MOHAWK POWER CORPORATION SCUU::£, Pto-&IA-9 NINE MILE POINT-UNIT 2 TITLE. CQNTAIMENT LEAKAGE HON{TOR!HC SYSTEM UPDATED SAFETY ANALYSIS REPORT USAR REVISION 13 OCTOBER 2000

THIS FIGURE HAS BEEN DELETED FIGURE 6.2-74 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT

FOR TYPEB TEST CONDITION DOUBLE O*RING SEAL FIGURE 6.2-75 N2 PURGE PENETRATION NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT USAR REVISION 3 OCTOBER 1991

O*RING SEAL FIGURE 6.2*75a TRAVERSING IN*CORE PROBE MIO*SPAN SINGLE O*RING FLANGE OF 2NMT*EJIB AT 2NMT*Z31B PENETRATION NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT USAR REVISION 3 OCTOBER 1991

F"O R *TYPE 8 TEST DOUBLE 0-RING SEAL FOR TYPE B TEST----' DOUBLE O*RING SEAL FIGURE 6.2*75b TRAVERSING IN*CORE PROBE 2NMT*Z31A,8,C,O&E PENETRATIONS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 I f *.;>'

FINAL SAFETY ANALYSIS REPORT USAR REVISION 3 OCTOBER 1991

THIS FIGURE HAS BEEN DELETED i

FIGURE :6.2-76 SECONDARY CONTAINMENT PRESSURE VERSUS TIME AFTER A LOSS OF COOLANT ACCIDENT (LOCA) I NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT - UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAr~ _RE'!IS ION 3

26 24 22 20 G:. 18 w

w a:

C>

w ts g

s....

w 14

<t a:

w Q.

L 12 w

_J

\

<t 10 z

w a:

\

w 8

8 6

\

\

4 2

~

0

-20 0 20 40 60 80 100 OUTSIDE AIR TEMPERATURE <DEGREE Fl FIGURE 6.2-77 EFFECT OF OUTSIDE AIR TEMPERATURE ON THE MINIMUM REQUIRED ORAWDOWN DIFFERENTIAL TEMPERATURE NIAGARA MOHAWK POWER CORPORATION I THIS DRAWING CREATED ELECTRONICALL y I NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S

0 0 0 ,...

0 ..,,

w CJ 0 0

co 0

'IS'

> 'IS' CJ i='

a: z w w I- 0 a:

< oa: oW 31= 0 Cl')

cow (") 31=

UJ ~ 0 w > a.

c 0 w 0 z (/)

w a:

~

w u 0

c a: 0 oU:: 0

"="LI.. N

> N w

UJ

(/)

w a:

a.

0 t=

<,... 0 0

N ,...

0 I-UJ 50 100 150 200 250 300 CAPACITY (10 CFM)

FIGURE 6.2-78 SGTSFANPERFORMANCECURVE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMl=NnMl=NT .4 SEPTEMBER 1983

THIS FIGURE HAS BEEN DELETED.

FIGURE 6.2,.,.79

(

RWCU ARRANGEMENT FROM ISOLATION VALVES TO WATER SEAL NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

l

~*

~ ~

I i

I I

• THIS FIGURE HAS BEEN DELETED I

_ _ ___J

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

FIGURE .6.2-80

• I I,

I l

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

I

--) ..~ ... . .. -

CONDENSATE STORAGE TANK 2CNS-TK1 A

--1 OUTLET EL. 253' -6" INSIDE CONDENSATE+ INSIDE f

STORAGE PIPE TANK BLDG TUNNEL EL. 247'-0"

....__ _ _ __.. EL. 245' INSIDE REACTOR BLDG 21CS*MOV129 EL. 242'-6" WETWELL EL. 199'-0" 21CS*V28 STR1 SUPPRESSION POOL I

I I*" ORC EL. 186'-9" I

21CS*V27 21CS*PI EL. 180'-2 3/4" FIGURE 6.2-81 RCIC PUMP SUCTION FROM

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

" ~

I

~

THIS FIGURE HAS BEEN DELETED i

i l FtGURE '6.2-82 NIAGARA MOHAWK POWER CORPORATtON NINE MILE POINT-UNIT 2 I FINAL SAFETY ANALYSIS REPORT

. I

~ ,*' - [ .

TO CONDENSATE STORAGE TANK, 2CNS-TK1 B INSIDE CONDENSATE STORAGE TANK BLDG

. f.

EL. 252' -2 1 /2" INSIDE PIPE WETWELL TUNNEL EL. 208'-0" 4INSIDE I REACTOR BLDG 2CSH*V59 EL. 190'-6" SUPPRESSION POOL TO r--ORC

.REACTOR VESSEL 3

EL. 178'-0 14" 2CSH

• P1 EL. 175'-0" 2CSH*MOV101 EL. 177'-0" FIGURE 6.2-83 HPCS PUMP SUCTION FROM SUPPRESSION POOL

• NIAGARA MCIHAWK POWER CORPORATfON

• NINE MU POINT-UNIT 2 UPD~TED.t-SWETY ANALYSIS REPORT __.

-i-:ERTICAL SEPARATION REACTOR VESSEL POSTULATED BREAK ELEV. VIEW EL. 309'-1 J115*

POSTULATED BREAK - - - -

FROM 6TH PT. :3 267'-3 s1e*

l HEATERS PRQ017 (ZERO GAP) 21A, 218 23A, 238 PRR018 (ZERO GAP)

ALL INSTRUMENT & EQUIPMENT r1 1s TO BE PREFIXED WITH "2FWS" FIG. 6.2-84 FEEDWATER LINES (FWS) TO REACTOR PRESSURE VESSEL NINE MILE POINT NUCLEAR STATION-UNIT 2 SCRIBA, NY UPDATED SAFETY ANALYSIS REPORT L _J USAR REVISION 16 OCTOBER 2004

2GSN-VS3, VSS 11 /2" 2GSN-V54, V56 I INSIDE REACTOR I BUILDING 1~ EL. 294'-0"C) 2 1 /2" 21AS I 21AS-V173, V176 *SOV168 I (NOTE 1) i 1 1/2" & *SOV166 I

I CL1S:l4i:l302 I I I

( I I

(>I FROM REACTOR I

l 2GSN BLDG INST.

I 2GSN -TK2 ORC I IRC I

-V52 AIR RECEIVER TANK 21AS-TK3 ....I,...

I EL. 264'-1 1 /2" I EL. 261'-0" I 2GSN-V58 AT 110 PSIG I

l 1 1 /2" CL153 CL302 NOTE 1: 2IAS*SOV166 HAS A MANUAL BYPASS VALVE, 2IAS*V1519 FIGURE 6.2-85 NITROGEN SYSTEM LINES TO REACTOR BUILDING INSTRUMENT AIR RECEIVER TANK NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT USAR REVISION 24 OCTOBER 21Z121Zl

~ .

~**-*-

~-* " - , .. - .

~

' ~

THIS FIGURE HAS BEEN DELETED i

~---~- __...___

FIGURE 6.2-86 l

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

\LOOP* A .

IDISCH~RG~ ' .

\LOOP* B .

0

AZIM~Tli~~1.§. ~

1 DISCHARGE

\A~~f!l_UrH - 54° LOOP-B SUCTION AZIMUTH .. 275°:

.270° 90° r, LOOP-C LOOP-A i SUCTION \ SUCTION

AZIM~Tfl.: 261°~ AZIMUTH - 95 ° *

• fj()ci

,I NOlUJIAL~POOl LEVEL I EL - 200' .

I DISCHARGE \EL - 198'

• SUCTION (TOP) *~EL _:\189'*8~--.

POOL BOTTOM 'EL - 176' FIGURE 6.2-87:

• NMP2 - RHR SUCTION & DISCHARGE SCHEMATIC (PLAN)

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

RC-PRIMARY CONTAINMENT SC-SECONDARY CONTAINMENT osc J!

ORC: IRC PENETRATION VAPOR OR ATMOSPHERIC PRESSURE APPLICABLE H =ELEVATION LOOP SEAL FIGURE 6.2-88 TYPICAL WATER LOOP SEAL

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

40 w

a:

(/)

(/)

w a:

Q.

iii 30

t a

c 25 0 1 2 3 4 5 6 TIME (HOURS)

FIGURE 6.2-89 NOTE: THESE RESULTS ARE VALID FOR DW TEMPS 70°F AND ABOVE DRYWELL PRESSURE DECAY TRANSIENT FOR HIGH PRESSURE STEAM BYPASS TEST NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMFNnMFNT ?7 JULY 1986

20

-en

~

D..

w

§ 15 en en w

a:

D..

..J

..J w

~

>a:

c 10 1 2 3 5 6 TIME (HOURS)

FIGURE 6.2-90 NOTE: THESE RESULTS ARE VALID FOR DW TEMPS 70°F AND ABOVE DRYWELL PRESSURE DECAY TRANSIENT FOR LOW PRESSURE STEAM BYPASS TEST NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

.llllY1QRR

(*-*-*

\

1400 1300 Ui z \

0 cc 1200 \

\

~

cc w

I-w 1100 \

\

e c

<C z

<C w 1000

e cc w

I-

<C

(/)

I-900 w

c..

0 cc Q

w 800

...I m

<C I-c..

w u

u 700

<C

e

e

<( 600

e 500 400....__________________________.____........._____.

0 50 100 150 200 250 300 SPRAY NOZZLE VELOCITY (FT/SEC)

FIGURE 6.2-91 SPRAY PATTERNS AND PARTICLE SIZE NIAGARA MOHAWK POWER CORPORATION NINE MILE* POINT-UNIT 2 UPDATED SAFETY ._ANALYSIS REPORT u~AR REVISION .4

f.

SPftAYHEAD~'

~ 49*

'i I

SECTION A-A (TYPICAL)

FIGURE 6.2-CJ2 RHR SUPPRESSION CHAMBER SPRAY HEADER, AND SPRAY NOZZLE LOCATIONS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 PLAN EL 215'-0" UPDATED SAFETY ANALYSIS REPORT

. USAR REVISION 4

SECTION A-A SECTION B-8 PLAN EL ze9*-0*

SPRAY NOZZLES OMITTED F(JI CLMITY FIGURE 6.2-'!3 F(JI LOCA TKJN SEE FIG\JRES 6.2*'12 At() 6.2*'14 RHR DRYWELL SPRAY HEADERS NIAGARA MOHAWK POWER CORPORATION NINE MILE. POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAA REVISION 4 OCTOBER 1qq2

• ~..:"

SECTION C-C (TYPICAL)

SECTION A-A

~

oo'*llf. EL!Ol'**f ~/Sf'RAYHUDIFEllAl.El

. EL.>Ol'-6"--*-v

~ - EL2.!tfl'~g*

t 1"1* ~

SECTION D*D SECTION 8-B ra1.u;GED PLAN El 289'*0" FIGURE 6.2-g4 SPRAY NOZZLE LOCATIONS FOR DRYWELLSPRAY HEADERS f l. NIAGARA MOHAWK POWER CORPORATION PLAN EL. 289'*0" NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT i USAR REVISJON 4 OCTOBER Jqq2

1.00 ("'- I I I I I I I I I I I I I I I I I I I I I--

I I I I I I I I I I I 1. I I I I I I I I 0.95 _._ ~~ ......., Outside Air Te~perature 1'- I I I I I I I I I I I I I I I I

~

I I I I I , I I I

'IJ I I I I I I 0.90 I I

- - --.-o deg F

• .~

.... ,I l

,_ _._ 20 deg F 0.85 ...

r>L, .... ...

( li

..... _.,_40deg F

,... 0.80 ..... " "' :X-60 deg F

~

u.. - ... -....

~

85deg F

... r....

\ J.

0.75 .... ... ...

Lo i....

~cu "" .... ..... .....

-~

':: 0.70 1-.,.

=.... 0.65 --- - -

0 ~-

r-..

~

0

~-

\lo..

~

0

~

(..) 0.60 -.. ,....

- .....,:>'.(

~

'-~

,._ ~

0.55 ~

--. L.

~-'

0.50

- ""I I 0.45 0.40 0.25 0.30 0.35 0.40 0.45 0.50 0.55 0.60 0.65 0.70 0. 75 0.80 0.85 0.90 0.95 1.00 Differential Pressure Measured at Steady State 1 Hour After Start of Test (" wg)

FIGURE 6.2-95A CORRECTION FACTORS FOR INLEAKAGE AT 0.25 INCHES WG NINE MILE POINT NUCLEAR ST ATION - UNIT 2 SCRIBA, N. Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 16 OCTOBER 2004 _J

1.15 _,_""""'...

ICHARCOAL FILTER

OUTLET TEMP- F I

I ..!

,,..J --0-:-80

.- _,.... .... -a-go 1~11

_.,_100

..1..1 l...tll lo' i .10

...t*

--.....:.110

- ... ....,.. ..... 120 V' V'

. ... ,,. -X-130

_[_,;" *\.

+/- -

J

..I

.J'

,,,,,,,., ...... -b-140

... _.......

• I.I'" I /. ' / ,__

J'

.... ... '..,; _,,, .... 'l C\I _.._

u.. 1.05 v 1.-

[_/

a:

1.....-

.- v

~-

.JI 0 .....

t.-' ~

~

1.....,111 i;....

-:IT ...... _,,,,.

I ......

~

• .J

• • -:,., .. / __,.

z 1.00 - .... ,.

17 i:;7 IT 0 I/

i.....

.1 .....

I..'

j:::

l/

~,.-

1'..,

0 i/

Ir UJ .

i...... l.J!f" I~

a: ... ......,,,. _.\("

I..'

a:

.J'-

I/ ./ -~ I./

~

0 0.95 I r '-"'"

0 ... *'

_.i['

.I ~

---~

/ I/ ~

JT

....... I/

.......  !/

I/ /

Ir .....

.J

• ""... .Jllr

~

0.90 , I/

l/ /

I r

,.... ~

r' V'

~

. v _..... _.,......

./

0.85

-20 -10 0 10 20 30 40 50 60 70 80 90 100 OUTSIDE TEMPERATURE DURING SGTS SURVEILLANCE TEST (F)

FIGURE 6.2-g59 CORRECTION FACTOR FOR FLOW METER READING NINE MILE POINT-UNIT 2 SOURCE: CALC. ES-259 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 1 S OCTOBER 2002

80 70

,,...... UNACCEPTABLE v.a "O

c:: REGION D 0

, r(

~

Vl

........., /

0

.. v vJ E

E= 60 c:: ~

~ ~,.JI 0

"O

~~

B

~

_,.,,,. ~I J,...... ,,.-

so ACCEPTABLE l-...1 y REGION

,......t...r

~y

µ r

,,._ l-1 r-

~,.....

n--~r 40 I t 1000 1100 1200 1300 1400 1500 1600 1700 1800 1900 2000 2100 2200 2300 2400 2500 2600 2700 Corrected Inleakage Aow (ACFM)

FIGURE 6.2-95C ORAWOOWN TIME VS.

CORRECTED INLEAKAGE FLOW NIAGARA MOHAWK POWER CORPORATION I THIS DRAWING CREATED ELECTRONICALLY I NINE MILE POINT-UNIT 2 SOURCE: CALC. ES-259 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S

1.35 RB TEMPERATURE - F-j I I I I I 70 I

65 - f.; J I 80

=-

1.30 I

,,. ,..._ I -

75 l 90

_, .,,. ~"

... 8~ ,, I 1- I-

=

.I i

_, 100

,,. ... ,,. , I I_

,,. ""' -~*

z,_

, .I 95

,, , ,,, ,,r .,.

_, .I

.,. ,, / 105 1.25

~

,, " ,,, t l

,, ,. . / ,, Ir I/

I/ I./

(t) ./

~

lL ,,,. I I Ir

• ~

.r / ./ I/

I

,/

,,. /

~

a:

I" I./ ./

JO Ir 0

.I r- ... . ,,. , ,,, II"

~

i .20 *-

r IF F /

u .....

~

1..,r ii"'"

~ .,.

u..

I.......

_;r '/

.... ..... .I' z ,,,,

.,.. ii"'" .

- L.;'""

0 .......

"" ....u;

_. .Jr

_.. ~

., .I t:= .......

... 7 1.15 ,, ...

(.) .......

w ....

1" A....I a: ..... ....,. ,,,.

• Y" cc ,,....

.I

....... L.....-

0 ,..

~ ~

~

~

~*

()

• ~

~

~*

1.10 _,,. .J" .... _,...

.... - ... i......

~

SELECT THE NEAREST LOWER REAGTOR BUILDING

~ ~. ~

~

r..,.. TEMPERATURE FOR

~

1.05 - *- - --

~

• - - DETERMINING THE INLEAKAGE

~

.- ~

~

~-

l7

~

1.00

-10 0 10 20 30 40 50 60 70 80 90 100 OUTSIDE TEMPERATURE (F} MEASURED AT STEADY STATE 1 HOUR AFTER START OF TEST FIGURE 6.2-g50 CORRECTION FACTOR FOR INLEAKAGE AT -20°F OUTSIDE AIR

& 105°F REACTOR BUILDING AIR NINE MILE POINT-UNIT 2 SOURCE: CALC.ES-259 UPDATED SAFETY ANALYSIS REPORT 1 USAR REVISION 1S OCTOBER 2002

PP!MAli'Y MODt!S ~

t. .tt.t.(lilPTY PftESSUR( OATAet.N<

MODE A ACCIDENT OR RCIC BACKUP, REACTOR AT HIGH PRESSURE, SUCTION ~=T~vtft.tOl.IC DATA St.IBYHEO TO !lfflSO FOR RtV£W, CXJ fOCATts THE'. DATA IS t<<)T FROM CONDENSATE STORAGE POSITION 0 I 1

2. ~ HJICAT(S UAXMM ' ........ VN.UE Of PNWl(T(lt roR lHC MOO£ SPECf'IED.

2 3 I 4 5 I 6 7 8 9 10 11 12 13 I 14 FLOW GPM IN/A 1550 t550IN/A J, ~~~:= ~NO:M.~ ~i: ;,;~~ti"'~~::r:.:.s~L 9f: IHO.ub£0 WKH 6.

PRESS. PSIA I 14.7 I I JU45 TEMP. "F IAMB.qo,. .. UOOE(WITHAPUIM'TOHOI' ~ FfNCIAV'ESS!LPft£$SU'IC.Of21!liPSIAntErLOW MUST I OEEQUM..lOOACRCATOtlt1Ni.IJ!dlCPM.

=tBf:~=T=~!i~~~~~=~~~

7 . . . MOOE r, nc NET POSmvt SUC:TIOH H(AI) U#Sttl AVM.ABl.£ AT "R!rEfttNCE LOCATION 2FE£TA80VETt£Pl.lt.IPUOl..fiTNJFLNIC!Ll.JSTtQUALOROa:r:o...s_n.THEHP5ti AVAl..M!ll,.( AT THC PWP sue.new HOZZl.£ MUST EOUAL THS VAL~ PU.IS TtE: CFFEREHCE "

(SEE NOTE 21l EL£VATION8(fW(EffTHCFttrtMJC(LOCATIOflNCI 1H(C!HT£RU£0f Tt<P\.MPSUCTK>>IHOZZLE.

MODE B ACCIOENT, REACTOR AT HIGH PRESSURE, SUCTION FROM SUPPRESSION POOL.

B. ~~ii:::~ ~o,!.,.~"~\~~vfl"- GPM.. TI£ .WM.ML! fM)t wsr EOUAL OR exam POSITION 0 4 5 I 6 7 8 g 10 11 12 13 14 19 20 1B FLOW GPM 1550 NI A 1550 1550 NI A 9. ~~~T~c:::._r~~.; ~f'~RIST==: ~~(l(!.=E~AKO ON PRESS. PSIA I 1145 TEMP. "F 1t2t114 10. ~~ ~~~::RST~..:O"'i~:.C~ T~~:.:.,EH :,,::-:::::.w.":.S*-! N(J MA'° 8C

11. ocu:n:

15.  ;~~~~~~g ~l~A:.::... ~Er;:cc:,o:(rJ~ SITE 5(AVIC£ WAT£ft 16.6PVAt.tt:!rOR£~TtnTl-94C(*8WftSOSeoPEARtASHOTto.

17.TAfll(llHOICATESVM..vtPOSlflONOURflCVNbOUSOP£ftATtilGMODES.

18. =~E!:~~11~ifJ:.=f~~z~:c~~~o or

=-

20. W WOO( t NfD wtTH A vt!Sll PAESSUAE l4,7 PS&A.M f'LOW '!lttR...1. NOT EYtttD FOR M001115 Pr.&t&, cHr T1-+tfltO OP TA""-'1..~Tl!O 'FLOW Sij~f..L.

01\..IV*"E.C TO TMllii Vi&&IEL W ~TH ACJ.CT'CR "6:S'BEL PRE~~ut:allii AT 1215 PSlA, U TH!. FLO\N Sf'ECIFle() !='OR MOOE CC MUS;T &£ EIXJAl.ED OR llX.C.i:iDliC WITM IWi SUtTION. ~~M TWI GONDEN~TE C:.,TOtu..Ge fl."f~T6M

• No w1n4 T,... Rs.i.cro* Pto.E5-&u1u eqiu~~ To 1a1s PSIA **

t3 ~:';~0~1t~1~~ =t~~~~~!_~~~~~~~\.~~o~:~~.

CT.e.RTUP ANO A.1.L MotJ<<IS ON TI.fl! P"OCllU Ot,A,a~) 'IHAL.l. NOT m:EE:D 7175 fiiPM A.VO THE MINIMUM FL.OW ".(ALL NOT IDE !)Et.CW "'40 GP'M M NJt"l-Cl.VITA'T'ION VAl...VI!.

g{:&

MODE E ACCIDENT, SYSTEM INJECTION AT RATED CORE FLOOD. SUCTION FROM Ht!AH f'M1!Alftt wr 5tR41 "'c -- -**----**** ~ ... --**~ . E22-1010 Ul.fl" 1111.0. Slf;T~ PUC l>IA ...... ~~* .. ********* ** 922-1020 CONDENSATE STORAGE HIG11 PRU!i\flf cmr '"'"'-~DUI~ SPtC *-- - -*-*--******* E22*40K>

POSITION 0 J

1 2 I 3 4 5 I 6 7 8 I 9 10 11 I 12 13 I 14

.;;"..,';',"-.a NIA 58 B56IN/A PRESS. PSIA l

'n J l I 8D T ........... ;i; TEMP.

• F NAB. N.48.

2014 014ot VAL'\.11!. P0:$IT\Q\J TP.8Lf

~:..~=-~ 79 - i.-t..*_.... r- 24... ---25.,...,.231 . .

v~vc r"'OoJ ltll)4I "°JO f'l)il l'.?lt l'O*.S "'1U F.O.S8 MaD&. A 0 0 c c c c c 0 MOD~ a c 0 c I: t Q c ()

MCOE c c 0 c c C' 0 c 0 Mf;~ C> e 0 c c c 0 c 0 MOJ:JE: t: D 0 c c c c c 0

.MODC I'" c 0 e c c 0 c 0 MOD£ G c: c c e c 0 0 0 NIODE H 0 ~ 0 Q c c c 0 c c c c" c MODI! 3' 0 t c c 0 Mr)DS 5 Cl r c c 0 c

"10Dli CC O \l;ltV CPE!l I! 0 c 0 (l c SOURCE: 731E932AF FIGURE: 6.3-1 Note: Mmh data on thh sheet war used far HIGH PRESSURE CORE SPRAY original pipe and compo11ent si;ing. Design PROCESS DIAGRAM requirements are based an Math specific SHEET 1 OF 2 analysis.

• NINE MILE POINT -UNIT 2

• OILU OUIGN CmlOJflOHl lt50JISINJOil!~ UPDATED SAFETY ANALYSIS REPORT t!ltJ1J1°'irtra1.l.4..-

L USAR REVISION 18 OCTOBER 2ooa_J

fest ..

\'

'1 ' li&t1;J21- A i3l "£4).a. ... i&l. *"'-' ~.\ ~ ..... isl. ..lit.. j 9 ~ A 11 a I di .iJ 11 l Jo i12 \ A A:"-'**< I I 1

.ll. *""'

r

\1 MODE J.I POSITIONO FLOW GPM ~

I SYSTEM TEST. SUCTION FROM CONDENSATe STORAGG

% ~  ?? 23 PRESS PSl,4 /.f.7 A A TEMP °F AMa 1,.40 lt;;~~d~ff#  ;;'"=u u,~;;.,,.

~

MODE .S P03/TION FLOWGPM Q

SYSTEM ON STANDBY DUTV N/A I

0 2 3 4 5 h 7 ,, . 10 // 12 0 '%

14-PR£3S P.S/11 14.1X xx TEMP "F

'Jf#,!'ff#

ftMB'"4D

_,,_ "9'.., AMS

-~"""

~

ACCIDENT Olt RCIC BACK-UP> REACTOR AT HIGl-I PRESSURE MODE CC (SGE NOTE; 22).SUCT/ON FROM T/.J/: SUPPRESSION POOL PD51TION FLOW GPM Q 18.5 19 i---i-J/57 5 10 SJ.7-I/

" " "'* -+.,o- 14. 15 11.111 11.S

~N(A IS I I 21! I 14.1 TEMP °F ' .%. 1°'9;AUA 9',,,1--+- 9{,AAM MAX PRE:SS DIFFERENCfF t.O I

~

~

TABLE IL LIMITING LINE LOSS FLOW.PATH

~

'-7-8-'f-IO-ll-J'Z.-/'5 IO-Zl-%1.-Z!!l-Z4'-'ZS-2!U/

4

-...j

~

4

~

l

~

FIGURE 6~3:1.1 1

'I HTGHPRE-SSURE COFfESPRA'n I

PROCESS DIAGRAM t

_, SHEET2 OF 2 NIAGARA MOHAWK POWER CORPORATION 4

NINE MILE POINT -UNIT ~

- r1:

1

.,,. ig1

., 1~!

'!' ., .,. I l~r~ 1s_r \§_f 11' 1.ZJ .,., "'1' l_§f

' ~ §_! . I !.QI UPDATED SflFETY ANALYSIS -REPORT

_USAR~!SI~8 NOVEM~§:R __ 19_<?5 _ - --. t

s a* .. ,,, . *

'f !O Tl<Bl..[11 1~LA~~r:i. ~~~~~;M.t't'N~~~~~~~". .~:~~~ffiD Ll!Jllt<<;LKLOSS 0 * 'I' * * ' TO NtOO FOR REVCW.cgJWCATE:S T~ Q,t.TA IS NOT SlGNlf"ICANT.

2-~~tii:6.MAX'Mt.J,n.NOMM.ll.MVAl.1J(orPAFl:AM£T[RFOR:THE

"*' >< I ':>-., >< >< >< ><

~40 ~AMS ,'% .3. ELEVATIONS ARtNOTINCLUXOINTI-!: APVALUESGIVEtttlEV,&,TIONS SJiAlL 8( NCll.C(D WHEN OCH:Rl.t:HN.:; FINJ.t. VALLCS roR THE EMPTY MAXPAtSSURt OATABl.,t.tfC;S.

ORO?f'tET 0 * 'I'

~BWO. 6 HUOO[ S, TH!: M"SHAVAl!.ABl.E WST EOUAL TH( VALVE SP£Cf'EOIN NDT(!:iPLUS20FCET.

7 100CPMIS Kt.UOE:ON TH[ fLOWCfV[NFOR'UOOI: 0 TOC01.1?£NSATE rQRLEAKAGtlNTHERACTOR!tiT[RW.LS.1114CPl.4lNUOOE£J.

s ~r~N'No12~~s~~E~~r=~tAL PRESSUR( OCTW!EN Tl-( REACTOR' 9 lH( FLOW SPCCJrlEO roR uooc r IS Tk( UA)(llJUl.I ALLOWASU:.

10 WE AP0CTW£ENPOSITION15 .U.Cl6Wll.LB!'. DE1£.RW.£DINPRt-ortRA-TIONAL TE:Sl THE AP Wl..l er: AOJUS'!'(O TO U(!;T nc FLOW RtOUIR\:t.l("ITS OfUOOEO.Eonr y,-1*0001"""' 12.PANGSYST£MOESIC14PRESSl.Ri:ANOTtJ.PtRA.TURtANOTH£ESTIMATEO LNC S(l:(S Ali£: f"Ofi Nf'ORYATION OM..:r ACTUAL OCS!CN H:M?tRAllffl(

"*' I'>< 1><1 ~ >< x P-PAATl...LLYOP!N AWJPRE:SSUR(ANOL"1'.SfZ£AS()(TtR\.lllN£0B'O-"i:RSSHAL!..M((T TH£Pf!OC£SSOIAGRAUHY0RAULCSF!£~CM!NTS C-fl.UYCLOSl:D 13. ANTl*CAVITATIONAL VALVES 0-fULLYOPEN

2. LPCS SYSH:M OCSIGN SP(ClrlCATION J OE:Lf:T[D A MJC\.CAR50l.£RSYST£MPROCTSSOIAGRAM 5_ Rt:SCIUAL HCAT R(MOVM.. SYSTEM PM>

SUf'PORTJNGOOCUMENTS 1 PRllCa;JNSTRUMENTSYMf!OlS ACCClfN1 5YSTEL4 OPt:~..:.T!N(. AT FMJNOUT 0 * ' I ' ~-.-_,.-.--,---.---

~ 1eoo 1 1aoO I>< >< 'X l.IAX?fi£SSURE OROflfEET Note: Mode data on this sheet was used for original pioe and compon_enl sizing. Design requirements are based on Mode specific analysis.

SOURCE: 761E220AF FIGURE [6.3-2 LOW PRESSURE CORE SPRAY SYSTEM PROCESS DIAGRAM SHEET 1OF1 1NIAGARA MOHAWK POWER COf~-PORA-fJON ININE MILE POINT -UNIT Z'r-tuPDATED SAFETY ANALYSIS REPORT

,3 4 '7

HPCS FLOW INJECTED TO VESSEL BASED ON MINIM~M TECH SPEC ACCEPTANCE CRITERI~

..... ~ :: ~ .~ lt ~= "= ~~ *~ =---*~; ~ - *-*-------~~---,..--.---- . -- ==~ ~= ~--------*,.__

1200.--..--..-.--.----y---.--r-r-r-1r-r-r---r---r--r--y-y---,r-T-r--r---.--r--Y-r-ir-T--r--Y--r--r--r-r-1r--1

---~--

- - - - - to- - - _ .. -- --* - * - *, _

---

~-II- f- - -- - - _ -.----*---- -- ___ --* - *- -- -i.- _ --

• - ~ . -- - *- - i--- - ... - - - ,_ - - - - ~ --

=:== --:: ------*---.---11--1--1---tt---t*-,_ - - - ..,.-

---

*-----------il--11.--8--

1000 l'i....

-..--..-.---1r--

• -11---9-- --*-*--'

- =:=

---1---1---f---t-+--t--t-t---t--'1-..... - ....

_,4_.___.__.._.,._,.__._,..__....__-t--_*--t--*- ---ii-ti--+-

f- - *- - * - - - - *-

f-- - --

• ~~_.._.__.__,.__._..._..--1~~-----~------*----l~-*-------*9--11-*-t----- -~-*---~--

.:_--l-=t:":::!~.:::-=.:t=.::~:=.:r~.::.-=+~~.;-.:,=-.-::----i_;:-_;::1.. :--1-1-~~---1_;:-_:~*~~_;----i-;:-_-1-t.:-~.. ,-=-!:=!:=:!.= - - - --* --

r- -- . ~- _....__ - * --

• - ... **--l*-+--*-- - - ---

,._ - ,_ --1--1--1--f.---l-t--41--t--+~.... -~1--4*--+--+--+--.--.-.-.~-.....-----+--*- r - - , _ *--*

t -

=: :- :.:

I-l-----l--l--l-~l--l-l---l--l--l--l--l-l---lf--t--fllltood--l--t-+-t-tt-t-t--t--t--i-'"f-f--ll-

• 1

.__._....--+-_.,_-+-*~l--f--l---l--l--l--f.-..f--t--lf-""'~--1-t--11--+---t--+--.---1---1-t-tl--I*- - -- - -* -

1-1---1-f--.1-.1.~-+--t--t--I~~...-........ -t---t-1--t--t--t-l-t--t-t--t-t--t -

---

~-~~~~l--f--1---l--l--l--f.---l-t--ll--f----t-~~~l--f----t--+--.--~-~-~-----*-* -* -- -_-_*-_~*-__*:-

..........,._+--ll--f-l*--t---t---t--*-t- - - -* - -*

I

-l-~i-1---l---l--l--1--1---l--11-1-t---l--tr-_._..

-= = ~ -_-.. ._--_-*_--:.l-1-*~~-:~:.-=l-._-_:~__-:_~+l--. ..f-_-:_~_-:_~--++-~.f- =* ~ ~- ~~

+-+-+--I- -- -*- -* -*- *-*

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-=====~-------~--~-~-=~=~--~~~~~~~~~~~~~=~~~'_,~*=~=~~~~=-*---===~

~- ~-~- _-: :- : -_:_ ~-* *=* :-_ = = = = -=I=.-:..

• • . . :- = -__-:------- - - -- - := -=* =* = -'= == =*: . : _*..-

• - - .... _ _ -*- _ _ , , _ -ll--.._-9--l~l-il*-----l------+-11-+-1---4-----............ ': - -'- -

-=:*--~--*-----*-4--a--1-+--ti-_..-1-:---1 ~~ ~- ~-~

400 - * -* * - *** - -- -----.i--111--

=-***---- - -_*-------*----11-- =,:= := -* -

I~

-~* ~ ~:~ >-- - ~ *=*~

~~

1---. .

-- *- -* - --- i - - t - - t - - _ _ ... _ -*----

300 -*  :=. --_ -: - . ::::. ::-: :. .:.:: 1 - _ . __ _ . _ __. .--.--1_:_ *-* :--~ ~ ,=:.

---1- - --

- **- *- - *-- - *--* -- -- *------"1t-1t -----*-1--it----*-----*.-.....-1--........,

-* *- . -- -* -- - -* -- - -i--- - r- _ ....

--1-*-11----1-............, := =.=

-*-~---*---*-I--*'- -*I-I-hi'-" -- - - - --

_-:: *= =,:_-*-_-,_._

2GO

- --- - >----tt--**- - _,____ - - - * - - - - * - - * - - - - - -

-*-----1--1-_..,_._.__..,..,_ *- - ,_ ._

_.__.._-1-11--"W*-.--t-- - -

-- ,_ -*-f---* -- - '

.::--=~*------

- ~...:-_:-,_-~_t-_:..._*-_:1-t- --:-f--.._.-_:_. . -.-_.-...--- _;-,__-._. ,_-_,.....,_ . .

..._...,_+--1.-.- --~ . ..;;..

~---~--**::::-_::-_::iL:""_:t-~_r::::.::-~flllll

• -1-- - --- - *- - 1 - - _ _ ___. _ _ __ . . _ _ _ . . _ _ _ . . . _ , _ _ _ _ _ --i-- -

- *- . - -- - - ..__ ~- - '"'- - ....,_.... * - \ - r--- -

• - - -- - - - --1--i--1--~1--1--1---1--1--t-t-l-""il*-t-

'-~

HIOO FIGURE 6.3-3a.

HEAD VERSUS HIGH PRE$SURE CORE SPRAY FLOW USED IN LOCA ANALYSIS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT~UNIT 2 UPDATED SAFETY ANALY~IS REPORT USAR REVISION 13

• OCTOBER 2000

0 N

r:

5 u..

0 100 ----------------N-PS_H_R~E~Q~U~l~R~ED~A~T~2~F~T~.A~B~O~V~E~M~O~U~N~T~l~N~G~F~L~A~NG~E~----~~ I-w w

0 u..

~

90 3500 :r fl) 0..

z 80 3000 70 2500

~

~ ~

u a z

w 60 <(

w 2000

r:

u ..J u.. <(

u.. I-w 50 0 1500 I-40 1000 30 500 a:

w 3:

20 3000 0 0..

w fl) a:

0 10 2000 :r:

w

~

<(

a:

0 1000 co 0 1000 2000 3000 4000 5000 6000 7000 8000 GALLONS PER MINUTE FIGURE 6.3-3b Note: Pgmp curve represents manufactgrer's lest eul"Jle.

Installed per/Ormanee anti minimum acceptable HIGH PRESSURE CORE SPRAY Technical SpeeiBealion p1r(ormanee ii below th& eune. PUMP CHARACTERISTICS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 13 OCTOBER 2000

LPCS FLOW INJECTED TO VESSEL BASED ON MINIMUM TECH SPEC ACCEPTANCE CRITERIA 4IO ..---.~--. *-

- --- - . - - -- -~-*----t*--+-~--

--i----

- - Jo--

, - ===_-.._-_-_--_*-*-_----._--ii-__-_- - -

~-* ~ *-

-I---+--+-----.--- - -- ,___ -- *-* - -* -- -- --* --- - -- - -

===___.____________

-+--+--+--1---t

• - - ,_ -*--------.-._,1---11---11--+--&*-

!--- --

• __ ., *- f--*- - -- --

- *- - - - - -- -* - - i-------1---tf-il_--+-_______

--l-_..,._......_...__.__._-1--t--t--*t--*I-.-.. - *- - - - -- *- - -"'- - --

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

. ====

400 L.*- - -

. .1--=:*

1 1 -.--1-...-..~-.-.Jt---.--11--1-*- I -- - - - - -- - -

• 1--11---------- - -- - - **- -- - --------

-= ======-=- =

=:::~~~::---::~::.:~:::=::::::::::::--~:::::::=--:..-=--:-~~--t 1-11--11--1--1--...... .*...............--1--11--t--t-.._._..,... ,.,..._--+-t--f--1 -- -- f - - -

..... **- - ~ - P-- - - - ~- - - - - 1-- - - - - - t"- - -

. . l-t---it---11-1-t-f'-..-..._-ll--t--t--t--t-..a""'"---t---t--t----t-'-- * - - - - _..__ *._...____ , _ _ _ .. __ - *-* - - r--- - - - -- *-

l-ll--ll--l--l-f.--1---1--~f-l-ll--ll-l--l*-+"""-:a...1-!oo...-1--1-- - * - - - -.....- - - - - - - ~ - -  :: --=-

l---ll--ll--l--l-f.--1---1--l--l--l--l--l--l---l--~.I.--- - - - - - 1- - *- - - -* -- 1- - * - -- - - - -- -

=~~===I=---= ==- - \--.: _ *-~* ~-~ *= ==-= =-= ~=~ =~- ~~- -~ : .

! **== =--= =-f- - = *.:~*::=-=I===-= -_:_ ==*-

200

-~

---

.,..---- ------1---1------ .__

~

~-

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

. . ._ ~ - - - ~ =~ ~ ~ ~- ~- - ~ :: ~~ -:. ==- =

150 - - **- --* -- *- - - -* -- - _,.. --. _*- -_ -_ _ x- *- -- -

=~- --- - -- .

~--

-- - - ***- -- -- - --- -*- -- __ , _ - * - *-11--it---11--+--1---1-_._..... _ - t -

• --L-. _-_ _- -_ -_ _ -

~ -*- ~

--* - ~- ~ ~~ ~=. ~~-

-~~~~~~~~~~~~======-----=~~~~~~~~~~~!t~~=

• - -*-~--- - - -- - --11--------+- to-* i . - - -*--------------- _ . . . , . _ _ . . ._ _ _ ""'"'-*- -- - - - -

FIGURE 6.3-4a.

HEAD VERSUS LOW PRESSURE CORE SPRAY FLOW USED IN LO~A ANALYSIS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 13 OCTOBER 2000

100 1200 10 0 N

I lL 90 1100 0 0 I-w w

u..

80 1000  :;; ~

0 I

...J (/)

u... 0..

70 900 2 z 800

~

z

~ 60

~

.f! ~

u>- 0

<(

~ 50 w 700 u I

...J u..

u..

w 40

<(

I-0 600 I-30 500 a:

w 20 400 5

2000 ~

(/)

a:

0 I

10 300 3.H.P. AT SP. GR.= 1.0 1500 w 0 ~~"""""""'""======i::::::::::::::=::::::i::::::::::::::::::::::::::::=:=:=:=::=:=:==::=::::__J1000 0 1000 2000 3000 4000 5000 6000 7000 8000 9000

~

GALLONS PER MINUTE Note: Pump cunre represenls manpfaclur1r's test cunre. FIGURE 6.3-4b lns1all1d performance and minimum acc1pla61e Technical Sp1dticalion per(ormance is below this cune.' LOW PRESSURE CORE SPRAY PUMP CHARACTERISTICS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 13 OCTOBER 2000

LPCI FLOW TO VESSEL BASED ON MINIMUM TECH SPEC ACCEPTANCE CRITERIA 250 0 ..........

r----.. .... r----.. ...............

Ci) 200 Q.. ~ r----..

"r----..i'-...

~

Q 1----i ~

I '-....

g

'-.... r--..._

150 w '-......

0::

"-r-..

CJ)

CJ) w  !""' ......

0:: "['..._

Q.. 100

..J

<(

i= ' .....__['....

z w

0:: "\

w "

lL "-

50

~

Q '\

'\...

'"'\

f\..

'\

0 Ill lfll0fll 2000 3000 4000 5000 6000 7000

" 8000 q0fll0 FLOW <GPM)

FIGURE 6.3-5a HEAD VERSUS LOW PRESSURE COOLANT INJECTION FLOW NINE MILE POINT NUCLEAR STATION - UNIT 2 I THIS DRAWING CREATED ELECTRONICALLY I SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT

,', , t.

USAR REVISION ch;:~,-,,

.*-, *.. L OCTOBER 2006 I

1000 10 0 N

I LI..

100 900  !) 0 NPSH REQUIRED AT 2 FT. w w

ABOVE PUMP MOUNTING FLANGE LI..

90 800 0

~

I

{/')

ci.

80 700 z 70 600

~ 60 QJ

~ 500

>- 0 u

z <(

UJ LU u 50 I 400

..J u.. <(

LI..

UJ 0 300 40 I-30 200 0::

w 20 100 1000 2 w

BHP AT SP. GR= 1.0 {/')

a:-

0 10 500 I l.i.l

~

<(

0::

0 0 CCI 0 1000 2000 3000 4000 5000 61JOO 7000 8000 9000 GALLONS PER MINUTE FIGURE 6.3-Sb Nole: Pume curl'e represents manutacturer's lest curl'e.

Installed performance and minimum acceptable RHR (LPCI)

Technical Specification per(Ormance is below this curl'e. PUMP CHARACTERISTICS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFElY ANALYSIS REPORT USAR REVISION 13 OCTOBER 2000

0 0

uw

~

w

E j::

0 CXl w

E j:: 0 N

f-0 a:

0 0

0 0

0 0 8<d" 0 8 8c.o 8N 0 w

N N ~ .... l-o z

FIGURE 6.3-Sc COMPARISON OF PEAK CL~ADOING TEMPERATURE VS. TIME FOR LOCA ANALYSIS WITH AND WITHOUT FLOW CONTROL VALVE CLOSURE NIAGARA MOHAWK POWER CORPORATIO NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR RBVJ:S:Ic:Jm 7 "*

G M e_

• ~~~.!JiZ~~-

i-----------1---::::;::;;:;:;:::;:;:;:::;:;;::::::---*

• 1'wTIU'.:'Ml!"..:ll.~1 I hl:ii 1 _..."

10 FIGURE 6. 3-60 HIGH PRESSURE CORE SPRAY SYSTEM 11 1------N-IN_E_Mll_E_P_O_IN_T- - - - ; 11 SOURCE. PIO~!SA~l6 NUCLEAR STATION - UNIT 2 TtTlE* HfQfPRf.SSURECOM:~'*AYSY1l£M SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT A M N USAR REVISION 15 OCTOBER 2004

M COHOENSATE STOAAC(

KnS*JKIA l3S,HICA1.5 RCJ($'J&l£M IE*U I TOA(ACTOABl.Jll:

SAMPl[SYST[M r-*

)HSJOE I '~'

REACTOR I 8Ult.DINC

~~~~'-!,~Ja3!r:a'f~~i!=~

1

~l1'4~~11J(BY~~~~SE~~m 3.~~~~~l,

'-~8

~

s C:::;;;:5ic;;:J;;J-':r'o

l*CSH*t81*64*21Z*I NSH*H3*1M<Z*I FIGURE 6.3-6b HIGH PRESSURE CORE SPRAY 11 NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 21 OCTOBER 2014

"'-r-'*

~~r CNS SYSTEM t~'-1 2-CSL-002-41-2!J-l T---------

~

~~

4V20 l~l RHSSYSTEH PI0-31C!B-61 RHSSYSTEM

~.4-lk IB*O r---T---T---&. ffizc102 mm :! 2-C5L-020-64-2!J-l

! Nt.s m E.j 0

!r.1~2

'-~1.,.;.--~~1--..,.i.....i...---.-

~ .........,.......,......._ _.__ _ _ _ _ _ _ _ _..._..__ _ _ _ _  !!"1---~_._,EJ_"_'_EJ~"1"':i-'--_._---"""""----....,.-----1 mm H-----'IVl201J*llVJ211J*I rrJ-IR' 2-CSL-0lB-47-2CJ-l FIGURE 6.3-7a LOW PRESSURE CORE SPRAY 11 NINE MILE POINT NUCLEAR STATION - UNIT SOURCE, PID-32A-19 SCRIBA, N. Y.

TITLE, LOW PRESSURE CORE SPRAY SYSTEM UPDATED SAFETY ANALYSIS REPORT A B c D G H K USAR REVISION 20 OCTOBER 2012

Peak Cladding Temperatures

"' -. 2400 II Nomlnol Reclrc Suction Line Break. HPCS DIG Failure 2200 a Nominal HPCS Line Break. LPCS DIG Fallure

/1 Nom1nal STM Break Outside Containment. LPCI DIG Failure 2000 o Nomlnal STH Break Inside Containment. HPCS DIG Failure IL" c:i

• Nominal FOWR Break. HPCS DIG Failure e.w 1800 UI

--*----- Appendix-K Recirc Suction Line Break. HPCS DIG Failure a:

. 1600 i

ILi D.

1400

~CJ II z

a 1200 ,I I

j I

0 1000

.ic -------***-------*11'-

~

D.

800 600 A 400

.01 .1 1 10 BREAK AREA (Sq.A.) FIGURE 6.3-8 PEAK CLADDING TEMPERATURE AND PEAK LOCAL OXIDATION VERSUS BREAK AREA NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT

core Power versus t1me for loss-of-coolant acc1dent analysis

--m- Nominal Decay Heat Curve o - Appendtx-K Decay Heat Curve 0.8 a:

u.J

~

0 0.6 Q.

u u.J Q 0.4 0.2 10 100 1000 10000 T1me After Break Cseconcss>

FIGURE 6.3-9 NORMALIZED CORE POWER VERSUS TIME FOR LOSS-OF-COOLANT ACCIDENT ANALYSIS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT nRS.'D D1"FTllTl'lm -, nt""'l'n'R'P.'D , ca QA

180 LI

~

Cl 160

=

Lo.I w

0 u

z.

= 140 z:

~

w

~ 120 c

Q z:

c 1 0 FT 2 BRW Lo.I JOO

~

a.

V'I w 80

-==

c.!l

I; u

i:: 60

it

~.....

~

J.O

....-'<c

..... 20 OL--~-1-~~-'-~--l~~-J....~~.1.-.~_.1..~~..l.-~~~~-'-~--'

0 lO 20 30 40 30 60 70 BO 90 100 BREA~ AREA (i OF OBA)

NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-10 TOTAL TIME FOR WHICH HIGHEST POWERED NODE REMAINS UNCOVERED VERSUS BREAK AREA, LPCS DIESEL GENERATOR FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

V1

~

w IZ

J BOO

"'"'a.

IZ w

~

....a:

c(

0 (00 B 12 16 tn1E AFTER !RE.Alt (SEC l FIGURE: 6.3-11 CORE AVERAGE PRESSURE FOLLOWING A DESIGN BASIS ACCIDENT RECIRCULATION SUCTION BREAK, LPCS DIESEL GENERATOR FAILURE NOTE: "This figure applies to the initial LOCA analysis." NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

t;j as Ii!

JEl ,lllf' UMCOVERY l

r l!MR PUlillH FWlllMG 8 12 15 Til'E ~TI:R !REM (SEC )

NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-12 NORMALIZED CORE AVERAGE INLET FLOW FOLLOWING A DESIGN BASIS ACCIDENT RECIRCULATION SUCTION BREAK, LPCS DIESEL GENERATOR FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N. Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

~

~

e 540 -

w

..,a::

0 520 """"

500 - I I I I I I I I I I I I I 0 4 8 12 16 TIME '-FTER 8R£AX (S[C )

INOTE: "This figure applies to the initial LOCA analysis." J FIGURE: 6.3-13 CORE INLET ENTHALPY FOLLOWING A DESIGN BASIS ACCIDENT RECIRCULATION SUCTION BREAK, LPCS DIESEL GENERATOR FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

1 4 13 1 2 0

..... 1 , JET P\"4P UHCDVERY ex l!fe; 1

~

a. 09

§ t-QC w

JC 08 07 HOTE l

£ 06

z:

~

0

~

!)

04 0 :5 HOTt 1 CPR*\ 0 at SPACER Z 02 01 0

0 2 4 6 6 I TJMC AFTER BREA~ !SEC )

NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-14 MINIMUM CRITICAL POWER RATIO FOLLOWING A DESIGN BASIS ACCIDENT RECIRCULATION SUCTION BREAK, LPCS DIESEL GENERATOR FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

Q

2 40 0

r

....:r TAF c:>

c

...~

IX 20

a 61\f' TIK£ AFTER BREAK (SEC l NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-15 WATER LEVEL INSIDE SHROUD FOLLOWING A DESIGN BASIS ACCIDENT RECIRCULATION SUCTION BREAK, LPCS DIESEL GENERATOR FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

BOO c..

I

"'a;w V) 400

"'"'....>o

.......er:

0 i:'a:;.i 00LL.L..L..Ll....LJLCP::=::========::c:==========t===========;,~====:l 100 200 300 400 TIME AFTER BRE.JJ: (SEC I NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-16 REACTOR VESSEL PRESSURE FOLLOWING A DESIGN BASIS ACCIDENT RECIRCULATION SUCTION BREAK, LPCS DIESEL GENERATOR FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

OIC!ET OF BOILING TftAHSJTIOM HIGH POWER AXlAl Pt>.!IE UKCOYERED l

r OllSET Of LOWER PLCHIRt FLASH!Hli iO !ERO Ol o

'-'-...1.-1.-'-'-'-...L-.l-'-'--~~~~~-'--~~~~--'...,_~~~~~~~~~

10 20 30 t.to TIHE AFTER BRE.-.X (SEC I NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-17 FUEL ROD CONVECTIVE HEAT TRANSFER COEFFICIENT DURING SLOWDOWN AT THE HIGH POWER AXIAL NODE FOLLOWING A DESIGN BASIS ACCIDENT RECIRCULATION SUCTION BREAK, LPCS DIESEL GENERATOR FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

lODO HIGHEST POWERED AXIAL PLAHE HlGllEST POWERED AXIAL PLAllE TO EXPERIENCE CPR

• 1 0 PRIOR TO JET Ptt1P UNCOVERY l HIGH PtlWER AXIAL PLANE REflOODED 2000

!c:

f5 BEGIMKIKG Cf SPRAY C01JLING i:

~

....lE Q

~ looa .,.,

~

,' *~--~-.,,/

.......~ ~

r HIGH POlilER AXIAL PLANE UNCOY£REO t

ONSET OF BOllIHG TRANSITION 0

aI l!J 100 1000 TIM£ AFlEl BREAK !SEC )

NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-18 PEAK CLADDING TEMPERATURE FOLLOWING A DESIGN BASIS ACCIDENT RECIRCULATION SUCTION BREAK, LPCS DIESEL GENERATOR FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

It..

I llf

~

a. 2000 I

i5 I-

""~

~

It..

!5 I-0

i:: 1000 D1 10 HID 1000 TJHE AF1ER BREAK (S£C I NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-19 AVERAGE FUEL TEMPERATURE FOLLOWING A DESIGN BASIS ACCIDENT RECIRCULATION SUCTION BREAK, LPCS DIESEL GENERATOR FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

('

~ JOO w

~

yt U1

....a::

IM

c Q.

0 so 10 100 ICOO 0 '

TIM( AFT(R BRE>JC. (SEC I NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-20 PCT ROD INTERNAL PRESSURE FOLLOWING A DESIGN BASIS ACCIDENT RECIRCULATION SUCTION BREAK, LPCS DIESEL GENERATOR FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

3 111

~

~ BOO

..."'a:

V1 Q..

~

c w

"'~

coo 10 20 30 t..10 T!ME AFTER BREA~ ISEC )

NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-21 CORE AVERAGE PRESSURE FOLLOWING A 1.0 SQ FT BREAK (LBM) RECIRCULATION SUCTION BREAK, HPCS FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

~

I-w

~ 0 6 w

t.O cc

"',..c w

~

Q i

N c

z

0 2 i

LOWER PLEHUM FLASHIHG

-o 6.__,_..._.__.__._,_.._._~l~0~~~~~-20..._~~~~-3~0~~~~~~40:=-~

TlME ArTCR SREJ\K (S£C )

NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-22 NORMALIZED CORE AVERAGE INLET FLOW FOLLOWING A 1.0 SQ FT BREAK (LBM)

RECIRCULATION SUCTION BREAK, HPCS FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

ID

....I SI.JO

~

I-i5 z:

w 2!i 520 500 '-'--'-'-~~........._,_._~~~~~-'-~~~~~~~~~~---~~

0 10 20 JO 40 TIME AFTER BREAK (S[c; I NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-23 CORE INLET ENTHALPY FOLLOWING A 1.0 SQ FT BREAK (LMB) RECIRCULATION SUCTION BREAK, HPCS FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

3 2B 26

2. 4 22 T-WIHDOW 0

a: 2 0:

JI 18 0

Do 1 6 LI

>-4 14 t5 12

~z: 1

....!IC OB 06 04 02 0

0 2 4 6 8 10 12 14 16 18 TIM£ AFTER BREAK (SEC )

NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-24 MINIMUM CRITICAL POWER RATIO FOLLOWING A 1.0 SQ FT BREAK (LBM) RECIRCULATION SUCTION BREAK, HPCS FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

E a

3 0 40

z

;

V>

\.I.I I=

TAF

~

VI z

w Cit I!! 20

~ BAF' lOD 200 300 llOO Tl>£ AFTER BREAK ISEC I NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-25 WATER LEVEL INSIDE SHROUD FOLLOWING A 1.0 SQ FT BREAK (LBM) RECIRCULATION SUCTION BREAK, HPCS FAILURE NINE MILE POINT NUCLEAR STATION-UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

1200 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - .

-.:c e::

VI 800 w

§

..."'"'a:

0...

V1 VI

...~

<..i i!'i a: coo 200 300 400 TlHE AFTER BAEAIC (S£C )

NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-26 REACTOR VESSEL PRESSURE FOLLOWING A 1.0 SQ FT BREAK (LBM) RECIRCULATION SUCTION BREAK, HPCS FAILURE NINE MILE POINT NUCLEAR STATION- UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

I.I. ONStT OF BOll.IHG TRAMSITIOH HIGH l'OW£1l AXIAL PlAllt UllCO'/fRED l

E

r ID -

~

ONSET OF LOWER PlEHUH FLASHING j:

u

~

u 01 ........_~*~'..L..L..U...!.1~~~~'~~~-L-'~~--L'~~~-11__~~--L*~~~~*L-10_z_E_Ro-L~'-l 0 10 20 JO 40 50 60 10 60 TlME AFTER BREA~ (~tC l I NOTE: "This figure applies to the initial LOCA analysis." I FIGURE: 6.3-27 FUEL ROD CONVECTIVE HEAT TRANSFER COEFFICIENT DURING SLOWDOWN ATTHE HIGH POWER AXIAL NODE FOLLOWING A 1.0 SQ FT BREAK (LBM) RECIRCULATION SUCTION BREAK, HPCS FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

3000 ,--------------------------------------.

HlGH POWER AXtAl PLANE REFLDOOED

(

BEClNNING or ~PRAV CODllHG 1000 -

- HIGH PO\ltR AXIAL PLAll£ UllCO'J£R£D T

~

c-c-

,_ ONSET OF BOlll~G TRANSITION 0 J I I 0 l 10 100 1000 TlHE AFTER eREAK ISEC )

I NOTE: "This figure applies to the initial LOCA analysis." I FIGURE: 6.3-28 PEAK CLADDING TEMPERATURE FOLLOWING A 1.0 SQ FT BREAK {LBM) RECIRCULATION SUCTION BREAK, HPCS FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

-i5 I-c 40

i;:

r a TAF

~

oo._._~*~,_._..__._...L..--1-~'~~~~~-'-'~~~~~---~*~~~~--,,-'-~~~_.

1OD 200 300 IUO Tl~{ Af"T(R BREAK (SCC )

NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-29 WATER LEVEL INSIDE SHROUD FOLLOWING A 1.0 SQ FT BREAK (SBM) RECIRCULATION SUCTION BREAK, HPCS FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

< !JOO

"'......a:

t..I

\l'I

""3 t-u 400 WC 0 ~t~

1 _._._---'---'--l--'-~1~l~~~~~--'-'~~*~~~-'---~~~~:-:---=~~~~

0 JOO 200 300 400 TIM£ AFlER 8~EAX. (S£C l NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-30 REACTOR VESSEL PRESSURE FOLLOWING A 1.0 SQ FT BREAK(SBM} RECIRCULATION SUCTION BREAK, HPCS FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFElY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

i:

.t I I

~

~ 10*

lie

~

E Q

u a:

w a...

10 2 ....

i:

...~....

w 0

I I I 0 100 200 300 400 T1'4£ AFTER BRE.U: (SEC )

I NOTE: "This figure applies to the initial LOCA analysis." I FIGURE: 6.3-31 FUEL ROD CONVECTIVE HEAT TRANSFER COEFFICIENT FOLLOWING A 1.0 SQ FT BREAK (SBM) RECIRCULATION SUCTION BREAK, HPCS FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

~

....g; 2000

...~

~

Ct

""0

~

....J u

~

"" 1000 0

o l-L-..J.-1..~-'-'--'-_...._,_~~~~~-L-~~~~~.J-~~~~~.a..-~~---

100 200 300 400 TIME AFTER BR£~ (S[C }

NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-32 PEAK CLADDING TEMPERATURE FOLLOWING A 1.0 SQ FT BREAK (SBM) RECIRCULATION SUCTION BREAK, HPCS FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

g 0

=>

0 40

~

i:

...~"'~

I- 20

<C

- Bl.f

[

r 0 o'-'-..___..._.._.__._._~20~0~~~~~ij~00~~~~~6-0~0~~~~--::-BO~O~~~--'

I I TIME ~TER BRW (SEC )

NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-33 WATER LEVEL INSIDE SHROUD FOLLOWING A 0.09 SQ FT BREAK (HIGHEST TEMPERATURE SMALL BREAK) RECIRCULATION SUCTION BREAK, HPCS FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

!200  !-----------------------------,

!S e:.

~

BOO Ill tJ CZ:

a.

V1

~

t:;

...a:

400 OOLL.LJ.._LI_LL-L.L20~0--~~~4~00~-----:6~0~0-----n;80~0;----

TIHE o\F'TtR BREAK (SEC )

NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-34 REACTOR VESSEL PRESSURE FOLLOWING A 0.09 SQ FT BREAK (HIGHEST TEMPERATURE SMALL BREAK) RECIRCULATION SUCTION BREAK, HPCS FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

I&.

l I I I I I I t

• I I I I

0. 200. 400. 600. 800.

TIME AFTER BREAK (S(C,J I NOTE: "This figure applies to the initial LOCA analysis." I FIGURE: 6.3-35 FUEL ROD CONVECTIVE HEAT TRANSFER COEFFICIENT FOLLOWING A 0.09 SQ FT BREAK (HIGHEST TEMPERATURE SMALL BREAK)

RECIRC. SUCTION BREAK, HPCS FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

Loi cc 2000

i

~

4l

...~

~

Cl C>

~

u

~

1000 a .._._....................._._. . . . . . ....._._~~~~~_,_~~~~~_.._~~~~-=-::".:-~~___.

0 200 400 600 800 TlHE AFTER B~EAK (SEC I NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-36 PEAK CLADDING TEMPERATURE FOLLOWING A 0.09 SQ FT BREAK (HIGHEST TEMPERATURE SMALL BREAK) RECIRCULATION SUCTION BREAK, HPCS FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

i.

THIS FIGURE HAS BEEN DELETED FIGURE 6:3-37 .

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS *REPORT 1---- --- - - - ---- ';.",.:;:- .: .~

• THIS FIGURE HAS BEEN DELETED FIGURE 6.3-38 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT

THIS FIGURE HAS BEEN DELETED FIGURE 6.3-39

' t I

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

THIS FIGURE HAS BEEN DELETED ..

1 FIGURE 6.3-40' ,

NIAGARA MOHAWK POWER CORPORATION ~

NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT r---- ----- - ~--- ***A.

60 g

g 40 0

i

...i:"'

~

z:

11111: l\FT£R BREAK I S£C l NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-41 WATER LEVEL INSIDE SHROUD FOLLOWING A MAXIMUM HPCS LINE BREAK, LPCS DIESEL GENERATOR FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

-~ eoo Vl

..._.a:

w In 0

u <400 o(

QC 200 t!OO TIME AFTER BR£AK (Ste )

NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-42 REACTOR VESSEL PRESSURE FOLLOWING A MAXIMUM HPCS LINE BREAK, LPCS DIESEL GENERATOR FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

~

I N

11.

I a:

z: 10*

cm

~

z:

ts u

0 Gt!

i....

~ 1ol ,_

e;

...~

z:

,=-...

u w

0 u""

I I I l 200 400 600 BOO TlME ArTER BREAK (SEC )

INOTE: "This figure applies to the initial LOCA analysis." I FIGURE: 6.3-43 FUEL ROD CONVECTIVE HEAT TRANSFER COEFFICIENT FOLLOWING A MAXIMUM HPCS LINE BREAK, LPCS DIESEL GENERATOR FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

3000 .---------------------~-----------..

(000

~

a:

J f-

....~

t.

f:!

i 1000

~...,

...""~

0 ._._......_.__._..__.__........._.__._~~~~___..~~~---'-~~-~-~------'

0 200 YOO 600 800 Tll1E AFTER BREAK (SEC )

NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-44 PEAK CLADDING TEMPERATURE FOLLOWING A MAXIMUM HPCS LINE BREAK, LPCS DIESEL GENERATOR FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

-t Q

I~

0 a: 4(1

z:

!I Ill

~

i 1

~

I I w

0 lAf V>

d>

-l Cl!

~ 20 BAF a 0._......__.__.___.1_LL1_..._~------'--------"'--------'-----'

200 400 500 800 Tll1E AF1ER BRE.QI'. IS£C )

NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-45 WATER LEVEL INSIDE SHROUD FOLLOWING A MAXIMUM FEEDWATER LINE BREAK, HPCS FAILURE NINE MILE POINT NUCLEAR STATION- UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

1200 ..------------------------r-----....

800

('

VI

~

=>

VI QC

.,,w.....

V'I

~

~00

~

u i.5 a::

200 l!OO 500 800 Tlf'I( AFlER BREAK (SEC )

NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-46 REACTOR VESSEL PRESSURE FOLLOWING A MAXIMUM FEEDWATER LINE BREAK, HPCS FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

10 ------------------------------------------------~~--

6

"""*I t:

N

....~

em 4 10

.c g

I::

0 a:

w VI

~

10Z

~

==:

~

....>v CJ u

I 800' 1 I I I

• I I I I I 0 200 400 500 TIME AfT£R BR£~ (SEC )

I NOTE: "This figure applies to the initial LOCA analysis." I FIGURE: 6.3-47 FUEL ROD CONVECTIVE HEAT TRANSFER COEFFICIENT FOLLOWING A MAXIMUM FEEDWATER LINE BREAK, HPCS FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

JODO ....- - - - - - - - - - - - - - - - - - - - - - - - - - .

20(}0 i:'

...'.!i

~

.......i5

ic

.Q

~

~

u 1000

~

0 0.......................~--------...""""---------...----------'"81~----

20 T1Ht AFTER BREAK (SEC )

NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-48 PEAK CLADDING TEMPERATURE FOLLOWING A MAXIMUM FEEDWATER LINE BREAK, HPCS FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

~ij~ -

~

Q

a

~o

- T rr t:J 0:

c I TAr

~

....w

""w-'

a.!

20 - !JAF' I

a 0 I ' I I I I I I I I I I I 0 200 400 600 BOO TIHE ArT£R BREAX (SEC )

I NOTE: "This figure applies to the initial LOCA analysis." I FIGURE: 6.3-49 WATER LEVEL INSIDE SHROUD FOLLOWING A MAXIMUM MAIN STEAM LINE BREAK INSIDE CONTAINMENT LPCI DIESEL GENERATOR FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

1200 tOOO 3.,.,

~

!i f

-I LLJ 11'1

~

"'" 400 .......

~

L>

i!i ....

lX 0 - I I I 1 I I I I I I 0 200 400 600 800 TIH'E AFTE~ BREAX {5EC }

I NOTE: "This figure applies to the initial LOCA analysis." I FIGURE: 6.3-50 REACTOR VESSEL PRESSURE FOLLOWING A MAXIMUM MAIN STEAM LINE BREAK INSIDE CONTAINMENT, LPCI DIESEL GENERATOR FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

i ...

I 1: I

~

...... to 4 r=

e,_

...:z:....u

- ...tu::

Q

~ to2 .._

~

....~..,

IU a""

~

, I I I I I I I I 1 I I I 0 200 400 600 BOO Tl~ AF1£R BREAK (SEC l I NOTE: "This figure applies to the initial LOCA analysis." I FIGURE: 6.3-51 FUEL ROD CONVECTIVE HEAT TRANSFER COEFFICIENT FOLLOWING A MAXIMUM MAIN STEAM LINE BREAK INSIDE CONTAINMENT, LPCI DIESEL GENERATOR FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

...... 2000 la.

i c(

(IC Q,.

c

~

~

Cl Cl

.c; u 11){)0

~

w a.

200 400 600 800 TIHE llf'TER BREA~ (SEC I NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-52 PEAK CLADDING TEMPERATURE FOLLOWING A MAXIMUM MAIN STEAM LINE BREAK, INSIDE CONTAINMENT LPCI DIESEL GENERATOR FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

t 40 CJ

~

0 IX

z:

V1

r ----

...9 V1

r.:

.....I w

..J 20 BAF a:

w

r OO........._...L-l.-'-'..._._...._._......1.-1~~~~~--1.~~~~~-'-~~~~~__,_,~__.

300 600 900 lZOO Tlll'E Afl(R 8RE"" {SEC I NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-53 WATER LEVEL INSIDE SHROUD FOLLOWING A MAXIMUM MAIN STEAM LINE BREAK OUTSIDE CONTAINMENT HPCI FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

800 w

~

..J w

"'"'>w

~

iiw 400 Cl:

300 600 900 lZOO Tlt!E AFTER BREAK !SEC )

NOTE: "This figure applies to the initial LOCA analysis. 11 FIGURE: 6.3-54 REACTOR VESSEL PRESSURE FOLLOWING A MAXIMUM MAIN STEAM LINE BREAK OUTSIDE CONTAINMENT, HPCS FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

6 10 1

N Lt..

I 0:

c aJ

z:

~

104 v

LL.

0 a:;

z:

E 10? -

j;::

u

""z 0

tJ t I I 600 'JtlO !ZOO Tl~ AFl(R BREAK (SEC )

INOTE: "This figure applies to the initial LOCA analysis." I FIGURE: 6.3-55 FUEL ROD CONVECTIVE HEAT TRANSFER COEFFICIENT FOLLOWING A MAXIMUM MAIN STEAM LINE BREAK OUTSIDE CONTAINMENT, HPCS FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

iaoo . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ,

~ 2000

....o;:::a""

""w 0..

c

~0 C>

u 1000

~

a.

0 LL..L.J.-1-LL_Ll-1-L------.i__-~----L-~-~--:-=~~

0 300 600 900 1200 Tll1E IJ"T£R BREAK (SEC l NOTE: "This figure applies to the initial LOCA analysis."

FIGURE: 6.3-56 PEAK CLADDING TEMPERATURE FOLLOWING A MAXIMUM MAIN STEAM LINE BREAK OUTSIDE CONTAINMENT, HPCS FAILURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 22 OCTOBER 2016

NINE MILE P( >INT 2 1 HOT CHANNEL OBA SUCT.BREAK 2 AVERAGE CHANNEL 3 TOP OF ACTIVE UEL HPCSOG FAILURE

60. t----------+------+------+----------t----

1-------

rrr-~--

40. ,--------------+------+------

2_J'=.=--'-_,.,,__

+:_-_' ---'y1+-2-3"-_--++:_,-=._-=._-::_ ' _z _J

_J --t---)!}J-:-, --,}-t- r --1-J

-1V+-+-

J h

I W 20. ! -----,

1vr

-..J v'------t------+-------1-----

...J r 0::::

w I

<(

. I I I I I I I I

0. .......__.-'--'-....L......L---- -

0. 60. 120. 180. 240.

ALISA 47E6F TIME 20151002 0803.5 (SECOND)

FIGURE: 6.3-57 NMP-2 DBA-HPCS DG FAILURE-APPENDIX K HOT AND AVERAGE CHANNEL WATER LEVELS NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 25 OCTOBER 2022

NINE MILE PC INT 2 1 VESSEL PRESSUR OBA SUCT.BREAK HPCSDG FAILURE 1.2------+-------+-------1------+-----

3 X10 0.8 \

t----+\-, ----+------- ---

\

\

tr)

Cl.

0.4 t----r---+------

w - ---+--------+----

t 0::

)

tr) tr) w 0:: ...

I I

0. * * *

• I 1 1 1 1 I

---

1 1

• ::.:* =======::1.=---::.:-:=-

______..1.*..::..:* == .. ------ -__ -

1 1

0. 60 120. 180. 240 ALISA 4 7E6F 20151002 0803.5 TIME <SECOND)

FIGURE: 6.3-58 NMP-2 DBA-HPCS DG FAILURE-APPENDIX K REACTOR VESSEL PRESSURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 25 OCTOBER 2022

NINE MILE PC INT 2 1 CONY HTC HOT

• 5 2 CONY HTC HOT *5 OBA SUCT.BREAK 3 RAD HTC HOT *5 HPCSDG FAILURE 4 RAD HTC HOT *6 5.-**- 5 TOT AL HTC HOT 5 6 TOTAL HTC HOT .6 I.!...

0 3. ------- - - - --.

N l -t I-I.!... i I

3 I

\

"""- 5 0:::

I

'-.. 2

)

-.\, 5

• & 5 2

6 2 8

\.5

\.:::_....__

Y\-ir--

.r - -

I- V m

r 2

,,s ""I;

- p:

-..., 2 1.

('.)

0 r\.

\

1n

_J I-0 1--

I-I-

I

-1.

- I l l I1 I I I L il I

0. 60 120. 180. 240 ALISA 47E6F 20151002 080.3.5 TIME (SECOND>

FIGURE: 6.3-59 NMP-2 DBA-HPCS DG FAILURE-APPENDIX K HEAT TRANSFER COEFFICIENT NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 25 OCTOBER 2022

NINE MILE PC INT 2 1 PEAK CLAD TEMF ERATURE OBA SUCT.BREAK HPCSOG FAILURE 3.

J 1-------+------+------1------ -+-----

XlO LL 2.

C) r\

w f- 1.

<(

0:::

w 0...

2 w

f-0_ l_u_1 j I I I I

0. 60. 120. 180. 240.

ALISA 47E6F 20151002 0803.5 TIME <SECOND)

FIGURE: 6.3-60 NMP-2 DBA-HPCS DG FAILURE-APPENDIX K PEAK CLADDING TEMPERATURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 25 OCTOBER 2022

NINE MILE PCDINT 2 1 HOT CHANNEL I 0.07 FT2 SUCT. - .APPK RATED 2 AVERAGE CHANNL 3 TOP OF ACTIVE F.'UEL HPCSDC FAILURE

60. I--------+------+------+--------+----

40. --1-------+-----

1 z 1 z 1 2 ' 2 z

z13 l J J -- J

'*1ti

{ \i -1

\

LL.

.._,, ,---.:_1

'*1'

\

f: '

w \-<

"--2

> ' 1 w 20.

- ""......J w -

f- -

<( -

s:

0.1111111 0.

ALISA 6COF5 200. 400.

_L 600. BOO.

20151013 1421.6 TIME (SECOND)

FIGURE: 6.3-61 NMP-2 0.07 FT2-HPCS DG FAILURE-APPENDIX K HOT AND AVERAGE CHANNEL WATER LEVELS NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 25 OCTOBER 2022

NINE MILE P INT 2 1 1 VESSEL PRESSU E 0.07 FT2 SUCT. - PK RATED HPCSDG FAILURE 1.2 1---------1i----------t-----

l x10 0.8

(/)

0...

w 0.4 0,.__._....__._........._,.__,__..___.______-------------

0. 200. 400. 600. BOO.

ALISA 6COF5 20151013 1421.6 TIME <SECOND)

FIGURE: 6.3-62 NMP-2 0.07 FTHPCS DG FAILURE-APPENDIX K REACTOR VESSEL PRESSURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 25 OCTOBER 2022

1 CONV HTC HOT 7 NINE MILE POINT 2 2 CONY HTC HOT 8 0.07 FT2 SUCT. - PK RATED 3 RAD HTC HOT *7 4 RAD HTC HOT *8 HPCSOG F AJLURE 5 TOT AL HTC HOT *7 5.-------1----------+---- 6 TOT AL HTC HOT 8 l.J...

l t 1 5 0 -.....---1----- ---- ----

/

I 3_,-----+-_t ____

N 1-

---

+---,

l. ___. __e .-.. - ---, ,

l.J... \ s I

0:::

/

2 1 t

I \ / , 2 8 2 O

........ ,l<<r7 2,--- i:---+--- _____

1

J I

m

1. 1--:

\, 1 --1f----t-----

c.,

0

_J u

I

.,L ...

I-I , '/s.

/

fl

,./ / :,1 I

//

4 j I I I I // LI

o. 200. 400. 600. 800.

ALISA 47E6F TIME (SECOND) 20151002 0803.5 FIGURE: 6.3-63 NMP-2 0.07 FT2-HPCS DG FAILURE-APPENDIX K HEAT TRANSFER COEFFICIENT NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 25 OCTOBER 2022

NINE MILE PC INT 2 1 PEAK CLADDING T MPERATURE 0.07 FT2 SUCT. - A'PK RATED HPCSDG FAILURE 3.

x103 2.

/.

LL C) w 0

w CY

-1 --+-

, 1.

CY

\ - (

\ -

_ _ ---I---

w D.... \,_ ____/ ---r---------1 2

w I-

0. - l I .I .I L11 1------------------

o. 200. 400. 600. 800.

ALISA 6COF5 20151013 1421.6 TIME <SECOND)

FIGURE: 6.3-64 NMP-2 0.07 FT':.HPCS DG FAILURE-APPENDIX K PEAK CLADDING TEMPERATURE NINE MILE POINT NUCLEAR STATION - UNIT 2 SCRIBA, N.Y.

UPDATED SAFETY ANALYSIS REPORT USAR REVISION 25 OCTOBER 2022

CO'Cll:~

1---------------------------~~-----~-------. . . ~~,~-~-i~~

MJt: &

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~POOLSWELL POOL FALL.. BACI<

Bj CONDENSATION OSCILLATIONS

~J3f~ CHUGGING 0 0.7 1.0 J 15 60 100 500 TIME AFTER BREAK (SEC)

FIGURE 6A.2-2 EVENT-TIME RELATIONSHIP FOR A TYPICAL OBA.

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

(1~ ML!L TIFLE SAV's ON FRESWRE sE"T (Z{,MW,.i:.C!y.:_$ITV.A(V,E, f r~~,~~>>}Z-0#~,)

f?-il AIR CLEARING FROM DAYWELL TO WETWELL

~ POOL SWELL/FALLBACK (MINOR)

@.~<<#§);;~~/;@//;0~]°EAr.19otJ)°JE~s~f19!{W/?'~~@ ~~-;-/;-:;,~~:;,,,

LOW PRESS ECCS REFLDOD wa

//,.

D 4 5 25 35 40 220 330 TIME AFTER BREAK (SEC)

FIGURE 6A.2-3 EVENT-TIME RELATIONSHIP FOR A TYPICAL IBA NIAGARA MOHAWK POWER CORPORATION NJNE MILE POINT-UJ\JIT 2 UPDATED SAFETY {-)r-.JAL YSlS REPORT

• MSIV'S WILL NOT NECESSARILY CLOSE DU.RING SBA BUT HAVE BEEU ASSUMED TO CLOSE FOLLOWING SCRAM

• • ASSUMES ALL DRYWELL AIR 15 PURGED TO WETWELL BEFORE STEAM FLOW CAN OCCUR k~%r& MULTIPLE SRV'S ON PRESSURE SET r@&{@ AIR CLEARING FROM DRYWELL l I I I I D 2 12 20 600 700 2000 TIME AFTER BREAK (SEC)

FIGURE 6A.2-4 EVENT-TIME RELATIONSHIP. FOR A TYPICAL SBA NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANAL YSfS REPORT

0 SEISMIC SLOSHING OF ANNULAR POOL q

r<'l 0 ~~ [

q p

j~

N

' I tJS\

!~ (I f\ t~

0 q - )

r= 14.167 I'\

' p r>

t-u.. ....... J ~ ~ c 4 I) r\ e= 0° c

f 1 t I

) )

' ~

~

> Z=O I

0 zo i

n 1 I}

-t- 'e'

! I l I 0 ~

~

Jv

( (

1

)

()

~r

)

WO ')

~

_J q

)

\J v

IJ.. - (

J UJ I )

b Cl I \ ~

0 q <i ~

' ~

\

I l ~I N

I 0

0 rO I

v-I 0

0

<;f 1

0.00 3.00 6.00 9.00 12.00 15.00 18.00 21.00 24.00 27.00 30.00 TIME {SECONDS}

FIGURE 6A.2-5 FREE SURFACE DEFLECTION TIME HISTORY AT r; 14.167 e=o* FOR OUTER SUPPRESSION POOL DUE TO SEISMIC SLOSHING (SSE)

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

'rr: AO c ..... urc.1nr,.1 n APRIL l 9B9

OUTER SUPPRESSION POOL

-0.86 Z=20' PRJMARY CONTAINMENT PEDESTAL----,  ;;;.:::=-..

ps1 N

I\)

._()

N tSl r=29.5' sF -2.34 1-r=37.5' \

psJ r=45.5'/ w~ CD

.m,...... .(J)

I

..J>. I\) w '-.!

..."° 1J -0

-0 "O

...UI ....I.II UI MINIMUM----_....

OYNAMJC PRESSURE FIGURE 6A.2-6 Z=HEIGHT FROM SUPPRESSION POOL FLOOR DYNAMIC PRESSURE CAUSED BY SSE GROUND HOTJON ON PRIMARY CONTAJNMENT r=RADIUS FROM REACTOR CENTER LINE WALLPPEOESTAL,AND BASEMAT AT er AZIMUTH NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 2 OCTOBER 1990

OUTER SUPPRESSION POOL 2=20'

/

PEDESTAL PRIMARY CONTAINMENT--i.:;;.,... /

1 MAXIMUM DYNAMIC PRESSURE

/

w l\J

~ /BASEMAT ,......

r=29.5'\ ]

v -. \ ]

r-45 5'

" _Z=0' I

Cn f'l O'l

'1 w

'"O "O

,..Ul ...

())

MlNIMUM OYNAMlC PRESSURE FIGURE 6A.2-7 Z=HEIGHT FROM SUPPRESSJON POOL FLOOR DYNAMIC PRESSURE CAUSED BY SSE GROUND MOT JON ON PRIMARY CONTAINMENT r=RADIUS FROM REACTOR CENTER LINE WALL,PEOESTAL.ANO BASEHAT AT 180" AZJMUTH NIAGARA MOHAWK POWER CORPORATION NINE MlLE POINT-UNIT 2 UPDATED SAFETY ~NALYSlS REPORT USAR REVISION 2 OCTOBER 19<30

6.!10

'i.CO

- 1.50 c

~

=

c_, l 1

0.00 I

-1.SO 1

~J co

-~ 50 ..___ _...__ _ _ _ _...___ _ _ _ _ _ _ _....___ _ _ _ _ _ __.___ _..___ _...___ __.

0.00 2.00 4.CO 6.C~ 6.CO 10.liO 12.ca 14.GO 111.00 10.0iJ TJME jSECONOSJ FIGURE 6A.2-8 LOAD TIME HJ.STORY FOR 1

• 25 FT. SECTION OF SRVDL QUENCHER ARM OBE-X DIRECTION NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 0 APRJL 1989

F..!lO I )

4.CO ._ I ~  !) * )

' ; [

' ~

r

( (

D

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(

(

2.CO >- ( I ; IJ ll I

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(

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v

(

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~.

(

,j

( D I

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)

~

~ ~

'- 0.00 c ';, I (

(

! '~ ' ~ I

> (

0 I

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( (

0 ( '(

(

i

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...J i )

-~.oa

~.

)

() '

' Ii l:J ( i

' ( ~

D D~

uO - (

4

' 'b I

l

(

' ii

-~.OCi -

• ~

.ncn'--~~-'--l~~-.__1~~-'--I~~-'--'~~-'--'~~~*.__~~~--~~__...__~~--'--~~~

Q.GO ~.00 ~co ii.CO 4.00 10.00 1::.oa 14.00 16.DD 10.00 2D.OD TIME (SECDrlOS)

FIGURE 6A.2-9 LOAD TlME HJSTORY FOR 1 .25 FT. SECTJON OF SRVDL QUENCHER ARM DBE-Y DIRECTION NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 0 AP~!L I FJ 9

l*-OU 1ei+.iO B.00

~

~

N

~

c

..J o.ua  ;

.a co

- hi. OU -

• * ~ . 0 0 1.---_ _......__ _-!......_ __.__ ___.__ __ ; ._ _-..1_ _ _:___ _....._._ _ ~ _ __.

o.oo 2.00 ~ 00 6.00 8.0J 10 00 12.00 JS.OD 19 .00 20.00 TIME (SECOllOSl FIGURE 6A.2~10 LOAD TlME HISTORY FOR 1.2S FT. SECTION OF SRVDL QUENCHER ARM OBE-Z DIRECTION NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSlS REPORT USAR REVISION C APRJL 1989

OEADWEIGHT; SEISMIC LOADS; LOCA PRESSURE AND TEMPERATURE TRANSIENTS

{

ACCUMULATED WATER ON FLOOR

}

JET IMPlt~GEMENT ANO PIPE WHIP z

0 i=

c

z NEGATIVE LOAD DURING REFLOOO 0 OOWNCOMER VERTICAL REACTION LOADS u

t!I z NEGATIVE LOAD Ci FOLLOWING SPRAY 4:

0 OOWNCOMER ACTUATION (REQUIRES

....I LATERAL OPERATOR ACTION)

REACTION POOL SWELL LOADS AIR COMPRESSION

) SECTION 4

' ' I

' I I 0.84 2.e,7 15 100 100 600 TIME AFTER LOCA (SEC) FIGURE 6A.2-11 LOAD COi'!L8.INATION HfSlDRY~~ STRUCrURE NOTE: AFFECTED,- DR Yh'ELL FLOOR, AC CJ DENT CONDITION , LARGE LINE BREAK fDSAI CONSIDERATION IS GIVEN TO REACTION LOADS ON THE DRYWELl FLOOR FROM OTHER STRUCTURES SUCH AS DRY WELL AND WETWELl, AND PEDESTAL NIAGARA MORAWK__ _POWERCORPORATJON NINE MILE POINT-UNIT 2 UPDATED.SAFETY ANALYSIS REPORT USAR REVISION 0 APRIL 198~

I I {

I OEACWE1GHT; SEISMIC LOADS. LOCA PRESSLRE AND TEMPERATURE TRAtlSIENTS HYDROSTAT.C PRESSURE lNCLUOlllG SEISMIC EFFECTS.

I VERTICAL REACTIOU LOAOS ' 1'EGATIVE LOAD NEGA rive LOAD I

DURING. REFLOOO FOLLOWING SPRAY I

ACTUATION I

I SUl!MERGl!O STRUCTURE LOADS oue TO CONDENSATION OSCILLATIONS & CHUGGUIO (REQUIRES I ;:: ) SE:CrtON 4 OPEAAfOR ACTIO~I) I Q

z LATERAL D

u LOAD I I

Cl

% SWELL ANO FAUBACK (CliUGGlllG) a FRICTION LOADS 0

...I I I

,..-...- 6Ullf3l.E FORMATION

_ / AHO SUPPRESSIOil POOL SWELL

/ AIR COM?RESSION I

I CONC ENSA Tl OtJ OSCllLATIOll CHUGGING I

I I I I J 0.7 .3 lS 100 >500 TIME AFTER LOC~ (SEC)

FIGURE 6A.2-12 NOTE .

CONSIDERATION IS QIJEll TO REACTION LOADS ON THE oow~wor.IER LOAD COMBINATION HISTORY, STRUCTURE FROM OTHER STRUCTURES SUCH AS THE DRYWELL FLOOR AND STRUCTURES ATT ACHED TO THE OOWNCOMEnS. AFFECTED: DOWNCOMERS, ACCIDENT

' CONDJTION: LARGE LINE BREAK (OBA)

NJ AGARA MO HA HK POWE ff CORPORATION NINE MILE :POINT-UNIT 2 UPDATED SAFETY ANAL 'i'SIS REPORT i!<;AR R!=Vr~Tl)N 0

OEAOWEIGHT, SEISMIC LOA OS; LOCA PRESSURE ANO TEMPERATURE TR.<ll'~SIENTS.

HYDROSTATIC PRESSURE INCLU01tm SEISMIC E.FFECTS; I co*omrna*

OSCILLATION I CHUGGING I

a

~

i=

I LATERAL LOADS (CHUGGING I SECTION 4 0 SU6MERGEO STi'WCTURE LOA OS z

0 DUE TO CONOENSA TION OSCILLATIONS AND CHUGGlllG 0

z i5 0_,

VERTICAL REACTIOll LOAOS uut iO \'Ell! CLEAHlfl~Ai;u Sll:AH FLOW I

tlEGATIVE LOAD I

FOLLOWING SPRAY ACTIVATION (REOUIRES OPERATOR ACTION) l

~

SECTION J I

ltMOVERTENT SINGLE I

SRV ACTUATION ADS ACTUATJOll I I I I I I I s 25 ~D .220 600 TIME AFTER LOCA (SEC) ti OTES:

1. THETIL1E OURATIOU FOR AOS FIGURE 6A.2-13 ACTUATION IS TVPICAllY 2 TO SMINUTES.

2. CONSIDERATION IS GIVEN TO

- LOAD COMBINATION HISTORY,STRUCTURE REACTION LOAOS ON THE AFFECTED: OOWNCOMERS, ACCIDENT OOWNCOMER FllOM OTHER STRUCTURES.

CONDITION: INTERMEDIATE LINE BREAK {IBA)

3. LOAO CDl-eHiATI Ofl HI STCRY l{:iY VARY 501-EWlit.T \.11 HI SI ZE OF ! BA. FOR NiflG~R~ MOHt?iWK POWE~ CORPORATION NINE *MILE POIN-Tt-UNIT EXAl-'PLE, SRV ;:cTUATl 0:1 llT se:r POJ llT

~l'IY OCCUR DURillG A St'"1.LER l BA.

2 UPDATEG SAFE TV ANAL.lSl S REPORT USAR REVISION 2 OCTOBER 15913

~

OEAOWEIGHT; SEISMIC LOADS; LOCA PRESSURE ANO TEMPEAATtJRE TRANSIENTS; HYDROSTATIC PRESSURE INCLUDING SEISMIC EFFECTS; z

0 E

0 SAV OPERATOR ACTUATION OF SRV FOR REACTOR ACTUATION ON z COOL DOWN } SECno"'

0 SET POINT u

CJ z

i5 ct 0 CHUGGING

-I SUBMERGED STRUCTURE LOADS DUE TO CHUGGING VERTICAL REACTION LOADS ) SECTION 4 II I 1 LATERAL LOADS FROM CHUGGING I

I .

1Q 600 2000 TIME AFTER LOCA (SEC)

NOTES:

COtJSIOERATJON IS GIVEN TO FIGURE _6A.2-14 REACTION LOADS ON THE OOWNCOMER FROM OTHER STRUCTURES LOAD COMBINATION HISTORY1 STRUCTURE AFFECTED: DOWNCOMERS 1 ACCIDENT CONDITION: SMALL LINE BREAK (SBA)

NIAGARA MOHAWK PO\vEfi CORPORATION NINE MJLE POlN-l-Uf\JIT 2 lnPWt TE{} SAFE1VY ~IP<SlS REPORT USAR REVISION 0

DEADWEIGHT; SEISMIC LOADS; HYDROSTATIC PRESSURE INCLUDING SEISMIC EFFECTS; z ONE TO ALL SRV LINES ON SETPOIUT 0

i= AIR BUBBLE OSCILLATION PRESSURE AND DRAG ) SECTION 3 Ci z

0 0

C}

2 0

ct 0

~

TIME FIGURE 6A.2-15 NOTE; CONSIDERATION IS GIVEN TO LOAD COMBINATION HISTOR~ STRUCTURE REACTION LOADS ON THE AFFECTED: DOWNCOMERS, ACCIDENT DOWNCOMER FROM OTHER STRUCTURES CONDITION : NONE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 0 APRIL 1989

OEADWEIGHT; SEISMIC LOADS; LOCA PRESSURE ANO TEMPERATURE TRANSIENTS:

POOL SWELL .

AIR z COMPRESSION 0

j:::

0;z

> SECTION 4 0

0 C!l z HYDROSTATIC 0 LOAD DUE TO

<t WATER SWELL ,

0

_,J =

I I 0.7 1.5 TIME AFTER LOCA (SEC)

NOTE: FIGURE 6.;.2-16 CONSIDERATION IS GIVEN TO REACTION LOAD COMBINATION HISTORY LOADS ON THE WETWELL WALLS FROM STRUCTURE AFFECTED: SUPPRESSION ATTACHED STRUCTURES CHAMBER WALLS ABOVE THE WATER LEVEL ACCIDENT CONDITION: LARGE LINE BREAK (DBA)

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

OEAO';'/EIGHT; SEISMIC LOADS; LOCA ?AESSURE ANO TEMPERAiUAE TRANSIEFHS; HYDROSTATIC PRESSURE INCLUDING SEISMIC EFFECTS; DOWN*

COMER VENT CLEARING JET LOADS cor~OENSATION OSCILLA Tl mis

~ SECTION 4 AND CHUGGING z

0 E BUBBLE c

z FORMATION 0

tJ

(.!!

z Q

~

0 INADVERTENT SINGLESAV ;i. SECTION 3 ACTUATION I I I I 0 0.7 1.J J 100 TIME AFTER LOCA (SEC)

FIGURE 6A.2-17 NOTE. LOAD COMBINA I ION HISTORY, STRUCTURE CONSIDERATION IS GIVEN TO RE,'\CTIOIJ AFFECTED: SUBMERGED SUPPRESSION LOADS ON rne WETWElL WALLS FROM ATTACHED STRUCTURES CHAMBER, ACCIDENT CONDITION: LARGE LINE BREAK (OBA)

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 0 APr*UL 195g

OEADWE:JGHT; SEISMIC LOADS; LOCA PRESSURE ANO TEMPERATURE TRANSIENTS; HYDROSTATIC PRESSURE INCLUDING SEISMIC EFFECTS; INADVERTENT SINGLE SRV > SECTION J a

j:::

ACTUATION 0

z I. ___

0 u

Cl

z:

i5

<t 0 A_o_s_A_c_r_u_A_r_ia_N_ _ _, } secnoN J

..J CONOENSA TION OSCILLATIONS AND CHUGGING } SECTION*

I I I I s 25 220 TIME AFTER LOCA (SEC) FIGURE 6A.2-18

/.07t..~:

LOAD COMBINATION HISTORY, STRUCTURE

r. T J; l?.l~Ec.~ LFiE.! c ;. r-u~ ~.=:r:r Bt:i 1:; r~- :;1:A~L 1 r*~ ih:. AFFECTED: SUBMERGED SUPPRESSION o; 2 7r.  ::a l.f*lU1ES.

• Ott.C~u

~- CVl;;io:rt.tTILt IS C1\C*1 -o n:::t.c1 .:i:. L O J.D~ en 7::£ hETfi'A-l CHAMBER ACCIDENT CONDITION:

W'!U.S i=M Qµ ~Ti.t-~*:i:D S:iP.UCii.iRE.S.

J. LO~D CO!.!EJl~'itO;i f1 STORY LIAY nR1 $0~'E"l<i ~Hi!

INTERMEDIATE LINE BREAK

~t: ::_ c;: tS:.. ;en [X!JJFLE~ SRV ACTU.:.Hc:: Al s::,..

rO.'IT l!:Y OCC~R O!Jnll;u A SMAlLEfl la~.

NIAGARA MOHAWK POWER CORPORATION NJNE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 0 APRIL 1989

DEAOWEIGHT; SEISMIC LOADS; LOCA PRESSURE AND TEMPERATURE TRANSIENTS:

HYDROSTATIC PRESSURE INCLUDING SEISMIC EFFECTS; Jr SAV SRV MANUAL ACTUATION ON > SECTION 3 z DEPAESSURATION 0 SETPOINT Q

z I

0

(

(.)

C!J CHUGGING z

0

<t 0

I

-I AIR CLEARING I I I I 10 20 600 700 TIME AFTER LOCA (SEC)

NOTE:

CONSIDERATION IS GIVEN TO REACTION FIGURE 6A.2-19 LOADS ON THE WETWELL WALLS LOAD COMBINATION HISTORY FROM ATTACHED STRUCTURES STRUCTURE AFFECTED: SUBMERGED SUPPRESSION CHAMBER,ACCIDENT CONDITION: SMALL LINE BREAK (SBA}

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 0 APRIL 198q

DEAOWEIGHT; SEISMIC LOADS; HYDROSTATIC PRESSURE INCLUDING SEISMIC EFFECTS; 5RV t\CTUA TlOt~ ON PRESSURE SETPOHIT

z ONE TO ALL VALVES 0

i= AIR BUBBLE DSC !LLA TIOI' Pl~ESSURt:: Ar JD CRAG 0

z 0 SECTION 3

(.)

CJ

z:

c c:(

0

..J 0

TIME NOTE: FIGURE 6A.2-20 CO!llSIDERATION IS GIVEN TO REACTION LOADS ON THE WETWELL WALLS LOAD COMBINATION HISTORY, STRUCTURE FROM ATTACHED STRUCTURES AFFECTED: SUBMERGED SUPPRESSION CHAMBER.ACCIDENT CONDITION: NONE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT APRIL 1989

OEAOWEIGHT; SEISMIC LOADS; LOCA PRESSURE AND TEMPERATURE TRANSIENTS; HYDROSTATIC PRESSURE INCLUDING SEISMIC EFFECTS; r

DOWNCDMER VENT CLEARING 1-J-ET-LO_"_o__. BUBBLE FORMATION POOL sweu. AIR COllOEHSATIOH OSCILLATION COMPRESSION ANO CHUGGING SECTJON C POOLSWEU DRAG LOADS FALL BACK LOADS SUBMERGEOSTRUCTURELOADS DUE TO CONDENSATION OSCILUTIOllS AllD CHUGGING

~l-=--==-====m:~ll-IA=O~YE-R~TE=t-IT_S_IN_G_L.E_,,,S_AV~A-C-T-UA-T-I0-11--~-=--------=--===== ~-SECTION3 I I I I I I B.6 LO 11)(1 TIME AFTER LOCA !SEC)

FIGURE 6A.2-21

• U\TF* '

lCONSIOERA TION IS GIVEN TO REACTION LOAD COMBINATION HISTORY~STAUCTURE LOADS 011 SUBMERGED STRUCTURES FROM AFFECTED: SMALL SUBMERGED STRUCTURES OTHER ATTACliED STflUCTUflES AND PIPING, ACCIDENT CONDITION :

LARGE LINE BREAK (OBA}

NIAGARA MOHAWK POWER CORPORATION SOURCE: CALCULATION 12177-ES-122 NINE MILE POINT -UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVIS ION 8 NOVEMBER 1995

OEADWEIGHT, SEISMIC LOADS; LOCA PRt;SSURE ANO TEMPERATURE TRANSIENTS; HVOROSTATIC PRESSURE INCLUDING SEISMIC EFFECTS; Ll_ _ _ _ _ _ _ _ _ __r_1o_N_A_N_o~c-ttu_a_G_1_N_G_________.J c_o_N_o_e_N_sA_r_1_0N__a_s_c1_UA .

SU6MERGED STRUCTURE LOADS OU£ TO SECTION 4 CONOENSATIOt~ OSCILLATIONS ANO CHUGGING

~

0 E

c 0

0 INADVERTENT SJl~GLE Cl SRV ACTUATION 2

c

<t '

....0

> SECTION 3 I AOS ACTUATIOtl I

I I I I I I 5 25 35 ~o 220 TIME AFTER lOCA {SEC)

NOIES:

1. l IS 6AEAK AREA, OEP!i'ND!:.NT, BUT IS TYPICAll YIN THE OROEn OF 2 TO 5 MINUTES FIGURE 6A.2-22

2. CONSIDERATION IS GIVEN TO REACTION LOADS ON SU81.1EfiGEO STRUCTURES FROM LOAD COMBINATlON HlSTDRY ~ STRUCTURE OTHER ATTACHED STRUCTURES AFFECTED: SMALL SUBMERGED STRUCTURES 3~ LO.'.l:i CO~! a: *J~Tlor: HfSTO=i r' :~~ :...'( \i~R I AND Pl PING. ACCIDENT CONDJTION I S.J:,' E\'ili,.lf \~ITd SIZE OF IDA. FOR INTERMEDIATE LINE BREAK CIBA>

.;.10.

;;

_:;, SHV ACiU:.f!Ctl ;;T SET

?C.ttT M~! OCCUR OJf:I~G ;.. 51,:#".LL ER IBA .

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 0 APRIL 1959

Oi:ADWEIGHT; SEISMIC LOADS; LOCA PRESSURE ANO TEMPERATURE TRANSIENTS; HYOROST A TIC PRESSURE INCLUDING SEISMIC EFFECTS; z

0 i= SRV ACTIVATION 0 ON SETPOINT SRV MANUAL DEPRESSURIZATION 2

0 u

G

z SECTION 3 0

<(

0

...J CHUGGING CHUGGING SUBMERGED STRUCTURE LOAD SECTION 4 AIR CLEARING I I I I 0 12 20 600 IV2000 TIME AFTER LOCA (SEC)

NOTE:

CONSIDERATION IS GIVEN TO REACTION FIGURE 6A.2-23 LOADS ON SUBMERGED STRUCTURES FROM OTHER ATTACHED STRUCTURES LOAD COMBINATION HISTORY 1 STRUCTURE AFFECTED= SMALL SUBMERGED STRUCTURES AND PIPING, ACC1DENT CONDITlON:

SMALL LINE BREAK CSBAJ NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNiT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 0 APRIL 1989

DEAOWEIGHT; SEISMIC LOADS HYDROSTATIC PRESSURE INCLUDING SEISMIC EFFECTS z

0 ONE TO ALL VALVES ON PRESSUR~ SETPOINT j:::

0 AIR BUBBLE OSCILLA T!ON PRESSURE AfliD DRAG z

0 0

(!J SECTION3 z

ad:

0

...I 0 TIME NOTE:

FIGURE 6A.2-24 CONSIDERATION IS GIVEN TO REACTION LOADSONSUBMERGEOSTRUCTURESFROM LOAD COMBINATION HISTORY, STRUCTURE OTHER ATTACHED STRUCTURES AFFECTED: SMALL SUBMERGED STRUCTURES AND PIPING. ACCIDENT CONDITION: NONE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 0

OEADWEIGHT; SEISMIC LOADS LOCA PRESSURE AND TEMPERATURE TRANSIENTS IMPACT LOADS z

0 i= FOOL SWELL 0

z DRAG LOADS 0

u CJ SECTION 4 z FALL BACK 5 LOADS

< BUBBLE 0

.J rORMATJON SUPPRESSION POOL CONDENSATION OSCILLATION SWELL AIR COMPRESSION AND CHUGGING

.._I_ _ _ _ _ _ _ _ 1N_A_rN_E_RT._'A_NT_S1_NG_LE_s_Rv_A_c_ru_A_T_10_N_ _ _ _ _ _ _ _ _.....1} SECTION 3 I I I 0.B 1.6 .2.'1 TIME AFTER LOCA (SEC)

FIGURE 6A.2-25 LOAD COMBINATION HISTORY, STRUCTURE AFFECTED: SMALL STRUCTURES ABOVE POOL AND BELOW BREAKTHROUGH, ACCIDENT CONDITION: LARGE LINE BREAK (DBA}

NIAGARA MOHAWK POWER CORPORATION SOURCE: CALCULATION 12177-ES-122 NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR HEVJSJON 8 NOVEMBER 199S

OEADWEIGHT; SEISMIC LOADS LOCA PRESSURE AND TEMPERATURE TRANSIENTS z

0 t=

0 BUBBLE SUPPRESSION POOL CONDENSATION OSCILLATION z FORMATION SWELL AIR COMPRESSION AND CHUGGING 0

(.)

t:J z

0

~

0

.J 0

TIME AFTER LOCA FIGURE 6A.2-26 LOAD COMBINATION HISTORY, STRUCTURE AFFECTED: SMALL STRUCTURES ABOVE BREAKTHROUGH, ACCIDENT CONDITION:

LARGE LINE BREAK (OBA}

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

CONTAINMENT PEDESTAL DOWNCOMER DISCHARGE LINE HIGHEST WATER LEVEL BASEMAT REFERENCE ORA WING STONE & WEBSTER 12177*EM*2J*18 FIGURE 6A.3- l UNIT 2 SUPPRESSION CHAMBER NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISICN 5 OCTOBER 19~3

~*

SPRING SET PRESSURE PSIG 1250 1200 1150 BOO 900 1000 1100 1200

---

iL:::"> MASS FLUX LBM/HA FIGURE 6A.3-2 UNIT 2 SAV-MASS FLOW RATES NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 5 OCTOBER 1993

180° 275° 257° 270a

() POSITION OF THE ADS-QUENCHERS FIGURE GA.3-3 POSITION OF THE QUENCHERS IHAGARA MOHAWK PO\-/ER CORPORATIOM NINE MILE POINT-UNIT 2 UPDATED SAFETY Al,JAL YSIS REPORT USAA REVISION 5 OCTOBER 1993

STRUCTURAL ANCHOR EL. 287'*2 r SAFETY RELIEF VALVE PSV 120

~LVENO.

7 3

RELIEF VALVE (VACUUM BREAKER) 4 EL. 2.53.5* RV 101 EL. 251' RV 201 10" X 12" REDUCER ELBOW DFIYWELL FLOOR LLVENO.

PENETRATION ANCHOR EL 24a *0" 1

12" LINE 4° 13' 7

_ __,__..,,._NORMAL WATER LEVEL.200' 4° 13' 8

EL. 179'*7" (CENTERLINE QUENCHER ARM)

FIGURE SA.3-4 SHORTEST SRV DISCHARGE LINE GEOMETRY NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 5 OCTOBER 1993

r SAFCTY RELIEF VALVE PSV 135 STRUCTURAL '

ANCHOR LvALVENO.

EL 287'-2" 10" LINE 10 RV 106 EL 253'6" AV 206 EL. 251' 10" x 12" REDUCER ELBOW PENETRATION ANCHOR 12" LINE EL 240'-0" 16 EL 179'-7" (CENTERLINE QUENCHER ARM)

FIGURE 6A.3- 5 LONGEST SRV DISCHARGE LINE GEOMETRY NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT YISIOH 5 QC TOBER 19<J3

DRYWELL DOWN COMER VENT__,,,.

SUPPRESSION CKAMBER AIRSPACE T

ti x,x,x WATER SLUG AIR BUBBLE:

SUPPRESSION POOL X - POOL OISPLACl:MENT X- POOL VELOCITY X - POOL ACCELERATION I m- SLOWDOWN MASS FLOW RATE

---_:=__sc"HEMA:-ric RE-PREsENrArloN oF SUPPRESSION POOL SWELL ANALYTICAL" MODEL NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-Ul\l!T 2 UPDATED SAFETY ANALYSIS *REPORT ACOTI 1 aao

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FIGURE 6A.4-2 PRIMARY CONTAINMENT PRESSURE DURING SUPPRESSION POOL SWELL FOLLOWING OBA NIAGARA MOHAWK POWER CORPORATION THIS ORAWl~G CREATED ELECTRONICALLY NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSJS REPORT USAR REV!SlON 8 NOVEMBER 199S

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FlGUAE 6A.4-3 SUPPRESSION POOL SURFACE ELEVATION FOLLOWING OBA NIAGARA MOHAWK POWER CORPORATION I fHIS DRAWING CREATED ELECTRON!CALLY I NINE MILE POINT-UNIT 2 SOURCE: CALCULATION 12177-ES-122 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER t99S

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@1S OfiAIJING CREATED ELECTRON!CALL'I I NINE MILE PO Il\JT-UN IT 2 SOURCE: CALCULATION 12177-E.S-122 UPDATED SAFETY ANALYSTS REPORT USAR REVISJON 8 NOVEMBER 199S

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ELEVATION FOLLOWING OBA NIAGARA MOHAWf< POWER CORPORATfON I HHS DRA\./!NG CREATED ELEC TP.ONICALL'( I f\J I f\J E MILE POINT-UNIT 2 SOURCE: CALCULATION 12177-ES-122 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 8 NOVEMBER 199S

DOWNCOMER VENT-".;;i" PRESSURE OF SUPPRESSION CHAMBER AIR SPACE. Ps MAXIMUM POOL SURFACE ELEVATION

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ACTUAL

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ASSUMED FIGURE 6A.4-6 ASSUMED PRESSURE DISTRIBUTION FOR SUPPRESSION POOL BOUNDARY LOADS DURING SUPPRESSION POOL SWELL NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL Sl\~ETY AN/~L YSl3 RC:i18RT

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1.1 l.~ 2.l Z.) Z.5 2.1 2.'i n>£ <E'IEll OOA ISECINh FIGURE 6A.4-7 SUPPRESSION POOL FALLBACK VELOCITY AND ELEVATION FOLLOWING OBA NIAGARA MOHAWK POWER CORPORATlON I THIS DRAYING CREATED ELECTRONICALLY I NINE MILE POINT-UNIT 2 SOURCE: CALCULATION 12177-ES-122 UPDATED SAFETY ANALYSIS REPORT USAR REVISION B NOVEMBER 1995

THIS FIGURE HAS BEEN DELETED F'tGURE 6A.4-8 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPOA fED SAH:. iY ANALYSIS REPORT USAR REVISION 5 OCTOBER 1993

(

THIS FIGURE HAS BEEN DELETED FrGURE 6A.4-CJ NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UFOA TED SAFE T < ANALYSIS REPOR i USAR REVISION 5 OCTOBER 1993

THIS FIGURE HAS BEEN DELETED FIGURE SA.4-10 I

NIAGARA MOHAWK POWER CORPORATION N!NE MILE POINT-UNIT 2 UPDATED SAFETY ANAL YSI~ REPORT USAR REVISION 5 OCTOBER 1993

z 0

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THIS FIGURE HAS BEEN DELETED FIGURE 6A.4-12 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 RE?ORT I UPOAT~D 5~FETY AhALY~S USAR REVISION 5 OCTOBER 1993

- /OESIGN MOMENT AXIS so*

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..._.........._ / I REACTOR

• ~210*

• OOWNCOMER +

FIGURE SA.4-13 DOWNCOMEA INDEXING WITH ASYMMETRIC AXIS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 17 JANUARY 1985

24.00 MAX PRESS= 17.810 PSI AT TIME= 0.062 SEC 16.00 a.oo

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FIGURE 6A.4-14 UNIT 2 CHUGGING WALL PRESSURE TJME HISTORY AT THE CORNER OF BASEMAT AND A

PEDESTAL WALL AND 9 DEGREE AZIMUTH GE801-SYMMETRIC LOAD CASE NIAGARA MOHAWK POWER CORPORATlON NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 5 OCTOBER 1993

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o.oo o.aa 0.40 0.60 IJ.80 1.0G 1.20 1.-40 1.SO 1.00 2.00 TIME (SEC)

FIGURE 6A.4-15 UNIT 2 CHUGGING WALL PRESSURE TINE HISTORY AT THE JUCTJON OF BASEMAT AND PEDESTAL WALL AND 9 DEGREE AZIMUTH. GE802 - SYMMETRIC LOAD CASE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 5 OCT<>SER t993

12.00 - - - . . . . - - - - . - - - - . - - - - - - . - - - - - . - - - . . . - - - . . . - - - - - . - - - - - . - - - -

MAX PRESS"" 8.047 PSI AT TIME= 0.040 SEC a.oo J - t - - - - + - - - - - - + - - - - + - - - - - + - - - - + - - - - + - - - - - t - - -- - - t 4.00 ,H t - - - - + - - - - t - - - t - - - - - + - - - - t - - - - - + - - - - t - - - - - t - - - r - - - - - - 1

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• S.00 t - - - + - - - - - + - - - - t - - - - + - - - - t - - - t - - - - + - - - - + - - - - f - - - - - 1

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0.00 0.20 0.40 0.60 0.80 1.00 1.20 1.40 1.60 1.80 2.00 TIME (SEC)

FIGURE SA.4-16 UNIT 2 CHUGGJNG WALL PRESSURE TIME HISTORY AT THE JUNCTION OF BASEMAT AND PEDESTAL WALL AND 9 DEGREE AZIMUTH GEB03-SYMMETR1C LOAD CASE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT US.lR R£VtSION 5 OCTOB£R 1993 ..

12.00 li;iAJt PRESS= 10.770 PSI ATTll!!JE= 0.046 SEC h- 1

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FIGURE 6A-4-17 UNIT 2 CHUGGING WALL PRESSURE TlME HlSTORY AT THE JUNCTlON OF BASEMAT AND PEDESTAL WALL AND 9 DEGREE AZIMUTH GE804-SYMMETRIC LOAD CASE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT U AR

12.llO MAX PRESS= 10.680 PSI AT TIME= 0.036 1SEC O.IW ..... I 1

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FIGURE 6A.4-18 UNIT 2 CHUGGJNG WALL PRESSURE TJHE HISTORY AT THE JUNCTION OF BASEMAT AND PEDESTAL WALL AND 9 DEGREE AZIMUTH GE80S-SYMMETRIC LOAD CASE NIAGARA MOHAWK POWER CORPOHATION NINE MJLE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT

• .- ..USAR R£VISION 5 OCTOGER l~s.t.S.

"6.00 ---....---------.------r---i---..,..----r----r---.....,..---.

IUIAlt PRESS:;; 4.433 PSI AT TIME= 0.050 SEC 4.00 ~'--+----1-----+--~-----il----+----t----+-----t-----t 2.{)0 iii '

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FIGURE 6A.4-19 UNIT 2 CHUGGlNG WALL PRE55URE TIME HISTORY AT THE JUNCTION OF BASEMAT AND PEDESTAL WALL AND 9 DEGREE AZJHUTH GE806-5YMMETRIC LOAD CASE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR ~EVlStQN 5 ocr~_.r=

12.lW>

~A.IC PRESS= 8.892 PSI A.T TIME= O.<l48 SEC L}..00 I

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FIGURE 6A.4-20 UNIT 2 CHUGGING WALL PRESSURE TIME HISTORY AT THE JUNCTION OF BASEHAT AND PEDESTAL WALL AND 9 DEGREE AZJHUTH GE807-SYHMETRIC LOAD CASE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 5 OCHla£R ~3*

1a.G.O 0.-'--"P---..,-----r--~----:r----r---.----.---r---.

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FIGURE 6A.4-21 UNIT 2 CHUGGJNG WALL PRESSURE TIME HISTORY AT THE JUNCTION OF BASEMAT AND PEDESTAL WALL AND 9 DEGREE AZIMUTH GE808-SYMMElRIC LOAD CASE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT

. USAR REVISIOO 5 OCTO&R 1993

MAX PRESS= 10.790 PSI AT TIME= 0.048 SEC O.Qtl -

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FIGURE 6A.4-22 UNIT 2 CHUGGING WALL PRESSURE T M HISTORY AT THE JUNCTION OF BASEMAT AND PEDESTAL WALL AND 9 DEGREE AZJMUTH GE809-SYMMETRIC LOAD CASE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT US~R REVISION 5 ~ ~ t~Sl5

MAU PRESS= 11.600 PSI

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FIGURE 6A.4-23 UNIT 2 CHUGGING WALL PRESSURE TIME HISTORY AT THE ~UNCTION OF BASEHA1 AND PEDESTAL WALL AND 9 DEGREE AZIMUTH GE810-SYHMETRIC LOAD CASE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPOATED_SAFETY ANALYSIS REPORT USAR REVISIOH OCTQS£R ~3

15.00 --------------.----,---,---~---r-----r-----r-=---a

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FIGURE 6A.4-24 UNIT 2 CHUGGING WALL PRESSURE TJME HlSTORY AT THE JUNCTION OF BASEMAT AND PEDESTAL WALL AND 9 DEGREE AZIMUTH GE811-SYMMETRlC LOAD CASE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USA.R REVISION 5 OCTOSER 19Sl.5

32.00 -

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FIGURE 6A.4-25 UNIT 2 CHUGGING WALL PRESSURE TIME HISTORY AT THE JUNCTION OF BASEHAT AND PEDESTAL WALL AND 9 DEGREE AZIMUTH .

GE801-ASYMMETRIC LOAD CASE .

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 5 OCT

6.00 - l!::IAX PREWi = 5.5fl6 PSI ATTlf:!IE = 0.636 SEC 4 .00 ,_ '-

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UNIT 2 CHUGGING WALL PRESSURE TlME HISTORY AT THE JUNCTION OF BASEMAT AND PEDESTAL WALL AND 9 DEGREE AZIMUTH GE802-ASYMMETRIC LOAD CASE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USA VISION 5 oc

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FIGURE 6A.4-27 UN1T 2 CHUGGING WALL PRESSURE TlME HISTORY AT THE JUNCTION OF BASEMAT AND PEDESTAL WALL AND g DEGREE AZ1MUTH GE803-ASYMMETRIC LOAD CASE --

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 5 OCTOBER 19~!i

.r:=:--

ll~AA PRESS= 9.489 PSI AT TIME = 0.046 SEC 4.00 -

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FIGURE 6A.4~28 UNIT 2 CHUGGING WALL PRESSURE TIME HISTORY AT THE JUNCTJON OF BASEMAT AND PEOE$TAL WALL AND 9 DEGREE AZlMUTH GE804-ASYMMETRIC LOAD CASE NJAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR REVISION 5 OCTOBER rgg.J

12.00 MAX PRESS = 9.153 PSI AT TIME= 0.036 SEC 8.00 ti

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FIGURE 6A.4-29 UNIT 2 CHUGGING WALL PRESSURE TIME HJSTORY AT THE JUNCTION OF BASEMAT AND PEDESTAL WALL AND 9 DEGREE AZIMUTH GE805-ASYMMETRIC LOAD CASE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT

.. USAR REVISION 5 OCTOBER 1993

G.00 .----....---..,.----..,---~----.---,----,...--~---,----,

~AX PReBS = 4.353 PSI AT Tlih'.IE = 0.050 SEC 4.00 - --~--~t.---1----+----+----t----t----t----t---~

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TIUE (&EC}

FIGURE 6A.4-30 UNIT 2 CHUGGI~G WALL PRESSURE TlHE HISTORY AT THE JUNCTION OF BASEHA T AND PEDESTAL WALL AND 9 DEGREE AZIMUTH GE806-A5YMMETRIC LOAD CASE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR RE VISION 5 OCTOBER IHl

12.00 ru!Alt PRESS"" 7.950 PSJ AT TtL\llE = 0.048 1SEC G.QO

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FIGURE 6A.4-31 UNIT 2 CHUGGING WALL PRESSURE TJHE HISTORY AT THE JUNCTJON OF BASEMAT AND PEDESTAL WALL AND 9 DEGREE AZIMUTH GE807-ASYMMETRIC LOAD CASE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT US.lR REVISION 5 OCTOBER 1993

12.0l>---...----....--------,-----,-----,.-----,---~----r----,

MAA PRESS= 8.582 PSI AT TIME= 0.038 SEC a.oo .__._._ _J - - - - - - + - - - - i - - - - ' - - - - " ' - - - - ' - - - - + - - - _ _ . . - - - ' 4 l

4.()0 ia

~,

{;':.

~ 'l (\,__ /"'... _,,.-_ . .

LY "l 1\

Cl!

!) 0.00 8l.:J \ / ~V ~... '=-er lf

-4.~

-6l.IXJ t - - - - + - - - + - - - - + - - - - + - - - - + - - - - t - - - - h - - - - - + - - - - + - - - - - 1

-12.(};0 ---"'----~--..L.----'----~--~--......L.----'---'-'---....1 O.c;:J 0.40 Q.(}4 0.00 1.GO 1.20 1.'40 1.60 1.00 2.00 TIME (SEC)

FIGURE 6A.4-32 UNIT 2 CHUGGING WALL PRESSURE TIME HISTORY AT THE JUNCTION OF BASEMAT AND PEDESTAL WALL AND 9 DEGREE AZIMUTH GE808-ASYHHETRIC LOAD CASE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT

---=

12.00 MAX PRESS =10.150 PSI 3 AT TIME:; 0.066 'SEC o.ao l~...

t

~

4.G;;J '

1

(,;;

0..

l v

r w

a j \ ".......f ~

v c . ._

> 0.@':J

"" - - ~ If I

ii;

~

-J.Gil O.f:l.O O.lil0 1.ca 1.20 1 ..CO 1.60 1.QO 2.00 TIUE {SEC)

FIGURE 6A.4-33 UNIT 2 CHUGGING VALL PRESSURE TJME-HISTORY AT THE ~UNCTION OF BA5EMAT AND PEDESTAL ~ALL AND 9 DEGREE AZIMUTH GE809-ASYMMETRIC LOAD CASE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT

,REVIStqN 5 OCT

ruJA.l( PRESS= 9.916 PSI AT Tll:.SE = 0.036 SEC a.oo ,_ . . . _ _ - l . - - - l l - - - + - - - - - - + - - - + - - - t - - - t - - - - r - - - - i

• O.rtU - - - - l - - - - - l - - - - - + - - - - - - - + . - - - - - - - 1 1 - - - - + - - - - 1

• 1.a.00 ._._-.li---"----...L----i----..&...-----1---_...---"'---------"""

o.C@ o..ae o.~ 0.00 1.00 1.20 1.40 1.60 UlD 2.00 Tl~IE (SEC}

FIGURE 6A.4-34 UNIT 2 CHUGGING WALL PRESSURE TIME HISTORY AT THE JUNCTION OF BASEMAT AND PEDESTAL WALL AND 9 DEGREE AZIMUTH GE810-ASYMMETR1C LOAD CASE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USAR RE VISION 5

• OCTOS£R ~3

12.f}O MAX PRESS =,10.880 PSI AT TIME= 0.046 SEC i

e.oo "

}I

~}l .

l 4.~

'~

~

v'"'

~

iii r

~

v l!.I Ci!  ! J \ F\_

> I.I.CJ I "" 'IQ..

~

'i'"

~

rt :1

-<J.~

~ ..._

0.<10 O.fHJ 1.oa 1.20 1.40 1.60 1.ca 2.00 TIME (5fC)

FIGURE 6A.4-35 UNlT 2 CHUGG1NG WALL PRESSURE TIME HISTORY AT THE JUNCTlON OF BASEMAT AND PEDESTAL WALL AND 9 DEGREE AZIMUTH GEB11-ASYMMETRIC LOAD CASE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT r:=r=---

USA8 REVISION S OCT08£R ffi~

a3 u se

<fl=- ~

2 r::

'I. :b + r cos e EL= 190 FT.

R:rsine 2 2 I

,-- : ( IX - b I + ( R)] /2 b

U = VELOCITY OF SPHERE, FT. I SEC cp = POTENTIAL FUNCTION, FT.2. I SEC x

r

~~ lr,e]

[R,x)

FIGURE 6A.4-36 1-----R---i>ol POOL BOTTOM DOWNCOMER WATER JET MODEL NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT VISION 0 APRIL 1989

---~/**-- STPUCTUPAL

,_ \

POINT OF lNTEREST

./

/

/

_,,/

/

• *'t :*c

• Y* 1

/ / ,*' , ,* .

(/

1

~*:*.-.

I '

\

, \,,

)*x .:

~\

I l HEAN RADUS ( R !t l = - - -

R, +

2 R~,

J

'y~r

. . ., </)P ..

\ *--<. I . . .*

\.. o;./"**-------** ,,/

'**' -.. . . . 11 _,./

_,/

~-

I -- 1 I

! x. y) COORDINATES FOR LOAD OUTPUT I I

( ~< *µ.) INTERNAL REFERENCE COORDINATES I FOR CAL CUL,<\ Tiot*l I l

I I

THE OUTER [QR ANNULAR> POOL IS '77"! RM

~ I rx -.µ.

C> * ' )

.;PPROX*1f'1A TED BY Ui\l\~RAPPIJ*JG ONE-HALF OF THE AN/\IULAR POOL .ll.i'ID fR4~JSFORl1ll\JC fT 1NTO A RECTANGULAR BOX. If I

1

-RM 2

l..::t- R2 *A,. ~ -x_I j_

FIGURE 6A.4-37 I

I I HEC1 ANGULAt1 80X Al-'1-'ROXIMA 1 luN roR ANNULAR POOL I

I I

NIAGARA MOHAWK POWER CORPORATION I NH~E MILE POINT-Uf'JIT 2 UPDATED SAFETY ANALYSIS REPORT 1 11~ ~o oc u r c r n...1 n ... ,~... . , __

STRUCTURAL POINT OF INTEREST 0

DRAWING ANGLE

µ.

l

'l

µ.' '

Lx T

1 l

2Rt

/

Rt J_

Id x 2R1

~

• FIGURE 6A.4-38 GECI Al'lGuLAH ouX Af-'!Ji;OXlfvtA flON FOR INNER POOL NIAGARA MOHAWK POWER CORPORATION NINE ~~ILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT

J RtSIOU~l llEAT REIAOVAl.

llEAr £XCHAtlGE~ "EIA." 'iTEM,I OIGCliAllGE 2*A~tS*OIJJ.~~l*1 EL1Wr*!\{" - - - - - - - - - - . . _ , - - - - - - 2 t

• Ht5JUUAL t1Elrl. T AEMO'IAl A' ?Uf.IP SUCT!Oll i*;,,us 02'4*1*1.

EL.. IJ$'.\I

• Ill" OE~IOilAl HEAT Rl!l.IO'IAL rnoM PUMP "PIA" lG .. ilf510Vt\l- HE.AT REMOVAL Fno .. PUMP ' PIU'

<;" Ac510UAL llEJ\1 ~'MOV4L

• 5 .. FUMP SUCTION

.AH!i*Ol4*1di"*'.a'

~l- ISS'-0" ---------~

/

1r.nu:.1 rGat Lt: 1H ft. l.lJO rl \'Jt

.':~ ~:~i~:~~~~\~01*) r. t. 1 u~:.. ~:.

.u  !;ll(:; lUJl!jtlJ _. ) t.l. H1] ~ ll SOURCE. EM-002A REV, 20 i

' !.t !;\ 1 ~;1 : ;11 ! flJJIJ tt  !:";~* * \!.

• • J H. :..,: 1t*i~ tl '"-;

FIGURE 6A 4-39 SUPPRESSION POOL PIPING

SUMMARY

COMPOSITE I Jlr'\f"i14r\'A MOHt"lh'V PDHER [ DRl'OflA fl UH Ht ~JE ~**1I LE P C1 If l f - U i\J I i 2.

UPDArEO SAFETY <\NP1L YS IS Hl:.PlJH f

(

soa------..----~-.--~~...-------~~------

375

-LI.

a::i

...J c 300 0

..J 225 0.5 O.G 0.7 0.8 0.9 1.0 1.1 TrME (SEC)

FIGURE 6A.4-40 WATER JET TIME HISTORY-ONE QUENCHER NIAGARA MOHAWK POWER CORPORATION !

NINE MILE POINT-UNIT 2 1

., UPDATED SAFETY ANALYSTS REPORT I USAR REVISIOl*J 0 APRIL 1989

270 240 210 180 I 150 G::

CD

!. 120 0

q; 0

-l 90 60 30

) I J/

0

.30 0.5 0.6 0.7 0.8 0.9 1.0 1.1 TIME (SEC)

FIGURE 6A.4-41 WATER JET TIME HISTORY-ONE QUENCHER ARM SEGMENT IN Z PLANE (VERTICAL!

~

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 lrs - ... . '*+-~--- *.. ~

UPDATED SAFETY ANALYSIS REPORT USAR REVISIOM 0 APRIL 1989

1.0

~ -~  :-....

7 0.9

~

~ j COALESCENCE OF BUBBLES (i.e. ENO OF LOCA BUBBLE LOAD) 0.8 y

0.7 0.6 c

-,.., 0.5 ....___

w

-.....c ' 0.4 g

- 0.3 0.2 -

0.1 0.84 0.85 0.86 0.87 0.88 0.69 0.90 0.91 0.92 TIME (SEC)

FIGURE 6A.4-42 LOCA AJR BUBBLE NORMALIZED LOAD TIME HlSTORY FDR A DDWNCOMER SEGMENT NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT U5AR REV[SIDN 0 APRIL 19BS

- *....:;i;::

-I .If ,1 n:

WATER

- LEVEL DRAGS AT TIME= 0.870 SECONDS 6 EL 201' SEGMENT NO.

x STANDARD DRAG (LBF) y z RESULTANT 5

4 i1.83' (TYP) 0.55 0.0 T

1 *2.23 2.30 2 0.32 -1.27 0.0 1.31 0.16 0.0 3 3 *0.63 0.65 4 0.07 *0.28 0.0 0.29 5 0.02 .Q,09 o.o 0.09 2 6 0.00 *0.01 o.o 0.01 TOTAL 1.14 *4.51 o.o 4.65 1

! ~2*~

- - EL19D' ACCELERATION DRAG (LBF)

SEGMENT NO.

x y z RESULTANT 1 132.08 -532.66 o.o 548.79 2 101.34 -400.89 0.0 413.50 3 73.55 -283.21 o.o 292.60 4 50.06 -187.75 o.o 194.31 5 29.17 -107.28 o.o 111.17 6 9.59 - 34.90 0.0 36.20 TOTAL 395.80 *1546.69 0.0 1596.58 TOTAL DRAG (LBF)

SEGMENT NO.

x y z RESULTANT 1 132.64 *534.90 0.0 551.09 2 101.66 *402.16 o.o 414.81 3 73.71 -283.84 o.o 293.26 4 50.13 -188.03 o.o 194.60 5 29.20 -107.37 o.o 111.27 6 9.60 - 34.91 0.0 JG.21 TOTAL 396.94 -1551.20 o.a 1601.23 POOL BOTTOM

////7 7// ///7 / / / /  !;I. 176' FIGURE 6A.4-43 LOAD DISTRIBUTION ON DOWNCOMf:'.R DUE TO LOCA AIR BUBBLE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2

. F!t JAL S/l.i=ETV Ai~AL YSl!:l ~t:PORT

24 22 20 18 15 -

i*1

..-POOLSWELL 12 IMPACT C:

>. 10 in

=

m UJ a

u c:

0 6

u. ,I SWELL 4

2 0

-2

-4

-5 0.9 1.0 1.2 1.4 1.6 1.s 2.0 2.2 VI 2.8 3.0 TIME (SEC)

FIGURE 6A.4-44 VERTICAL LOAD ON LINE 2 ICS-012-75-2 DUE TO POOL SWELL AND FALLBACK NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

soo I I

600 -

<lOO r-I t

)

200 ,_

ii::

I I

ID UJ u

a:

0 u..

0 t

.l

-200 ~

I'

-400 r'

-600 -

1.0 1.1 1.2 1.3 1.4 1.5 TIME (SEC} FIGURE .6A.4-45 HORIZONTAL LOAD ON LINE 2 ICS-012-75-2 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

1.0 0.8 0.6 I/

0.4 w

a:

en 0.2 cn w

a:

a..

o.o c

w N

. .J -0.2.

~

Q:

0 z -0.4 A

-0.6

-0.8

-1.0 0.00 O.BO !. 60 2.40 3.20 4.00 4.80 TIME (SEC)

FIGURE 6A. 4-46 CO LOAD TIME HISTORY FOR OOWNCOMER 43 (4TCO RUN 12)

I NIAGARA MOHAWK POWER CORPORATION l NINE MILE POINT-UNIT 2 UPDA7ED SA~ETY ANALYSIS REPORT USAA REVIS~ 5 OCTOBER 1993

--.. _!..£..L_ ~

WATER

- - - LEVEL

. 6 EL 201' I 5 i

I 4 1.83' {TYP}

I I J T

2 1

- - - EL190'

~ 2*-s=-}

I SEGMENT NO.

x TOTAL DRAG CLBFJ y z RESULTANT 1 392.22 1024.76 0.0 1097.25 2 303.41 774.29 0.0 831 .52 3 221 .18 S50.95 0. <21 593.69 4 150.35 367.66 0.0 397.21 r; 87.35 211.14 0.0 228.SQJ

! 6 28.65 68.89 0.0 74.61 TOTAL 1183.17 2997.69 0.0 3222.BB POOL BOTTOM .

/ / / / / / / / / / / / / / / / EL 176' I

FIGURE 6A.4-47 i D.r:" A I< I r)Ar:)

• f:"IT<:;T~iRIJTT('f\I (ll\' f')n\oJr,frh(v1cql 4TCO RUN12, 11-2r s~c

• J'

-- I NIAGARA MOHAWK POWER CORPORA.TION I I

I NINE MILE POIN"f-UN!T 2

~- UPDATED SAFETY ANALYSIS REPORT

1c1t.O nr-\JTrrn"' I"'\

~ -

~J.l/l tn WATER I

I -

~

- - LEVEL 6 EL 201' 5

1

-~

4 1.83' (TYP) 3 r

i I

- --. 2 I SEGHEMT NO.

x TOTAL DRAG ILBFl y z RESULTANT 1

-- EL 190' 1 1491.19 !l1.fll -1 861

• 20 2384.89 1~ 2 *~1 x7Y 2 1407.93 0.0 -14B7.4S 2048. 11 3 803.86 0. Q) -1064.22 1333.70

,.4 735. gs 0.0 -711 .08 1023.35

i 467.93 0.0 -446.23 646.59 5 409.44 0.0 -146.13 182.57 TOTAL 5316.30 0.0 -5716.31 *7619.21 I

--- ..~ -

z.

POOLBOTIOM

///77 7// /7/7/7/7 EL176' I~

I i FIGURE 6A.4-48 PEAK LOAD FOR CHUGGING ON DOWNCOMER FOR SOURCE GEBO!

I N[AGARA MOHAWK POWER CORPORATION l

\

'.NINE MJLi:- PO!~JT-UNIT 2 I I lP~TBJ SAFETY ANAL VSIS ~PORT r r 11~ l\ D D C1.rt~IJ"\JU .. ..._,._..,..,..,Ulfl_. .. ..jfi.O Q

THIS FIGURE HAS BEEN DELETED FlGURE 6A.4-49 NIAGARA MOHAWK POWER CORPORAT[ON NINE MILE POINT-UNIT 2 I

UPOA T~O SAFETY AMAL Y'S!~ Rf PliRT USAR REVISION 5

20 PSAM~

18 '-..-....

_,.,,, /:1

_/

~

7 16

~

u.

z 14

/

I'"

0 j::

<t

/

12 UJ

_j POSHV * - LI IJ.I 10 UJ v

~

<t /

/

LL. B a:

en 6

v

...I 0

0

n. /

/

4 2

v 0

~

0.0 0.2 0.4 0.6 0.8 1.0 1.2 TIME AFTER VENT CLEARING (SEC)

"'SWEC EQUIVALENT OF MARK 11 PSAM FIGURE 6A.4-50 POOL SURFACE ELEVATION VS TIME COMPARISON OF POSHY & PSAM NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT21 SEPTEMBER 1985

0 w

en 1-u..

u 0

...J w

w

(.)

<t u..

0::

l en

...J 0

0 c..

POSHV *_/

0'--~~~~_.__~~~~_._~~~~~~~~~~~~~~-'-~~~~-'

o.o 0.2 0.4 0.6 o.a 1.0 1.2 TIME AFTER VENT CLEARING {SEC)

,._SWEC EQUIVALENT OF MARK 11 PSAM FIGURE 6A.4-51 POOL SURFACE VELOCITY VS TJME COMPARISON OF POSHY & PSAM NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANAL YSS REPORT

fl- - *-

40 38 POSHY * -\

- 36

~ ,,,__.

- /j*

<t en 34 ll.

w .........

a:

/

l 32

~

C/J w

en PSAM-0:: 30 V""

0.

lJJ

-J

~ ~

Ill 28 OJ m 26 a:

<t 24 22 20 0.0 0.2 0.4 0.6 O.B 1.0 1.2 TIME AFTER VENT CLEARING (SEC)

• SWEC EQUIVALENT OF MARK II PSAM FIGURE 6A.4-52 AIR BUBBLE PRESSURE VS TIME COMPARISON OF POSHY & PSAM NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

~- ~

AMENDMENT 21 SEPTEMBER 1985

50 e:.

en 45 w

a: POSHY *1

> 40

~ ~~

(/)

CJ)

LU c: 35 a.

LU u

30

~ PSAMJ

/

~

0...

Cf) a:

<t 25 c: V" w

cc 20 ~

~ ~

ct ~

[j 1s -

z 0

CJ) 10 Cf)

LU c:: 5 a..

a.

J CJ) 0 0.0 0.2 0.4 O.fi 0.8 1.0 1.2 TIME AFTER VENT CLEARING (SEC)

• SWEC EQUIVALENT OF MARK II PSAM FIGURE 6A.4-53 SUPPRESSION CHAMBER AIRSPACE PRESSURE VS TIME COMPARISON OF POSHY & PSAM NIAGARA MOHAWK POWER CORPORATION NINE M-ILE POINT~UNIT 2 FINAL SAFETY ANALYSIS REPORT AMi=NnMFNT ?1 SEPTEMBER 1985

20 18 16

-z i=" LOCTVS LL 14 0 POSHY

• t-

~ 12 UJ

-l UJ 10 w

u

<(

LL 8 a:

'.)

CJ)

..J 6 0

0 a.. 4 2

0 0.0 0.2 0.4 0.6 0.8 1.0 1.2 TIME AFTER VENT CLEARING {SEC)

• SWEC EQUIVALENT OF MARK II PSAM FIGURE 6A.4-54 POOL SURFACE ELEVATION VS TIME COMPARISON OF LOCTVS & POSHY NIAGARA MOHAWK POWER CORPORATION NINE Ml LE POf NT-UNIT 2 FINAL SAFETY ANALYSIS REPORT SFPTFMRFR 1 f:l8fi

-u UJ 25 en u..

20 C3 0

....I POSHV

• w 15 LlJ

(.)

ct u.

c::

> 10 en

-l 0

0 a..

5 TIME AFTER VENT CLEARING (SEC)

FIGURE 6A.4-55 POOL SURFACE VELOCITY VS TIME "SWEC EQUIVALENT OF MARK II PSAM COMPARISON OF LOCTVS & POSHY NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANAL YSlS REPORT Al\Al=Nf1MFNT ?1 SFPTFMRFR 1 \=lR~

40 38 I POSHY *~.

7 36 "

34

/

~

/

""-~

~

~

r--.....__ /

A LU 32 ~

a: "---- ~

=>

Cl) en 30 w

~

r.r: ""--- LOCTVS Cl. 28 I Ul ca DJ 26 co er:

24

<t 22 0.2 0.4 0.6 0.8 1.0 1.2 TIME AFTER VENT CLEARING (SEC)

FIGURE 6A.4-56 xsWEI EQUIVALENT OF MARK II PSAM AIR BUBBLE PRESSURE VS TIME COMPARJSON OF LOCTVS & POSHY NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

50

~

(/J

c. 45 ~

r LU a:: POSHY "'- ~ /

y/v

~

i 40

(/)

en w \

a::

\ --- -

35

/V/

a.

w v

r

(.) -ii

~ 30

~

a.

en 0:

25

<(

'_}

. /~

a: LOCTVS -

w 20 co .

<( --~~

-~

r 15 u

z 0

en 10 CJ'J w

a: 5 a.

0.

J

(/J 0

0.0 0.2 0.4 0.6 0.8 1.0 1.2 TIME AFTER VENT CLEARING (SEC)

"SWEC EQUIVALENT OF MARK ll PSAM FIGURE 6A.4-57 SUPPRESSION CHAMBER AIRSPACE PRESSURE VS TJME COMPARISON OF LOCTVS & POSHY NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

- AMENCfMENT 21

!- -_., .,......, . ----1 l

'------------~--~**.~;'-----

!}:*:* f.*'X(

r-1 II

_ ,.. --;r;li**---" \.

\ .. ~ 111,-r;u"""'"n~ullt1'l<lt.J**I 1111<1'"'"'au:: * *;';101

<:u* u - r ..... tTl"r.I J

a

~

--<t*t**H

./

I

' ';;j-- '"""

\ !*~-.

\\

ii tr(" IJ

\ *:

j~

c

1.50 -

l 25 (J

1.00 "az i=

<(

a: 0.75 w

/Al ~\

\

-l w

u ,~

u c(

l 0.50 ~

'i / ' \

,~I~

\~,,

'\

v

'\.:

~

~

0.25 ' ~'\

-,)~ ~

~~.

0.00 .._

,./

- ~

0.00 0.02 0.04 0.05 0.08 0.10 0.l2 0.14 0.16 0.1H 0.20 0.22 0.24 PERIOD IN SECS FIGURE 6A.5-2 AAS OF VERTICAL ACCELERATION PEDESTAL TOP {ELEV. 266 54 NODE 141)

SAFETY RELIEF VALVE DISCHARGE 0.010 OSCILLATOR DAMPING SYMMETRICAL LOADING

- - - * - - - - - 0.020 OSCILLATOR DAMPING O.OJO OSCILLA TOA DAMPING NIAGARA MOHAWK POWER CORPORATIO~~

- - - * - - - - 0.040 OSCILLATOR DAMPING NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

1 50

1. 25 1.00 -- - -

(

t:I z

0 j::

[: ~

q:

er 0.75 w

...J UJ u ~.,

u I fl

~

)'

0.50 ....__

~u ~~ fl f1 \~

I I

\\

f-- I

~ .... ,"""'-.J \ . I

\l 0 -~

~ "=--

J I ~

--~

--~ ~.

0 00 0 .00 0.02 0.04 0.06 0.08 0.10 0.12 0.14 0.16 0.16 0.20 0.22 0.24 PERIOD IN SECS FIGURE 6A.5-3 ARS OF VERTICAL ACCELERATION PRIMARY CONTAINMENT (ELEV. 315.25 NODE 136) SAFETY RELIEF VALVE 0.010 OSCILLATOR DAMPING DISCHARGE SYMMETRICAL LOADING

---~---- 0.020 OSCILLATOR DAMPING 0.030 OSCILLATOR DAMPING NIAGARA MOHAWK POWER CORPORATION

- - - - - - - - 0.040 OSCILLATOR DAMPING NINE MILE POINT-UNIT 2 FlNAL SAFETY ANALYSIS REPORT

I 1.50 1.25 1.00 Cl z

0 j:::

c: 0.75 1.U

...J w

u u

~

0 .50 0 .25 0 00

/~ ~ .. ~~~-

.- --~ ..

O_OQ 0.02 0.04 O.OG o.oa 0.10 0.12 0.14 0.16 0.18 0.20 0.22 0.24 PERlOO IN SECS FIGURE 6A.5-4 ARS OF RADIAL .A.CCELERATION PEDESTAL TOP (ELEV. 266.54 NOOE 141!

SAFETY F!EL!EF VALVE DISCHARGE 0.010 OSCILLATOR DAMPING SYMMETRICAL LOADING

- - - - - - - - 0.020 OSCILLATOR DAMPING 0.030 OSCILLATOR DAMPING NIAGARA MOHAWK POWER CORPORATION

- - - - - - - - 0 040 OSCILLATOR DAMPING NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

1.50 l . 25 ,___.

1.00

<.:l z

0 j::

ct.

er. 0.75 IJJ

....J IJJ CJ ~

u 0.50 >----*

.1 0 25

~

~,

./

0 00 -

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SAFETY RELIEF VALVE DISCHARGE 0.030 OSCILLATOR DAMPING 0.040 OSCILLATOR DAMPING SINGLE VALVE LOADING NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FJNAL SAFETY ANALYSIS REPORT AMENDMENT 16 DECEMBER 1984

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---

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1.50 1.25 1.00 z

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CONTAINMENT (EL. 315.25) 0.020 OSCILLA TOA DAMPING 0.030 OSCILLATOR DAMPING CONDENSATION OSCILLATION LOAD ANALYSIS ADS LOADING 0.040 OSCILLATOR DAMPING NIAGARA MOHAWK POWER CORPORATION NINE fv11LE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 23 DECEMBER 1985

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---

* 0.030 OSCILLATOR DAMPING 800 SERIES CHUGGING LOADS 0.040 OSCILLATOR DAMPING NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMEND1VlENT 23 DECEMBER 1985

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---

0.030 OSCILLATOR DAMPING BOO SERIES CHUGGING LOADS 0.040 OSCILLATOR DAMPING NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 23 DECEMBER 1985

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- - - - - 0.030 OSCILLATOR DAMPING PEDESTAL TOP (ELEV. 266 54) 0.040 OSCILLATOR DAMPING 800 SERIES CHUGGING LOADS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 23 DECEMBER 1985

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---

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NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT P.Jv1ENDMENT 23 DECEMBER 1985

• l TYPE OF SUPPOF> T LOCATION (NODE)

RPV NOZZLE 5, 480,58()

ffJW,Fi'( CONTAINM.:NT 28Q, 265, 290, 295, PENETRATION 300, 305, 310 SNUBBCRS 37, 39, 40, 74, 94,

95. 133, 140, 158, 160, 181, 183, 420, 112\, 45\l, ~51, 521, 535, 547, 550 R.'GllJ riES TR.<\iN13 215, 2.20, 250, 265, 534 l. -

10, 69. t05, 157, 185, 235. 470, 530 FIGURE 6A.9-1 FEEDWATER PIPING (12177-NP(C)-AX-17A}

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT USJ>.R REVISION' 7 OCTOBER 199~

135 13~0-~c;-~~~,...,_" 136

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{400 1405 1~10 230 1125 HO 11 l TYPE OF SUPPORT LOCATION (NOOE)

RPV NOZZLE 5 cD 110 105 SNUBBEflS 500, 42, 5-l, 60, 110, 1110, *125, 65 IOU 135 10 05 75 95 80 SPRING HANGERS 53, 95, 111. 126.137 90 FIGURE 6A 9 -2 REACTOR CORE ISOLJ>..T:ON COOLING PIPlNG (121/7-f'.JP(C)-AX-76A)

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 23 DECEMBER 1985

y

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HPV NOZZLE 2 PAIMflAY CONTAINMENT 545, 550, 560, 565, 570, PENE-1 RATION 575, 560, 600, 585, 5~5 46,60,61.65,952,995, SNUBBERS 1071, l 73, 174, 179, j 90, FIGURE 6A.9-3 226.255.305,365,367, 380,900,4 66,490, 70 I 0 710,711,2003,2020,20~8.

REACTOR WATER CLEAN UP PIPING 2054 ,3030 ,3090,4050 .4086 (12177-NP(C)-AX-748) 31,36,64 76.95,503, 520,BD,8 UM.185,96,91 I, 805,200,227,330,701, NIAGARA MOHAWK POWER CORPORATlOll RIG 0 CONSTRAINTS BS, 1072,7350,445,456, NJNE MILE POINT-UNIT 2 4 4 50,260.2068.2075.2084. UPDATED SAFETY ANALYSIS REPORT 085 4076 4097 [j , *)

USAR REVISION 1 DCT011 F.R 1 q 'l *1

TH~S FIGURE !HAS SEEN DElETEo*r I FIGURE SA.10-1 CONTORT COMPUTER MODEL SCHEMATIC NIAGARA MOHAWK POWER CORPORATION NINE IVHLE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

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A - Ir.::. i:.10 t.ion of ~r~ns-f ~r to el-terno~e Ul\JIT 2 POOL TEMPE?.AIURE shu"ta:o1m cochr.g. TRANSIENT: CASE 2.

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NIAGARA MOHIA'IK POWER CORPOAATlOfl NINE MILE POINT - UNIT 2 UPDATED SAFETV ANALYSIS REPORT USAFi REVISION 0 APl1JL 1989

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0 100~-~-~-~--J----__~' -~r----~

E G

F 0 200 400 600 800 1000 1200 REACTOR VESSEL PRESSURE {PSIA) 42.0 94.0 158.7 212.6 267.8 QUENCHER MASS FLUX {Lf!M/(SEC-FT !1 1

A - 1n11Jatloo of tron~fsr l<> altdrnntu FIGURE 6A.10-11 nl\utd-0wn ::oollng.

UNIT 2 POOL TEMPERATURE 8 - t,* ..,,). , \"'~M S_,_,.. :l~~. i£_i,,"'Sh~-t,.::?:'. :Jrc'fJ1~

Hi;. 57(,;1,1 G ::.:*L*d*...-:.. :..n.:.s;:

M/-.SS FLUX PLOT; CASE lb.

rHAGARA t.101-J_..,\IK POWER CORPORATION

! NINE MILE POINT - UNIT 2 L

UPDATED SAFETY ANALYSIS REPORT US.t:..R REVISION I OCTOBER 1939

250 I

p 0

,,.J 0

0 L 214 F T 0

~r------__

E 200 F NUAEG lOCAl TEMPJ,.TUR* " " "

M p 200 E

A A

~--S:..__ ";..

1---___

T u

R e

---

--.._----+---

n I 150 N POOL O~EMPERATURE D

E G

F 100 ---

a 200 400 600 800 1000 1200 fiEACTOt1 VESSEL PAESSUFIE (PSJA) 42.0 94.0 158.7 212.6 267.8 QUENCHER MASS FLUX [L13M/CS!;C*FT'll A* 1111t111t100 of iran~lor lo olrnrnnto FIGURE 611..10-12 ahuldown coollno.

UNIT 2 FOOL TEMPERATURE

- MASS FLUX PLOT: CASE 2.

NIAGARA MOHfWI< POWER COFiPORf.TION NINE MILE POINT - UNIT 2 1.FDATEO SAFF-T'r ANALYSIS REPORT US ..O.R RE VISION t OCTOBER 1989

p a

a 0 L 214 F T 0 E 200 F NURE:G 078 LOCAL TEMPE ATURE LIMIT M 200 p

E R

~-,.._,.-,A A

T '-)

u R

E I 150 POOL BULK EMFERATURE N

D E

G F

• 100 0 200 400 600 800 1000 1200 REACTOR VESSEL PRESSURE (PSIA}

42.0 94.0 158.7 212.6 267.8 QUENCHER MASS FL.,UX !LBM/(SEC-FT )l 1

A - lnltlotlon of tranafar to alternate FIGURE: 6A.10-12A ahutdown cooling.

UNIT 2 POOL TEMPERATURE MASS FLUX: EPU CASE 2.

NINE MILE POINT-UNIT 2 hJCTE: THIS IS AN APPROXiMATE REPRESENTATION OF EPU. UPDATED SAFETY ANALYSIS REPORT L USAR REVISION 20 OCTOBER 2612

250 . - - - -

r-0 0

L 0 2H F T 0 qa E 200 F NUREG 0763 LOCAL TEMPE ATUBE LIMIT M 200 i---,~~~~~-+-~~~__;::=--~;-.~~~~~-;-~~~~~---';-.~~~~~-L-.~~~~~--1 p

E R

""'~

A T

u R

E I

150 r--~~~~~-'r--~~~~~-t--=---...0=-~~---;~~~~~~-+-~~~~~~1*~~~~~~4 POOL BULK TEMPERATURE N

D E

G F

0 200 400 600 500 1 000 1200 REACTOR VESSEL P BES SU RE ( PSIA l 42.0 94.0 158.7 212.6 267.8 QUENCHER IAASS FLUX ILBMl{SEG*FT'll FIGURE 6A.10-i3 i A

• lnltl;:illor. or tron,tor lo nl!ornot" I chuldown cooling.

UNIT 2 POOL TEMPERATURE B - ".!.Xl!.'t~.\l euLtt ;::!X.'L Tt.1. 1;::E:.1:..r*..:i1~ Gu~ll*V

~nv sn:~~"' ~-1$!:H..1MJE Fn.:.s~ .

- MASS FLUX PLOT: CASE 3.

NIAGARA MOH WIK POWER CORPORATlOtJ NINE MILE POlNT - UNIT 2 UPDATED SAFETY ANALYSJS RE POAT USAR RE VISION I OCTOBER 1989

I O"

I'I

,~t--- PEDESTAL WALL

.w a-- CONTAINMENT WALL 180° ELEVATIONS WATER SURFACE -26.6' QUENCHER 't 3.5' BOTTOM OF POOL o.a*

TEMPERATURE SENSOR TT15 - 3.5' TT18 - 3.5' TT23 -11.4' TT48 -25.7' FIGURE 6A.10-14 LA SALLE SUPPRESSION POOL SCHEMATIC NIAGARA MOHAVVI<. POWER CORPORATION NINE NliLE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

90° 0° -...J.J-------1+---~~--tt-------lt- i 60° TANGENTIAL QUENCHER (1 OF 18)

RADIAL QUENCHER 210° (TYPICAL OF 17)

ELEVATIONS WATER SURFACE - 24.00' QUENCHER <<t, 3.Sa' BOTTOM OF POOL o.o*

FIGURE SA.10-15 NMP2 SUPPRESSI01\J POOL SGHEMATIC NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL ~AFE fY ANALYSIS REPOR i AMENDMENT 22 NOVEMBER 1985

90 0

0 LL- 80

(!)

UJ c

LU a: 0 TEMPEST I- TEST SENSOR TT15

~

c:: (FAR FIELD) w Cl.

~

w I- 70 soli=======L======-=*~6===---

=--=--=l~.-=--==-=-=ll::::=====~-Jb=-=-~-

-~-~J~,-=====-~J~--

-=- ~~==:jJ 0 10 20 30 40 50 60 70 80 TIME (MINUTES)

FIGURE 6A.10-16 TEMPEST BENCHMARK COMPARISON WITH LA SALLE POOL TEMPERATURE TEST DATA NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 22 NOVEMBER 1985

110 ~

100 0 TEMPEST 0 TEST SENSOR TT18 0 {NEAR FIELD) 0 0 IJ.. 0

(!; 0

(

UJ 90 0 Cl w

er

J I-

<t a:

w BO a..

~

w I-70 60i!========li::==::::=::=;;;:;;;;;f=:::::=~*z-~*~~*~*'::=;;;;:::;;~;z;;:;;i!=z::::=~:.:;;;;-*=~~

=:-;;:;:-;.~-:::;::;:;:.:;t;:::::=::::.::.."'"'-.::.+/-=::;:::::::=:;:;;::=;:::::j 0 10 20 30 40 50 60 70 80 TIME (MINUTES)

FIGURE 6A.10-17 TEMPEST BENCH~.t1ARK COMPARISON WITH LA SALLE POOL TEMPERATURE TEST DATA NIAGARA MOHAWK POWER CORPORATION NINE MJLE POINT-UNIT 2 FINAL SAFETY ANAL YSJS REPORT AMENDMENT 22 NOVEMBER 1985

110 -

0 TEMPEST

• oo TEST SENSOR TT23 (NEAR FIELD) a LL.

Cl UJ c 90 w

a:

I-

<(

a:

LU D. 80 *

!E w

I-

.~*

70 '

60 --* - . --~'-==- ~--*~,_,.,, *-* -:-::-.- . -1~ ' - -1~~---~ -,--,.-J_ ~ - - '

0 10 20 30 40 50 60 70 80 TIME (MINUTES)

FIGURE 6A.10-18 TEMPEST BENCHMARK COMPARISON WITH LA SALLE POOL TEMPERATURE TEST DATA NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 22 NOVEMBER 1985

110 0 TEMPEST TEST SENSOR TT48 (SURFACE)

LL.

CJ w

0 w

c:

J I-

~

tr w

0.

2 w

I-10~-=-===-~*-~--=-=

-=-==-=-4=o.==.-==...;;i:..;-~-~

.==..~*=-.::*=*- ~L~-::=-;:=.=..;

--:.=::-=-~-:::.:--:::.;-=-

- -==l~==:--=:::::;;;ll=:=======-'

0 10 20 30 40 50 60 70 80 TIME (MINUTES)

FIGURE 6A.10-19 TEMPEST BENCHMARK COMPARISON WITH LA SALLE POOL TEMPERATURE TEST DATA Nl.A.G.A.AA MOHAWI< POWER CORPORATION f\JINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 22 NOVEMBER 1985

10 - RADIAL QUENCHER a

u::-

~

u:u.

2i 6 a.:

~

w I-

~

..J m 4 0

I-

..J

~

u a..J 2

0 2 4 s a 10 12 14 16 TIME AFTER SRV ACTUATION (MIN)

FIGURE 6A.10-20 SUPPRESSION POOL LOCAL TO BULK TEMPERATURE DIFFERENCE NIAGARA MOHAWK POWER CORPORATION NINE f\~ILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 22 NOVEMBER 1985

FLOW VOLUME j NOTE:

DASHED LINES INDICATE NODE BOUNDARIES OR MASS ANO ENERGY CONTROL VOLUMES SOLID LINES INDICATE INTERNAL JUNCTION OR MOMENTUM CONTROL VOLUMES FIGURE 68-1 STAGGERED MESH CONTROL VOLUME APPROXIMATION FOR THREED NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

-=====-====-==><k""""""=---==-===-========-........=============-====-=====-=4============~====:=l-=-=====~-=-==~

START READ INPUT PARAMETERS SET INITIAL CONDITIONS FOR PROBLEM COMPUTE TIME STEP ANO ADVANCE TIME COMPUTE JUNCTION MASS FLOW RATES COMPUTE NODAL PROPERTIES PRINT AS REQUESTED NO STOP FIGURE 68-2 COMPUTATIOl\JAL BLOCK DIAGRAM FOR THREED NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAfE rv ANALYSIS REPORT

I oo I

LOOP-A DISCHARGE LOOP-B AZIMUTH - 315° DISCHARGE AZIMUTH - 54 ° LOOP-a SUCTION AZIMUTH - 275u ~,;7'---_

270°- -90° LOOP-A LOOP-C SUCTION SUCTION AZIMUTH - 95° AZIMUTH - 261° 1ao 0 l\fORMAL POOL LEVEL EL - 200' DISCHARGE EL - 198' SUCTION (TOP) EL- 189'*8" POOL BOTTOM EL - 176' J. FIGURE GC-1 UNIT 2 - AHA SUCTION R.

DISCHARGE SCREMATIC NIAGARA MOHAWK POWER CORPORATION

~

1 NINE MILE POINT-UNIT 2 1

UPDATED SAFETY ANALYSIS REPORT

=======-=============........-=-==~U~SA~R~R~EV~l~Sl~O~N~8;=-====""""""'==~N~O~V~E~M~B~ER~1~99~5