ML20112D049

Containment P/T Analysis for Design Basis LOCA - Suppl a

ML20112D049
Person / Time
Site:	San Onofre
Issue date:	02/17/1995
From:	Barbour P, Castello T, Evinay A SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20112D021	List: ML20112D020 ML20112D023 ML20112D035 ML20112D038 ML20112D041 ML20112D049 ML20112D052
References
N-4080-026, N-4080-026-R00, N-4080-26, N-4080-26-R, NUDOCS 9606040037
Download: ML20112D049 (320)

Text

i I

N-4080-026 Suppl A Rev 0: LOCA Containment P/T l

9606040037 960529 PDR ADOCK 05000361 i P PDR

_ m

sam - com.

• se - c r CALC NO. N-4080026 CCN NOJ PAGE TOTAL NO. OF PAGES N1 1 mTEnas CALCounoN PREUM. CCN NO. S(o CHANGE NoDCE SCCfg/

BASE CALC. m 0 mf C^ "

CALCuLADoN CHANGE NOTICE (cCog 2 & 3 l CC"7 / C CALCULADON SUB ECT Contanment P/T Analysis for Design Basis LOCA - SUPPLEMENT A CALCULADON CROOWEX ENGINEEMC SYSTEM NUMBERMtMAN STADON SYSTEM DEWGNATOR I d

g ll M""."e^n*e o Em i.Cm*d w

• '"*"*d 1201 / BBB CONTROLLED PROGRAM OR PROGRAWOATABASE NAMEst VERMON/ RELEASE NO.e)

D" d"**E i ACCORDANCE WTH O ALsO, usTED sEtow i

1. sREF oE.CRenON OP iCC=CCN: O m.nAu O OATA.A.E NE100 (COPATTA) G1-15  ;

)

Revise sheets 8 through 65 of tne base calculation to refor to the Suppierrelt A Results & Conclusions.

]

Add Supplement A to the base calculation.

]

Supplement A provides a new Analyssa of Record (AOR) for the Containment Bulldog pressure and l

temperature reaponse to the Design Basis Loss of Coolant Accident (LOCA) event. Consistent with i the licensing basis for SONGS 2 & 3, the new AOR is performed w>le the containment initial l pressure at 14.7 psia. A second analysis is also included which assumes tile containment initial l

pressure is at the Technical Specification maximum value of 1.6 jmig (16.2 psia) to demonstrate i that the peak post LOCA pressure remams below the 60 psig contanmett design value. The j results of this new analysis are applicable to containment functional dessgn and in-containment j equipment , qualification,  ;

This new analysis employs slightly lower containment spray flow rates than were used in the base calculation to bound the lowest spray flow rates expected with 7.5% degraded containment spray pump performance in addition, the emergency air cooling unit start time has been delayed to coincide with the ,

start of full containment spray flow at 60 seconds to provide margin to accomodate future changes in ECU l startup timing.

The results of the base calculation are obsoleted by this new AOR. However the base calculation, itself remains applicable as a detailed source document for the input parameters used in the containment P/T 3

analysis.

INmADNG N E88NT (DCP/MMP, FCN, OTHEFg P/A Rev.

2. OTHER AFFECTED N ad8NTS (CHECK AS APPUCASLE FOR CCN ONLY);

See Calc Cross Index 0 vEs O NO OTHER AFFECTED DOCUMENTB 00ST AND ARE CENmED ON ATTACHED FORM 30-503.

3.APPROVAU DSCPUNE/ Esc NUCLEAR SAFETY ANALYSIS l 3

ALLEN EVINAY

- - - pax k 51385 Aw _

i PAUL BARBOUR nu m a b

sax -

51379 h

> DM .4 ,

1[d9f i D.w .

e tM i

% d/es-4.- AsoGNEDSUPPLEMENT CCN eATE ALMDE9d0NA l u .cE -

ECE 24-1221 PEV. 9/01

NES&L DEPARTMENT CALCULATION SHEET ',,c7

, 0 % ,0. u _, ,,,,30,3e Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CoNVERSloN: g CCN No. CCN ~ l Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 8 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

A.Evino v oI/31/9.7 P. Barb.u i- c1/31/75~ 5 rwis .rcerton is AGPLACEO dY 36cTros) 2 IN .stJPPt.91Gs>T A 2 RESULTS/ CONCLUSIONS AND RECOMMENDATIONS RESULTS/ CONCLUSIONS The se of this calculation has been to evaluate the short and long term effect f the con ' nt pressure-temperature transient resulting from a de. sign basis LOCA ith a loss of offsite wer.

Figure 2-1 pre ts the containment gauge pressure versus time for the D A LOCA. The plot in Figure 2-1

• generated using the data presented in Table 8.3-1 Figure 2-2 presents the ump and vapor temperatures versus time r the DBA LOCA. The plots in Figure 2-2 am ge rated using the data presented in T e 8.3-1.

Figure 2-3 presents the conde ' g heat tansfer coefficien sed by the COPA'ITA Code versus time for the DBA LOCA. The plot in Figure 2- is generated using the data presented in Table 8.3-1.

Figums 2-4A and 2-4B present the ene conte of a number of different components of the LOCA model versus time for the DBA A. The plots in Figures 2-4A and 2-4B are generated using the data presented in Table . -2. For further discussion on heat sink energies, refer to Section 8.3.2.

Figure 2-5 presents surface tempera s versus time or five heat sinks for the DBA LOCA.

The plots in Figure 2-5 are gene using the data p nted in Table 8.3-3. The heat sink data plotted is for the followin eat sinks:

HS 2 Containment Bu' ding Cylinder above grade HS 8 Lined refue ' canal walls HS 9 Steam Ge tor compartment walls, unlined refueling walls & other internal s HS 15 Misce eous carbon steel: thickness < 0.5" HS 16 El ' cal equipment Figures 2- and 2-2 show that the containment peak pressure (56.9 psig) is belo the design pressu of 60 psig and the peak vapor temperature (294 'F) is below the design t perature of 3

~

'F. Therefore, General Design Criteria 16 and 50 (See Section 1.2) are met. The co ent pressum at 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (86400 seconds) is less than 12.5 psig (the pressure m e COPA'ITA output at 80000 seconds). This is considerably less than half of the peak pressure. Themfore, General Design Criterion 38 (See Section 1.2) is also met.

l

l NES&L DEPARTMENT i CALCULATION SHEET '""'

PREUM. CCN NO. c -t PAGE_.3OF_aro l Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 l ccN CONVERSION: J

' CCN No. CCN - I Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 9 REV ORIGINATOR DATE IRE DATE REV

] ORIGINATOR DATE IRE DATE R O R. Nakano 01/18/94 J. Elliott 01/20/94 '

4. Edin y as/3:/,3r p. 64 oy. ol/31/sg 5 s.

l 7W TABL4 IS AtPO9C4.b d Y TAblC 2-l M SUN *L6M6^lT' O {

Table 2-1 presents the accident chronology for the DBA LOCA.

i i

Table 2-1 i ACCIDENT CHRONOLOGY FOR THE DBA LOCA (DESLS) t I

TIME EVENT 1 j (seconds)

Break occurs [

17 l Peak containment pressure d[g blowdown phase 22.0 End of wdown 22.0 Start of Emergene ore Cooling injection phase

! 22.0 of Core Reflood 35 \

[ Start of air cooler fans 60 AXIM CONTAINMENT TEMPERATURE (294 *F) j 60 Start of Containment Spray injection phase 211.1

[ End of Core Reflood 211.1

[ Start of Post Reflood

, 241

[ MAXIMUM CDNTAINMENT PRESSURE (56.9 psig) f 573.273

[ f Post Reflood l l

523.273

/ End of CE.,,o ided % .nd ene,gy reiease d.ta )

l Start of COPATTA Code mass energy release calculations 573.273 [

22)d End of Emergency Core Coo injection phase j

[2280 Start of Emergency Core Cooling roc ulation phase 2280 End of Contamment Spray injection

[ 2280 Start of Containment Spray recirculation p 7200 HPSI realigned to a 50:50 split between hot and cold leg tion

) [ 10' End of COPATTA Code Calculations \

/

9

_ ,_c7 . - . . ._r

= * 'P 2 { @

i P

F s

5 S!o 8

1 4 ,5' Eo 2 .

E.

o Q

~

O FIGURE 2-1 g 3 E m x -

3 r

'm >r -

LOCA WITH LOP - CONTAINMENT PRESS E N o a

e o

t o i

a o Ozm 70_..., . . " . , '", . " , . - , "", "", .

" ": m w 5q ~& 5=

=

a m C$

r-

Max ss = 56.9 psig at 241 sec  : n T y c p{

0-1-g m w x oi a

s 60 h i & m u

,s g

3 m -

. 2 w

3 P

$ =5  ? o 2H K n 2- e.

1 50 - -

s  ? 8 in m

@  :  : 6 ' y I5 m

m  :  : e e s. n y 40 : s  : g g g g g E m g

a - -

x m

= g z 9

: 3 M 30 :  : n

$ . , f W - -

E 2 g

'h o a

H 20 h 5

m 4

g hp pe z  : .  : E Ez O 10 - -

s g he 0 -

- E nn 9

2

5 o 99 9 O 5 g 5 -58 2 D 1e- 1 e+00 1 e+01 1e+02 1e+03 1e+04 1e+05 1e 06 1e+07 n m n s.

n 4 3 ze m I O m TIME FOLLOWING BREAK (seconds) t  !

in

{

,* g 1

z lt N P e A o k '

(P

} o<m=

o =q F 7

- g- 2.

a

-> ?

2 S

b h

s.

Z x

h g

SSo

- r

$O FIGURE 2-2 E R E - E' LOCA WITH LOP - TEMPERATURE VAPOR SUw g 0 o !KC>z Q

M TEMP TEW d D $ o O

a C,' $

~

s m a m Fr 350 ~m ..."". . -s . '-n - "", . .. .", . "m "" N @' *  ? E>0 '

Max Vap Temp = 294 F at 60 se d

n  ?

u a-x

" HmD "O# $'

- Max Sump mp = 249 F at 28 s -

b 7 9

@m ,

M a

m W E 3 m

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o yy zn l

.......e . . . . . . . . . . . . . . . . . . . . . . . . ........e . . . . . . . . . . .... . . . . . . . .

t M oo g 1 n< '

i 1 01 1 e+00 1 e+01 1 e+02 1 e+03 1 e+04 1 e+05 1 e 6 1 e+07 09 z

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TIME FOLLOWING BREAK (seconds) "

S z loh O

m m p

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_ _ _ _ _ _ - _ . . _ _ __- .. - _ . - - - - - - - - - . - - - - - - - - - - _ --~_ - ----_ . - - -

O 3  ?  ?

2 E $

M d E R

-:n

= -

s o e n

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8 o

o .

R b E - E- 2 o FIGURE 2-3 j

$ 9 l Ey LOCA WITH LOP - CONDENSING HT e ,

~

J r'" 2 4 k o 4 o Om z '

300 -

'G h > a C cn. e

\",.."",.-",~~,~",.~~.~"..."-- a b ia =

m 1

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k y >  ? ?dQ, 250 -

f 3

n w tu

=

a "O>

c m g N R  ? w 2H E  : '

@) l- m5, a' 200 - -

6 1

E =

i IN m

o o

$ 5 b '

h E o s

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t

- h ~

g M o

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g) A z m z A Q O O 100 - -

m $

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$5 5

s g cz 50 - -

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ni og s i

ze TIME FOLLOWING BREAK (seconds) s

@ '2 s 5 i ~ R z le P , 2 O

k- --*

m Q) e p +- < m z

3  !" '?

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s h

• F s

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n 0.,

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g E.

s Q

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FIGURE 2-4A 3

e < 3 K C) r

= r VAPOR LOCA WITH LOP - ENERGY SUMP ----- TO L o o a

R i

q

' r" zm -

m O

i C; h 2 o z

c v>

m 5 ei

% g m j (n ['" r -

1e+10 3

. . . " , . . . . " , . " " , '".i - . ' " , . - , . " , ' ": $ #

f E>c, 4

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=

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_ _ _ ,- _ ____.------- _ --- _ .-= . _ _ - _ _ _ . _ _ _ ,

w ,o) g (f) m -

l

/ ,_ ',,,

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- o 4  %- h x B = g z

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m b o

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e

% 'z.

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1 s S

8_

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)* g oo g2 z

2

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1e+04 ' ' " " ' ' ' ' ' " " ' ' ' " " " ' ' ' ' ' " " ' ' ' ' " " ' ' ' ' " " ' ' " " ' ' ' ' " "

M 58z D 1 01 1e+00 1e+01 1e+02 1e+03 1e+04 1e+05 1e 06 1e+07 Ry 4 ,

.h ze m I* ,

TIME FOLLOWING BREAK (seconds) R i

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FIGURE 2-4B e g g j p LOCA WITH LOP - ENERGY N 3 '

HEAT HEAT ----- CONT AIR s q O o a

i q

m O rZ ,

Om D $ Z StrKS XCFNGR SPRAY CLR b 4 o C U) g m - > e ,

w iB = 3 m F r-  ;

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"i

/

, i "-

D O I C j- ym hO  !

} m 5-E

3 M in E

o u -3l O

1e+10 r 1 S P o

= ,

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m 2q. '

! ,jg,::===--=! $  :. - g. g M z 1e+O9 r E

'4fr9 x >

1 &

s { E F Z -i r -

o e. m

~J 1e+O8 r , ;5;/, - ,

3 e o  ; Qm

$ i a '@ Es !; O P H

~

1e+07 E

r

' 'c C/'c /

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9 Z

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/ I 1 9, @ $

m

8  : A 9 Z ff W 8 to 1e+O5 r 1 f' l i -

~

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a' o a

1e+O4 r 1 5 E$

!  ! D N g 1e+03 r 1

)

% o y

nn 99 2

.o

{E 1e+02 M .5y g 1 01 1 e+00 1 e+01 1 e+02 1 e+03 1 e+04 1 e+05 1 06 1 e+07 1

85 z

i

> m 8*

TIME FOLLOWING BREAK (seconds) m ii CD  % a' m

z l%

O O

n M u y

) < m :n

= 'E R 2 E. 3-  :

9 8 a r

4 %

> x -

R z, E 9 0 S n o a 3 2, E a > 8 $

E. Q FIGURE 2-5

• 3 EO i LOCA WITH LOP - HEAT SINK SURFACE T P S E

s- I m

> i m r HS 2 HS 8 ----- HS 9 - -"

HS 15 HS 16 D, o 1 M gZ C D5 x  !

2 a !C$I m r gyG, 300 .

- . . . . - , . . . ~ , ....--i . - . . ..~~> . . . . . , . . . . . ~ .

& 9 $ y r u a- x Am o M ~>

O2 .

..- '/ /

/

.N. g p 8'a g ry,

?

a.

w 2 -i R. T. E s:. [7 h

- 250 -

/s s. 7 e i 4 9c y E ME Z -i u_

~

i if .-

N. t 9 o e. m W /fc 's' h x "

>o % Em H '

E i .

.' hq N 8 L"

g M o

O P

] / /

• z

' r

• 9 m R

& /

4 200 -

t z

T il }e I N

m 2

o llJ / f m a /

/

I t i O

1 / I  % b w / l'. g u m

p / i f s e 35 150 -

/

e' .

j/

\

\

E EE rz

' -/ \ b y 'n e

(..=::::' k b on 99 9 k g

' ' ' " " ' ' ' " ' " " ' ' ' ' " " ' ' ' ' " " " ' ' ' " " ' ' " " " " ' ' " " ' ' " " " # 60 '7 100 $

• S$

1 O1 1 e+00 1 e+O 1 1 e+02 1e+03 1 e+04 1 e+05 1 e+ 1e+07 ze s

9 'E I TIME FOLLOWING BREAK (seconds) .b 2  % 2 z

O I*

o

= m e

) <mz t k

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ________I\__D_d _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _- _

l ICCN NOJ N-1 CALCULATION TITLE PAGE PnEtiu. CCN NO. p,og p op %

CCN CONVERSION:

Cele. No. N-4080-026 DCP/MMP/FIDCN/FCN No. & Rev. N/A CCN NO. CCN.

Subject Containment Pfr Analysis for Desien Basis LOCA - SUPPLEMENT A Sheet Al System Number / Primary Station System Designator 1201 / BBB SONGS Unit 2&3 0-Class 11 Tsch. Spec. Affecting? MNO O YES, Section No. N/A Equipment Tag No. N/A CONTROLLED PROGRAM / DATABASE NAME(S) VERSION / RELEASE NO.(S)

PROGRAM P M/ O DATABASE DATABASE IN ACCORDANCE WITH NES&L 4151 NE100 (COPATTA) G1-15 RECORDS OF ISSUES REV.

TOM PREPARED APPROVED I DISC. (Print name/ initial) (Signature) g g 77 ORIG. GS Other 0 ORIGINAL ISSUE $^ D a

_ A-77 ALLEN EVINAY ,

PAUL BARBO 1 P I ORIG. GS Y Other IRE DM DATE ORIG. GS Other IRE DM DATE ORIG. GS Other IRE DM DATE l

l Space for RPE Stamp, identify use of an alternate calc., and notes as applicable. I I

This calculation was prepared using Word Perfect 5.1 software as an electric typewriter. The WPS.1 software was not used for any computational portions of the calculation.

This calc. was prepared for the identified DCP/MMP. OCP completion and turnover acceptance to be venfied by receipt of a memorandum directing DCN Conversion. Upon receipt, this calc. represents the as-built condition. Memo date by SCE 261211 REV BSt

CALCULATION CROSS-lNDEX ICCN NW PREUM. CCN NO.

y,I PAGE M OF g g CCN CONVERSION Calculation No. N-4080-026 - SUPPLEMENT A Sheet No. A2 CCN NO. CCN- /

Cale.rev. INPUTS OUTPUTS Does the out-number and IdentNy output interface These interfacing calculations and/or documents calc / document CCN, DCN, Re W'elh h dp c a TCN/Rev., FIDCN. or calculation are used in these interfacing require initials and revised may require revision of the sub' ject tracking number.

relon?

calculation.

Calc / Document No. Rev.No. Calc / Document No. Rev.No. YES / NO I Calculatione: UFSAR, Section 3.11.3.1.1 10 Yes SAR23-341 N-4080426 0 UFSAR, Section 6.2.1 10 Yes SAR23-357 M4014409, Supplement A 0 DBD SO23-TR-EQ 1 Yes SAR23-341*

! M-0072436 0 DBD-SO23-TR-AA 0 Yes NEDOTRAK Log AJB-94404 DBD-S023-400 0 Yes NEDOTRAK Log VJB-95401 EQOPe M37600 Yes NEDOTRAK Log BCA3479 M37601 M37606 M37607 M37606 Unit 2 Operating Uscense & Technical M37609 SpecNications Amdt 101 M37610 M37612 Unit 3 Operating Ucense & Technical M37615 SpecNications i Amdt 90 M37618 M37619 M37620 M37621 M37624 M37629 M37631 M37635 M37636 M37640 M37641 M37644 M37646 M37703 M37704

! M37705 M37706 M36279 ]

f I scE 2e-424 REV. 0 7/s2 [

REFERENCE:

NES&L 24 7-15]

_ _ _ _ .- - .= -

I CALCULATION CROSS-INDEX ICCN NOJ PREUM. CCN NO. M~[ PAGE I2 OF N CCN CONVERSION.

Calculation No. N-4080-026 - SUPPLEMENT A Sheet No. A3 CCN NO. CCN- T Caic. rev. INPUTS i number and OUTPUTS Does the out- , ,

F**Pon b These interfacing calculations and/or documents ** *

• Results and' conclusion of the subject Ic/ ent provide input to the subject calculation, and N require ' *' '

, calculation are used in these interfacing tracking number.

revised may requite revision of the subject rWalon?

ald calculation.

Calc / Document No. Rw. No. Calc / Document No. Rw. No. YES / NO <

II EQDPs, cont'd i M38290 Yes NEDOTRAK Log BC-93479 M38377 M38378 M38379 M38381 M38382 i M38383 M38384 M38385 M38773 i M38785 M38790 M38798 M39079

. M40819 M85083 M85091 M85102 ,r ,r M85108

• Performed by NEDO EQ Group as automatic follow-on to IVA of UFSAR Change c::E 2e-424 REV. 0 7/92 [

REFERENCE:

NES&L 2&7-15]

L___________________ ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

NES&L DEPARTMENT ICCN NO/

CALCULATION SHEET PREUR CCN NO. N-1 PAGE O OF M CCN CONVERSION 3 Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026 Sun-A CCN NO. CCN - l Subject CONTAINMENTP/T ANALYSIS for )ESIGN 1LASIS LOCA Sheet No. A-4 i

REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARSOUR 02/03/95 i

i TABLE OF CONTENTS i

PAGE l

1.0 PURP0SE................................................... A-5 8

i 2.0 RESULTS/ CONCLUSIONS /RECOMMENDATI0NS....................... A-8 3.0 AS S UM P T I ON S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A - 2 3 i

i 4.0 DESIGN INPUTS..............................................A-24 I i

1 5.0 M ET H0DO LOGY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A - 2 7

6.0 REFERENCES

...................... ..........................A-28

,i 7.0 NOM EN C LATU R E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-3 0 J

) 8.0 C A LC U LAT I ON S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-31 9.0 COPATTA INPUT FILES........................................A-34 4

10.0 SELECTED OUTPUT DATA.......................................A-45 l APPENDIX A (C0PATTA Code I/O Fil e Information) . . . . . . . . . . . . . . . . . . . A-77 e

l i

1' 3Gk N NLW WR) 1

l NES&L DEPARTMENT CCN NOJ CALCULATION SHEET PaEuu CCN m. N.i ,AoE a O , a CCN CONVERSION Project or DCP/MMP SONGS UNrrS 2 and 3 Calc No. N-4080 826 Sim A CCN NO. CCN - l 1 Subject CONTAINMENTPfr ANALYSIS for )ESIGN MsrR1 A)CA

< Sheet No. A-5' I REV ORIGINATO*l DATE BRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 1.0 PURPOSE 1.1 TASK DESCRIPTION l The purpose of this Supplement A is to provide a new calculation of the i Containment P/T response to the Design Basis LOCA (DB LOCA) event consistent with

! the Licensing Basis of SONGS Units 2 and 3 (reference 6.2), where the pre-LOCA

) initial containment pressure is the nominal atmospheric value (14.7 psia) used in prior UFSAR containment functional design. The results of this Supplement A i will become the A0R for the Desiga Basis analysis (DBA) LOCA for the containment j functional design and Equipment Qualification. The Supplement A contains l additional results to support plant operations aspects of containment P/T j

analysis. Supplement A will also serve as the A0R for calculation of peak post-i LOCA containment pressure with the initial containment pressure at 1.5 psig, f

documenting the existence of peak pressure margin under maximum containment j initial pressure conditions (Technical Specification maximum value of 16.2 psia (1.5 psig per LCO 3.6.1.4)) .

! The prior analysis of reference 6.1 remains valid for the purposes of defining

] the input modelling for the Design Basis LOCA containment P/T analysis for all i parameters except those minor changes identified below.

?

! This Supplement A incorporates several minor changes in the containment heat l removal spray system (CSS) and emergency air cooler unit (ECU) performance j parameters:

i 1.1.1 The containment injection mode spray flow rate is reduced to 1600 gps,

bounding the lowest calculated minimum injection spray flow with 7.5%

j degraded containment spray pumps (reference 6.3).

5

! 1.1.2 The containment recirculation mode spray flow rate is reduced to 1950 gpm, l bounding the lowest calculated recirculation spray flow with 7.5% degraded j containment spray pumps (reference 6.3).

I 1.1.3 The emergency air cooling unit (ECU) start time is delayed to coincide with the start time of full containment spray flow at 60 seconds. This

, change adds 25 seconds to the currently calculated post-LOCA start time i for the ECUS with loss of power (reference 6.13) at a very small penalty i in containment P/T response while providing margin for future changes in j ECU start time.

1

! The Design Basis LOCA event continues to be the 9.8175 ft2 Double-Ended Suction l Leg Slot (DESLS) Break LOCA with maximum safety injection flow and loss of off-i, site power (LOOP).

1 i

i R " C FRW W l

_. ~. _ _ _ _ __ . _ . .

NES&L DEPARTMENT ICCN NO./

CALCULATION SHEET mu. CCN No. N-1 PAGE OF bb CCN CONVERSION r Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Sun-A CCN No. CCN -

Subject _CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A-6 j REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE l ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 i

Bechtel Standard Computer Code NE100, Release G1-15 (C0PATTA) (reference 6.4),

on the Nuclear Fuels Engineering IBM-RISC workstation system is used in this i calculation to evaluate the containment pressure and temperature transients for l the design basis LOCA analysis. I 1

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NES&L DEPARTMENT iCcN NO/

i CALCUL.ATION SHEET mEuM. CCN No. N.1 pAoE /b OF M CCN CONVERSION t Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Sun-A CCN NO. CW -

Subject CONTAINMENTPfr ANALYSIS for DESIGN llASIS LOCA Sheet No. A-7 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 l

1.2 CRITERIA, CODES and STANDARDS i

The criteria, Design Basis codes and standards LOCA (reference 6.1, ap)plicable to the Containment are also generally applicable in P/T this Analysis for analysis. The applicable regulatory design criteria include:

i

• General Design Criterion (GDC) 16, " Containment Design"

• General Design Criterion (GDC) 38, " Containment Heat Removal" General Design Criterion (GDC) 50, " Containment Design Basis".

4 The applicability of these criteria to peak containment pressure and temperature

are described in detail in Reference 6.1.

2 1

The containment design pressure and temperature are 60 psig and 300 F per the Technical Specifications (references 6.5 and 6.6, Section 5.2.2) respectively.

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u - =w.w

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PREUM. CCN No. N-1 pAos /7 or 86 l

Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080 026-Sun-4 CCN CONVERSION l CCN No. CCN -

l 1

Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A-8 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 1

2.0 RESULTS/ CONCLUSIONS AND REC 000tENDATIONS I 2.1 RESULTS/ CONCLUSIONS 2.1.1 Initial Containment Pressurt 9 0 PSIG l

Figures 2-1 through 2-6 show the analysis results out to 1E+7 seconds (116 days),

which is far enough out in time to demonstrate the return of containment ,

conditions to near ambient values. Section 10 contains tabulated data taken from l the A0R computer output which was used to prepare the graphs included in this section.

Figure 2-1 presents the containment gauge pressure versus time for the Design .

Basis LOCA. The plot in Figure 2.1 is generated using the data presented in l Section 10.1.

Figure 2-2 presents the containment sump and vapor region temperatures versus time for the Design Basis LOCA. The plots in Figure 2.2 are generated using the data presented in Section 10.1. ,

j Figure 2-3 presents the condensing heat transfer coefficient at the surface of the structural heat sinks versus time used by the COPATTA Code during the Design Basis LOCA. The plot in Figure 2.3 is generated using the data presented in Section 10.1.

Figure 2-4A presents the energy content of containment steam and air in the vapor region, the combined steam and air energy, the water energy content in the sump region, and combined total for the vapor and sump regions. The plots in Figure 2-4A are generated using the data presented in Section 10.2.

l Figure 2-4B presents the integrated energy content of the containment building '

structural heat sinks, integrated energy transferred out of the containment through the ECUS and spray heat exchangers, and the integrated energy transferred from the vapor region to the containment sump water by the CSS. The plots in Figure 2-4B are generated using the data presented in Section 10.2.

Figure 2-5 presents the inside surface temperature of heat sink 1 (reactor building dome, painted steel liner plate) to represent the maximum post-LOCA temperature of the containment structure. The plot in Figure 2.5 is generated using the data presented in Section 10.1.

Figure 2-6 presents the CCW heat load from one train of ECUS (2ECOs) and the Spray Hx, together with the combined total. The plots in Figure 2.6 are generated using the data presented in Section 10.2.

NES&L DEPARTMENT cCN NO./

CALCULATION SHEET PREUM. CCN NO. N-1 PAGE b OFM l CCN CONVERSON '

Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Suo-A CCN No. CCN -

Subject CONTAINMENTP/T ANALYSIS for")ESIGN HASIS LOCA Sheet No. A-9 REY ORIGINATOR DATE lRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 Table 2-1 presents the containment P/T Design Basis LOCA accident chronology for case of the initial containment pressure of 14.7 psia (0 psig).

The calculated pressure and also peak pressure less than of 55.1 the previously psig ispeak identified lesspressure than the 60 p(sig design 56.9psig) in the prior AOR (N-4080-026, reference 6.1). The decrease in the peak pressure is mainly attributed to the change in the initial containment pressure from 1.5 psig to 0 psig.

It should be noted that this new A0R peak pressure for the Design Basis LOCA is unchanged from the original AOR value of 55.1 psig documented in calculation N-4080-002 (reference 6.14) although the current analysis includes degraded performance parameters for both containment sprays and ECU heat removal systems and reduced gap conductance between the containment liner plate and concrete shell. The explanation for this apparent anomaly is that the current analysis ,

also includes updated structural heat sink surface areas which were originally utilized in early containment steam line break P/T analyses such as calculations N-4080-005 and N-4080-007 (references 6.15 and 6.16, respectively), as well as the current MSLB containment P/T A0R in N-4080-027 (reference 6.17). The updated heat sinks were not incorporated into LOCA analysis prior to calculation N-4080-026 since the LOCA peak containment pressure was non-limiting and the updated heat sinks only served to lower the calculated peak pressure. The use of different heat sink models for LOCA and MSLB analyses is discussed in the UFSAR (section 6.2.1.1.3.1.B), and the heat sink input used for the MSLB analyses as well as the new LOCA analyses in this calculation are provided in UFSAR Table 6.2-13.

The calculated peak vapor temperature of 295.4 F is less than the 300 F design temperature. The peak vapor temperature of 295.4 F is slightly greater than the previously identified peak temperature (294.5 F) in the prior A0R (N-4080-026, reference 6.1). The increase in the peak temperature is primarily attributed to the reduced air mass in the containment with 0 psig initial containment pressure compared with the prior analysis at 1.5 psig. The lower air inventory reduces the total containment heat capacity, resulting in slight increase in short-tenn peak temperature [see BN-TOP-3, Revision 4, Section 4.1.2 and Table 15 (reference 6.8)]. The delay in ECU startup time from 35 seconds to 60 seconds also adds to the slight increase in the peak vapor temperature as compared to the prior analysis.

i

NES&L DEPARTMENT icCN NO./

CALCULATION SHEET PREUM. CCN NO. N1 pAoE /f OF M CCN CONVERSION Project or DCP/MMP SONGS UNTTS 2 and 3 Calc No. N-4080426-Suo-A CCN NO. CCN - I Subject CONTAINMENTP/T ANALYSIS for DESIGN 1IASIS1RA Sheet No. A-10 Rev ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 2.1.2 Initial containment Pressure 9 1.5 PSIG Table 2-2 presents the containment P/T Design Basis LOCA accident chronology for I the case of the initial containment pressure of 16.2 psia (1.5 psig).

The calculated peak pressure of 57.0 psig is less than the 60 psig design pressure but slightly greater than the previously identified peak pressure (56.9 psig) in the prior A0R (N-4080-026, reference 6.1). The increase in the peak pressure is attributed to the changes in the delay in the ECU start time and reduced CSS injection rates (see Section 1.1).

The calculated peak vapor temperature of 294.9 F is less than the 300 F design temperature. The peak vapor temperature of 294.9 'F is slightly greater than the previously identified peak temperature (294.5 F) in the prior A0R (N-4080-026, reference 6.1). The increase in the peak temperature is primarily attributed to the delay in ECU startup time from 35 seconds to 60 seconds.

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n R j g l 4o 8 FIGURE 2-1 n, g LOCA WITH LOP - CONTAINMENT PRESSURE l j f]5 rh 70 i r iuni i i i i nni , ,iin e 3 8 O Max Press = 55.1 at 250 sec j l 3 h Cz 60 y g

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? Q U

NES&t. DEPARTMENT scCN NOJ CALCULATION SHEET eREuu. ccN NO. N-i gAoE 27 0g*

CCN CONVERSION Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Sun-A CCN NO. CCN - f Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA 9heet No. A-18

~

REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 'E DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 Table 2-1 CONTAINMENT P/T DESIGN BASIS LOCA EVENT CHRONOLOGY Initial Containment Pressure = 14.7 psia <

l TIME ( seconds ) EVENT 0.0 LOCA Occurs 17.0 Peak Containment pressure during Blowdown Phase (43.0 psig) 22.0 End of Blowdown 22.0 Start of Emergency Core Conling (ECC) Injection Phase 22.0 Start of Core Reflood 60.0 Start of Emergency Air Coolers 60.0 Containment Injection Sprays Start 60.0 Peak Containment Temperature 295.4 'F 211.1 Start of Post-Reflood 250.0 Peak Containment Pressure of 55.1 psig reached 573.3 End of Post-Reflood I

M N Nt;W 4/WG

NES&L DEPARTMENT CCN NOJ CALCULATION SHEET eReuu. CCN NO. N.i ,,oE 2,% 0 CCN CONVERSION l Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Sun-A CCN NO. CCN -

l Subject CONTAINMENTP/T ANALYSIS for DESIGNJASIS LOCA Sheet No. A-19 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 J

i l

i Table 2-1  !

(Continued) 1

CONTAINMENT P/T DESIGN BASIS LOCA Y .\

EVENT CHRONOLOGY Initial Containment Pressure = 14.7 psia j

3 TIME ( seconds ) EVENT l

573.3 End of ABB-CE-provided Mass and Energy Data 573.3 Start of COPATTA Mass and Energy Release Calculations 600.0 Containment Liner Plate at Maximum Temperature of 271.5 'F 2284 End of ECC Injection Phase 2284 Start of ECC Recirculation Phase 2284 End of CS Injection Phase 2284 Start of CS Recirculation Phase 7200 HPSI Realigned to 50:50 split between HL and CL Injection 1E+7 END of COPATTA Run KA 3 L'". NLVV WWO

NES&L DEPARTMENT ICCN NO./ l CALCULATION SHEET Paeuu. CCN NO. N-1 ,,oe n 0, a 6 '

CCN CONVERSION

{

Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080426-Sun-A CCN NO. CCN - l Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A-20 REV ORIGINATOR DATE IRE

)

DATE REV ORIGINATOR DATE IRE DATE l g AREN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 l

Table 2-2 l CONTAINMENT P/T DESIGN BASIS LOCA i EVENT CHRON0 LOGY l

Initial Containment Pressure = 16.2 psia I

} TIME ( seconds ) EVENT

{

1 2

0.0 LOCA Occurs i

, 17.0 Peak Containment pressure during

Blowdown Phase (44.6 psig) i' 22.0 End of Blowdown l 22.0 Start of Emergency Core Cooling l- (ECC) Injection Phase

}

I 22.0 Start of Core Reflood j 60.0 Start of Emergency Air Coolers 1

l i

60.0 Containment Injection Sprays Start i

! 60.0 Peak Containment Temperature j 294.9 'F I 211.1 Start of Post-Reflood i 252.0 Peak Containment Pressure of

] 57.0 psig reached

573.3 End of Post-Reflood '

u===.-

1 NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PREUM. CCN NO. N-1 PAGE b OF N '

CCN CONVERSION Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-426-Sun-A CCN NO. CCN -

{

Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A-21 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 l

Table 2-2 1

(Continued) i CONTAINMENT P/T DESIGN BASIS LOCA EVENT CHRONOLOGY Initial Containment Pressure = 16.2 psia 573.3 End of ABB-CE-provided Mass and Energy Data 573.3 Start of COPATTA Mass and Energy Release Calculations 600.0 Containment Liner Plate at Maximum Temperature of 270.7 'F 2284 End of ECC Injection Phase 2284 Start of ECC Recirculation Phase 2284 End of CS Injection Phase 2284 Start of CS Recirculation Phase 7200 HPSI Realigned to 50:50 split between HL and CL Injection 1E+7 END of COPATTA Run u = = =-

NES&L DEFARTMENT ICCN NOJ CALCULATION SHEET eaEuu. CCN NO. N-1 exoE m Og &

CCN CONVERSION Project Or DCP/MMP SONGS UNrlS 2 and 3 Calc No. N-4080-026-Sun-A CCN NO. CCN -

Subject CONTAINMENTPfr ANALYSIS for DESIGN BASIS LOCA Sheet No. A- 22 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR d2/03/95 2.2 RECOMMENDATIONS This Supplement A provides a new analysis of record for the containment pressure )

and temperature response to the Design Basis LOCA event for containment functional design as reported in Section 6.2 of the UFSAR. The new analysis is l also applicable to equipment qualification analysis. Supplement A also provides analysis for the determination of peak post-LOCA pressure margin starting with the maximum initial containment pressure conditions [ Technical Specification maximum value of 16.2 psia (1.5 psig per LC0 3.6.1.4)].

Section 6.2 of the UFSAR will be revised to replace the detailed results of the old AOR (initial containment pressure at zero psig) with the results of the new AOR for the same initial containment pressure of zero psig. Text will be added to clarify that analyses were also done with the initial containment pressure at 1.5 psig to confirm that the peak post-LOCA pressure remains below the containment design value of 60 psig when the initial pressure is at the Technical Specification maximum LC0 value of 1.5 psig.

The prior containment P/T response analysis contained in N-4080-026, Revision 0, remains applicable only for the purposes of defining the input modelling for the DB-LOCA containment P/T analysis for all parameters except those changes identified in this Supplement A to the calculation.

mem

NES&L DEPARTMENT ICCN NOJ

. CALCULATION SHEET eREau. CCN NO. N-1 g, e n 0, a Project or DCP/MMP SONGS UNrrS 2 and 3 Calc No. N-4080-426-Sup-A CCNNo.CONVERSION CCN CCN - l Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A- 23 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 i

3.0 ASSUMPTIONS The assumptions used in this calculation are identical to those used in the prior

Containment P/T Analysis for Design Basis LOCA (reference 6.1), except where noted. Reference 6.1 remains valid for the purposes of defining the input

, modelling for the DB-LOCA containment P/T analysis for all parameters except d

those changes identified in this Supplement A to the calculation. The assumptions in reference 6.1 are arranged in groups which parallel the COPATTA Code card series data input. The modifications to reference 6.1 assumptions are listed below.

3.1 CARD SERIES 1 3.1.a ITEM 5: CONTAINMENT INITIAL TEMPERATURE t

In both the A0R (reference 6.1) and this analysis, the containment initial temperature was assumed to be 120 F. This is the maximum average containment temperature per SONGS Unit 2 and 3 Technical Specifications LC0 3.6.1.5 (references 6.5and6.6).

3.2 CARD SERIES 5 7

3.2.a ITEM 3: CONTAINMENT EMERGENCY AIR COOLER START TIME i

In the AOR (reference 6.1), the containment air cooler start delay time was j identified as 35 seconds in the Design Input 4.3.a. In the present analysis the air cooler start time has been increased to 60 seconds to coincide with the i containment spray actuation time. This includes a 10 seconds delay time for the emergency diesel generator actuation after LOOP. The emergency air cooling units l have relatively little impact on short-term containment pressure and temperature, and by adding 25 seconds delay to ECU initiation, margin is added to accommodate potential changes in the timing of ECU startup. For example, based on the

methodology contained in calculation N-4080-003 (reference 6.13), the 60 second start time for the ECUS is equivalent to assuming a 47-second stroke time for the CCW block valves that supply cooling water to the air coolers, if all other

parameters affecting ECU start time were to remain unchanged.

k l

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NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PREUM. CCN NO. N-1 PAGE OF CCN CONVERSION Project or DCP/MMP SONGS UNFFS 2 and 3 Cale No. N-4080-026-Suo-A CCN NO. CCN -

Subject CONTAINMENTPrr ANALYSIS for DESIGN BASIS LOCA Sheet Ne .A-24 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 FAUL BARBOUR 02/03/95 4.0 DESIGN INPUT The design input used in this calculation are identical to those used in the prior Containment P/T Analysis for Design Basis LOCA (reference 6.1), except where noted. Reference 6.1 remains valid for the purposes of defining the input modelling for the DB-LOCA containment P/T analysis for all parameters except those changes identified in this Supplement A to the calculation. The design inputs in reference 6.1 are arranged in groups which parallel the COPATTA Code card series data input. The modifications to reference 6.1 assumptions are listed below.

4.1 CARD SERIES 0 The last four zero entries on this card are deleted. The G1-15 (RISC) version of COPATTA does not utilize these data entry locations.

4.2 CARD SERIES 1 4.2.a ITEM 2: PROBLEM RUN TIME The problem run time will be set to 1E+7 seconds (-116 days), the same run time used for the prior analysis in the base calculation (reference 6.1). This run time of IE+7 seconds is sufficiently long to show the containment pressure and temperature have returned to near ambient values.

l 4.2.b ITEM 3: INITIAL CONTAINMENT PRESSURE Consistent with the original design basis containment P/T response analysis for LOCA reported in the UFSAR supporting containment functional design (UFSAR Section 6.2), and SONGS Units 2 and 3 licensing basis (reference 6.2), the initial containment pressure will be set to 14.7 psia (0 psig). Sensitivity studies in Bechtel Topical report BN-TOP-3 (reference 6.8) show that the short-term peak vapor temperature increases with decreasing initial containment I pressure because lower initial pressure corresponds to a smaller initial air mass l in containment and a corresponding smaller containment total heat capacity.  !

The Supplement A also provides an analysis for the determination of peak post- l LOCA containment pressure where the initial containment pressure is set at the i Technical Specification maximum value of 16.2 psia (1.5 psig per LC0 3.6.1.4).

l I

l M M PUEO 4W j

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PREtiu. CCN NO. N-1 PAGE OF CCN CONVERSION Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4086 026-Sun-A CCN NO. M -

Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A-25 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95

4. 3- CARD SERIES 5 The last two entries on this card ( 0 and 105 ) are deleted. The G1-15 (RISC)

, version of COPATTA does not utilize these entry locations 4.3.a ITEM 3: CONTAINMENT EMERGENCY AIR COOLER START TIME In the present analysis, the air cooler start delay time has been increased from 35 seconds to 60 seconds to coincide with the containment spray actuation time.

The increase in air cooler start delay time will provide margin to accommodate potential changes in the timing of ECU startup such as an increase in the stroke

] time of the CCW block valves that isolate the cooling water from the air coolers. I 4.4 CARD SERIES 301 Minor changes -are made to card series 301 input to correct typographical errors at 19.8 and 432.076 seconds. This card series provides the mass flow rate and fluid enthalpy entering the containment from LOCA. The data is for the Design basis LOCA at 102% power with 9.8175 ft2 double-ended suction leg slot (DESLS) break. The changes made to correct input data are :

19.8, 7.146e+06, 4.8810er02 - 19.800, 6.066e+06, 4.8810e+02 432.076, 4.8233e+06, 1.1593e+02 - 432.076, 4.8233e+06, 1.1817e+02 j i

4.5 CARD SERIES 601 Minor changes are made to card series 601 input to correct typographical error  !

which inadvertently rammed down the reflood period spillage down to the initial {

post-reflood value rather than holding it constant ~as specified by ABB-CE in  !

their original data transmittal letter (reference 6.7).

The changes are: 1 From: )

$ LIST P00L=601, 0.00, 0.00, 0.00, 28.00, 0.00, 0.00, 28.00, 4.e+06, 5.362e+08, PRESENT N-4080-026 211.101, 8.73e+05, 7.7e+07, a m mesw 1

d NES&L DEPARTMENT CCN NOJ CALCULATION SHEET Pae';u. CCN No. N-1 pAGe 8 07 %

CCN CONVERSION Project Or DCP/MMP SONGS UNrrS 2 and 3 Calc No. N-4060-026-Sun-A CCN No. CCN -

, Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A-26 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE allen EVINAY 01/31/95 PAUL BARBOUR 02/03/95 1

To:-

$ LIST P00L=601,

, 0.00, 0.00, 0.00, 28.00, 0.00, 0.00, 28.00, 4.823e+06, 5.362e+08, ADD LINE 211.10, 4.823e+06, 5.362e+08, NEW N-4080-026 211.101, 8.73e+05, 7.7e+07,

, 4.6 CARD SERIES 801 l No changes are made to card series 801 input except:

l 4.6.a.2(a) CONTAINMENT SPRAY INJECTION MODE SPRAY FLOW RATE The minimum containment spray pump flow Rate with 7.5% pump degradation has been

changed to 1606 gpm (reference 6.3). In this Supplement A the value has been 5 rounded down to 1600 gpm providing a small margin over the minimum predicted spray flow. Using the same criteria as in the previous analysis (reference 6.1),

this value translates to a flow rate of 7.956E+5 lb/hr for 100 F water coming i from the RWST.

! The containment spray flow is switched to CSS recirculation flow at 2284 seconds.

4 This calculated value is slightly longer than the previous value of 2280 seconds

(reference 6.1, section 4.10.b.1 and 4.10.b.2) due to the slightly smaller

injection spray flow (1600 gpm v.s. 1612 gpm) used in this re-analysis. In addition to CSS recirculation flow, containment heat removal is also provided by the continued operation of the single train emergency air cooler units (2 ECUS).

4.6.a.2(b) CONTAINMENT SPRAY RECIRCULATION MODE SPRAY FLOW RATE The containment recirculation spray flow is rounded down to 1950 gpm from the minimum calculated value of 1991 gpm used in the prior analysis (reference 6.1),

providing a small conservatism for the long-term containment cooldown analysis.

3 Based on the same sump water temperature previously used in reference 6.1 the 4

corresponding mass flow rate is 9.30e+5 lbm/hr.

4.7 CARD SERIES 1101 The G1-15 (RISC) version of COPATTA does not have the option of multiple tables of ECU performance versus containment temperature for various values of cooling i water supply temperature. Therefore, following the card series identifier ( $ LIST P00L=1101 ), the input consists data pairs of containment saturatinn temperature and ECU heat removal rate.

4 4 M N Ntw d,W

_ ____ . _ _ _ . _ _ _ _ . _ ~._ _ _ -------- - --- - - - --- - -----

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PREUM. CCN No. N-1 PAGE b OF b CCN CONVERSION .

Project or DCP/MMP SONGS UNrrS 2 and 3 Calc No. N-4080-026-Sun-A CCN No. CCN - /

Subject CONTAINMENTPfr ANALYSIS for DESIGN BASIS LOCA Sheet No. A-27 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 1

5.0 METHODOLOGY

)

Thg Containment P/T LOCA evaluated in this calculation is the design basis 9.8175 ft DESLS at 102% power with loss of off-site power and with loss of one train j each of containment emergency air coolers and containment sprays.

The evaluation used the Bechtel COPATTA computer code (reference 6.5) to simulate the containment response to the LOCA.

The methodology employed in this calculation is identical to the present AOR (reference 6.1) for the Containment P/T Design Basis LOCA, with the exception

that two different pre-LOCA containment pressure conditions are analyzed:

1) Initial Containment Pressure of 14.7 psia (reference 6.2) for Containment P/T Functional Design.

2) Initial Containment Pressure of 16.2 psia, maximum Technical Specification value, for peak post-LOCA containment pressure margin determination.

Small reductions in containment spray flow have been made to provide some margin with respect to currently calculated minimum values. In addition, the start time of the emergency air cooling units (ECUS) has been arbitrarily delayed to coincide with the start of containment spray to provide future margin on the timing of ECU startup.

J umem

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PREUM. CCN No. N-1 PA?E J 7 OF b CCN CONVERSION Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Suo-A CCN NO. CCN -

Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A- 28 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE 1RE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 I

6.0 REFERENCES

6.1 SONGS Units 2&3 Calculation N-4080-026, Revision 0, " Containment P/T Analysis for Design Basis LOCA", January 13, 1994.

6.2 Memo from J.l. Rainsberry to A.J. Brough, " Peak Containment Pressure Calculations, San Onofre Nuclear Generating Station, Units 2 and 3",

May 12, 1994.

6.3 SONGS Units 2&3 Calculation M-0014-009, Revision 0, Supplement A,

" Containment Spray (CSS) In Service Minimum Requirements, July 28, 1994.

6.4 Bechtel Standard Computer Program, NE100, COPATTA, Version G1-15,

" Containment Temperature and Pressure Transient Analysir", User and Theory Manuals.

6.5 SONGS Unit 2 Operating License and Technical specifications, up to and including Amendment 101.

6.6 SONGS Unit 3 Operating License and Technical specifications, up to and including Amendment 90.

6.7 Letter, CE to BPC, "FSAR Mass / Energy Release Data for Containment Design",

S-CE-2604, dated March 1,1976 (CDM No. C760301G-45-2-4SVT).

6.8 Bechtel Topical Report BN-TOP-3, Revision 4, " Performance and Sizing of Dry; Pressure Containments", March 1983.

6.10 SONGS Units 2 and 3 Calculation M-DSC-243, Revision 0, " Thermal Lag Analysis of Electrical Equipment at SONGS 2 & 3 due to MSLB",

December 23, 1991.

6.11 SONGS Units 2 and 3 CCN 1 to Calculation M-DSC-243, Revision 0, " Thermal Lag Analysis of Electrical Equipment at SONGS 2 & 3 due to MSLB",

January 15, 1992.

6.12 SONGS Units 2 and 3 Calculation M-0072-036, Revision 0, " Containment Emergency Cooler Performance Verification", December 9,1993.

6.13 SONGS Units 2 and 3 Calculation N-4080-003, Revision 5, " Containment Spray (CSS) and Emergency Cooling Unit (ECU) Actuation Times",

December 23, 1993 6.14 SONGS Units 2 and 3 Calculation N-4080-002, Revision 1, " Containment Pressure-Temperature Transient Analysis", October 19, 1976 u--

NES&L DEPARTMENT ICCN NO/

CALCULATION SHEET PaEuu. CCN NO. N-1 ,,oE3 a 0, %

CCN CONVERSION ,

CCN NO. CM -

! Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080426 Suo-A Subject CONTAINMENTP/r ANALYSIS for DESIGN BASIS LOCA Sheet No. A-29 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE lRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95

, 6.15 SONGS Units 2 and 3 Calculation N-4080-005, Revision 0, "MSLB Analysis for 2

Environmental Qualification", March 15, 1978

, 6.16 SONGS Units 2 and 3 Calculation N-4080-007, Revision 2, " Containment

Pressure and Temperature From MSLB at Various Power Levels (NRC Question

022.7)", April 21,1983 1 6.17 S0iiGS Units 2 and 3 Calculation N-4080-027, Revision 0, " Containment P/T l Ana'iysis for Design Basis MSLB", January 13, 1994 a

1 1

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i l

i i

j i

J RA 2b425 NEW NUG e

--- q i

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PREUM. CCN NO. N-1 pAse # op % )

CCN CONVERSION i CCN NO. CM - )

Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Sun-A l

Subject CONTAINMENTPfr ANALYSIS forDESIGN BASIS LOCA Sheet No. A-30 l REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE l g AUEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 7.0 NOMENCLATURE Abbreviations are defined when first used within the body of the text.

4 4

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s M ? "I, Rh &

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PREUM. CCN No. N-1 PAGE OF b CCN CONVERSION l Project or DCP/MMP SONGS UNTFS 2 and 3 Calc No. N-4080-026-Suo-A CCN No. CCN - I Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A-31 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE l ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 8.0 CALCULATION l

8.1 COPATTA CODE INPUT DATA - Initial Containment Pressure cpi = 14.7 psia l COPATTA input data for the Containment P/T Design Basis LOCA Analysis for Equipment Qualification uses the Containment P/T Design Basis LOCA Analysis q (reference 6.1) input data with modifications to reflect changes in containment spray flow rate (reference 6.2), initial containment pressure and condensate revaporization fraction to generate containment temperature and pressure profiles for the Equipment Qualification Thermal Analysis. Only the changes to the reference 6.1 input data will be presented in the following subsections.

8.1.1 TITLE CARD

• DBLOCA+ LOOP (DESLS), cpi =0.0 psig, MAX SI, CSS =1600/1950 gpm, ECUS @60s 8.1.2 CARD SERIES 0 1

No changes made to Card Series 0 of reference 6.1 other than the deletion of the last four zero entries on the Bechtel input file as non-applicable to COPATTA version G1-15.

8.1.3 CARD SERIES 1 General Problem Information

& LIST P00L=1,1E7,14.7,2.305E6,120,0.6.20,582.945,1,1,0.08,14.7,0,0.50 $END ITEM 2: TNFL = IE7 seconds ( per 4.2.a )

ITEM 3: PAIR = 14.7 psia The initial containment pressure before the LOCA mass and energy release is set to 14.7 psia for Design Basis calculations, as discussed in the Design Input Item 4.2.b.

Card Series input ITEMS 4 through 10 remain unchanged from that of reference 6.1.

8.1.4 CARD SERIES 5 Air Cooler Information 1

$ LIST P00L=5,2,60,1E7,0,0 $END ITEM 3: This item reflect the change of Containment Air Cooler start time from 35 seconds to 60 seconds as discussed in Design Input Item 4.3.a. No other changes have been made to this card data.

=== -

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NES&L DEPARTMENT ICCN NOJ l CALCULATION SHEET PREuu. CCN NO. N-1 pAGE h OF b CCN CONVERSION Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Sun-A CCN NO. CCN - )

Subject .f0NTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A-32

, REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 8.1. 5 CARD SERIES 801 (Table 9)

This Card Series reflect the change of Containment Spray System (CSS) injection

flow rate from 1612 gpm to 1600 gpm. The input in this table is also modified to account for the change in time to CSS recirculation time from 2280 seconds to 2284 seconds due to the change of the CSS flow rate from 1612 gpm to 1600 gpm (see section 4.10 reference 6.1, sheet #56 for the calculation of t-recirc). The a

CSS recirculation flow rate has also been changed from 1991 gpm to 1950 gpm per 4

4.6.a.2(b) (9.30e+5 lbm/hr) and this is reflected in the input shown below.

$ LIST P00L=801, O, 0, 0, 0, 100, 100, 60, 0, 0, 0, 100, 100, i 60, 7.956e+05, 0, 0, 100, 100, 573.273, 7.956e+05, 0, 0, 100, 100, 573.273, 7.956e+05, 3.12e+06, 0.90, 100, 100, 800, 7.956e+05, 3.12e+06, 0.90, 100, 100, 900, 7.956e+05, 3.12e+06, 0.91, 100, 100, 1500, 7.956e+05, 3.12e+06, 0.92, 100, 100, 2284, 7.956e+05, 3.12e+06, 0.93, 100, 100, 2284, 9.303e+05, 6.30e+05, 0.67, 0, 0, -

3000, 9.303e+05, 6.30e+05, 0.68, 0, 0, i

4000, 9.303e+05, 6.30e+05, 0.68, 0, 0, 5000, 9.303e+05, 6.30e+05, 0.70, 0, 0, 7200, 9.303e+05, 6.30e+05, 0.73, 0, 0, 7200, 9.303e+05, 6.30e+05, 0.50, 0, 0, j 1.00e+7, 9.303e+05, 6.30e+05, 0.50, 0, 0 $END 8.1.6 CARD SERIES 1101 Items 2,3 and 4 of reference 6.1 input are deleted as-not applicable to the G1-15

(RISC) version of COPATTA.

l All other input used in this calculation remain unchanged from that of Reference 6.1, as described in Sections 8.1.1 through 8.1.33, except as changed in the

preceding paragraphs.

i d

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. - , .. = _ . - - -

NES&L DEPARTMENT ICCN NOJ i CALCULATION SHEET PREUM. CCN NO. N-1 PAGE OF b CCN CONVERSION Project or DCP/MMP SONGS UNTFS 2 and 3 Calc No. N-4080-426-Suo-A CCN NO. CCN - f

., Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A-33 REV ORIGINATOR DATE tRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 i

a 8.2 COPATTA CODE INPUT DATA - Initial Containment Pressure cpi = 16.2 psia l Supplement A also provides additional analysis to determine the margin for peak post-LOCA containment pressure under maximum containment initial pressure i conditions [ Technical Specification maximum value of 16.2 psia (1.5 psig per LC0 3.6.1.4)]. COPATTA input data for the this case is presented as changes made to

the COPATTA input for Containment P/T Design Basis LOCA Analysis and Equipment l

Qualification, presented in Section 8.1 of this document.

8.2.1 TITLE CARD o TSLOCA+ LOOP (DESLS), cpi =1.5 psig, MAX SI, CSS =1600/1950 gpm, ECUS 960s l 8.2.2 CARD SERIES 0 i No changes made to Card Series 0 of reference 6.1 other than the deletion of the j last four zero entries on the Bechtel input file as non-applicable to COPATTA version G1-15.-

8.2.3 CARD SERIES 1 General Problem Information

& LIST P00L=1,1E7,16.2,2.305E6,120,0.6,20,582.945,1,1,0.08,14.7,0,0.50 $END

! ITEM 3: PAIR = 16.2 psia The initial containment pressure before the LOCA mass and energy release is set to 16.2 psia for the peak post-LOCA containment pressure analysis, as discussed

in the Design Input Item 4.2.b.

1 i

)

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i 1

4 i

M N NLW 4/FJ

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET eReuu.CCNNO. N-1 ,Aoe e Og a l CCN CONVERSION Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Suo A CCN NO. CCN -

Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A-34 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ,

ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 9.0 COPATTA INPUT FILES 9.1 DBLOCA cpi = 14.7 psia  !

o DBLOCA+ LOOP (DESLS), cpi =0.0 psig, MAX SI, CSS =1600/1950 gpm, ECUS 060s

$ LIST P00L=0,2,1,0,1 $END

$ LIST P00L=1,1E7,14.7,2.305e6,120,0.6.20,582.945,1,18,0.00,14.7,0.5 $END

$ LIST P00L=2,0,0,1.68e5,2934,0,120,573.273 $END

$ LIST P00L=3,0,0,0,0,0,1.00e7,0,0,0,0 $END 4

$ LIST P00L=4,1,6860,216,105,3.0e6,0,0,0,0,0,0,0 $END '

$ LIST P00L=5,2,60,1.0e7,0,0 $END l

$ LIST P00L=6,0,0,0 $END

$ LEAK N0 PEN =0 $END

$ LIST P00L=101,  !

0.0000, 0.0000, j 5.7327E+02, 0.0000,  ;

5.7327E+02, 3.2931E+08, l 6.0000E+02, 3.2624E+08, 1 8.0000E+02, 3.0812E+08, 1.0000E+03, 2.9449E+08, J 2.0000E+03, 2.2734E+08, 4.0000E+03, 1.7963E+08, 6.0000E+03, 1.5728E+08, 8.0000E+03, 1.4506E+08, 1.0000E+04, 1.3706E+08, l 2.0000E+04, 1.1366E+08, l 4.0000E+04, 8.9771E+07, l 6.0000E+04, 7.8463E+07, l 8.0000E+04, 7.2141E+07, i 1.0000E+05, 6.7894E+07, 2.0000E+05, 5.4991E+07, 4.0000E+05, 4.1412E+07, 6.0000E+05, 3.4734E+07, -

8.0000E+05, 3.0911E+07, 1.0000E+06, 2.8363E+07, 2.0000E+06, 2.1296E+07, 4.0000E+06, 1.4713E+07, 6.0000E+06, 1.1629E+07, i 1.0000E+07, 8.5482E+06 $END l

$ LIST P00L=201, l 0, 2.5836e7, 211.10, 2.5836e7, i 211.10, 0, 1 573.273, 0, 573.273, 1.2635e7, 8.64e+04, 1.2635e7, i n;,t = = =w uso

NES&L DEPARTMENT ICCN NO./

CALCULATION SHEET PREUM. CCN No. N-1 PA?E OF b CCN CONVERSION l Project or DCP/MMP SONGS UNrrS 2 and 3 Calc No. N-4080-026-Suo-A CCN No. CCN - I Subject CONTAINMENTPfr ANALYSIS for DESIGN BASIS LOCA Sheet No. A-35 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 i

'l 8.64e+04, 0, 1.00e+07, 0 $END

$ LIST P00L=301, 0, 0, 0, 0.025, 2.7068e+08, 5.4632e+02, 0.075, 2.6757e+08, 5.4681e+02, 0.175, 2.8058e+08, 5.4848e+02, 0.20, 3.3993e+08, 5.4933e+02, 0.225, 3.3506e+08, 5.4967e+02, 0.25, 3.3534e+08, 5.5012e+02, 0.40, 3.1384e+08, 5.5312e+02, 0.75, 2.9337e+08, 5.6162e+02, 0.85, 2.7364e+08, 5.6237e+02, 1.0, 2.4650e+08, 5.6329e+02, 1.2, 2.2548e+08, 5.6429e+02, 2.0, 2.0756e+08, 5.6709e+02, 3.0, 1.8229e+08, 5.7573e+02, 4.0, 1.5767e+08, 5.9697e+02, 5.0, 1.3255e+08, 6.3045e+02, 6.0, 1.1328e+08, 6.5884e+02, 8.0, 9.4860e+07, 6.7161e+02, 10.0, 7.8800e+07, 6.8765e+02, 12.0, 5.4454e+07, 7.6610e+02, 13.5, 3.566e+07, 8.640e+02, 14.5, 2.888e+07, 7.502e+02, 15.0, 2.627e+07, 7.199e+02, '

16.0, 1.768e+07, 6.699e+02, 17.1, 1.119e+07, 6.556e+02, q 17.2, 1.140e+07, 6.386e+02, k 17.3, 9.065e+06, 6.213e+02, l 18.5, 6.152e+06, 6.439e+02, 19.3, 8.806e+06, 4.605e+02, 19.8, 6.066e+06, 4.881e+02, _

l 20.6, 4.172e+06, 5.348e+02, J 20.8, 1.016e+07, 3.317e+02,  !

21.4, 3.629e+06, 3.700e+02, i 21.6, 1.77e+06, 3.66e+02, I 21.8, 3.0e+05, 3.46+02, I 22.0, 0.00, 0.00, '

22.0, 0.00, 0.00, 22.25, 5.8302e+05, 1.3000e+03, 23.25, 9.2236e+05, 1.3000e+03, 24.25, 1.5463e+06, 1.3000e+03, 25.25, 2.0444e+06, 1.3000e+03, 26.25, 2.4255e+06, 1.3000e+03,  !

27.75, 2.8736e+06, 1.3000e+03, j sGk i542b NLM 4/90

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PREt_iu. CCN NO. N-1 PAGE OF N CCN CONVERSION  !

Project Or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Sun-A CCN No. CCN - '

Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A-36 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE l

IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 l

28.00, 1.8443e+06, 1.3000e+03, j 36.00, 1.8201e+06, 1.3000e+03, <

44.50, 1.7920e+06, 1.3000e+03, l 44.75, 2.7987e+06, 1.3000e+03, 75.00, 2.6467e+06, 1.3000e+03, l 3

100.00, 2.5190e+06, 1.3000e+03, 125.00, 2.3921e+06, 1.3000e+03, )

150.00, 2.2677e+06, 1.3000e+03, '

j 175.00, 2.1401e+06, 1.3000e+03, i 200.00, 2.0116e+06, 1.3000e+03,  !

211.10, 1.9553e+06, 1.3000e+03,

{

211.101, 2.2478e+06, 1.1865e+03, 211.336, 2.2378e+06, 1.1865e+03, i 211.573, 2.2279e+06, 1.1865e+03, 4

211.812, 2.2179e+06, 1.1865e+03, 212.052, 2.2080e+06, 1.1865e+03, 213.026, 2.1615e+06, 1.1877e+03, 215.073, 2.0469e+06, 1.1878e+03, 216.989, 1.9466e+06, 1.1879e+03,

219.039, 1.8464e+06, 1.1880e+03, 221.233, 1.7463e+06, 1.1881e+03, 1 222.894, 1.6748e+06, 1.1883e+03, 1

225.021, 1.5891e+06, 1.1884e+03, 226.920, 1.5179e+06, 1.1885e+03,

, 228.953, 1.4468e+06, 1.1887e+03, 231.139, 1.3760e+06, 1.1889e+03, 233.014, 1.3194e+06, 1.1891e+03, 235.017, 1.2631e+06, 1.1892e+03,

, 237.167, 1.2070e+06, 1.1894e+03,

, 238.890, 1.1647e+06, 1.1900e+03,

240.719, 1.1232e+06, 1.1898e+03, 242.668, 1.0816e+06, 1.1900e+03, 245.484, 1.0265e+06, 1.1902e+03, -

l 246.897, 9.9907e+05, 1.1904e+03, 249.420, 9.5821e+05, 1.1906e+03, 251.151, 9.3110e+05, 1.1908e+03, 254.936, 8.7746e+05, 1.1911e+03, 259.251, 8 2462e+05, 1.1914e+03, J 262.929, 7.8563e+05, 1.1917e+03, .

267.086, 7.4729e+05, 1.1919e+03, I q 271.855, 7.0974e+05, 1.1921e+03, l

281.634, 6.4948e+05, 1.1925e+03, i i

292.060, 6.0412e+05, 1.1925e+03, I 302.415, 5.7236e+05, 1.1923e+03, 311.215, 5.5256e+05, 1.1919e+03, 321.094, 5.3597e+05, 1.1820e+03, i

M = "= Mtyv ArWD

NES&L DEPARTMENT CCN NO /

CALCULATION SHEET PREUM. CCN NO. N-1 PAGE OF CCN CONVERSION j Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Suo-A CCN NO. CCN - I i'

Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A-37 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 v

331.360, 5.2312e+05, 1.1820e+03,

, 340.999, 5.1401e+05, 1.iS19e+03, i 351.095, 5.0663e+05, 1.1810e+03,

361.352, 5.0080e+05, 1.1819e+03, 371.311, 4.9637e+05, 1.1818e+03, 391.750, 4.8974e+05, 1.1818e+03., ,

411.491, 4.8546e+05, 1.1819e+03, 432.076, 4.8233e+05, 1.1817e+03, j 452.069, 4.8013e+05, 1.1817e+03, 471.774, 4.7851e+05, 1.1816e+03,

. 524.047, 4.7578e+05, 1.1816e+03, 573.273, 4.7426e+05, 1.1816e+03, 573.273, 0.00, 0.00, 1.00e+07, 0.00, 0.00 $END

$ LIST P00L=401,

! O, 0, 0, 1

211.1, 0, 0, 573.273, 0, 0, 573.273, 1, 1,

! 8.64e+04, 1, 1, l 8.64e+04, 1, 0,

. 1.00e+07, 1, 0 $END

$ LIST P00L=501, 1 0.0, 0, 0, 1.0e+07, 0, 0 $END

$ LIST P00L=601, 0.00, 0.00, 0.00, 28.00, 0.00, 0.00, 28.00, 4.823e+06, 5.362e+08, 211.10, 4.823e+06, 5.362e+08, 211.101, 8.73e+05, 7.7e+07, 211.336, 8.83e+05, 7.8e+07, 211.573, 8.93e+05, 7.9e+07, 211.812, 9.03e+05, 7.9e+07, 212.052, 9.13e+05, 8.0e+07,

! 213.026, 9.60e+05, 8.4e+07, 4 215.073, 1.07e+06, 9.5e+07, l 216.989, 1.17e+06, 1.0e+08, 219.039, 1.27e+06, 1.le+08, 221.233, 1.37e+06, 1.2e+08,

222.894, 1.45e+06, 1.3e+08, 225.021, 1.53e+06, 1.3e+08, i

226.920, 1.60e+06, 1.4e+08, 4 228.953, 1.67e+06, 1.5e+08, 231.139, 1.75e+06, 1.5e+08, 233.014, 1.80e+06, 1.6e+08, l

N= SP O 1

NES&L DEPARTMENT ICCN NOJ 4

CALCULATION SHEET PREUM. CCN NO. N-1 PAGE Y70F bb CCN CONVERSION Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Suo-A CCN NO. CCN - f Subject CONTAINMENTPfr ANALYSIS for DESIGN BASIS LOCA Shee'. No. A-38

~

REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE l g AREN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 1

235.017, 1.86e+06, 1.6e+08, j 237.167, 1.91e+06, 1.7e+08, 238.890, 1.96e+06, 1.7e+08, f

240.719, 2.00e+06, 1.8e+08, 242.668, 2.04e+06, 1.8e+08, 245.484, 2.09e+06, 1.8e+08, ,

246.897, 2.12e+06, 1.9e+08, j 249.420, 2.16e+06, 1.9e+08,

, 251.151, 2.19e+06, 1.9e+08, 254.936, 2.24e+06, 2.0e+08, 4

259.251, 2.30e+06, 2.0e+08, l 262.929, 2.34e+06, 2.le+08,  !

! 267.086, 2.37e+06, 2.le+08, l

, 271.855, 2.41e+06, 2.le+08, 281.634, 2.47e+06, 2.2e+08, J

292.060, 2.52e+06, 2.2e+08, 302.415, 2.55e+06, 2.2e+08, I 4

311.215, 2.57e+06, 2.3e+08, l 321.094, 2.59e+06, 2.3e+08, 331.360, 2.60e+06, 2.3e+08, .

340.999, 2.61e+06, 2.3e+08, 351.095, 2.61e+06, 2.3e+08, l, 361.352, 2.62e+06, 2.3e+08, 371.311, 2.62e+06, 2.3e+08,

, 391.750, 2.63e+06, 2.3e+08, 411.491, 2.64e+06, 2.3e+08, 432.076, 2.64a+06, 2.3e+08, >

l 452.069, 2.64e+06, 2.3e+08, 471.774, 2.64e+06, 2.3e+08, 524.047, 2.65e+06, 2.3e+08, j

. 573.273, 2.65e+06, 2.3e+08, 573.273, 0.00, 0.00, 1.00e+07, 0.00, 0.00 $END

$ LIST P00L=701, 0, 0, 1, 0, 211.1, 0, 1, 0, 211.1, 0, 0, 0, 573.273, 0, 0, 0, 8.64e+04, 0, 0, 0, 1.00e+07, 0, 0, 0 $END

$ LIST P00L=801, 0, 0, 0, 0, 100, 100, 60, 0, 0, 0, 100, 100, 60, 7.956e+05, 0, 0, 100, 100, 573.273, 7.956e+05, 0, 0, 100, 100, 573.273, 7.956e+05, 3.12e+06, 0.90, 100, 100,

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PREuu. CCN NO. N-1 PAGE OF CCN CONVERSION Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Sun-A CCN NO. CCN -

Subject CONTAINMENTPfr ANALYSIS for DESIGN BASIS LOCA Sheet No. A-39 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALL.EN EVINAY 01/31/95 FAUL BARBOUR 02/03/95 800, 7.956e+05, 3.12e+06, 0.90, 100, 100, 900, 7.956e+05, 3.12e+06, 0.91, 100, 100, 1500, 7.956e+05, 3.12e+06, 0.92, 100, 100, 2284, 7.956e+05, 3.12e+06, 0.93, 100, 100, 2284, 9.303e+05, 6.'30e+05, 0.67, 0, 0, 3000, 9.303e+05, 6.30e+05, 0.68, 0, 0, 4000, 9.303e+05, 6.30e+05, 0.68, 0, 0, 5000, 9.303e+05, 6.30e+05, 0.70, 0, 0, 7200, 9.303e+05, 6.30e+05, 0.73, 0, 0, 7200, 9.303e+05, 6.30e+05, 0.50, 0, 0, 1.00e+7, 9.303e+05, 6.30e+05, 0.50, 0, 0 $END

$ LIST P00L=901, 0.0, 0, 0, 1.0e+07, 0, 0 $END

$ LIST P00L=1001, 0, 100, 2.0, 24, 100, 2.0 $END

$ LIST P00L=1101, 105, 0.000, 120, 1.670e+06, 130, 3.020e+06, 140, 4.570e+06, 150, 6.320e+06, 160, 8.270e+06, 170, 1.040e+07, 180, 1.273e+07, 190, 1.523e+07, 200, 1.788e+07, 210, 2.068e+07, 220, 2.361e+07, 230, 2.664e+07, 240, 2.974e+07, 250, 3.291e+07, _

260, 3.611e+07, 270, 3.931e+07, 280, 4.252e+07, 287, 4.474e+07, 290, 4.569e+07, 300, 4.882e+07 $END

$ LIST P00L=1201, 0.0, 0.729, 0.1, 0.737, 0.2, 0.747, 0.3, 0.757, 0.4, 0.771, 0.5, 0.788, u = = =,. .w

NES&L DEPARTMENT icCN NOJ CALCULATION SHEET PREW. MN NO. N-1 pros D op %

CCN CONVERSION Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Sun-A CCN NO. CCN - [

Subject CONTAINMENTPfr ANALYSIS for DESIGN BASISIDCA Sheet No. A-40 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 0.6, 0.809, 0.7, 0.832, .

0.8, 0.863, I 0.9, 0.912, I 1.0, 0.961, 1.1, 0.983, 1.2, 0.995, )

1.3, 1.000 $END i

$ LIST P00L=9001, )

1, 0.05, 0.1, 10, '

10, 0.05, 1.0, 9 .

20, 0.05, 1.0, 10, 1 100, 0.1, 1.0, 20, 1 300, 1.0, 5.0, 10, 400, 1.0, 10.0, 10, 600, 2.0, 10.0, 10, 3e+03, 5.0, 50.0, 4, 4e+03, 10.0, 100, 5, le+04, 50.0, 500, 4, 4e+04, 50.0, 2500, 4, le+05, 50.0, 5000, 2, 3e+05, 50.0, 25000, 4, le+06, 50.0, le+05, 1, le+07, 50.0, Se+05, 1, 2e+07, 50.0, Se+05, 1 $END

$ LIST P00L=9999 $END

• HS #1 - REACTOR BUILDING DOME

$ LIST P00L=101001, 100, 7, 0, 0, 0, 0, 34693.22 $END  !

$ LIST P00L=101101, 5, 0.00075, 3, 0.02158, i 3, 0.02193, 10, 0.06360, l 20, 0.23028, 37, 1.00110,

21, 4.06363 $END

! $ LIST P00L=101201, 4, 1, 5, 2, 2, 2, 2 $END -

$ LIST P00L=101300, 0, 0 $END

$ LIST P00L=101400, 2, 2, 1, 1 $END

• HS #2 - CYLINDER WALL BETWEEN El. 29'6" AND 112'0" l

$ LIST P00L=102001, 100, 7, 0, 0, 0, 0, 38120 $END l

$ LIST P00L=102101, 5, 0.00075, 3, 0.02158, l 3, 0.02193, 10, 0.06360, 20, 0.14694, 37, 0.917761, 21, 4.35526 $END

$ LIST P00L=102201, 4, 1, 5, 2, 2, 2, 2 $END

$ LIST P00L=102300, 0, 0 $END

, $ LIST P00L=102400, 2, 2, 1, 1 $END

• HS #3 - CYLINDER WALL BETWEEN El. 15'0" AND El. 29'6"

$ LIST P00L=103001, 100, 7, 0, 0, 0, 0, 6667.38 $END

j u - mi;w 4rso

NES&L DEPARTMENT ICCN NOJ l CALCULATION SHEET PREUM. CCN NO. N-1 PAGE OF CCN CONVERSION Project or DCP/MMP SONGS UNITS 2 and 3 Caic No. N-4080-026-Suo-A CCN NO. CCN - f Subject CONTAINMENTP/T ANALYSIS forDESIGN BASIS 10CA Sheet No. A- 41 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE .

A1.LEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95

$ LIST P00L=103101, 5, 0.00075, 3, 0.02158, 3, 0.02193, 10, 0.06360, 20, 0.14694, 37, 0.917761, 21, 4.35526 $END

$ LIST P00L=103201, 4, 1, 5, 2, 2, 2, 2 $END

$ LIST P00L=103300, 0, 0 $END

$ LIST P00L=103400, 2, 2, 0, 2 $END

• HS #4 - BASEMAT (OTHER THAN REACTOR BASEMAT)

$ LIST P00L=104001, 53, 5, 0, 0, 0, 0, 12800 $END

$ LIST P00L=104101, 3, 0.00067, 7, 0.1, 20, 1.52698,  ?, 1.54781, 20, 11.02150 42.0

$ LIST P00L=104201, 4, 2, 2, 1, 2 $END

$ LIST P00L=104300, 0, 0 $END

$ LIST P00L=104400, 3, 3, 0, 3 $END

• HS #5 - REACTOR BASEMAT & S.G. PEDESTALS

$ LIST P00L=105001, 70, 4, 0, 0, 0, 0, 1644 $END

$ LIST P00L=105101, 4, 0.00158, 10, 0.1, 30, 2.00, 25, 8.43092 $END

$ LIST P00L=105201, 4, 2, 2, 2 $END

$ LIST P00L=105300, 0, 0 $END

$ LIST P00L=105400, 3, 3, 0, 3 $END

• HS #6 - REACTOR CAVITY WALLS BELOW El. 15'0"

$ LIST P00L=106001, 93, 5, 1, 11.75, 0, 0, 21.5 $END

$ LIST P00L=106101, 5, 11.75192, 7, 11.77292, 30, 13.29923, 30, 19.29923, 20, 25.25192 $END

$ LIST P00L=106201, 4, 2, 2,.2, 2 $END

$ LIST P00L=106300, 0, 0 $END

$ LIST P00L=106400, 3, 3, 0, 3 $END

• HS #7 - REACTOR CAVITY WALLS AB0VE El. 15'0"

$ LIST P00L=107001, 68, 5, 0, 0, 0, 0, 2810 $END

$ LIST P00L=107101, 5, 0.00192, 7, 0.02292, -

15, 0.40192, 20, 2.00, 20, 4.00192 $END

$ LIST P00L=107201, 4, 2, 2, 2, 2 $END

$ LIST P00L=107300, 0, 0 $END

$ LIST P00L=107400, 2, 2, 0, 2 $END

• HS #8 - LINED REFUELING CANAL WALLS

$ LIST P00L=108001, 86, 6, 0, 0, 0, 0, 9200 $END

$ LIST P00L=108101, 5, 0.01563, 20, 0.1, 1S, 0.41563, 20, 2.00, 20, 4.01563, 5, 4.01755 $END

$ LIST P00L=108201, 3, 2, 2, 2, 2, 4 $END

$ LIST P00L=108300, 0, 0 $END

$ LIST P00L=108400, 2, 2, 2, 2 $END

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET eReuu. CCN No. N-1 g,os s/ og es CCN CONVERSION Project or DCP/MMP SONGS UNrrS 2 and 3 Calc No. N-4080-026-Sun-A CCN No. CCN - 1 Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A- 42 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95

• HS #9 - S.G. CMPRTMNT WALLS, UNLINED REFL CNL WALLS /0TH INT WALLS

$ LIST P00L=109001, 78, 4, 0, 0, 0, 0, 41976 $END

$ LIST P00L=109101, 5, 0.00192, 10, 0.04233, 12, 0.1, 50, 1.71876 $END

$ LIST P00L=109201, 4, 2, 2, 2 $END

$ LIST P00L=109300, 0, 0 $END

$ LIST P00L=109400, 2, 2, 0, 2 $END

• HS #10 - FLOOR SLABS (OTHER THAN BASEMATS)

$ LIST P00L=110001, 67, 6, 0, 0, 0, 0, 17474 $END

$ LIST P00L=110101, 3, 0.00014, 5, 0.005348, 20, 0.105348, 15, 0.505348, 20, 1.505348, 3, 1.506015 $END

$ LIST P00L=110201, 4, 1, 2, 2, 2, 4 $END

$ LIST P00L=110300, 0, 0 $END

$ LIST P00L=110400, 2, 2, 2, 2 $END

• HS #11 - LIFTING DEVICES (EXCEPT STAINLESS STEEL PARTS)

$ LIST P00L=111001, 17, 2, 0, 0, 0, 0, 57286 $END

$ LIST P00L=111101, 6, 0.00125, 10, 0.042917 $END

$ LIST P00L=111201, 4, 1 $END

$ LIST P00L=111300, 0, 0 $END

$ LIST P00L=111400, 2, 2, 0, 2 $END l

• HS #12 - MISCELLANE0US CARBON STEEL - THICKNESS > 2.50 INCHES

$ LIST P00L=112001, 64, 4, 0, 0, 0, 0, 516 $END

$ LIST P00L=112101, 6, 0.0005, 17, 0.084, 15, 0.20, 25, 0.310849 $END

$ LIST P00L=112201, 4, 1, 1, 1 $END I

$ LIST P00L=112300, 0, 0 $END l

$ LIST P00L=112400, 2, 2, 0, 2 $END 1

• HS #13 - MISCELLANE0US CARBON STEEL: 1.00"< THICKNESS <2.50" l

$ LIST P00L=113001, 32, 2, 0, 0, 0, 0, 12042 $END

$ LIST P00L=113101, 6, 0.00063, 25, 0.16967 $END

$ LIST P00L=113201, 4, 1 $END

$ LIST P00L=113300, 0, 0 $END -

$ LIST P00L=113400, 2, 2, 0, 2 $END

• HS #14 - MISCELLANE0US CARBON STEEL: 0.50"< THICKNESS <1.00"

$ LIST P00L=114001, 19, 2, 0, 0, 0, 0, 64693 $END

$ LIST P00L=114101, 5, 0.000674, 13, 0.038607 $END

$ LIST P00L=114201, 4, 1 $END

$ LIST P00L=114300, 0, 0 $END I

$ LIST P00L=114400, 2, 2, 0, 2 $END l

• HS #15 - MISCELLANE0US CARBON STEEL: THICKNESS <0.5" l

$ LIST P00L=115001, 17, 2, 0, 0, 0, 0, 98913.6 $END l

$ LIST P00L=115101, 6, 0.000606, 10, 0.012833 $END

$ LIST P00L=115201, 4, 1 $END i

$ LIST P00L=115300, 0, 0 $END i

$ LIST P00L=115400, 2, 2, 0, 2 $END l

l J

.- - _ _ -. ~ -

] NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PRELIM. CCN NO. N-1 PAGE I 20F b CCN CONVERSION CCN NO. CM -

Project Or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080426-Sun-A

Subject CONTAINMENTPfr ANALYSIS for DESIGN BASIS LOCA Sheet No. A- 43 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95

• HS #16 - ELECTRICAL EQUIPMENT

$ LIST P00L=116001, 8, 1, 0, 0, 0, 0, 37644.5 $END

$ LIST P00L=116101, 7, 0.0054 $END

$ LIST P00L=116201, 1 $END

$ LIST P00L=116300, 0, 0 $END

$ LIST P00L=116400, 2, 2, 0, 2 $END

!

• HS #17 - MISCELLANEOUS STAINLESS STEEL

$ LIST P00L=117001, 16, 1, 0, 0, 0, 0, 24048 $END

$ LIST P00L=117101, 15, 0.01747 $END

$ LIST P00L=117201, 3 $END

$ LIST P00L=117300, 0, 0 $END

$ LIST P00L=117400, 2, 2, 0, 2 $END

• HS #18 - UNLINED REFUELING CANAL WALLS BELOW El. 63'6"

$ LIST P00L=118001, 48, 4, 0, 0, 0, 0, 3700 $END

$ LIST P00L=118101, 5, 0.00192, 7, 0.02292, 15, 0.40192, 20, 2.00192 $END

$ LIST P00L=118201, 4, 2, 2, 2 $END

$ LIST P00L=118300, 0, 0 $END

$ LIST P00L=118400, 2, 2, 0, 2 $END

• HS #19 - REACTOR BLDG CYLINDER #3: SECTIONS WITH STIFFENERS

$ LIST P00L=119001, 100, 7, 0, 0, 0, 0, 1590.68 $END

$ LIST P00L=119101, 5, 0.00075, 20, 0.66742, 3, 0.66777, l 15, 0.70944, 20, 0.79278, 16, 1.44278,

' 20, 4.87885 $END

$ LIST P00L=119201, 4, 1, 5, 2, 2, 2, 2 $END

$ LIST P00L=119300, 0, 0 $END

. $ LIST P00L=119400, 2, 2, 1, 1 $END

• HS #20 - VENT TUNNELS

$ LIST P00L=120001, 23, 2, 0, 0, 0, 0, 2827 $END i $ LIST P00L=120101, 10, 0.0005, 12, 0.03175 $END

$ LIST P00L=120201, 4, 1 $END

$ LIST P00L=120300, 0, 0 $END .'

$ LIST P00L=120400, 2, 2, 0, 2 $END -

1 $ LIST P00L=410001,

. 25, 54, 0.8, 30, 10, 54, 0.1, 20, 0.0174, 0.0103 $END

$ LIST P00L=500000 $END i,

e si.h &E5 NUR NUQ

NES&L DEPARTMENT ICCN NO/

CALCULATION SHEET rREuu. CCN NO. N-1 g,oE s 0, se CCN COf#ERSION f

Project or DCP/MMP _ SONGS ' UNITS 2 and 3 Calc No. N-4080-026-Sun-A CCN NO. CCN - l Subject CONTAINMENTPfr ANALYSIS for DESIGN BASIS LOCA Sheet No. A-44 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 4

9.2 TSLOCA cpi = 16.2 psia

• TSLOCA+ LOOP (DESLS), cpi =1.5 psig, MAX SI, CSS =1600/1950 gpm, ECUS 960s

$ LIST P00L=0,2,1,0,1 $END

$ LIST P00L=1,1E7,16.2,2.305e6,120,0.6.20,582.945,1,18,0.00,14.7,0.5 $END All other input data is identical to the DBLOCA input data.

4

NES&L DEPARTMENT ICCN NO./

CALCULATION SHEET PREUM. CCN NO. N-1 PAGE 5 OF bb CCN CONVERSION Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-426-Suo-A CCN NO. CCN - f Subject CONTAINMENTP/T ANAI,ySIS for DESIGN BASIS LOCA Sheet No. A- 45 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 10.0 SELECTED OUTPUT DATA The tabulated data presented in Sections 10.1 and 10.2 consists of partial output of the COPATTA calculation made for this analysis with the initial containment pressure 0 0 PSIG.

10.1 Tables for Figures 2-1, 2-2 and 2-5 CONTAINMENT CONTAINMENT CONTAINMENT HEAT SINK 1

TIME PRESSURE VAPOR TEMP SUMP TEMP (LEFT BOUND)*

(SEC) (PSIG) (F) (F) (F) 0 0.00 120.00 120.00 1 6.68 173.11 211.06 126.2 1 2 11.69 197.16 212.02 3 16.00 212.43 216.68 4 19.78 223.39 221.70 5 23.24 232.08 225.69 6 26.22 238.77 229.96 7 29.02 244.51 232.05 8 31.47 249.70 234.56 9 33.81 253.41 236.59 10 35.82 256.86 238.60 195.9 11 37.76 260.02 240.16 12 39.41 262.74 241.27 13 40.78 264.72 242.14 14 41.94 266.61 242.77

, 15 42.58 267.43 243.44 16 42.90 267.87 244.00 M ."_ " . NhW 4/50 i

I NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PREuu. CCN NO. N1 PAGE b OF bb CCN CONVERSION i Project or DCP/MMP .. SONGS UNTFS 2 and 3 Calc No. N-40B&4264ius-A CCN NO. CCN - l )

Subject CONTAINMENTP/r ANALYSIS forDESIGN BASIS [DCA Sheet No. A-46 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE l ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 i

CONTAINMENT CONTAINMENT CONTAINMENT NEAT SINK 1

TIME PRESSURE VAPOR TEMP SUMP TEMP (LEFT BOUND)* ,

(SEC) (PSIG) (F) (F) (F) 17 43.00 267.98 244.47 1

18 42.92 267.88 244.81 19 42.79 267.69 245.10 i 20 42.62 267.46 245.44 226.0 4

l 22 42.22 266.86 245.93 i 24 41.89 266.43 246.07 l 25 41.81 266.63 246.13

26 41.80 267.12 246.19 28 41.87 268.70 246.30 i

30 41.90 269.75 245.52 32 41.91 270.75 244.75 33 41.93 271.28 244.37 34 41.96 271.84 244.00 36 42.00 272.97 243.26 38 42.05 274.11 242.53 40 42.12 274.30 241.82 219.7 42 42.19 276.47 241.13

44 42.26 277.65 240.45 45 42.23 278.45 240.11 46 42.47 279.60 239.78 .

48 42.74 281.89 239.12 50 43.01 284.17 238.48 f, 52 43.28 286.42 237.84

--- l

, NES&L DEPARTMENT ICCN NOJ

CALCULATION SHEET PREUM. CCN No. N-1 PAGE I boF Ob CCN CONVERSION l Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Suo-A CCN No. CCN - f Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A-47 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE g AM.EN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 q ,

i '

) CONTAINMENT CONTAINMENT CONTAINMENT HEAT SINK i 1 4

TIME PRESSURE VAPUR TEMP SUMP TEMP (LEFT BOUND)*

I (SEC) (PSIG) (F) (F) (F) 54 43.56 288.70 237.23 f 56 43.85 290.93 236.62

} 58 44.12 293.15 236.03 60 44.40 295.35 235.44 229.8 62 44.41 293.37 234.88 g 64 44.41 291.34 234.32

66 44.41 289.33 233.77

- 68 44.42 287.35 233.23 1

70 44.43 285.38 232.70 I 75 44.46 280.63 231.42 80 44.52 276.08 230.18 236.9 85 44.62 271.76 228.99 90 44.87 270.75 227.89 95 45.34 271.43 226.66 100 45.66 271.85 225.87 242.9 '

105 46.12 272.91 224.91 110 46.51 273.28 223.99 115 46.94 273.45 223.13 120 47.32 274.42 222.27 125 47.52 274.22 221.46 130 48.04 274.77 220.68 135 48.44 275.33 219.92 140 48.83 275.85 219.40 u - ,o s

NES&L DEPARTMENT LCCN NOJ  !

CALCULATION SHEET PaEuu. CCN NO. N-1 g,os 90, &

CCN CONVERSION CCN NO. CCN -

) Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Sun-A

] Subject CONTAINMENTPfr ANALYSIS for DESIGN BASIS LOCA Sheet No. A- 48 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95

CONTAINMENT CONTAINMENT CONTAINMENT HEAT SINK

! 1

! TIME PRESSURE VAPOR TEMP SUMP TEMP (LEFT BOUND)*

(SEC) (PSIG) (F) (F) (F) j 145 49.29 276.93 218.48 5

150 49.67 277.34 217.79 254.5 i 155 49.99 277.47 217.15 4

4 160 50.38 277.89 216.50 165 50.77 278.36 215.89 1

170 51.13 279.06 215.28 4

5 175 51.48 279.37 214.72 1 180 51.85 279.88 214.16 185 52.23 280.27 213.61 l 190 52.58 280.68 213.09 l

195 52.96 281.27 212.58 l 200 53.37 281.84 212.06 l 205 53.71 282.17 211.58 i 210 54.04 282.48 211.12 215 54.35 282.81 211.11 j 220 54.61 283.12 211.16

, 225 54.80 283.36 211.16 i 230 54.95 283.53 211.12

! 235 55.03 283.63 211.06

) 240 55.08 283.74 210.95

245 55.13 283.74 210.85_

250 55.13 283.74 210.72 268.0 255 55.13 283.73 210.58 i

, m--

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET Paeuu. CCN NO. N.i e,oe 580 ,a6 Pro}ect or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Sun-A CCN CCN No.CONVERSION CCN - l Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A-49 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 CONTAINMENT CONTAINMENT CONTAINMENT HEAT SINK 1

TIME PRESSURE VAPOR TEMP SUMP TEMP (LEFT BOUND)*

(SEC) (PSIG) (F) (F) (F) 260 55.11 283.71 210.42 265 55.07 283.66 210.25 270 55.02 283.61 210.08 275 54.97 283.54 209.90 280 54.90 283.47 209.71

, 285 54.84 283.39 209.53 l

290 54.76 283.31 209.34

295 54.70 283.22 209.14

300 54.63 283.14 208.94 269.8

, 310 54.49 282.96 208.54 320 54.34 282.78 208.15 330 54.20 282.61 207.76

340 54.05 282.44 207.37 350 53.92 282.28 206.98

! 400 53.21 281.41 204.74 270.9 450 52.88 281.00 203.32 2

500 52.58 280.61 201.68 271.3 550 52.36 280.34 200.15 600 51.96 279.83 198.31 271.5 i

700 50.87 278.44 194.34 800 49.92 277.21 190.98 270.1 900 49.08 276.11 188.05 48.33 1000 275.10 185.46

u = = nw .

i

NES&L DEPARTMENT ICCN NOJ 1 CALCULATION SHEET PaEuu. CCN NO. N-1 ,,oE e 0, a CCN CONVERSION Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Sun-A CCN No. CCN -

Subject CONTAINMENTPfr ANALYSIS for DESIGN BASIS LOCA Sheet No. A- 50 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE

ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 i

i CONTAINMENT CONTAINMENT CONTAINMENT HEAT SINK 4

1 i TIME PRESSURE VAPOR TEMP SUMP TEMP (LEFT BOUND)*

(SEC) (PSIG) (F) (F) (F) 1100 47.63 274.17 183.17 1200 47.26 273.64 181.12 267.7 1300 46.62 272.76 179.29 1 1400 46.01 271.91 177.63 266.4 1500 45.38 271.03 176.13 l

1600 44.81 270.21 174.74 265.2 1700 44.25 269.40 173.47 1800 43.69 268.58 172.28 263.9

} 1900 43.13 267.75 171.19 2000 42.58 266.92 170.16 262.6 2100 42.03 266.09 169.20 2200 41.50 265.29 168.30 261.1 l 2300 41.00 264.51 167.75 2400 40.56 263.84 168.85 259.8 i

2500 40.17 263.26 169.94 1

2600 39.80 262.68 170.99 258.8 2700 39.39 262.03 172.02 2800 38.98 261.40 173.04 257.6 2900 38.58 260.77 174.02 3000 38.20 260.15 175.00 256.5 3500 36.34 257.14 179.51 253.7

, 4000 34.72 254.38 183.54 251.1 8000 25.87 237.24 203.80 234.9 u===,,-

i 4

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PRELIM. CCN NO. N-1 PAGE b OF b CCN CONVERSION Project or DCP/MMP SONGS UNTFS 2 and 3 Calc No. N-4080-026-Suo-A CCN NO. CCN -

Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A- 51 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE ALEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 CONTAINMENT CONTAINMENT CONTAINMENT HEAT SINK 1

TIME PRESSURE VAPOR TEMP SUMP TEMP (LEFT BOUND)*

(SEC) (PSIG) (F) (F) (F) 9000 24.54 234.25 206.86 10000 23.58 232.03 209.19 229.7 _ _ _

15000 20.72 224.93 214.74 20000 19.00 220.27 215.51 218.2 40000 14.39 205.95 206.90 204.6 60000 11.68 195.72 197.30 194.7 90000 8.60 _181.76 187.81 181.8 1E+5 7.64 176.64 183.17 176.6 2E+5 4.84 158.75 167.98 158.5 3E+5 3.74 149.88 161.72 149.5 4E+5 2.81 141.35 156.37 141.7 SE+5 2.33 136.30 152.98 136.4 6E+5 1.91 131.59 150.11 132.0 7E+5 1.64 128.47 148.14 128.7 8E+5 1.41 125.49 146.37 125.8 9E+5 1.23 123.16 144.94 123.4 1E+6 1.08 121.10 143.72 121.3 1.5E+6 0.59 115.64 140.39 115.2 2E+6 0.43 113.32 136.04 112.3 4E+6 0.29 111.00 126.70 110.0 6E+6 0.20 109.72 122.27 108.9 1E+7 0.14 108.50 117.82 108.0

• Inside surface temperature of containment c.ome.

- =w -

NES&L DEPARTMENT iCCN NOJ CALCULATION SHEET PREUM. CCN NO. N-1 PAGE [O[ OF bb CCN CONVERSION Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Suo-A CCN NO. CCN - l Subject COfRAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sneet No. A- 52 REV ORIGINATOR DATE lRE DATE REV ORIGINATOR DATE 1RE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 1

10.1 (CONTINUED)

Table for FIGUMt 2-3 Condensing Heat Transfer coefficient v.s. Time j TIME CONDENSING

! HEAT TRANSFER COEFFICIENT sec BTU /hr-ft' "F 0 0 0.05 9.3 0.1 9.9 0.2 12.7 I

0.5 18.6

! 0.4 16.7 0.6 20.1 l 0.8 22.9 1 25.5 1 2 37.5 4 59.9 1

6 85.2 8 -113.6 10 142.0 12 170.4 4

14 198.8 16 227.2 18 255.6 19 255.6 20 229.8 22 206.6 24 185.7

26 166.9 28 150.0 30 134.8 35 113.6 40 113.4 4 45 113.2 50 113.7 u-=-

1 NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PREuM. CCN No. N-1 PAGE OF CCN CONVERSION Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Sun-A CCN No. CCN - f Subject CONTAINMENTPfr ANALYSIS for DESIGN BASIS LOCA Sheet No. A- 53 REV ORIGINATOR I DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BAR8OUR 02/03/95 TIME CONDENSING HEAT TRANSFER COEFFICIENT sec BTU /hr-ft' *F 55 114.3 60 114.8 70 116.8 80 119.3 90 120.7 100 122.1 125 125.7 130 126.3 140 127.7 150 128.8 175 131.7 200 134.2 225 136.1 250 136.5 275 136.2 300 -135.7 400 134.0 500 132.9

.1000 126.1 2000 113.8 3000 102.7 4000 95.0 5000 89.7 7000 80.5 10000 68.3 20000 55.9 50000 39.2 70000 33.9 100000 26.4 500000 15.2 1000000 11.1 10000000 8.1 iGk Z "Z. Nt;W 49D

~; NES&L DEPARTMENT ICCN NOJ

)

s CALCULATION SHEET PRELIM. CCN No. N-1 PAGE OF CCN CONVERSION l Project Or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Suo-A CCN No. CCN -

1 Subject CONTAINMENTPfr ANALYSIS for DESIGN BASIS LOCA Sheet No. A-54 l REV ORIGINATOR DATE tRE DATE REV ORIGINATOR DATE 1RE DATE  !

ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 2 .

l 10.2 Table for FIGURE 2-4A

i l

r Integrated Energy Content of Containment Steam, Air and Combined Vapor  !

i Mixture; Sump Region; and Combined total of Vapor and Sump Regions l ll I

1 INTEGRATED ENERGY 4' j

TIME STEAM AIR VAPOR SUMP TOTAL 1

, (SEC) ( BTU ) (BTU) (BTU) (BTU) ( BTU )

I 3

j 0.1 1.37e+07 1.47e+07 2.84e+07 1.61e+06 3.00e+07 1 4.23e+07 1.59e+07 5.82e+07 8.73e+06 6.70e+07 t

j 2 6.96e+07 1.65e+07 8.61e+07 1.52e+07 1.01e+08 3 9.34e+07 1.69e+07 1.10e+08 2.17e+07 1.32e+08 1 l

j 4 1.14e+08 1.72e+07 1.31e+08 2.75e+07 1.59e+08 5 1.33e+08 1.73e+07 1.50e+08 3.26e+07 1.83e+08

., 6 1.50e+08 1.76e+07 1.67e+08 3'.70e+07 2.04e+08 I 7 1.65e+08 1.77e+07 1.83e+08 4.08e+07 2.24e+08 8 1.79e+08 1.78e+07 1.97e+08 4.44e+07 2.41e+08

9 1.91e+08 1.79e+07 2.09e+08 4.77e+07 2.57e+08 10 2.03e+08 1.80e+07 2.21e+08 5.08e+07 2.72e+08 l

l j K.P. ' "_. retyv 4/UD 1

I l

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET eREuu. CCN NO. N.i ,,oE #O, %

CCN CONVERSION Project Or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Sun.A CCN NO. CCN -

Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A-55 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUI, BARBOUR 02/03/95 INTEGRATED ENERGY FIG 2-4A i

i 4 TIME STEAM AIR VAPOR SUMP TOTAL (SEC) ( BTU ) (BTU) ( BTU ) (BTU) (BTU) 11 2.13e+08 1.80e+07 2.31e+08 5.34e+07 2.85e+08 12 2.22e+08 1.82e+07 2.40e+08 5.55e+07 2.96e+08 1

13 2.31e+08 1.82e+07 2.49e+08 5.71e+07 3.06e+08 14 2.36e+08 1.81e+07 2.54e+08 5.82e+07 3.13e+08 15 2.40e+08 1.82e+07 2.58e+08 5.94e+07 3.17e+08 16 2.41e+03 1.83e+07 2.60e+08 6.05e+07 3.20e+08 17 2.42e+08 1.83e+07 2.60e+08 6.15e+07 3.22e+08

18 2.42e+08 1.83e+07 2.60e+08 6.22e+07 3.22e+08 l 19 2.41e+08 1.83e+07 2.59e+08 6.28e+07 3.22e+08 20 2.40e+08 1.83e+07 2.58e+08 6.35e+07 3.22e+08 22 2.38e+08 1.83e+07 2.56e+08 6.46e+07 3.21e+08 24 2.36e+08 1.83e+07 2.54e+08 6.51e+07 3.19e+08 l

25 2.35e+08 1.83e+07 2.54e+08 6.54e+07 3.19e+08 26 2.35e+08 1.83e+07 2.53e+08 6.56e+07 3.19e+08 28 2.35e+08 1.83e+07 2.53e+08 6.60e+07 3.19e+08 30 2.34e+08 1.83e+07 2.53e+08 6.66e+07 3.19e+08 4

i iGk aM NLVV WWQ l

NES&L DEPARTMENT ICCN NO./

CALCULATION SHEET eReuu.CCNno. w-1 ,Aae 60,

• CCN CONVERSION Project or DCP/MMP SONGS UNTFS 2 and 3 Calc No. N-4080-026-Suo-A CCN No. CCN - l Subject CONTAINMEMP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A-56 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 INTEGRATED ENERGY FIG 2-4A TIME STEAM AIR VAPOR SUMP TOTAL (SEC) (BTU) (BTU) (BTU) (BTU) (BTU) 32 2.34e+08 1.84e+07 2.52e+08 6.73e+07 3.20e+08 33 2.34e+08 1.84e+07 2.52e+08 6.76e+07 3.20e408 4

34 2.34e+08 1.84e+07 2.52e+08 6.79e+07 3.20e+08 i

36 2.34e+08 1.84e+07 2.52e+08 6.85e+07 3.21e+08 38 2.34e+08 1.85e+07 2.52e+08 6.91e+07 3.21e+08 40 2.33e+08 1.85e+07 2.52e+08 6.96e+07 3.22e+08 ,

i 42 2.33e+08 1.85e+07 2.52e+08 7.02e+07 3.22e+08 44 2.33e+08 1.85e+07 2.52e+08 7.08e+07 3.23e+08 45 2.33e+08 1.86e+07 2.52e+08 7.11e+07 3.23e+08 4

4 46 2.34e+08 1.86e+07 2.52e+08 7.14e+07 3.24e+08 I

I 48 2.34e+08 1.87e+07 2.53e+08 7.19e+07 3.25e+08 50 2.35e+08 1.87e+07 2.54e+08 7.25e+07 3.26e+08 52 2.36e+08 1.88e+07 2.54e+08 7.30e+07 3.27e+08 ,

1 54 2.36e+08 1.88e+07 2.55e+08 7.36e+07 3.29e+08 56 2.37e+08 1.89e+07 2.56e+08 7.41e+07 3.30e+08 58 2.38e+08 1.89e+07 2.57e+08 7.47e+07 3.31e+08 60 2.39e+08 1.90e+07 2.58e+08 7.52e+07 3.33e+08 l l

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PREUM. CCN NO. N-1 PAG 9 OF Ob CCN CONVERSION Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Sun-A CCN NO. CM - f

Subject CONTAINMENTPfr ANALYSIS for DESIGN BASIS LOCA Sheet No. A- 57 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 i

'l l

l INTEGRATED ENERGY FIG 2-4A TIME STEAM AIR VAPOR SUMP TOTAL (SEC) ( BTU ) { BTU) (BTU) ( BTU ) (BTU) 62 2.39e+08 1.89e+07 2.58e+08 7.57e+07 3.34e+08 64 2.40e+08 1.89e+07 2.59e+08 7.63e+07 3.35e+08 66 2.41e+08 1.88e+07 2.60e+08 7.68e+07 3.37e+08 68 2.42e+08 1.88e+07 2.61e+08 7.73e+07 3.38e+08 i 70 2.43e+08 1.87e+07 2.62e+08 7.79e+07 3.39e+08

! 75 2.45e+08 1.86e+07 2.64e+08 7.92e+07 3.43e+08 l 80 2.47e+08 1.85e+07 2.66e+08 8.05e+07 3.46e+08 85 2.50e+08 1.84e+07 2.68e+08 8.17e+07 3.50e+08 l 90 2.52e+08 1.84e+07 2.70e+08 8.31e+07 3.53e+08 95 2.54e+08 1.84e+07 2.72e+08 8.45e+07 3.57e+08

\

100 2.56e+08 1.84e+07 2.74e+08 8.59e+07 3.60e+08 105 2.59e+08 1.82e+07 2.77e+08 8.72e+07 3.64e+08 i i 110 2.61e+08 1.83e+07 2.79e+08 8.86e+07 3.68e+08 115 2.63e+08 1.84e+07 2.81e+08 9.00e+07 3.71e+08

120 2.65e+08 1.83e+07 2.83e+08 9.13e+07 3.75e+08 125 2.67e+08 1.84e+07 2.85e+08 9.27e+07 3.78e+08 j 130 2.69e+08 1.84e+07 2.88e+08 9.41e+07 3.82e+08 1

4 Lh *W NkW 410 i

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PREUM. CCN No. N-1 PAGE[470Fhb CCN CONVERSION Project or DCP/MMP SONGS UNTFS 2 and 3 Calc No. N-4080-026-Suo-A CCN NO. CCN -

1 i Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS _LOCA Sheet No. A-18 REV ORIGINATOR DATE tRE DATE REV ORIGINATOR DATE tRE DATE ALIIN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 INTEGRATED ENERGY FIG 2-4A TIME STEAM AIR VAPOR SUMP TOTAL (SEC) (BTU) (BTU) (BTU) ( BTU ) (BTU) j 135 2.71e+08 1.84e+07 2.90e+08 9.54e+07 3.35e+08

^

140 2.73e+08 1.84e+07 2.92e+08 9.67e+07 3.89e+08 145 2.76e+08 1.83e+07 2.94e+08 9.80e+07 3.92e+08 1

150 2.78e+08 1.84e+07 2.96e+08 9.94e+07 3.95e+08 155 2.80e+08 1.85e+07 2.98e+08 1.01e+08 3.99e+08 2 160 2.82e+08 1.85e+07 3.00e+08 1.02e+08 4.02e+08 i 165 2.84e+08 1.85e+07 3.02e+08 1.03e+08 4.06e+08 170 2.86e+08 1.84e+07 3.04e+08 1.05e+08 4.09e+08 t

175 2.88e+08 1.85e+07 3.06e+08 1.06e+08 4.12e+08 180 2.90e+08 1.86e+07 3.08e+08 1.07e+08 4.16e+08 185 2.92e+08 1.85e+07 3.10e+08 1.09e+08 4.19e+08 190 2.94e+08 1.86e+07 3.12e+08 1.10e+08 4.22e+08 195 2.96e+08 1.86e+07 3.14e+08 1.11e+08 4.25e+08 200 2.98e+08 1.85e+07 3.16e+08 1.12e+08 4.29e+08 1

205 3.00e+08 1.85e+07 3.18e+08 1.14e+08 4.32e+08

, 210 3.01e+08 1.86e+07 3.20e+08 1.15e+08 4.35e+08 215 3.03e+08 1.87e+07 3.22e+08 1.16e+08 4.38e+08 i

O M %M M

NES&L DEPARTMENT IICCN NOJ CALCULATION SHEET l eaEuu. CCN NO. N-1 ,,oE 6so,s CCN CONVERSION

, Project or DCP/MMP SONGS UNTFS 2 and 3 Calc No. N-4080-026-Suo A CCN No. CCN -

Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A-59 REV ORIGINATOR DATE BRE DATE REV ORIGINATOR DATE 1RE DATE allen EVINAY 01/31/95 PAUL BARBOUR 02/03/95 INTEGRATED ENERGY FIG 2-4A TIME STEAM AIR VAPOR SUMP TOTAL (SEC) ( BTU ) (BTU) (BTU) (BTU) (BTU) 220 3.04e+08 1.87e+07 3.23e+08 1.17e+08 4.40e+08 225 3.05e+08 1.87e+07 3.24e+08 1.18e+08 4.42e+08 230 3.06e+08 1.86e+07 3.25e+08 1.18e+08 4.43e+08 235 3.07e+08 1.87e+07 3.25e+08 1.19e+08 4.44e+08 240 3.07e+08 1.85e+07 3.26e+08 1.20e+08 4.46e+08 245 3.07e+08 1.86e+07 3.26e+08 1.21e+08 4.47e+08

?50 3.07e+08 1.86e+07 3.26e+08 1.22e+08 4.47e+08 255 3.07e+08 1.86e+07 3.26e+08 1.23e+08 4.48e+08 260 3.07e+08 1.86e+07 3.25e+08 1.24e+08 4.49e+08 ,

l 265 3.07e+08 1.85e+07 3.25e+08 1.25e+08 4.50e+08 l

270 3.06e+08 1.85e+07 3.25e+08 1.25e+08 4.50e+08 275 3.06e+08 1.85e+07 3.25e+08 1~.26e+08 4.51e+08 280 3.06e+08 1.85e+07 3.24e+08 1.27e+08 4.51e+08 285 3.05e+08 1.85e+07 3.24e+08 1.28e+08 4.52e+08 290 3.05e+08 1.84e+07 3.23e+08 1.29e+08 4.52e+08 295 3.05e+08 1.85e+07 3.23e+08 1.30e+08 4.53e+08 300 3.04e+08 1.85e+07 3.23e+08 1.31e+08 4.53e+08 l

M N i

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET eREuu. CCN No. N-1 ,AoE e 0, se  ;

Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Suo-A CCN CCN No.CONVER$10N CCN - l I l

Subject CONTAINMENTPfr ANALYSIS for DESIGN BASIS LOCA Sheet No. A-60 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 i INTEGRATED ENERGY FIG 2-4A TIME STEAM AIR VAPOR SUMP TOTAL (SEC) ( BTU ) (BTU) (BTU) ( BTU ) ( BTU )

310 3.03e+08 1.85e+07 3.22e+08 1.32e+08 4.54e+08 320 3.03e+08 1.85e+07 3.21e+08 1.34e+08 4.55e+08 330 3.02e+08 1.85e+07 3.20e+08 1.36e+08 4.56e+08 340 3.01e+08 1.85e+07 3.19e+08 1.38e+08 4.57e+08 350 3.00e+08 1.85e+07 3.19e+08 1.39e+08 4.58e+08 400 2.97e+08 1.86e+07 3.15e+08 1.48e+08 4.63e+08 450 2.94e+08 1.86e+07 3.13e+08 1.56e+08 4.69e+08 500 2.93e+08 1.86e+07 3.11e+08 1.64e+08 4.75e+08 550 2.91e+08 1.86e+07 3.10e+08 1.72e+08 4.82e+08 600 2.89e+08 1.86e+07 3.08e+08 1.79e+08 4.87e+08 700 2.83e+08 1.85e+07 3.01e+08 1.94e+08 4.95e+08 800 2.77e+08 1.85e+07 2.96e+08 2'.08e+08 5.04e+08 900 2.73e+08 1.85e+07 2.91e+08 2.21e+08 5.13e+08 1.0e+03 2.68e+08 1.85e+07 2.87e+08 2.35e+08 5.22e+08 1.le+03 2.64e+08 1.84e+07 2.83e+08 2.49e+08 5.31e+08 1.2e+03 2.61e+08 1.82e+07 2.79e+08 2.62e+08 5.41e+08 1.3e+03 2.57e+08 1.82e+07 2.75e+08 2.75e+08 5.51e+08

- = -

NES&L DEPARTMENT ICCN NO/

CALCULATION SHEET PREUM. CCN No. N.1 PAGE 70 OF b0 CCN CONVERSION

Proj:ct or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Sup-A CCN No. CCN - l

Subject .CQMTAINMENTPfr ANALYSIS for DESIGN BASIS LOCA Sheet No. A-61 l REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 d

INTEGRATED ENERGY FIG 2-4A TIME STEAM AIR VAPOR SUMP TOTAL

) (SEC) (BTU) ( BTU ) (BTU) (BTU) ( BTU )

1.4e+03 2.54e+08 1.82e+07 2.72e+08 2.88e+08 5.60e+08 1.5e+03 2.50e+08 1.83e+07 2.68e+08 3.02e+08 5.70e+08

1.6e+03 2.47e+08 1.83e+07 2.65e+08 3.15e+08 5.80e+08 3

1.7e+03 2.43e+08 1.83e+07 2.62e+08 3.28e+08 5.89e+08 k'

1.8e+03 2.40e+08 1.82e+07 2.58e+08 3.40e+08 5.99e+08 l

1.9e+03 2.37e+08 1.82e+07 2.55e+08 3.53e+08 6.09e+08 s

l 2.0e+03 2.34e+08 1.82e+07 2.52e+08 3.66e+08 6.18e+08 i

j 2.le+03 2.31e+08 1.82e+07 2.49e+08 3.79e+08 6.28e+08

, 2.2e+03 2.28e+08 1.82e+07 2.46e+08 3.91e+08 6.37e+08 2.3e+03 2.25e+08 1.81e+07 2.43e+08 4.03e+08 6.46e+08 2.4e+03 2.24e+08 1.81e+07 2.42e+08 4.06e+08 6.48e+08 2.5e+03 2.20e+08 1.84e+07 2.38e+08 4.10e+08 6.48e+08 2.6e+03 2.18e+08 1.81e+07 2.36e+08 4.14e+08 6.49e*08 2.7e+03 2.16e+08 1.81e+07 2.34e+08 4.17e+08 6.51e+08 2.8e+03 2.13e+08 1.81e+07 2.32e+08 4.20e+08 6.52e+08 2.9e+03 2.11e+08 1.81e+07 2.29e+08 4.24e+08 6.53e+08 3.0e+03 2.09e+08 1.80e+07 2.27e+08 4.27e+08 6.54e+08 a==ma

. . . . _ - - _. . _ . , = - _ _ -

NES&L DEPARTMENT ICCN NO/ j CALCULATION SHEET PREuM. CCN No. N.1 pace 7/ ops'o  ;

CCN CONVERSION l Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Suo-A CCN No. CCN - f

Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A-62 i REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 1

l INTEGRATED ENERGY FIG 2-4A I I

TIME STEAM AIR VAPOR SUMP TOTAL i

I (SEC) ( BTU ) ( BTU ) ( BTU ) (BTU) ( BTU )

l 3.5e+03 2.00e+08 1.79e+07 2.17e+08 4.42e+08 6.59e+08 l 4.0e+03 1.90e+08 1.78e+07 2.08e+08 4.55e+08 6.63e+08

8.0e+03 1.43e+08 1.47e+07 1.58e+08 5.23e+08 6.80e+08 9.0e+03 1.36e+08 1.74e+07 1.53e+08 5.33e+08 6.86e+08 f

1.0e+04 1.30e+08 1.73e+07 1.48e+08 5.41e+08 6.89e+08

1.5c+04 1.15e+08 1.72e+07 1.32e+08 5.61e+08 6.93e+08 j 2.0e+04 1.05e+08 1.70e+07 1.22e+08 5.64e+08 6.87e+08 4.0e+04 8.06e+07 1.67e+07 9.73e+07 5.41e+08 6.38e+08 1

6.0e+04 6.35e+07 1.64e+07 7.99e+07 5.08e+08 5.88e+08 9.0e+04 4.97e+07 1.61e+07 6.58e+07 4.87e+08 5.52e+08

)

i 1.0e+05 4.47e+07 1.60e+07 6.07e+07 4.73e+08 5.33e+08 i

! 2.0e+05 3.01e+07 1.55e+07 4.57e+07 4.27e+08 4.73e+08 1

3.0e+05 2.45e+07 1.53e+07 3.99e+07 4.08e+08 4.48e+08 4.0e+05 2.00e+07 1.51e+07 3.51e+07 3.91e+08 4.26e+08 5.0e+05 1.77e+07 1.50e+07 3.26e+07 3.81e+08 4.14e+08 6.0e+05 1.57e+07 1.49e+07 3.06e+07 3.72e+08 4.03e+08 7.0e+05 1.45e+07 1.48e+07 2.93e+07 3.66e+08 3.95e+08

NES&L DEPARTMENT lCcN NOJ CALCULATION SHEET PRELIM. CCN NO. N-1 PAGE MOF b CCN CONVERSION Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Suo-A CCN NO. CCN -

Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A. 63 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 INTEGRATED ENERGY FIG 2-4A TIME STEAM AIR VAPOR SUMP TOTAL (SEC) ( BTU ) (BTU) ( BTU ) ( BTU ) { BTU ) l l

8.0e+05 1.34e+07 1.47e+07 2.81e+07 3.61e+08 3.89e+08 1 I

9.0e+05 1.26e+07 1.47e+07 2.73e+07 3.56e+08 3.84e+08 l

1.0e+06 1.20e+07 1.46e+07 2.66e+07 3.52e+08 3.79e+08 1.5e+06 9.58e+06 1.45e+07 2.41e+07 3.42e+08 3.66e+08 2.0e+06 8.93e+06 1.44e+07 2.33e+07 3.29e+08 3.52e+08 2.5e+06 8.82e+06 1.44e+07 2.32e+07 3.21e+08 3.44e+08 3.0e+06 8.61e+06 1.44e+07 2.30e+07 3.14e+08 3.37e+08 1

4.0e+06 8.38e+06 1.43e+07 2.27e+07 2.99e+08 3.22e+08 5.0e+06 8.20e+06 1.43e+07 2.25e+07 2.92e+08 3.15e+08 6.0e+06 7.98e+06 1.43e+07 2.23e+07 2.85e+08 3.07e+08 7.0e+06 7.93e+06 1.43e+07 2.22e+07 2.82e+08 3.04e+08 8.0e+06 7.84e+06 1.43e+07 2.21e+07 2.78e+08 3.00e+08 9.0e+06 7.77e+06 1.43e+07 2.21e+07 2.75e+08 2.97e+08 1.0e+07 7.77e+06 1.43e+07 2.21e+07 2.71e+08 2.93e+08 i

i NES&L DEPARTMENT '

ICCN NOJ CALCULATION SHEET PREuM. CCN NO. N-1 PAGE OF bh Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Sun-A CCN CONVERSION l CCN NO. CCN -

Subject CONTAINMENTP/I' ANALYSIS for DESIGN BASIS LOCA Sheet No. A-64 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 10.2 (Continued)

Table for FIGURE 2-4B 1

Integrated Energy Content of the Containment Building Structural Heat Sinks;

, Integrated Energy Transferred out of the Containment through the ECUS and 4

4 Spray Heat Exchangers; and Integrated Energy transferred from the Vapor Region to the Containment Sump Water by the CSS i

}

INTEGRATED ENERGY TIME HEAT ECUS (AC) CONTAINMENT SPRAY SINKS SPRAYS HX (SEC) (BTU) (BTU) (BTU) (BTU) 1 0.1 3.92e-01 1 6.73e+06

2 3.01e+05 i

{ 3 6.85e+05 4 1.20e+06 l

1.83c+06 l 5 i

! 6 2.59e+06 7 3.47e+06 8 4.44e+06 9 5.51e+06 10 6.65e+06 M M NEW 41K) 0

NES&L DEPARTMENT ICCN NOJ I

CALCULATION SHEET eReuu. CCN NO. N.1 ,,oE 7'/og tw CCN CONVERSION Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4086426 Sun A CCN NO. CCN -

j Cubject SONTAINMENTP/r ANALYSIS for DESIGN BASISIDCA Sheet No. A-65 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 i l 3

INTEGRATED ENERGY FIG 2-4B j TIME HEAT ECUS (AC) CONTAINMENT SPRAY

SINKS SPRAYS HX

! (SEC) (BTU) (BTU) (BTU) (BTU) i i

11 7.85e+06

12 9.10e+06 13 1.04e+07 14 1.17e+07 i

~

15 1.30e+07 1 16 114e407 17 1.57e+07

18 1.70e+07 l 19 1.82e+07 20 1.94e+07 22 2.16e+07 24 2.35e+07 j 25 2.44e+07

)

2 26 2.53e+07 4

28 2.69e+07 i

30 2.83e+07 i

32 2.97e+07 f N& NN N 1

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PRELIM. CCN No. N-1 pf,og Yop 86 CCN CONVERSION CCN NO. CCN -

Prrject or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4086426-Sun-A Subject COfRAINME!WPfr ANALYSIS forDESIGN BASIS LOCA Sheet No. A-66 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 INTEGRATED ENERGY FIG 2-4B TIME NEAT ECUS (AC) CONTAINMENT SPRAY SINKS SPRAYS HX (SEC) (BTU) ( BTU ) (BTU) ( BTU )

33 3.03e+07 34 3.09e+07 36 3.22e+07 38 3.33e+07 40 3.44e+07 42 3.55e+07 44 3.66e+07 45 3.72e+07 46 3.77e+07 48 3.88e+07 50 3.98e+07 52 4.08e+07

)

54 4.18e+07 I

56 4.28e+07 58 4.37e+07 l 60 4.47e+07 2.16e+03 1 I

62 4.56e+07 4.55e+04 8.58e+04 K4 N NtVV 4/90 l

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET easuM. cCN NO. N-1 pros 7 6 cp 8 (o CCN CONVERSION Pr: ject or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080426-Sun-A CCN No. CCN -

Subject _COPfrAINMENTP/r ANALYSIS forDESIGN BASISIACA Sheet No. A-67 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 l INTEGRATED ENERGY FIG 2-4B TIME HEAT ECUS (AC) CONTAINMENT SPRAY i SINKS SPRAYS HX i

! (SEC) (BTU) (BTU) (BTU) -(BTU) 1 1 64 4.65e+07 8.88e+04 1.71e+05 1 j i 66 4.75e+07 1.32e+05 2.55e+05 68 4.83e+07 1.'76e+05 3.38e+05 I

70 4.92e+07 4.20e+05 4.20e+05 75 5.13e+07 3.28e+05 6.22e+05 80 5.33e+07 4.36e+05 8.19e+05 j 85 5.53e+07 5.46e+05 1.01e+06 90 5.71e+07 6.55e+05 1.20e+06 l 95 5.90e+07 7.65e+05 1.43e+06

]

100 6.07e+07 8.75e+05 1.58e+06 105 6.25e+07 9.86e+05 1.77e+06 t

110 6.42e+07 1.10e+06 1.96e+05

. 115 6.58e+07 1.21e+06 2.15e+06 4

} 120 6.74e+07 1.32e+06 2.34e+06

. 125 6.90e+07 1.43e+06 2.53e+06 i 130 7.05e+07 1.55e+06 2.72e+06 J

135 7.20e+07 1.66e+06 2.92e+06 M NW NM

NES&L DEPARTMENT ICCN NO/

CALCULATION SHEET PREUM. CCN NO. N-1 PAGE 770F b CCN CONVERSION I Pr: ject or DCP/MMP . SONGS UNITS 2 and 3 Calc No. N-4080426&m-A CCN NO. CM - f )

Subject CONTAINMENTP/r ANALYSIS for DESIGN BASIS LOCA Sheet No. A-68 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 INTEGRATED ENERGY FIG 2-4B TIME HEAT ECUS (AC) CONTAINMENT SPRAY SINKS SPRAYS HX (SEC) (BTU) (BTU) (BTU) (BTU) 140 7.35e+07 1.77e+06 3.11e+06 145 7.49e+07 1.89e+06 3.31e+06 150 7.64e+07 2.00e+06 3.50e+06 155 7.77e+07 2.12e+06 3.70e+06 160 7.91e+07 2.23e+06 3.89e+06 165 8.05e+07 2.35e+06 4.09e+06 l

170 8.18e+07 2.47e+06 4.29e+06 .

1 175 8.31e+07 2.58e+06 4.49e+06 180 8.43e+07 2.70e+06 4.98e+06 185 8.56e+07 2.82e+06 4.88e+06 190 8.68e+07 2.93e+06 5.08e+06 195 8.80e+07 3.06e+06 5.28e+06 200 8.92e+07 3.18e+06 5.48e+06 205 9.04e+07 3.30e+06 5.68e+06 210 9.16e+07 3.42e+06 5.88e+06 215 9.27e+07 3.54e+06 6.08e+06 220 9.38e+07 3.66e+06 6.29e+06

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PRELIM. ccN NO. N1 PAGE 7h OF bb CCN CONVERSION CCN NO. CCN -

Pr: Ject or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-486426 Suo-A Subject CONTAINMENTPfr ANALYSIS for DESIGN BASIS LOCA Sheet No. A- O REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 INTEGRATED ENERGY FIG 2-4B TIME HEAT ECUS (AC) CONTAINMENT SPRAY SINKS SPRAYS HX (SEC) (BTU) ( BTU ) ( BTU ) (BTU) 225 9.49e+07 3.78e+06 6.49e+06 230 9.60e+07 3.90e+06 6.69e+06 235 9.70e+07 4.02e+06 6.90e+06 240 9.80e+07 4.14e+06 7.10e+06 245 9.90e+07 4.26e+06 7.30e+06 259 1.00e+08 4.38e+06 7.50e+06 255 1.01e+08 4.50e+06 7.70e+06 260 1.02e+08 4.63e+06 7.91e+06 265 1.03e+08 4.75e+06 8.11e+06 270 1.04e+08 4.87e+06 8.31e+06 275 1.04e+08 4.99e+06 8.51e+06 280 1.05e+08 5.11e+06 8.72e+06 285 1.06e+08 5.23e+06 8.92e+06 290 1.07e+08 5.35e+06 9.72e+06 295 1.08e+08 5.47e+06 9.32e+06 300 1.08e+08 5.59e+06 9.53e+06 310 1.10e+08 5.83e+06 9.93e+06 Ak N NkVV 4/W0

l NES&L DEPARTMENT ICCN NOJ  !

CALCULATION SHEET PREUM. CCN No. N-1 PAGE N OF h CCN CONVERSION 1 I

Prrjoct or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4086426Sem-A CCN NO. CCN - l i Subject CONTAINMENTP/r ANALYSIS forDESIGN BASISIX)CA Sheet No. A-70 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 INTEGRATED ENERGY FIG 2-4B i

TIME HEAT ECUS (AC) CONTAINMENT SPRAY

! SINKS SPRAYS HX i (SEC) (BTU) (BTU) (BTU) (BTU) 4 320 1.11e+08 6.08e+06 1.03e+07 330 1.13e+08 6.32e+06 1.07e+07 340 1.14e+08 6.56e+06 1.11e+07 350 1.15e+08 6.80e+06 1.15e+07 400 1.21e+08 8.00e+06 1.35e+07 2

450 1.26e+08 9.19e+06 1.59e+07 i 500 1.30e+08 1.04e+07 1.75e+07 l l

) 550 1.34e+08 1.16e+07 1.95e+07

. l l 600 1.38e+08 1.27e+07 2.15e+07

) 700 1.44e+08 1.51e+07 2.55e+07 l 800 1.50e+08 1.74e+07 2.94e+07 900 1.55e+08 1.97e+07 3.33e+07 4

{ 1.0e+03 1.60e+08 2.20e+07 3.72e+07 1.le+03 1.64e+08 2.42e+07 4.10e+07

! 1.2e+03 1.68e+08 2.65e+07 4.49e+07 1.3e+03 1.72e+08 2.87e+07 4.87e+07 1.4e+03 1.75e+08 3.10e+07 5.25e+07 IO ME O

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET eReuu. CCN No. N-1 ,,os 8 00, a PrrJoct or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4088426 Sim A CCN CCN No.CONVERSION CCN - l Subject CONTAINMENTPfr ANALYSIS for DESIGN BASIS IACA Sheet No. A-71 REV ORIGINATOR DATE BRE DATE REV ORIGINATOR DATE BRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 INTEGRATED ENERGY FIG 2-4B TIME HEAT ECUS (AC) CONTAINMENT SPRAY  ;

SINKS SPRAYS HX l (SEC) (BTU) (BTU) (BTU) ( BTU )

1.5e+03 1.79e+08 3.32e+07 5.63e+07 l 1.6e+03 1.82e+08 3.53e+07 6.00e+07  ;

i 1.7e+03 1.85e+08 3.75e+07 6.38e+07 l

1.8e+03 1.87e+08 3.97e+07 6.75e+07 1.9e+03 1.90e+08 4.18e+07 7.12e+07 l 2.0e+03 1.92e+08 4.40e+07 7.49e+07 I 2.le+03 1.95e+08 4.72e+07 7.86e+07 2.2e+03 1.97e+08 4.82e+07 8.22e+07 2.3e+03 1.99e+08 5.03e+07 8.59e+07 1.71e+05 2.4e+03 2.02e+08 5.34e+07 8.95e+07 1.32e+06 2.5e+03 2.04e+08 5.44e+07 9.31e+07 2.49e+06 1 2.6e+03 2.06e+08 5.65e+07 9.67e+07 3.68e+06 2.7e+03 2.08e+08 5.85e+07 1.02e+08 4.89e+06 2.8e+03 2.10e+08 6.06e+07 1.03e+08 6.12e+06 2.9e+03 2.11e+08 6.26e+07 1.09e+08 7.37e+06 .

3.0e+03 2.13e+08 6.46e+07 1.10e+08 8.63e+06 3.5e+03 2.21e+08 7.45e+07 1.28e+08 1.52e+07 u - =w.w

NES&L DEPARTMENT lecN NOJ CALCULATION SHEET PREuu. ecN NO. N-1 pAoE 8l OF h CCN CONVERSION Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Sun-A CCN NO. CCN -

3 Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A- 72 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE l ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 INTEGRATED ENERGY FIG 2-4B I I

TIME HEAT ECUS (AC) CONTAINMENT SPRAY SINKS SPRAYS HX 1 (SEC) (BTU) ( BTU ) (BTU) (BTU) y 0

}

a 4.0e+03 2.29e+08 8.42e+07 1.44e+08 2.?"# *

~~

8.0e+03 2.66e+08 1.54e+08 2.57e+08 i

9.0e+03 2.73e+08 1.61e+08 2.80e+08 1.06e+0b ~

, 1.0e+04 2.79e+08 1.85e+08 3.02e+08 1.25e+08 1.5e+04 3.05e+08 2.57e+08 4.02e+08 2.23e+08 2.0e+04 3.27e+08 3.24e+08 4.92e+08 3.24e+08

{ 4.0e+04 3.86e+08 5.62e+08 8.08e+08 7.13e+08

6.0e+04 4.15e+08 7.63e+08 1.08e+09 1.07e+09 9.0e+04 4.38e+08 1.02e+09 1.43e+09 1.54e+09

{  :

1.0e+05 4.34e+08 1.09e+09 1.53e+09 1.69e+09 2.0e+05 4.14e+08 1.62e+09 2.32e+09 3.22e+09 f

3.0e+05 4.03e+08 2.02e+09 2.92e+09 4.02e+09 4.0e+05 3.79e+08 2.32e+09 3.40e+09 5.01e+09 1 5.0e+05 3.54e+08 2.56e+09 3.76e+09 5.91e+09

6.0e+05 3.31e+08 2.77e+09 4.05e+09 6.75e+09 i

i 7.0e+05_ 3.11e+08 2.93e+09 4.27e+09 7.55e+09 8.0e+05 2.93e+08 3.08e+09 4.45e+09 8.32e+09

- N

s, NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PREuu. CCN NO. N-1 proE 62or4 CCN CONVERSION Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080426-Suo-A CCN No. CCN - f Sub!N:t CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A- 73 S REV ORIGINATOR DATE lRE DATE REV ORIGINATOR DATE 1RE DATE g AuEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 l

l INTEGRATED ENERGY FIG 2-4B )

i I TIME HEAT ECUS (/s) CONTAINMENT SPRAY SINKS SPRAYS HX (SEC) (BTU) ( BTU ) ( BTU ) ( BTU )

e 9.0e+05 2.78e+08 3.20e+09 4.59e+09 9.06e+09 l

1.0e+06 2.66e+08 3.31e+09 4.88e+09 9.77e439 2.38e+08 1.5e+06 3.70e+09 4.69e+09 1.31e+10 I

2.0e4'f 2.25e+08 3.89e+09 4.88e+09 1.62e+10 2.5e+06 2.27e+08 4.04e+09 4.78e+09 1.S!e+10 3.0e+06 2.30e+08 4.16e+09 4.6Fe509 ~2.14e+10 4.0e+06 2.39e+08 4.36e+09 A.T5e+09 2.57e+10 5.0e+06 2.75e+08 4.48e+09 4.22e+09 3.12e+10

- 6.0e+06 2.91e+08 4.53e+09 4.01e+09 3.28e+10 4

7.0e+06 3.31e+08 4.57e+09 3.97e+09 3.58e+10 )

8.0e+06 3.79e+08 4.67e+09 3.92e+09 3.86e+10 ,

t.

I 9.0e+06 4.04e+08 4.69e+09 3.85e+09 4.00e+10 1.0'e+07 4.58e+08 4.69e+09 3.82e+09 4.25e+10 i

i i

l l

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PREUM. CCN NO. N-1 PAGEh30F

' CCN CONVERSION Project or DCP/MMP SONGS UNITS 2 and 3 Cale No. N-4080-026-Suo-A CCN NO. CCN -

Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A- 74 ___ _

REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE BRE DATE AllIN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 10.2 (Continued) l Table for FIGURE 2-6 CCW Heat Load from 1 Train of ECUS (2 ECUS) and Spray-Hx and Combined Total l

HEAT RATES TIME ECUS (AC) SPRAY AC+ SPRAY (SEC) ( BTU /HR ) ( BTU /HR ) ( BTU /HR )

6.0e+01 7.79e+07 7.79e+07 l

1.0e+02 7.95e+07 7.95e+07 l

3.0e+02 8.70e+07 8.70e+07 5.Ge+02 8.54e+07 8.54e+07 6.0e+02 8.49e+07 8.49e+07 7.0e+02 8.40e+07 8.40e+07 8.0e+02 8.31e+07 8.31e+07 4

9.0e+02 8.26e+07 8.26e+07 1.0e+03 8.17e+07 8.17e+07 2.0e+03 7.67e+07 7.67e+07

~

2.3e+03 7.51e+07 4.11e+07 1.162e+08 2.5e+03 7.42e+07 4.25e+07 1.167e+08 2.6e+03 7.39e+07 4.32e+07 1.171e+08 2.7e+03 7.31e+07 4.45e+07 1.176e+08 m um

• l NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PREUM. CCN No. N-1 PAGE bYOF h CCN CONVERSON Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Suo-A CCN No. CCN - f Subject CONTAINMENTP/T ANALYSIS for DESIGN BASIS LOCA Sheet No. A-75 __

REM~ ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 HEAT RATES TIME ECUS (AC) SPRAY AC+ SPRAY (SEC) ( BTU /HR ) ( BTU /HR ) (BTU /HR) 1 l

3.0e+03 7.23e+07 4.58e+07 1.181e+08 l 4.0e+03 6.86e+07 5.14e+07 1.200e+08 l

1 i 6.0e+03 6.24e+07 5.93e+07 1.217e+08

, 8.0e+03 5.77e+07 6.48e+07 1.225e+08 1.0e+04 5.44e+07 6.84e+07 1.228e+08 1.5e+04 5.01e+07 7.21e+07 1.222e+08 i

j 2.0e+04 4.71e+07 7.26e+07 1.197e+08 1

3.0e+04 4.30e+07 7.03e+07 1.133e+08 l

4.0e+04 3.90e+07 6.69e+07 1.059e+08 5.0e+04 3.60e+07 6.34e+07 9.94e+07 6.0e+04 3.35e+07 6.05e+07 9.40e+07

'7.0e+04 3.15e+07 5.81e+07 8.96e+07 8.0e+04 2.99e+07 5.62e+07 8.61e+07 9.0e+04 2.63e+07 5.43e+07 8.06e+07 1.0e+05 2.37e+07 5.12e+07 7.50e+07 ,

2.0e+05 1.60e+07 4.13e+07 5.72e+07 3.0e+05 1.25e+07 3.71e+07 4.96e+07

)

amm .-

, NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET rREuu. CCN uo. N., e,oes/Oga, CCN CONVERSION l Project or DCP/MMP SONGS UNITS 2 and 3 Calc No. N-4080-026-Suo-A CCN NO. CCN - f

Subject CONTAINMENTPTT ANALYSIS for DESIGN BASIS LOCA __ Sheet No. A-76 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 W

HEAT RATES l TIME ECUS (AC) SPRAY AC+ SPRAY (SEC) ( BTU /HR ) ( BTU /HR ) ( BTU /HR )

4.0e+05 9.62e+06 3.36e+07 4.32e+07 5.0e+05 7.94e+06 3.14e+07 3.93e+07 6.0e+05 6.49e+06 2.95e+07 3.60e+07 7.0e+05 5.54e+06 2.82e+07 3.38e+07 8.0e+05 4.75e+06 2.71e+07 3.18e+07 9.0e+05 4.17e+06 2.61e+07 3.03e+07 1.0e+06 3.61e+06 2.53e+07 2.90e+07 1.5e+06 1.75e+06 2.31e+07 2.49e+07 2.0e+06 1.13e+06 2.03e+07 2.14e+07 3.0e+06 8.18e+05 1.73e+07 1.81e+07 4.0e+06 5.72e+05 1.42e+07 1.48e+07 5.0e+06 4.60e+05 1.34e+07 1.39e+07  ;

l

., 6.0e+06 3.09e405 1.20e+07 1.23e+07 7.0e+06 1.85e+05 1.09e+07 1.11e+07 8.0e+U6 6.69e+04 9.83e+06 9.89e+06 i 9.0e+06 1.70e+01 9.14e+06 9.14e+06  !

'i 1.0e+07 1.53e+01 8.38e+06 8.38e+06 l

~ ~ ~ l l

l

NES&L DEPARTMENT ICCN NOJ CALCULATION SHEET PREUM. CCN NO. N-1 PAGE hh0F h CCN CONVERSION l Project or DCP/MMP SONGS UNrrS 2 and 3 Calc No. N-4080-026-Suo-A CCN No. CCN -

l j Subject CONK'MENTP/r ANALYSIS for DESIGN BASIS LOCA Sheet No. A- 77 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE ALLEN EVINAY 01/31/95 PAUL BARBOUR 02/03/95 l

1 f APPENDIX A (COPATTA Code I/O File) l The C0PATTA Code input files are presented in Section 9 of this calculation.

, The COPATTA Code output files are included on Microfiche. The output files j name and date are as follows:

FICHE TITLE : DBLOCA J2732 13-Jan-95 JOB TITLE  :

• DBLOCA+ LOP (DESLS), cpi =0.0 psig, MAX SI, CSS =1600/1950

gpm, ECUS 060s

! 12-12-94 RUN DATE  : 21:08:39 GMT LAST SHEET : Page 512 a

i FICHE TITLE : TSLOCA J2745 13-Jan-95 i

JOB TITLE  :

• TSLOCA+ LOP (DESLS), cpi =1.5 psig, MAX SI, CSS =1600/1950 gpm, ECUS 060s RUN DATE  : 12-23-94 00:38:52 GMT LAST SHEET : Page 512 a

s

CALCULATION TITLE PAGE g,"c'cuuo.

moE _ or _

CCN CONVER$10N; Calc. No. N-4080-026 DCP/MMP/FIDCN/FCN No. & Rev. N/A ccN No. CCN Subject CONTAINMENT P/T ANALYSIS FOR DESIGN BASIS LOCA Sheet i SystIm Number / Primary Station System Desig r -BE-96 / XBI ' BBB SONGS Unit 2&3 Q-Class II*

1. lao I Tach Spec Affecting? NO X YES, Sebion No. B3.6.1.4 Equipment Tag No. N/A i

~

PROGRAM / DATABASE NAME(S)

] PROGRAM VERSION / RELEASE NO(S).

COMPUTER X ALSO USTED BELoW FROGRAM/ DATABASE DATABASE IN ACCoRDANCE WITH NES&L 416-1 ' DECAY' MAP,121 Version 01

'COPATTA' MAP-175 Version G1/14 RECORD OF ISSUES REV. TOTAL SHTS PREPARED APPROVED DISC LAST (Print name/ initial) (Signature)

I SHT.

O SEE NOTE I BELOW 217 ORIG t

• other ggs ISSUED FOR USE R. Nakano /JAl i

.._BPC N. 217 IRE DM DATE J. Elliott l - 2. t3 - 9 4-

, ORIG / GS other IRE DM DATE orig GS 1 other i ... . .-- ... --._..... . -- . _ -_ .

ORIG GS other

, lpace for RPE stamp, identify use of an alternete calc., and notes as applicable.

Discidmer: This calculation was prepared using Word Perfect 5.1 software. However, WP 5.1 was not used for any computations in the calculation.

• Containment isolation valves, penetrations, and heat removal systems are QC-II per the Songs 2,3 Q-List (CDM 90034)

Note ).

The purpose of Revision 0 is to resolve OIRs91-072,92-046 and 92-058 which state that inconsistencies found in Calculation N-4080@2 need to be corrected.

O This csic. was prepared for the sdentified DCP/MMP. DCP completion and turnover acceptance to be venfied by reciept of a memorandum diracting DCN conversion. Upon receipt, this calc. represents the as-budt condition. Memo date by

CALCULATION CROSS INDEX '

" "ScN No.

I PA. OP CCN CONVERSION:

Calculation No. N-4080-026 Sheet No. 2 CCN No. CCN-INPUTS OUTPUTS Does the Calc. rev. These interfacing calculations and/or Resuhs and conclusions of the subject output interface number and documents provide input to the subject calculation are used in thc.ie interfacing calc / document Identify output interface responsible calculation, and if revised may require calculations and/or documents. require revision 7 calc / document CCN, DCN supervisor revision of the subject calculation.

TCNIRev. or FIDCN initials and - - - '

date Calc / Document No. Rev. No. Calc / Document No. Rev. No. IES/NO O Calculation C-257-1.06 I l Units 2&3 UFSAR 9 YES UFSAR Change Request No.

g Calculation M-0014409 0 i SAR23-278 '

3 Calculation M4026001 5 DBD-SO23-TR-AA 0 nman AIB ~W-ed Calculation M-0026402 1 DBD-SO23-TR-EQ A o#As %%,%-o%,Q~o'J8 Calculation M-0072436 0 DBD-SO23-400 0 NaboTan Actiou aciWQ-of Calculation N-0880415 0 g% mon C A Calculation N-4080-002 1 SONGS Unit 2 Technical Specifications A.108 Calculation N-4080-003 5 B3.6.1.4 (page B3/4 6-2, Amend.16)

Calculation N-4080 005 0 M g4g Calculation N-0240406 0 SONGS Urit 3 Technical Specifications A. 97 l B3.6.1.4 (page B3/4 6-2, Orig Issue) s Unit 2 Operating License and Technical Specs Amend.108 LCO 3.6.1.4 (page 3/4 6-7, Orig issue) Calculation N-4080002 1 NcDoTM Nbg co$

LCO 3.6.1.5 (page 3/4 6-8, Orig issue)

Sect. 5.2.2 (page 5-1. Amend. (Orig issue) EDQP M37600 Unit 3 Operating License and Technical Specs Amend. 97 EDQP M37601 LCO 3.6.1.4 (page 3/4 6-7, orig Issue) EDQP M37606 LCO 3.6.1.5 (page 3/4 6-8, Orig Issue) EDQP M37607 g e cction 5.2.2 (page 5-1, Orig Issue) EDQP M37608

• Units 2&3 UFSAR 9 EDQP M37609 EDQP M37612 DBD-SO23-400 0 EDQP M37615 ygggK DBD-SO23-TR-EQ A EDQP M37618 qyq EDQP M37619 SD-SO23 360 2 EDQP M37620 SD4023-390 1 EDQP M37621 SD-SO23-400 2 EDQP M37624 SD-SO23 720 1 EDQP M37629 .

SD-SO23-740 3 EDQP M37631 )

EDQP M37635 EDQP M37636

}

CALCULATION CROSS INDEX "uncN No. P.ee eP CCN CONVERSION:

Calculation No. N-4080-026 Sheet No. 3 CCN NO. CCN-INPUTS OUTPUTS Does the Calc. rev. These interfacing calculations and/or esults an conclus of me subject output interface number and documents provide input to the subject calculati n are used in these interfacing calc / document identify output interface responsible calculation, and if revised may require calculates and/or docurnents. mguire revision? calc / document CCN, DCN supervisor revision of the subject calculation.

TCN/Rev. or FIDCN initials and ---

date Calc / Document No. Rev. No. Calc / Document No. Rev No. YES/NO j.g.g PalD 40lll A P&lD 40ll4A 26 10 EDQP M37640 ygp ~

EDQP M37641 P&lD 40!!4B 14 EDQP M37644 P&ID 41072A 7 EDQP M37646 EDQP M37703 EQ Condition Monitoring Program Assessment Manh 1988 EDQP M37704 EDQP M37705 Sol 23-XXIV-37.26.12 0 (PCN 0-1) EDQP M37706 EDQP M38279 NCR 93030001 EDQP M38290 NCR 93030002 EDQP M38377 NCR 93030003 EDQP M38378 gg NCR 93030004 EDQP M38379 f-EDQP M38381 b qp,q EDQP M38382 EDQP M38383 EDQP M38384 g f,p.y EDQP M38385 EDQP M38773 EDQP M38785 EDQP M38789 EDQP M38790 EDQP M33798 EDQP M39079 EDQP M40819 EDQP M35083 i EDQP M85091 EDQP M85102 (

t NES&L DEPARTMENT CALCULATION SHEET 'oc" " '

PRELIM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN No. CCN -

Subject _Qn.ntainment P/T Analvsis for Desian Basis LOCA Sheet No. 4 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R E

O R. Nakano 01/18/94 J. Elliott 01/20/94 y 5

i TABLE OF CONTENTS CALCULATION COVER SHEET ............................... 1 CALCULATION CROSS INDEX . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1 TABLE OF CONTENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 1

PURPOSE............................................... 5 1.1 TASK DESCRIPTION .................................... 5 1.2 CRITERIA, CODES AND STANDARDS ........................ 6 2 RESULTS/ CONCLUSIONS AND RECOMMENDATIONS , . . . . . . . . . . . . . . . 8 2.1 RESULTS/ CONCLUSIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 2.2 RECOMMENDATIONS ..................................16 3 AS SUMPTIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 4 DESI G N INPUT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 3 5 METHODOLOGY . . . . . . . . . . . . . . . . . .......................79 6 REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 80 7 NOMENCLATURE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 85 8 CALCULATION .........................................86 8.1 COPATTA CODE INPUT DATA ............................. 86 8.2 COPATTA CODE INPUT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 171 8.3 COPATTA CODE OUTPUT .............................. 179 8.4 MASS AND ENERGY BALANCES . . . . . . . . . . . . . . . . . . . . . . . . . . 207 9 COPIES OF MISCELLANEOUS REFERENCES . ...................214 APPENDIX A (COPATTA Code I/O File Information) . . . . ....... ... ... 217

_ J

l NES&L DEPARTMENT t CALCULATION SHEET 'cc" " d PRELIM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 5 l REV ORIGINATOR \

DATE IRE DATE REV ORIGINATOR DATE IRE DATE R l 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

S 1 PURPOSE 1.1 TASK DESCRIFFION The purpose of this calculation is to evaluate the contamment pressure and temperature response to a design basis Irss-of-Coolant-Accident (LOCA) for SONGS Units 2 and 3.

The results of this calculation supersede the results of Calculatior N-4080-002, " Containment l Press-Temp Transient Analysis", (Reference 6.1.g) with respect only to the Design Basis 2 l LOCA event (9.8175 ft Double Ended Suction Leg Slot (DESLS) Break with maximum safety injection flow). Per the conclusions presented in Calculation N-4080-002, this is the worst case LOCA, and will envelope all the other break types. The changes in design input and assumptions used in this calculation will not alter the relative severity of the different break scenarios, and thus the DESLSB will remain the limiting case. I In this calculation, both the short term and the long term effects of a pressure-temperature transient due to a desiga br. sis LOCA with a loss of offsite power (LOP) will be evaluated.

The design basis LOCA is being revised to resolve inadequacies in the original analysis identified in the following Open Item Reports:

91-072 Calculation N-4080-002 (Reference 6.1.g) uses a containment liner to concrete conducrance of 100 BTU /h-ft2 "F which is non conservative.

This calculation uses a conservative interface conductance of 50 BTU /h-ft2 .op given in BN-TOP-3 (Reference 6.11) (See Design Input Item 4.13).92-046 Calculation N-4080-002 used input that did not have proper references or justifications.

This calculation provides references for all design inputs and justifications for l

all assumptions.  ;92-058 The RWST volume modeled in Calculation N-4080-002 gave non-conservative j results This calculation models an RWST volume that will give conservative results l (See Design Input Item 4.10.b.1) l l

l

~

l b

l NES&L DEPARTMENT CALCULATION SHEET 'cc" " >

PRELIM. CCN NO. PAGE OF i Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 6 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 E 4

v 5

1 This calculation also addresses the reduced Containment Spray flowrates as described in disposition step 2 of NCRs 93030001,93030002,93030003, and 93030004.

(References 6.19). This calculation incorporates the minimum spray flow identified in Calculation M-0014-009 (Reference 6.1.b). i

-l The Bechtel Standard Computer Code MAP-175, Release Gl-14 (COPATTA) will be used in this calculation to evaluate the pressure-temperature transient.

J 1.2 CRITERIA, CODES AND STANDARDS The containment stmeture is to be designed such that it is capable of withstanding the adverse effects of a postulated LOCA. Applicable regulatory design criteria are provided in l Appendix A to 10 CFR Part 50 (Reference 6.4.a). These criteria include: '

l e General Design Criterion 16, " Containment Design" i

e General Design Criterion 38, " Containment Heat Removal" e General Design Criterion 50, "Contamment Design Basis" i

General Design Criterion 16 requires that a reactor containment and associated systems shall be provided to establish an essentially leak tight barrier to assure that the containment design conditions important to safety are not exceeded for as long as the conditions require. Per Standard Review Plan 6.2.1.1.A (Reference 6.4.c), to satisfy the requirements of this criterion, the calculated containment peak pressure after a LOCA should be less than the l design containment peak pmssure.

General Design Criterion 38 requires that the containment heat removal systems function to rapidly reduce the containment pressure following any LOCA, and maintain the pressure at an acceptably low level. Per Standard Review Plan 6.2.1.1.A, to satisfy the requirements of this criterion requires an analysis to show that the containment pressure can be reduced to less than fifty percent of the containment peak pressure within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the start of the LOCA.

General Design Criterion 50 requires that the reactor containment stmeture, including access openings, penetrations, and the containment heat removal system, shall be designed so that the contamment structure and its internal components can accommodate, without exceeding the design leakage rate and with sufficient margin, the calculated pressure condition resulting from a LOCA. As with Criterion 16, per Standard Review Plan 6.2.1.1.A, to satisfy the requirements of Criterion 50, the calculated containment peak pressure after a LOCA should be less than the design containment peak pressure.

J

NES&L DEPARTMENT CALCULATION SHEET 'cc" " '

PRELIM. CCN No. PAGE_ OF_

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSloN:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 7 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 "

5 The containment design pressure is 60 psig and the containment design temperature is 300 *F per the Technical Specifications (References 6.3.a & b, Section 5.2.2).

NES&L DEPARTMENT CALCULATION SHEET l',7gjgc,ac. ,,c, c, Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CoNVERSloN:

cCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 8 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 5

2 RESULTS/ CONCLUSIONS AND RECOMMENDATIONS 2.1 RESULTS/ CONCLUSIONS The purpose of this calculation has been to evaluate the short and long term effects of the containment pressure-temperature transient resulting from a design basis LOCA with a loss of offsite power.

Figure 2-1 presents the containment gauge pressure versus time for the DBA LOCA. The plot in Figum 2-1 is generated using the data pmsented in Table 8.3-1.

Figure 2-2 presents the sump and vapor temperatures versus time for the DBA LOCA. The plots in Figure 2-2 are generated using the data presented in Table 8.3-1.

Figure 2-3 presents the condensing heat transfer coefficient used by the COPA'ITA Code versus time for the DBA LOCA. The plot in Figure 2-3 is generated using the data presented in Table 8.3-1.

Figures 2-4A and 2-4B present the energy content of a number of different components of the LOCA model versus time for the DBA LOCA. The plots in Figures 2-4A and 2-4B are generated using the data pmsented in Table 8.3-2. For further discussion on heat sink energies, refer to Section 8.3.2.

Figure 2-5 presents surface temperatures versus time for five heat sinks for the DBA LOCA.

The plots in Figure 2-5 are generated using the data presented in Table 8.3-3. The heat sink data plotted is for the following heat sinks:

HS 2 Containment Building Cylinder above grade HS 8 Lined refueling canal walls HS 9 Steam Generator compartment walls, unlined refueling canal walls & other internal walls HS 15 Miscellaneous carbon steel: thickness < 0.5" HS 16 Electrical equipment Figures 2-1 and 2-2 show that the containment peak pressure (56.9 psig) is below the design pressure of 60 psig and the peak vapor temperature (294 *F) is below the design temperature of 300 *F. Therefore, General Design Criteria 16 and 50 (See Section 1.2) are met. The containment pressure at 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (86400 seconds) is less than 12.5 psig (the pressure from the COPATTA output at 80000 seconds). This is considerably less than half of the peak pressure. Therefore, General Design Criterion 38 (See Section 1.2) is also met.

NES&L DEPARTMENT CALCULATION SHEET '

'cc" ". CCM NO.

PRELIM PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CcN CONVERSION- l CCN No. CCN - l Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 9 REV ORIGINATOR DATE l IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 4

l Table 2-1 presents the accident chronology for the DBA LOCA.

Table 2-1 l

ACCIDENT CHRONOLOGY FOR THE DBA LOCA (DESLS) I l

TIME EVENT 4+%nds) 0.0 Break occurs 17 Peak containment pressure during blowdown phase 22.0 End of Blowdown 22.0 Start of Emergency Core Cooling injection phase 22.0 Start of Core Reflood 35 Start of air cooler fans 60 MAXIMUM CONTAINMENT TEMPERATURE (294 *F) 4 60 Start of Containment Spray injection phase 211.1 End of Core Renood 211.1 Start of Post-Reflood 241 MAXIMUM CONTAINMENT PRESSURE (56.9 psig) 573.273 End of Post-Reflood 573.273 End of CE-provided mass and energy release data 573.273 Stan of COPATTA Code mass and energy release calculations 2280 End of Emergency Core Cooling injection phase 2280 Start of Emergency Core Cooling recirculation phase 2280 End of Containment Spray injection phase 2280 Start of Containment Spray recirculation phase 7200 HPSI realigned to a 50:50 spht between hot and cold leg injection 10' End of COPATTA Code Calculations

]

m E 'P o 2 E

' {-

^

8 a

-" g n R Z o a 8 y z - n 8 5 E- 2 O FIGURE 2-1 o g a E LOCA WITH LOP - CONTAINMENT PRESSURE a

3 I >

o i

q m

o Om rZ 70 _

" "; E w

m 3

5Cy y)

F

Max Press = 56.9 psig at 241 sec  : E --

c u 5- E-

"4' ) m{

S.5 60 -

m o M S

E , O m>

tu 8 R 2 e.

a ZHE

[ 50 - --

8 CD m

@ g Id m

<o  :  : e o s. n tu 40 - -- ~ c = m T -

$ 5 0 9 d q -

g m g g

~

~

A P k

4 30 -

2 Z

A W _

_- Q O 2 - -

8 Z - -

6

< 20 -

_g m m

p O

ga mO

_- g cz O 10 - 2 g  !!

O -

9 o aa zz =

O D *"

m P@

1e-01 1 e+00 1 e+01 1 e+02 1 e+03 1 e+04 1 e+05 1 e+O6 1 e+07 g5 zy U) I O ,

TIME FOLLOWING BREAK (seconds) 5 iif E 2 =

z l 0 o m

> a l 3 m O l4=<mz

=  ? A 2 go %

x ~ a g n R z

cu o

o a O r m -

FIGURE 2-2 LOCA WITH LOP - TEMPERATURE

$ g 3

[

8

@oO E D m

VAPOR SUtvP o m m r Z TEMP TEW $ o 4 O $

m - > o C, a m B m F r-350 ", - ", - ", ", ", - ... i . -

5 ED0

. Max Vapor Temp = 294 F at 60 sec F m-x

" 4mT m

O k

- Max Sump Temp = 249 F at 28 sec e' 2 $g

" a n g a 300 - -

g' mm 1H z E -

F o,

e.

. o m Lij -

~ 0 r- 92.

I 250 -

.-s -

E 8 9 d J '/ N -

e $ > z F

• P N'-sg

<t .. . - .. --- , -

. . z g

N /' ,,,, -

Q o 200 -

\ / -

8 N / s 6

. N / \ .

o to ll)

H _

N/ 'ss _

a e

m ;g a m o .

N -

CZ 150 -

• F5 7 g:

s --s'N S

. . Z

s. oo z

" O gz O 100 '

-E e o<

1e-01 1 e+00 1 e+01 1 e+02 1 e+03 1 e+04 1 e+05 1 e+O6 1 e+07 09 ze x

m 7

1 g ,>

TIME FOLLOWING BREAK (seconds)

• 2

- ,S z I o

- on

> a l m

4= < m :p

=  ?  ?

o 2 2 @

E S x

Z g o R 5 8 o r

W s) " o U

Q 3 4 3  %

FIGURE 2-3 9 l ' F

~

Ey LOCA WITH LOP - CONDENSING HTC o a

o o Om z m

300 -

"m ", . " , . " " , . ", . " " , - ""m - "

- g m

j 5C$

W Fp

- Max HTC = 256 BTU /hr-f t _p 2 _

w y g )l- -mgv p a- g' 250 - -

m R "O>

~

~

- $ =  ?

e.

$Z U' E

u. - -

g (/) m el 200 - -

m "E 5 0 - -

o E. m 1 - -

t o  ? Em H E - -

8 3 o P 3

H 150 -

9 y

' Z CD - -

=

~ u Q o U 100 - -

?

k - - o I m

- 9 m os can e

g z 50 - -

8 F8

- - g gu

- - z oo z o hh 9 0 4 ft1 zo O 7 1e-01 1 e+00 1 e+01 1 e+02 1 e+03 1 e+04 1 e+05 1 e+O6 1 e+07 n o9 ze TIME FOLLOWING BREAK (seconds) m 9 'E s

$ 8 z  !

o e

i l

M M

.<m=

J

n T T Q 2.

e  %

x o

~ 2 o o 2 E o o 3 o w

. m e

- n

> a FIGURE 2-4A 3 q o a a N E Q LOCA WITH LOP - ENERGY

= m 3 Io >

VAPOR SLMP ----- TOTAL oa o

i q

br O

zm 3 z m 5 > o Cme ,

= m F B a r-1e+10 3

. . . . " , . .."."i . . . . . , . . . . . , .

........ . . . . . , .....~.. . . . . " . .

• i  ?>a 5 g a- g --i mU m o M O >o m p 1e+O9 r , 8 2 2 a 2 -i g

~__ -------  : e.

} _,,,,._ p

___Crnen

-- - o g

,/- ' ' ,. - _

y 1 -4 m

3 1e+O8 _r -

9 o F-  :

/'

-______ i

s o 5-

,_ am 00

o -3 O o

P --l 3A > 2 o

1e+07  :

r ,- ,

Z L') /

g-  :  : = u

' Q o

_- 03 o

uJ 1e+06 7' , 6 u

: g o ;g a e m o z CZ s: z 1e+05 r , g 0 2

!  ! 9 gg 2 g zz 9 58z 1e+04 ' ' ' ' " " ' ' ' ' ' " " ' ' ' ' ' " " ' ' ""

d 1e-01 1e+OO 1e+01 1 e+02 1 e+03 1 e+04 1 e+05 1 e+O6 1 e+07 gg ze m I o i TIME FOLLOWING BREAK (seconds) R ii*  !;

=

z l 0

- on

> a l N O due aC m 2 k________.____ __ _ _ __ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

'E '?

o m 2 E. j-8 a n -

• g n R

5 8 o x

u ~.

n e o a .ie o ~

Q FIGURE 2-48 e 3 E LOCA WITH LOP - ENERGY

3 I

HEAT HEAT ----- CONT AIR o

i q

m O %J m r2 XCHNGR SPRAY CLR D E Z sirKS m - > o C C/) e 65 m

a m r r-a r c a 1e+11 - -

"i - - - - - - -

i l y) mm 1e+10 r

',, ' 3 -

-e m

• O>

u Z $

1 8: _ o a "

g g g

1. ,,g -===-~=; .

1e+O9 r j

1 E

@E-4 Z

5 -

?

/,4;^c.# m y.

e.

- o D 1e+O8 H

r ,/ 1 e g

o

=

Dm 5' y m

E

, 5 s ,3,,

5 o

~

1e+07 r g' / 1 T > Z

>  ! 4 I [  !

z

/

h 1e+O6 r 1

W -

/ )

2 o

fu 1e+05 r / ,/

il 1

9 e

N m ,a an 1e+04 r 1 E

w E" O

.o aq a n 1e+03 r z a no E

o y 22 9 1e+02 ' ' ' " " ' ' ' ' ' " " ' ' ' ' ' " " ' ' ' ' ' " " ' ' ' ' ' " " ' ' ' ' ' " "

M 5o

- z 1e-01 1 e+00 1 e+01 1 e+02 1 e+03 1 e+04 1e+05 1e+06 1 e+07 Rg ze m '* ,

. TIME FOLLOWING BREAK (seconds)  ! iii  !;

2 =

z l

-O o

, p

> a l Y b

&<ma

w. _ _. ._ _. _. . - _ _

1

=  ?  ?

3 e- e-e e O O x -

• 8 a R 5 8 o E I E. O FIGURE 2-5 LOCA WITH LOP - HEAT SINK SURFACE TEMP HS 2 HS 8 ----- HS 9 g3 15 HS 16 o N  !!> z m m P C o 4 O Om a

g m 5 > 5Cy' a r g-300 . . . . . . . , ......,,i , . . . . . . . . . . . . . . . . , . , . , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , ,

A <

o, C

a >c GHm u li>*

fr'N_.

m  ? m ~$

Ox r* , -? -/ . ,-

'%: . 8 _

o na

//

\:.

• A 8 "

E&

0) m 250 -

'\,

5' lh /f'\.7 \

o E'

m Ik o

w // 5-i i:.

' x. n o -

e. m i 1 o H J / /

s.

o B "

4 9

P z

H i

• 9

< 200 - i / -

z T l sll il 2 6 w /

2 o 03 O.

1 /

/ l ll i i 9 o

N H '

/

/ $i i i i !

9 e

"m-CD mn ,

150 -

/  : :

ll

\

\

z rz '

/

/

!/ \ 3 -gz o

/ '/ \ o

, gu g

/ .-. - C .. z

\ oo z oo

• • P E

y zo

' ' ' " ' ' - '"' . . ~ ~ . ' ......... . . . . . . . . , - . ......i ........

100 . . . . . . . . ,

1e-01 1 e+00 1 e+01 1 e+02 1 e+03 1 e+04 1 e+05 1 e+O6 .1 e+O7 ze .

Y -

A TIME FOLLOWING BREAK (seconds)  !!! .

• =

z l 9 o O

> a a w 4=<mm

NES&L DEPARTMENT l CALCULATION SHEET 'cc" " '

PRELIM. CCN NO. PAGE OF

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

ccN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 16 i

. REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

y 5

l i 2.2 RECOMMENDATIONS Since this calculation is the new record of analysis for the Design Basis LOCA Pressure-

! Temperature Analysis, it should be noted in Calculation N-4080-002 that the results of the DESLSB case (Case 1 of page 6 of Reference 6.1.g) have been superseded by the results of

{ this calculation.

In addition, all documents identified on the output side of the Calculation Cross Index Table should be reviewed to assess if this analysis has any impact on them.

NES&L DEPARTMENT CALCULATION SHEET 'cc"os PRELIM. CCN No. PAG E__, oF_

l Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSloN:

CCN No. CCN -

k Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 17 1

REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R l l 0 R. Nakano 01/18/94 J. Elliott 01/20/94

^

h S

3 ASSUMPTIONS )

1 l

' This section presents the assumptions that are used in this calculation. The assumptions are arranged in groups which parallel the Card Series data input employed by the COPATTA l

Code (Reference 6.5.b).

3.1 CARD SERIES 1

a. ITEM 6: INITIAL CONTAINMENT RELATIVE HUMIDITY l

l

' The initial relative humidity inside the containment is assumed to be 60 percent. The COPATTA Code User's Manual (Reference 6.5.b, page 3-1) states that abnormal termination of the code mn has been encountered when a relative humidity of 0 percent has been used, and recommends that the mirdmum relative humidity value should be at least 1 percent.

Technically, a higher relative humidity will yield a lower peak pressure. However, the effect is small; per Table 15 of BN-TOP-3 (Reference 6.11) increasing the relative humidity from 1 percent to 100 percent will decrease the containment peak pressure by approximately 0.4 psig. Therefore, the effect of increasing the relative humidity from 1 percent to 60 percent will decrease the containment peak pressure by approximately 0.2 psig. The probability of actually having a low relative humidity of 1 percent in a closed containment with the reactor at power is remote. Experience indicates that containments tend to be hot and humid, not hot and dry. Therefore, use of a higher relative humidity of 60 percent is realistic.

Table 0-1 of draft Environmental Qualification Design Basis Document DBD-SO23-TR-EQ (Reference 6.6.b), indicates that the normal containment relative humidity is 60 percent.

However, footnote "d" to Table 0-1 states that a document of record for this value has not been obtained.

b. ITEM 11: CONTAINMENT HEAT SINK REVAPORIZATION FRACTION In this analysis, no credit will be taken for containment heat sink revapodzation. Per the COPATTA Code Theory Manual (Reference 6.5.b, Appendix D,Section III.b), when the contamment atmosphere is at or below the saturation temperature, all condensate formed on the heat sinks is transferred directly to the sump. When the atmosphere is superheated, revaporization allows for the condensate to be transferred to the vapor region. The introduction of the relatively cold revaporized water mass to the superheated vapor J

1 NES&L DEPARTMENT l

CALCULATION SHEET 'cc" " d PREUM. CCN NO. PAGE _ OF__

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION.

CCN NO. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 18 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 E 5

environment reduces the average energy concentradon in the vapor space, consequently reducing the containment pressure and temperature. NUREG-0588 (Reference 6.4.b, Appendix B, Section 1.b) allows for up to 8 percent of the condensate to be transferred to the vapor region during the performance of equipment qualification analyses. Since the ,

LOCA provides only low levels of superheat prior to initiation of containment sprays at 60 l seconds and the peak vapor temperature remains below the 300 *F design value, no credit l for revaporization of the heat sink condensate will be taken.

i l

c. ITEM 12: TOTAL PRESSURE OUTSIDE CONTAINMENT The total pressure outside containment is assumed to be 14.7 psia. SONGS Units 2 and 3 are located at sea level. At this elevation, standard atmospheric pressure is approximately 14.7 psia per Table 3 of the ASHRAE Handbook (Reference 6.13). Per the COPATTA Code Theory Manual (Reference 6.5.b), the code uses the outside atmosphere total pressure in evaluating leakage rates between the containment and the outside environment. In this analysis no leakage is postulated and hence no leakage calculations are performed.

Therefore, any outside atmosphere total pressure may be modeled with no adverse impact on the analysis results.

d. ITEM 13: RELATIVE HUMIDITY OF OUTSIDE ATMOSPHERE The relative humidity of the outside atmosphere is assumed to be 50 percent. Per the I COPATTA Code Theory Manual (Reference 6.5.b), the code uses the outside atmosphere relative humidity in evaluating leakage rates between the containment and the outside environment. In this analysis no leakage is postulated and~hence no leakage calculations are performed. Therefore, any outside atmosphere relative humidity may be modeled with no adverse impact on the analysis results.

NES&L DEPARTMENT CALCULATION SHEET 'cc"

• PRELIM. CCN WO. PAGE OF

, Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 19 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5

~

\

3.2 CARD SERIES 2 a ITEM 6: HTC BETWEEN CONTAINMENT ATMOSPHERE AND SUMP LIQUID The. total heat transfer coefficient (HTC) for the heat trr^r between the liquid (sump) and vapoi regions of the containment is assumed to be 0 B'. --*F. A typical containment atmosphere to sump liquid HTC of 0.0 BTU /hr *F is hsd in section 3.3.1 and Table 4 of Bechtel Topical Report BN-TOP-3 (Reference 6.11). Use of this value is also recommended by Bechtel Nuclear Standard N2.3.2 (Reference 6.12, sheet 5).

The COPATTA Code uses the containment atmosphere to sump liquid HTC in evaluating heat transfer between the containment atmosphere and the sump liquid. Use of a smaller HTC is conservative because it will inhibit heat transfer from the containment air to the sump liquid, maximize containment air energy, and consequently yield higher containment pressures and tensperatures.

i l

NES&L DEPARTMENT CALCULATION SHEET '

'o'" ". CCN N O.

PRELIM PAGE oF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containenent P/T Analvsis for Desian Basis LOCA Sheet No. 2Q REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 E 5

3.3 CARD SERIES 4  !

I

a. ITEM 3: SDCHX SURFACE AREA l This calculation models a Shutdown Cooling Heat Exchanger (SDCHX) heat transfer surface area of 6860 square feet.

The Units 2 and 3 SDCHX Technical Manuals (References 6.9.a & b) describe a 7000 square foot SDCHX surface area. This area is consistent with the description present in SI/CS/SDC System Description SD-SO23-740 (Reference 6.7.e, section 2.2.20). However, to address possible plugging and corrosion, this calculation will assume (per engineering judgement) a two percent reduction in the surface area:

Asocax = 0.98 x 7000 ft2 = 6860 ft2 Minimizing the heat exchanger surface area minimizes the heat removed from the recirculating sump water via the heat exchanger, which minimizes the effectiveness of the Containment Spray System to reduce the containment air energy, thereby yielding a larger containment air energy inventory that will maximize the contamment pressures and temperatures during the sump water recirculation phase of the transient analysis, i

i

i NES&L DEPARTMENT l

! CALCULATION SHEET 'cc""o' PRELIM. CCN NO. PAGE__,OF _

i Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N 4080-026 CCN CONVERSION:

j CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 21 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

i j 3.4 CARD SERIES 5

{ a. ITEM 2: NUMBER OF EMERGENCY COOIlNG UNITS OPERATING

! In this analysis, only one of the two emergency cooling unit trains (air cooler trains) will be j assumed to be operational. As shown on P&ID 40172A (Reference 6.8.d), each tmin has two emergency cooling units. Therefore, two emergency cooling units are assumed to be operational in the LOCA analysis.

Per a July 30,1992 E-Mail message (Reference 6.2.e), the generic assumption in a typical Pressure-Temperature analysis would be a single failure causing the loss of one train of containment cooling. The only common mode single failure at SONGS that can prevent an emergency air cooler train start-up is power related. To produce the loss of one air cooler train requires.one failure of a Diesel Generator or a 4.16 KV bus, either of which will disable all pumps on that train (one Containment Spray pump and one Component Cooling Water pump). The 480 V power on the same train will also be disabled, prepy nting the startup of thegwo emergency cooling unit fans and disabling two LPSI MOV s, and four HPSI MOV'K The design basis LOCA mass and energy release data is based on maximum safety injection flows which require two HPSI trains, two LPSI trains, and all twelve penetation MOVi to be functional. Therefore, the power failure that would cause the loss of one train of containment cooling is in conflict with the design basis blowdown data.

However, to be consistent with the model used in the past and because it is a conservative assumption, only one emergency cooling unit train will be modeled in this analysis.

b. ITEM 4: EMERGENCY COOLING UNITS' SHUTOFF TIME The containment emergency cooling units are assumed to operate for the duration of the accident (1.0e7 seconds = 116 days).

NES&L DEPARTMENT CALCULATION SHEET ,'7,gnou yo. ,,, c , o,  ;

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 22 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 3.5 CARD SERIES 1001 i i 1 a. ITEMS 3 and 6: TEMPERATURE OF OUTSIDE ATMOSPHERE l

l The outside air temperature at SONGS is assumed to be 100 'F. This temperature is conservatively greater than the normal temperatures which are noted in the SONGS Units j

2&3 UFSAR (Reference 6.3.c, section 2.3.2.1.2 and Table 2.3-6). Per the UFSAR, San 1 Onofre meteorological data taken during the years 1974 and 1975 may be considered representative of normal conditions at the site. During this two year period, the absolute maximum temperature recorded at the site was 34.3 C (93.7 *F), occurring with an offshore Santa Ana wind on September 23,1975.

! Per the COPATTA Code Theory Manual (Reference 6.5.b, section 3.2.3), the Code uses the outside atmosphere temperature in evaluating leakage rates between the containment and the outside environment. Per the COPATTA Code User's Manual (Card Series 1001), the Code l also uses the outside atmosphere temperature in initializing the outer surface temperature of the containment structum, and in evaluating heat transfer between the outer surface of the containment stmeture and the outside environment. In this analysis no leakage to the outside atmosphere is postulated, and hence no leakage calculations are performed. Therefore, heat transfer to the environment dictates the modeling choice. '

Use of a higher air temperature is conservative because it will reduce heat transfer to the envimnment. Bechtel Nuclear Standard N2.3.2 (Reference 6.12, sheet 13) states that for a concrete containment stmeture the effect of heat transfer to the outside air is very small and i vinually negligible with respect to the peak containment pressures and temperatures. l l However, this is tme only in the short term following the onset of the accident. Long-term post-accident pressures and temperatures will be slightly increased by maximizing the ambient temperature of the outside atmosphere.

I

b. ITEMS 4 and 7: HTC BETWEEN A HEAT SINK AND OUTSIDE ATMOSPHERE The heat transfer coefficient between a heat sink and the outside atmosphere is assumed to be 2

[ 2.0 BTU /hr-ft - F. Use of this value is recommended in Bechtel Design Standard N2.3.2 (Reference 6.12, page 13).

1 i l

NES&L DEPARTMENT CALCULATION SHEET 'cc" " '

PREUM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 23 4

REV ORIGINATOR DME 1RE DATE REV ORIGINATOR DATE 1RE DATE R 0 R. Nakano 01/[8/94 J. Elliott 01/20/94 5

4 DESIGN INPUT This section presents the design input used in this calculation. The design inputs are armnged in groups which parallel the Card Series data input employed by the COPATTA Code.

1 4.1 CARD SERIES 0

a. ITEM 2: FLOW PATH THROUGH THE SDCHX The Shutdown Cooling Heat Exchanger (SDCHX) removes heat only from the spmy flow path. P& ids for Containment Spray System (40114A and 40114B) (References 6.8.b & c) show that the SDCHX cools water flowing through the contaimnent spray system during both

, the injection and recirculation phases. The low pressure safety injecdon water flows directly to the reactor coolant loop, as it is prevented from entering the SDCHX by normally closed valves HV-8152 and HV-8153. The high pressure safety injection water also flows directly

, to the reactor coolant loop, as it is not designed with cross-connections to allow a flow path through the SDCHX.

The COPATTA Code must be informed which flow path's~iiia'yWcooled.by the SDCHX. If i

the Containment Spray flow path is not cooled by the SDCHX, then the warmer spray water will minimize the effectiveness of the Containment Spray System to reduce the contaimnent y air energy. If the Safety Injection water is not cooled by the SDCHX, then the warmer l Safety Injection water will maximize the mass and energy release from the Reactor Vessel to 3

the containment, thereby yielding a larger containment air energy inventory that will maximize the contamment pressures and temperatures.

NES&L DEPARTMENT CALCULATION SHEET 'cc" "os PRELIM. CCM HO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

, CCN NO. CCN --

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 24 l REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE l DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 h 4

} l 4.2 CARD SERIES 1 I 4 a. ITEM 3: INITIAL CONTAINMENT PRESSURE The maximum allowable containment pressure is 1.5 psig per U23 Tecimical Specification Limiting Condition for Operation (LCO) 3.6.1.4 (Reference 6.3.a & b). This is equivalent j to a pressure of 16.2 psia (1.5 psig + 14.7 psi).

Per the COPATTA Code Theory Manual (Reference 6.5.b, section 3.1.1), the Code uses the

initial containment pressure in the determination of the initial mass of air in the containment I'

air space. The effect of varying the initial containment pressure is addressed in Bechtel l Topical Report BN-TOP-3 (Reference 6.11, section 4.1.2 and Table 15). Based on the data presented in BN-TOP-3, it is concluded that maximizing the initial contamment pressure will maximize the. peak containment pressure. Consequently, long-term post-accident pressures will also be maximized.  ;

i

b. ITEM 4: CONTAINMENT NET FREE VOLUME The containment net free volume of 2.305e6 cubic ft is determined by Civil Calculation i

C-257-1.06.01 (Reference 6.1.a, page 7). This volume is conservatively based on a

. reduction of the containment gross volume by 110 percent of the components volume. This represents a mduction by a margin of 3.0e4 cubic ft to account for components not

considemd explicitly in the Civil Calculation.

1 Per the Copatta Code Theory Manual (Reference 6.5.b, section 3.1.1), the Code uses the i

containment volume in the determination of the initial masses of air and water in the l containment air space. Per Bechtel Topical Report BN-TOP-3 (Reference 6.11, section 4.1.1.1), the containment volume is also used in evaluating the containment pressure, volume and energy relationship. Equations presented in Section 4.1.1.1 of BN-TOP-3 show that the

containment pressure is inversely proportional to the contamment volume. It is for this

reason that Section 3.3.1 and Figure 16 of BN-TOP-3 recommend that the minimum

) containment net free volume should be modeled. Because the ideal gas law states that pressure is proportional to temperature, minimizing the containment net free volume will

. maximize the peak containment temperature. Consequently, long-term post-accident pmssures and temperatures will also be maximized.

i s

NES&L DEPARTMENT

=

CALCULATION SHEET 'cc" " '

{ PRELIM. CCW No. PAG E__ 0F__ )

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSloN: l CCN No. CCN -

Subject Containment Pfr Analysis for Desian Basis LOCA Sheet No. 25 REV ORIGINATOR DATE IRE DATE REV ONGINATOR l DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 "

i  ! 4 i

p l c. ITEM 5: INITIAL CONTAINMENT TEMPERATURE l

l The initial bulk average containment atmosphere temperature is 120 'F. Technical i

Specification LCO 3.6.1.5 (References 6.3.a & b) indicates that this is the maximum

allowable containment temperature. The Eauipment Onalification Condition Monitorine

Program Assessment (Refemnce 6.10), contains the results of a study documenting actual 4

Units 2 and 3 environmental conditions during a data collection period of October 7,1985 to i October 17, 1986. Figure 3-2 of the report shows that the maximum bulk average Unit 2 l Containment temperature is 119 'F, and Figure 3-3 shows that the maximum bulk

average Unit 3 Containment temperature is 104 F.

[

, Per the COPATTA Code Theory Manual (Reference 6.5.b, section 3.1.1), the Code uses the j initial containment temperatum in the determination of the initial mass of air in the s

' containment air space. Per sections 3.1.2 and A.3 of the COPATTA Code Theory Manual, the Code also uses the initial containment temperature in the determination of the initial temperature profiles of those heat sinks in contact with the containment air.

The effect of varying the initial containment temperature is addressed in Bechtel Topical

! Report BN-TOP-3 (Reference 6.11, section 4.1.2 and Table 15). Based on the data j presented, it is concluded that maximizing the initial containment temperature will maximize both the peak containment pressure and temperature. This conclusion is consistent with the i fact that maximizing the initial containment teroperature will increase the initial heat sink j temperatures, thereby minimizing the effectiveness of the larger structural heat sinks in i removing energy from the containment air space. Consequently, long-term post-accident j- pressures and temperatures will also be maximized.

i

(

d. ITEM 8: INITIAL AVERAGE REACTOR COOLANT TEMPERATURE

] CE Ixtter S-CE-2604 (Reference 6.2.a) provides the mass and energy release data to be i modeled for the LOCA scenario. Appendix H to this CE Letter indicates that an initial i average (reactor) coolant temperature of 582.945 F should be modeled in the containment pressure-temperature analyses. This temperature is similar to the 582.1 'F average Reactor Vessel operating temperature specified in the RCS System Description SD-SO23-360 i (Reference 6.7.a, section 2.2.1).

i This parameter is used to set the initial temperature of all heat conducting region surfaces in contact with the reactor coolant. Since no heat sinks in contact with the reactor coolant are J

explicitly modeled in this analysis, the average reactor coolant temperature is not actually used in the COPATTA calculation.

i 1

NES&L DEPARTMENT CALCULATION SHEET '

yn?s"nou yo. ,,, c ,_ o,_

Project or DCP/MMP_ SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERslON:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 2f>

REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R O R. Nakano 01/18/94 J. Elliott 01/20/94 5

4.3 CARD SERIES 2

a. ITEM 5: REACTOR WATER VOLUME BELOW THE PIPE RUPTURE The mptured pipe connects to the reactor vessel at a nozzle, and the reactor vessel water below this nozzle connection will not be drained from the vessel via the pipe break.

Therefore, the maximum volume of water that may be in the vessel at the end of blowdown is equivalent to the reactor water volume below the pipe rupture. Per Appendix C to CE Letter S-CE-3242 (Reference 6.2.c), the volume of water below the nozzles of the reactor vessel is 2934 ft'.

Per Bechtel Topical Report BN-TOP-3 (Reference 6.11, section 3.2.4), for those time periods not addressed by the NSSS blowdown data, one may model the decay heat, sensible heat and metal-water reaction evaporation of the water remaining in the reactor vessel. If the exact water volume (mass) in the vessel is greater than the mass evaporated by the addition of decay heat, sensible heat, and metal-water reaction, then the excess reactor water volume modeled will be released to the containment sump where it would anificially depress the sump water temperature profile.

b. ITEM 8: TIME TO BEGIN THE MASS AND ENERGY BALANCE CALCULATIONS The time at which mass and energy balance calculations for the water within the reactor vessel will begin is 573.273 seconds. CE Ietter S-CE-2604 (Reference 6.2.a) provides tne 2

9.82 ft double ended suction leg slot (DESLS) break mass and energy release data. The mass and energy release data for the " Post-Reflood" Phase'of the DESLS break are provided in Appendix A (Table 1-3) to the letter. The last data entry is for time 573.273 seconds.

Per Bechtel Topical Repon BN-TOP-3 (Reference 6.11, section 3.2.4), for those time periods not addressed by the NSSS blowdown data, one may model the decay heat evaporation of the water remaining in the reactor vessel. At the specified time the temperature of all water within the vessel will be set to the saturation temperature corresponding to the total containment pressure in order to establish a staning point for succeeding calculations of vessel water energy. The core decay heat (Card Series 101), the sensible heat energy (Card Series 201), and the Safety Injection (Card Series 801) will begin to be added to the reactor vessel at this time. The specified time for this variable is equivalent to the end of the frothing phase as didated by the CE mass and energy release dats.

{

NES&L DEPARTMENT l CALCULATION SHEET =' l PAELIM. CCN NO. PAGE__ OF_

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containrnent P/T Analvsis for Desian Basis LOCA Sheet No. 77 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE BRE DATE R R. Nakano 01/18/94 J. Elliott "

O 01/20/94 4

l 4.4 CARD SERIES 4

a. ITEM 2: TYPE OF PRIMARY HEAT EXCHANGER l A single pass shell and U-tube (2 tube passes) heat exchanger is modeled in this analysis.

The Single pass shell and U-Tube shutdown cooling heat exchanger (SDCHX) design is described in the Units 2 and 3 SDCHX Technical Manuals (References 6.9.a & b). The SDCHX type is consistent with the description pmsent in SI/CS/SDC System Description SD-SO23-740 (Reference 6.7.e, section 2.2.20).

1 The type of heat exchanger dictates the efficiency of heat transfer between the recirculating sump water and the cooling Component Cooling Water System water. Per the COPATTA l Code Theorf Manual (Reference 6.5.b, section 3.2.2.2), the Code uses efficiency equations from comoact Heat Exchaneers by Kays and London (Reference 6.14).

b. ITEM 4: OVERALL PRIMARY HEAT EXCHANGER HTC The overall heat exchanger heat transfer coefficient of the Shutdown Cooling Heat Exchanger s

(SDCHX) is modeled as 216 BTU /hr-ft *F. This overall heat transfer coefficient is provided in the Units 2 and 3 SDCHX Technical Manuals (References 6.9.a & b). These two documents provide data for " Mode 4" operation defining a situation with 225 *F tube side water, which corresponds to what should be the maximum sump water temperature (it is noted that " Mode 4" operation as used in this discussion is a vendor defined term that should not be confused with " Mode 4" of reactor operations as defined in the Operating License).

The shell side flow rate for this mode is 3,000,000 lbs/hr of 120 *F water which corresponds to the coolant flow mte presented in Item 6 of this Card Series. In " Mode 4" operation a

" service" transfer rate of 216 BTU /hr-ft2 *F is provided to address performance reduction due to aging / fouling of the tubes. This " service" value is contrasted with the " clean" transfer mte of 283 BTU /hr-ft2..F provided in the Technical Manuals, and the 285 BTU /hr-ft 2_op value present in SI/CS/SDC System Description SD-SO23-740 (Reference 6.7.e, section 2.2.20).

Minimizing the SDCHX overall heat transfer coefficient minimizes the heat removed from the recirculating sump water via the HX, which minimizes the effectiveness of the Containment Spray System to reduce the containment air energy, thereby yielding a larger contaimnent air energy inventory that will maximize the containment pressures and temperatures during the recirculation phase of the transient analysis.

J

NES&L DEPARTMENT CALCULATION SHEET 'cc" " >

PRELIM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No N-4080-026 CCN CONVERSION:

CCN No. CCN --

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 28

! REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 "

5 l

l c. ITEhi 5: PRIMARY HEAT EXCHANGER COOLANT INLET TEhiPERATURE The primary heat exchanger coolant inlet temperature is 105 F. The maximum inlet temperature of the SDCHX coolant is no greater than the maximum Component Cooling Water System (CCWS) heat exchanger outlet tempenture. Per CCWS Design Basis Document DBD-SO23-400 (Reference 6.6.a, Table 0-1) and Calculation M-0026-001 (Reference 6.1.c, page 6), the maximum CCWS heat exchanger outlet temperature is 105 F.

Maximizing the SDCHX coolant inlet temperature minimizes the heat removed from the recirculating sump water via the HX, which minimizes the effectiveness of the Containment Spray System to reduce the contamment air energy, thereby yielding a larger contamment air energy inventory that will maximize the containment pressures and temperatures.

I i

d. ITEM 6: PRIMARY HEAT EXCHANGER COOLANT FLOW RATE i 1

1 Per Component Cooling Water System (CCWS) Design Bases Document DBD-SO23-400 '

(Reference 6.6.a, Table 3-1) and Calculation M-0026-002 (Reference 6.1.d, page 40), the required CCWS flow to the Shutdown Cooling Heat Exchanger is 6000 gpm per train. This value was identified as being requin:d because of its use in the original design basis LOCA pressure-temperature analysis of Calculation N-4080-002 (Reference 6.1.g, page 585). The CCWS flow rate of 6000 gpm specified in the CCWS DBD is consistent with the normally throttled 6000 gpm flow through the SDCHX that is specified in CCW System Description SD-SO23-400 (Reference 6.7.c, section 2.2.11).

The CCWS mass flow rate through the SDCHX can be calculated by dividing the volumetric flow rate by the specific volume of the CCWS coolant entering the SDCHX. Per Design Input Item 4.4.c, the maximum inlet temperature of the SDCHX coolant is no greater than 105 'F. At this temperature the cooling water has a specific volume of 0.016147 ft'/lbm (Reference 6.16, page 87). Therefore, the SDCHX coolant mass flow rate is:

$1 = [(6000 gal / min) x (60 min /hr)] + [(7.4805 gal /ft') x (0.016147 ft 3/lbm)]

, M = 3.0 x 106 lbm/hr This mass flow rate is equivalent to the 3 x 106 lbm/hr mass flow rate of the SDCHX l

coolant provided in the Units 2 and 3 SDCHX Technical Manuals (References 6.9.a & b).

These two documents provide data for " Mode 4" opemtion defining a situation with 225 *F tube side water, which corresponds to what should be the maximum sump water temperature

! (it is noted that " Mode 4" operation as used in this discussion is a vendor defined tenn that

NES&L DEPARTMENT CALCULATION SHEET 'oc" " '

PREUM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 cCN CoNVERSloN:

ccN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 29 l REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 '

R. Nakano 01/18/94 J. Elliott 01/20/94 4 !

l should not be confused with " Mode 4" of reactor operations as defined in the Operating License).

Minimizing the SDCHX inlet coolant mass flow rate minimizes the heat removed from the l recirculating sump water via the HX, which minimizes the effectiveness of the Containment Spray System to reduce the containment air energy, thereby yielding a larger containment air energy inventory that will maximize the contamment pressures and temperatures.

l l

l 1

NES&L DEPARTMENT CALCULATION SHEET 'cc" PRELIM. CCN WO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desion Basis LOCA Sheet No. 30 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

4 4.5 CARD SERIES 5 >

a. ITEM 3: TIME OF AIR COOLER INITIATION The containment emergency cooling units' start time is 35 seconds for the LOCA with a loss of offsite power.

Per the Engineered Safety Features Actuation System's System Description (Reference 6.7.d, section 2.1.2.1.3), a CCAS is generated upon receipt of two out of four low pressurizer pressure or high containment pressure signals.

l Calculation N-4080-003 (Reference 6.1.h, Section 8.1) determined that the emergency cooling units would be functional within 34 seconds for a LOCA with a loss of offsite power. To pmvide margin to address any f.iture changes in system performance, this

! analysis assumes that the time of air cooler initiation with a loss of offsite power is 35 '

seconds. This assumption mpmsents the addition of one seconds of delay time to the air cooler initiation time determined by Calculation N-4080-003.

Delaying the start of the containment air cooler operation conservatively delays the removal of containment atmosphere energy via the emergency cooling units, thereby maintaimng a

! larger contaimnent air energy inventory that will maximize the containment pressures and temperatures,

b. ITEM 8: TEMPERATURE OF AIR COOLER HEAT EXCHANGER COOLANT The air cooler heat exchanger coolant temperature is 105 F. The maximum inlet temperature of the air cooler HX coolant is no greater than the maximum Component Cooling Water System (CCWS) heat exchanger outlet temperature. Per CCWS Design Basis Document DBD-SO23-400 (Reference 6.6.a, Table 0-1) and Calculation M-0026-001 (Reference 6.1.c, page 6), the maximum CCWS heat exchanger outlet temperature is 105 *F.

Since the CCW piping is not insulated, it is expected that heat will be lost between the heat exchanger and containment. Additionally, heat will be gained by the CCW system once the piping enters containment because of the high ambient temperature following a LOCA. It is reasonable to assume that the tempenture entering the coolers is the same as the temperature leaving the heat exchanger.

NES&L DEPARTMENT CALCULATION SHEET '

' c" ".

PREUM CCN NO. PAGE_ OF_

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 31 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

Maximizing the air cooler coolant temperature minimizes the heat removed from the contamment air circulating through the air cooler, thereby yielding a larger containment air energy inventory that will maximize the contamment pressures and temperatures. l i

l I

NES&L DEPARTMENT CALCULATION SHEET 'cc" " '

PRELIM. CCN NO. PAGE_ of _

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSloN:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. _J2_

EEV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R E

O R. Nakano 01/18/94 J. Elliott 01/20/94 4

4.6 CARD SERIES 101: REACTOR CORE DECAY POWER CE I.etter S-CE-2604, (Reference 6.2.a) provides the mass and energy release from time zero to the end of entrainment (i.e., the " Blowdown", " Post-Blowdown" and "Reflood" phases). Per Appendix I to this letter, the mass and energy release data considers core power transient and decay heat. Per Appendix A (Table 1-3) to this letter, the last of the I NSSS supplied mass and energy release data is at time 573.273 seconds. The methodology to be used in evaluating core decay heat for times after 573.273 seconds is taken from NRC Branch Technical Position (BTP) ASB 9-2 (Reference 6.4.e). This analysis employs this methodology by using Bechtel Standard Application Program MAP-121, the " DECAY" Code 1 I

(Reference 6.5.a). The BTP ASB 9-2 methodology includes 20 percent margin for decay times of less than 1000 seconds, and 10 percent margin for decay times greater than 1000 seconds.

l Input to the DECAY Code consists of the reactor power level and the reactor operating time.

Standard Review Plan 15.6.5 (Reference 6.4.d, section III.4.2) states that a conservative evaluation of the dose consequences of a LOCA should model a power level of the licensed core thermal power, plus an allowance of two percent to account for power meast:rement uncertainties. Paragraph 2.(1) of the Operating License (References 6.3.a & b) indicates that the reactor power level should not exceed a maximum value of 3390 hNt. Therefore, a power level of 3458 MWt will be modeled, corresponding to an energy rate of:

$ = (1.02 x 3390 AMt) x (3.413 x 106 BTU /MWt-hr)

$ = (3458 MWt) x (3.413 x 106 BTU /MWt-hr) s = 1.180 x 10" BTU / hour In this calculation no energy from the hydrogen recombiners is modeled because it is negligible compared to the decay heat energy. The hydrogen recombiners are each rated at 75 KW (2.56e5 Btu /hr) and provide about 60 KW (2.05e5 Btu /hr) pott accident. As can be seen from the decay energy generated below, the energy from the hyd mgen recombiners is negligible.

NRC Branch Technical Position ASB 9-2 (Revision 2) addresses the equations and input parameters that are to be used in evaluating reactor core decay heat. Per the BTP, an opemting history of 16,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> is considered representative of inany end-of-first or equilibrium cycle conditions and is, therefore, acceptable for use in a core decay heat evaluation. For this analysis a two year (17,520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br />) operating cycle will be conservatively assumed.

1 NES&L DEPARTMENT CALCULATION SHEET 'cc"

• PRELIM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN No. CCN --

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 33 i

REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 The reactor power level of 3458 MWt (1,180e10 BTU /hr) and the reactor operating time of 17,520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br /> are inputs to the calculation of reactor core decay heat energy release that will be modeled for times at which CE has not provided mass and energy release data.

Maximizing the reactor power level and the operating time will maximize the core decay heat energy release for these later times, and consequently increase the long-term containment pressures and temperatures. Because the core decay heat energy release prior to the end of the CE provided mass and energy releese is included in the CE data, the reactor power level and decay heat calculations for the Card Series 101 input have no effect on the peak pressure and temperature which occur prior to the end of the CE supplied mass and energy release data at 573.273 seconds.

The input of the DECAY Code case run is:

NRC 1.180E10 17520 2

DECAYHT.0UT Y

24 0 573.273 6E2 BE2 1E3 2E3 4E3 6E3 BE3 1E4 2E4 4E4 6E4 8E4 1ES 2E5 4E5 6ES BE5 1E6 2E6 4E6 6E6 1E7 The output of the DECAY Code case run is:

MAP-121 DECAY HEAT CALCULATION CODE, VERSION V01:

COPYRIGHT 1979,1988 Bechtel Power Corporation NRC DECAY HEAT MODEL (ASB-92, REY. 2, 1981)

NRC VER$10N CALCULATES RESIDUAL DECAY HEAT BY EQUATIONS PRESENTED IN NRC BRANCH TECHNICAL POSITION ASB 9-2. REV.2 JULY 1981. CODE CALCULATES DECAY HEAT RESULTING FROM FIS$10N PRODUCT DECAY, FP,AND THE DECAY OF U-239 AND NP-239. THE TOTAL DECAY RATE, INCLUDING THE APPROPRIATE UNCERTAINTY FACTORS IS LABELED TOTAL. THE TOTAL HEAT RELEASED IS LABELED INTEGRAL. RESULTS ARE ACCURATE ONLY UP TO 1.0E07 SEC.

OPERATING POWER = .11800E+11 BTU /HR

NES&L DEPAPJMENT CALCULATION SHEET 'c 7,0c, uo.

,n, ,,o,_ o,_

Project or DCP/MMP SONGS Units 2 & 3 Calc, No. N-4080-026 CCN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA 1 Sheet No. 34  !

l REV ORIGINATOR DATE 1RE DATE REV I

ORIGINATOR DATE IRE DATE R '

O R. Nakano 01/18/94 J. Elliott 01/20/94 "

l 1 I

l I l OUTPUT FILENAME = DECAYHT.0UT REACTOR OPERATING TIME = .17520E+05 HRS USER-SELECTED TIME AFTER SHUTDOWN (SEC.):

.0000E+00 .5733E+03 .6000E+03 .8000E+03 .1000E+04 .2000E+04 4000E+0<. .6000E+04 .8000C+04 .1000E+05 .2000E+05 .4000E+05 ,

l

.6000E+05 .8000E+05 .1000E+06 .2000E+06 .4000E+06 .6000E+06 4

.8000E+06 .1000E+07 .2000E+07 .4000E+07 .6000E+07 .1000E+08 l TIME FP U-239 NP-239 U239+NP239 TOTAL (SEC) (BTU /HR) (BTU /HR) (BTU /HR) (BTU /HR) (BTU /HR)

.00000E+00 .98388E+09 .18833E+08 .17924E+C8 .36757E+08 .11800E+11

.57327E+03 .29718E+09 .14213E+08 .17920E+08 .32132E+08 .32931E+09

! .60000E+03 .29429E+09 .14027E+08 .17919E+08 .31947E+08 .32624E+09

.80000E+03 .27749E+09 .12715E+08 .17916E+08 .30631E+08 .30812E+09

.10000E+04 .26505E+09 .11526E+08 .17911E+08 .29437E+08 .29449E+09

.20000E+04 .20241E+09 .70540E+07 .17880E+08 .24934E+C8 .22734E+09

.40000E+04 .15920E+09 .26422E+07 .17788E+08 .20430E+08 .17963E+09

.60000E+04 .13861E+09 .98965E+06 .17678E+08 .18667E+08 .15728E+09

.80000E+04 .12713E+09 .37069E+06 .17561E+08 .17932E+08 .14506E+09

.10000E+05 .11948E+09 .13884E+06 .17444E+08 .17582E+08 .13706E+09

.20000E+05 .96797E+08 .10236E+04 .16860E+08 .16861E+08 .11366E+09

.40000E+05 .74023E+08 .55638E-01 .15748E+08 .15748F.+08 .89771E+08

.60000E+05 .63753E+08 .30241E-05 .14710E+08 .14710E+08 .78463E+08

.80000E+05 .58401E+08 .16437E-09 .13740E+08 l

.13740E+08 .72141E+08

.10000E+06 .55060E+08 .89342E 14 .12834E+08 .12834E+08 .67894E+08 1

1

.20000E+06 .45865E+08 .42489E-35 .91260E+07 .91260E+07 .34991E+08 40000E+06 .36798E+08 .00000E+00 46141E+07 .46141E+07 .414.12E+08

.60000E+06 .32401E+08 .00000E+00 .23329E+07 .23329E+07 .34734E+08

.80000E+06 l

.29732E+08 .00000E+00 .11795E+07 .11795E+07 .30911E+08 '

.10000E+07 .27766E+08 .00000E+00 .59638E+06 .59638E+06 .28363E+08

.20000E+07 .21276E+08 .00000E+00 .19705E+05 .19705E+05 .21296E+08

.40000E+07 .14713E+08 .00000E+00 .21513E+02 .21513E+02 .14713E+08

.60000E+07 .11629E+08 .00000E+00 .23486E-01 .23486E-01 .11629E+08

.10000E+08 .85482E+07 .00000E+00 .27992E-07 .27992E-07 .85482E+07 Following is the normalized decay heat graph which plots the normalized decay heat versus time after shutdown.

I E

o m  ?  ?

2 c--

2..

2 2 2 g o R f 5 8 o r 3 - o E

O 4 Y g $O s

LOCA WITH LOP - NORMALIZED DECAY HT CRV E g 2::

)

o m e 2 n

o i

a o z C Om 10 ..",....",.",",.....,",...","; g $ g @p* p

[  :  :

• y 9)a W - -

F x ym 3 - - = m O - -

m s

o M

, O>-1m Q- 8 "5 2 a 2 K 10-' r: = t O  : e g) m Z

F-o h

r.

Id m

[

m B Dm E y w o w 5 -

Q. 10-2 , , g = g z O  :  :

: z g - -

a k Q o O

m

- . o Z 8 O 10-3  :

E a

o ga o

F-  : -

m- Ez O  :  : 3 .E 8

< - - g os

[ - - E R 88 z 10 -*

m

'OO

~

10 -' 10 10' 10 10 10* 105 105 107 n5 n ';

ze TIME AFTER SHUTDOWN (SEC) s W 'E s i a z l

• O o m

h Q m G 4xs < m 2

l NES&L DEPARTMENT CALCULATION SHEET 'cc" "o '

PRELIM. CCN NO. PAGE._ OF_ ,

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 36 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

S 4.7 CARD SERIES 201

a. ZIRCONIUM METAL-WATER REACTION ENERGY At high temperatures, the Zirconium metal present in the fuel cladding will react with the mactor water and release energy. This Zirconium metal-water reaction energy is released via the blowdown into the contamment air space. Maximizing the Zirconium metal-water l

i reaction energy release maximizes the cor.taimnent pressure and temperature.

The energy release associated with the metal-water reaction is not incorporated into the CE blowdown data, and it is necessary to explicitly model the metal-water reaction energy for times prior to the end of the CE supplied blowdown profile. Page 2 of CE Letter S-CE-2604, (Reference 6.2.a), states that the maximum allowable Zirconium metal-water reaction energy mlease should be modeled as a constant release rate over the time interval between the start of the LOCA and the end of reflood. Section 6.2.1.3.8 of Appendix I of l

Letter S-CE-2604 states that the Zirconium metal-water reaction releases a total of i 1.515 x 10' BTU. This energy miease was based on an active core Zirconium metal mass  ;

of 54645 lbm, with a molecular weight of 91.22 lbm/lbm-mole, a reaction energy of l 252900 BTU /lbm-mole, and a maximum allowable one percent reaction: '

E., m = (0.01) x (54645 lbm) x (252900 BTU /lbm-mole) / (91.22 lbm/lbm-mole)

= 1.515 x 106 BTU Table 1-2 of CE Letter S-CE-2604 indicates that the end of mflood occurs at time 211.10 seconds. Therefore, the zirconium metal water reaction releases energy between 0 and 211.10 seconds at a constant rate of:

$,_,, m . = (1.515 x 106 BTU) x (3600 sec/hr) / (211.10 sec - O sec)

= 2.5836 x 107 BTU / hour

b. STORED SENSIBLE HEAT ENERGY PRIRASE At the end of the post-reflood phase a significant amount of sensib'e heat energy remains stored in various RCS components. As time passes and the primary coolant decreases in temperature, this stored energy will be released back to the primary coolant. The CE supplied energy release data addmssing this stored energy is not provided for times subsequent to the end of the post-reflood period. It is therefore necessary to add this sensible heat over some user specified time interval. The shorter the time interval the faster the

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l

energy is released into the containment air space, and the greater the containment pressure and temperature response.

Table 1-3 of CE Letter S-CE-2604 (Reference 6.2.a) indicates that the end of the Post-Reflood phase occurs at time 573.273 seconds. Appendix B to CE Letter S-CE-3242 ,

(Reference 6.2.c), tabulates the quantity of stored sensible heat in various components at this I time, for a reference temperature of 32 *F. Appendix C to CE Letter S-CE-3242 tabulates 1 the temperatures of these various components at this same time. The heat capacity and mass i of each component is tabulated in Appendix E to CE Letter S-CE-2604. With this information, Calculation N-4080-002 (Reference 6.1.g) determined the average component temperature, and the total quantity of stored sensible heat in various components at this time, for a reference temperature of 32 F. This stored sensible heat was then manipulated to 6

determine that a total of 301.22 x 10 BTU is stored as sensible heat in the various components at the end of the Post-Reflood phase, at a revised reference temperature of i 105 *F.

' l Since cooldown of the contamment requires many days, a conservative approximation is to add this sensible heat energy over a short duration of one day (86400 seconds). Therefore, i

sensible heat energy is released to the Reactor Vessel between 573.273 and 86400 seconds at i, a constant rate of:

j s,.,a = (301.22 x 106 BTU) x (3600 sec/hr) / (86400 sec - 573.273 sec) 7 i = 1.2635 x 10 BTU / hour 4

i i

f a

4

NES&L DEPARTMENT CALCULATION SHEET  !' d"u$cN No. eAce or Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CoNVERSloN:

CCN No. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 38 )

REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 E S

4.8 CARD SERIES 301 Card Series 301 is a table that is used to input blowdown following pipe rupture. It provides the water addition rate and the enthalpy of the water at various times. The NSSS vendor j

determines the mass and energy release data that describes a spectmm of break types and '

break sizes. This " blowdown" data is introduced into the containment air space where it serves to increase both the containment pressure and temperature. Incmasing the total mass and energy release will increase the containment pressure and temperature response. l l

The conclusions presented in Calculation N-4080-002 (Reference 6.1.g) indicate that the worst case LOCA is for the condition of a 9.8175 square foot ama double ended suction leg slot (DESLS) break, with failure of a single cooling train. The mass and energy release data 4 for this LOCA case are provided in Tables 1-1 through 1-3 of the CE Letter S-CE-2604 l (Reference 6.2.a), and documented in the tables below. I l

Break mass flow rates in CE Ixtter S-CE-2604 are presented in units of pounds per second. l The water addition rates entered into Card Series 301 are in units of pounds per hour. The l Card Series 301 input data were calculated by scahng the CE break mass flow rates by the conversion factor of 3600 seconds per hour.

Break energy flow rates in CE Letter S-CE-2604 break energy flow rates are presented in units of Million BTU per second. The water enthalpies entered into Card Series 301 are in units of BTU per pound. The Card Series 301 input data were calculated by dividing the CE energy flow rates by the CE mass flow rates at each time step, and then multiplying by the conversion factor of 1 x 106 BTU per Million BTU.

" Blowdown" phase (0 s t s 22.0 sec)

The " Blowdown" phase exists fmm time zero to the time that the vessel has emptied.

The mass and energy release data for the " Blowdown" Phase of the DESLS break are presented below as provided in Appendix A (Table 1-1) to CE Letter S-CE-2604.

The mass and energy release mtes are assumed to vary linearly between each data point in the following table.

NES&L DEPARTMENT i CALCULATION SHEET 'cs"gou ,0.

,,, ,_ o ,_

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

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! Subject Containment P6 Analvsis for Desion Basis LOCA i

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) 0 R. Nakano 01/18/94 J. Elliott 01/20/94

h S

i I LOSS OF COOLANT ACCIDENT MASS AND ENERGY RELEASE DATA (Blowdown Phase)

(9.8175 ft' break area, Double Ended Suction Iag Slot Break TIME NSSS SUPPLIED DATA DATA CONVERTED FOR CODE USE CS 301, Item 1 (CE Letter S-CE-2604) Card Series 301, Items 2 & 3 BREAK MASS BREAK ENERGY BREAK MASS BREAK BREAK FLOW RATE FLOW RATE FLOW RATE ENTHALPY ENERGY (sec) Obm/sec) (10' BTU /sec) Obm/ hour) (BTU /lbm) FLOW RATE (BTU /hr) 0 0 0 0 0 0 0.025 75188 41.077 2.7068e +08 5.4632e+02 1.4788e +11 0.075 74324 40.641 2.6757e+08 5.4681e+02 1.4631e +11 0.175' 77939 42.748 2.8058e +08 5.4848e+02 1.5389e +11 0.20 94424 51.870 3.3993e +08 5.4933e +02 1.8673e +11 0.225 93071 51.158 3.3506e +08 5.4967e +02 1.8417e +11 0.25 93149 51.243 3.3534e+08 5.5012e +02 1.8447e + 11 0.40 87178 48.220 3.1384e +08 5.5312e+02 1.7359e+11 0.75 81491 45.767 2.9337e +08 5.6162e +02 1.6476e + 11 0.85 76010 42.746 2.7364e +08 5.6237e+02 1.5389e + 11 1.0 68473 38.570 2.4650e +08 5.6329e +02 1.3885e +11 1.2 62633 35.343 2.2548e +08 5.6429e+02 1.2723e +11 ,

2.0 57656 32.696 2.0756e +08 5.6709e +02 1.1771e +11 3.0 50637 29.153 1.8229e +08 5.7573e +02 1.0495e +11 4.0 43798 26.146 1.5767e +08 5.9697e+02 9.4126e +10 5.0 36820 23.213 1.3255e +08 6.3M5e + 02 8.3567e +10 6.0 31466 20.731 1.1328e +08 6.5884e +02 7.4632e +10 8.0 26350 17.697 9.4860e +07 6.7161e +02 6.3709e + 10 10.0 21889 15.052 7.8800e +07 6.8765e+02 5.4187e +10 12.0 15126 11.588 5.4454e +07 7.6610e + 02 4.1717e +10 13.5 9905 8.5578 3.566e + 07 8.640e + 02 3.0808e +10 14.5 8021 6.0176 2.888e +07 7.502e + 02 2.1663e +10 15.0 7296 5.2521 2.627e +07 7.199e + 02 1.8908e +10

l NES&L DEPARTMENT CALCULATION SHEET 'cc" " '

PRELIM. CCN NO. PAGE OF 1

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

l CCN No. CCN -

{ Subject $.ontainment P/T Analvsis for Desian Basis LOCA Sheet No. 40 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

~

I 1

i LOSS OF COOLANT ACCIDENT 2 MASS AND ENERGY RELEASE DATA (Blowdown Phase) l (9.8175 ft break area, Double Ended Suction ?.eg Slot Break

} TIME NSSS SUPPLIED DATA DATA CONVERTED FOR CODE USE CS 301, Item 1 (CE Letter S-CE-2604) Card Series 301, Items 2 & 3 j BREAK MASS BREAK ENERGY BREAK MASS BREAK BREAK

FLOW RATE FLOW RATE FLOW RATE ENTHALPY ENERGY (sec) Obm/sec) (10' BTU /sec) Obm/ hour) (BTU /lbm) FLOW RATE

{ (BTU /hr)

I j 16.0 4910 3.2893 1.768e + 07 6.699e + 02 1.1841e +10 f

17.1 3107 2.0371 1.119e +07 6.556e + 02 7.3336e+09 i 17.2 3168 2.0232 1.140e +07 6.386e +02 7.2835e+09 17.3 2518 1.5644 9.065e +06 6.213e + 02 5.631 Se + 09 18.5 1709 1.1004 6.152e + 06 6.439e + 02 3.9614e+09 19.3 2446 1.1263 8.806e+06 4.605e +02 4.0547e +09 19.8 1985 0.96886 7.146e +06 4.881e +02 3.4879e +09 20.6 1159 0.61984 4.172e +06 5.348e +02 2.2314e +09 20.8 2823 0.93645 1.016e +07 3.317e + 02 3.3712e +09 21.4 1008 0.37291 3.629e +06 3.700e +02 1.3425e +09 21.6 492 0.18020 1.77e +06 3.66e +02 6.4872e +08 21.8 84 0.028758 3.0e +05 3.4e +02 1.0353e +08 22.0 0 0 0 0 0 "Reflood" chase (22.0 < t s; 211.I sec)

The "Reflood" phase exists from the time the vesse.1 has emptied to the time that entrainment ends. The mass and energy release data for the "Reflood" Phase of the DESLS break are presented below as provided in Appendix A (Table 1-2) to CE Letter S-CE-2604. The mass and energy release rates are assumed to vary linearly between each data point in the following table.

I

NES&L DEPARTMENT CALCULATION SHEET 'cc" No '

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LOSS OF COOLANT ACCIDENT MASS AND ENERGY RELEASE DATA (Reflood Phase)

(9.8175 ft8 break area, Double Ended Suction Leg Slot Break TIME NSSS SUPPLIED DATA DATA CONVERTED FOR CODE USE CS 301, Item 1 (CE Letter S-CE-2604) Card Series 301, items 2 & 3 BREAK MASS BREAK ENERGY BREAK MASS BREAK BREAK ENERGY FLOW RATE FLOW RATE FLOW RATE ENTHALPY FLOW RATE (sec) (Ibm /sec) (10' BTU /sec) (Ibm / hour) (BTU /lbm) (BTU /hr) 22.C 0.00 0.00 0.00 0.00 0.00 22.25 161.95 0.210530 5.8302e +05 1.3000e+03 7.57908e +08 23.25 256.21 0.333078 9.2236e +05 1.3000e+03 1.19908e +09 24.25 429.52 0.558376 1.5463e + 06 1.3000e + 03 2.01015e+09 25.25 567.88 0.738240 2.0444e +06 1.3000e + 03 2.65766e +09 l

26.25 673.75 0.875877 2.4255e +06 1.3000e +03 3.15316e+09 i 27.75 798.22 1.037687 2.8736e +06 1.3000e+03 3.73567e +09 .

28.00 512.31 0.666007 1,8443e+06 1.3000e+03 2.39763e +09 36.00 505.59 0.657271 1.8201e+06 1.3000e +03 2.36618e +09 44.50 497.77 0.647104 1.7920e+06 1.3000e +03 2.32957e +09 44.75 777.41 1.010629 2.7987e +06 1.3000e +03 ~ 3.63826e+09 75.00 735.20 0.955764 2.6467e +06 1.3000e +03 3.44075e+09 100.00 699.71 0.909620 2.5190e +06 1.3000e +03 3.27463e +09 8

125.00 664.47 0.863805 2.3921e +06 1.3000e +03 3.10970e +09 150.00 629.91 0.818881 2.2677e +06 1.3000e +03 2.94797e +09 175.00 594.47 0.772807 2.1401e +06 1.3000e +03 2.78211e + 09 200.00 558.78 0.726408 2.0116e +06 1.3000e + 03 2.61507e +09 211.10 543.15 0.706090 1.9553e +06 1.3000e +03 2.54192e+09

4 NES&L DEPARTMENT

CALCULATION SHEET '

'cc".

PREUMCCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

. CCN NO. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 42 i

4 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R

! O R. Nakano 01/18/94 J. Elliott 01/20/94 '

i l 4 ,

i l

. " Post-Reflood" phne (211.1 < t s; 573.273 sec)

The " Post-Reflood" (or " Frothing") phase exists from tile time that entrainment has ended until the time that the steam generator secondary temperature has essentially reached equilibrium with the primary side temperature so that there is no longer a significant driving potential for secondary to primary heat transfer. The mass and

energy release data for the " Post-Reflood" Phase of the DESLS break are provided in j Appendix A (Table 1-3) to CE Letter S-CE-2604.

LOSS OF COOLANT ACCIDENT MASS AND ENERGY RELEASE DATA (Post-Reflood Phase)

(9.8175 ft2 break area, Double Ended Suction Leg Slot Break TIME NSSS SUPPLIED DATA DATA CONVERTED FOR CODE USE CS 301, Item 1 (CE Letter S-CE-2604) Card Series 301, Items 2 & 3 BREAK MASS BREAK ENERGY BREAK MASS BREAK BREAK ENERGY FLOW RATE FLOW RATE FLOW RATE ENTHALPY FLOW RATE (sec) Obm/sec) (10' BTU /sec) Obm/ hour) (BTU /lbm) (BTU /hr) 211.101 624.38 0.740830 2.2478e+06 1.1865e+03 2.66699e +09 211.336 621.62 0.737560 2.2378e +06 1.1865e +03 2.65522e+09 211.573 618.86 0.734290 2.2279e+06 1.1865e +03 2.64344e+09 211.812 616.09 0.731010 2.2179e+06 1.1865e +03 2.63164e +09 l 212.052 613.33 0.727730 2.2080e +06 1.1865e +03 2.61983e +09 213.026 600.41 0.713130 2.1615e +06 1.1877e +03 2.56727e+09 215.073 568.58 0.675350 2.0469e +06 1.1878e +03 2.43126e +09 216.989 540.72 0.642320 1.9466e +06 1.1879e +03 2.31235e +09 219.039 512.88 0.609310 1.8464e +06 1.1880e +03 2.19352e +09 221.233 485.07 0.576330 1.7463e +06 1.1881e +03 2.07479e +09 222.894 465.22 0.552800 1.6748e + 06 1.1883e +03 1.99008e +09 225.021 441.42 0.524590 1.5891e +06 1.1884e +03 1.88852e +09 226.920 421.64 0.501140 1.5179e +06 1.1885e +03 1.80410e +09 228.953 401.90 0.477740 1.4468e+06 1.1887e +03 1.71986e +09 231.139 382.21 0.454410 1.3760e +06 1.1889e + 03 1.63588e +09 233.014 366.51 0.435800 1.3194e + 06 1.1891e +03 1.56888e +09 m.-.,_

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cCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 43 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

S l

LOSS OF COOLANT ACCIDENT 8 MASS AND ENERGY RELEASE DATA (Post-Reflood Phase)

(9.8175 ft break area, Double Ended Suction Leg Slot Break i

TIME NSSS SUPPLIED DATA DATA CONVERTED FOR CODE USE CS 301, Item 1 (CE Letter S-CE-2604) Card Series 301, Items 2 & 3 BREAK MASS BREAK ENERGY BREAK MASS BREAK BREAK ENERGY FLOW RATE FLOW RATE FLOW RATE ENTHALPY FLOW RATE (sec) Obm/sec) (10' BTU /sec) Obm/ hour) (BTU /lbm) (BTU /hr) 235.017 350.86 0.417260 1.2631e +06 1.1892e + 03 1.50214e +09 237.167 335.27 0.398780 1.2070e + 06 1.1894e +03 1.43561e +09 238.890 323.52 0.384980 1.1647e +06 1.1900e + 03 1.38593e +09 240.719 312.00 0.371210 1.1232e +06 1.1898e +03 1.33636e +09 242.668 300.44 0.357520 1.0816e +06 1.1900e +03 1.28707e +09 245.484 285.13 0.339370 1.0265e +06 1.1902e +03 1.22173e +09 246.897 277.52 0.330350 9.9907e+05 1.1904e +03 1.18926e+09 249.420 266.17 0.316900 9.5821e +05 1.19%e + 03 1.14084e +09 251.151 258.64 0.307980 9.3110e +05 1.1908e +03 1.10873e +09 254.936 243.74 0.290320 8.7746e+05 1.1911e + 03 1.04515e +09 259.251 229.06 0.272910 8.2462e +05 1.1914e +03 9.82476e +08 262.929 218.23 0.260060 7.8563e +05 1.1917e +03 9.36216e +08 267.086 207.58 0.247420 7.4729e +05 1.1919e +03 8.90712e +08 271.855 197.15 0.235030 7.0974e + 05 1.1921e +03 8.46108e +08 281.634 180.41 0.215140 6.4948e +05 1.1925e +03 7.745Gle +08 292.060 167.81 0.200110 6.0412e +05 1.1925e +03 7.20396e + 08 302.415 158.99 0.189560 5.7236e +05 1.1923e +03 6.82416e +08 311.215 153.49 0.182950 5.5256e +05 1.1919e + 03 6.58620e +08 321.094 148.88 0.175980 5.3597e +05 1.1820e + 03 6.33528e +08 331.360 145.31 0.171760 5.2312e +05 1.1820e +03 6.18336e+08 340.999 142.78 0.168750 5.1401e +05 1.1819e +03 6.07500e+ 08 l 351.095 140.73 0.166330 5.0663e +05 1.1819e +03 5.98788e+08 I 361.352 139.11 0.164410 5.0080e +05 1.1819e +03 5.91876e +08 l

l

NES&L DEPARTMENT CALCULATION SHEET 'cc" "o '

PREUM. CCN WO. PAGE__ OF_,,

Project Or DCP/MMP SONGS Units 2 & 3 Calc. No N-4080-026 CCN CONVERSION

l CCN NO. CCN -

l Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 44 i i

REV ORIGINATOR DATE BRE DATE REV ORIGINATOR DATE tRE DATE R l 0 R. Nakano 01/18/94 J. Elliott 01/20/94 h l i

s i

i LOSS OF COOLANT ACCIDENT MASS AND ENERGY RELEASE DATA (Post-Reflood Phase)

(9.8175 ft' break area, Double Ended Suction Leg Slot Break i

TIME NSSS SUPPLIED DATA DATA CONVERTED FOR CODE USE i CS 301, item 1 (CE Letter S-CE-2604) Card Series 301, Items 2 & 3 i

BREAK MASS l BREAK ENERGY EREAK MASS BREAK BREAK ENERGY

FLOW RATE FLOW RATE FLOW RATE ENTHALPY FLOW RATE

', (sec) Obm/sec) (10' BTU /sec) Obm/ hour) (BTU /lbm) (BTU /hr) 371.311 137.88 0.162950 4.9637e +05 1.1818e +03 5.86620e +08 391.750 136.M 0.160770 4.8974e +05 1.1818e +03 5.78772e +08 411.491 134.85 0.159380 4.8546e +05 1.1819e +03 5.73768e +08

432.076 133.98 0.155320 4.8233e +05 1.1593e +03 5.59152e +08 452.069 133.37 0.157600 4.8013e + 05 1.1817e +03 5.67360e +08 471.774 132.92 0.157060 4.7851e +05 1.1816e +03 5.65416e +08 l 524.M7 132.16 0.156160 4.7578e +05 1.1816e +03 5.62176e+ 08 573.273 131.74 0.155660 4.7426e +05 1.1816e +03 5.603760e +08

{

i 573.273 0.00 0.00 0.00 0.00 0.00

] 1.00e +07 0.00 0.00 0.00 0.00 0.00 l

1 l

4 4

l l

NES&L DEPARTMENT CALCULATION SHEET 'cc" " >

PRELIM. CCN No. PAG E__ 0F_

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CoNVERSloN:

CCN No. CCN -

Subject Contair, ment P/T Analysis for Desian Basis LOCA Sheet No. 45 9

REV ORIGINATC R DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 E 5

4.9 CARD SERIES 601 Card Series 601 is used to add water and/or energy directly to the containment sump, regardless of the enthalpy of the water being added. The water and/or energy being added to the sump represents reactor vessel spillage and direct floor spillage of the Safety Injection flow during the recirculation phase of the transient analysis.

In this analysis Card Series 601 is used to model spillage of the Safety Injection flow that is 2

implicitly addressed in the 9.82 ft double ended suction leg slot (DESLS) mass and energy release data provided in CE Ixtter S-CE-2604 (Reference 6.2.a). The mass and energy

/ release data for the " Post-Reflood" Phase of the DESLS break are provided in Appendix A (Table 1-3) to the letter. The mass and energy release data are based on maximum Safety Injection flow rates, that is, assuming offsite power is available. The last data entry is for time 573.273 seconds. It is before this time that the Safety Injection Phase is implicitly modeled in Card Series 801 of the COPATTA Code. And, it is before this time that Card Series 601 is used to model spillage of the Safety Injection flow. -

l

a. REACTOR VESSEL SPIILAGE Reactor vessel spil' age is that spillage to the containment sump which occurs when some fraction of the safety injection flow that enters the primary part of the NSSS overfills the reactor vessel, and overflows out thmugh the break hole. Because this spillage has first mixed with the remaming fluid in the reactor vessel, it is characterized by the thermal properties (temperaturd cf the reactor vessel fluid inventory. Maximizing reactor vessel mass and energy spillage conservatively maximizes the temperature of the containment sump water inventory. Maximizing the sump temperature minimizes the effectiveness of the Containment Spray System to reduce the containment air energy.

" Blowdown" phase reactor vessel so_ illace (0 s t s 22.0 sec)

CE Letter S-CE-2604 (Appendix A, Table 1-1), states that for the case of the double ended suction leg slot (DESLS) break, the blowdown phase ends at 22 seconds.

Appendix C to this same letter states that safety injection pump flow was not modeled during blowdown since the end of blowdown occurred before the postulated thirty second delay in obtaining Safety Injection pump flow. Therefore, there is no

" Blowdown" Phase reactor vessel mass and energy spillage release for the DESLS break.

f

NES&L DEPARTMENT CALCULATION SHEET 'l4"gcu uo. ,,c,_ og_

Project or DCP/MMP_S.pfJGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN No. CCN -

i Subject Containment P/T Analysis for Desion Basis LOCA Sheet No. 46 i

j REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 h 5

"Reflood" phase reactor vessel spillage (22.0 < t s ?ll.1 sec)

CE Letter S-CE-2604 (Appendix B, Table 1), provides the "Reflood" Phase reactor

vessel mass and energy spillage data for the DESLS break. The data indicates that j 27.272 x 106 BTU of energy, and 245322 lbm of mass will spill into the sump at a uniform rate over the time period of 28.00 to 211.10 seconds. Therefore, mass and

! energy spillage is released during the Reflood Phase between 28.00 and 211.10 seconds at constant rates of:

Nia.rioca en. .piii r = (245322 lbm) x (3600 s/hr) / (211.10 - 28.00 s)

] = 4.823 x 106 lbm/ hour

$n.nood m .pm .r. ,

= (27.272 x 106 BTU) x (3600 s/hr) / (211.10 - 28.00 s)

= 5.362 x 108 BTU / hour

" Post-Reflood" phase reactor vessel soillage (211.1 < t s 573.273 sec)

CE Letter S-CE-2604 (Appendix B), states that the " Post-Reflood" reactor vessel mass and energy spillage data for the DESLS break is defined by the difference between a constant total (blowdown plus spillage) mass release rate of 867 lbm/sec and the " Post-Reflood" blowdown mass release rates dermed in Appendix A (Table 1-3) to the same letter. The " Post-Reflood phase reactor vessel mass and energy spillage begins at time 211.101 seconds, and continues until the end of blowdown at 573.273 seconds. The enthalpy of the spillage is assumed to be the 88 BTU /lbm value listed in Appendix B to the letter. The following table presents the results of the calculations that determine the " Post-Reflood" Phase Reactor Vessel Mass & Energy Spillage:

NES&L DEPARTMENT CALCULATION SHEET ' I

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i " POST-REFLOOD" PHASE REACIDR VESSEL MASS & ENERGY SPILLAGE 4

)

NSSS SUPPLIED DATA DATA COMRTED SPILLAGE 7;gg (CE Letter S-CE-2604) FOR COPATTA CODE USE FRACTION IN CARD SERIES 601 SPILLAGE + BREAK SPILLAGE SPILLAGE SPILLAGE BREAK MASS MASS ENTHALPY MASS ENERGY FLOW RATE FLOW RATE FLOW RATE FLOW RATE (sec) Obm/sec) Obm/sec) (BTU /lbm) (Ibm /hr) (BTU /hr) (unitiess) 211.101 867 624.38 88 8.73e +05 7.7e + 07 0.28 211.336 867 621.62 88 8.83e +05 7.8e + 07 0.28 211.573 867 618.86 88 8.93e +05 7.9e +07 0.29 211.812 867 616.09 88 9.03e + 05 7.9e + 07 0.29 212.052 867 613.33 88 9.13e + 05 8.0e + 07 0.29 213.026 867 600.41 88 9.60e +05 8.4e +07 0.31 215.073 867 568.58 88 1.07e +06 9.5e +07 0.34 216.989 867 540.72 88 1.17e +06 1.0e +08 0.38 219.039 867 512.88 88 1.27e +06 1 le+08 0.41 221.233 867 485.07 88 1.37e +06 1.2e + 08 0.44 222.894 867 465.22 88 1.45e + 06 1.3e +08 0.46 225.021 867 441.42 88 1.53e +% 1.3e +08 0.49 226.920 867 421.64 88 1.60e +06 1.4e + 08 0.51 228.953 867 401.90 88 1.67e +06 1.5e +08 0.54 231.139 867 382.21 88 1.75e +06 1.5e + 08 0.56 233.014 867 366.51 88 1.80e +C6 1.6e + 08 0.58 235.017 867 350.86 88 1.8UO6 1.6e + 08 0.60 237.167 ' 867 335.27 88 1.91e +06 1.7e +08 0.61 238.890 867 323.52 88 1.96e +06 1.7e + 08 0.63 240.719 867 312.00 88 2.00e +06 1.8e + 08 0.64 242.668 867 300.44 88 2.04e +06 1.8e + 08 0.65 245.484 867 285.13 88 2.09e +06 1.8e + 08 0.67 246.897 867 277.52 88 2.12e +06 1.9e + 08 0.68 249.420 867 266.17 88 2.16e +06 1.9e + 08 0.69 251.151 867 258.64 88 2.19e +06 1.9e +08 0.70

NES&L DEPARTMENT.

CALCULATION SHEET ',Reu'" " $CN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 48 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5

" POST REFLOOD' PHASE REAC'IUR VESSEL MASS & ENERGY SPILLAGE NSSS SUPPLIED DATA DATA CONVERTED SPILLAGE TIME FOR COPATTA CODE USE (CE Letter S.CE-2604) FRACTION IN CARD SERIES 601 SPILLAGE + BREAK SPILLAGE SPILLAGE SPILLAGE BR'3AK MASS MASS ENTHALPY MASS ENERGY FLOW RATE FLOW RATE FLOW RATE FLOW RATE (sec) Obm/sec) (Ibm /sec) (BTU /lbm) (Ibm /hr) (BTU /hr) (unitiess) 254.936 867 243.74 88 2.24e + 06 2.0e +08 0.72 259.251 867 229.06 88 2.30e +06 2.0e +08 0.74 262.929 867 218.23 88 2.34e + 06 2.le + 08 0.75 267.086 867 207.58 88 2.37e +06 2.le + 08 0.76 271.855 867 197.15 88 2.41e +06 2.le + 08 0.77 281.634 867 180.41 88 2.47e +06 2.2e +08 0.79 292.060 867 167.81 88 2.52e +06 2.2e +08 0.81 302.415 867 158.99 88 2.55e +06 2.2e + 08 0.82 311.215 867 153.49 88 2.57e +06 2.3e + 08 0.82 321.094 867 148.88 88 2.59e +06 2.3e + 08 0.83 331.360 867 145.31 88 2.60e +06 2.3e + 08 0.83 340.999 867 142.78 88 2.61e + 06 2.3e +08 0.84 351.095 867 140.73 88 2.61e + 06 2.3e + 08 0.84 361.352 867 139.11 88 2.62e +06 2.3e +08 0.84 371.311 867 137.88 88 2.62e +06 2.3e+08 0.84 391.750 867 136.04 88 2.63e +06 2.3e +08 0.84 411.491 867 134.85 88 2.64e + 06 2.3e +08 0.34 432.076 867 133.98 88 2.64e + 06 2.3e +08 0.85 452.069 867 133.37 88 2.64e + 06 2.3e + 08 0.85 471.774 867 132.92 88 2.64e + 06 2.3e + 08 0.85 524.047 867 132.16 88 2.65e +06 2.3e + 08 0.85 573.273 867 131.74 88 2.65e +06 2.3e + 08 0.85 gm . - - , , -

l NES&L DEPARTMENT l

CALCULATION SHEET 'cca '

PRELIM. CCN No. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSloN:

CcN No. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 49 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R O R. Nakano 01/18/94 J. Elliott 01/20/94 5

b. DIRECT FLOOR SPILLAGE l

1 CE Ixtter S-CE-2604 (Reference 6.2.a, Appendix C), states that direct floor spillage is that j spillage to the containment floor which occurs when some fraction of the safety injection 1 l flow does not actually enter the primary part of the NSSS, but instead is injected directly into ~

l the containment. Maximizing direct floor mass and energy spillage conservatively reduces  !

cooling of the reactor vessel water inventory, thereby maximizing the steaming of the vessel water inventory, and consequently maximizing the containment pressure and temperature response.

" Blowdown" phase direct floor spillage (0 s t s 22.0 sec) l CE Ietter S-CE-2604 (Appendix A, Table 1-1), states that for the case of the double ended suction leg slot (DESLS) break, the blowdown phase ends at 22 seconds.

l Appendix C to this same letter states that safety injection pump flow was not modeled during blowdown since the end of blowdown occurred before the postulated thiny l

second delay in obtaining Safety Injection pump flow. Therefore, there is no

" Blowdown" Phase direct floor mass and spillage release for the DESLS break.

l "Reflood" phase direct floor soillage (22.0 < t s 211.1 sec)

Reactor Coolant System P&ID 40111A (Reference 6.8.a), shows that each of the four l safety injection nozzles are located, respectively, in the fou; RCS Pump discharge i

legs. CE Letter S-CE-2604 (Appendix C), states that with this armngement there is '

! no "Reflood" Phase direct floor mass and energy spillage data for the DESLS break.

l The concept behind this assumption is that the RCS Pumps act as check valves, not allowing backficw to the DESLS break location.

l l " Post-Reflood" chase direct floor spillage (211.1 < t s 573.273 sec)

Reactor Coolant System P&ID 40111 A shows that each of the four safety injection l

nozzles are located, respectively, in the four RCS Pump discharge legs. CE Letter S-CE-2604 (Appendix C), states that with this arrangement there is no " Post-Reflood" Phase direct floor mass and energy spillage data for the DESLS break. The concept behind this assumption is that the RCS Pumps act as check valves, not allowing backflow to the DESIE break location.

NES&L DEPARTMENT CALCULATION SHEET 'cc" "os PRELIM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analvsis for Desion Basis LOCA Sheet No. 50 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 E S

4.10 CARD SERIES 801 l a. INJECTION MODE CHARACTERISTICS Initially the Containment Spray System (CSS) draws water from the Refueling Water Storage Tank (RWST) upon receipt of a Containment Spray Actuation Signal (CSAS). Per the Engineered Safety Features Actuation System (ESFAS) System Description (Reference 6.7.d, section 2.1.2.1.4), a CSAS is generated upon receipt of two out of four high-high Containment pressures and a Safety Injection Actuation Signal (SIAS). Per Section 2.1.2.1.1 of the ESFAS System Description, a SIAS is generated upon receipt of two out of four low pressurizer pressures or a high containment pressure.

a.1 Injection Mode Start Times a.1.(a) Contamment Spray System Injection Mode Start Time With a loss of offsite power, the containment spray would be functional within 59 seconds per Calculation N-4080-003 (Reference 6.1.h, Section 8.2). To provide margin to address any future changes in system perfomiance, this analysis assumes that the time of containment spray initiation with a loss of offsite power is 60 seconds. The initiation time of 60 seconds is consistent with the initiation time modeled in previous LOCA analyses, including Calculation N-4080-002 (Reference 6.1.g).

Delaying the start of the containment spray system operation conservatively delays the removal of containment atmosphere energy via the CSS, thereby maintaining a larger containment air energy inventory that will increase the maximum containment pressure and temperature.

Once initiated, the containment spray system operates for the duration of the accident. The design basis LOCA is non-isolable and nomial shutdown cooling cannot be established.

Therefore, continued operation of the spray system following the injection mode, during long-term contaimnent cooling, to recirculate the containment sump water through the SDHX is essential for reactor decay heat removal and sump water cooling.

a.l.(b) Safety Injection System Injection Mode Start Time The Safety Injection System (SIS) supplies water to the reactor via pressurized discharge from the Safety Injection Tanks (SITS) as well as via pumped flow from the RWST upon

1 i 1 i NES&L DEPARTMENT CALCULATION SHEET ' ,c" "%cu no.

l, ,,,, o, Proj ct or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CoNVERSloN:

l CCN No. CCN -

Subject Containrnent P/T Analysis for Desian Basis LOCA Sheet No. 51 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 4

l l

receipt of a Safety Injection Actuation Signal (SIAS). Per the ESFAS System Description (Reference 6.7.d, Section 2.1.2.1.1), a SIAS is generated upon receipt of two out of four l low pressurizer pressures or a high containment pressure.

SIS pumped flow during the early stages of the LOCA is implicitly addressed in the mass and energy release data provided in CE Letter S-CE-2604 (Reference 6.2.a). As such, the

initial SIS flow characteristics need not be modeled explicitly as input data to the COPATTA Code until the end of the CE provided mass and energy release. The final mass and energy 2

release data entry for the 9.82 ft double ended suction leg slot break mass and energy release data entry is for time 573.273 seconds. It is only after this time that Card Series 801 of the COPA'ITA Code will be used to explicitly model the SIS Injection Mode flow characteristics. I Although the SIS Injection Mode is not explicitly modeled in the COPATTA Code until the  !

end of the mass and energy release at 573.273 seconds, knowledge of the true safety injection start time is needed to assist in the determination of when the Recirculation Actuation Signal is initiated. Appendix C to CE Ietter S-CE-2604 states that 9 30 secend l delay is postulated prior to the occurrence of safety injection pump flow. This time is later than the safety injection flow start time of 12 seconds indicated by the flow data presented in CE Letter S-CE-3129 (Reference 6.2.b, Appendix D, page D-1). Engineering judgement dictates that the safety injection flow start time of 12 seconds is actually the start of flow from the nitrogen pressurized SITS. Therelore, a SIS Injection Mode start time of 30 l seconds will be used in evaluating RWST inventory depletion.

a.l.(c) Charging System Injection Mode Start Time The charging system supplies water to the Safety Injection System from the RWST upon receipt of a SIAS. Per the ESFAS System Description (Reference 6.7.d, Section 2.1.2.1.1),

a SIAS is generated upon receipt of two out of four low pressurizer pressures or a high containment pressure. In responding to the SIAS, the LPSI and HPSI pumps first deliver flow to the SIS at time 30 seconds (see section a.1.(b) above). It is assumed that in responding to the SIAS, the charging pumps also deliver flow to the SIS at time 30 seconds.

l a.2 Injection Mode Flow Rates I

a.2.(a) Containment Spray Systerr mjectDn Mode Flow Rate i l

1

NES&L DEPARTMENT CALCULATION SHEET l' 4LWou no. ,,c, o, Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSloN:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 52 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE BRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 h 5

A CSS injection mode volumetric flow rate of 1612 gallons / minute will be modeled beginning at the time that a full flow spray pattern is initiated at the spray nozzles, and continuing until the recirculation mode begins. This flow rate of 1612 gallons / minute represents the minimum CSS injection mode flow rate, and is calculated in Calculation M-0014-009 (Reference 6.1.b, page 15). This flow rate is for the conditions of a CSS Pump degradation of 7.5 percent, a containment peak pressure of 60 psig, and a minimum RWST water level of 33.35 feet.

Minimizing the CSS injection mode flow rate reduces the amount of spray water available to mmove energy from the containment air space, thereby maximizing the contamment pressures and temperatures.

At an injection mode water temperature of 100 *F (see section a.3 below), the containment spray flow rate of 1612 gallons / minute has a specific volume of 0.016130 ft $/ pound (Reference 6.16, page 88), and will be modeled in Card Series 801 with a mass flow rate of:

IN = [(1612 gallons / min) + (0.016130 ft2 /lbm)] x (0.13368 ft /$ gallon) x (60 min / hour)

M = 8.02e5 pounds / hour l a.2.(b) Safety Injection System Injection Mode Flow Rate CE Letter S-CE-2604 (Refemnce 6.2.a) provides the 9.82 ft2 double ended suction leg slot break mass and energy release data. To ensure consistency with the safety injection assumptions employed in the LOCA mass and energy release model of Appendix H to CE Letter S-CE-2604, this calculation will model a maximum Safety Injection scenario by basing the calculations on both HPSI headers and two of the three'HPSI pumps being operational, as well as the sole LPSI header and both LPSI pumps.

Per Appendix H to CE Letter S-CE-2604, each of the two HPSI pumps is capable of delivering 660 gallons / minute, and each of the two LPSI pumps is capable of delivering l 2750 callons/ minute. If additive, one would calculate that the total SIS injection mode flow l rate prior to recirculation would be 6820 gallons / minute, representing a HPSI pumps flow rate of 1320 gallons / minute (2 pumps at 660 gpm/HPSI pump) and a LPSI pumps flow mte

] of 5500 gallons / minute (2 pumps at 2750 gpm/LPSI pump).

. However, the flows are not additive. When two pumps supply flow to the same piping j'

header, the pressure effects associated with the common header cause the delivered flow to be less than the delivered flow associated with having the two pumps supply flow to separate headers. As noted previously, the two HPSI pumps deliver flow to two separate HPSI i

NES&L DEPARTMENT CALCULATION SHEET l' 4"fgca uc. ,,c,_ o,_

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CoNVERSloN:

CCN NO. CCN -

Subject Containment PTT Analysis for Desian Basis LOCA Sheet No. 53 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

[ 4 i headers, while the two LPSI pumps feed a common LPSI header. Therefore, engineering

judgement dictates that the HPSI pumps would still provide a total flow rate of 1320 l

gallons / minute, but that the LPSI pumps would provide a total flow rate of less than 5500 '

gallons / minute.

The lower total SIS injection mode flow rate is confirmed by Appendix B to CE Letter S-CE-2604 which states that the safety injection input mass flow rate is 867 pounds /second. l At an injection mode water temperature of 100 *F (see section a.3 below), this safety injection flow has a specific volume of 0.016130 ft'/ pound (Reference 6.16, page 88), and is equivalent to a flow rate of 6277 gallons / minute:

Q31,w = (867 lbm/sec) x (0.016130 ft'/lbm) x (7.4805 gal /ft 8) x (60 sec/ min)

Q31,w = 6277 gal / min It is this safety injection pumped flow rate that is modeled in Card Series 801 as:

1(i = (867 pounds / seconds) x (3600 seconds / hour) lii = 3.12e6 pounds / hour This equates to a flow rate of 4957 gallons / minute for the LPSI pumps, which is less than 5500 gallons / minute (2 pumps @ 2750 gpm/LPSI pump):

Qursi = 6277 gal / min - 1320 gal / min Qups, = 4957 gal / min a.2.(c) Charging System Injection Mode Flow Rate Per CVCS System Description SD-S023-390 (Reference 6.7.b, Part 1, Section 2.2.26), the three charging pumps each have a nominal pump flow rate of 44 gpm. Per Technical Specification LCO 3.1.2.1 (References 6.3.a & b), as a minimum, one boron injection flow path shall be operable, and this flow path should utilize o e charging pump. Per CVCS System Description SD-S023-390 all three pumps start a a SIAS. In this calculation, a j total of three charging pumps will be modeled, and the total charging flow rate will be: l l Qcycs,W = (44 gallons / minute) x (3 pumps) = 132 gallons / minute Maximizing the number of pumps nmning will quicken the drammg of the RWST. The time l of occurrence of peak containment pressure and temperature is dependent on the start of the CSS injection mode. Therefore, the time of CSS recirculation mode initiation will have no l

l __

i NES&L DEPARTMENT CALCULATION SHEET ""

!'!Euu%cN uo. race or Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-02fi CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 54 REV ORIGINATOR DATE lRE DATE REV ORIGINATOR DATE 4 1RE DATE R O R. Nakano 01/18/94 J. Elliott 01/20/94 "

]

5 4

impact on the containment peak pressure or temperature. However, accelerating the CSS and SIS recirculation mode initiation will hasten the switch from spmy droplets composed of relatively cold RWST water to droplets composed of relatively hot containment sump water.

Increasing the spray droplet water temperature reduces the ability of the spray droplets to remove energy from the contaimnent air space, thereby maximizing the containment pressures and temperatures during the recirculation phase of the LOCA analysis.

a.3 Injection Mode Water Temperature / Source The SIS and CSS initially draw water from the RWST upon receipt of a SIAS, and subsequently from the Containment Sump upon receipt of a Recirculation Actuation Signal (RAS). Technical Specification LCO 3.5.4(c) (References 6.3.a & b) indicates that the maximum allowable RWST temperature is 100 *F. It is assumed that the SIS and CSS flow l

during the Injection Mode is at this maximum allowable RWST temperature of 100 F. l Maximizing the RWST water temperature increases the CSS injection mode water droplet temperature. Incmasing the spmy droplet water tempemture reduces the ability of the spray droplets to remove energy from the containment air space, thereby maximizing the containment pressures and temperatures.

l The introduction of safety injection water into the reactor coolant system provides additional l mass and energy that will be eventually introduced into the containment air space. An j increase in the safety injection water temperature results in a decrease in the amount of

, energy required to convert the safety injection liquid water to steam. Therefore, maxumzmg j the safety injection water temperature allows for more energy to be released into the i Containment air space, thereby maximizing containment pressums and temperatures.

a.4. Injection Mode Safety Injection System Spillage i The injection mode SIS spillage is discussed in Design Input Item 4.10.b.4.

4 1

(

NES&L DEPARTMENT CALCULATION SHEET 'cc".

PRELIMCCN Wo. PAGE_ OF_

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desion Basis LOCA Sheet No. 55 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5

b. RECIRCULATION MODE CHARACTERISTICS s

b.1 Recirculation Mode Start Time The Recirculation Actuation Signal (RAS) is designed to change suction of the HPSI and CS i pumps from the RWST to the Containment Emergency Sump when the RWST level is low. j The source of CSS and SIS water transfers from the RWST to the containment sump upon l receipt of a RAS. Per the ESFAS System Description (Reference 6.7.d, section 2.1.2.1.7),

an RAS is generated upon receipt of two out of four RWST low level signals. During the i injection mode the RWST water is discharged in the form of containment spray, safety injection, and charging flow. To determine the time of CSS and SIS recirculation mode initiation it is necessary to quantify the useable RWST water volume, the flow rates exiting

, the RWST during the injection mode, and the time that these flow rates begin their injection

! mode discharge. j l

l The useful RWST volume is modeled as 300,000 gallons. CE Letter S-CE-6814 (Reference 6.2.d) states that the volume required for injection is 313,706 gallons when instrument error of the RWST low level setpoint and the RAS setpoint are considered, and 300,000 gallons when this instmment error is not considered. Per CE Ietter S-CE-6814, these minimum tmnsfer volumes are sufficient to allow at least 20 minutes of combined HPSI/LPSI flow to the RCS prior to recirculation mode (in which only the HPSI pumps provide flow to the RCS). In this calculation, the RWST volume is minimized to hasten the start of the recirculation mode. The RWST volume used is consistent with the injection phase RWST volume requirement given in Section VII of Calculation N-02404)06 (Reference 6.1.j)

With a loss of offsite power (LOP), the CSS establishes a spray flow of 1612 gallons / minute beginning at time 60 seconds (see discussion of time of CSS injection mode initiation).

With a maximum SI scenario, the two HPSI pumps and the two LPSI pumps discharge a total of 6277 gallons / minute beginning at time 30 seconds (see discussion of time of SIS l injection mode initiation).

The three charging pumps discharge 132 gallons / minute beginning at time 30 seconds (see discussion of time of charging pumps injection mode initiation).

Based on these flow rates and times, the solutions of the following equations indicate that the RWST will deplete its useable water volume of 300,000 gallons in 2280 seconds with a loss of offsite power:

l

r l NES&L DEPARTMENT l

CALCULATION SHEET 'ccs$c, n no. ,,,,_ o,_

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CoNVERSloN:

CCN No. CCN - '

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 56 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

4 Vasr = 300000 gallons

= [(6277 gpm) x (tms - 30 sec) / (60 sec/ min)] '

+ [(1612 gpm) x (t.s - 60 sec) / (60 sec/ min)]

+ [(132 gpm) x (t w - 30 sec) / (60 sec/ min)]

l tma,wwp = 2280 seconds l

l 3

The time of occurTence of peak containment pressure and tempenture is dependent on the l start of the CSS injection mode. Therefore, the time of CSS recirculation mode initiation l will have no impact on the containment peak pressure or temperature. However, accelerating the CSS and SIS recirculation mode initiation will hasten the switch from spray droplets composed of relatively cold RWST water to droplets composed of relatively hot contaimnent sump water. Increasing the spmy droplet water temperature reduces the ability of the spray droplets to remove energy fmm the containment air space, thereby maximizing the containment pressures and temperatures.

l l

b.2 Recirculation Mode Flow Rates  !

b.2.(a) Containment Spmy System Recirculation Mode Flow Rate A CSS recirculation mode volumetric flow rate of 1991 gallons / minute begins coincident with the conclusion of flow realignment following the RAS, and continuing for the duration of the accident. This flow rate is determined by Calculation M-0014-009 (Reference 6.1.b, page 15) for the condition of CSS Pump degradation of 7.5 percent, and 225 *F sump water.

The time of occurrence of peak containment pressure and temperature is dependent on the start of the CSS injection mode. Therefore, the CSS recirculation mode flow rate will have no impact on the contamment peak pressure or temperature. However, decreasing the CSS recirculation mode flow rate will reduce the amount of spray water available to remove energy from the containment vapor space, thereby reducing the rate of long term containment l cooldown and depressurization.

At a recirculation mode water temperature of 225 *F (see following discussion), the 4

containment spmy flow rate of 1991 gallons / minute has a specific volume of 0.016812 ft 3/ pound (Reference 6.16, page 86), and will be modeled in Card Series 801 with a mass flow rate of:

NES&L DEPARTMENT CALCULATION SHEET 'cc" "o ' 1 PREUM. CCN Wo. PAGE__ oF_ 1 Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CoNVERSloN:

ccN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 57 REV ORIGINATOH DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 h ;

=

• 14 = [(1991 gallons / min) + (0.016812 ft'/lbm)] x (0.13368 ft'/ gallon) x (60 min / hour) l M = 9.50e5 pounds / hour i

f l t l l b.2.(b) Safety Injection System Recirculation Mode Flow Rate Per ESFAS System Description SD-SO23-720 (Reference 6.7.d, SDCN 1-1), upon 3

generation of a RAS, the LPSI pumps are stopped, and the suction of the HPSI and CS I pumps transfer from just the RWST to the combined path of the RWST and Containment I Sump and then operator action isolates the RWST from the HPSI and CS pump suction lines.

A maximum Safety Injection scenario is modeled to ensure consistency with the SI assumptions employed in the LOCA mass and energy release model. CE Ietter S-CE-2604 (Reference 6,2.a) provides the 9.82 ft 2double ended suction leg slot (DESLS) break mass and energy release data.

l l During recirculation the flow rate will be from the two HPSI pumps only. Therefore the total SIS injection mode flow rate after the start of recirculation is:

Qsr.=in: = 2 pumps @ 660 gpm/HPSI pump = 1320 gal / min L

At a recirculation mode water temperature of 225 'F, the safety injection flow rate of 1320  ;

gallons / minute has a specific volume of 0.016812 ft'/ pound (Reference 6.16, page 86), and '

will be modeled in Card Series 801 with a mass flow rate of:

l 14 = [(1320 gallons / min) + (0.016812 ft3 /lbm)] x (0.13368 ft'/ gallon) x (60 min / hour)

M = 6.30e5 pounds / hour

~

The introduction of safety injection water into the reactor coolant system provides additional mass and energy that will be eventually introduced into the containment air space.

The introductory text to CE Letter S-CE-2604 states that the LOCA (blowdown) analysis has been performed conservatively assuming maximum safety injection flow rates. This conclusion is echoed in Appendix I to CE Letter S CE-2604 (Section 6.2.1.3.7) which states that maximum safety injection flows are conservative for calculating containment peak

l. pressures, and that maximum SIS flows were used in the generation of all LOCA mass and

energy release data.

l

NES&L DEPARTMENT CALCULATION SHEET ""> l PRELIM. CCN NO. PAGE__ oF _  !

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION: l l CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 58 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 b.3 Recirculation Mode Water Temperature / Source Per ESFAS System Description SD-SO23-720 (Reference 6.7.d, SDCN 1-1), upon generation of a RAS, the LPSI pumps are stopped, and the suction of the HPSI and CS pumps transfer from just the RWST to the combined path of the RWST and Containment Sump and then operator action isolates the RWST from the HPSI and CS pump suction lines.

Previous analysis contained in Calculation N-4080-002 (Reference 6.1.g, page 7) indicates that the containment sump water temperature is above 200 *F during the first two hours of the LOCA event. And, as previously discussed, the maximum allowable RWST temperature is 100 *F. In this calculation, it is assumed that only the Containment Sump supplies the water to the HPSI and CS pumps during the recirculation mode. When the source of water is the containment sump, the temperature of the CS and the SI is the time dependent temperature of the sump and the COPATTA code will use the intemally calculated sump temperature. . This conservatively maximizes the temperature of the recirculation mode water.

Maximizing the recirculation mode water temperature increases the CSS recirculation mode water droplet temperature. Increasing the spray droplet water temperature reduces the ability l of the spray droplets to remove energy from the containment air space, thereby maximizing the containment pressures and temperatures.

The introduction of safety injection water into the reactor coolant system pmvides additional mass and energy that will be eventually introduced into the containment air space. An l increase in the safety injection water temperature results in a decrease in the amount of energy required to convert the safety injection liquid water to steam. Therefore, maximizing the safety injection water temperature allows for more energy to be released into the Contamment air space, thereby maximizing contamment pressures and temperatures.

b.4. Recirculation Mode Safety Injection System Spillage Not all of the Safety Injection water actually enters the reactor vessel. Prior to recirculation, if the postulated accident is modeled assuming that all SI flow enters the vessel, the input cold (100 *F) water will absorb the heat input with no boiloff, and actually cool down the reactor vessel water below saturation. (This was determined in Calculation N-0880-015 (reference 6.1.f). The ultimate pressures and temperatures will increase by accounting for spillage.

l

NES&L DEPARTMENT CALCULATION SHEET 'lni;$o, uo. ,,,,_ o,.__

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CoNVERSloN:

CCN No. CCN -

Subject Containrnent P/T Analysis for Desian Basis LOCA Sheet No. 59 REV ORIGINATOR DATE IRE DATE REV ORICINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 The fraction of SI flow that is spilled directly to the containment sump is included in the l

NSSS-supplied data provided by CE letter S-CE-2604 (Reference 6.2.a) up to time i t = 573.273 seconds following the begmning of the postulated accident.

From t = 573.3 seconds to the beginning of recirculation, and beyond to t = 7200 seconds (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />), the spillage fraction is taken from Calculation N-0880-015, with an adjustment '

made to account for diffemnces in the safety injection flow rates assumed. The new spillage fraction, Su, is calculated using the following method:

mass spilled from reactor vessel = mass entering reactor vessel - mass to be filled.

The mass to be filled is a constant, but the spillage fraction and the mass entering the reactor vessel change with time. The amount of mass entering the reactor vessel at various times that are to be modeled in this calculation am as given in the preceding sections. These mass flows are used with the spillage fmetions and mass entering given in Calculation N-0880-015 to determine the spillage fractions used in this calculation.

Mg , oyg = Mgy, oys - Myrtz S new = M gy, n,, - My,u, S *1d o = Mgg, ,, g Sy=

M gs Mg ,oys - Msz.old = Mg ,n,,- Mg ,,,,,

NES&L DEPARTMENT CALCULATION SHEET '

'cc" ". CCM NO.

PRELIM PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN - .

l

\

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 60 l l

l REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R l 0 R. Nakano 01/18/94 J. Elliott 01/20/94 h

s l 1

l l dividing all by M .old sz and mulplying M,,,,, by M**'"*" g

, we ge t sz,new Mg ,,,s _ Msz,old , Ms.ne, Mgr ,n,, _

Msz,new Msz. old Msz.old Msz,old M gy,,,, Mgg,,yg l

g M gy,,,, Mgy,n,,

_3,g _

Nsz,old Mgz,,yg M##'"*"

So -1= ( Sy - 1)

Msz, old sr.old (S o - 1) = Sy -1 sz,new l

Sy=1+ *1# ( oS - 1) sz,nev l

l where, Msr.,,, = New SI flow rate entering the reactor vessel from Design Input Items 4.10.a.2.(b) and 4.10.b.2.(b)

Msi,oa = SI flow rate entering the reactor vessel from Calculation N-880-015 Ms,,,, = New mass spilled out of reactor vessel Ms oa = mass spilled out of reactor vessel from Calculation N-880-015 So = Spillage fraction from Calculation N-880-015 Su = Adjusted spillage fraction By including spillago in the model, artificially lowering the reactor vessel water temperature below saturation will Se avoided, resulting in increased contamment pressure and temperature.

The following table shows the calculation of the adjusted spillage fraction from t= 573.273 seconds to t=7200 seconds into the LOCA.

l

[

f I

NES&L DEPARTMENT CALCULATION SHEET 'cc" "o '

PRELIM. CCN NO. PAG E._, OF_

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 61 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 h

4 SPILLAGE FRACTION FROM TIME T=573.273 SECONDS TO T=7200 SECONDS TIME SAFETY INJECTION FLOW RATES SPILLAGE FRACTION (10' 1b/hr)

(seconds) fr m Calculation New SIS flow from Calculation Adjusted for N-0880-015 p.13 rate N-0880-015 p.13 new parameters

{

573.300 2.710 3.12 .884 .90  !

600 2.710 3.12 .885 .90 700 2.710 3.12 .887 .90 800 2.710 3.12 .890 .90 900 2.710 3.12 .893 .91 1000 2.710 3.12 .896 .91 1500 2.710 3.12 .906 .92

2000 2.710 3.12 .918 .93 l

2280 2.710 .630 .923 (interpolated) .67 3000 2.710 .630 .926 .68 4000 .422 .630 .528 .68 5000 .422 .630 .557 .70 1

6000 .422 .630 .586 .72 l

~

7200 (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) .422 .630 .601 (interpolated) .73

c. LONG-TERM RECIRCULATION MODE CHARACTERISTICS l

c.1 Long-Tenn Recirculation Mode Start Time Per Emergency Operating Instmetion SO23-12-3 (Reference 6.3.d, Action 23b), at i

approximately two hours into the LOCA, the high pressure portion of the Safety Injection i System will be realigned by the Operator for simultaneous hot and cold injection. Per System Description SD-SO23-740 (Reference 6.7.e, Section 3.3.3), in this mode of operation the Safety Injection System is aligned so that approximately 50 percent of the flow delivered

NES&L DEPARTMENT CALCULATION SHEET 'c "'

PREUM. cCN No. PAGE oF Project or DCP/MMP SONGS Units 2 & 3 Calc. iJo. N-4080-026 cCN CoNVERSloN:

ccN No. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 62 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 1 I

by each HPSI pump goes into the hot legs, and appmximately 50 percent goes into the cold legs.

i c.2 Long-Term Recirculation Mode Flow Rates c.2.(a) Containment Spray System Long-Term Recirculation Mode Flow Rate During the long-term recirculation mode no changes are made to the Contamment Spray System flow rate established during the recirculation mode. As in the recirculation mode, a CSS long-term recirculation mode volumetric flow rate of 1991 gallons / minute is modeled.

This flow rate is determined by Calculation M-0014-009 (Reference 6.1.b, page 15), and is for the condition of CSS Pump degradation of 7.5 percent, and 225 'F sump water.

The time of occurrence of peak containment pressure and temperature is dependent on the start of the CSS injection mode. Therefore, the CSS long-term recirculation mode flow rate will have no impact on the containment peak pressure or temperature. However, decreasing the CSS long-term recirculation mode flow rate will reduce the amount of spray water available to remove energy from the containment air space, thereby sustaining the initially high containment pressures and temperatures over the long term.

At a long term recirculation mode water temperature of 225 *F, the containment spray flow rate of 1991 gallons / minute has a specific volume of 0.016812 ft'/ pound (Reference 6.16, page 86), and will be modeled in Card Series 801 with a mass flow rate of:

M = [(1991 gallons / min) + (0.016812 ft3/lbm)] x (0.13368 ft'/ gallon) x (60 min / hour)

M = 9.5e5 pounds / hour

)

c.2.(b) Safety Injection System Long-Term Recirculation Mode Flow Rate Per ESFAS System Description SD-SO23-720 (Reference 6.7.d, SDCN 1-1), upon generation of a RAS, the LPSI pumps are stopped, and the suction of the HPSI and CS pumps transfer from just the RWST to the combined path of the RWST and Containment Sump and then operator action isolates the RWST from the HPSI and CS pump suction lines.

A maximum Safety Injection scenario is modeled to ensure consistency with the SI assumptions employed in the LOCA mass and energy release model. CE Ietter S-CE-2604 (Reference 6.2.a) provides the 9.82 ft 2double ended suction leg slot (DESLS) break mass 1

NES&L DEPARTMENT r CALCULATION SHEET 'c"" '

j PRELIM. CCN NO. PAGE__ OF_

l Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. _63 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 h 5

and energy release data. The mass and energy release calculations will be modeled with both HPSI headers and two of the three HPSI pumps operational.

Per Appendix H to CE Letter S-CE-2604, each HPSI pumps delivers 660 gallons / minute.

Therefore the total SIS injection mode flow rate after the start of recirculation is:

Q31, w = 2 pumps x 660 gpm/HPSIP .

Q31,m % = 1320 gal / min l l

At a recirculation mode water temperature of 225 F, the safety injection flow rate of 1320 gallons / minute has a specific volume of 0.016812 ft'/ pound (Reference 6.16, page 86), and will be modeled in Card Series 801 with a mass flow rate of:

M = [(1320 gallons / min) + (0.016812 ft3/lbm)] x (0.13368 ft /3 gallon) x (60 min / hour)

M = 6.3e5 pounds / hour The introduction of safety injection water into the reactor coolant system pmvides additional mass and energy that will be eventually introduced into the containment air space. The  ;

introductory text to CE Letter S-CE-2604 states that the LOCA (blowdown) analysis has  ;

been performed conservatively assuming maximum safety injection flow rates. This conclusion is echoed in Appendix I to CE Letter S-CE-2604 (Section 6.2.1.3.7) which states that maximum safety injection flows are conservative for calculating contamment peak pressures, and that maximum SIS flows were used in the generation of all LOCA mass and l energy release data.

c.3 Long-Term Recirculation Mode Water Temperature ~

Per ESFAS System Description SD-SO23-720 (Reference 6.7.d, SDCN 1-1), upon generation of a RAS, the LPSI pumps are stopped, and the suction of the HPSI and CS pumps transfer from just the RWST to the combined path of the RWST and Containment i Sump and then operator action isolates the RWST from the HPSI and CS pump suction lines.

Previous analysis contained in Calculation N-4080-002 (Reference 6.1.g, page 7) indicates that the containment sump water temperature is above 110 *F after the first two hours of the LOCA event. And, as previously discussed, the maximum allowable RWST temperature is 100 F. In this calculation, it is assumed that only the Containment Sump supplies the water to the HPSI and CS pumps during the long-term recirculation mode. When the source of I

water is the contamment sump, the temperature of the CS and the SI is the time dependent temperature of the sump and the COPATTA code will use the internally calculated sump l

NES&L DEPARTMENT CALCULATION SHEET 'cc" PRELIM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. NO. N-4080-026 ' CCN CONVERSION:

CCN NO. CCN -

Subject _Qontainment P/T Analysis for Desian Basis LOCA Sheet No. 64 REV ORIGINATOR DATE BRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

4 temperature. This conservatively maximizes the temperature of the long-term recirculation mode water.

Maximizing the long-term recirculation mode water temperature increases the CSS long-term recirculation mode water droplet temperature. Increasing the spray droplet water temperature reduces the ability of the spray droplets to remove energy from the containment air space, thereby maximizing the containment pressures and temperatures.

The introduction of safety injection water into the reactor coolant system provides additional mass and energy that will be eventually introduced into the containment air space. An incmase in the safety injection water temperature results in a decmase in the amount of energy required to convert the safety injection liquid water to steam. Therefore, maximizing the safety injection water temperature reduces the fraction of the decay and sensible heat used to raise the SI water to the saturation temperature, and increases the fraction of decay and sensible heat which goes into boiling the reactor vessel water. By boiling off more RV water, the quantity of steam generated is greater than with a lower SI long-term recirculation j mode water temperature.

c.4. Long-Term Recirculation Mode Safety Injection System Spillage Per System Description SD-SO23-740 (Reference 6.7.e, Section 3.3.3), in the long-term recirculation mode of operation the Safety Injection System (SIS) is aligned so that approximately 50 percent of the flow delivered by each HPSI pump goes into the hot legs from the reactor vessel to the steam generators, and appmximately 50 percent gaes into the cold legs (i.e., the reactor coolant pumps suction and discharge piping from the steam generators to the reactor vessel). This flow alignment is consistent with the pos:-LOCA Emergency Operating Instmetion SO23-12-3 (Reference 6.3.d, Attachment 17).

Not all of the Safety Injection water remains in the reactor vessel after being introduced by the SI flow. All of the cold leg injection inflow from a single HPSI pump will spill out via the break.

With the double ended suction leg slot (DESLS) break of a cold leg, all hot leg injection flow will mach the vessel core. At 2 hrs, the decay heat energy is about 1.5e8 BTU /hr (Design Input Item 4.6 for Card Series 101) and the sensible energy is about 1.26e7 BTU /hr (Design Input Item 4.7 for Card Series 201). Therefore,1.63e8 BTU /hr (1.5e8 + 1.26e7) is the energy rate at 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> equivalent to the mass of water lost as steam via decay heat and sensible heat boiling the reactor water away. This water loss is replaced by the HPSI flow into the vessel. Any HPSI flow above the mass of water lost due to decay and sensible heats

NES&L DEPARTMENT CALCULATION SHEET 'cc" "o '

PREUM. CCN NO. PAGE oF Proj;ct or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. G5 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 "

4 will spill out onto the floor. The energy required to convert saturated water at 225 'F to saturated steam at an assumed contaimnent pressure of 22 psig (confirmed by summary of results) is 974.7 Btu /lbm (1168.0 - 193.28 from Steam Tables, Reference 6.16, pages 87 and I

94). Therefom, the Safety Injection coolant mass flow that will be needed to replace the water mass loss due the boil-off is:

I S,1 = (1.63e8 BTU / hour) + (974.7 BTU / pound)

M = 1.67e5 pounds / hour l Per Section c.2.(b) the mass flow rate of the two HPSI pumps is 6.3e5 pounds / hour. This is 1 1

3.15e5 pounds / hour for each HPSI pump. The mass of water spilled from the vessel will be '

approximately 1.48 pounds / hour (3.15e5 - 1.67e5). This gives a spillage fraction of about -

0.5. j l I Although the mactor vessel boil-off rate. due to decay heat and sensible energy is less than the rate of the hot leg injection inflow, all of the excess hot leg injection inflow will spill only after passing through the reactor vessel. Since this excess flow is not immediately l spilled after the introduction by the SIS, it is not considered as spilled flow in the Card I Series 801 input.

l Since each of the two HPSI pumps supplies the same flow rate, this scenario implies that 50 percent of the long-term recirculation mode SI flow will spill. Therefore, the spillage factor that modeled in Card Series 801 for times greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> will be 0.50.

l At the start of long-term recirculation mode at two hours, the decay heat and sensible energy l boiloff rate is equivalent to about one-half the flow rate from a single HPSI pump.

l i

l l

e l

1

NES&L DEPARTMENT

! CALCULATION SHEET 'cc""os PRELIM. CCN WO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containtnent P/T Analvsis for Desian Basis LOCA l Sheet No. 66 l

REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R l 0 R. Nakano 01/18/94 J. Elliott 01/20/94 "

l 1

5 l

4.11 CARD SERIES 1101

a. ITEMS 5 and 6: AIR COOLER HEAT REMOVAL RATES l

The air cooler heat removal rate as a function of containment atmosphere saturation tempenture is determined in Calculation M-0072-036 (Reference 6.1.e) for the conditions of a CCWS volumetric flow rate at the inlet to a containment emergency air cooler of 2000 gallons / minute at 105 *F, a constant air flow rate through the air cooler of S

31000 ft / minute, and a water side fouling factor of 5 x 104. The air cooler duty curve detennined in Calculation M-0072-036 is plotted and tabulated on sheets 8 and 10 of that calculation.

The air cooler duty curve detennined in Calculation M-0072-036 includes performance data for a superheated containment condition when the contaimnent atmosphere saturation tempenture exceeds 300 *F (corresponding to a containment atmosphere saturation pressure of 67 psia). The COPATTA Code requires air cooler data for saturated conditions only.

Since the contamment peak temperature determined by previous LOCA P-T analyses has been below 300 *F, data for above 300 *F is considered irrelevant for this calculation.

Card Series 1101 is entered in the input data file as shown in the following table. As an initialization point, when the containment air temperature is equivalent to the CCW temperatum of 105 *F at the inlet to the air cooler, then the air cooler will not remove any heat from the containment air.

i r

I

j NES&L DEPARTMENT CALCULATION SHEET 'cc" " '

PREUM. CCN NO. PAGE,_ OF__

I Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

l Subject Containment P/T Analysis for Desiore Basis LOCA Sheet No. 67 1

j REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R

} O R. Nakano 01/18/94 J. Elliott 01/20/94 '

4 4

i CONTAINMENT AIR COOLER ABIIIn' ID REMOVE AIR ENERGY l

CONTAINMENT ATMOSPHERE AIR COOLER HEAT

SATURATION TEMPERATURE REMOVAL RATE CONTAINMENT (Cale M-0072-036, pg 10) (Cale M-0072-036, pg 10)

Card Series 1101, Item 5 ATMOSPHERE CONDITIONS

Card Series 1101, Item 6 1

('F) (BTU / hour) 105 0.000 Initial Condition 120 1.670e +06 Saturated Condition 130 3.020e +06 Saturated Condition 140 4.570e + 06 Saturated Condition 150 6.320e +06 Saturated Condition 160 8.270e +06 Saturated Condition 170 1.040e +07 Saturated Condition 180 1.273e + 07 Saturated Condition 190 1.523e +07 Saturated Condition 200 1.788e +07 Saturated Condition 210 2.068e + 07 Saturated Condition 220 2.361e +07 Saturated Condition 230 2.664e +07 Saturated Condition 240 2.974e + 07 Saturated Condition 250 3.291e + 07 Saturated Condition 260 3.611e + 07 Saturated Condition 270 3.931e + 07 Saturated Condition 250 4.252e + 07 Saturated Condition 287 4.474e + 07 LOCA Peak Temperature

• 290 4.569e + 07 Saturated Condition 300 4.882e + 07 Saturated Condition 2: 320 N/A Superheated Condition l l

• 1 Previously identified in Calculation N-4080-002 (Reference 6.1.g, page 6) l l

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NES&L DEPARTMENT CALCULATION SHEET 'cc" "o '

PREUM. CCN NO. PAGE _ OF _

Proj ct or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 cCN CoNVERSloN:

CCN No. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 69 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

i 5 1,

4.12 CARD SERIES 1201

a. ITEMS 2 and 3

CONTAINMENT SPRAY HEAT TRANSFER EFFICIENCY Containment spray heat transfer efficiency varies as a function of the ratio of water vapor to

air mass in the containment atmosphere. Data points listed in the following table are extracted from Bechtel Topical Report BN-TOP-3 (Reference 6.11, Revision 4, Section 3.2.6 and Figure 2). Per BN-TOP-3, this data is for a spray system with a mean spray drop diameter of 1000 microns and a drop fall height of 20 feet, and is standard "for virtually all PWR contain:nent analyses".

' Per the UFSAR (Reference 6.3.c, Section 6.2.2.1.2.2.B), the SONGS Units 2&3 mean spray droplet diameter is about 660 microns. Since efficiency is inversely proportional to the diameter, use of spray heat transfer efficiency data applicable to a larger spray drop diameter is conservative. Decreasing the CSS efficiency reduces the ability of the spray droplets to )

, remove energy from the containment air space, thereby maximizing the contamment l pressures and temperatures.

CONTAINMENT SPRAY SYSTEM HEAT TRANSFER EFFICIENCY STEAM TO AIR MASS RATIO SPRAY EFFICIENCY Card Series 1201, Item 2 Card Series 1201, Item 3 (unitiess) (percent) 0.0 72.9 0.1 73.7 0.2 74.7 0.3 75.7 0.4 77.1 0.5 78.8 0.6 80.9 2

0.7 83.2 0.8 86.3 0.9 91.2 4

1.0 96.1 1.1 98.3 1.2 99.5 1.3 100.0

NES&L DEPARTMENT CALCULATION SHEET 'cc" l PRELIM. CCN NO. PAG E_,, OF__,_

l Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION: i CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 70  !

REV ORIGINATOR DATE IRE DATE REV ORIGINATOR l DATE IRE DATE R

)

0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

h s

l l

4.13 HEAT SINK DATA SERIES

a. CONTAINMENT LINER / CONCRETE AIR GAP INTERFACE l In this analysis the effective thickness of the interface (air gap) will be modeled as 0.00035 feet. This value is based on a containment liner to containment concrete interface conductance of 50 BTU /hr-ft2 *F, and an air thermal conductivity of 0.0174 BTU /hr-ft- F.

A typical containment liner to containment concrete interface conductance of 2

50 BTU /hr-ft *F will be modeled. This conductance of 50 BTU /hr-ft2 *F is listed in Bechtel Topical Report BN-TOP-3 (Reference 6.11, Section 3.3.1 and Table 4). Appendix

, A of BN-TOP-3 (page A-4) indicates that an effective one-dimensional interface conductance of this value will ensure a conservative estimate of heat transfer to the containment wall.

There will be some resistance to heat tansfer from the containment atmosphere to the contamment structure at the containment liner-concrete interface due to air gaps or voids between the liner and the concrete. This resistance is accounted for in this interface conductance. Use of a smaller interface conductance is conservative because it will inhibit heat transfer from the containment air to the containment concrete walls, maximize containment air energy, and consequently yield higher containment pressures and

temperatures.

At a long-term average post-accident contaimnent air temperature of 200 *F, Engineerine Heat Transfer (Reference 6.15, Table A-6, page 577) indicates that the air thermal conductivity is 0.0174 BTU /hr-ft *F. The thermal conductivity of a material is a measure of the material's ability to conduct heat. Minimizing a heat sink's thermal conductivity will inhibit heat transfer from the contamment air to the heat sinks. During the early part of an accident this will maximize contamment air energy, and consequently yield higher containment pressures and temperatures.

Based on a containment 2

liner to containment concrete interface conductance (h) of 50 BTU /hr-ft - F, and an air thermal conductivity (k) of 0.0174 BTU /hr-ft- F, the effective thickness of the interface (air gap) will be:

Interface thickness, At = (0.0174 BTU /hr-ft *F) + (50 BTU /hr-ft _op) 2 i

Interface thickness, At = 0.00035 feet l

NES&L DEPARTMENT CALCULATION SHEET ' " '

PRELIM. CCN Wo. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 71 REV ORIGINATOR DATE IP.E DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

4

b. HS #1 - REACTOR BUILDING DOME The characteristics of the Reactor Building Dome am as determined in Calculation N-4080-002 (Reference 6.1.g, pages 121 through 125) for Heat Sink 1, except for the thickness of the Containment Liner / Concrete air gap interface.

l The thickness of the Containment Liner / Concrete air gap interface is modified to address a I change in the containment liner to containment concrete interface conductance, as discussed in Design Input Item 4.13.a.

l

c. HS #2 - REACTOR BUILDING CYLINDER #1 (ABOVE GRADE, BETWEEN EL. 29'6" AND 112'0")

l The characteristics of the Reactor Building Cylinder #1 (above grade, between plant elevations 29'6" and 112'0") are as determined in Calculation N-4080-002 (pages 125 l through 128) for Heat Sink 2, except for the thickness of the Containment Liner / Concrete air gap interface.

The thickness of the Containment Liner / Concrete air gap interface is modified to address a change in the containment liner to containment concrete interface conductance, as discussed in Design Input Item 4.13.a.

d. HS #3 - REACTOR BUILDING CYLINDER #2 (BELOW GRADE, BETWEEN EL.15'0" AND 29'6")

The characteristics of the Reactor Building Cylinder #2 (below grade, between plant elevations 15'0" and 29'6") are as determined in Calculation N-4080-002 (pages 134 through 136) for Heat Sink 3, except for the thickness of the Containment Liner / Concrete air gap interface.

The thickness of the Containment Liner / Concrete air gap interface is modified to address a change in the containment liner to contamment concrete interface conductance, as discussed in Design Input Item 4.13.a.

l NES&L DEPARTMENT CALCULATION SHEET 'cyggcoo.

, ,,,, og Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 72 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 4

e. HS #4 - BASEMAT (OTHER THAN THE REACTOR BASEMAT)

The characteristics of the Basemat (other than the Reactor Basemat) are as determined in Calculation N-4080-002 (pages 137 through 139) for Heat Sink 4.

l f. HS #5 - REACTOR BASEMAT AND STEAM GEhTRATOR PEDESTALS l

The characteristics of the Reactor Basemat and Steam Generator Pedestals are as determined in Calculation N-4080-002 (pages 139 through 141) for Heat Sink 5.

g. HS #6 - REACTOR CAVITY WALLS BELOW EL.15'0"

, The characteristics of the Reactor Cavity Walls below plant elevation 15'0" are as determined in Calculation N-4080-002 (pages 142 through 144) for Heat Sink 6.

l i h. HS #7 - REACTOR CAVITY WALLS ABOVE EL.15'0" The characteristics of the Reactor Cavity Walls above plant elevation 15'0" are as detennined l in Calculation N-4080-002 (pages 144 through 146) for Heat Sink 7.

l 1

i. HS #8 - LINED REFUELING CANAL WALLS The characteristics of the Lined Refueling Canal Walls are~as determined in Calculation l N-4080-002 (pages 146 through 149) for Heat Sink 8.

l l j. HS #9 - STEAM GENERATOR COMPARTMENT WALLS, UNLINED REFUELING CANAL WALLS ABOVE EL. 63'6", AND OTHER INTERIOR WALLS The characteristics of the Steam Generator Compartment Walls, Unlined Refueling Canal Walls above plant elevation 63'6", and Other Interior Walls are as determined in Calculation N-4080-002 (pages 149 through 152) for Heat Sink 9.

NES&L DEPARTMENT CALCULATION SHEET l' E"u"UCHO. F'AG E OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION: i

! CCN No. CCN - I Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 73 a RV ORIGINATOR l DATE IRE DATE REV ORIGINATOR DATE 1RE DATE R i 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

l l 5 4

1

k. HS #10 - FLOOR SLABS (OTHER THAN BASEMATS)

] The characteristics of the Floor Slabs (other than basemats) represent a refinement of the i characteristics of determined in Calculation N-4080-002 (pages 152 through 155) for Heat l Sink 10. l l

A review of Calculation N-4080-002 (page 153) indicates that the concrete thickness of the floor slabs is 1.5 feet, and is based on input data provided as Attachment 1 to Calculation l N-4080-002 (page 327). When the nodalization of the Concrete Region was performed, Calculation N-4080-002 (page 153) modeled the concrete as Heat Sink 10 Regions 3, 4 and 5, with a total concrete thickness of 2.0 feet. To model the correct concrete thickness

requires that the Region 5 thickness be reduced by 0.5 feet.  !

l. HS #11 - LIFTING DEVICES (EXCEPT STAINLESS STEEL PARTS)

The chancteristics of the Lifting Devices (except stainless steel parts) are as determined in Calculation N-4080-005 (Refertace 6.1.i, pages 42 through 44) for Heat Sink 10. This heat sink description represents a refir.ement of the characteristics of the Lifting Devices first determined in Calculation N-4080-002 (pages 156 through 158) for Heat Sink 11.

m. HS #12 - AUSCELLANEOUS CARBON STEEL (WTTH THICKNESS GREATER THAN 2.50 IN)

The chameteristics of the Miscellaneous Carbon Steel (with thickness greater than 2.50 in) are as determined in Calculation N-4080-005 (pages 44 through 47) for Heat Sink 11. This heat sink description represents a refinement of the characteristics of the Miscellaneous Carbon Steel first determined in Calculation N-4080-002 (pages 158 through 161) for Heat Sink 12.

n. HS #13 - MISCELLANEOUS CARBON STEEL (WITH THICKNESS BETWEEN 1.00 IN AND 2.50 IN)

The characteristics of the Miscellaneous Carbon Steel (with thickness between 1.00 in and 2.50 in) are as determined in Calculation N-4080-005 (pages 47 through 50) for Heat Sink

12. This heat sink description represents a refinement of the characteristics of the Miscellaneous Carbon Steel first determined in Calculation N-4080-002 (pages 161 through 165) for Heat Sink 13.

NES&L DEPARTMENT CALCULATION SHEET 'ls"gcn yo. ,,, o ,_ o,_

Projict or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 74 i REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

. s j

o. HS #14 - h0SCELLANEOUS CARBON STEEL (WITH THICKNESS BETWEEN 0.50  ;

IN AND 1.00 IN)

The chameteristics of the Miscellaneous Carbon Steel (with thickness between 0.50 in and 1.00 in) are as determined in Calculation N-4080-005 (pages 50 through 54) for Heat Sink

13. This heat sink description represents a refinement of the characteristics of the Miscellaneous Carbon Steel first determined in Calculation N-4080-002 (pages 165 through 169) for Heat Sink 14.

p. HS #15 - MISCELLANEOUS CARBON STEEL (WITH THICKNESS LESS THAN 0.50 IN)

The chameteristics of the Miscellaneous Carbon Steel (with thickness less than 0.50 in) are as determined in Calculation N-4080-005 (pages 54 through 59) for Heat Sink 14. This heat sink description represents a refinement of the characteristics of the Miscellaneous Carbon  !

Steel first determined in Calculation N-4080-002 (pages 169 through 173) for Heat Sink 15. l

q. HS #16 - ELECTRICAL EQUIPMENT The characteristics of the Electrical Equipment are as determined in Calculation N-4080-005 (pages 59 through 61) for Heat Sink 15. This heat sink description represents a refinement of the characteristics of the Electrical Steel first determined in Calculation N-4080-002 (pages 174 through 176) for Heat Sink 16.

r. HS #17 - MISCELLANEOUS STAINLESS STEEL The characteristics of the Miscellaneous Stainless Steel are as determined in Calculation N-4080-005 (pages 62 through 65) for Heat Sink 16. This heat sink description represents a refinement of the characteristics of the Miscellaneous Stainless Steel as first detennined in Calculation N-4080-002 (pages 176 thmugh 179) for Heat Sink 17.

NES&L DEPARTMENT CALCULATION SHEET 'cc" " '

PRELIM. CCN NO. PAGE,_ OF,__

1 Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

l CCN No. CCN -

h Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 75 i

REV ORIGINATOR DATE IRE DATE REV l ORIGINATOR DATE 1RE DATE R

) 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

8 i

j

s. HS #18 - UNLINED REFUEllNG CANAL WALLS (BELOW EL. 63'6")

The chameteristics of the Unlined Refueling Canal Walls (below plant elevation 63'6") are as i determined in Calculation N-4080-002 (pages 180 through 182) for Heat Sink 18.

t. HS #19 - REACTOR BUILDING CYLINDER #3 (THE CONTAINMENT SECTION i

WITH EMBEDDED SuntNERS BETWEEN EL. 29'6" AND 112'0")

The characteristics of the Reactor Building Cylinder #3 (the Containment Section with Embedded Stiffeners between plant elevations 29'6" and 112'0") are as determined in Calculation N-4080-002 (pages 183 through 189) for Heat Sink 19, except for the thickness of the Containment Liner / Concrete air gap interface, and except for the thickness of the concrete layer.

The thickness of the Containment Liner / Concrete air gap interface is modified to address a change in the containment liner to containment concrete interface conductance, as discussed in Design Input Item 4.13.a.

Due to an addition error, Calculation N-4080-002 (page 188) improperly modeled the concrete layer as 3.56524 feet thick. In this analysis the concrete layer will be modeled as 4.21108 feet, corresponding to the average thickness that was actually determined in Calculation N-4080-002 (page 186).

i l

u. HS #20 - VENT TUNNELS The characteristics of the Vent Tunnels are as determined in Calculation N-4080-002 (pages 190 through 192) for Heat Sink 20.

NES&L DEPARTMENT CALCULATION SHEET '"o' PRELIM, CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

ccN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 76 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 "

4 414 CARD SERIES 410001: MATERIAL PROPERTIES This Card Series provides the thermal conductivity and the volumetric heat capacity of the material used in this analysis. Five materials are utilized by this analysis:

Material 1 Carbon Steel '

Material 2 Concrete Material 3 Stainless Steel Material 4 Organic Paint Coating Material 5 Air Gap The thermal conductivity of a material is a measure of the material's ability to conduct heat.

Minimizing a heat sink's thermal conductivity will inhibit heat transfer from the containment ,

air to the heat sinks. During the early part of an accident this will maximize containment air l energy, and consequently yield higher containment pressures and temperatures. I The volumetric heat capacity of a material is a measure of the material's ability to store energy. Minimizing a heat sink's volumetric heat capacity will inhibit heat retention by the heat sink, and consequently maximize energy retention within the containment air. This will yield higher containment pressures and temperatures.

a. ITEMS 2 and 3: CARBON STEEL, A typical Carbon Steel thermal conductivity of 25 BTU /hr-ft *F is listed in Bechtel Topical Report BN-TOP-3 (Reference 6.11, Section 3.3.1 and Table 4). Use of this value is recommended by Bechtel Nuclear Standard N2.3.2 (Reference 6.12, sheet 14).

A typical Carbon Steel Volumetric Heat Capacity of 54 BTU /ft' *F is listed in Bechtel Topical Report BN-TOP-3 (Section 3.3.1 and Table 4). Use of this value is recommended by Bechtel Nuclear Standard N2.3.2 (sheet 14).

b. ITEMS 4 and 5: CONCRETE A typical Concrete thermal conductivity of 0.8 BTU /hr-ft *F is listed in Bechtel Topical  ;

Report BN-TOP-3 (Reference 6.11, Section 3.3.1 and Table 4). Use of this value is recommended by Bechtel Nuclear Standard N2.3.2 (Reference 6.12, sheet 14).

NES&L DEPARTMENT CALCULATION SHEET 'cc" Mod PRELIM. CCN No. PAG E_,_ Os__

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 cCN CoNVERSloN:

CCN No. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. _77 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE BRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 E 5

A typical Concrete Volumetric Heat Capacity of 30 BTU /ft$ - F is listed in Bechtel Topical Repon BN-TOP-3 (Section 3.3.1 and Table 4). Use of this value is recommended by Bechtel Nuclear Standard N2.3.2 (sheet 14).

c. ITEMS 6 and 7: STAIhcESS STEEL A typical Stainless Steel thermal conductivity of 10 BTU /hr-ft- F is listed in Bechtel Topical Report BN-TOP-3 (Reference 6.11, Section 3.3.1 and Table 4). This value is typical for Types 304 and 316 austenitic stainless steel used for inside contamment SS piping. Use of a value of 10 BTU /hr-ft *F is recommended by Bechtel Nuclear Standard N2.3.2 (Refen:nce 6.12, sheet 14).

A typical Stainless Steel Volumetric Heat Capacity of 54 BTU /ft'- F is listed in Bechtel Topical Repon BN-TOP-3 (Section 3.3.1 and Table 4). 'Use of this value is recommended by Bechtel Nuclear Standard N2.3.2 (sheet 14).

d. ITEMS 8 and 9: ORGANIC PAINT COATING A typical Organic Paint thermal conductivity of 0.1 BTU /hr-ft- F is listed in Bechtel Topical Repon BN-TOP-3 (Reference 6.11, Section 3.3.1 and Table 4). Use of this value is recommended by Bechtel Nuclear Standard N2.3.2 (Reference 6.12, sheet 14).

A typical Organic Paint Volumetric Heat Capacity of 20 BTU /ft3 - F is listed in Bechtel Topical Repon BN-TOP-3 (Section 3.3.1 and Table 4). Use of this value is recommended by Bechtel Nuclear Standard N2.3.2 (sheet 14).

e. ITEMS 10 and 11: AIR GAP (@ 200 'F)

At a long-term average post-accident containment air temperature of 200 *F, the book Encineerine Heat Transfer. by S.T. Hsu, (Reference 6.15, Table A-6, page 577) indicates that the air thermal conductivity is 0.0174 BTU /hr-ft *F.

The volumetric heat capacity is equal to the product of the air density (p) and the specific heat of air at constant volume (C,). The air specific heat capacity at constant volume rather than at constant pressure (C,,) is employed because the contamment air pressure is not constant, it varies greatly during the course of the accident. However, the air volume of the heat sinks is constant. The specific heat of air at constant volume is equal to the product of

~

r l

NES&L DEPARTMENT '

CALCULATION SHEET 'cc"os PREl.lM. CCN NO. PAGE OF Project Or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

( CCN NO. CCN -

l Subject Containment P/T Analysis for Desian Basis LOCA Sheet NO. 78 1

REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 the specific heat of air at constant pressure and the ratio of specific heats (k = C,/C,). At a i long-term average post-accident containment air temperature of 200 F, the book Engineerine Heat Transfer, by S.T. Hsu, (Table A-6, page 577) indicates that p is equal to 0.060 lbm/ft', and C, is equal to 0.241 BTU /lbm *F. Crane Technical Paper 410 I l (Reference 6.17, page A-22) indicates that k is equal to 1.4. Therefore, the air volumetric heat capacity is-l pC, = (0.060 lbm/ft') x (0.241 BTU /lbm *F) + (1.4) pC, = 0.0103 BTU /ft' *F 1

1 I

f

NES&L DEPARTMENT CALCULATION SHEET 'cc" No '

PRELIM. CCN No. PAGE OF Proj:ct or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

l CCN No. CCN -

l Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 79 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 5

l l 5 METHODOLOGY l

2 The DESLS LOCA break with a total break area of 9.82 ft is evaluated in this calculation.

The evaluations utilized the Bechtel COPATTA computer code (Reference 6.5.b) to model the containment response to the break.

The COPATTA Code is capable of considering the effects of reactor system blowdown, core decay power energy release, metal-water reaction energy release, and sensible heat release from the reactor system piping. In addition, the Code can consider heat absorption by the containment structure and equipment within the structure, and engineered safeguard features I

including emergency cooling units, containment sprays, and reactor core safety injection.

The COPATTA Code calculates conditions in two separate regions of the containment: the containment atmosphere (vapor region), and the sump (liquid region). Following completion of the primary system blowdown, the program also calculates conditions in a third region, the water contained in the reactor vessel. The three regions are open systems in a thermodynamic sense since the COPATTA Code permits mass flow across the boundaries of

, all three regions. Mass and energy are transfemxi between the liquid and vapor regions by l boiling, condensation, or liquid dropout. Each region is assumed homogeneous, but a l tempemture difference can exist between regions. Any moisture condensed in the vapor l region during a time increment is assumed to fall immediately into tet liquid region.

l Non-condensible gases are included in the vapor region.

l This analysis with the COPATTA Code is presented in four sections:

, Section 8.1: COPATTA Code Card Series Input Data

~

i Section 8.2: COPATTA Code Input Files Section 8.3: COPATTA Code Output l

Section 8.4: Mass and Energy Balance l

)

NES&L DEPARTMENT CALCULATION SHEET 'cc" " '

PRELIM. CCM NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Cab. No. N-4QBO-026 CCN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 80 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 6 REFERENCES 6.1 Calculations

a. SONGS Units 2&3 Calculation C-257-1.06.01, Revision 1, " Containment Shell Analysis - Containment Passive Heat Sink" (dated 07/28/77).

b. SONGS Units 2&3 Calculation M-0014-009, Revision 0, " Containment Spray Pumps In Service Testing Minimum Requirements".

~

c. SONGS Units 2&3 Calculation M-0026-001, Revision 5, " Component Cooling Water Heat Exchangers" (dated 11/15/89).

d. SONGS Units 2&3 Calculation M-0026-002, Revision 1, " Component Cooling Water System - Sizing of CCW Pumps" (dated 01/31/77).

e. SONGS Units 2&3 Calculation M-0072-036, Revision 0, " Containment Emergency Cooler Performance Verification".

1

f. SONGS Units 2&3 Calculation N-0880-015, Revision 0, " Double Ended Pump Suction LOCA Long term Mass / Energy Release and COPATTA Analysis (NRC Question 022.31)".

g. SONGS Units 2&3 Calculation N-4080-002, Revision 1, " Containment Press.-Temp I Transient Analysis" (dated 10/19/76).

l

h. SONGS Units 2&3 Calculation N-4080-003, Revision 5, "Contamment Spray (CS) and Emergency Fan (EF) Actuation Times" (dated 12/23/93)

i. SONGS Units 2&3 Calculation N-4080-005, Revision 0, "MSLB Analysis for Environmental Qualif~ication".

j. SONGS Units 2&3 Calculation N-0240-006, Revision 0, "RWST Tech Spec Requirement".

6.2 Correspondence

a. Letter from CE to BPC, S-CE-2604, dated March 1,1976.

(CDM number C760301G-45-2-4SVT).

NES&L DEPARTMENT CALCULATION SHEET l'l","Mcn no. ,,c, o, l Proj:ct or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION-  !

CCN NO. CCN - I Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. J _ l REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

4 i

1

b. Letter from CE to BPC, S-CE-3129, dated July 28,1976.

(CDM number C760728G-43-40-2). .

c. Letter fmm CE to BPC, S-CE-3242 dated September 13, 1976.  !

(CDM number C760913G-18-18-2). I

d. Ietter from CE to BPC, S-CE-6814 dated August 24,1981.

(CDM number C810824G).

e. E-Mail message from Tom Yackle to Gary Johnson and Bernie Carlisle,

" Containment Spray Assessment", dated July 30,1992. A copy of tids reference is provided in Section 9.

i l 6.3 Licensine Documents j a. San Onofre Unit 2 Operating License and Technical Specifications, up to and i including Amendment 101.

b. San Onofm Unit 3 Operating License and Technical Specifications, up to and including Amendment 90.

c. SONGS 2&3 Updated Final Safety Analysis Report (UFSAR), up to and including Revision 9.

d. SONGS 2&3 Emergency Opming Instruction SO23-12-3, " Loss of Coolant l

Accident", Revision 8.

l 6.4 Regulatory Documents

a. 10 CFR Part 50, "" Domestic Licensing of Production and Utilization Facilities".

Revised as of January 1,1993.

b. NUREG-0588, Rev 1, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment".

s

c. NUREG-0800, Standard Review Plan 6.2.1.1.A, Revision 2, July 1981, "PWR Dry Containments, Including Subatmospheric Containments".

NES&L DEPARTMENT CALCULATION SHEET 'ccd " >

PRELIM. CCM No. PAGE _ OF _

i Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CcN CONVERSION:

I CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 82 l

1 0 R akano 01 18 94 J. Elli tt 01 20 94 l 5 1

d. NUREG-0800, Standard Review Plan 15.6.5, Revision 2, July 1981, " Loss-of-

! Coolant Accidents Resulting from Spectnim of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary".

e. NRC Branch Technical Position (BTP) ASB 9-2, Revision 2, July 1981, " Residual Decay Energy for Light-Water Reactors for Iong-Term Cooling" (Attachment to SRP 9.2.5).

6.5 Bechtel Computer Programs t a. Bechtel Standard Application Program MAP-121, DECAY, Version V01, "ANS and NRC Decay Heat Generation", User's, Theoretical, and Validation Manuals.

b. Bechtel Standard Application Program, MAP-175, COPATTA, Version G1-14,

" Containment Pressure and Tempenture Transient Analysis", User & Theory Manuals.

i 6.6 Desien Basis Document Reoorts 1

a. DBD-SO23-400, Revision 0, " Component Cooling Water System" (dated 12/27/91).

b. DBD-SO23-TR-EQ, Revision 0, " Environmental Qualification Topical Report" l (dated 12/27/91) 6.7 System Descriptions

a. SD-SO23-360, Revision 2, " Reactor Coolant System".

l I b. SD-S023-390, Revision 1, " Chemical and Volume Control System".

l l c. SD-SO23-400, Revision 2, " Component Cooling Water System".

d. SD-SO23-720, Revision 1, " Engineered Safety Features Actuation System".

c. SD-SO23-740, Revision 3, Safety Injection, Containment Spray, and Shutdown Cooling Systems".

i NES&L DEPARTMENT CALCULATION SHEET 'cc"

,ae "ogcn no. ,,c, o, Proj:ct or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CoNVERSloN:

CCN No. C CN -

Subj ct Containrnent P/T Analvsis for Desian Basis LOCA Sheet No. 83 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

h l

, S 1

! 6.8 Drawings

a. P&ID 40111 A, Revision 26, Reactor Coolant System-System No.1201.

b. P&ID 40114A, Revision 10, Contamment Spray System-System No.1206.

I

c. P&ID 40114B, Revision 14, Containment Spray System-System No.1206. l l

d. P&ID 40172A, Revision 7, Contamment HVAC System (Emergency)-System No.

1501.

6.9 Vendor Documents

a. CE Technical Manual " Shutdown Cooling Heat Exchanger" for SONGS Unit 2 l (S O23-932-15-0).

l l b. CE Technical Manual " Shutdown Cooling Heat Exchanger" for SONGS Unit 3 (S O23-932-14-0). l l

l 6.10 The " Equipment Qualification Condition Monitoring Program Assessment" of March 1988 (CDM# 1814-AH704-M0001) 1 6.11 Bechtel Topical Report BN-TOP-3, Revision 4, " Performance and Sizing of Dry; Pressure Containments", dated March 1983.

l l 6.12 Bechtel Nuclear Design Standard N2.3.2, Revision 0, " Containment Analysis, dated l July 1975.

l l

! 6.13 1989 ASHRAE Handbook of Fundamentals. I-P Edition, published by the American Society of Heating, Refrigeration and Air Conditioning Engineers, Inc., Atlanta, Georgia,1989.

6.14 W. M. Kay and A. L. London, Compact Heat Exchangers, (Palo Alto), National Press,1955.

NES&L DEPARTMENT i

CALCULATION SHEET '" o '

PRELIM. CCN NO. PAGE _ 0F _

l Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

l CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 84 l

I REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R l 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

l

, 5 l 6.15 Shao Ti Hsu, Engineering Heat Transfe_C, published by D. Van Nostrand Company, l Inc. of Princeton, New Jersey,1963.

i 6.16 ASME Steam Tables, Fifth Edition, published by the American Society of Mechanical Engineers".

l 6.17 Crane Technical Paper No.410, " Flow of Fluids", Twenty Fourth Printing-1988.

l 6.18 SO123-XXIV-37.26.12, Revision 0, PCN 0-1, " Environmental Qualification (EQ)

Master List".

1 6.19 NCRs 93030001,93030002,93030003, and 93030004. All dated 12/21/93 J

l 1

l l

I l

I

+

2

NES&L DEPARTMENT CALCULATION SHEET E"u"lica e no. exoE or i 1

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 cCN CONVERSION: 1 CCN NO. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 85 l '

REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 5

7 NOMENCLATURE CCS Containment Cooling System (Containment Air Cooling System)

CCWS Component Cooling Water System CE Combustion Engineering CSAS Containment Spray Actuation Signal CSS Containment Spray System CVCS Chemical and Volume Control System i DESLS Double Ended Suction Leg Slot ECCS Emergency Core Cooling System l ESFAS Engineered Safety Features Actuation Signal l HPSI High Pressum Safety Injection i HTC Heat Transfer Coefficient I l HVAC Heating, Ventilation and Air Conditioning l LCO Limiting Condition of Operation l LOCA Loss of Coolant Accident

! LOP Loss of Offsite Power LPSI Low Pressure Safety Injection MOV Motor Operated Valve l

NCR Non-Conformance Report i NSSS Nuclear Steam Supply System l RAS Recirculation Actuation Signal RB Reactor Building l RCS Reactor Coolant System RWST Reactor Water Storage Tank SDCHX Shutdown Cooling Heat Exchanger l SIAS Safety Injection Actuation Signal

' SIS Safety Injection System SIT Safety Injection Tank l UHS Ultimate Heat Sink l

l

NES&L DEPARTMENT CALCULATION SHEET '

'cca ". CCN NO.

PRELIM PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 cCN CONVERSION:

CCN NO. CCN -

Subject _ Containment P/T Analysis for Desian Basis LOCA Sheet No. SS REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

4 8 CALCULATION 8.1 COPATTA CODE INPUT DATA Section 8.1.1 presents the title card. Sections 8.1.2 through 8.1.25 will provide input data for the variable data series, while Sections 8.1.27 through 8.1.33 will provide input data for the heat sink data series. Section 8.1.26 presents the variable end card, and Section 8.1.33 presents the end card.

Item 1 in all Card Series is the Card Series Identifier, i.e. the Card Series number.

8.1.1 TITLE CARD l

l This card must precede each set of base case data. It must contain an asterisk in Column I 1, and any combination of numeric and alphanumeric characters in the remaining 79 columns. The information on this card will appear at the top of each page of output for l this prime case problem. This calculation evaluates one case, and the following TITLE l

i CARD will be used:

• LOCA WITH A LOSS OF OFFSITE POWER i

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Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 87 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R O R. Nakano 01/18/94 J. Elliott 01/20/94 E 5

l 8.1.2 CARD SERIES 0: Option Infonnation Card Series 0 provides option infonnation, This Card Series is entered in the input data file as:

l l

l & LIST P00L=0,2,1,0,1,0,0,0,0/

The entries in Card Series 0 include:

ITEM 2: IHEAT = 2 l A value of 2 indicates that a single heat exchanger is modeled for containment spray only per Design Input Item 4.1.a.

l ITEM 3: NOIT = 1 i

i A value of 1 disables the option to iterate for the estimated time to peak pressure. If a I value of 0 is modeled, Item 10 on Card Series 1 icdicates the first guess for the estimated time of peak pressure to be used in the modified Tagami condensation heat transfer coefficient calculation. If a value of 1 is modeled, Item 10 on Card Series 1 indicates the l

actual time of peak pressure to be used in the modified Tagami condensation heat transfer coefficient calculation.

For the version of the COPATTA code that is used for this analysis, a value of 0 for the NOIT variable gives an application error. Because of this, in this calculation, no l iterations for the peak pressure will be performed by the code. Instead, an assumed peak pressure will be input based on peak pressure used in previous analysis (See Item 10 on Card Series 1).

ITEM 4: NPTOP = 0 l A value of 0 requests a normal set of data at each printout time step.

As recommended by sheet 4 of Bechtel Nuclear Standard N2.3.2 (Reference 6.12), a normal set of data should be requested at each printout time step.

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ITEM 5: LAST = 1 A value of 1 indicates that this is the last case in a series of COPATTA Code runs.

As discussed on page 3-11 of the COPATTA User's Manual (Reference 6.5.b), the option to terminate must equal I because the change case option is not active. I l

l ITEM 6: IUHS_ TYPE = 0 A value of 0 indicates that no Ultimate Heat Sink (UHS) is to be modeled.

ITEM 7: IHE_SRC = 0 A value of 0 indicates that the constant temperature and mass flow rate defined in Items 5 and 6 of Card Series 4 will be used for the Shutdown Cooling Heat Exchanger (SDCHX) data.

ITEM 8: IEX_HE_ TYPE = 0 This parameter is used to model external heat loads if the value of IHEAT is greater than or equal to four in Item 2 of Card Series 0. In this analysis IHEAT is assigned a value of 2, so any value may be modeled for IEX_HE_ TYPE. Therefore, a value of 0 is arbitrarily chosen to be modeled.

ITEM 9: IHE_UAMOD = 0 A value of 0 indicates that the COPA7TA Code should use the SDCHX overall heat tansfer coefficient on Item 4 of* Card Series 4 as a constant.

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Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 89 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE tRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

l l 8.1.3 CARD SERIES 1: General Problem Information i

I l

i Card Series 1 provides general problem information. This Card Series is entered in the input data file as:

l l & LIST POOL =1,1.0e7,16.2, 2.305e6,120, 0.6, 20, 582.945,1,18, 0.00,14.7, 0.50/

l The entries in Card Series 1 include: l l ITEM 2: TFNL = 1.0e7 seconds l l Calculations will be terminated at 1.0 x 107seconds  !

l l

Per Procedure SO123-XXIV-37.26.12 (Reference 6.18, Attachment 5, Section D.2.a), the l dumtion of an accident can be as long as 120 days. To facilitate the use of this analysis l l in Environmental Qualification efforts with the creation of an extended pressure-temperature profile, the duration of the run will be set to the time of 1.0 x 107 l seconds (approx.116 days) which envelops the time needed to retum the containment to ambient temperature and pressure and meets the intent of the EQ requiremert to provide long term analysis out to 120 days post-accident.

l l ITEM 3: PAIR = 16.2 psia The initial pressure inside the Containment prior to the start of the LOCA mass and l energy release is 16.2 psia (1.5 psig), as discussed in Design Input Item 4.2.a.

l ITEM 4: VOL = 2.305e6 ft2 l The containment net free volume is 2.305e6 cubic feet, as discussed in Design Input l Item 4.2.b.

l ITEM 5: TAIR = 120 *F The containment atmosphere temperature prior to the start of the LOCA mass and energy

( release is 120 *F, as discussed in Design Input Item 4.2.c.

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ITEM 6: HUM = 0.6 l The relative humidity of the atmosphere inside the Containment prior to the start of the LOCA mass and energy release is 60 percent, as discussed in Assumption 3.1.a.

1 ITEM 7: NSL = 20 i

As detailed in Section 8.1.27, twenty Heat Sinks are modeled in this calculation.

ITEM 8: TBOIL = 582.945 *F The temperature of the primary coolant prior to the stait of the LOCA mass and energy release is 582.945 *F, as discussed in Design Input Item 4.2.d. This value sets the initial temperature of all heat conducting region surfaces in contact with the primary coolant.

ITEM 9: TCHECK = 1 1

If the option to iterate for peak pressure is enabled (Item 3 on Card Series 0 is zero),

then the variable TCHECK represents the time in seconds up to which the program will search for a second pressure peak after a first one has been located. The time to a second pressure peak is used to determine the condensation heat transfer coefficient; this quantity is used with the modified Tagami condensing heat transfer coefficient.

Since the option to iterate for peak pressure is disabled ~(Item 3 on Card Series 0 is one),

the TCHECK variable is not used. If the TCHECK variable is not used, Bechtel Nuclear ,

Design Standarti N2.3.2 (Reference 6.12, page 5) states that the variable should be l assigned a value of 1 second. l l

l ITEM 10: THSDD = 18 seconds The THSDD value indicates the first guess for the estimated time of peak pressure to be used in the modified Tagami condensation heat transfer coefficient calculation. The LOCA pressure-temperature analyses of Calculation N-4080-002 (Reference 6.1.g, pages 6 and 195) modeled a THSDD value of 18 seconds and the same will be used as an assumption in this calculation.

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ITEM 11: EVAP = 0.0 l

The fraction of heat condensate which will be allowed to revaporize is zero. No credit for revaporization is taken in this analysis per Assumption 3.1.b.

l ITEM 12: ENVRNP = 14.7 psia l The total pressure outside contamment is assumed to be 14.7 psia per Assumption 3.1.c.

l ITEM 13: ENVRH = 0.50 The relative humidity of the outside atmosphere is assumed to be 50 percent per Assumption 3.1.d.

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8.1.4 CARD SERIES 2 : Additional General Problem Information Card Series 2 provides additional general problem information. This Card Series is entered in the input data file as:

& LIST P00L=2, 0, 0,1.68e5, 2934, 0,120, 573.273/

The entries in Card Series 2 include:

ITEM 2: MWATR = 0 lbs l

The amount of water to be introduced as a step input at the time blowdown starts is

modeled as O pounds.

ITEM 3: UTOT = 0 BTU l

The total enthalpy associated with the water entered as variable MWATR is arbitrarily set to 0 BTU (any value is acceptable since variable MWATR is set to O pounds) l ITEM 4: MLEFT = 1.68e5 lbm The variable hUlFT is the mass of water left in the primary system available to be evaporated by reactor decay heat (Card Series 101) or metal water reaction heat (Card i

' Series 201). At time PHELP (Item 8 in this Card Series 2) if the volume occupied by MLEFT exceeds the volume given by REVOL (Item 5.in this Card Series 2), then the volume occupied by MLEFT is decreased to the point where it is equal to REVOL.

l The volume given by REVOL is the true volume left in the primary system available to be evaporated by reactor decay heat or metal water reaction heat. Therefore, if the variable MLEFT is assigned a value greater than the mass equivalent to the volume of REVOL, then the COPA'ITA Code will be forced to employ the correct volume as specified by REVOL.

i The actual mass of water left in the vessel atS time PHELP (573.273 seconds) will be equivalent to the REVOL volume of 2934 ft volume divided by the specific volume of saturated water at the containment pressure present at the time PHELP. Card Series 301 i

data gives a bmak enthalpy of 1181.57 Btu /lbm which is the enthalpy at the saturated temperature of 306.6 *F and a saturated liquid specific volume of 0.017516 ftS/lbm l

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Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 93 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE BRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 l (Reference 6.16, page 94). At this specific volume, the REVOL water volume is equivalent to 1.675e5 lbm (2934 3ft + 0.017516 8/lbm). Therefore, the variable MLEFT will be rounded up to 1.68e5 pounds.

ITEM 5: REVOL = 2934 ft8 The reactor volume below the pipe mpture is 2934 cubic feet, as discussed in Design Input Item 4.3.a.

ITEM 6: HAB = 0 BTU /hr *F l

The total heat transfer coefficient for the heat transfer between liquid (sump) and vapor regions of the containment is modeled as 0 BTU /hr- F per Assumption 3.2.a.

ITEM 7: TCONT = 120 F If the temperature boundary control on Heat Sink Card Series 1XX400 equals zero, then the variable TCONT is used to define the convective heat transfer coefficient and the bulk temperature to which the heat sink surfaces are exposed. Each of the twenty heat sinks modeled in this analysis assigns the temperature boundary control on Heat Sink Card Series 1XX400 a value other than zero. Since the variable TCONT is not used, Bechtel Nuclear Standard N2.3.2 (Refemnce 6.12, page 5) states that any positive value may be modeled. Since Calculation N-4080-002 (Reference 6.1.g, page 21) employed an arbitrary value of 120 F, this analysis will also model an arbitrary value of 120 *F.

ITEM 8: PHELP = 573.273 seconds The time at which mass and energy balance calculations for the water within the reactor vessel will begin is 573.273 seconds, as discussed in Design Input Item 4.3.b.

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5 8.1.5 CARD SERIES 3: Leakage from Containment Card Series 3 allows modeling of the addition and/or deletion of air / steam via containment HVAC operation. No credit is taken for HVAC operation in this LOCA analysis:

Therefore, this Card Series is entered in the input data file as:

& LIST P00L=3, 0, 0, 0, 0, 0, 1.00e7, 0, 0, 0, 0/ i The entries in Card Series 3 include:

ITEM 2: 0 seconds )

The HVAC start time is 0.0 seconds.

ITEM 3: 0 ft'/ minute 6

The initial HVAC volume addition rate is 0 cubic feet / minute.

ITEM 4: 0 *F l

The initial tempenture of the air added is 0 F.

ITEM 5: 0 percent The initial relative humidity of the air added is 0 percent.

ITEM 6: 0 ft / minute S

The initial HVAC volume removal rate is O cubic feet / minute.

ITEM 7: 1.00e7 seconds The HVAC stop time is 1.00e7 seconds. This is the time up to which the analysis is run.

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ITEM 8: 0 ft /3 minute The final HVAC volume addition rate is O cubic feet / minute.

I ITEM 9: 0 *F The final temperature of the air added is 0 F.

ITEM 10: 0 percent The final relative humidity of the air added is 0 percent.

ITEM 11: 0 ft'/ minute The final HVAC volume removal rate is O cubic feet / minute.

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8.1.6 CARD SERIES 4: Heat Exchanger Data i

Card Series 4 provides for simulation of heat exchangers for long term analysis of the effectiveness of the containment spray and safety injection systems.

Card Series 4 also provides for a means of starting the containment spray. The COPATTA ,

Code compares two potential startmg times for the containment spray, and starts the emergency cooling units at the later of the two times. The first time is specified by the first non-zero spray flow entry in Card Series 801, Item 2. The second time, TNOW, is defined as the sum of the time at which the spray initiation signal (Item 12) is reached, and the instrumentation and equipment delay time (ftem 13). In this analysis, the desired containment spray start time is to be the time modeled in Card Series 801. To ensure that i

the Card Series 801 time is used by the COPATTA Code, the Items 12 and 13 variables are modeled as O psia and 0 seconds, respectively. This leads to the calculation of a contamment l spray stait time of 0 seconds for the variable TNOW, and forces the code to employ the larger time specified in Card Series 801.

l Tids Card Series is entered in the input data file as:

4

& LIST P00L=4, 1, 6860, 216, 105, 3.0e6, 0, 0, 0, 0, 0, 0, 0, 0/

I The entries in Card Series 4 include:

1 ITEM 2: IHEX = 1 A value of 1 indicates that a single pass shell and U-tube (2 tube passes) heat exchanger j is modeled in this analysis, as discussed in Design Input Item 4.4.a.

ITEM 3: HEX (1) = 6860 ft2 The primary heat exchanger surface area is modeled as 6860 square feet. As discussed in Assumption 3.3.a, to address possible plugging and corrosion, a two percent reduction in the surface area has been assumed.

ITEM 4: HEX (2) = 216 BTU /hr-ft 2.op i The overall heat exchanger heat transfer coefficient is 216 BTU /hr-ft2 - F as discussed in Design Input Item 4.4.b.

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ITEM 5: HEX (3) = 105 F The primary heat exchanger coolant inlet temperatum is 105 *F as discussed in Design  !

Input Item 4.4.c.

ITEM 6: HEX (4) = 3.0e6 lbm/hr The primary heat exchanger coolant flow rate is 3.0 x 106 lbm/hr as discussed in Design Input Item 4.4.d.

ITEM 7: IHIX = 0 l

A value of 0 indicates that no secondary heat exchanger is modeled in this analysis.

ITEMS 8 thmugh 11: 0, 0, 0, 0 These entries are all zero, since there are no secondary heat exchangers in use.

Per the COPATTA Code Users Manual (Reference 6.5.b, page 3-20), if only a primary heat exchanger is used, zeroes should be input for Items 7 through 11, and 14.

ITEM 12: 0 psia As discussed in the introduction to this Card Series 4, the containment spray pmssure initiation signal is modeled as 0 psia.

ITEM 13: 0 seconds As discussed in the intmduction to this Card Series 4, the instrumentation and equipment delay time after receiving the pressure signal is modeled as 0 seconds.

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ITEM 14: DMINL = 0 lb/hr This entry is zero, since there are no secondary heat exchsngers in use.

Per the COPATTA Code Users Manual (Reference 6.5.b, page 3-20), if only a primary heat exchanger is used, zeroes should be input for Items 7 through 11, and 14.

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Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 99 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 '

R. Nakano 01/18/94 J. Elliott 01/20/94 I 4

8.1.7 CARD SERIES 5: Air Cooler Information Card Series 5 provides for the selection of the number of contamment emeigency cooling units (air coolers) operating, and the period of operation. The air cooler heat removal capability curve is read into the problem in Card Series 1101.  ;

1 The COPATI'A Code compares two potential starting times for the emergency cooling units, and starts the units at the later of the two times. The first time is specified by Item 3. The second time, TNOW, is defined as the sum of the time at which the air cooler initiation signal (Item 5) is reached, and the TDELAY sign d pmcessing delay time (Item 6). In tids analysis, the desired air cooler start time is to N toe time modeled in Item 3. To ensure that the Item 3 time is used by the COPATTA Code, the Items 5 and 6 variables are modeled as O psia and 0 seconds, respectively. This leads to the calculation of an air cooler start time of 0 seconds for the variable TNOW, and forces the code to employ the larger time specified in l Item 3.

Card Series 5 is entered in the input data file :

& LIST POOL =5, 2, 35, 1.0e7, 0, 0, 0, 105/

The entries in Card Series 5 include:

ITEM 2: 2 There are two containment emergency cooling units modeled in this analysis as discussed in Assumption 3.4.a.

ITEM 3: 35 seconds for LOCA with a loss of offsite power.

The value represents the emergency cooling units' starting time as discussed in Design Input Item 4.5.a.

ITEM 4: 1.0e7 seconds The shutoff time for the emergency cooling units is modeled as 1.0 x 10' seconds. Use of this time will ensure that the containment cooling units will operate for the duration of the accident, as discussed in Assumption 3.4.b.

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ITEM 5: 0 psia '

As discussed in the introduction to this Card Series 5, the air cooler pressure initiation signal is modeled as O psia.

ITEM 6: TDELAY = 0 seconds I

l As discussed in the introduction to this Card Series 5, the instrumentation delay time after mceiving the pressure signal is modeled as 0 seconds.

ITEM 7: IAC SRC = 0 A value of 0 indicates that the air cooler heat exchanger coolant temperature is the constant value given in Item 8 of this Card Series 5.

ITEM 8: 105 "F The temperature of the air cooler heat exchanger coolant is 105 *F as discussed in Design Input Item 4.5.b.

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l R. Nakano 01/18/94 J. Elliott 01/20/94 4

8.1.8 CARD SERIES _6: Instantaneous Release of Energy Card Series 6 provides for the instantaneous release of a specified amount of energy (to the containment atmosphere, containment sump, or to the reactor vessel water) at any one time during the accident. However, other than blowdown, no instantaneous release of energy is modeled in this analysis. Therefore, Card Series 6 is entered in the input data file as:

& LIST P00L=6, 0, 0, 0/

ITEM 2: TPULSE = 0 seconds Per the COPATTA Code Users Manual (Reference 6.5.b, page 3-23), zeroes may be input for Items 2 through 4 if an instantaneous release of energy is not modeled.

ITEM 3: IPULSE = 0 Per the COPATTA Code Users Manual (page 3-23), zeroes may be input for Items 2 through 4 if an instantaneous release of energy is not modeled.

ITEM 4: UPULSE = 0 BTU Per the COPATTA Code Users Manual (page 3-23), zeroes may be input for Items 2 through 4 if an instantaneous release of energy is not modeled.

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Subject Containment Pfr Analysis for Desian Basis LOCA Sheet No. 102 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R l 0 R. Nakano 01/18/94 J. Elliott 01/20/94 h i 5 8.1.9 CARD SERIES LEAK: Leakage Paths Between Containment and Outside Atmosphere.

No leakage from containment to outside containment is modeled in this analysis. This Card Series is entered in the input data file as:

] & LEAK NOPEN=0/

l i

The variable NOPEN is equal to zero because the number of openings in the contamment is zero.

5

Per the COPATTA Code Users Manual (Reference 6.5.b, page 3-25), if NOPEN is equal to i zero, then the other variables may be omitted from the Card Series LEAK.

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8.1.10 CARD SERIES 101: Reactor Com Decay Power (Table 2)

Card Series 101 is a table that is used to input mactor core decay power. This table is used in combination with information provided in Card Series 401 and 701. The reactor core decay power table includes up to 25 sets of the following data entered in columnar form:

1. Time (seconds)

2. Decay power generation mte (BTU /hr)

This Card Series is discussed in Design Input Item 4.6. Card Series 101 is entered in the input data file as shown below. Decay heat for times prior to 573.273 seconds are incorporated into the CE supplied blowdown data of Card Series 301, and need not be entered in Card Series 101. .

In Card Series 401, a constant scaling factor of unity is applied to the decay power generation rate data contained in this Card Series 101. This Card Series 401 scaling factor will direct 100 percent of the reactor core decay power into the energy inventory of the reactor vessel water.

In Card Series 701, a constant scaling factor of zero is applied to the decay power generation rate data contained in this Card Series 101. The Card Series 701 scaling factor will direct 0 percent of the reactor core decay power into the contaimnent atmosphere.

l & LIST P00L=101, 0.0000, 0.0000, 5.73273e+02, 0.0000, 5.7327E+02, 3.2931E+08, ~

6.0000E+02, 3.2624E+08, 8.0000E+02, 3.0812E+08, l 1.0000E+03, 2.9449E+08, i

2.0000E+03, 2.2734E+08, 4.0000E+03, 1.7963E+08, l 6.0000E+03, 1.5728E+08, 8.0000E+03, 1.4506E+08, 1.0000E+04, 1.3706E+08, 2.0000E+04, 1.1366E+08, 4.0000E+04, 8.9771E+07, 6.0000E+04, 7.8463E+07, 8.0000E+04, 7.2141E+07, 1.0000E+05, 6.7894E+07, 2.0000E+05, 5.4991E+07, 4.0000E+05, 4.1412E+07, 6.0000E+05, 3.4734E+07, 8.0000E+05, 3.0911E+07, 1.0000E+06, 2.8363E+07, 2.0000E+06, 2.1296E+07, 4.0000E+06, 1.4713E+07,

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PRELIM. CCN NO. PAGE OF Project Or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

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Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 104 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. NakanO 01/18/94 J. Elliott 01/20/94 '

O 6.0000E+06, 1.1629E+r7, 1.0000E+07, 8.5482F#06/

l

NES&L DEPARTMENT CALCULATION SHEET 'cc" " '

PRELIM. CCM No. PAG E__ OF_,,

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 105 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 4

8.1.11 CARD SERIES 201: Reactor Metal-Water Reaction (Table 3)

Card Series 201 is a table that is used to input reactor metal-water reaction rate. This table is used in combination with information presented in Card Series 401 and 701. In this analysis, Card Series 201, in combination with Card Series 401 and 701, is also used to input the depressurization energy (i.e., the sensible heat addition occurring at the end of the post-Reflood phase) to be added to the reactor vessel. The combined reactor metal-water reaction and depressurization energy table includes up to 25 sets of the following data, entered in columnar form:

1. time (seconds) I

2. energy release rate (BTU / hour) l This Card Series is discussed in Design Input Item 4.7. Card Series 201 is entered in the input data file as shown below.

In Card Series 401, a constant scaling factor of zero is applied to the Zirconium metal-water reaction energy release rate data contained in this Card Series 201. In Card Series 401, a constant scaling factor of unity is applied to the sensible heat addition data contained in this Card Series 201. These Card Series 401 scaling factors will direct 0 percent of the metal-water reaction energy into the energy inventory of the reactor vessel water, and 100 percent of the sensible heat energy into the reactor vessel water.

In Card Series 701, a constant scaling factor of one is applied to the Zirconium metal-water reaction energy release rate data contained in this Card Series 201. In Card Series 701, a constant scaling factor of zero is applied to the sensible heat addition data contained in this Card Series 201. The Card Series '701 scaling factors will' direct 100 percent of the metal-water reaction energy into the containment atmosphere, and 0 percent of the sensible heat energy into the containment atmosphere.

& LIST P00L=201, 0, 2.5836e7, 211.10, 2.5836e7, 211.10, 0, 573.273, 0, 573.273, 1.2635e7, 8.64e+04, 1.2635e7, 8.64e+04, 0, 1.00e+07, 0/

l NES&L DEPARTMENT l

CALCULATION SHEET 'cc" "o '

PRELIM. CCN 20. PAGE _ OF _

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 106 l REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

s l

l 8.1.12 CARD SERIES 301: Blowdown Following Pipe Rupture (Table 4) l l

Card Series 301 is a table that is used to input blowdown following the pipe mpture. The l blowdown table includes up to 200 sets of the following data entered in columnar form:

i l

1. time (seconds)

2. water addition mte (pounds / hour) l 3. enthalpy of the water being added (BTU / pound)

The input data to be used in Card Series 301 is discussed in Design Input Item 4.8. This Card Series is entered in the input data file as shown below. The mass and energy release rates are assumed to vary linearly between each data point.

& LIST Poole301, 0, 0, 0, 0.025, 2.7068e+08, 5.4632e+02, 0.075, 2.6757e+08, 5.4681e+02, 0.175, 2.8058e+08, 5.4848e+02,

! 0.20, 3.3993e+08, 5.4933e+02, O.225, 3.3506e+08, 5.4967e+02, 0.25, 3.3534e+08, 5.5012e+02,

, 0.40, 3.1384e+08, 5.5312e+02, 0.75, 2.9337e+08, 5.6162e+02, 0.85, 2.7364e+08, 5.6237e+02, 1.0, 2.4650e+08, 5.6329e+02, 1.2, 2.2548e+08, 5.6429e+02, 2.0, 2.0756e+08, 5.6709e+02, 3.0, 1.8229e+08, 5.7573e+02, 4.0, 1.5767e+08, 5.9697e+02, l 5.0, 1.3255e+08, 6.3045e+02, l 6.0, 1.1328e+08, 6.5884e+02, 8.0, 9.4860e+07, 6.7161e+02, 10.0, 7.8800e+07, 6.8765e+02,

! 12.0, 5.4454e+07, 7.6610e+02, -

l 13.5, 3.566e+07, 8.640e+02, 14.5, 2.888e+07, 7.502e+02, 15.0, 2.627e+07, 7.199e+02, 16.0, 1.768e+07, 6.699e+02, 17.1, 1.119e+07, 6.556e+02, 17.2, 1.140e+07, 6.386e+02, 17.3, 9.065e+06, 6.213e+02, 18.5, 6.152e+06, 6.439e+02, 19.3, 8.806e+06, 4.605e+02, 19.8, 7.146e+06, 4.881e+02, i 20.6, 4.172e+06, 5.348e+02,

, 20.8, 1.016e+07, 3.317e+02, 21.4, 3.629e+06, 3.700e+02, 21.6, 1.77e+06, 3.66e+02, 4

21.8, 3.0e+05, 3 . 4 e+ 02, 4 22.0, 0.00, 0.00, 22.0, 0.00, 0.00, 22.25, 5.8302e+05, 1.3000e+03, 23.25, 9.2236e+05, 1.3000e+03, 24.25, 1.5463e+06, 1.3000e+03, 25.25, 2.0444e+06, 1.3000e+03,

NES&L DEPARTMENT CALCULATION SHEET 'cc" " '

PREUM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 107 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R l

0 R. Nakano 01/18/94 J. Elliott 01/20/94 E 5 l l

l l

l 26.25, 2.4255e+06, 1.3000e+03, '

i 2 7.75, 2. 8736e+06, 1.3000e+03, 28.00, 1.8443e+06, 1.3000e+03, 36.00, 1.8201e+06, 1.3000e+03, 44.50, 1.7920e+06, 1.3000e+03, 44.75, 2.7987e+06, 1.3000e+03, 75.00, 2.6467e+06, 1.3000e+03, 100.00, 2.5190e+06, 1.3000e+03, 125.00, 2.3921e+06, 1.3000e+03, 150.00, 2.2677e+06, 1.3000e+03, .

175.00, 2.1401e+06, 1.3000e+03,

! 200.00, 2.0116e+06, 1.3000e+03, t

211.10, 1.9553e406, 1.3000e+03, .

l 211.101, 2.2478e+06, 1.1865e+03,  !

211.336, 2.2378e+06, 1.1865e+03, 211.573, 2.2279e+06, 1.1865e+03, 211.812, 2.2179e+06, 1.1865e+03, 212.052, 2.2080e+06, 1.1865e+03, 213.026, 2.1615e+06, 1.1877e+03, 215.073, 2.0469e+06, 1.1878e+03, 216.989, 1.9466e+06, 1.1879e+03, l

219.039, 1.8464e+06, 1.1880e+03, 221.233, 1.7463e+06, 1.1881e+03, 222.894, 1.6748e+06, 1.1883e+03, 225.021, 1.5891e+06, 1.1884e+03, 226.920, 1.5179e+06, 1.1885 e+03, 228.953, 1.4468e+06, 1.1887e+03, 231.139, 1.3760e+06, 1.1889e+03, 233.014, 1.3194e+06, 1.1891e+03, 235.017, 1.2631e+06, 1.1892e+03, 237.167, 1.2070e+06, 1.1894e+03, 238.890, 1.1647e+06, 1.1900e+03, 240.719, 1.1232e+06, 1.1898e+03, 242.668, 1.0816e+06, 1.1900e+03, 245.484, 1.0265e+06, 1.1902e+03, 246.897, 9.9907e+05, 1.1904e+03, 249.420, 9.5821e+05, 1.1906e+03, 251.151, 9.3110e+05, 1.1908e+03, l

254.936, 8.7746e+05, 1.1911e+03, 259.251, 8.2462e+05, 1.1914e+03, l

262.929, 7.8563e+05, 1.1917e+03, -

267.086, 7.4729e+05, 1.1919e+03, 271.855, 7. 0974 e+05, 1.1921e+03, 281.634, 6.4948e+05, 1.1925e+03, 292.060, 6.0412e+05, 1.1925e+03, 302.415, 5.7236e+05, 1.1923e+03, 311.215, 5.5256e+05, 1.1919e+03, 321.094, 5.3597e+05, 1.1820e+03, 331.360, 5.2312e+05, 1.1820e+03, 340.999, 5.1401e+05, 1.1819e+03, 351.095, 5.0663e+05, 1.1819e+03, 361.352, 5.0080e+05, 1.1819e+03, 371.311, 4.9637e+05, 1.1818e+03, 391.750, 4.8974e+05, 1.1818e+03, 411.491, 4. 8546e+ 05, 1.1819e+03, 432.076, 4.8233e+05, 1.1593e+03, 452.069, 4.8013e+05, 1.1817e+03, 471.774, 4.7851e+05, 1.1816e+03, 524.047, 4. 75 78e+05, 1.1816e+03,

, 573.273, 4. 7426e+05, 1.1816e+03, l 573.273, 0.00, 0.00, l

1.00e+07, 0.00, 0.00/

i

NES&L DEPARTMENT CALCULATION SHEET 'cc" " ' '

PRELIM. CCN MO. PAG E__,,, OF_, ,_

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 108 REV ORIGINATOR DATE BRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 8.1.13 CARD SERIES 401: (Table 5)

Card Series 401 is a table that is used to describe the energy addition to the reactor vessel water from core decay power (Card Series 101), the metal-water reaction (Card Series 201),

and the sensible heat addition occurring at the end of the post-Reflood phase (Card Series 201). This table designates the fraction of each of these energy sources that is added to the energy inventory in the reactor vessel. This table includes up to 20 sets of the following data entered in columnar form:

' 1. time (seconds)

2. decay power multiplier (dimensionless)

3. metal-water reaction multiplier (dimensionless)

The decay power multiplier is the fraction of the decay power presented in Card Series 101 that is added to the reactor vessel. As discussed in Design Input Item 4.6, for times earlier than 573.273 seconds, decay power (or core decay heat) is considered in the CE supplied mass and energy release data of Card Series 301, and no Card Series 101 core decay heat is added to the energy inventory in the reactor vessel. Therefore, for times earlier than 573.273 seconds, the decay power multiplier is set to zero. For times later than 573.273 seconds, all of the core decay heat that is modeled in Card Series 101 is added to the enerby inventory in the reactor vessel. Therefore, for times later than 573.273 seconds, the decay power multiplier is set to unity.

The metal-water reaction multiplier is the fraction of the metal-water reaction energy as presented in Card Series 201, and the fraction of the sensible heat addition occurring at the end of the post-Reflood phase as presented in Card Series 201, that is added to the reactor vessel. ~

As discussed in Design Input Item 4.7.a, the Zirconium metal-water reaction energy release is modeled as a constant energy release rate over the time interval between the start of the LOCA and the end of the reflood phase at time 211.1 seconds. This metal-water reaction energy is released via the blowdown into the containment air space; none of the metal-water reaction energy is released to the energy inventory in the reactor vessel. Therefore, for times earlier than 211.1 seconds the metal-water reaction multiplier as used to address the metal-water reaction energy is set to zero. For times later than 211.1 seconds no metal-water reaction energy is released; therefore, for times later than 211.1 seconds the metal-water reaction multiplier as used to address the metal-water reaction energy is set to zero.

NES&L DEPARTMENT CALCULATION SHEET 'cc"

• PREUM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis fer Desian Basis LOCA Sheet No. 109 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/1 P/94 J. Elliott 01/20/94 h

5 As discussed in Design Input Item 4.7.b, at the end of the post-reflood phase a significant amount of sensible heat energy remains stored in various RCS components. As time passes and the primary coolant decreases in temperature, this stored energy will be released back to the primary coolant. This sensible heat energy is modeled as entering the Reactor Vessel over the time interval between the end of the post-reflood phase at time 573.273 seconds and the end of the first day of the accident (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, equal to 86,400 seconds). For times earlier than 573.273 seconds, no sensible heat energy is released; therefore, the metal-water reaction multiplier as used to address the sensible heat energy is set to zero. For times between 573.273 and 86400 seconds, all of the sensible heat energy that is modeled in Card Series 201 is added to the energy inventory in the reactor vessel. Therefore, for times between 573.273 and 86400 seconds, the metal-water reaction multiplier as used to address the sensible heat energy is set to unity. For times later than 86400 seconds, no sensible heat energy is released; therefore, the metal-water reaction multiplier as used to address the sensible heat energy is set to zeru.

Card Series 401 shall be entered in the input data file as:

& LIST P00L=401, 0, 0, 0, 211.1, 0, 0, 573.273, 0, 0,

, 573.273, 1, 1, l 8.64e+04, 1, 1, i

l 8.64e+04, 1, 0, 1.00e+07, 1, 0/

l

.l l

l

NES&L DEPARTMENT CALCULATION SHEET 'cc" " '

PREUM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 110 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5-l 1

l 8.1.14 CARD SERIES 501: Blowdown Following Pipe Rupture (Table 4) l l This Card Series is used only if number of points are more than can fit in Card Series 301.

l The Card Series 501 table includes up to 200 sets of the following data entered in columnar form:

1. time (seconds) l 2. water addition rate (pounds / hour)

3. energy addition rate (BTU / hour) D*

l Card Series 501 is not needed since Card Series 301 had enough space for all data.

Therefore, Card Series 501 shall be entered as:

l & LIST PO0t,=501, 0.0, 0, 0, 1.0e+07, 0, 0/

~

l

NES&L DEPARTMENT CALCULATION SHEET '

'cc" ". CCN NO.

PRELIM PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 111 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 5

8.1.15 CARD SERIES 601: (Table 7) l This Card Series is used to add water and/or energy directly to the containment sump,

! mgardless of the enthalpy of the water being added. This card is generally used to describe i the spillage of ECCS injection water that overflows the reactor vessel downcomer when the l vessel is full. The Card Series 601 table includes up to 80 sets of the following data entered

in columnar form

l l 1. time (seconds) l

2. water addition rate (pounds / hour) j

3. energy addition rate (BTU / hour)

In this analysis Card Series 601 is used to model spillage of the Safety Injection flow that is implicitly addressed in the mass and energy release data provided in CE Letter S-CE-2604 (Reference 6.2.a). As discussed in Design Input Item 4.9.a,27.272 x 106 BTU of energy, and 245322 lbm of mass will spill into the sump at the following uniform rates over the time period of 28.00 to 211.10 seconds:

Ma,w %, ,p%, , = 4.823 x 106 lbm/ hour 8,,w %, ,,,w. , = 5.362 x 108 BTU / hour The rest of the parameters to be entered into Card Series 601 are as discussed in Design Input Item 4.9 and as shown below.

O.IST P00L=601, 0.00, 0.00, 0.00, 28.00, 0.00, 0.00, 28.00, 4.823e+06, 5.362e+08, 211.101, 8.73e+05, 7.7e+07, 211.336, 8.83e+05, 7.8e+07, 211.573, 8.93e+05, 7.9e+07, 211.812, 9.03e+05, 7.9e+07, 212.052, 9.13e+05, 8.0e+07, 213.026, 9.60e+05, 8.4e+07, 215.073, 1.07e+06, 9.5e+07, 216.989, 1.17e+06, 1.0e+08, 219.039, 1.27e+06, 1.ie+08, 221.233, 1.37e+06, 1.2e+08, 222.894, 1.45e+06, 1.3e+08, 225.021, 1.53e+06, 1.3e+08, 226.920, 1.60e+06, 1.4e+08, 228.953, 1.67e+06, 1.5e+08, 231.139, 1.75e+06, 1.5e+08, 233.014, 1.80e+06, 1.6e+08, 235.017, 1.86e+06, 1.6e+08, l

NES&L DEPARTMENT CALCULATION SHEET '

'cc" ". CCN NO.

PRELIM PAGE OF Proj:ct or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 cCN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 112 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R O R. Nakano 01/18/94 J. Elliott 01/20/94 E y

5 237.167, 1.91e+06, 1.7e+08, 238.890, 1.96e+06, 1.7e+08, 240.719, 2.00e+06, 1.8e+08, 242.668, 2.04e+06, 1.8e+08, 245.484, 2.09e+06, 1.8e+08, 246.897, 2.12e+06, 1.9e+08, 249.420, 2.16e+06, 1.9e+08, 251.151, 2.19e+06, 1.9e+08, I

254.936, 2.24e+06, 2.0e+08, i 259.251, 2.30e+06, 2.0e+08, 262.929, 2.34e+06, 2.1e+08, 267.086, 2.37e+06, 2.1e+08, 271.855, 2.41e+06, 2.1e+08, 281.634, 2.47e+06, 2.2e+08, 292.060, 2.52e+06, 2.2e+08, 302.415, 2.55e+06, 2.2e+08, 311.215, 2.57e+06, 2.3e+08, 321.094, 2.59e+06, 2.3e+08, 331.360, 2.60e+06, 2.3e+08, 340.999, 2.61e+06, 2.3e+08, 351.095, 2.61e+06, 2.3e+08, l 361.352, 2.62e+06, 2.3e+08, l 371.311, 2.62e+06, 2.3e+08, 391.750, 2.63e+06, 2.3e+08, 411.491, 2.64e+06, 2.3e+08, 432.076, 2.64e+06, 2.3e+08, 452.069, 2.64e+06, 2.3e+08, i

, 471.774, 2.64e+06, 2.3e+08, i l 524.047, 2.65e+06, 2.3e+08,

573.273, 2.65e+06, 2.3e+08, j 573.273, 0.00, 0.00, l 1.00e+07, 0.00, 0.00/

{

NES&L DEPARTMENT CALCULATION SHEET '=od PREUM. CCN Wo. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CcN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 113 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 8.1.16 CARD SERIES 701: (Table 8)

Card Series 701 is a table that is used to describe the energy addition to the containment atmosphere from core decay power (Card Series 101), the metal-water reaction (Card Series 201), and the sensible heat addition occurring at the end of the post-Reflood phase (Card Series 201). This table designates the fraction of each of these energy sources that is l added to the energy inventory in the containment atmosphere. Card Series 701 also provides l for arbitrary addition of water mass to the containment atmosphere. This table incudes includes up to 20 sets of the following data entered in columnar form:

1. time (seconds) i 2. decay power multiplier (dimensionless) l 3. metal-water reaction multiplier (dimensionless)

4. water. addition rate (pounds / hour)

The decay power multiplier is the fraction of the decay power presented in Card Series 101 that is added to the containment atmosphere. As discussed in Design Input Item 4.6, for l times earlier than 573.273 seconds, decay power (or core decay heat) is considered in the CE supplied mass and energy release data of Card Series 301, and no Card Series 101 core l decay heat is added to the energy inventory in the contamment atmosphere. Therefore, for l times earlier than 573.273 seconds, the decay power multiplier is set to zero. For times later than 573.273 seconds, all of the com decay heat that is modeled in Card Series 101 is added to the energy inventory in the reactor vessel and not the containment atmosphere. Therefore, for times later than 573.273 seconds, the decay power multiplier is set to zero.

l The metal-water reaction multiplier is the fraction of the metal-water reaction energy as l presented in Card Series 201, and the fraction of the sensible heat addition occurring at the

! end of the post-Reflood phase as presented in Card Series 201, that is added to the l containment atmosphere.

As discussed in Design Input Item 4.7.a, the Zirconium metal-water reaction energy release is modeled as a constant energy release rate over the time interval between the start of the LOCA and the end of the reflood phase at time 211.1 seconds. This metal-water reaction I energy is released via the blowdown into the containment air space. Therefore, for times l earlier than 211.1 seconds the metal-water reaction multiplier as used to address the

! metal-water reaction energy is set to unity. For times later than 211.1 seconds no

metal-water reaction energy is released; therefore, for times later than 211.1 seconds the metal-water reaction multiplier as used to address the metal-water reaction energy is set to zero.

NES&L DEPARTMENT CALCULATION SHEET 'cc" " >

PRELIM. CCN NO. PAGE__ OF__

Proj:ct or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analtsis for Desian Basis LOCA Sheet No. 114 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 "

4 As discussed in Design Input Item 4.7.b, at the end of the post-reflood phase a significant amount of sensible heat energy remains stored in various RCS components. As time passes and the primary coolant decreases in temperature, this stored energy will be released back to the primary coolant. This sensible heat energy is modeled as entering the Reactor Vessel l

over the time interval between the end of the post-reflood phase at time 573.273 seconds and ~'

the end of the first day of the accident (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, equal to 86,400 seconds). For times earlier than 573.273 seconds, no sensible heat energy is released; therefore, the metal-water reaction multiplier as used to address the sensible heat energy is set to zero. For times between 573.273 and 86400 seconds, all of the sensible heat energy that is modeled in Card Series 201 is added to the energy inventory in the reactor vessel, and not to the containment atmosphere. Therefore, for times between 573.273 and 86400 seconds, the metal-water reaction multiplier as used to address the sensible heat energy is set to zero. For times later than 86400 seconds, no sensible heat energy is released; therefore, the metal-water reaction multiplier as used to address the sensible heat energy is set to zero.

This analysis does not model water addition to the containment atmosphere. Therefore, Card Series 701 shall be entered in the input data file as:

1

& LIST P00L=701, l

0, 0, 1, 0, '

211.1, 0, 1, 0, 211.1, 0, 0, 0, 573.273, 0, 0, 0, 8.64e+04, 0, 0, 0, 1.00e+07, 0, 0, 0/

. . -_= .- ._

NES&L DEPARTMENT CALCULATION SHEET l',s$cn uo. ,,o,_ o,_

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION: l CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 115 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 '

R. Nakano 01/18/94 J. Elliott 01/20/94 5 l l

8.1.17 CARD SERIES 801: (Table 9)

Card Series 801 is a table that provides input of information on the characteristics of the containment spmy system, the core safety injection system, and the source of water supply for these systems. The Card Series 801 table includes up to 16 sets of the following data entered in columnar form:

1. time (seconds)

2. containment spray flow rate (pounds / hour) l 3. reactor core safety injection water flow rate (pounds / hour) l 4. fraction of the safety injection flow poured directly into the containment sump due to injection into a ruptured pipe (dimensionless)

5. water temperature of containment spray ( F) l 6. water. temperature of safety injection (*F) l l This Cani Series is discussed in Design Input Item 4.10. When the source of water is the l containment sump, the temperature of the CS and the SI is the time dependent temperature of the sump (modeled in COPA'ITA as 0 *F). Card Series 801 shall be entered in the input l

data file as:

& LIST P00L=801, 0, 0, 0, 0, 100, 100, 60, 0, 0, 0, 100, 100, 60, 8.02e+05, 0, 0, 100, 100, 573.273, 8.02e+05, 0, 0, 100, 100,

! 573.273, 8.02e+05, 3.12e+06, 0.90, 100, 100, 800, 8.02e+05, 3.12e+06, 0.90, 100, 100, 900, 8.02e+05, 3.12e+06, 0.91, 100, 100, 1500, 8.02e+05, 3.12e+06, 0.92, 100, 100,'

2280, 8.02e+05, 3.12e+06, 0.93, 100, 100, 2280, 9.50e+05, 6.30e+05, 0.67, 0, 0, 3000, 9.50e+05, 6.30e+05, 0.68, 0, 0, 4000, 9.50e+05, 6.30e+05, 0.68, 0, 0, 5000, 9.50e+05, 6.30e+05, 0.70, 0, 0, 7200, 9.50e+05, 6.30e+05, 0.73, 0, 0, 7200, 9.50e+05, 6.30e+05, 0.50, 0, 0, 1.00+e7, 9.50e+05, 6.30e+05, 0.50, 0, 0/

r l

l NES&L DEPARTMENT CALCULATION SHEET 'cc" "o '

PRELIM. CCN WO. PAGE _ OF _

i Project or DCP/MMP_ SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 116 REV ORIGINATOR DATE IRE DATE REV ORIGT.dATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

f 4

8.1.18 CARD SERIES 901: (Table 10) l Card Series 901 pmvides for the arbitrary addition of air to the contamment atmosphere.

The arbitrary air addition table includes up to 20 sets of the following data entered in columnar form:

1. time (seconds)

2. containment air addition rate (pounds / hour) l 3. temperature of the added air ( F)

However, no arbitrary air addition is modeled in this analysis. Therefore, Card Series 901 shall be entered as:

SLIST P00L=901, 0.0, 0, 0, 1.0e+07, 0, 0/

i NES&L DEPARTMENT l

CALCULATION SHEET l' ,c"

, $c, no. ,,,,__ o,-

i Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSloN:

{

eCN NO. CCN -

Subj!ct Containment P/T Analvsis for Desian Basis LOCA Sheet No. 117 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

4 8.1.19 CARD SERIES 1001: (Table 11)

Card Series 1001 is used to determine the effect of cyclic outside temperature variations c.i long term post-accident temperature and pressure transients within the containment. The l time period covered by the data should be from zero to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The program will then use the data for succeeding 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> periods in very long time problems. The cyclic outside temperature variation table includes up to 25 sets of data of the following data entered in columnar form:

1. time (seconds)

2. temperature of the outside air ( F)

3. heat transfer coefficient between a heat sink and the outside atmosphere 2

(BTU /hr-ft *F)

In this problem no time-dependent atmospheric variations are modeled, and therefore the same data values are entered at times 0 and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Card Series 1001 is entered in the DBA LOCA input data file as:

l l & LIST P00L=1001,

! O, 100, 2.0, 24, 100, 2.0/

l The entries in Card Series 1001 include:

ITEM 2: 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />

, The initial time in hours. The staning time of the first.24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cycle is 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

1 ITEM 3: 100 'F The outside air temperature at the stan of the first 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cycle is assumed to be 100 *F as discussed in Assumption 3.5.a.

l ITEM 4: 2.0 BTU /hr-ft 2 ,op The heat transfer coefficient between a heat sink and the outside atmosphere at the start of the first 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cycle is assumed to be 2.0 BTU /hr-ft 2- F as discussed in Assumption 3.5.b.

NES&L DEPARTMENT CALCULATION SHEET >

'cc" ". CCN NO.

PRELIM PAGE_ _ OF_

ProjsCt or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desion Basis LOCA Sheet No. 118 l

REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE R l

0 R. Nakano 01/18/94 J. Elliott 01/20/94 h 5

ITEM 5: 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l

l The ending time of the first 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cycle is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l ITEM 6: 100 *F l

l The outside air temperature at the end of the first 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cycle is assumed to be 100 F as discussed in Assumption 3.5.a (same as at the start of the cycle).

l l

ITEM 7: 2 BTU /hr-ft _op 2 l

The heat transfer coefficient between a heat sink and the outside atmosphere at the end of 2

the first 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cycle is assumed to be 2.0 BTU /hr-ft _oF as discussed in Assumption 3.5.b (same as at the start of the cycle).

I i

NES&L DEPARTMENT CALCULATION SHEET 'cc" " '

PREUM. CCN NO. PAGE_ OF _

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment PTT Analvsis for Desian Basis LOCA Sheet No. 119 l

[ REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 "

4 8.1.20 CARD SERIES 1101: (Table 12)

As defined by Item 2 of Card Series 5, two containment emergency cooling units (air coolers) are modeled in this analysis. Card Series 1101 is used to describe the heat removal capability of one air cooler as a functio.: of containment atmosphere saturation temperature.

Card Series 1101 provides for a table of tables, each table representing a discrete air cooler coolant temperature.

Card Series 1101 is entered in the DBA LOCA input data file as:

& LIST P00L=1101, 1, 21, 105, 105, 0.000, 120, 1.670e+06, 130, 3.020e+06, 140, 4.570e+06, 150, 6.320e+06, 160, 8.270e+06, 170, 1.040e+07, 180, 1.273e+07, 190, 1.523e+07, 200, 1.788e+07, 210, 2.068e+07, 220, 2.361e+07, 230, 2.664e+07, 240, 2.974e+07, 250, 3.291e+07, 260, 3.611e+07, 270, 3.931e+07, 280, 4.252e+07, 287, 4.474e+07, 290, 4.569e+07, 300, 4.882e+07/

The entries in Card Series 1101 include: _

ITEM 2: INUM = 1 The value of 1 indicates that only one table of air cooler heat removal capability as a ftmetion of containment atmosphere saturation temperature is modeled. Separate tables

, are required for each air cooler coolant temperature, and this analysis only models a l single air cooler coolant temperature.

1

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1 NES&L DEPARTMENT CALCULATION SHEET 'cc" " '

PRELIM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 cCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 120 REV ORIGINATOR DATE th? DATE REV ORIGIN 4 TOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

s

, I ITEM 3: 21 l A value of 21 indicates that there are twenty-one sets of data in the table (Items 5 and 6) describing air cooler heat removal capability as a function of containment atmosphere saturation temperature.

ITEM 4: 105 *F The table (Items 5 and 6) describing air cooler heat removal capability as a function of containment atmosphere saturation temperature is based on an air cooler inlet tempemture a of 105 F, as discussed in Card Series 4, Item 5 and Card Series 5, Item 8.

ITEMS 5 and 6 Containment atmosphere saturation temperature (*F), and Corresponding cooler heat removal rate (BTU / hour)

The input data to be used in defining the Items 5 and 6 entries are discussed in Design Input Item 4.11.a.

NES&L DEPARTMENT CALCULATION SHEET '"N "o '

PRELIM. CCN NO. PAGE_ OF_

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Ba. sis LOCA Sheet NO. 121 REV ORIGINATOR DATE BRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

4 8.1.21 CARD SERIES 1105: UHS Parameters Card Series 1105 is used to provide the Ultimate Heat Sink (UHS) parameters as a function of time. Since no UHS are modeled in this analysis (See Item 6 of Card Series 0), Card Series 1105 is not included in the input file.

8.1.22 CARD SERIES 1106: External Heat Load / Sink Card Series 1106 is used to describe the time behavior of an external heat load / sink that is used only when IHEAT Option 5, 6 and 7 is defined for Item 2 of Card Series 0. In this l analysis, Item 2 of Card Series 0 is defined as 2, therefore Card Series 1106 is not included in the input file.

l 8.1.23 CARD SERIES 1110: Heat Transfer Coefficient Multipliers Carti Series 1110 describes the time behavior of the overall heat transfer coefficients for the primary and secondary heat exchangers used in the system. These values are multipliers for the values on Items 4 and 9 of Card Series 4, for the primary and secondary heat exchangers, respectively. In this analysis the Shutdown Cooling Heat Exchanger (SDCHX) is modeled as the primary heat exchanger; no secondary heat exchanger is modeled. The overall SDCHX heat transfer coefficient defined in Item 4 of Card Series 4 is a constant value, therefore Card Series 1110 is not included in the input file.

NES&L DEPARTMENT l

A CALCULATION SHEET 'cc" " >

PRELIM. CCN NO. PAGE OF l Project or DCP/MMP SONGS Units 2 & 3 Calc. No N-4080-026 CCN CONVERSION:

CCN NO. CCN -

j Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 122 i

REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R i O R. Nakano 01/18/94 J. Elliott 01/20/94 '

v 5

I

'8.1.24 CARD SERIES 1201: Table 13 i

Card Series 1201 provides for variation in the containment spray efficiency as a function of i.

the ratio of water vapor to air mass in the containment atmosphere. The contamment spray efficiency table includes up to 40 sets of the following data entered in columnar form:

1. (RATIO) the containment steam / air mass ratio (dimensionless) l l 2. (ETANOZ) spray efficiency (fraction) l 1

1 ,

l This Card Series is discussed in Design Input Item 4.12. Card Series 1201 is entered in the '

input data file as:

i & LIST Po0L=1201, O.0, 0.729,

, 0.1, 0.737, 0.2, 0.747, 0.3, 0.757, 0.4, 0.771, 1 0.5, 0.788, 1

0.6, 0.809, 0.7, 0.832, 0.8, 0.863, 0.9, 0.912, 1.0, 0.961, 1.1, 0.983, 1.2, 0.995, 1.3, 1.000/

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NES&L DEPARTMENT CALCULATION SHEET 'cc" "o '

PRELIM. CCW No. PAGE oF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 cCN CoNVERS ON:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 123 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 h 5

8.1.25 CARD SERIES 9001: Table 14 Card Series 9001 is used to specify the calculational time intervals and the data printout j intervals. The calc / print time table includes up to 50 sets of the following data entered in l columnar form:

1. time (seconds)

2. calculational interval (seconds) l l

3. energy balance printout interval (seconds) I

4. heat sink printout frequency (dimensionless) l Card Series 9001 is entered in the input data file as:

l

& LIST P00L=9001, i

5, 0.05, 0.1, 50, 10, 0.05, 0.25, 20, 15, 0.05, 0.50, 10, 20, 0.05, 0.50, 10, 100, 0.1, 1.0, 10, 200, 1.0, 5.0, 10, 400, 1.0, 10.0, 5, 700, 2.0, 20.0, 5, 3e+03, 5.0, 50.0, 2, le+04, 50.0, 500, 7, 1e+05, 50.0, 1e+04, 1, 1e+06, 50.0, 1e+05, 1, 1 e+07, 50.0, Se+05, 1, 2e+07, 50.0, Se+05, 1/

The selection of the time steps is based on the guidance given in Bechtel Nuclear Standard N2.3.2 (Reference 6.12, sheet 14 of 24). The present analysis uses a higher calculational

, frequency than that suggested in N2.3.2 in order to improve accuracy of the results. Finer l timesteps are particularly important for the heat sink energy at long times (See section l 8.3.2).

7 As shown in the following tables, for an analysis run time of 1 x 10 seconds (Card Series 1, Item 2), this data will generate a total of 20,790 internal calculations, 321 energy balance printouts and 50 heat sink printouts:

l l

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NES&L DEPARTMENT CALCULATION SHEET '

'cc" ". CCN WO.

PRELIM PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Sc 4lect Containment P/T Analysis for Desian Basis LOCA Sheet No. 124 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R l 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

S INTERNAL CALCULATIONAL FREQUENCY TIME INTERVAL TIME INTERVAL INTERNAL NUMBER OF DURATION CALCULATION ' INTERNAL (seconds) INTERVAL CALCULATIONS (every # seconds)

(seconds)

O to 5 5 0.05 100 5 to 10 5 0.05 100 10 to 15 5 0.05 100 15 to 20 5 0.05 100 20 to 100 80 0.1 800 100 to 200 100 1.0 100 l

200 to 400 200 1.0 200 400 to 700 300 2.0 150 700 to 3e3 2,300 5.0 460 3e3 to le4 7,000 50.0 140 le4 to le5 90,000 50.0 1800 le5 to le6 900,000 50.0 18,000 le6 to le7 9,000,000 50.0 180,000 Total Number of calculations : 202,050.00

NES&L DEPARTMENT CALCULATION SHEET '

'cc" ". CCN No.

PRELIM PAGE OF Proitet or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CoNVERSloN:

CCN No. CCN -

l Subj:ct Containment P/T Analysis for Desian Basis LOCA Sheet No. 125 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 5

ENERGY BALANCE PRINTOUT FREQUENCY TIME INTERVAL TIME INTERVAL ENERGY BALANCE NUMBER OF DURATION PRINTOUT INTERVAL ENERGY BALANCE (seconds) (seconds) (every # seconds) PRINTOUTS 0 to 5 5 0.10 50 l

i 5 to 10 5 0.25 20 l

l 10 to 15 5 0.50 10 15 to 20 5 0.50 10 l

20 to 100 80 1 80 l 100 to 200 100 5 20 200 to 400 200 10 20 400 to 700 300 20 15 l 700 to 3e3 2,300 50 46 3e3 to le4 7,000 500 14 le4 to le5 90,000 10,000 9 1e5 to le6 900,000 100,000 9 l

j le6 to le7 9,000,000 500,000 18 Total Number of Energy Balance Printouts: 321 l

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l NES&L DEPARTMENT CALCULATION SHEET '

'cc" ". CCN NO.

PRELIM PAG _e_ OF_

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 126 1

l REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 "

s 1

HEAT SINK PRINTOUT FREQUENCY l

l TIME INTERVAL NUMBER OF HEAT SINK NUMBER OF ENERGY BALANCE PRINTOUT INTERVAL HEAT SINK (seconds) PRINTOUTS (one for every # PRINTOUTS energy printouts)

O to 5 50 50 1 S to 10 20 20 1 10 to 15 10 10 1 15 to 20 10 10 1 20 to 100 80 10 8 100 to 200 20 10 2 200 to 400 20 5 4 400 to 700 15 5 3 700 to 3e3 46 2 23 3e3 to le4 14 7 2 le4 to le5 9 1 9 le5 to le6 9 1 9 le6 to le7 18 1 18 Total Number of Heat Sink Printouts: 82 l

l l

NES&L DEPARTMENT CALCULATION SHEET M"un SCN No. exoE_ or_

Project Or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment PTT Analysis for Desian Basis LOCA Sheet No. 127 i

REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 l 8.1.26 VARIABLE END CARD l

l

' This card must follow the group of variable data cards. It contains the following fixed infonnation in Columns 2 through 17:

& LIST POOL =9999/

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NES&L DEPARTMENT CALCULATION SHEET " No' PRELIM. CCN No. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERStoN:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 128 REV ORIGINATOR DATE IRE DATE REV CRIGINATOR DATE IRE DATE R 0 8 R. Nakano 01/18/94 J. Elliott 01/20/94 4

8.1.27 HEAT SINK DATA SERIES The heat sink data series are used to describe the characteristics of the stmetural heat sinks.

In this analysis twenty heat sinks are modeled (Card Series 1, Item 7). Each heat sink (number XX) is detailed in the COPA'ITA Code as a set of heat sink data cards. These data cards include:

Title Card Card Series 1XX001 Card Series 1XX101 Card Series 1XX201 Card Series 1XX300 Card Series 1XX400 Card Series 1XX001 contains general information on be heat sink. Card Series 1XX101 provides information on heat sink mesh point spacing. Card Series 1XX201 specifies the set of material properties for each region of the heat sink. Card Series 1XX300 selects the type and variation in magnitude of the decay power source within the heat sink. Card Series 1XX400 is used to select the appropriate boundary conditions for the left and right surfaces of each heat sink.

In general, the presence (or increase in size) of a heat sink has two consequences: (1) depressing the peak contamment pressure and temperature by absorbing energy released via the break, and (2) extending the duration of above ambient containment pressures and temperatures by mleasing energy back into the containment during the latter part of the nominal 120-day (actual 116-day) post-accident period. Beyond these two general consequences, the impact of a change in the modeling of a heat sink (e.g., a change in the heat sink layer thicknesses) is difficult to qualify,

NES&L DEPARTMENT l

CALCULATION SHEET ' "

lREun SCN No. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 '

CCN CONVERSloN:

l cCN No. CCN -

l Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 129 l l

REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94

• 5 8.1.27.1 HS #1 - Reactor Building Dome The characteristics of the Reactor Building Dome are as determined in Calculation N-4080-002 (Reference 6.1.g, pages 121 through 125) for Heat Sink 1, except for the thickness of the Containment Liner /Conente air gap interface. 'l As discussed in Design Input Item 4.13.a, the effective thickness of the interface (air gap) will be 0.00035 feet. With this change, Heat Sink #1 describes the Reactor Building Dome  ;

as modeled:

l Geometry Slab l Surface Area 34693.22 ft2 Organic Paint (material 4) thickness-Left 0.00075 ft (= 0.009 in)

Boundary Carbon Steel (material 1) Uner thickness 0.02083 ft (= 0.25 in)

Air Gap Interface (material 5) thickness 0.00035 ft Concrete (material 2) thickness-Right Boundary 4.0417 ft (= 48.5 in)

Left Boundary condition Exposed to containment atmosphere l Right Boundary condition Exposed to outside environment The effect of the change in the air gap thickness is reflected in Card Series 101101. This Card Series defines the location of the right boundary and nodalization of each region. The air gap is the third region of Heat Sink 1. The increase in the modeled air gap thickness from 0.00017 feet to 0.00035 feet requires that the modeled location of the Region 3 right boundary be increased by 0.00018 feet. To maintain the coriect thickness of each Region that follows the air gap region necessitates that the modeled locations of the right boundaries of these subsequent regions be increased by the same 0.00018 feet. The changes from the right boundary locations determined in Calculation N-4080-002 are:

1st Region: no change in the right boundary location 2nd Region: no change in the right boundary location 3rd Region: right boundary shifted from 0.02175 to 0.02193 feet 4th Region: right boundary shifted from 0.06342 to 0.06360 feet 5th Region: right boundary shifted from 0.2301 to 0.23028 feet 6th Region: right boundary shifted from 1.000921 to 1.0011G feet 7th Region: right boundary shifted from 4.06345 to 4.06363 feet

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. NES&L DEPARTMENT '

1 CALCULATION SHEET 'cc" "o ' l PRELIM. CCN NO. PAGE__OF _

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN No. CCN --

Subject Containment P/T Analvsis for Desian Basis LOCA 1

Sheet No. 130 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 1 0 R. Nakano 01/18/94 J. Elliott 01/20/94 E l

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The Card Series set defining Heat Sink 1 is entered in the input data file as:

• H$ #1 - REACTOR BUILDING DOME

& LIST P00L=101001, 100, 7, 0, 0, 0, 0, 34693.22/

1 & LIST P00L=101101, 5, 0.00075, 3, 0.02158, 3, 0.02193, 10, 0.06360, 20, 0.23028, 37, 1.00110, 21, 4.06363/

& LIST P00L=101201, 4, 1, 5, 2, 2, 2, 2/

& LIST P00L=101300, 0, 0/

i & LIST P00L=101400, 2, 2, 1, 1/

4

NES&L DEPARTMENT CALCULATION SHEET 'cc" " d PRELIM. CCW NO. PAGE__ OF_

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-01[j CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 131 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 8.1.27.2 HS #2 - Reactor Building Cylinder #1 (above grade, between El. 29'6" and 112'0")

The characteristics of the Reactor Building Cylinder #1 (above gmde, between plant elevations 29'6" and 112'0") are as determined in Calculation N-4080-002 (Reference 6.1.g, pages 125 through 128) for Heat Sink 2, except for the thickness of the Containment Liner / Concrete air gap interface.

As discussed in Design Input Item 4.13.a, the effective thickness of the interface (air gap) will be 0.00035 feet. With this change, Heat Sink #2 describes the Reactor Building Cylinder 1 as modeled:

l Geometry Slab Surface Ama 38120 ft2 Organic Paint (material 4) thickness-Ieft 0.00075 ft (= 0.009 in) 1 Boundary l Carbon Steel (material 1) Liner thickness 0.02083 ft (= 0.25 in)

Air Gap Interface (material 5) thickness 0.00035 ft Concmte (material 2) thickness-Right Boundary 4.33333 ft (= 52 in) l Left Boundary condition Exposed to containment atmosphere Right Boundary condition Exposed to outside envimnment The effect of the change in the air gap thickness is reflected in Card Series 102101. This Card Series defines the location of the right boundary and nodalization of each region. The air gap is the third region of Heat Sink 2. The increase in the modeled air gap tidekness from 0.00017 feet to 0.00035 feet requires that the modeled location of the Region 3 right boundary be increased by 0.00018 feet. To maintain the correct thickness of each Region that follows the air gap region necessitates that the modeled locations of the right boundaries of these subsequent regions be increased by the same 0.00018 feet. The changes from the right boundary locations determined in Calculation N-4080-002 are:

1st Region: no change in the right boundary location 2nd Region: no change in the right boundary location 3rd Region: right boundary shifted fmm 0.02175 to 0.02193 feet 4th Region: right boundary shifted fmm 0.06342 to 0.06360 feet 5th Region: right boundary shifted from 0.14676 to 0.14694 feet 6th Region: right boundary shifted from 0.917581 to 0.917761 feet

NES&L DEPARTMENT j CALCULATION SHEET 'cc = '

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Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 132 REV ORIGINATOR i DATE IRE DATE REV ORIGINATOR DATE IRE DATE R I O R. Nakano 01/18/94 J. Elliott 01/20/94 h

5 7th Region: right boundary shifted from 4.35508 to 4.35526 feet l

The Card Series set defining Heat Sink 2 is entered in the input data file as:

• HS #2 - CYLINDER WALL BETWEEN El. 29'6" AND 112'0"

& LIST P00L=102001, 100, 7, 0, 0, 0, 0, 38120/

& LIST P00L=102101, 5, 0.00075, 3, 0.02158, 3, 0.02193, 10, 0.06360, 20, 0.14694, 37, 0.917761, 21, 4.35526/

& LIST P00L=102201, 4, 1, 5, 2, 2, 2, 2/

& LIST P00Ls102300, 0, 0/

ELIST P00L=102400, 2, 2, 1, 1/

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i NES&L DEPARTMENT i

CALCULATION SHEET 'co" "

PREUM

. CCN NO. PAGE OF Proj:ct or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

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l Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 133 I REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R l 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 l l l

8.1.27.3 HS #3 - Reactor Building Cylinder #2 (below grade, between El.15'0" and 29'6")

The characteristics of the Reactor Building Cylinder #2 (below grade, between plant l elevations 15'0" and 29'6") are as determined in Calculation N-4080-002 (Reference 6.1.g, pages 134 through 136) for Heat Sink 3, except for the thickness of the Containment Liner / Concrete air gap interface.

As discussed in Design Input Item 4.13.a, the effective thickness of the interface (air gap) will be 0.00035 feet. With this change, Heat Sink #3 describes the Reactor Building Cylinder 2 as modeled:

Geometry Slab Surface Area 6667.38 ft2 Organic Paint (material 4) thickness-Left 0.00075 ft (= 0.009 in)

Boundary l

Carbon Steel (material 1) Liner thickness 0.02083 ft (= 0.25 in)

Air Gap Interface (material 5) thickness 0.00035 ft Concrete (material 2) thickness-Right Boundary 4.33333 ft (= 52 in) l I2ft Boundary condition Exposed to containment atmosphere l Right Boundary condition Insulated, no heat transfer to the I ground outside the lower portion of the Reactor Building Cylinder Because there is no heat transfer across the right boundary, the bulk temperature control for the right boundary condition is not used by the COPATTA Code. Therefore, in this analysis the bulk temperature control for the right boundary condition is modeled as the containment vapor temperature for convective heat transfer or the saturation tempenture at the l cor"ainment steam partial pressure for condensing heat transfer (i.e., Option 2 for Item 5 of l Cacu 3eries IXX400). This differs from the modeling of Calculation N-4080-002, which employed Option 0 for Item 5 of Card Series IXX400. Since the bulk tempemture control for the right boundary condition has no meaning for this Heat Sink, the decision to model Item 5 with Option 2 rather than Option 0 has the beneficial consequence of allowing the use of any positive value to be modeled as the variable TCONT in Item 7 of Card Series 2.

The effect of the change in the air gap thickness is reflected in Card Series 103101. This Card Series defines the location of the right boundary and nodalization of each region. The air gap is the third region of Heat Sink 3. The increase in the modeled air gap thickness

NES&L DEPARTMENT CALCULATION SHEET '""" '

PRELIM. CCN MO. PAGE oF Project or DCP/MMP SQNQS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

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Subject Containment P/T Analysts for Desian Basis LOCA Sheet No. '34 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE l R

E O R. Nakano 01/18/94 J. Elliott 01/20/94 y I

from 0.00017 feet to 0.00035 feet requires that the modeled location of the Region 3 right boundary be increased by 0.00018 feet. To maintain the correct thickness of each Region that follows the air gap region necessitates that the modeled locations of the right boundaries of these subsequent regions be increased by the same 0.00018 feet. The changes from the right boundary locations determined in Calculation N-4080-002 are:

1st Region: no change in the right boundary location 2nd Region: no change in the right boundary location 3rd Region: right boundary shifted from 0.02175 to 0.02193 feet 4th Region: right boundary shifted from 0.06342 to 0.06360 feet 5th Region: right boundary shifted from 0.14676 to 0.14694 feet 6th Region: right boundary shifted from 0.917581 to 0.917761 feet 7th Region: right bounoary shifted from 4.35508 to 4.35526 feet The Card Series set defming Heat Sink 3 is entered in the input data file as:

• MS #3 - CYLINDER WALL BETWEEN El. 15'0" AND El. 29'6"

& LIST P00L=103001,100, 7, 0, 0, 0, 0, 6667.38/

& LIST P00L=103101, 5, 0.00075, 3, 0.02158, 3, 0.02193, 10, 0.06360, 20, 0.14694, 37, 0.917761, 21, 4.35526/

& LIST P00Ls103201, 4, 1, 5, 2, 2, 2, 2/

ELIST P00L=103300, 0, 0/

& LIST P00L=103400, 2, 2, 0, 2/

NES&L DEPARTMENT CALCULATION SHEET 'cc" " '

PRELIM. CCN MO. PAGE OF

! Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

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Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 135 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE lRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 4

l l 8.1.27.4 HS #4 - Basemat (other than the Reactor Basemat) l The characteristics of the Basemat (other than the Reactor Basemat) are as determined in i Calculation N-4080-002 (Reference 6.1.g, pages 137 through 139) for Heat Sink 4.

1 Heat Sink #4 describes the Basemat (other than Reactor Basemat) as modeled:

Geometry Slab Surface Area 12800 ft2 l l Organic Paint (material 4) thickness-Left 0.00067 ft (= 0.008 in) l l Boundary l

l Concrete #1 (material 2) thickness 1.52631 ft Carbon Steel (material 1) Liner thickness 0.02083 ft (= 0.25 in)

Concrete #2 (material 2) thickness-Right 9.473685 ft j l Boundary l Ieft Boundary condition Exposed to containment sump l l water Right Boundary condition Insulated, no heat transfer to the ground beneath the basemat Due to an addition error, Calculation N-4080-002 (page 138) incormctly modeled the right boundary coordinate of the second Concrete Region at 11.02105 feet. The determination of the right boundary coordinate of the second Concrete region was based on the right boundary coordinate of the Carbon Steel Region of 1.54736 feet, rather than the correct coordinate of 1.54781 feet. In this analysis the right boundary coordinate of the second concrete region '

will be modeled at the correct position of 11.02150 feet:

Right Boundary Coordinate of Concrete Region #2 = 1.54781 ft + 9.473685 ft

= 11.02150 feet Because there is no heat transfer across the right boundary, the bulk temperature control for

! the right boundary condition is not used by the COPATTA Code. Therefore, in this analysis the bulk temperature control for the right boundary condition is modeled as the containment liquid temperature (i.e., Option 3 for Item 5 of Card Series 1XX400). This differs from the modeling of Calculation N-4080-002, which employed Option 0 for Item 5 of Card Series IXX400. Since the bulk temperature control for the right boundary condition has no meaning for this Heat Sink, the decision to model Item 5 with Option 3 rather than Option 0 i

NES&L DEPARTMENT CALCULATION SHEET 'cc" "o '

PRELIM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 136 REV ORIGINATOR DATE IRE DATE REV ORIG 1NATOR DATE IRE DATE R E

l 0 R. Nakano 01/18/94 J. Elliott 01/20/94 y 5

l l

l l has the beneficial consequence of allowing the use of any positive value to be modeled as the variable TCONT in Item 7 of Card Series 2.

The Card Series set defining Heat Sink 4 is entered in the input data file as:

• HS #4 - BASEMAT (OTHER THAN REACTOR BASEMAT)

& LIST P00L=104001, 53, 5, 0, 0, 0, 0, 12800/

& LIST P00L=104101, 3, 0.00067, 7, 0.1, 20, 1.52698, 2, 1.54781, 20, 11.02150/

& LIST P00L=104201, 4, 2, 2, 1, 2/

& LIST P00L=104300, 0, 0/

, & LIST P00L=104400, 3, 3, 0, 3/

l l

NES&L DEPARTMENT l

CALCULATION SHEET ' ""

SEu UCN NO. PAGE OF Projzct or DCP/MMP_ SONGS Units 2 & 3 Calc. No. N-4080-026 CcN CONVERSION:

{

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 137 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE BRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

S 8.1.27.5 HS #5 - Reactor Basemat and Steam Generator Pedestals The characteristics of the Reactor Basemat and Steam Generator Pedestals are as determined in Calculation N-4080-002 (Reference 6.1.g, pages 139 through 141) for Heat Sink 5.

Heat Sink #5 describes the Reactor Basemat and Steam Generator Pedestals as modeled:

Geometry Sho Surface Area 1644 ft2 Organic Paint (material 4) thickness-Left 0.00158 ft Boundary Concrete (material 2) thickness-Right Boundary 8.42934 ft Left Boundary condition Exposed to contamment sump water Right Boundary condition Insulated, no heat tansfer to the ground beneath the basemat In Calculation N-4080-002 (page 141) the heat transfer coefficient control for the left boundary condition was modeled as Option 11 for Item 2 of Card Series 1XX400. This resulted in the use of a user specified heat transfer coefficient entered in Card Series 420001.

In Calculation N-4080-002 (page 193) a heat sink to contamment sump water heat transfer  !

coefficient of 0.4 BTU /hr-ft 2- F was specified. This same heat transfer coefficient value is I available as Option 3 for Item 2 of Card Series 1XX400. To negate the need for input for l Card Series 420001, in this calculation the heat transfer coefficient control for the left boundary condition is modeled as Option 3 for Item 2 of Card Series 1XX400.

Because there is no heat transfer across the right boundary, the bulk temperature control for the right boundary condition is not used by the COPA'ITA Code. Therefore, in this analysis the bulk temperature control for the right boundary condition is modeled as the containment liquid temperature (i.e., Option 3 for Item 5 of Card Series 1XX400). This differs from the modeling of Calculation N-4080-002, which employed Option 0 for Item 5 of Card Series 1XX400. Since the bulk tempemture control for the right boundary condition has no meaning for this Heat Sink, the decision to modelItem 5 with Option 3 rather than Option 0 has the beneficial consequence of allowing the use of any positive value to be modeled as the variable TCONT in Item 7 of Card Series 2.

NES&L DEPARTMENT CALCULATION SHEET '

'cc" ".CCM NO.

PRELIM PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 cCN CONVERSION:

CCN NO. CCN - )

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 138 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 5

The Card Series set defining Heat Sink 5 is entered in the input data file as:

• HS #5 - REACTOR BASEMAT & S.C. PEDESTALS

& LIST POOL =105001, 70, 4, 0, 0, 0, 0, 1644/

l & LIST P00L=105101, 4, 0.00158, 10, 0.1, l 30, 2.00, 25, 8.43092/

l & LIST P00L=105201, 4, 2, 2, 2/

l & LIST P00L=105300, 0, 0/

& LIST P00L=105400, 3, 3, 0, 3/

i 1

N d

NES&L DEPARTMENT CALCULATION SHEET 'cs"Lno.

la ,,,, ,_ o,_

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 139 i

REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE 1RE DATE R l 0 R. Nakano 01/18/94 J. Elliott 01/20/94 " '

5 8.1.27.6 HS #6 - Reactor Cavity Walls below El.15'0" The characteristics of the Reactor Cavity Walls below plant elevation 15'0" are as determined in Calculation N-4080-002 (Reference 6.1.g, pages 142 through 144) for Heat Sink 6.

Heat Sink #6 describes the Reactor Cavity Walls below El.15'0" as modeled:

Geometry Cylindrical Inside Radius 11.75 ft Height of Cylinder (wall height) 21.5 ft l Surface Area 1590 ft2 Organic Paint (material 4) thickness-Ieft 0.00192 ft (= 0.023 in)

Boundary Concrete (material 2) thickness-Right Boundary 13.5 ft (= 162 in) left Boundary condition Exposed to containment sump water Right Boundary condition Insulated, no heat transfer to the ground on the opposite side of the walls Due to an addition error, Calculation N-4080-002 (page 143) incorrectly modeled the right boundary coordinate of the Concrete Region at 25.25 feet. The determination of the right boundary coordinate of the Concrete region was based on adding the thickness of the Concrete Region to the inside radius of the cylinder model, and neglecting to add the thickness of the Organic Paint Region. In this analysis the right boundary coordinate of the Concrete Region will be modeled at the correct position of 25.25192 feet:

Right Boundary Coordinate of Concrete Region = 11.75 ft + 0.00192 ft + 13.5 ft

= 25.25192 feet In Calculation N-4080-002 (page 198) the cylinder height was incorrectly entered into the COPATTA Code input file as 8.5 feet, rather than the 21.5 feet value calculated on page 143. In this analysis the cylinder height will be modeled as 21.5 feet.

In Calculation N-4080-002 (page 144) the heat transfer coefficient control for the left boundary condition was modeled as Option 11 for Item 2 of Card Series 1XX400. This

NES&L DEPARTMENT CALCULATION SHEET 'cc" " '

PRELIM. CCN RO. PA G E__ OF__

Project or DCP/MMP SONGS Units 2 & 3 Calc No. N-4080-026 cCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 140 l

! REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE R l 0 R. Nakano 01/18/94 J. Elliott 01/20/94 5

resulted in the use of a user specified heat tmnsfer coefficient entered in Card Series 420001.

In Calculation N-4080-002 (page 193) a heat sink to containment sump water heat transfer coefficient of 0.4 BTU /hr-ft 2- F was specified. This same heat transfer coefficient value is available as Option 3 for Item 2 of Card Series 1XX400. To negate the need for input for Card Series 420001, in this calculation the heat transfer coefficient control for the left boundary condition is modeled as Option 3 for Item 2 of Card Series IXX400.

Because them is no heat transfer across the right boundary, the bulk temperature control for the right boundary condition is not used by the COPATTA Code. Therefore, in this analysis the bulk temperature control for the right boundary condition is modeled as the containment liquid temperature (i.e., Option 3 for Item 5 of Card Series 1XX400). This differs from the modeling of Calculation N-4080-002, which employed Option 0 for Item 5 of Card Series 1XX400. Since the bulk temperature control for the right boundary condition has no meaning for this Heat Sink, the decision to model Item 5 with Option 3 rather than Option 0 has the beneficial consequence of allowing the use of any positive value to be modeled as the variable TCONT in Item 7 of Card Series 2.

l The Card Series set defining Heat Sink 6 is entered in the input data file as:

• HS #6 - REACTOR CAVITY WALLS BELOW El. 15'0" l & LIST P00L=106001, 93, 5,1,11.75, 0, 0, 21.5/

& LIST P00L=106101, 5, 11.75192, 7, 11.77292, 30, 13.29923, 30, 19.29923, 20, 25.25192/

& LIST P00L=106201, 4, 2, 2, 2, 2/

& LIST P00L=106300, 0, 0/

& LIST P00L=106400, 3, 3, 0, 3/

l

NES&L DEPARTMENT CALCULATION SHEET 'cc" "o '

PREUM. CCW NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN No. CCN --

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 141 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R

! O R. Nakano 01/18/94 J. Elliott 01/20/94 '

4 8.1.27.7 HS #7 - Reactor Cavity Walls above El.15'0" l

The characteristics of th: Reactor Cavity Walls above plant elevation 15'0" are as determined j

! in Calculation N-4080-002 (Reference 6.1.g, pages 144 thmugh 146) for Heat Sink 7.

1 Due to heat sink symmetry, only one-half of the heat sink is modeled. The modeled surface area is the total heat sink surface area, equal to twice the actual surface area of one side of the heat sink. The modeled thickness of the center concrete portion is one-half of the actual thickness of the center concrete portion of the heat sink. And, the modeled outside boundary is the adiabatic (insulated) condition existing at the midplane of the symmetrical heat sink.

1 Heat Sink #7 describes the Reactor Cavity Walls above El.15'0" as modeled:

Geometry Slab l

l Surface Area 2810 ft2 l Organic Paint (material 4) thickness-Left 0.00192 ft (= 0.023 in)

Boundary l Concrete (material 2) thickness-Right Boundary 4.00 ft (= 48 in)

Left Boundary condition Exposed to containment atmosphere Right Boundary condition Insulated, no heat transfer is l modeled across the heat sink centerline l Because there is no heat transfer across the right boundary, the bulk temperature control for the right boundary condition is not used by the COPATTA-Code. Therefore, in this analysis the bulk temperature control for the right boundary condition is modeled as the containment vapor temperature for convective heat transfer or the saturation temperature at the containment steam partial pressure for condensing heat transfer (i.e., Option 2 for Item 5 of Card Series 1XX400). This differs fmm the modeling of Calculation N-4080-002, which employed Option 0 for Item 5 of Card Series 1XX400. Since the bulk temperature control for the right boundary condition has no meaning for this Heat Sink, the decision to model Item 5 with Option 2 rather than Option 0 has the beneficial consequence of allowing the use l of any positive value to be modeled as the variable TCONT in Item 7 of Card Series 2.

I 4

m n .emam 4: u Ama A a 4s- s - p --o &J -- 14-A A' s,.1..4,. -- aw. ..a.

NES&L DEPARTMENT CALCULATION SHEET 'oc" " '

PRELIM, CCW NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 142 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 The Card Series set defining Heat Sink 7 is entered in the input data file as:

HS #7 - REACTOR CAVITY WAL LS ABOVE Et.1580a

& LIST P00L=107001, 68, 'i, 0, 0, 0, 0, 2810/

& LIST P00L=107101, 5, 0.00191, 7, 0.02292, 15, 0.40192, 20, 2.00, 20, 4.00192/

& LIST P00L=107201, 4, 2, 2, 2, 2/

& LIST P00L=107300, 0, 0/

& LIST P00L=107400, 2, 2, 0, 2/

l l

l k

i

{

1 l

l l

l

NES&L DEPARTMENT '

CALCULATION SHEET 'cc" "o '

PRELIM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 cCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 143 REV ORIGINATOR DATE 1RE DATE REV OR!GINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 8.1.27.8 HS #8 - Lined Refueling Canal Walls l The characteristics of the Lined Refueling Canal Walls are as determined in Calculation N-4080-002 (Reference 6.1.g, pages 146 through 149) for Heat Sink 8.

Heat Sink #8 describes the Lined Refueling Canal Walls as modeled:

1 Geometry Slab Surface Area 9200 ft2 l Stainless Steel (material 3) thickness-Left 0.01563 ft (= 0.1875 in) l Boundary

( Concrete (material 2) thickness 4.00 ft (= 48 in)

Organic Paint (material 4) thickness-Right 0.00192 ft (= 0.023 in)

Boundary l 1

l Left Boundary condition Exposed to containment atmosphere l

! Right Boundary condition Exposed to containment atmosphere The Card Series set defining Heat Sink 8 is entered in the input data file as:

• HS #8 - LINED REFUELING CANAL WALLS

& LIST P00L=108001, 86, 6, 0, 0, 0, 0, 9200/

& LIST P00L=108101, 5, 0.01563, 20, 0.1, 15, 0.41563, 20, 2.00, 20, 4.01563, 5, 4.01755/

l & LIST P00L=108201, 3, 2, 2, 2, 2, 4/

& LIST P00L=108300, 0, 0/

& LIST P00L=108400, 2, 2, 2, 2/

1 l

l i

l l

4

NES&L DEPARTMENT CALCULATION SHEET  !'E"un sCN No. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 144 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

8.1.27.9 HS #9 - Steam Generator Compartment Walls, Unlined Refueling Canal Walls above El. 63'6", and Other Interior Walls The characteristics of the Steam Generator Compartment Walls, Unlined Refueling Canal Walls above plant elevation 63'6", and Other Interior Walls are as determined in Calculation N-4080-002 (Reference 6.1.g, pages 149 through 152) for Heat Sink 9.

l Due to heat sink symmetry, only one-half of the heat sink is modeled. The modeled surface l

area is the total heat sink surface area, equal to twice the actual surface area of one side of the heat sink. The modeled thickness of the center concrete portion is one-half of the actual thickness of the center concrete portion of the heat sink. And, the modeled outside boundary is the adiabatic (insulated) condition existing at the midplane of the symmetrical heat sink.

Heat Sink #9 describes the Steam Generator Compartment Walls, Unlined Refueling Canal Walls above El. 63'6", and Other Interior Walls as modeled:

Geometry Slab i Surface Area 41976 ft2 Organic Paint (material 4) thickness-Left 0.00192 ft (= 0.023 in)

Boundary Concrete (material 2) thickness-Right Boundary 1.71684 ft left. Boundary condition Exposed to containment atmosphere j Right Boundary condition Insulated, no heat transfer across the heat sink centerline l

Because there is no heat tmnsfer across the right boundary, the bulk temperature control for the right boundary condition is not used by the COPA'ITA Code. Therefore, in this analysis the bulk tempemture control for the right boundary condition is modeled as the containment vapor temperature for convective heat transfer or the saturation temperature at the containment steam partial pressure for condensing heat transfer (i.e., Option 2 for Item 5 of Card Series IXX400). This differs from the modeling of Calculation N-4080-002, which employed Option 0 for Item 5 of Card Series IXX400. Since the bulk temperature control i

for the right boundary condition has no meaning for this Heat Sink, the decision to model Item 5 with Option 2 rather than Option 0 has the beneficial consequence of allowing the use of any positive value to be modeled as the variable TCONT in Item 7 of Card Series 2.

l l

l l

NES&L DEPARTMENT '

1 CALCULATION SHEET ',cc7 a, "%cu go. ,,,,_ o,_ i Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 145 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE BRE DATE R O R. Nakano 01/18/94 J. Elliott 01/20/94 E y

5 The Card Series set defining Heat Sink 9 is entered in the input data file as:

• HS #9 - S.G. CMPRTMNT WALLS, UNLINED REFL CNL WALLS /0TH INT WALLS

& LIST P00L=109001, 78, 4, 0, 0, 0, 0, 41976/

& LIST P00L=109101, 5, 0.00192, 10, 0.04233, 12, 0.1, 50, 1.71876/

& LIST P00L=109201, 4, 2, 2, 2/

& LIST P00L=109300, 0, 0/

& LIST P00L=109400, 2, 2, 0, 2/

NES&L DEPARTMENT CALCULATION SHEET ' i;"fics ls no. ,,,, o, Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN NO. CCN -

l Subject _Containrnent P/T Analysis for Desian Basis LOCA Sheet No. 146 1

REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 4

l 8.1.27.10 HS #10 - Floor Slabs (other than basemats) l The characteristics of the Floor Slabs (other than basemats) represent a refinement of the l t characteristics determined in Calculation N-4080-002 (pages 152 through 155) for Heat l Sink 10.

l Heat Sink #10 describes Floor Slabs (other than basemats) as modeled:

l Geometry Slab 1

Surface Area 17474 ft2 Organic Paint #1 (material 4) thickness-Left 0.00014 ft Boundary Carbon Steel (material 1) thickness 0.005208 ft (= 0.0625 in)

Concrete (material 2) thickness 1.5 ft Organic Paint #2 (material 4) thickness-Right 0.000667 ft (= 0.008 in)

Boundary Left Boundary condition Exposed to containment atmosphere Right Boundary condidon Exposed to containment atmosphere l

The 17474 square foot surface area of the floor slabs modeled in this analysis is equivalent to the concrete side surface area given in Calculation C-257-1.96.01 (Reference 6.1.a, pages 15 and 26). The same calculation gives a metal decking are of 23,240 squam feet (page 26).

The higher area is due to the metal decking which is corrugated steel while the smaller area is the area of the concrete slab under it. The smaller area of 17474 square foot will be I conservatively used here.  !

Calculation N-4080-002 (Reference 6.1.g, page 152) used a value of 17172 square feet and is based on input data provided as Attachment 1 to Calculation N-4080-002 (page 328). This surface area differs from that described in Calculation N-4080-005 (Reference 6.1.i, page 42), which attempted to refine the floor slab heat sink model by increasing the surface area l of the floor slab from 17172 to 23240 square feet. Although the area was to be increased, i

the actual COPATTA Code nms of Calculation N-4080-005 continued to model the original smaller floor slab surface area of 17172 square feet.

As discussed in Design Input Item 4.13.k, when the nodalization of the Concrete Region was performed, Calculation N-4080-002 (page 153) modeled the concrete as Heat Sink 10 Regions 3,4 and 5, with a total concrete thickness of 2.0 feet rather than 1.5 feet. To

NES&L DEPARTMENT CALCULATION SHEET 'l,,"j lcy no. g,c, o, Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 147 I REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 i

V 5

l model the correct concrete thickness requires that the Region 5 thickness be reduced by 0.5 i

feet. This is accomplished by shifting the right boundary of Region 5 to the left by 0.5 feet.

As a consequence, the right boundary of Region 6 (the second Organic Paint layer) must also  ;

be shifted to the left by 0.5 feet. The changes from the right boundary locations determined '

in Calculation N-4080-002 are:

l 1st Region: no change in the right boundary location 2nd Region: no change in the right boundary location 3rd Region: no change in the right boundary location 4th Region: no change in the right boundary location 5th Region: right boundary shifted from 2.005348 to 1.505348 feet 6th Region: right boundary shifted from 2.006015 to 1.506015 feet The Card Series set defining Heat Sink 10 is entered in the input data file as:

I

• HS #10 - FLOOR SLABS (OTHER THAN ELSEMATS) j & LIST P00L=110001, 67, 6, 0, 0, 0, 0,17474/

t & LIST P00L=110101, 3, 0.00014, 5, 0.005348, i 20, 0.105348, 15, 0.505348, 20, 1.505348, 3, 1.506015/

& LIST P00L=110201, 4, 1, 2, 2, 2, 4/

& LIST P00L=110300, 0, 0/

. & LIST P00L=110400, 2, 2, 2, 2/

l l

l l

l 1

NES&L DEPARTMENT CALCULATION SHEET 'c76$cy no.

,, ,,,, o, Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 cCN CONVERSloN:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 148 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 I 8.1.27.11 HS #11 - Lifting Devices (except stainless steel pans) l The characteristics of the Lifting Devices (except stainless steel pans) are as determined in Calculation N-4080-005 (Reference 6.1.i, pages 42 through 44) for Heat Sink 10. This heat l sink description represents a refinement of the characteristics of the Lifting Devices first determined in Calculation N-4080-002 (Reference 6.1.g, pages 156 through 158) for Heat l Sink 11.

Due to heat sink symmetry, only one-half of the heat sink is modeled. The modeled surface area is the total heat sink surface area, equal to twice the actual surface area of one side of the heat sink. The modeled thickness of the center carbon steel ponion is one-half of the

! actual thickness of the center caIbon steel portion of the heat sink. And, the modeled outside boundary is the adiabatic (insulated) condition existing at the midplane of the symmetrical heat sink.

( Heat Sink #11 describes the Lifting Devices (except stainless steel pans) as modeled:

I l

l Geometry Slab l Surface Area 57286 ft2 l Organic Paint (material 4) thickness-Left 0.00125 ft (= 0.015 in)

Boundary Carbon Steel (material 1) thickness-Right 0.041667 ft Boundary l

I.cft Boundary condition Exposed to containment atmosphere Right Boundary condition Insulated, no heat transfer across the heat sink centerline Because there is no heat transfer across the right boundary, the bulk temperature contml for the right boundary condition is not used by the COPAT1'A Code. Therefore, in this analysis the bulk temperature control for the right boundary condition is modeled as the containment

, vapor temperature for convective heat transfer or the saturation temperature at the l containment steam panial pressure for condensing heat transfer (i.e., Option 2 for Item 5 of Card Series IXX400). This differs from the modeling of Calculation N-4080-002, which employed Option 0 for Item 5 of Card Series 1XX400. Since the bulk temperature control for the right boundary condition has no meanmg for this Heat Sink, the decision to model Item 5 with Option 2 rather than Option 0 has the beneficial consequence of allowing the use of any positive value to be modeled as the variable TCONT in Item 7 of Card Series 2.

i

NES&L DEPARTMENT CALCULATION SHEET 'cc" " d PRELIM. CCN No. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CoNVERSloN:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 149 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 i

The Card Series set defining Heat Sink 11 is entered in the input data fue as:

• HS #11 - LIFTING DEVICES (EXCEPT STAINLESS STEEL PARTS)

& LIST P00L=111001,17, 2, 0, 0, 0, 0, 57286/

& LIST P00L=111101, 6, 0.00125, 10, 0.042917/

& LIST P00L=111201, 4, 1/

& LIST P00Ls111300, 0, 0/

& LIST P00L=111400, 2, 2, 0, 2/

i l

l l

[

I

NES&L DEPARTMENT CALCULATION SHEET 'ccM"os PRELIM. CCW NO. PAG 2_,_ OF _

Project or DCP/MMP__ SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 150 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 E s

l l 8.1.27.12 HS #12 - Miscellaneous Carbon Steel (with thickness greater than 2.50 in) l The characteristics of the Miscellaneous Carbon Steel (with thickness greater than 2.50 in) are as determined in Calculation N-4080-005 (Reference 6.1.i, pages 44 through 47) for Heat i Sink 11. This heat sink description represents a refinement of the characteristics of the  !

l Miscellaneous Carbon Steel first determined in Calculation N-4080-002 (Reference 6.1.g, pages 58 through 161) for Heat Sink 12.

Due to heat sink symmetry, only one-half of the heat sink is modeled. The modeled surface area is the total heat sink surface area, equal to twice the actual surface area of one side of the heat sink. The modeled thickness of the center carbon steel ponion is one-half of the actual thickness of the center carbon steel ponion of the heat sink. And, the modeled outside boundary is the adiabatic (insulated) condition existing at the midplane of the symmetrical heat sink.

l Heat Sink #12 describes the Miscellaneous Carbon Steel (with thickness greater than 2.50 in) as modeled:

Geometry Slab Surface Area 516 ft2 Organic Paint (material 4) thickness-Left 0.0005 ft (= 0.006 in)

Boundary Carbon Steel (material 1) thickness-Right 0.310349 ft Boundary Left Boundary condition Exposed to containment atmosphere Right Boundary condition Insulated, no heat transfer across  ;

, the heat sink centerline l

l Calculation N-4080-005 (page 44) calculates a Miscellaneous Carbon Steel surface area of 516 square feet. However, due to an apparent transcription error, a surface area of 596 i j square feet was modeled in the Calculation N-4080-005 COPATTA Code input files. This i i calculation will model the calculated area of 516 square feet.

I Calculation N-4080-005 (page 45) calculates a right boundary coordinate of 0.310849 feet for the Carbon Steel Region. However, for unknown reasons, a right boundary coordinate of 0.34414 feet was modeled in the Calculation N-4080-005 COPATTA Code input files. This calculation will model the calculated right boundary coordinate of 0.310849 feet for the Carbon Steel Region.

NES&L DEPARTMENT CALCULATION SHEET 'cc" " '

PRELIM. CCN NO. PA G E__ OF_,

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 151 1

REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

1 5 l

l Because there is no heat transfer across the right boundary, the bulk temperature control for the right boundary condition is not used by the COPATTA Code. Therefore, in this analysis the bulk temperature control for the right boundary condition is modeled as the containment vapor temperature for convective heat transfer or the saturation temperature at the l

contamment steam partial pressure for condensing heat transfer (i.e., Option 2 for Item 5 of Card Series 1XX400). This differs from the modeling of Calculations N-4080-002 and N-4080-005, which employed Option 0 for Item 5 of Card Series 1XX400. Since the bulk temperature control for the right boundary condition has no meaning for this Heat Sink, the l decision to model Item 5 with Option 2 rather than Option 0 has the beneficial consequence of allowing the use of any positive value to be modeled as the variable TCONT in Item 7 of Card Series 2.

The Card Series set defining Heat Sink 12 is entered in the input data file as:

• HS #12 - MISCELLANEOUS CARBON STEEL - THICKNESS > 2.50 INCHES

& LIST P00L=112001, 64, 4, 0, 0, 0, 0, 516/

& LIST P00L=112101, 6, 0.0005, 17, 0.084, 15, 0.20, 25, 0.310849/

& LIST P00L=112201, 4, 1, 1, 1/

& LIST P00L=112300, 0, 0/

& LIST P00L=112400, 2, 2, 0, 2/

NES&L DEPARTMENT CALCULATION SHEET l

' pygc, eo. ,,c,__ o,___

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CoNVERSloN:

CCN No. CCN -

l Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 152 l

REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

8.1.27.13 HS #13 - Miscellaneous Carbon Steel (with thickness between 1.00 in and 2.50 in) l The characteristics of the Miscellaneous Carbon Steel (with thickness between 1.00 in and i

2.50 in) are a refinement of those detemlined in Calculation N-4080-005 (Reference 6.1.i, l pages 47 through 50) for Heat Sink 12 which in turn repmsent a refinement of the l

characteristics of the Miscellaneous Carbon Steel first determined in Calculation N-4080-002 (Reference 6.1.g, pages 161 through 165) for Heat Sink 13.

An ermr was made in Calculation N-4080-005 for Heat Sink 12 on page 48. There are four Safety Injections Tanks and the area of only one tank was modeled by Calculation N-4080-005. Correcting this error will change the surface area for Heat Sink 13 in this analysis to 12042 square feet and the effective carbon steel thickness to 0.1692 feet.

Due to heat sink symmetry, only one-half of the heat sink is modeled. The modeled surface i area is the total heat sink surface area, equal to twice the actual surface area of one side of l

the heat sink. The modeled thickness of the center carbon steel portion is one-half of the actual thickness of the center carbon steel portion of the heat sink. And, the modeled outside boundary is the adiabatic (insulated) condition existing at the midplane of the symmetrical heat sink.

l Heat Sink #13 describes the Miscellaneous Carbon Steel (with thickness between 1.00 in and 2.50 in) as modeled:

Geometry Slab Surface Area 12042 ft2 l

Organic Paint (material 4) thickness-Left 0.00063 ft Boundary Carbon Steel (material 1) thickness-Right 0.16924 ft Boundary Left Boundary condition Exposed to containment atmosphere l Right Boundary condition Insulated, no heat transfer across the heat sink centerline Because there is no heat transfer across the right boundary, the bulk temperature control for the right boundary condition is not used by the COPATTA Code. Therefore, in this analysis

the bulk temperature control for the right boundary condition is modeled as the containment vapor temperature for convective heat transfer or the saturation temperature at the containment steam partial pressure for condensing heat transfer (i.e., Option 2 for Item 5 of

NES&L DEPARTMENT CALCULATION SHEET '

'cc" ". CCN NO.

PRELIM PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desic, Basis LOCA Sheet No. 153 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R O R. Nakano 01/18/94 J. EL'ott 01/20/94 E v

i 4 I i l 4 l j Card Series 1XX400). This differs from the modeling of Calculations N-4080-002 and N-4080-005, which employed Option 0 forItem 5 of Card Series 1XX400. Since the bulk temperature control for the right boundary condition has no meaning for this Heat Sink, the decision to modelItem 5 with Option 2 rather than Option 0 has the beneficial consequence i of allowing the use of any positive value to be modeled as the variable TCONT in Item 7 of j Card Series 2.

1 4

The Card Series set defining Heat Sink 13 is entered in the input data file as:

• HS #13 - MISCELLANEOUS CARBON STEEL: 1.00"< THICKNESS <2.50"

& LIST P00L=113001, 32, 2, 0, 0, 0, 0, 12042/

& LIST P00L=113101, 6, 0.00063, 25, 0.16967/

& LIST P00L=113201, 4, 1/

& LIST P00L=113300, 0, 0/ l

& LIST P00L=113400, 2, 2, 0, 2/

q NES&L DEPARTMENT j CALCULATION SHEET '" o '

PRELIM. CCN Wo. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 cCN CONVERSION:

CcN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 154 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

4 8.1.27.14 HS #14 - Miscellaneous Carbon Steel (with thickness between 0.50 in and 1.00 in)

The characteristics of the Miscellaneous Carbon Steel (with thickness between 0.50 in and i

1.00 in) are as determined in Calculation N-4080-005 (Reference 6.1.i, pages 50 through 54)

for Heat Sink 13. This heat sink description represents a refinement of the characteristics of the Miscellaneous Carbon Steel first determined in Calculation N-4080-002 (Reference 6.1.g, pages 165 through 169) for Heat Sink 14.

Due to heat sink symmetry, only one-half of the heat sink is modeled. The modeled surface area is the total heat sink surface area, equal to twice the actual surface area of one side of the heat sink. The modeled thickness of the center carbon steel portion is one-half of the actual thickness of the center carbon steel portion of the heat sink. And, the modeled outside boundary is the adiabatic (insulated) condition existing at the midplane of the symmetrical heat sink.

Heat Sink #14 describes the Miscellaneous Carbon Steel (with thickness between 0.50 in and 1.00 in) as modeled:

Geometry Slab Surface Area 64693 ft2 Organic Paint (material 4) thickness-Left 0.000674 ft Boundary Carbon Steel (material 1) thickness-Right 0.037933 ft Boundary Left Boundary condition Expo _ sed to containment atmosphere Right Boundary condition Insulated, no heat transfer across the heat sink centerline Because there is no heat transfer acruss the right boundary, the bulk temperature control for the right boundary condition is not used by the COPATTA Code. Therefore, in this analysis the bulk temperature control for the right boundary condition is modeled as the containment vapor temperature for convective heat transfer or the saturation temperature at the containment steam partial pressure for condensing heat tmnsfer (i.e., Option 2 for Item 5 of Card Series IXX400). This differs from the modeling of Calculations N-4080-002 and N-4080-005, which employed Option 0 for Item 5 of Card Series IXX400. Since the bulk temperature control for the right boundary condition has no meaning for this Heat Sink, the decision to model Item 5 with Option 2 rather than Option 0 has the beneficial consequence

NES&L DEPARTMENT CALCULATION SHEET 'cc"o '

PRELIM. CCN NO. PAGE _ OF _

Project or DCP/MMP_ SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 155 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 E 5

of allowing the use of any positive value to be modeled as the variable TCONT in Item 7 of Card Series 2.

The Card Series set defining Heat Sink 14 is entered in the input data file as:

• HS #14 - MISCELLANEOUS CARBON STEEL: 0.50"< THICKNESS <1.00"

& LIST P00L=114001, 19, 2, 0, 0, 0, 0, 64693/

& LIST P00L=114101, 5, 0.000674, 13, 0.038607/

& LIST P00L=114201, 4, 1/

& LIST P00L=114300, 0, 0/

& LIST P00L=114400, 2, 2, 0, 2/ 3

{

i 1

5 l

NES&L DEPARTMENT CALCULATION SHEET 'cc" "os PRELIM. CCN NO. PAGE oF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 156 l

REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

l V 8.1.27.15 HS #15 - Miscellaneous Carbon Steel (with thickness less than 0.50 in) l The characteristics of the Miscellaneous Carbon Steel (with thickness less than 0.50 in) are as determined in Calculation N-4080-005 (Reference 6.1.i, pages 54 through 59) for Heat Sink 14. This heat sink description represents a refinement of the characteristics of the Miscellaneous Carbon Steel first determined in Calculation N-4080-002 (Reference 6.1.g, pages 169 through 173) for Heat Sink 15.

Due to heat sink symmetry, only one-half of the heat sink is modeled. The modeled surface area is the total heat sink surface area, equal to twice the actual surface area of one side of the heat sink. The modeled thickness of the center carbon steel portion is one-half of the actual thickness of the center carbon steel portion of the heat sink. And, the modeled outside boundary is the adiabatic (insulated) condition existing at the midplane of the symmetrical heat sink.

Heat Sink #15 describes the Miscellaneous Carbon Steel (with thickness less than 0.50 in as modeled:

Geometry Slab Surface Area 98913.6 ft 2 i

Organic Paint (material 4) thickness-Left 0.000606 ft Boundary Carbon Steel (material 1) thickness-Right 0.012227 ft Boundary Left Boundary condition Exposed to containment atmosphere Right Boundary condition Insulated, no heat transfer across the heat sink centerline Because there is no heat transfer across the right boundary, the bulk temperature control for the right boundary condition is not used by the COPATTA Code. Therefore, in this analysis the bulk tempenture control for the right boundary condition is modeled as the containment

{ vapor temperature for convective heat transfer or the saturation tempenture at the containment steam partial pressure for condensing heat transfer (i.e., Option 2 for Item 5 of Cani Series 1XX400). This differs from the modeling of Calculations N-4080-002 and N-4080-005, which employed Option 0 for Item 5 of Card Series IXX400. Since the bulk temperature control for the right boundary condition has no meaning for this Heat Sink, the decision to modelItem 5 with Option 2 mther than Option 0 has the beneficial consequence

NES&L DEPARTMENT CALCULATION SHEET 'cc" "o' PRELIM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

f CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 157 REV ORIGINATOR DATE lRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 h 4

I of allowing the use of any positive value to be modeled as the variable TCONT in Item 7 of l Card Series 2.

The Card Series set derming Heat Sink 15 is entered in the input data file as:

• HS #15 - MISCELLANEOUS CARBON STEEL: THICKNESS (0.5" l & LIST P00L=115001,17, 2, 0, 0, 0, 0, 98913.6/

l & LIST P00L=115101, 6, 0.000606, 10, 0.012833/

l & LIST P00Ls115201, 4, 1/

& LIST P00L=115300, 0, 0/

& LIST P00L=115400, 2, 2, 0, 2/

l l

l l

i i

(

I

(

l

r l NES&L DEPARTMENT CALCULATION SHEET 'cc" " >

PRELIM. CCN NO. PAGE _ OF_,_

Project or DCP/MMP_ SONGS Units 2 & 3 Calc. No.X-4080-026 ccN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 158 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 "

, 8 8.1.27.16 HS #16 - Electrical Equipment The characteristics of the Electrical Equipment are as determined in Calculation N-4080-005 (Reference 6.1.i, pages 59 through 61) for Heat Sink 15. This heat sink description represents a refinement of the characteristics of the Electrical Steel first determined in Calculation N-4080-002 (Reference 6.1.g, pages 174 through 176) for Heat Sink 16.

Calculation N-4080-005 (page 61) recommends use of a 37644 square foot surface area. The modeled surface area of 37644.5 square feet possesses the extra significant digit found in an interim calculation step as shown in Calculation N-4080-005 (page 60).

Heat Sink #16 describes the Electrical Equipment as modeled:

Geometry Slab l

Surface Area 37644.5 ft2 Carbon Steel (material 1) thickness-Ixft and 0.0054 ft Right boundaries j Ixft Boundary condition Exposed to contamment atmosphere l Right Boundary condition Insulated, no heat transfer to inside l of electrical equipment Because there is no heat transfer across the right boundary, the bulk temperature control for the right boundary condition is not used by the COPATTA Code. Therefore, in this analysis the bulk temperature control for the right boundary condition is modeled as the contamment l vapor temperature for convective heat transfer or the saturation temperature at the containment steam partial pressure for condensing heat transfer (i.e., Option 2 for Item 5 of Card Series 1XX400). This differs from the modeling of Calculations N-4080-002 and N-4080-005, which employed Option 0 for Item 5 of Card Series 1XX400. Since the bulk temperature control for the right boundary condition has no meaning for this Heat Sink, the decision to model Item 5 with Option 2 rather than Option 0 has the beneficial consequence of allowing the use of any positive value to be modeled as the variable TCONT in Item 7 of Card Series 2.

1 NES&L DEPARTMENT CALCULATION SHEET 'cc" "

PRELIM. CCN NO. PAGE _ OF _

l Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T AnalvsiLfor Desian Basis LOCA Sheet Nc. 159 i

REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE BRE DATE R E

0 R. N;kenn 01/18/94 J. Elliott 01/20/94 S

The Card Series set defining Heat Sink 16 is entered in the input data file as:

• HS #16 - ELECTRICAL EQUIPMENT

& LIST P00L=116001, 8, 1, 0, 0, 0, 0, 37644.5/

& LIST P00L=116101, 7, 0.0054/

& LIST P00L=116201, 1/

& LIST P00L=116300, 0, 0/

& LIST P00L=116400, 2, 2, 0, 2/

l l

l  !

1 1

i I l

NES&L DEPARTMENT CALCULATION SHEET ' ,c"gc, l; no. ,,,,_ o,_

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN --

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 160 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 4

8.1.27.17 HS #17 - Miscellaneous Stainless Steel The characteristics of the Miscellaneous Stainless Steel are as detennined in Calculation N-4080-005 (Reference 6.1.i, pages 62 through 65) for Heat Sink 16. This heat sink description represents a refinement of the characteristics of the Miscellaneous Stainless Steel as first determined in Calculation N-4080-002 (Reference 6.1.g, pages 176 through 179) for Heat Sink 17.

Due to heat sink symmetry, only one-half of the heat sink is modeled. The modeled surface an:a is the total heat sink surface area, equal to twice the actual surface area of one side of the heat sink. The modeled thickness of the center stainless steel portion is one-half of the actual thickness of the center stainless steel portion of the heat sink. And, the modeled outside boundary is the adiabatic (insulated) condition existing at the midplane of the symmetrical heat sink.

Heat Sink #17 describes the Miscellaneous Stainless Steel as modeled:

Geometry Slab Surface Area 24048 ft2 Stainless Steel (material 3) thickness-Left and 0.01747 ft Right boundaries left Boundary condition Exposed to containment atmosphere Right Boundary condition Insulated, no heat transfer across the heat sink centerline Because there is no heat transfer across the right boundary, the bulk temperature control for the right boundary condition is not used by the COPATTA Code. Therefore, in this analysis the bulk temperature control for the right boundary condition is modeled as the contamment vapor temperature for convective heat transfer or the saturation temperature at the containment steam partial pressure for condensing heat transfer (i.e., Option 2 for Item 5 of Card Series IXX400). This differs from the modeling of Calculations N-4080-002 and N-4080-005, which employed Option 0 for Item 5 of Card Series IXX400. Since the bulk temperature control for the right boundary condition has no meaning for this Heat Sink, the decision to model Item 5 with Option 2 rather than Option 0 has the beneficial consequence of allowing the use of any positive value to be modeled as the variable TCONT in Item 7 of Card Series 2.

l I

NES&L DEPARTMENT CALCULATION SHEET 'oc" " '

PRELIM. CCN NO. PAGE__OF _

4 1

Proiset or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 161 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE R ;

O R. Nakano 01/18/94 J. Elliott 01/20/94 '

f 5 1 The Card Series set defining Heat Sink 17 is entered in the input data file as:

• HS #17 - MISCELLANEOUS STAINLESS STEEL

& LIST P00L=117001, 16, 1, 0, 0, 0, 0, 24048/

& LIST P00L=117101, 15, 0.01747/

& LIST P00L=117201, 3/

& LIST P00L=117300, 0, 0/

& LIST P00L=117400, 2, 2, 0, 2/

i l

l l

I 1

l l

NES&L DEPARTMENT CALCULATION SHEET 'cc" "o '

PRELIM. CCN NO. PAGE OF l Proj:ct or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 cCN CONVERSION:

I CCN NO. CCN -

l Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 162 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE dRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 E 5

i 8.1.27.18 HS #18 - Unlined Refueling Canal Walls (below El. 63'6")

The characteristics of the Unlined Refueling Canal Walls (below plant elevation 63'6") are as determined in Calculation N-4080-002 (Reference 6.1.g, pages 180 through 182) for Heat Sink 18.

Due to heat sink symmetry, only one-half of the heat sink is modeled. The modeled surface area is the total heat sink surface area, equal to twice the actual surface area of one side of the heat sink. The modeled thickness of the center concrete portion is one-half of the actual thickness of the center concrete portion of the heat sink. And, the modeled outside boundary is the adiabatic (insulated) condition existing at the midplane of the symmetrical heat sink.

Heat Sink #18 describes the Unlined Refueling Canal Walls (below El. 63'6") as modeled:

Geometry Slab Surface Ama 3700 ft2 Organic Paint (material 4) thickness-Left 0.00192 ft (= 0.023 in)

Boundary Concrete (material 2) thickness-Right Boundary 2.0 ft I2ft Boundary condition Exposed to containment atmosphere Right Boundary condition Insulated, no heat transfer across the heat sink centerline bue to an addition error, Calculation N-4080-002 (page 181) incorrectly modeled the right boundary coordinate of the Concrete Region at 2.00 feet. The determination of the right boundary coordinate of the Concrete region neglected to add the thickness of the Organic Paint Region. In this analysis the right boundaiy coordinate of the Concrete Region will be modeled at the correct position of 2.00192 feet:

Right Boundary Coordinate of Concrete Region = 2.0 ft + 0.00192 ft

= 2.00192 feet Because there is no heat transfer across the right boundary, the bulk temperature control for j the right boundary condition is not used by the COPATI'A Code. Therefore, in this analysis

! the bulk temperature control for the right boundary condition is modeled as the contamment l vapor temperature for convective heat transfer or the saturation temperature at the containment steam partial pressure for condensing heat transfer (i.e., Option 2 for Item 5 of Card Series IXX400). This differs from the modeling of Calculation N-4080-002, which

NES&L DEPARTMENT CALCULATION SHEET 'cc7;gc, yo.

,a, ,,c, o, Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 163 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 employed Option 0 for Item 5 of Card Series 1XX400. Since the bulk temperature control for the right boundary condition has no meaning for this Heat Sink, the decision to model Item 5 with Option 2 rather than Option 0 has the beneficial consequence of allowing the use of any positive value to be modeled as the variable TCONT in Item 7 of Card Series 2.

The Card Series set defining Heat Sink 18 is entered in the input data file as:

• HS #18 - UNLIKED REFUELING CANAL WALLS BELOW El. 63'6"

& LIST P00L=118001, 48, 4, 0, 0, 0, 0, 3700/

& LIST P00L=118101, 5, 0.00192, 7, 0.02292, 15, 0.40192, 20, 2.00192/

4 LIST Po0L=118201, 4, 2, 2, 2/

f. LIST P00L=118300, 0, 0/

& LIST POOL =118400, 2, 2, 0, 2/

5 l

l - _ _ _ -

NES&L DEPARTMENT CALCULATION SHEET ',c",[s%cieyo.

l,t ,,, ,__ o,-

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN NO. CCN -

l Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 164 4

REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R l 0 R. Nakano 01/18/94 J. Elliott 01/20/94 h

4

, 8.1.27.19 HS #19 - Reactor Building Cylinder #3 (the Containment Section with Embedded 1

Stiffeners between El. 20'6" and 112'0")

The characteristics of the Reactor Building Cylinder #3 (the Containment Section with Embedded Stiffeners between plant elevations 29'6" and 112'0") are as determined in Calculation N-4080-002 (Reference 6.1.g, pages 183 through 189) for Heat Sink 19, except for the thickness of the Containment Liner / Concrete air gap interface, and except for the thickness of the concrete layer.

J Due to an addition error, Calculation N-4080-002 (page 188) improperly modeled the concrete layer as 3.56524 feet thick. In this analysis the concrete layer will be modeled as 4.21108 feet, corresponding to the average thickness that was actually determined in '

l Calculation N-4080-002 (page 186). And, as discussed in Design Input Item 4.13.a, the

, effective thickness of the interface (air gap) will be 0.00035 feet. With these changes, Heat Sink #19 describes the Reactor Building Cylinder 3 as modeled:

Geometry Slab Surface Area 1590.68 ft2

, Organic Paint (material 4) thickness-Left 0.00075 ft (= 0.009 in) i Boundary Carbon Steel (material 1) Liner thickness 0.66667 ft (= 8 in)

! Air Gap Interface (material 5) thickness 0.00035 ft d

Concrete (material 2) thickness-Right Boundary 4.21108 ft l Left Boundary condition Exposed to containment atmosphere l Right Boundary condition Exposed to outside environment I

The effect of the changes in the air gap thickness is reflected in Card Series 119101. This l Card Series defines the location of the right boundary and nodalization of each region. The air gap is the third region of Heat Sink 19. The increase in the modeled air gap thickness i from 0.00017 feet to 0.00035 feet requires that the modeled location of the Region 3 right boundary be increased by 0.00018 feet. To maintain the correct thickness of each Region that follows the air gap region necessitates that the modeled locations of the right bounAries of these subsequent regions be increased by the same 0.00018 feet.

Due to an addition error, Calculation N-4080-002 (page 188) incorrectly modeled the right boundary coordinate of the Concrete Region at 4.23283 feet. The determination of the right I

. _ -= . - .. - . . . . -_

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Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 165 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

4 l

boundary coordinate of the Concrete region is based on adding the thickness of the Concrete l Region to the thicknesses of the Organic Paint, Carbon Steel and Air Gap Interface regions.

The original calculations considered a Carbon Steel thickness of 0.02083 feet rather than the correct thickness of 0.66667 feet. Correcting this ermr, and adjusting for the change in the ,

Air Gap Interface Region thickness, allows for the calculation of a 7th Region right boundary coordinate of 4.87885 feet:

Right Boundary Coordinate = 0.00075 ft + 0.66667 ft + 0.00035 ft + 4.21108 ft of Concete Region = 4.87885 feet

]

l The changes from the right boundary locations detennined in Calculation N-4080-002 are:

1st Region: no change in the right boundary location 2nd Region: no change in the right boundary location 3rd Region: right boundary shifted from 0.66759 to 0.66777 feet 4th Region: right boundary shified from 0.70926 to 0.70944 feet l 5th Region: right boundary shifted from 0.7926 to 0.79278 feet

. 6th Region: right boundary shifted from 1.4426 to 1.44278 feet

7th Region

right boundary shifted from 4.23283 to 4.87885 feet i

The Card Series set defining Heat Sink 19 is entered in the input data file as:

1

• HS #19 - REACTOR BLDG CYLINDER F3: SECTIONS WITH STIFFENERS

& LIST P00Ls119001, 100, 7, 0, 0, 0, 0, 1590.68/

4

& LIST P00L=119101, 5, 0.00075, 20, 0.66742, 3, 0.66777, 15, 0.70944, 20, 0.79278, 16, 1.44278, 20, 4.87885/

i & LIST P00L=119201, 4, 1, 5, 2, 2, 2, 2/

& LIST P00L=119300, 0, 0/ -

& LIST P00L=119400, 2, 2, 1, 1/

"r l

NES&L DEPARTMENT CALCULATION SHEET ' '" s%CM MO.

!seu PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

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Subject Containment PTT Analvsis for Desian Basis LOCA Sheet No. 166 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 5

8.1.27.20 HS #20 - Vent Tunnels The characteristics of the Vent Tunnels are as determined in Calculation N-4080-002 l (Reference 6.1.g, pages 190 through 192) for Heat Sink 20. I Heat Sink #20 describes the Vent Tunnels as modeled:

1 Geometry Slab Surface Area 2827 ft2 l Organic Paint (material 4) thickness-Left 0.0005 ft (= 0.006 in) l Boundary Carbon Steel (material 1) thickness-Right 0.03125 ft (= 0.375 in)

Boundary Left Boundary condition Exposed to containment atmosphere Right Boundary condition Insulated (approximating an infinitely thick tunnel wall)

Because there is no heat transfer across the right boundary, the bulk temperature control for the right boundary condition is not used by the COPATTA Code. Therefore, in this analysis the bulk tempemture control for the right boundary condition is modeled as the containment vapor temperature for convective heat transfer or the saturation temperature at the containment steam partial pressure for condensing heat transfer (i.e., Option 2 for Item 5 of Card Series 1XX400). This differs from the modeling of Calculation N-4080-002, which employed Option 0 for Item 5 of Card Series IXX400. Since the bulk temperature control for the right boundary condition has no meaning for this Heat Sink, the decision to model Item 5 with Option 2 rather than Option 0 has the beneficial consequence of allowing the use of any positive value to be modeled as the variable TCONT in Item 7 of Card Series 2.

The Card Series set defining Heat Sink 20 is entered in the input data file as:

• HS #20 VENT TUNNELS

& LIST P00L=120001, 23, 2, 0, 0, 0, 0, 2827/

& LIST P00Ls120101, 10, 0.0005, 12, 0.03175/

& LIST P00L=120201, 4, 1/

& LIST P00L=120300, 0, 0/

& LIST P00L=120400, 2, 2, 0, 2/

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Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 167 REV ORIGINATOR DATE lRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

l 5

8.1.28 CARD SERIES 410001: Table 15 Card Series 410001 is a table that is used to describe the material properties in the heat sink l calculations. The Card Series 410001 table includes the following data entered in columnar form:

1. thermal conductivity (BTU /hr-ft- F)

2. volumetric heat capacity (BTU /ft3 - F)

I & LIST P00L=410001, 1

25, 54, 0.8, 30, i 10, 54, l 0.1, 20, 0.0174, 0.0103/

l The entries in Card Series 410001 define five materials. These materials include:

l

! ITEMS 2 and 3: Material 1 - Carbon Steel Material 1 is defined as Carbon Steel. Per Design Input Item 4.14.a, the thermal conductivity and volumetric heat capacity of Carbon Steel is:

i k = 25 BTU /hr-ft *F pC, = 54 BTU /ft3 - F ITEMS 4 and 5: Material 2 - Concrete Material 2 is defined as Concrete. Per Design Input Item 4.14.b, the thermal conductivity and volumetric heat capacity of Concrete is:

l k = 0.8 BTU /hr-ft *F pC, = 30 BTU /ft3 *F

\

l f

i l

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Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 168 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 ITEMS 6 and 7: Material 3 - Stainless Steel Material 3 is defined as Stainless Steel. Per Design Input Item 4.14.c, the thermal conductivity and volumetric heat capacity of Stainless Steel is:

k = 10 BTU /hr-ft- F pC, = 54 BTU /ft'- F ITEMS 8 and 9: Material 4 - Organic Paint Coating Material 4 is defined as Organic Paint Coating. Per Design Input Item 4.14.d, the thermal conductivity and volumetric heat capacity of Organic Paint Coating is:

k = 0.1 BTU /hr-ft- F pC, = 20 BTU /ft3 *F ITEMS 10 and 11: Material 5 - Air Gap (@ 200 'F)

Material 5 is defined as the Air Gap Interface between the Contaimnent Building walls and the Carbon Steel Liner, at a containment air temperature of 200 *F. Per Design Input Item 4.14.e, the thermal conductivity and volumetric heat capacity of the Air Gap is:

k = 0.0174 BTU /hr-ft- F pC, = 0.0103 BTU /ft'- F ,

j NES&L DEPARTMENT l CALCULATION SHEET l's"J lcn 20. ,,c ,_, c,_

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 169 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 8.1.29 CARD SERIES 420001: Table 16 Card Series 420001 is used to specify arbitrary constant non-condensing heat transfer coefficients to be assumed at any heat sink surface. This table is required if a heat transfer coefficient control of 10 to 15 is specified for Items 2 or 4 in Card Series 1XX400. In this model, heat transfer coefficient controls other than 10 to 15 are specified for Items 2 and 4 in Card Series 1XX400. Therefore, this Card Series is not used.

8.1.30 CARD SERIES 430001: Table 17 Card Series 430001 is used to describe the time-dependent condensing heat transfer coefficients to be assumed at any heat sink surface. This table is required if a heat transfer coefficient control of 5 or 8 is specified for Items 2 or 4 in Card Series 1XX400. In this model, heat transfer coefficient controls other than 5 or 8 are specified for Items 2 and 4 in Card Series IXX400. Therefore, this Card Series is not used.

8.1.31 CARD SERIES 440001: Table 18 Card Series 430001 is used to describe an additional set of time-dependent condensing heat transfer coefficients to be assumed at any heat sink surface. This table is required if a heat transfer coefficient control of 6 is specified for Items 2 or 4 in Card Series 1XX400. In this model, heat transfer coefficient controls other than 6 are specified for Items 2 and 4 in Card Series 1XX400. Therefore, this Card Series is not used.

8.1.32 CARD SERIES 450001: Table 19 Card Series 450001 is used to describe the temperature-dependent non-condensing heat transfer coefficients to be assumed at any heat sink surface. This table is required if a heat transfer coefficient control of 7 is specified for Items 2 or 4 in Card Series 1XX400. In this model, heat transfer coefficient controls other than 7 are specified for Items 2 and 4 in Card Series 1XX400. Therefore, this Card Series is not used.

NES&L DEPARTMENT CALCULATION SHEET 'cca " '

PREUM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

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Subject Containment P/T Analvsis for Desian Basis LOCA

. Sheet No. 170 j REV ORIGINATOR DATE lRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

, 5 l

8.1.33 CARD SERIES 500000 End Card

].

If heat sink data is used, this card must follow the complete set of base case data.

Otherwise it may be omitted. In this calculation, heat sink data is used. The card

contains the following fixed information in Columns 2 through 19

& LIST POOL =500000/

1 b l j

l i

q a

i NES&L DEPARTMENT CALCULATION SHEET 'cc" " '

PREUM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 171 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 8.2 COPA'lTA CODE INPUT l A Copy of the input file for the LOCA is presented in this section.

8.2.1 Input File for LOCA with a Loss of Offsite Power

• LOCA WITH A LOSS OF OFFSITE POWER

& LIST POOL =0,2,1,0,1,0,0,0,0/

& LIST P00L=1, le7, 16.2, 2.305e6, 120, 0.6, 20, 582.945, 1, 18, 0.00, 14.7, 0.50/

& LIST P00L=2, 0, 0,1.68e5, 2934, 0,120, 573.273/

& LIST P00L=3, 0, 0, 0, 0, 0, 1.00e7, 0, 0, 0, 0/

& LIST P00L=4, 1, 6860, 216, 105, 3.0e6, 0, 0, 0, 0, 0, 0, 0, 0/

& LIST P00L=5, 2, 35, 1.0e7, 0, 0, 0, 105/

& LIST P00L=6, 0, 0, 0/

& LEAK NOPENr0/

& LIST POOL =101, 0.0000, 0.0000,

! 5.73273e+02, 0.0000, l 5.7327E+02, 3.2931E+08, 6.0000E+02, 3.2624E+08, 8.0000E+02, 3.0812E+08, 1.0000E+03, 2.9449E+08, 2.0000E+03, 2.2734E+08, 4.0000E+03, 1.7963E+08, 6.0000E+03, 1.5728E+08, 8.0000E+03, 1.4506E+08,

, 1.0000E+04, 1.3706E+08, 1 2.0000E+04, 1.1366E+08, l 4.0000E+04, 8.9771E+07, 6.0000E+04, 7.8463E+07, l

8.0000E+04, 7.2141E+07, 1.0000E+05, 6.7894E+07, 2.0000E+05, 5.4991E+07, l 4.0000E+05, 4.1412E+07, 6.0000E+05, 3.4734E+07, 8.0000E+05, 3.0911E+07, 1.0000E+06, 2.8363E+07, l 2.0000E+06, 2.1296E+07, l 4.0000E+06, 1.4713E+07, 6.0000E+06, 1.1629E+07, 1.0000E+07, 8.5482E+06/

& LIST P00L=201, 0, 2.5836e7,

, 211.10, 2.5836e7, i

211.10, 0, 573.273, 0, 573.273, 1.2635e7, 8.64e+04, 1.2635e7, 8.64e+04, 0, 1.00e+07, 0/

& LIST P00L=301, 0, 0, 0, 0.025, 2.7068e+08, 5.4632e+02,

0.075, 2.6757e+08, 5.4681e+02, 0.175, 2.8058e+08, 5.4848e+02, 0.20, 3.3993e+08, 5.4933e+02, O.225, 3.3506e+08, 5.4967e+02, 0.25, 3.3534e+08, 5.5012e+02,

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Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 172 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 4

0.40, 3.1384e+08, 5.5312e+02, 0.75, 2.9337e+08, 5.6162e+02, 0.85, 2.7364e+08, 5.6237e+02, 1.0, 2.4650e+08, 5.6329e+02, 1.2, 2.2548e+08, 5.6429e+02, 2.0, 2.0756e+08, 5.6709e+02, 3.0, 1.8229e+08, 5.7573e+02, 4.0, 1.5767e+08, 5.9697e+02, 5.0, 1.3255e+08, 6.3045e+02, 6.0, 1.1328e+08, 6.5884e+02, I 8.0, 9.4860e+07, 6.7161 e+02, 10.0, 7.8800e+07, 6.8765e+02,

] 12.0, 5.4454e+07, 7.6610e+02, 13.5, 3.566e+07, 8.640e+02, 14.5, 2.888e+07, 7.502e+02, 15.0, 2.627e+07, 7.199e+02,

, 16.0, 1.768e+07, 6.699e+02, 17.1, 1.119e+07, 6.556e+02, 17.2, 1.140e+07, 6.386e+02,

, 17.3, 9.065e+06, 6.213e+02, 18.5, 6.152e+06, 6.439e+02,

'19.3, 8.806e+06, 4.605e+02, 19.8, 7.146e+06, 4.881e+02, 20.6, 4.172e+06, 5.348e+02, i 20.8, 1.016e+07, 3.317e+02, 1 21.4, 3.629e+06, 3.700e+02, 21.6, 1.77e+06, 3.66e+02, 21.8, 3.0e+05, 3.4e+02, t 22.0, 0.00, 0.00, 22.0, 0.00, 0.00, 22.25, 5.8302e+05, 1.3000e+03, 23.25, 9.2236e+05, 1.3000e+03, 24.25, 1.5463e+06, 1.3000e+03, 25.25, 2.0444e+06, 1.3000e+03, 26.25, 2.4255e+06, 1.3000e+03, 27.75, 2.8736e+06, 1.3000e+03,

, 28.00, 1.8443e+06, 1.3000e+03, 36.00, 1.8201e+06, 1.3000e+03, 44.50, 1.7920e+06, 1.3000e+03, 44.75, 2.7987e+06, 1.3000e+03, 1

75.00, 2.6467e+06, 1.3000e+03, 100.00, 2.5190e+06, 1.3000e+03, 125.00, 2.3921e+06, 1.3000e+03, 150.00, 2.2677e+06, 1.3000e+03, 175.00, 2.1401e+06, 1.3000e+03, 200.00, 2.0116e+06, 1.3000e+03, 211.10, 1.9553e+06, 1,3000e+03,

211.101, 2.2478e+06, 1.1865e+03, a

211.336, 2.2378e+06, 1.1865e+03, 211.573, 2.2279e+06, 1.1865e+03, 211.812, 2.2179e+06, 1.1865e+03, 212.052, 2.2080e+06, 1.1865e+03, 213.026, 2.1615e+06, 1.1877e+03, 215.073, 2.0469e+06, 1.1878e+03, 216.989, 1.9466e+06, 1.1879e+03, 219.039, 1.8464e+06, 1.1880e+03, 221.233, 1.7463e+06, 1.1881e+03, 222.894, 1.6748e+06, 1.1883e+03, 225.021, 1.5891e+06, 1.1884e+03, 226.920, 1.5179e+06, 1.1885e+03, 228.953, 1.4468e+06, 1.1887e+03, 231.139, 1.3760e+06, 1.1889e+03,

NES&L DEPARTMENT CALCULATION SHEET '

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PREUM CCN WO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN No. CCN -

Subject _C_ontainment P/T Analvsis for Desian Basis LOCA Sheet No. 173 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE R O R. Nakano 01/18/94 J. Elliott 01/20/94 E y

5 l

l 233.014, 1.3194e+06, 1.1891e+03, 235.017, 1.2631e+06, 1.1892e+03, 237.167, 1.2070e+06, 1.1894e+03, 238.890, 1.1647e+06, 1.1900e+03, 240.719, 1.1232e+06, 1.1898e+03, 242.668, 1.0816e+06, 1.1900e+03, 245.484, 1.0265e+06, 1.1902e+03, 246.897, 9.9907e+05, 1.1904e+03, 249.420, 9.5821e+05, 1.1906e+03, 251.151, 9.3110e+05, 1.1908e+03, 254.936, 8.7746e+05, 1.1911e+03, 259.251, 8.2462e+05, 1.1914e+03, 262.929, 7.8563e+05, 1.1917e+03, 267.086, 7.4729e+05, 1.1919e+03, 271.855, 7.0974e+05, 1.1921e+03, 281.634, 6.4948e+05, 1.1925e+03, 292.060, 6.0412e+05, 1.1925e+03, 302.415, 5.7236e+05, 1.1923e+03, 311.215, 5.5256e+05, 1.1919e+03, 321.094, 5.3597e+05, 1.1820e+03, 331.360, 5.2312e+05, 1.1820e+03, 340.999, 5.1401e+05, 1.1819e+03, 351.095, 5.0663e+05, 1.1819e+03, 361.352, 5.0080e+05, 1.1819e+03, 371.311, 4.9637e+05, 1.1818e+03, 391.750, 4.8974e+05, 1.1818e+03, 411.491, 4.8546e+05, 1.1819e+03, 432.076, 4.8233e+05, 1.1593e+03, 452.069, 4.8013e+05, 1.1817e+03, 471.774, 4.7851e+05, 1.1816e+03, 524.047, 4.7578e+05, 1.1816e+03, 573.273, 4.7426e+05, 1.1816e+03, 573.273, 0.00, 0.00, 1.00e+07, 0.00, 0.00/

& LIST P00L=401, 0, 0, 0, 211.1, 0, 0, 573.273, 0, 0, 573.273, 1, 1, 8.64e+04, 1, 1, 8.64e+04, 1, 0, 1.00e+07, 1, 0/

& LIST P00L=501, 0.0, 0, 0, 1.0e+07, 0, 0/

LLIST P00L=601, 0.00, 0.00, 0.00, 28.00, 0.00, 0.00, 28.00, 4.823e+06, 5.362e+08, 211.101, 8.73e+05, 7.7e+07, 211.336, 8.83e+05, 7.8e+07, 211.573, 8.93e+05, 7.9e+07, 211.812, 9.03e+05, 7.9e+07, 212.052, 9.13e+05, 8.0e+07, 213.026, 9.60e+05, 8.4e+07, 215.073, 1.07e+06, 9.5e+07, 216.989, 1.17e+06, 1.0e+08, 219.039, 1.27e+06, 1.1e+08, i 221.233, 1.37e+06, 1.2e+08, 222.894, 1.45e+06, 1.3e+08, 225.021, 1.53e+06, 1.3e+08, 226.920, 1.60e+06, 1.4e+08,

NES&L DEPARTMENT CALCULATION SHEET PRELIM d

'cc" ". CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-OL CcN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 174 n

REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 I

228.953, 1.67e+06, 1.5e+08, 231.139, 1.75e+06, 1.5 e+08, 233.014, 1.80e+06, 1.6e+08, 235.017, 1.86e+06, 1.6e+08, 237.167, 1.91e+06, 1.7e+08, 238.890, 1.96e+06, 1.7e+08, 240.719, 2.00e+06, 1.8e+08, 242.668, 2.04e+06, 1.8e+08, 245.484, 2.09e+06, 1.8e+08, 246.897, 2.12e+06, 1.9e+08, 249.420, 2.16e+06, 1.9e+08, 251.151, 2.19e+06, 1.9e+08, 254.936, 2.24e+06, 2.0e+08, 259.251, 2.30e+06, 2.0e+08, ,

262.929, 2.34e+06, 2.1e+08, 267.086, 2.37e+06, 2.1e+08, i 271.855, 2.41e+06, 2.1e+08, 281.634, 2.47e+06, 2.2e+ 08, 292.060, 2.52e+06, 2.2*+08, 302.415, 2.55e+06, 2.2e+08, 311.215, 2.57e+06, 2.3e+08, 321.094, 2.59e+06, 2.3e+08, 331.360, 2.60e+06, 2.3e+08, 340.999, 2.61e+06, 2.3e+08, 351.095, 2.61e+06, 2.3e+08, 361.352, 2.62e+06, 2.3e+08, 371.311, 2.62e+06, 2.3e+08, 391.750, 2.63e+06, 2.3e+08, 411.491, 2.64e+06, 2.3e+08, 432.076, 2.64e+06, 2.3e+08, 452.069, 2.64e+06, 2.3e+08, 471.774, 2.64e+06, 2.3e+08, 524.047, 2.65e+06, 2.3e+08, 573.273, 2.65e+06, 2.3e+08, 573.273, 0.00, 0.00, 1.00e+07, 0.00, 0.00/

& LIST P00L=701, 0, 0, 1, 0, 211.1, 0, 1, 0, 211.1, 0, 0, 0, 573.273, 0, 0, 0, 8.64e+04, 0, 0, 0, 1.00e+07, 0, 0, 0/

& LIST P00L=801, 0, 0, 0, 0, 100, 100, 60, 0, 0, 0, 100, 100, 60, 8.02e+05, 0, 0, 100, 100, 573.273, 8.02e+05, 0, 0, 100, 100, 573.273, 8.02e+05, 3.12e+06, 0.90, 100, 100, 800, 8.02e+05, 3.12e+06, 0.90, 100, 100, 900, 8.02e+05, 3.12e+06, 0.91, 100, 100, 1500, 8.02e+05, 3.12e+06, 0.92, 100, 100, 2280, 8.02e+05, 3.12e+06, 0.93, 100, 100, 2280, 9.50e+05, 6.30e+05, 0.67, 0, 0, 3000, 9.50e+05, 6.30e+05, 0.68, 0, 0, 4000, 9.50e+05, 6.30e+05, 0.68, 0, 0, 5000, 9.50e+05, 6.30e+05, 0.70, 0, 0, 7200, 9.50e+05, 6.30e+05, 0.73, 0, 0, 7200, 9.50e+05, 6.30e+05, 0.50, 0, 0, 1.00e+7, 9.50e+05, 6.30e+05, 0.50, 0, 0/

& LIST P00L=901, 0.0, 0, 0,

NES&L DEPARTMENT CALCULATION SHEET '

'cc" ". CCN NO.

PRELIM PAGE,_,,oF _

ProjIct or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 cCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 175 l REV ORIGINATOR DATE IRE DATE REV OPIGINATOR DATE BRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 l I 1.0e+07, 0, 0/

& LIST P00L=1001, 0, 100, 2.0,

, 24, 100, 2.0/

! & LIST POOL =1101, 1, 21, 105, l 105, 0.000, 120, 1.670e+06, 130, 3.020e+06, l 140, 4.570e+06, 150, 6.320e+06, 160, 8.270e+06, 170, 1.040e+07, 180, 1.273e+07, 190, 1.523e+07, l 200, 1.788e+07, 210, 2.068e+07, 220, 2.361e+07, 230, 2.664e+07, 240, 2.974e+07, 250, 3.291e+07, 260, 3.611e+07, 270, 3.931e+07, l

280, 4.252e+07, 287, 4.474e+07, 290, 4.569e+07, 300, 4.882e+07/

& LIST POOL =1201, 0.0, 0.729, 0.1, 0.737, 0.2, 0.747, l 0.3, 0.757, 0.4, 0.771, 0.5, 0.788, 0.6, 0.809, 0.7, 0.832, i 0.8, 0.863, '

O.9, 0.912, 1.0, 0.961, i

1.1, 0.983, i 1.2, 0.995, 1.3, 1.000/ _

& LIST P00Ls?001, 5, 0.05, 0.1, 50, 10, 0.05, 0.25, 20, 15, 0.05, 0.50, 10, 20, 0.05, 0.50, 10, 100, 0.1, 1.0, 10, 200, 1.0, 5.0, 10, 400, 1.0, 10.0, 5, 700, 2.0, 20.0, 5, 3e+03, 5.0, 50.0, 2, 1e+04, 50.0, 500, 7, 1 e+05, 50.0, 1e+04, 1, 1e+06, 50.0, 1e+05, 1, 1 1e+07, 50.0, Se+05, 1, l 2e+07, 50.0, Se+05, 1/

& LIST P00Lx9999/

• HS #1 - REACTOR BUILDlHG DOME

! & LIST POOL =101001, 100, 7, 0, 0, 0, 0, 34693.22/

& LIST P00Ls101101, 5, 0.00075, 3, 0.02158, 3, 0.02193, 10, 0.06360, 20, 0.23028, 37, 1.00110,

NES&L DEPARTMENT CALCULATION SHEET 'cc" " >

PREUM. CCW WO. PAGE _ OF _

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

l CCN NO. CCN -

l Subject Containrnent P/T Analysis for Desian Basis LOCA Sheet No. 176 l

REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 l 21, 4.06363/

l & LIST POOL =101201, 4, 1, 5, 2, 2, 2, 2/

} & LIST P00L=101300, 0, 0/

& LIST P00L=101400, 2, 2, 1, 1/

• HS #2 - CYLINDER WALL BETWEEN El. 29'6= AND 112'0=

SLIST POOL =102001, 100, 7, 0, 0, 0, 0, 38120/

& List POOL =102101, 5, 0.00075, 3, 0.02158, 3, 0.02193, 10, 0.06360, 20, 0.14694, 37, 0.917761, i 21, 4.35526/

l & LIST POOL =102201, 4, 1, 5, 2, 2, 2, 2/

& LIST POOL =102300, 0, 0/

SLIST P00L=102400, 2, 2, 1, 1/

• HS #3 - CYLINDER WALL BETWEEN El. 15'0= AND El. 29'6"

& LIST P00L=103001, 100, 7, 0, 0, 0, 0, 6667.38/

& LIST POOL =103101, 5, 0.00075, 3, 0.02158, l 3, 0.02193, 10, 0.06360, l 20, 0.14694, 37, 0.917761, l 21, 4.35526/

l & LIST P00L=103201, 4, 1, 5, 2, 2, 2, 2/

& LIST P00L=103300, 0, 0/

I ALIST POOL =103400, 2, 2, 0, 2/

l

• HS #4 - BASEMAT (OTHER THAN REACTOR BASEMAT)

& LIST POOL =104001, 53, 5, 0, 0, 0, 0, 12800/

& LIST POOL =104101, 3, 0.00067, 7, 0.1, 20, 1.52698, 2, I.54781, 20, 11.02150/

& LIST POOL =104201, 4, 2, 2, 1, 2/

& LIST Po0L=104300, 0, 0/

& LIST P00L=104400, 3, 3, 0, 3/

• HS #5 - REACTOR BASEMAT & S.G. PEDESTALS

& LIST POOL =105001, 70, 4, 0, 0, 0, 0,1644/

& LIST POOL =105101, 4, 0.00158, 10, 0.1, 30, 2.00, 25, 8.43092/

& LIST Po0L=105201, 4, 2, 2, 2/

& LIST POOL =105300, 0, 0/

& LIST POOL =105400, 3, 3, 0, 3/

• HS #6 - REACTOR CAVITY WALLS BELOW El. 15'0=

& LIST POOL =106001, 93, 5, 1, 11.75, 0, 0, 21.5/

& LIST POOL =106101, 5, 11.75192, 7, 11.77292, 30, 13.29923, 30, 19.29923, -

20, 25.25192/

& LIST POOL =106201, 4, 2, 2, 2, 2/

& LIST POOL =106300, 0, 0/

& LIST POOL =106400, 3, 3, 0, 3/

• MS #7 - REACTOR CAVITY WALLS ABOVE El. 15'0"

& LIST POOL =107001, 68, 5, 0, 0, 0, 0, 2810/

& LIST POOL =107101, 5, 0.00192, 7. 0.02292, 15, 0.40192, 20, 2.00, 20, 4.00192/

& LIST POOL =107201, 4, 2, 2, 2, 2/

& LIST POOL =107300, 0, 0/

& LIST P00L=107400, 2, 2, 0, 2/

• HS #8 - LINED REFUELING CANAL WALLS

( & LIST P00L=108001, 86, 6, 0, 0, 0, 0, 9200/

& LIST POOL =108101, 5, 0.01563, 20, 0.1, 15, 0.41563, 20, 2.00, 20, 4.01563, 5, 4.01755/

l & LIST POOL =108201, 3, 2, 2, 2, 2, 4/

! & LIST P00L=108300, 0, 0/

l & LIST POOL =108400, 2, 2, 2, 2/

l

• MS #9 - S.G. CMPRTMNT WALLS, UNLINED REFL CNL WALLS /0TH INT WALLS

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CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 177 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 S

& LIST P00L=109001, 78, 4, 0, 0, 0, 0, 41976/

& LIST P00L=109101, 5, 0.00192, 10, 0.04233, 12, 0.1, 50, 1.71876/

& LIST P00L=109201, 4, 2, 2, 2/

& LIST P00L=109300, 0, 0/

& LIST P00L=109400, 2, 2, 0, 2/

• HS #10 - FLOOR SLABS (OTHER THAN BASEMATS)

& LIST P00L=110001, 67, 6, 0, 0, 0, 0, 17474/

& LIST P00L=110101, 3, 0.00014, 5, 0.005348, 20, 0.105348, 15, 0.505348, 20, 1.505348, 3, 1.506015/

& LIST P00L=110201, 4, 1, 2, 2, 2, 4/

& LIST P00L=110300, 0, 0/

& LIST P00L=110400, 2, 2, 2, 2/

• HS #11 - LIFTING DEVICES (EXCEPT STAINLESS STEEL PARTS)

& LIST P00L=111001, 17, 2, 0, 0, 0, 0, 57286/

& LIST P00L=111101, 6, 0.00125, 10, 0.042917/

& LIST P00L=111201, 4, 1/

& LIST P00L=111300, 0, 0/

& LIST P00L=111400, 2, 2, 0, 2/

• HS #12 - MISCELLANEOUS CARBON STEEL - THICKNESS > 2.50 INCHES

& LIST P00L=112001, 64, 4, 0, 0, 0, 0, 516/

& LIST P00L=112101, 6, 0.0005, 17, 0.084, 15, 0.20, 25, 0.310849/

& LIST P00L=112201, 4, 1, 1, 1/

& LIST P00L=112300, 0, 0/

& LIST P00L=112400, 2, 2, 0, 2/

• HS #13 - MISCELLANEOUS CARBON STEEL: 1.00"< THICKNESS <2.50"

& LIST P00L=113001, 32, 2, 0, 0, 0, 0, 12042/

& LIST P00L=113101, 6, 0.00063, 25, 0.16967/

& LIST P00L=113201, 4, 1/

& LIST P00L=113300, 0, 0/

& LIST P00L=113400, 2, 2, 0, 2/

• HS #14 MISCELLANEOUS CARBON STEEL: 0.50"< THICKNESS <1.00"

& LIST P00L=114001, 19, 2, 0, 0, 0, 0, 64693/

& LIST P00L=114101, 5, 0.000674, 13, 0.038607/

& LIST P00L=114201, 4, 1/

& LIST P00L=114300, 0, 0/

& LIST P00L*114400, 2, 2, 0, 2/

• HS #15 - MISCELLANEOUS CARBON STEEL: THICKNESS <0.5"

& LIST P00L=115001, 17, 2, 0, 0, 0, 0, 98913.6/

& LIST P00L=115101, 6, 0.000606, 10, 0.012833/

& LIST P00L=115201, 4, 1/

& LIST P00L=115300, 0, 0/

&L1ST P00L=115400, 2, 2, 0, 2/

• HS #16 - ELECTRICAL EQUIPMENT

& LIST P00L=116001, 8, 1, 0, 0, 0, 0, 37644.5/

& LIST P00L=116101, 7, 0.0054/

> & LIST P00L=116201, 1/

& LIST P00L=116300, 0, 0/

& LIST P00L=116400, 2, 2, 0, 2/

• HS #17 MISCELLANEOUS STAINLESS STEEL

& LIST P00L=117001,16,1, 0, 0, 0, 0, 24048/

& LIST P00L=117101, 15, 0.01747/

& LIST P00L=117201, 3/

'l

& LIST P00L=117300, 0, 0/

& LIST P00L=117400, 2, 2, 0, 2/

• HS #18 - UNLINED REFUELING CANAL WALLS BELOW El. 63'6"

& LIST P00L=118001, 48, 4, 0, 0, 0, 0, 3700/

& LIST P00L=118101, 5, 0.00192, 7, 0.02292, 15, 0.40192, 20, 2.00192/

& LIST P00L=118201, 4, 2, 2, 2/

NES&L DEPARTMENT CALCULATION SHEET '

'c" " . CCN NO.

PRELIM PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containrnent P/T AnalvSis for Desian Basis LOCA Sheet No. 178 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 4

1 l

& LIST P00L=118300, 0, 0/

& LIST P00L=118400, 2, 2, 0, 2/

• HS #19 - REACTOR BLDG CYLINDER #3: SECTIONS WITH ST!FFENERS

& LIST P00L=119001,100, 7, 0, 0, 0, 0,1590.68/

ELIST P00L=119101, 5, 0.00075, 20, 0.66742, 3, 0.66777, 15, 0.70944, 20, 0.79278, 16, 1.44278, 20, 4.87885/

& LIST P00L=119201, 4, 1, 5, 2, 2, 2, 2/

& LIST P00L=119300, 0, 0/

& LIST P00L=119400, 2, 2, 1, 1/

• HS #20 - VENT TUNNELS

& LIST P00L=120001, 23, 2, 0, 0, 0, 0, 2827/

& LIST P00L=120101, 10, 0.0005, 12, 0.03175/

& LIST P00L=120201, 4, 1/

& LIST POOL =120300, 0, 0/

& LIST P00L=120400, 2, 2, 0, 2/ i l

& LIST P00L=410001, '

25, 54, 0.8, 30, 10, 54, 0.1, 20, 0.0174, 0.0103/

& LIST P00L=500000 / .

NES&L DEPARTMENT CALCULATION SHEET ""'

PRELIM. CCN NO. PAGE_.,_ OF__

Project or DCP/MMP SONGS Units 2 & 3 Caic. No. N-4080-028 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA . Sheet No. 179 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 8.3 COPA'ITA CODE OUTPUT

l l

i 8.3.1 Quinut Emoloved for Summarv of Results h

Several plots are presented in Section 2 of this analysis. The COPATTA Code output data used to generate these plots are tabulated in this section.

j 4

a. The following data which is extracted from the COPATTA Code output is presented in .

Table 8.3-1:

i l

Containment pressure (psia) from the COPATTA output and the containment gauge i pressure (psig) with respect to the outside environment pressure of 14.7 psia. The containment gauge pressure (psig) is plotted against ti ne in Figure 2-1 for the DBA

! LOCA case.

Sump temperature ( F) and vapor temperature (*F). The two tempentures (*F) are plotted against time in Figure 2-2 for the DBA LOCA case.

i

2 Condensing heat transfer coefficient (Bru/hr-ft - F). This is plotted against time data l in Figure 2-3 for the DBA LOCA case.

1 i

! b. Table 8.3-2 presents the various energies versus time data that is plotted in Figures 2-4A j and 2-4B for the DBA LOCA case. All the data was extracted directly from the COPATTA Code output. l 3

l- c. Table 8.3-3 presents the surface temperatures of various containment heat sinks versus j time data that is plotted in Figure 2-5 for the DBA LOCA case. Since heat sink data was j

not requested for all the times in the COPATTA Code output, the heat sink data provided is only for the times that the program was requested to print it (See Section 8.1.25). The heat sinks are:

! HS 2 Containment Building Cylinder above grade i HS 8 Lined refueling canal walls f

HS 9 Steam Genemtor companment walls, unlined refueling canal walls & other j internal walls l HS 15 Miscellaneous carbon steel

thickness < 0.5" l HS 16 Electrical equipment i

i t

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CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 180 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 h

5 I

l Table 8.3-1 l DBA LOCA PRESSURE, TEMPERATURE AND HTC DATA ELAPSED PRESSURE GAUGE VAPOR TEMP SUMP TEMP CONDENSING TIME PRESSURE HTC (Seconds) (Psia) (Psig) (*F) (*F) (Bru/hr-R2 'F) 0.05 16.2099 1.5139 110.191 212.916 8.66132 0.1 16.5674 1.8714 115.618 214.52 9.46209 0.2 17.2822. 2.5862 125.373 216.548 11A36 0.3 18.1282 3.4322 136.055 218.096 14.0837 0.4 18.9045 4.2085 143.946 217.015 15.8076 l

l 0.5 19.6132 4.9172 149.323 215.304 16.9939 0.6 20.3386 5.6426 155.223 214.625 18.8116 0.7 21.0465 6.3505 160.959 215.695 20.1424 0.8 21.7257 7.0297 165.753 216.734 21.2876 l

0.9 22.3517 7.6557 169.855 217.698 22.514 f 1 22.9151 8.2191 172.507 217.647 23.5069 l 1.1 23.4838 8.7878 175.745 217.45 24.5493 1.2 23.9873 9.2913 178.477 217.88 25.6617 1.3 24.5087 9.8127 181.185 217.463 26.6576 1.4 25.0227 10.3267 183.743 217.202 27.5404 1.5 25.5296 10.8336 186.168 217.065 28.3283 1.6 26.0115 11.3155 188.39' 217.025 29.0847 1.7 26.5M2 11.8082 190.583 217.06 30.5449 1.8 26.9903 12.2943 192.675 217.159 31.8692 1.9 27.4703 12.7743 194.675 - 217.311 33.0763 2 27.9441 13.2481 196.59 217.506 34.1806 2.1 28.3913 13.6953 198.346 217.737 35.1964 2.2 28,8487 14.1527 200.I53 217.99 36.1173 2.3 29.309 14.613 201.846 218.278 36.9921 2.4 29.7582 15.0622 203.475 218.58 38.2468 2.5 30.2015 15.5055 205.043 218.899 39.4165 2.6 30.639 15.943 2 % .555 219.229 40.5056 2.7 31.0363 16.3403 207.898 219.735 41.5276 2.8 31.46M 16,7644 209.58 220.383 42.4671 2.9 31.8691 17.1731 210.628 220.72 43.3422 l 3 32.2828 17.5868 211.944 221.059 44.1795 3.1 32.6918 17,9958 213.219 221.401 44.9683

- . _ -~ _ _ __

- . - - . - _ . _ . - - - . = - - - . _

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PREUM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3

{ Calc. No. N-4080-026 CCN CONVERSION:

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l Subject _ Containment P/T Analvsis for Desian Basis LOCA Sheet No. 181

) REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE lRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

V

8

Table 8.3-1

! DBA LOCA PRESSURE, TEMPERATURE AND HTC DATA

,i l

ELAPSED PRESSURE GAUGE VAPOR TEMP SUMP TEMP CONDENSING i TIME PRESSURE HTC (Seconds) (Psia) (Psig) (*F) (*F) (Btu /hr-ft2 ..p) l 3.2 33.0967 18.4007 214.457 221.744 45.7141 3.3 33.4976 18.8016 215.662 222.088 46.8651 l 3.4 33.8942 19.1982 216.832 222.432 48.2853 3.5 34.2865 19.5905 217.97 222.775 49.7054 3.6 34.6668 19.9708 219.055 223.405 51.1256 i.

i 3.7 35.0421 20.3461 220.109 224.014 52.5457 l 3.8 35.3448 20.6488 220.947 224.626 53.9659 l 3.9 35.752 21.056 222.339 225.213 55.386 4 36.0781 21.3821 222.936 225.695

) 56.8 % 2

, 4.1 36.4459 21.7499 223.936 226.162 58.2263 a

j 4.2 36.7902 22.0942 224.814 226.615 59.6465

4.3 37.1485 22.4526 225.74 226.902 61.0667 4.4 37.5039 22.8079 226.646 227.185 62.4868 j 4.5 37.8608 23.1648 227.543 227.465 63.907 l' 4.6 38.1977 23.5017 228.381 227.94 65.3271 4.7 38.5534 23.8574 229.254 228.208

{ 66.7473 4.8 38.8921 24.1961 230.075 228.595 68.1674

] 4.9 39.2033 24.5073 230.821 229.059 69.5876

5 39.5295 24.8335 231.594 229.421 71.0077 5.25 40.3337 25.6377 233.465 - 230.341 74.5581 l 5.5 41.0327 26.3367 235.052 231.27 78.1085

{ 5.75 41.8007 27.1047 237.027 232.136 81.6589 6 42.5318 27.8358 238.343 232.846 85.2093 6.25 43.2545 28.5585 239.872 233.472 88.7597 6.5 43.9588 29.2628 241.334 234.218 92.3101 j 6.75 44.6482 29.9522 242.737 234.907 95.8604

7 45.3226 30.6256 244.084 235.603 99.4108

] 7.25 45.9645 31.2685 245.31 236.256 102.961 j 7.5 46.5356 31.8396 246.444 236.912 106.512

7.75 47.1616 32.4656 247.633 237.539 110.062 i 8 47.7772 33.0812 248.783 238.06 113.612 j 8.25 48.3756 33.6796 249.885 238.649 117.163 4

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CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 182 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

4 Table 8.3-1 DBA LOCA PRESSUPI, TEMPERATURE AND HTC DATA ELAPSED PRESSURE GAUGE VAPOR TEMP SUMP TEMP CONbENSING TIME PRESSURE HTC (Seconds) (Psia) (Psig) (*F) (*F) (Bru/hr-ft2..p) 8.5 48.9698 34.2738 250.962 239.052 120.713 8.75 49.5513 34.8553 252.002 239.47 124.264 9 50.116 35.42 252.998 239.939 127.814 9.25 50.6715 35.9755 253.964 240.402 131.364 9.5 51.165 36.469 254.812 240.891 134.915 9.75 51.6298 36.9338 255.603 241.321 138.465 10 52.1886 37.4926 256.615 241.754 142.015 10.5 53.1801 38.4841 258.319 242.557 149.116 11 54.1127 39.4167 259.85 243.286 156.217 11.5 54.9534 40.2574 261.023 243.874 163.318 12 55.8084 41.1124 262.357 244.264 170.419 12.5 56.4266 41.7306 263.308 244.728 177.519 13 57.1137 42.4177 264.35 245.119 184.62 13.5 57.719 43.023 265.26 245.447 191.721 14 58.255 43.559 266.186 245.734 198.822 14.5 58.6004 43.9044 266.558 246.068 205.922 15 58.9523 44.2563 267.412 246.367 213.023 15.5 59.0967 44.4007 267.281 246.641 220.124 16 59.2342 44.5382 267.48 246.883 227.225 16.5 59.3124 44.6164 267.677 - 247.118 234.326 17 59.3293 44.6333 267.748 247.333 241.426 17.5 59.2948 44.598b 267.567 247.505 248.527 l

18 59.2447 44.5487 267.5 247.654 255.628 18.5 59.1852 44.4892 267.412 247.783 248.905 19 59.1163 44.4203 267.313 247.923 255.628 19.5 59.0394 44.3434 267.198 248.097 255.628 20 58.958 44.262 267.077 248.25 229.78 21 58.7654 44.0694 266.795 248.537 255.628 22 58.5434 43.8474 266.47 248.715 206.546 23 58.3587 43.6627 266.21 248.777 195.825 24 58.2145 43.5185 266.016 248.834 185.661 25 58.1416 43.4456 266.212 248.887 176.024

NES&L DEPARTMENT CALCULATION SHEET 'cc" "o '

PREUM. CCN No. PAGE . oF_

t Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CcN CoNVERSloN: l l CCN No. CCN -- l l Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 183 I l REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

f

, \

s l

Table 8.3-1 DBA LOCA PRESSURE, TEMPERATURE AND HTC DATA ELAPSED PRESSURE GAUGE VAPOR TEMP SUMP TEMP CONDENSING TIME PRESSURE HTC (Seconds) (Psia) (Psig) ('F) ('F) (Btu /hr-ft: *F) 26 58.1236 43.4276 266.699 248.936 166.888 27 58.1495 43.4535 267.412 248.983 158.226 28 58.2001 43.5041 268.243 249.028 150.013 29 58.2404 43.5444 268.841 248.62 142.227 30 58.2365 43.5405 269.298 248.216 134.845 l 31 58.2401 43.5441 269.78 247.818 127.846 I 32 58.2509 43.5549 270.283 247.425 121.21 33 58.2685 43.5725 270.81 247.037 114.918 34 58.2927 43.5967 271.357 246.655 108.954 35 58.3224 43.6264 271.922 246.277 103.298 36 58.3513 43.6553 272.487 245.906 102.435 37 58.3814 43.6854 273.056 245.541 102.38 38 58.4127 43.7167 273.625 245.182 102.327 39 58.4511 43.7551 274.197 244.827 102.278 40 58.487 43.791 274.8 244.478 102.231 41 58.5218 43.82a8 275.379 244.135 102.187 42 58.5576 43.8616 275.958 243.796 102.145 43 58.5945 43.8985 276.541 243.462 102.106 44 58.6326 43.9366 277.127 243.133 102.07 l 45 58.7085 44.0125 277.922 - 242.809 102.09 46 58.845 44.149 279.052 242.49 102.2 47 58.9817 44.2857 280.179 242.175 102.312 48 59.1188 44.4228 281.304 241.866 102.424 49 59.2559 44.5599 282.423 241.561 102.538 50 59.3934 44.6974 283.538 241.262 102.652 51 59.5309 44.8349 284.648 240. % 6 102.767 52 59.6687 44.9727 285.754 240.675 102.884 53 59.8067 45.1107 286.856 240.388 103.001 l

54 59.9521 45.2561 287.974 240.105 103.12 l

55 60.0907 45.3947 289.071 239.825 103.239 I 56 60.2295 45.5335 290.163 239.549 103.359 57 60.3686 45.6726 291.251 239.277 103.48 1

NES&L DEPARTMENT CALCULATION SHEET '

'cc" ". CCN NO.

PRELIM PAGE _ OF _

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 184 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

4 Table 8.3-1 DBA LOCA PRESSURE, TEMPERATURE AND HTC DATA l

ELAPSED PRESSURE GAUGE VAPOR TEMP SUMP TEMP CONDENSING j TIME PRESSURE HTC (Seconds) (Psia) (Psig) ('F) (*F) (Bru/hr-ft2 ..p) 58 60.5075 45.8115 292.332 239.009 103.602 59 60.6466 45.9506 293.41 238.745 103.725 60 60.7858 46.0898 294.481 238.484 103.848 61 60.7941 46.0981 293.548 238.227 104.082 62 60.7962 46.1002 292.54 237.974 1M.316 63 60.799 46.103 291.538 237.724 104.55 64 60.8025 46.1065 290.545 237.478 IM 784 65 60.8069 46.1109 289.561 237.235 105.018 66 60.8119 46.1159 288.582 236.995 105.253 67 60.8174 46.1214 287.609 236.758 105.487 68 60.8159 46.1199 286.62 236.525 105.721 69 60.8224 46.1264 285.657 236.294 105.955 70 60.8294 46.1334 284.7 236.067 106.189 71 60.837 46.141 283.75 235.842 106.423 72 60.8452 46.1492 282.807 235.621 106.656 73 60.8537 46.1577 281.866 235.402 106.89 74 60.8629 46.1669 280.935 235.186 107.123 75 60.8726 46.1766 280.009 234.973 107.356 76 60.8828 46.1868 279.088 234.763 107.588 77 60.8932 46.1972 278.171 234.555 107.821 78 60.9044 46.2084 277.264 234.351 108.052

79 60.9202 46.2242 276.41 234.149 108.284 80 60.9336 46.2376 275.529 233.949 108.514 4

81 60.9461 46.2501 274.638 233.752 108.745 82 60.9493 46.2533 273.719 233.557 108.975 83 60,9748 46.2788 272.876 233.365 109.205 84 61.0029 46.3069 272.065 233.175 109.434 85 61.0312 46.3352 271.257 232.988 109.662 86 61.0606 46.3646 270.461 232.803 109.89 87 61.1148 46.4188 270.207 232.631 110.% 8 88 61.1543 46.4583 270.326 232.463 110.237 89 61.2257 46.5297 270.393 232.3 110.395

NES&L DEPARTMENT CALCULATION SHEET '

'cc" PRELIM". CCM NO. PAGE OF

! Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN NO. CCN --

j Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 185 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 h 4

Table 8.3-1

DBA LOCA PRESSURE, TEMPERATURE AND HTC DATA ELAPSED PRESSURE GAUGE VAPOR TEMP SUMP TEMP CONDENSING TIME PRESSURE HTC (Seconds) (Psia) (Psig) (*F) (*F) (Bru/hr-ft2 .p) 90 61.3M9 46.6089 270.5 232.136 110.564 l 91 61.3876 46.6916 270.645 231.975 110.731 4

92 61.466 46.77 270.762 231.818 110.894 93 61.5542 46.8582 270.942 231.66 111.057 i 94 61.6333 46.9373 271.M 4 231.507 111.224

95 61.7114 47.0154 271.111 231.354 111.4

96 61.7912 47.0952 271.238 231.205 111.557 97 61.8698 47.1738 271.331 231.058 111.723 98 61.9454 47.2494 271.409 230.913 111.893 l

99 62.0321 47.3361 271.588 230.77 112.049 100 62.1066 47.4106 271.654 230.63 112.223 105 62.5131 47.8171 272.188 229.953 113.104 l 110 62.9187 48.2227 272.727 229.327 113.808 115 63.3938 48.6978 273.25 228.758 114.603 l

120 63.7601 49.0641 274.102 228.207 115.365 e

125 64.1652 49.4692 274.403 227.703 110.268 i 130 64.5608 49.8648 275.103 227.258 116.908

! 135 64.9563 50.2603 275.614 226.839 117.647 140 65.3468 50.6508 276.079 226.455 118.371

l 145 65.6828 50.9868 276.179 - 226.113 119.097 150 66.1323 51.4363 277.168 225.787 119.715 155 66.455 51.759 277.283 225.514 120.458 j 160 66.895 52.199 278.082 225.241 121.08 j 165 67.152 .i2.456 278.138 225.028 121.645 170 67.6709 52.9749 279.353 224.815 122.274

, 175 67.9271 53.2311 279.253 224.651 122.949 180 68.2905 53.5945 279.562 224.499 123.469

185 68.6609 53.9649 280.02 224.374 124.024 190 69.0964 54.40M 280.961 224.258 124.581 j 195 69.4464 54.75 M 281.219 224.177 125.188 200 69.7692 55.0732 281.398 224.128 125.758 l

210 70.5057 55.8097 282.52 224.077 126.767 4

i

l NES&L DEPARTMENT CALCULATION SHEET " "UCN NO.

eREu PAGE _ 0F _

{ Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN No. CCN -

i Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 186 4

4

) REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

i .

i 5 !

l i

Table 8.3-1 l DBA LOCA PRESSURE, TEMPERATURE AND HTC DATA l

$ ELAPSED PRESSURE GAUGE VAPOR TEMP SUMP TEMP CONDENSING TIME PRESSURE HTC j (Seconds) (Psia) (Psig) ('F) ('F) (Bru/hr-ft2,.p) 220 f 71.0368 56.3408 282.898 224.063 127.511 3 230 71.3732 56.6772 283.296 223.813 127.966 240 71.5525 56.8565 283.531 223.389 128.16 l 250 71.5529 56.8569 283.505 222.895 128,194 260 71.5215 56.8255 283.466 222.312 128.117 270 71.4355 56.7395 283.362 221.7 127.975 280 71.3168 56.6208 283.219 221.062 127.793  ;

290 71.1806 56.4846 283.055 220.419 127.589 l 300 71.036 56.34 282.881 219.758 127.373 310 70.8887 56.1927 282.703 219.105 127.153 320 70.7399 56.0439 282.523 218.479 126.93 330 70.5929 55.8969 282.345 217.857 126.709 340 70.4504 55.7544 282.172 217.242 126.495 350 70.2712 55.5752 281.954 216.657 126.291 360 70.1419 55.4459 281.796 216.063 126.093 370 70.0195 55.3235 281.646 215.478 125.903 380 69.9033 55.2073 281.503 214.906 125.722 390 69.7939 55.0979 281.368 214.345 125.55 400 69.6917 54.9957 281.242 213.792 125.386 420 69.5019 54.8059 281.006 - 212.716 125.08 440 69.3241 54.6281 280.785 211.69 124.792 460 69.1744 54.4784 280.597 210.705 124.545 480 69.0461 54.3501 280.436 209.762 124.33 500 68.9343 54.2383 280.294 208.855 124.139 520 68.8371 54.1411 280.171 207.982 123.97 540 68.7536 54.0576 280.063 207.143 123.821 560 68.6816 53.9856 279.97 206.337 123.69 580 68.5607 53.8647 279.817 205.444 123.481 600 68.3132 53.6172 279.506 204.333 123.073 620 68.0777 53.3817 279.208 203.265 122.679 640 67.8498 53.1538 278.919 202.239 122.295 660 67.6312 52.9352 278.64 201.251 121.921

NES&L DEPARTMENT CALCULATION SHEET 'cc" " '

PREUM. CCN HO. PAGE_.,OF _

Proirct or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSloN:

CCN No. CCN -

. hf.iject Containment P/T Analysis for Desian Basis LOCA Sheet No. 187 1

REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 h l s 1

1 1 Table 8.3-1 DBA LOCA PRESSURE, TEMPERATURE AND HTC DATA i

, ELAPSED PRESSURE GAUGE VAPOR TEMP SUMP TEMP CONDENSING l

TIME PRESSURE HTC i (Seconds) (Psia) (Psig) ('F) ('F) (Bru/hr-ft2 ..p) i l

680 67.4194 52.7234 278.37 200.299 121.556

I 700 67.2137 52.5177 278.106 199.385 121.199 .

750 66.7269 52.0309 277.477 197.246 120.328 800 66.2643 51.5683 276.874 195.292 119,494 j i 850 65.8297 51.1337 276.303 193.481 118.691 900 65.4238 50.7278 275.766 191.78 117.925 950 II.'J414 50.3454 275.255 190.194 117.187 1000 64.6735 49.9775 274.76 188.717 116.465 1050 64.3196 49.6236 274.281 187.338 115.758 1100 64.1014 49.4054 274.125 186.053 115.M 4 g

1150 63.9235 49.2275 273.731 184.83 114.309

! 1200 63.5919 48.8959 273.276 183.694 113.619 1250 63.2701 48.5741 272.831 182.622 112.938 t 1300 62.9564 48.26M 272.395 181.605 112.264 1350 62.6492 47.9532 271.965 180.641 111.593 1400 62.3478 47.6518 271.54 179.726 110.924 1450 62.0145 47.3185 271.07 178.865 110.265 i 1500 61.7223 47.0263 270.653 178.035 109.599 1550 61.4337 46.7377 270.24 177.243 108.931 1600 61.1481 46.4521 269.828 - 176.487 108.259 1 1650 60.864 46.168 269.416 175.763 107.582 1700 60.5811 45.8851 269.004 175.07 106.899 l 1750 60.2992 45.6032 268.591 174.405 106.21 4

1800 60.018 45.322 268.177 173.766 105.514 1850 59.7387 45.M27 267.764 173.151 I M.811 j 1900 59.4588 44.7628 267.347 172.56 104.1 1950 59.1822 44.4862 266.933 171.989 103.381 i

2000 58.9031 44.2071 266.513 171.438 102.653 2050 58.6285 43.9325 266.098 170.906 101.924 l 2100 58.3586 43.6626 265.687 170.391 101.201

)- 2150 58.0937 43.3977 265.282 169.893 100.48 2200 57.8358 43.1398 264.884 169.411 99.763

. . . .- . - _ . - - . . . . = _ . - _ . . . . - -.- - _ . - .

J NES&L DEPARTMENT

! 'oo" "o '

CALCULATION SHEET PREUM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

} CCN NO. CCN -

j Subject Containment P/T Analvsis for Desion Basis LOCA Sheet No. 188 i

i REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE BRE DATE R

O R. Nakano 01/18/94 J. Elliott 01/20/94 '

3 1 5 1 Table 8.3-1 DBA LOCA PRESSURE, TEMPERATURE AND HTC DATA I ELAPSED PRESSURE GAUGE VAPOR TEMP SUMP TEMP CONDENSING l TIME PRESSURE HTC (Seconds) (Psia) (Psig) (*F) (*F) (Bru/hr-ft2 .p) 2250 57.5812 42.8852 264.49 168.945 99.0486 2300 57.3384 42.6424 264.116 168.904 98.389

~ i 2350 57.1158 42.4198 263.779 169.477 97.9037 2400 56.8954 42.1994 263.443 170.043 97.6135 2450 5f.7285 42.0325 263.265 170.605 97.314 2500 56.5927 41.8967 262.98 171.154 97.0112 2550 56.3441 41.6481 262.598 171.707 96.724 l 2600 56.133 41.437 262.271 172.247 96.4335 2650 55.9236 41.2276 261.946 172.782 96.1439 2700 55.7174 41.0214 261.625 173.309 95.8549 2750 55.513 40.817 261.305 173.831 95.5665 2800 55.3118 40.6158 260.988 174.346 95.2784 I 2850 55.1123 40.4163 260.673 174.854 94.9909 2900 54.9154 40.2194 260.361 175.357 94.7036 2950 54.72 40.024 260.05 175.853 94.4167 1 3000 54.5273 39.8313 259.742 176.343 94.1298 3500 52.6975 38.0015 256.753 180.941 91.2102  !

4000 51.0112 36.3152 253.89 185.006 88.1836 4500 49.4815 34.7855 251.194 188.565 85.2343 5000 48,1465 33.4505 248.758 - 191.696 82.4939 5500 46.9927 32.2967 246.586 194.415 79.9269 6000 46.0112 31.3152 244.685 196.812 77.4269 6500 45.1436 30.4476 242.962 198.891 75.1352 7000 44.3377 29.6417 241.325 200.702 73.023 7500 43.4859 28.7899 239.552 202.577 70.5811 8000 42.6535 27.9575 237.776 204.384 68.0688 8500 41.9431 27.2471 236.225 205.946 65.8152 9000 41.3299 26.6339 234.858 207.31 63.7571 9500 40.8626 26.1666 233.798 208.509 62.405 10000 40.3574 25.6614 232.634 209.566 61.5095 20000 35.5087 20.8127 220.342 215.431 50.4008 30000 32.8521 18.1561 212.531 211.652 43.7984

NES&L DEPARTMENT

• CALCULATION SHEET 'cc" '

PREUM. CCN NO. PAGE OF l

4 Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSloN:

] CCN NO. CCN -

Subject Containmant P/T Analvsis for Desian Basis LOCA Sheet No. 189 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

l 1 5 4

i i Table 8.3-1 DBA LOCA PRESSURE, TEMPERATURE AND HTC DATA l

ELAPSED PRESSURE GAUGE VAPOR TEMP SUMP TEMP CONDENSING TIME PRESSURE HTC (Seconds) (Psia) (Psig) (*F) (*F) 2 (Bru/hr-ft 'F)

I 40000 30.7096 16.0136 205.487 2 % .396 38.8706 50000 29.1652 14.4692 199.856 201.194 35.3921 60000 27.9373 13.2413 195.038 196.847 32.6189 70000 27.0427 12.3467 191.286 193.228 30.2761 l 80000 26.3517 11.6557 188.227 190.414 28.6527 90000 24.8048 10.1088 180.791 187.508 26.1161 100000 23.8314 9.1354 175.613 182.885 24.0539 200000 21.0258 6.3298 157.681 167.984 19.2198 300000 19.9059 5.2099 148.75 161.915 16.7703 400000 18.9703 4.2743 140.146 156.473 15.1295 500000 18.4714 3.7754 135.019 153.085 13.9466 600000 18.0519 3.3559 130.356 150.257 12.7164 700000 17.7818 3.0858 127.162 148.25 11.7625 800000 17.5394 2.8434 124.153 146.462 10.7882 900000 17.3602 2.6642 121.835 145.032 9.99401 1000000 17.2105 2.5145 119.833 143.864 9.8 % 88 1500000 16.7607 2.0647 115.059 140.569 8.94011 2000000 16.6411 1.9451 113.305 135.644 8.46055 2500000 16.5991 1.9031 112.659 133.255 8.2858 3000000 16.5306 1.8346 110.696 131.016 8.1962 3500000 16.5319 1.8359 111.503 128.728 8.01969 4000000 16.4827 1.7867 110.986 126.446 7.8936 4500000 16.4599 1.7639 110.677 125.317 7.84542 5000050 16.4128 1.7168 108.832 124.221 7.8673 5500050 16.4221 1.7261 110.076 123.146 7.77228 6000050 16.4063 1.7103 109.758 122.045 7.7478 6500050 16.3947 1.6987 109.598 121.479 7.7219 7000050 16.3893 1.6933 109.438 120.928 7.71904 7500000 16.3878 1.6918 109.247 120.376 7.7339 8000000 16.3732 1.6772 109.126 119.835 7.6921 8500050 16.3659 1.6699 108.971 119.293 7.68153 9000050 16.3456 1.6496 108.854 118.777 7.61585

NES&L DEPARTMENT l CALCULATION SHEET 'cc" " '

PRELIM. CCN NO. PAGE OF j Projset or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 190 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE BRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 E 4

1 1

Table 8.3-1 d

DBA LOCA PRESSURE, TEMPERATURE AND HTC DATA ELAPSED PRESSURE GAUGE VAPOR TEMP SUMP TEMP CONDENSING l TIME PRESSURE HTC  !

(Seconds) (Psia) (Psig) (*F) (*F) (Bru/hr-ft2 .p) 9500050 16.3399 1.6439 108.726 118.252 7.60776 I 10000000 16.335 1.639 108.556 117.676 7.60776 i

1  !

l f

4 4

4 i

i i

NES&L DEPARTMENT CALCULATION SHEET =3 PRELIM. CCN NO. PAGE OF Project or DCP/MMPJONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 191 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

V 5

Table 8.3-2 DBA LOCA ENERGY DATA ENERGY (Million of BTUS)

ELAPSED TIME STEAM & SUMP TOTAL HEAT SINK HEAT CONT AIR (Seconds) AIR EXCHANGER SPRAY COOLER 0.05 25.0485 0.331456 25.38 -0.00002624 0 0 0 0.1 26.6493 0.763169 27.4125 -0.00009559 0 0 0 0.2 29.973 1.66222 31.6352 -0.00002038 0 0 0 0.3 33.974 2.7555 36.7295 0.00138748 0 0 0 0.4 37.9006 3.74946 41.65 0.0M73591 0 0 0 0.5 41.7716 4.66152 > 6.4331 0.00987801 0 0 0 0.6 45.5708 5.57408 51.1449 0.0168506 0 0 0 0.7 49.2521 6.5324 55.7845 0.0257022 0 0 0 0.8 52.8497 7.47295 60.3226 0.0362731 0 0 0 0.9 56.225 8.36379 64.5888 0.N85122 0 0 0 1 59.4289 9.14312 68.5721 0.0622899 0 0 0 1.1 62.4704 9.86365 72.334 0.0774232 0 0 0 1.2 65.3268 10.6065 75.9333 0.0940231 0 0 0 1.3 68.1688 11.2651 79.4339 0.112018 0 0 0 1.4 70.9751 11.925 82.9001 0.131399 0 0 0 1.5 73.7463 12.5858 86.3321 0.152034 0 0 0 1.6 76.4839 13.2459 89.7298 0.173824 _ 0 0 0 1.7 79.1869 13.9062 93.0931 0.197058 0 0 0 1.8 81.8556 14.566 96.4215 0.221972 0 0 0 1.9 84.4905 15.2247 99.7152 0.248455 0 0 0 2 87.092 15.8822 102.974 0.276358 0 0 0 2.1 89.6612 16.5366 106.198 0.305592 0 0 0 2.2 92.192 17.1933 109.385 0.336116 0 0 0 2.3 94.6991 17.8373 112.536 0.367906 0 0 0 2.4 97.164 18.4819 115.651 0.401095 0 0 0 2.5 99.6062 19.1225 118.729 0.435726 0 0 0 2.6 102.011 19.7588 121.77 0.471717 0 0 0 2.7 104.366 20.4075 124.774 0.508987 0 0 0 2.8 106.657 21.0842 127.741 0.547485 0 0 0 2.9 108.97 21.7015 130.671 0.587173 0 0 0 1

NES&L DEPARTMENT CALCULATION SHEET 'oc" ".

PREUM CCN NO. PAGE ,0F_

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 192 REV ORIGINATOR DATE ME DATE REV ORIGINATOR DATE BRE DATE R

, O R. Nakano 01/18/94 J. Elliott 01/20/94 '

i 4

a l Table 8.3-2

, DBA LOCA ENERGY DATA l

ENERGY (Million of BTUS) l ELAPSED

! TIME STEAM & SUMP TOTAL HEAT SINK HEAT CONT AIR (Seconds) AIR EXCHANGER SPRAY COOLER 2  :

1 I

3 111.247 22.3177 133.564 0.628033 0 0 0 1

3.1 113.496 22.9278 136.424 0.670037 0 0 0 t 3.2 115.722 23.5312 139.253 0.713096 0 0 0 1

! 3.3 117.925 24.1277 142.053 0.75725 0 0 0 3.4 120.1M 24.7174 144.821 0.802929 0 0 0 3.5 122.258 25.3001 147.558 0.850149 0 0 0 l 3.6 124.341 25.9225 150.264 0.898883 0 0 0 l 3.7 126.4 26.5372 152.937 0.949111 0 0 0 I f 3.8 128.433 27.1458 155.579 1.00078 0 0 0 J 3.9 130.436 27.752 158.188 1.05386 0 0 0 j 4 132.445 28.319 160.764 1.10846 0 0 0

4.1 134.43 28.8802 163.31 .?.16453 0 0 0 l 4.2 136.379 29.448 165.827 1.22208 0 0 0 J

4.3 138.347 29.9668 168.314 1.28108 0 0 0 1

4.4 140.296 30.476 170.772 1.34155 0 0 0 4.5 142.228 30.971 173.199 1.4035 0 0 0 l

l 4.6 144.09 31.5047 175.595 1.46692 0 0 0 j 4.7 145.985 31.9749 177.96 1.53168 . 0 0 0 f 4.8 147.825 32.469 180.294 1.59777 0 0 0 4.9 149.605 32.9907 182.595 1.66517 0 0 0 j 5 151.395 33.4691 184,864 1.73388 0 0 0 l 5.25 155.783 34.6354 190.418 1.91128 0 0 0 5.5 160.045 35.7692 195.814 2.09653 0 0 0 5.75 164.183 36.8637 201.047 2.28946 0 0 0 j 6 168.242 37.8701 200.112 2.4901 0 0 0 l 6.25 172.199 38.8437 211.042 2.69828 0 0 0 l 6.5 176.038 39.8334 215.872 2.91365 0 0 0 3

6.75 179.799 40.8012 220.601 3.13574 0 0 0

7 183.469 41.7593 225.229 3.3644 0 0 0 7.25 187.089 42,6669 229.756 3.59946 0 0 0 f

7.5 190.561 43.6201 234.181 3.8404 0 0 0 l

4

! NES&L DEPARTMENT CALCULATION SHEET 'cc" Nos PRELIM. CCN NO. PAGE _ OF _

Projtet or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 193 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 l

, h 5

i Table 8.3-2 4 DBA LOCA ENERGY DATA i

ENERGY (Million of BTUS)

EL.APSED

TIME STEAM & SUMP TOTAL HEAT SINK HEAT CONT AIR

(Seconds) AIR EXCHANGER SPRAY COOLER i

7.75 193.975 44.5297 238.505 4.08742 0 0 0 8 197.328 45.3986 242.726 4.34023 0 0 0 8.25 200.58 46.2736 246.854 4.59873 0 0 0 l 8.5 203.808 47.0865 250.894 4.8627 0 0 0 8.75 206.959 47.8899 254.848 5.13171 0 0 0 9 210.019 48.697 258.716 5.40557 0 0 0 9.25 213.009 49.487 262.496 5.68407 0 0 0 9.5 215.867 50.321 266.188 5.96705 0 0

] 0 9.75 218.753 51.0389 269.792 6.25395 0 0 0 J

10 221.563 51.7453 273.308 6.54501 0 0 0 l 10.5 226.9 53.1552 280.055 7.13875 0 0 0 11 231.953 54.4348 286.388 7.74694 0 0 0 11.5 236.691 55.5842 292.275 8.36748 0 0 0 1 12 241.18 56.5063 297.686 8.99874 0 0 0

~

l 12.5 245.225 57.3989 302.624 9.63914 0 0 0

, 13 248.946 58.1319 307.078 10.2871 0 0 0

] 13.5 252.243 58.749 310.992 10.9411 0 0 0 j 14 254.983 59.2971 314.28 11.6003 _ 0 0 0 14.5 256.998 59.9318 316.93 12.2625 0 0 0 l

15 258.578 60.5074 319.086 12.9261 0 0 0

. 15.5 259.672 61.1247 320.796 13.59 0 0 0 i 16 260.373 61.6453 322.018 14.2525 0 0 0 16.5 260.736 62.1261 322.862 14.9122 0 0 0 17 260.851 62.5739 323.425 15.5686 0 0 0 17.5 260.72 62.9524 323.673 16.221 0 0 0 18 260.437 63.2891 323.726 16.8684 0 0 0 18.5 260.1G4 63.5928 323.697 17.5011 0 0 0 19 259.73 63.9168 323.647 18.1204 0 0 0 19.5 259.298 64.3017 323.599 18.7334 0 0 0 4

20 258.852 64.6531 323.505 19.3223 0 0 0 i 21 257.84 65.33 323.17 20.4582 0 0 0

NES&L DEPARTMENT CALCULATION SHEET "" '

PREUM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desion Basis LOCA Sheet No. 194 REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 h l 5 Table 8.3-2 DBA LOCA ENERGY DATA ENERGY (Million of BTUS) l ELAPSED TIME STEAM & SUMP TOTAL HEAT SINK HEAT CONT AIR (Seconds) AIR EXCHANGER SPRAY COOLER 22 256.637 65.805 322.442 21.50N 0 0 0 23 255.618 66.0564 321.674 22.4863 0 0 0 l 24 254.844 66.2934 321.137 23.4227 0 0 0 25 254.339 66.5165 320.855 24.3143 0 0 0 26 254.054 66.7291 320.783 25.1649 0 0 0 27 253.947 66.9323 320.879 25.9778 0 0 0 j 28 253.945 67.1267 321.072 26.756 0 0 0 29 253.686 67.4615 321.148 27.5013 0 0 0 30 253.466 67.7875 321.253 28.2149 0 0 0 31 253.282 68.1053 321.387 28.8983 0 0 0 32 253.133 68.4151 321.548 29.5532 0 0 0 33 253.017 68.7175 321.735 30.1809 0 0 0 34 252.932 69.0127 321.945 30.7828 0 0 0 35 252.875 69.3016 322.176 31.3602 0 0 0.00210985 36 252.812 69.5908 322.403 31.9214 0 0 0.02321N 37 252.756 69.8777 322.634 32.4766 0 0 0.044315 38 252.706 70.1624 322.869 33.0255 0 0 0.0654239 39 252.663 70.4448 323.108 33.5684 0 0 0.0865377 40 252.626 70.7251 323.351 34.1055 0 0 0.107658 41 252.595 71.0031 323.598 34.6368 0 0 0.128784 42 252.57 71.2789 323.849 35.1623 0 0 0.149916 43 252.55 71.5526 324.103 35.6823 0 0 0.171053 44 252.537 71.8243 324.361 36.1969 0 0 0.192197 45 252.667 72.094 324.761 36.7062 0 0 0.213349 j 46 253.026 72.3621 325.388 37.2116 0 0 0.234525 l 47 253.387 72.6286 326.015 37.7133 0 0 0.255731

( 48 253.751 72.8935 326.644 38.2115 0 0 0.276968 I 49 254.117 73.157 327.274 38.7061 0 0 0.298235 f 50 254.486 73.419 327.905 39.1973 0 0 0.319533 51 254.857 73.6795 328.536 39.685 0 0 0.340861 52 255.23 73.9383 329.169 40.1693 0 0 0.362219 l

l

NES&L DEPARTMENT CALCULATION SHEET 'cc" " ' l PRELIM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN No. CCN --

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 195 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 '

R. Nakano 01/18/94 J. Elliott 01/20/94 f 5

Table 8.3-2 l DBA LOCA ENERGY DATA ENERGY (Million of BTUS)

ELAPSED '

TIME STEAM & SUMP TOTAL HEAT SINK HEAT CONT AIR l (Seconds) AIR EXCHANGER SPRAY COOLER l 53 255.606 74.1956 329.802 40.6501 0 0 0.383603

( $4 255.985 74.4515 330.436 41.1275 0 0 0.405015 55 256.366 74.7058 331.071 41.6015 0 0 0.426455 56 256.749 74.9587 331.707 42.0722 0 0 0.447921 57 257.134 75.2102 332.344 42.5396 0 0 0.469414 58 257.521 75.4601 332.981 43.0038 0 0 0.490934 l 59 257.911 75.7086 333.619 43.4648 0 0 0.512481 l

60 258.302 75.9556 334.257 43.9228 0 0 0.534055 61 258.711 76.2012 334.912 44.3772 0 0.M31664 0.555M9 62 259.123 76.4452 335.568 44.8276 0 0.0861095 0.577249 63 259.538 76.6875 336.225 45.2742 0 0.128829 0.598856 64 259.956 76.9284 336.884 45.7169 0 0.171327 0.62047 65 260.377 77.1677 337.544 46.1558 0 0.213605 0.642092 66 260.8 77.4055 338.206 46.5911 0 0.255664 0.663721

( 67 261.226 77.6417 338.868 47.0228 0 0.297506 0.685357 68 261.655 77.87M 339.531 47.451 0 0.339132 0.707001 69 262.086 78.1097 340.196 47.8756 0 0.380539 0.728651 70 262.519 78.3415 340.861 48.2968 0 0.421733 0.750309 71 262.955 78.5718 341.527 48.7146 0 0.462714 0.771975 72 263.392 78.8007 342.193 49.1292 0 0.503485 0.793648 73 263.832 79.0281 342.861 49.5406 0 0.544M6 0.81533 l 74 264.274 79.2542 343.529 49.9488 0 0.584399 0.83702 75 264.719 79.4789 344.198 50.3538 0 0.624545 0.858718 76 265.165 79.7022 344.867 50.7558 0 0.664486 0.880424 77 265.613 79.9242 345.537 51.1548 0 0.7M223 0.902139 78 266.062 80.1448 346.207 51.5508 0 0.743756 0.923862 79 266.514 80.364 346.878 51.944 0 0.783091 0.945594

, 80 266.967 80.5818 347.548 52.3343 0 0.822236 0.967335

81 267.421 80.7983 348.219 52.722 0 0.861184 0.989085

! 82 267.877 81.0135 348.89 53.1067 0 0.899931 1.01084 83 268.334 81.2274 349.562 53.4888 0 0.93848 1.03261 l

l

NES&L DEPARTMENT CALCULATION SHEET '

'cc" ".

PREUM CCN NO. PAG E.,_. OF., _

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 cCN CONVERSION:

CCN No. CCN --

Subject Containment Pfr Analysis for Desian Basis LOCA Sheet No. 196 REV ORIGINATOR DATE IRE DATE REV CRIGINATOR DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 Table 8.3-2 DBA LOCA ENERGY DATA ENERGY (Million of BTUS)

ELAPSED TIME STEAM & SUMP TOTAL HEAT SINK HEAT CONT AIR (Seconds) AIR EXCHANGER SPRAY COOLER 84 268.793 81.44 350.233 53.8684 0 0.976846 1.05439 85 269.252 81.6515 350.9N 54.2454 0 1.01503 1.07618 86 269.713 81.8618 351.575 54.62 0 1.05304 1.09798 87 270.149 82.0975 352.246 54.9922 0 1.0909 1.1198 88 270.581 82.337 352.918 55.3621 0 1.12877 1.14163 89 271.008 82.5804 353.588 55.7296 0 1.16666 1.16347 90 271.441 82.8174 354.258 56.0952 0 1.20458 1.18533 91 271.874 83.0534 354.928 56.4587 0 1.24252 1.20721 92 272.306 83.2909 355.596 56.8203 0 1.28048 1.22911 93 272.743 83.522 356.265 57.18 0 1.31847 1.25102 94 273.178 83.7548 356.932 57.5379 0 1.35649 1.27296 95 273.616 83.9837 357.599 57.8938 0 1.39453 1.29491 96 274.049 84.2167 358.266 58.2479 0 1.43259 1.31688 97 274.485 84.446 358.931 58.6002 0 1.47068 1.33887 98 274.918 84.677 359.595 58.9506 0 1.50879 1.36088 99 275.355 84.9042 360.259 59.2993 0 1.54693 1.38291 100 275.789 85.1328 360.922 59.6462 0 1.58509 1.40496 105 277.975 86.2417 364.217 61.362 0 1.77635 1.51547 110 280.162 87.3285 367.491 63.0362 0 1.96817 1.62647 115 282.319 88.4198 370.739 64.6722 0 2.16068 1.73796 120 284.533 89.4276 373.961 66.271 0 2.35371 1.84993 125 286.729 90.4233 377.152 67.8364 0 2.54749 1.96239 130 288.872 91.4487 380.321 69.3616 0 2.74146 2.0752 135 291.031 92.4252 383.456 70.8568 0 2.9361 2.18851 140 293.179 93.3784 386.558 72.3232 0 3.13132 2.30228 145 295.29 94.3332 389.623 73.7625 0 3.32714 2.41653 150 297.424 95.2273 392.652 75.1762 0 3.52341 2.53125 155 299.488 96.1538 395.642 76.565 0 3.72034 2.64643 160 301.606 96.9872 398.594 77.9282 0 3.91777 2.76204 165 303.629 97.8752 401.505 79.2685 0 4.11582 2.87811 170 305.694 98.68 4M.374 80.5862 0 4.3143 2.99461

,_ ~ --

I

', NES&L DEPARTMENT

' \

CALCULATION SHEET 'cc" " > l PREUM. CCN No. PAGE_ _ O.r_

, Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

l Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 197

?

I REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE 4

1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

4 i

Table 8.3-2 l DBA LOCA ENERGY DATA ENERGY (Million of BTUS)

ELAPSED j TIME STEAM & SUMP TOTAL HEAT SINK HEAT CONT AIR i (Seconds) AIR EXCHANGER SPRAY COOLER t

i

175 307.683 99.5183 407.201 81.8824 0 4.51345 3.11155

. 180 309.681 100.305 409.985 83.1573 0 4.713 3.22892 185 311.648 101.075 412.724 84.4138 0 4.913 3.34674

] 190 313.623 101.794 415.417 85.6504 0 5.11351 3.46498 l 195 315.547 102.518 418.065 86.869 0 5.31459 3.58366 j 200 317.424 103.243 420.667 88.0686 0 5.51613 3.70275 j 210 321.148 104.593 425.74 90.4082 0 5.92055 3.94197 i 220 324.226 106.157 430.383 92.6697 0 6.32666 4.18252 l 230 325.957 107.806 433.763 94.84 0 6.73391 4.42399 A

240 326.744 109.499 436.242 96.9089 0 7.14182 4.66596 250 326.831 111.299 438.13 98.8737 0 7.54993 4.9081 1 260 326.563 113.067 439.63 100.739 0 7.95801 5.15022 f 270 326.034 114.855 440.889 102.512 0 8.36594 5.39222 1 280 325.352 116.64 441.992 104.198 i 0 8.77359 5.63401 l 290 324.584 118.424 443.008 105.8 % 0 9.1809 5.87554 l 300 323.775 120.191 443.966 107.342 0 9.58783 6.1168

! 310 322.953 121.949 444.902 108.814 0 9.99437 6.35775 320 322.127 123.712 445.839 110.228 0 10.4005 6.59841 330 321.31 125.462 446.772 111.589 0 10.8 % 3 6.83876 340 320.52 127.197 447.718 112.9 0 11.2116 7.07883 350 319.712 128.97 448.682 114.164 0 11.6165 7.31856 360 318.99 130.678 449.667 115.386 0 12.021 7.55799 370 318.303 132.373 450.675 116.568 0 12.4252 7.79716 380 317.65 134.057 451.707 117.713 0 12.829 8.0361 390 317.032 135.731 452.762 118.824 0 13.2325 8.2748 400 316.448 137.393 453.841 119.903 0 13.6357 8.51329 420 315.363 140.693 456.057 121.977 0 14.4414 8.98969 440 314.346 143.975 458.321 123.943 0 15.2461 9.46527 460 313.482 147.217 460.699 125.813 0 16.0498 9.94005 480 312.732 150.429 463.161 127.601 0 16.8527 10.4142 500 312.069 153.619 465.688 129.315 0 17.655 10.8877 i

l

i NES&L DEPARTMENT CALCULATION SHEET '

'oc" PRELIM ". CCN WO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CcN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 198 l

l REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE 1RE DATE R

! O R. Nakano 01/18/94 J. Elliott 01/20/94 5

Table 8.3-2 DBA LOCA ENERGY DATA ENERGY (Million of BTUS)

ELAPSED TIME STEAM & SUMP TOTAL HEAT SINK HEAT CONT AIR (Seconds) AIR EXCHANGER SPRAY COOLER 520 311.485 156.79 468.274 130.965 0 18.4567 11.3607 540 310.972 159.941 470.913 132.556 0 19.2579 11.8333 560 310.523 163.078 473.6 134.096 0 20.0586 12.3055 580 309.809 166.139 521.467 135.586 0 20.8589 12.7773 600 308.423 169.M 522.937 137.015 0 21.6581 13.2482 620 307.098 171.922 524.453 138.389 0 22.4559 13.7179 640 305.819 174.788 526.007 139.715 0 23.2524 14.1865 660 3M.584 177.639 527.593 141 0 24.M 77 14.654 680 303.388 180.476 529.209 142.246 0 24.8417 15.1205 700 302.226 183.31 530.852 143.457 0 25.6345 15.586 750 299.445 190.362 535.053 146.349 0 27.6119 16.7456 800 296.82 197.376 539.372 149.066 0 29.5823 17.8995 850 294.339 204.326 543.776 151.649 0 31.5462 19.M 79 900 292.016 211.204 548.256 154.114 0 33.504 20.1913 950 289.813 218.045 552.799 156.472 0 35.4559 21.3298 1000 287.693 224.851 557.396 158.734 0 37.4022 22.4638 1050 285.648 231.624 562.04 160.906 0 39.3431 23.5935 1100 283.588 238.385 566.705 163.015 - 0 41.28 24.72 1150 281.669 245.044 571.39 165.057 0 43.2146 25.8445 1200 279.761 251.747 576.111 167.022 0 45.1442 26.965 1250 277.904 258.422 580.86 168.916 0 47.0687 28.0816 1300 276.089 265.072 585.631 170.745 0 48.9884 29.1944 1350 274.31 271.699 590.417 172.516 0 50.9032 30.3033 1400 272.562 278.305 595.215 174.232 0 52.8133 31.4086 1450 270.805 284.933 600.023 175.896 0 54.7186 32.5101 1500 269.109 291.498 604.838 177.509 0 56.6187 33.6078 1550 267.43 298.M2 609.655 179.078 0 58.5143 34.7018 1600 265.766 304.568 614.473 180.603 0 60.4052 35.7924 i 1650 264.111 311.077 619.288 182.088 0 62.2916 36.8795 1700 262.465 317.569 624.098 183.533 0 64.1734 37.9632 1750 260.824 324.M4 628.904 184.941 0 66.0506 39.0435

NES&L DEPARTMENT CALCULATION SHEET '

'cc". CCN NO.

PRELIM PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 199 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94

• 5 Table 8.3-2 DBA LOCA ENERGY DATA ENERGY (Million of BTUS) ,

ELAPSED 1 TIME STEAM & SUMP TOTAL HEAT SINK HEAT CONT AIR (Seconds) AIR EXCHANGER SPRAY COOLER 1800 259.188 330.503 633.701 186.313 0 67.9233 40.1204 1850 257.562 336.946 638.489 187.651 0 69.7913 41.1938 '

1900 255.935 343.374 643.267 188.957 0 71.6547 42.2639 1950 254.314 349.784 648.036 190.223 0 73.5135 43.3305 2000 252.694 356.181 652.797 191.465 0 75.3677 44.3932 2050 251.093 362.561 657.562 192.669 0 77.2171 45.452 2100 249.523 368.928 662.34 193.847 0 79.0613 46.507 l 2150 247.982 375.28 667.131 195.001 0 80.9002 47.5582 2200 246.47 381.616 671.931 196.132 0 82.7338 48.6058 2250 244.981 387.954 676.741 197.24 0 84.5622 49.6498 2300 243.62 392.494 679.843 198.328 0.234518 86.3929 50.6902 l 2350 242.436 394.327 680.37 199.4 0.824514 88.2278 51.7275 2400 241.265 396.14 680.893 200.457 1.41975 90.0554 52.7618 2450 240.075 397.945 681.407 201.505 2.02011 91.8764 53.7935 2500 238.936 399.679 681.909 202.544 2.62555 93.6923 54.8235 2550 237.764 401.473 682.412 203.564 3.23608 95.5008 55.8505 2600 236.642 403.205 682.915 204.565 3.85165 97.3018 56.8744 2650 235.532 404.918 683.415 205.551 4.47216 99.0958 57.8954 2700 234.437 406.609 683.911 206.521 5.09755 100.883 58.9135 2750 233.354 408.282 684.403 207.478 5.72777 102.663 59.9289 2800 232.284 409.933 684.891 208.42 6.36276 104.436 60.9416 2850 231.226 411.564 685.373 209.348 7.00245 106.201 61.9515 2900 230.179 413.175 685.85 210.263 7.6468 107.959 62.9587 2950 229.143 414.768 686.322 211.166 8.29574 109.71 63.9633 3000 228.118 416.34 686.788 212.055 8.94921 111.454 64.9652 3500 218.277 431.041 691.124 220.281 15.7031 128.541 74.8484 4000 208.94 444.012 694.646 227.536 22.8603 144.943 84.462 4500 200.656 455.278 697.702 233.934 30.3728 160.66 93.8303

. 5000 193.552 465.224 700.556 239.674 38.1949 175.749 102.974 5500 187.382 473.863 703.072 244.918 46.2889 190.178 111.906 6000 181.773 481.689 705.134 249.789 54.6209 204.013 120.652

NES&L DEPARTMENT CALCULATION SHEET '

'cc" P5ELIM". CCM MO. PAG E._ OF,._

l Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCM NO. CCN ~

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 200 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94

? 5 1

1 Table 8.3-2 DBA LOCA ENERGY DATA 1

ENERGY (Milhon of BTUS) i ELAPSED I TIME STEAM & SUMP TOTAL HEAT SINK HEAT CONT AIR l

(Seconds) AIR EXCHANGER SPRAY COOLER l 1

\

6500 176.972 488.468 7 % .918 254.29 63.1602 217.321 129.24 7000 172.734 494.428 708.465 258.566 71.8797 230.177 137.683 7500 168.147 500.633 709.907 262.5 80.7676 242.614 145.991 8000 163.688 506.641 711.277 266.082 89.8427 254.582 154.133 8500 159.898 511.839 712.533 269.423 99.0738 266.148 162.121 9000 156.609 516.382 713.656 272.613 108.441 277.401 169.98 9500 153.615 520.391 714.$69 275.728 117.926 288.396 177.727 10000 150.913 523.947 715.317 278.716 127.516 299.169 185.382 20000 124.502 545.61 709.383 327.653 328.777 488.357 325.525 30000 110.265 536.541 685.352 361.686 529.516 652.491 450.1 40000 98.5195 522.543 659.007 385.003 721.46 802.057 563.273 50000 90.237 508.094 635.806 400.67 903.502 939.668 666.356 60000 83.5234 495.946 616.547 412.883 1076.5 1069.03 761.783 70000 78.7242 485.681 601.193 422.736 1242.13 1191.28 850.81 80000 75.0166 477.684 589.263 431.219 1401.83 1308.42 934.835 90000 66.6362 470.016 572.703 434.57 1556.71 1418.87 1013.47 100000 61.3853 456.674 553.735 430.539 17 M.13 1515.08 1081 200000 46.6452 413.213 494.453 412.879 2966.5 2295.14 1604.57 300000 40.8826 395.347 470.382 393.995 4063.47 2878.42 1986.26 400000 36.1727 379.273 449.148 369.018 5058.92 3326.83 2281.67 500000 33.7167 369.193 436.371 343.351 5970.61 3664.85 2512.45 600000 31.6987 360.764 425.721 318.998 6827.77 3926.29 2702.33 700000 30.4085 354.76 418.297 297.612 7639.83 4125.25 2858.26 800000 29.2779 349.41 411.699 278.778 8418.09 4275.86 2991.55 900000 28.4526 345.127 406.504 263.681 9165.98 4383.34 3105.85 1000000 27.7704 341.641 402.263 251.347 9890.8 4457.56 3204.17 1500000 25.4807 331.826 389.919 221.339 13297.7 4525.06 3536.81 2000000 24.9512 316.76 371.877 216.307 16337.9 4365.38 3721.13 2500000 24.7719 309.463 363.142 221.285 19036 4225.98 3868.74 3000000 24.6315 302.618 354.918 224.558 21528.3 4105.23 3997.09 3500000 24.4939 295.631 346.536 227.603 23812.9 4002.17 4105.66

NES&L DEPARTMENT CALCULATION SHEET '

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PRELIM PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

cCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA i

Sheet No. 201 l REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R O R. Nakano 01/18/94 J. Elliott 01/20/94

h 5

i

Table 8.3-2 DBA LOCA ENERGY DATA

, l ENERGY (Milbon of BTUS)

' ELAPSED TIME STEAM & SUMP TOTAL HEAT SINK HEAT CONT AIR (Seconds) AIR EXCHANGER SPRAY COOLER 1 4000000 24.2484 288.672 338.064 233.133 25887.1 3915.01 4193.65 l 4500000 24.1425 285.224 333.901 241.715 27802.2 3838.85 4265.89 5000050 24.1295 281.864 329.927 253.003 29617.6 3769.03 4328.14

{ 5500050 23.9819 278.593 325.905 266.896 31333.2 3705.69 4380.42 6000050 23.9257 275.229 321.878 283.525 32948.8 3648.55 4422.72 6500050 23.8722 273.499 319.786 302.851 34485.7 3596.11 4457 7000050 23.862 271.815 317.787 323.891 35974.1 3546.67 4486.17 7500000 23.8799 270.125 315.811 346.586 37413 3500.11 4510.21 i 8000000 23.8026 268.476 313.779 370.955 38797.3 3456.88 4529.1 8500050 23.7785 266.82 311.795 397.027 40133.6 3416.5 4542.61 9000050 23.6566 265.255 309.806 424.789 41421.8 3380.25 4550.05 9500050 23.6383 263.648 307.879 452.214 42665.8 3351.2 4550.3 10000000 23.6331 261.889 305.803 478.788 43856.7 3323.05 4550.3 i

4 i

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NES&L DEPARTMENT CALCULATION SHEET 'c""'

PRELIM. CCM NO. PAG 9_.,OF _,

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSloN:

CCN NO. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 202 l REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 E S

l

Table 8.3-3 i

DBA LOCA SURFACE TEMPERATURES FOR VARIOUS HEAT SINKS l ELAPSED HS 2 HS 8 HS 9 HS 15 HS 16 TIME ('F) (*F) (*F) ('F) (*F)

(Seconds)

! 0.05 118.46 119.99 120 119.84 119.99 5 159.66 128.7 183.71 157.11 135.89 l

10 195.62 149.55 226.26 194.2 180.77 l 15 219.14 175.87 246.65 220.62 228.11 20 225.65 198.14 250.63 230.68 254.68 I 30 218.12 212.12 243.81 232.65 263.87 40 216.97 216.6 240.54 237.53 265.23 50 222.03 221.31 242.89 244.65 266.12 60 226.93 225.97 245.69 250.75 267.53 70 230.86 230.14 247.45 255.23 268.58 80 234.34 233.77 249.01 258.77 269.13 90 237.51 236.99 250.59 261.67 269.61 100 240.54 239.95 252.38 264.26 270.39 150 252.64 251.88 260.36 273.21 275.53 200 261.46 260.67 266.98 279.19 280.58 250 266.73 266.5 270.47 282.46 283.27 j 300 268.7 268.77 271.05 282.76 283.21 350 269.52 269.59 271.08 282.75 283.03 400 269.94 269.96 271.09 282.71 282.79 500 270.37 270.35 271.1 282.54 282.62 600 270.54 270.59 271.04 282.32 282.37 700 269.91 269.99 270.19 282.02 281.95 800 269.21 269.29 269.39 281.59 281.29 900 268.51 268.6 268.64 281.09 280.52 l 1000 267.85 267.95 267.95 280.55 279.71 1100 267.41 267.44 267.57 279.99 278.87 1200 266.85 266.96 266.92 279.41 278.06

( 1300 266.23 266.35 266.28 278.81 277.24 1400 265.62 265.73 265.65 278.19 276.41 1500 264.98 265.11 265.01 277.56 275.58 f

1600 264.37 264.49 264.37 276.9 274.74 1700 263.74 263.87 263.74 276.24 273.91

i NES&L DEPARTMENT CALCULATION SHEET '

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PRELIM PAGE OF i Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

{ CCN NO. CCN -

} Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 203 f

1 REV ORIGINATOR DATE BRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

i 4 I \

1 I

{ Table 8.3-3 l 1

DBA LOCA SURFACE TEMPERATURES FOR VARIOUS HEAT l SINKS

ELAPSED HS 2 HS 8 HS 9 HS 15 HS 16 j TIME ('F) (*F) ('F) (*F) ('F) j (Seconds)

, 1800 263.11 263.24 263.1 275.56 273.08 i

1900 262.47 262.61 262.45 274.87 272.24 2000 261.76 261.91 261.71 274.16

{ 271.41 j 2100 261.02 261.17 260.96 273.45 270.58 2200 260.29 260.44 260.23 272.73 269.75 t 2300 259.59 259.74 259.53 272.01 268.92 2400 258.99 259.12 258.94 271.28 268.12 2500 258.53 258.66 258.51 270.58 267.35

? . 2600 257.97 258.11 257.94 269.87 266.61 2700 257.43 257.56 257.39 269.18 265.89 l

2800 256.89 257.02 256.85 268.48 265.18 2900 256.36 256.49 256.32 267.79 264.48 3000 255.84 255.97 255.8 267.11 263.8 l 6500 240.11 240.24 240.06 246.25 244.08

10000 230.07 230.2 230.05 234.26 233.49 b 20000 218.08 218.19 218.14 220.42 220.72

] 30000 210.94 211.06 210.99 212.63 212.9 40000 204.03 204.17 204.09 205.6 205.92

}

j 50000 198.66 198.8 198.74 199.9 200.17 l 60000 193.99 194.14 194.08 195.05 195.29 i 70000 190.25 190.41 190.37 191.27 191.46

! 80000 187.17 187.33 187.3 188.22 188.39 90000 180.84 181.24 180.78 181.15 180.79 3 100000 175.6 175.61 175.63 175.64 175.83 j 20C000 157.54 158.84 159.83 157.67 157.77 j 300000 148.63 151.58 152.55 148.75 148.8 400000 140.64 144.76 145.35 140.14 140.2 4

500000 135.43 139.64 139.88 134.95 135.05 1 600000 131.07 135.08 135.01 130.28 130.39

) 700000 127.74 131.44 131.17 126.9 127.19

! 800000 124.8 128,16 127.75 123.96 124.18 1

900000 122.35 125.38 124.89 121.69 121.85 1

NES&L DEPARTMENT CALCULATION SHEET 'cc" " '

PREUM. CCN NO. PAGE OF Projtet or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 204 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 h 5

Table 8.3-3 DBA LOCA SURFACE TEMPERATURES FOR VARIOUS HEAT

! SINKS i

4 1 ELAPSED HS 2 HS 8 HS 9 HS 15 HS 16 l TIME ('F) (*F) ('F) (*F) ('F)

] (Seconds) 1000000 120.29 123.01 122.48 119.57 119.85 1500000 114.53 116.06 115.58 114.1 114.62 2000000 112.33 113.32 113.21 112.35 112.87 2500000 111.6 112.63 112.5 111.79 112.36

3000000 111.11 112.11 112.09 111.33 111.93 3500000 110.6 111.52 111.52 110.79 111.45 4000000 110.11 110.95 110.95 110.27 110.9 4500000 109.81 110.63 110.65 110.01 110.61 5000050 109.53 110.33 110.34 109.72 110.31 5500050 109.28 110.05 110.07 109.45 110.04 6000050 109.01 109.74 109.75 109.14 109.71 6500050 108.84 109.58 109.59 108.99 109.57 7000050 108.7 109.41 109.44 108.83 109.39 7500000 108.54 109.25 109.23 108.67 109.24 8000000 108.43 109.13 109.12 108.53 109.08 8500050 108.29 108.97 108.97 108.38 108.92 9000050 108.18 108.86 108.85 108.28 108.85 9500050 108.07 108.77 108.75 108.15 108.73 10000000 108.07 108.77 108.75 108.15 108.73 i

l l

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l NES&L DEPARTMENT CALCULATION SHEET 'cc" "o ' l PRELIM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN No. CCN - I Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 205 l REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

5 8.3.2 Additional Outout Interoretation The drop in the total heat sink energy at later times results from the fact that the temperatures of the heat sinks that are not exposed to the sump drop below the initial temperature of 120 *F. Cooling a heat sink below the initial temperature of 120 F pmduces i a negative net heat transfer. However, after about lE6 seconds while the overall containment is cooling down, the heat sink energy is increasing due to energy transfer from the sump to the very large heat sinks exposed to the sump. The rest of the heat sinks are approximately at equilibrium with the containment vapor and therefore there is a very small amount of energy transfer from those heat sinks to the containment. The energy transfer into the heat sinks in contact with the sump dominates the small loss in energy of the other heat sinks, and thus there is an increase in the overall integrated heat sink energy.

The following boundary conditions are modeled for the various heat sinks in the containment.

All the 20 heat sinks modeled fallinto one of the 4 categories shown.

Ieft Boundary Right Boundary 1 vapor outside air 2 sump insulated 3 vapor vapor 4 vapor insulated To explain the increase in the total heat sink energy at later times, the temperature of one heat sink from each one of the above categories is shown in Table 8.3-4 for times greater than IE6. The representative heat sinks chosen are:

HS2 Containment Building Cylinder above grade-vapor /outside air HS 4 Basemat (other than reactor Basemat)-sump / insulated HS 8 Lined refueling canal walls-vapor / vapor l HS 9 Steam Generator companment walls, unlined refueling canal walls & other internal walls-vapor / insulated As can be seen from Table 8.3-4, the temperatures of HS2, HS8 and HS9 drop below the

! initial temperature of 120 F, while the temperature of HS4 is remains above 120 F . The heat sinks not in contact with the sump are approximately at equilibrium with the containment atmosphere which is below 120 F after about 12 days. The sump water tempemture remains above 120 *F for about 90 days, which, when combined with the slow rate of heat transfer modeled in the program, causes the large sump heat sinks to reach their i

maximum energy inventories after the heat sinks exposed to vapor have cooled back to near I

ambient conditions.

1 NES&L DEPARTMENT CALCULATION SHEET '

' o" ". CCN NO.

PRELIM PAGE OF i Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

j ccN NO. CCN -

i Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 206 i

1 i REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R

0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

i 5 4

i Table 8.3-4 i

SURFACE TEMPERATURES FOR HEAT SINKS t

f TIME HS2 HS4 HS8 HS9 l 1000000 120.29 138.6399 123.01 122.48 l 1500000 114.53 136.8313 116.06 115.58 2000000 112.33 134.3802 113.32 113.21 2500000 111.6 132.5316 112.63 112.5 3000000 111.11 130.9672 112.11 112.09

} 3500000 110.6 129.3869 111.52 111.52

! 4000000 110.11 127.7794 i

110.95 110.95 l 4500000 109.81 126.637 110.63 110.65 5000050 109.53 125.6979 110.33 110.34 l

j 5500050 109.28 124.8071 110.05 110.07 l 6000050 109.01 123.9316 109.74 109.75 6500050 108.84 123.2845 109.58 109.59 7000050 108.7 122.7371 109.41 109.44 7500000 108.54 122.2332 109.25 109.23 8000000 108.43 121.743 109.13 109.12 8500050 108.29 121.2604 108.97 108.97 9000050 108.18 120.7874 108.86 108.85 9500050 108.07 120.3222 108.77 108.75 10000000 108.07 120.3222 108.77 108.75

NES&L DEPARTMENT l

CALCULATION SHEET 'cc" "o '

{ PRELIM. CCN NO. PAGE_,_,OF__

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 cCN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 207

REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

f 1

5 l 8.4 MASS AND ENERGY BALANCES I

) To ensure masonableness of the results, mass and energy balances are performed for a j selection of times from the COPATTA Code output.

I

a. Table 8.4-1 presents the mass balance for the DBA LOCA

b. Table 8.4-2 presents the energy balance for the DBA LOCA.

i i A review of these tables indicates that the COPATTA Code mass and energy inventories i rarely differ by more than 0.01 percent. This fact verifies that the mass and energy input

{ parameters have been properly conserved within the COPATTA Code logic.

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NES&L DEPARTMENT CALCULATION SHEET 'cc" ".CCNWo.

PRELIM PAGE_0F ,

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 208 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 8

Table 8.4-1 (Sheet 1 of 3) 1 MASS BALANCE FOR DBA LOCA l

MASS BALANCE El_APSED TIME SINCE BREAK (seconds) 17" 22* 60'" 210'0 240*

1 PROGRAM INPUTS'"

J j Initial Steam 6.809 6.809 6.809 6.809 6.809 Initial Air 163.198 163.198 163.198 163.198 163.198 Break Flow (CS 301) 503.460 512.704 535.855 633.447 647.015 4

ECCS Spillage (CS 601) 0.0 0.0 39.803 144.583 156.936 CS Flow (CS 801) 0.0 0.0 0.0 33.417 40.100 i S1 Flow (CS 801) 0.0 0.0 0.0 0.0 0.0 Reactor Vessel Water

• 0.0 0.0 0.0 0.0 0.0 Total Program Input 673.47 682.71 745.67 981.45 1,014.06 PROGRAM INVENTORY (*

Steam 220.246 216.477 215.189 274.366 279.394

Air 163.198 163.198 163.198 163.198 163,198 Sump 290.023 303.033 367.284 543.915 571.491 I

Reactor Vessel 0.0 0.0 0.0 0.0 0.0 Total Program Inventory 673.47 682.71 745.67 981.48 1,014.08 i

Difference In Totals

• with 0.00 0.00 0.00 0.03 0.02 l respect to Program Inputs

$ Percent Difference with respect 0.00 % 0.00 % 0.00 % 0.00 % 0.00 %

to Program Inputs i

4

NES&L DEPARTMENT l

j CALCULATION SHEET 'ccd " '

PRELIM. CCR MO. PAG E_., OF_,,,,

l Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 209 REV ORIGINATOR DATE

)

IRE DATE REV ORIGINATOR DATE 1RE DATE R )

O R. Nakano 01/18/94 J. Elliott 01/20/94 l 5

Table 8.4-1 (Sheet 2 of 3)

MASS BALANCE FOR DBA LOCA MASS BALANCE EI.APSED TIME SINCE BREAK (seconds) 580* 2300* IE50 1E7*

]

PROGRAM INPUTS

• I Initial Steam 6.809 6.809 6.809 6.809 Initial Air 163.198 163.198 163.198 163.198 I Break Flow (CS 301) 697.265 697.265 697.265 697.265 ECCS Spillage (CS 601) 396.333 396.333 396.333 396.333 '

CS Flow (CS 801) 115.844 494.564 494.564 494.564 SI Flow (CS 801) 5.200 1478.54 1478.54 1478.54 Reactor Vessel Water

• 168 168 168 168 Total Program Input 1,552.65 3,404.71 3,404.71 3,404.71 PROGRAM INVENTORY

• Steam 264.084 204.788 40.927 7.431 Air 163.198 163.198 163.198 163.198 Sump 957.432 2867.82 3027.04 3057.99 Reactor Vessel 167.956 168.930 173.554 179.812 Total Program Inventory 1,552.67 3,404.74 3,404.72 3,408.43 l

i

~

l Difference In Totals

• with 0.02 0.03 0.01 3.72 respect to Program Inputs Percent Difference with respect 0.00 % 0.00 % 0.00 % 0.11 %

to Program Inputs t

4 4

NES&L DEPARTMENT CALCULATION SHEET '" o '

PRELIM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVER$10N:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 210 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE R E

0 R. NakanO 01/18/94 J. Elliott 01/20/94 4

Table 8.4-1 (Sheet 3 of 3)

MASS BALANCE FOR DBA LOCA Notes:

(a) Water, Steam and Air masses are presented in 1000 pound increments.

(b) 1.68E5 lbm (1182 Btu /lbm) of water appear at the start of the reactor water vessel calculations at 573.273 seconds.

(c) The time of 17 seconds corresponds to the peak pressure before the end of blowdown phase.

(d) The time of 22 seconds corresponds to the end of blowdown phase.

(e) The time of 60 seconds corresponds to the establishment of a fully developed containment spray injection phase flow rate of 1612 gallons / minute.

(f) The time of 210 seconds corresponds to the nearest output time step for the end of the core reflood phase at 211.1 seconds.

(g) The time of 240 seconds corresponds to the nearest output time step for the occurrence of the pressure peak of 58.9 psig at 241 seconds.

(h) The time of 580 seconds corresponds to the nearest output time step for the i end of CE data at the end of the froth period at 573.273 seconds. i (i) The time of 2300 seconds corresponds to the nearest output time step for the l start of recirculation at 2280 seconds.

(j) The time of IE5 seconds corresponds to the nearest output time step for the i end of the first day (86400 seconds) after the accident.  ;

(k) The time of IE7 seconds corresponds to the end of the code run.

I i

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NES&L DEPARTMENT I CALCULATION SHEET 'cc" "o ' i PRELIM. CCN No. PAGE OF ]

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:  !

CCN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 211 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

S Table 8.4-2 (Sheet 1 of 3)

ENERGY BALANCE FOR DBA LOCA l

4 ENERGY BALANCE ELAPSED TIME SINCE BREAK (seconds) 17* 22* 60"" 210' 240'a PROGRAM INPUTS)

Initial Water Vapor / Air 23.326 23.326 23.326 23.326 23.326 Break Flow (CS 301) 315.548 320.462 350.551 477.419 493.604  !

ECCS Spillage (CS 601) 0.0 0.0 4.410 15.570 16.652 CS Flow (CS 801) 0.0 0.0 0.0 2.272 2.727 SI Flow (CS 801) 0.0 0.0 0.0 0.0 0.0 RCS sensible Heat (CS 201) 0.122 0.158 0.431 1.507 1.514 Core Decay Heat (CS 101) 0.0 0.0 0.0 0.0 0.0 Air Cooler Removal (CS 5) -0.0 -0.0 -0.534 -3.942 -4.666 Total Program Input 339.00 343.95 378.18 516.15 533.16 1

i f PROGRAM INVENTORYt  !

j Steam 240.551 236.372 237.256 300.617 306.167 j Air 20.300 20.265 21.N 6 20.530 20.576 Cont. Atmosphere (Steam + Air) 260.85 256.64 258.30 321.15 326.74 j l

l Sump 62.574 65.805 75.956 1M.593 109.499

! Reactor Vessel 0.0 0.0 0.0 0.0 0.0 3

Structural Heat Sinks 15.569 21.500 43.923 90.482 96.909 l Recirculation HX 0.0 0.0 0.0 0.0 0.0 t

j Total Program loventory 338.99 343.95 378.18 516.23 533.15 l Difference In Totals

• with -0.01 0.00 0.00 0.08 -0.01 respect to Program Inputs Percent Difference with respect 0.00 % 0.00 % 0.00 % 0.02 % 0.00 %

to Program Inputs 1

4

NES&L DEPARTMENT CALCULATION SHEET 'cc" No '

PRELIM. CCM NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 212 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 E R. Nakano 01/18/94 J. Elliott 01/20/94 5

i Table 8.4-2 (Sheet 2 of 3)

ENERGY BALANCE FOR DBA LOCA l

. ENERGY BALANCE ELAPSED TIME SINCE BREAK (seconds) l j 580S' 2300* IESS 1E7W PROGRAM INPUTS")

l Initial Water Vapor / Air 68.854 68.854 68.854 68.854 l

l Break Flow (CS 301) 553.076 553.076 553.076 553.076 ECCS Spillage (CS 601) 37.590 37.590 37.590 37.590 CS Flow (CS 801) 7.877 33.627 33.627 33.627 l

SI Flow (CS 801) 0.354 100.530 100.530 100.530 l RCS sensible Heat (CS 201) 1.535 7.572 302.742 302.742 l

l Core Decay Heat (CS 101) 0.548 127.850 2666.14 48060.3 1

Air Cooler Removal (CS 5) -12.777 -50.690 -1081.00 -4550.30 Total Program Input 657.06 878.41 2,681.56 44,6 % .42 PROGRAM INVEITTORY

i Steam 289.178 223.488 43.672 7.776 l

Air 20.631 20.132 17.714 15.857 Cont. Atmosphere (Steam + Air) 309.81 243.62 61.39 23.63 Sump 166.139 392.494 456.674 261.889 i Reactor Vessel 45.519 43.729 35.676 20.280 l

Structural Heat Sinks 135.586 198.328 430.539 478.788 Recirculation HX 0.0 0.235 17M.13 43856.7 Total Program Inventory 657.05 878.41 2,688.41 44,641.29 Difference In Totals"' with -0.01 0.00 6.85 34.87 respect to Program Inputs i Percent Dtfference with respect 0.00 % 0.00 % 0.26 % 0.08 %

to Program Inputs l

l NES&L DEPARTMENT CALCULATION SHEET 'c"" '

PRELIM. CCN NO. PAGE OF Project or DCP/MMP_ SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN No. CCN --

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 213 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE BRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

S l

l Table 8.4-2 (Sheet 3 of 3)

ENERGY BALANCE FOR DBA LOCA l Notes:

(a) All energy inputs and inventories are presented in one million BTU increments. Reference temperatures for energy inventories are 32 F for water and steam, 0 *R for air, and 120 'F (initial containment

temperature) for stmetural heat sinks.

l (b) The time of 17 seconds corresponds to the peak pressure before the end I t

of blowdown phase.

(c) The time of 22 seconds corresponds to the end of blowdown phase. l (d) The time of 60 seconds corresponds to the establishment of a fully developed containment spray injection phase flow rate of 1612 gallons / minute.

(e) The time of 210 seconds corresponds to the nearest output time step for the end of the core reflood phase at 211.1 seconds.

l (f) The time of 240 seconds corresponds to the nearest output time step for l the occurrence of the pressure peak of 58.9 psig at 241 seconds.

l (g) The time of 580 seconds corresponds to the nearest output time step for l

l the end of CE data at the end of the froth period at 573.273 seconds.

l (h) The time of 2300 seconds corresponds to the nearest output time step l

for the start of recirculation at 2280 seconds.

(i) The time of IE5 seconds corresponds to the nearest output time step for the end of the first day (86400 seconds) after the accident.

(j) The time of IE7 seconds corresponds to the end of the code run.

l l

t i,

l l

L__

NES&L DEPARTMENT CALCULATION SHEET "

eREudCN No. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 214 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 '

4 i

9 COPIFJS OF MISCELLANEOUS REFERENCES COPY OF REFERENCE 6.2.e

[2] From: PAUL BARBOUR at NESL310/25/93 9:18AM (5241 bytes: 97 In)

To: MARK DRUCKER at NESL2

Subject:

Containment Spray Assessment Forwarded From: TOM YACKLE at NESL5 7/30/92 9:33AM (5049 bytes: 97 In)

To: GARY S JOHNSON at NESL3, BERNIE CARLISLE at NESL4 l cc: MALCOLM ANDERSON, PAUL BARBOUR at NESL3, BILL FLOURNOY at NESL3, RICHARD GOLD at NESL4

Subject:

Containment Spray Assessment 4

-Message Contents Comment below. Tom 1

1 Paul Barbour and I discussed this effect of reduced spray on the PT analyses and what effect the lowered spray flow might have. In the process, we discovemd some conflicting assumptions that will be good news for the LOCA impact and might mean that it will not be l

necessary to modify the spray orifices to increase spray flow.

Here's the scoop:

~

The design basis LOCA mass energies are based on maximum SI flows I which require two HPSI's and two LPSI's and all 12 penetration MOV's to be functional. The generic assumption for the PT analysis assumes loss of one train of containment cooling (spray and contamment coolers). The only common mode single failure that can produce the tmin failure in the containment cooling systems is power related.

Further examination of the power supplies indicates that:

DG or 4 KV bus failure kills all pumps.

i 480 V bus failure kills not only the CS and CCS MOV's but two of the LPSI MOV's and four HPSI MOV's.

NES&L DEPARTMENT CALCULATION SHEET 'cc" " 3 PREUM. CCN NO. PAGE__ oF__

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSloN:

CCN No. CCN -

6ubject Containment P/T Analysis for Desian Basis LOCA Sheet No. 215 TV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R

( R. Nakano 01/18/94 J. Elliott 01/20/94 y S

Therefore, these two assumptions are dependent on two independant not one common single failure to produce these conditions (CS failure and a CCS related failure) which exceeds the design basis requin:ments. The limiting single failure for the LOCA PT assessment can credit the addition of one train of containment coolers (crediting both trains) when considering the flows from a single train of REDUCED spray flow. This is inherantly OK since two trains of coolers is 100% of required cooling by design. Two trains of CS and one cooler train is inherantly OK as well relative to the existing analysis.

MSLB PT analysis:

This analysis will still be bounded by a train failure assumption for limiting single failure. The peak temperature turns immediately after initiation of spmy when only the presence of spmy not the flow rate is critical. The spray header fill time calculation needs to be reviewed to determine the ramifications of lower spray delivery on the initiation time of spray. This review is in progress. We have initiated a new calculation basis for MSLB review that calculates a worst case delivery rate to the containment at the original design pressure of 60 psig with degraded pumps acceptable to the existing IST data (7.3 %

degradation). If the MSLB PT assessment remains acceptable, does not cause an EQ impacting change in the PT profiles and does not remove all margin for future pmblems, it seems reasonable to leave the existing orifices alone. The containment spray calculation could go ahead and complete the analysis that shows as acceptable the removal of the spray system orifices even though we have no plans to change them now. Then that future NCR condition (perhaps a new PT analysis) could have its solution already analyzed.

NCR or No NCR:

I'm not sure the second option requires an NCR or not. It's my understanding that until we have an unanalyzed change there is no requirement for an NCR. Technically we would have to take the new spray data and incorporate it into our design information related to the Fr analyses. Can this be handled through NEDOTRAK via the CS

1 NES&L DEPARTMENT CALCULATION SHEET 'cc" "o '

PRELIM. CCW MO. PAGE_ OF_

Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 CCN CONVERSION:

CCN NO. CCN -

Subject Containment P/T Analvsis for Desian Basis LOCA Sheet No. 216 REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE R 0 R. Nakano 01/18/94 J. Elliott 01/20/94 "

5 I vote for NEDOTRAK via the calc. cross reference. We have tried this in other examples and it seems to work. On the output side state the impact and

)

have the other DM provide a log number. This covers your organization and l they are on the hook fmm that point on. Of course, if NCR conditions are

{

satisfied, then so be it. Tom I

cales cross reference showing a change required in the pts knowing the results will be acceptable or would an NCR be required? I would l

like to get a concensus from both DM's on the final approach to be '

taken in regards to this issue so that I can be prepared to make the proper response when the calc is about to be issued.

l If you have any questions or input that might change our direction (holes in our approach), give me a call at 51265 so that the groups can stay on the path that pmvides a satisfactory conclusion to this important issue.

Thanks, GSJ I

NES&L DEPARTMENT CALCULATION SHEET 'c""'

PRELIM. CCN NO. PAGE OF Project or DCP/MMP SONGS Units 2 & 3 Calc. No. N-4080-026 ccN CONVERSION:

ccN No. CCN -

Subject Containment P/T Analysis for Desian Basis LOCA Sheet No. 217 at 217 4

REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE R O R. Nakano 01/18/94 J. Elliott 01/20/94 5

I APPENDIX A (COPATTA Code I/O File Information)

The COPATTA Code input file is presented in Section 8 (page 171) of this calculation.

The COPA7TA Code output file is included on Microfiche. The output file name and date

, are as follows:

1 FILE TITLE: LOCA WITH LOSS OF OFFSITE POWER. I RUNDATE: 1-13-94 RUNTIME: 11:19:09 LAST SHEET: Page 562 4

d I

j

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i l

i l

Letter from S.D. Root to A.J. Thiel dated March 24, 1995," Review of ESF-Integrated Load Sequence Testing Design Response Time Requirements - Units 2 Cycle 8 San Onofre Nuclear Generating Station, Units 2&3"

(

l 4 March 24, 1995 MR. A. J. THIEL

SUBJECT:

Review of ESF Integrated Load Sequence Testing Design Response Time Requirements - Unit 2 Cycle 8 San Onofre Nuclear Generating Station, Units 2&3

REFERENCES:

A. Technical Specification Surveillances 4.8.1.1.2.d.7 and 4.8.1.1.2.d.13 B. Procedure S023-3-3.12 C. UFSAR Table 8.3-1, " List of Loads Supplied by Class 1E AC System" D. Design Calculation E4C-082 Rev 1, CCN N3: " System Dynamic voltages During Design Basis Accident" E. NCR 93070031 Disposition Step 2: System Impact Analysis, Time Delay in Automatic Sequencing of ESF Loads, by K. P. Wells, dated January 31, 1995 F. Technical Specification Table 3.3-5, ESF Response Times G. E-Mail from A. J. Eckhart to S. Root, et al.,

dated March 20, 1995, subject: "AGASTAT Relay Concern for Sequential DG Loading" (attached)

H. Design Calculations N-4080-026 Supplement A Rev 0 (Design Basis LOCA containment pressure-temperature analysis), and N-4080-027 Supplements A and B Rev 0 (Design Basis MSLB containment pressure-temperature analysis) .

I. Design Change Package (DCP) 2E3-2060.00SE, Attachment 1A: " System Impact Analysis for Enhanced Degraded Voltage Protection Scheme" I. PURPOSE The purpose of this memorandum is to review the design response .*

tima requirements for integrated Engineered Safety Feature (ESF) load sequencing applicable to Unit 2 Cycle 8. These requirements j .

1 i

e

=< +-

a

. g.

March 24, 1995 i will be used to assess operability and reportability of any ESF

' load sequence timing relays that fail to meet the +/-10% 21 interval requirement of the current Technical Specifications i

i (Reference A), during Reference B testing.

i II.

l RESULTS - APPLICABLE TO UNIT 2 CYCLE 8 i

j ESF load sequence timing relays that operate within +/-2.5 seconds-for the LPSI and SWC pumps, -2.5/+7.4 seconds for the AFW i

pump, -2.5/+17 seconds for the Emergency Chillor, and within +/-

! 10% of settina for other loads, can be considered to satisfy their design response time requirements with no further evaluation. When evaluated on a case-by-case basis, this j

4 tolerance may be extended subject to the limitations described in Paragraph IV.D below.

i 1

III. BACKGROUND i

Sequencing of ESF loads onto the safety related electrical i

busses at San Onofre Units 2 and 3 is controlled by i

' individual sequence timing relays for each load, rather than

' a master load sequence controller. The load sequence timing relays begin timing when there is a safety Injection i

Actuation Signal (SIAS) and 4kV bus voltage is available.

As described in Reference C, the permanently connected loads (eg. 480V motor control centers) and HPSI pump are connected 4 to the 4kV bus with no delay, followed by the LPSI pump at

+5 seconds, the containment spray pump at +10 seconds, the Component Cooling Water (CCW) pump at +15 seconds, and the Saltwater Cooling pump at +20 seconds.

! Some HVAC loads (fans) are sequenced to the 480V bus at +5 seconds. Permissives are provided to the 4kV Auxiliary Feedwater (AFW) pump at +30 seconds, and to the Emergency Chiller at +35 seconds (via the AFW pump controls). Actual AFW pump start and Emergency chiller start may occur after these permissives, due to other signals needed (ie, EFAS for.

the AFW

Chiller) pump,

. Theand internal design program specified timer foron tolerance thethe Emergency individual i

load sequence timing relays is +/-10% of setting. The interval between sequenced loads depends on the operation of their two independent timing relays.

9 IV. . DISCUSSION

~

{' -

A. INTERVAL REQUIREMENTS j -

2 2 -

1 March 24, 1995 The Reference A requirements on timing relay interval were intended to prevent . overlap of adjacent ESF load groups during sequencing to the bus. Overlap of adjacent ESF load groups was presumed to result in unacceptable bus voltage and diesel. generator transient conditions.in the absence of analysis and test to the contrary. Additionally, analyses of ESF not beensystem interactions with out-of-sequence loading had performed.

Electrical system performance has now been analyzed for complete overlap of adjacent load groups (except SWC and AFW), per Reference D. -Reference D demonstrates that acceptable voltage is maintained with an ESF load sequence timing tolerance of +/-2.5 seconds for the most limiting conditions, with either offsite power or the diesel generator. Additionally, ESF system interactions, for load group overlap resulting from a load sequence timing tolerance of +/~2.5 seconds, have now been evaluated by Reference E and also shown to be acceptable. However, this is not the limiting condition for some loads, as discussed below.

' The Reference D analysis included concurrent start of the AFW pump (start permissive at nominal time of +30 seconds) and the emergency chiller (start permissive at nominal time of +35 seconds). Since these two systems have no process interactions, and the emergency chiller start time is controlled by the internal program timer to +52 (+/-21) seconds, the tolerance on the AFW pump'and emergency chiller sequence timing relays could be extended to within the respective safety analysis limits.  :

B. SAFETY ANALYSIS REQUIREMENTS Overall response time requirements are specified for each ESF system in Reference F. The specified response times include ESF actuation signal response, logic delays, and diesel generator start / load delays, in addition to the valve stroke times or pump response time, as applicable. For pumps, a response time of 0.4' seconds is assumed for breaker closing, and 4 seconds for acceleration to rated speed (at sustained 75% bus voltage, consistent with the original i equipment specification requirements). Both system valve response and pump response are governed by the same overall response time limit, unless separately specified.

A review was conducted with Nuclear Fuels Analysis to verify which systems have an assumed safety analysis response which would be affected by a 10% delay in sequencing of the pump.

This review included the Reload Analysis Groundrules, which 3

m e

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March 24, 1995 governs analysis of future operating cycles. As discussed in Reference G, the only systems for-which the assumed response would be affected by a 10% delay in pump sequencin were verified to be the containment spray and CCW systems, g which are governed by the containment pressure analyses.

This is consistent with the existing requirements of Reference F, which specifies a separate pump response time-requirement for only these two systems. The containment pressure analyses (Reference H) specifically account for the 10% tolerance on start time of the containment Spray and CCW pumps, although a shorter than 4 second acceleration time is assumed. The shorter allowed acceleration time is considered acceptable based on the actual bus voltage recovery predicted by Reference D for both offsite (degraded  ;

grid) and diesel generator bus supplies. l Reference G also indicated that a delay'substantially larger than 10% would be acceptable for the LPSI pump, from which flow is credited only after the safety injection tanks have discharged and the LPSI valves are fully open. Per Reference F, an overall LPSI response of 41.2 seconds is assumed on SIAS, including 11.2 seconds.for'the signal and diesel generator, which leaves 30 seconds for the sequence timing relay and pump, while the valves are opening. The full +/-2.5 second tolerance on the LPSI pump sequence timing relay, supported by the electrical analysis, would therefore as well.

be acceptable from a system performance standpoint The SWC pump is not specifically addressed in the safety analyses. Since the SWC system is the heat sink for the CCW system, however, SWC system response must support the CCW system.

Due'to the thermal mass of the combined CCW and SWC systems, a 2.5 second delay in SWC pump start time will not affect this function. Therefore, the full +/-2.5 second tolerance on the SWC pump sequenced timing relay, supported by the electrical analysis, would be acceptable from a system performance standpoint as well.

The AFW pump is not specifically addressed in the safety analyses. Only an overall response time is assumed. The overall time is limited to 52.7 seconds per Reference F, which diesel includes generator. 0.9 seconds for EFAS and 10 seconds for the Including the required 4.4 seconds for breaker close and pump acceleration, a maximum of 37.4 seconds would be permitted for pump start time. A minimum start time of 27.5 seconds is assumed in Reference D. Thus, a tolerance of -2.5/+7.4 seconds is

,. pump start permissive timing relay. permitted for the AFW

, 4 l

l

. . . y

. . . __ ~ . ~ ._- .- - - . . . - _ _ _ _ _ _ _

4

{ Harch 24, 1995 t

The Emergency Chiller is not specifically addressed in the safety analyses. . However, the system response would be

unaffected as long as the load sequence start permissive is provided before the internal program timer tries to start

the chiller. The nominal program timer setting is 52 seconds. A minimum start time of 32.5 seconds is assumed in Reference D. Thus, a tolerance of -2.5/+17 seconds is permitted for the Emergency Chiller start permissive timing

relay. ,

' Therefore, a load sequence timing relay setting tolerance of

+/-2.5 seconds for the LPSI and SWC pumps, -2.5/+7.4 seconds e

for the AFW pump, -2.5/+17 seconds for the Emergency Chiller

and +/-10% of setting for the other loads, is supported by

the safety analyses.

C. DEGRADED GRID VOLTAGE REQUIREMENTS 1

, The Degraded Grid Voltage with SIAS Signal (DGVSS) was

installed by DCP 2&3-2060.00SE, and will be placed in service following NRC approval of the applicable Technical Specification change. Reference I, paragraph 1A.8.2.2,

already evaluated potential start, stop and restart of i equipment in the two affected load groups (at +0 and +5

seconds) during a degraded grid voltage transient.

Acceptable results were shown for both the case in which a LPSI pump starts and does not start before DGVSS actuation.

Therefore, based on the sequence of events shown in the l figure of Reference I, a tolerance of +/-2.5 seconds on the

LPSI pump start would be acceptable.

l D. LIMITING REQUIREMENTS k

Based on the discussion in sections IV.A through C above,  ;

the limiting requirement for load sequence timing relays is set by the electrical and safety analyses, which support a  !

j tolerance of +/-2.5 seconds for the LPSI and SWC pumps,

) +7.4/-2.5 seconds for the AFW pump, +17.4/-2.5 seconds for the Emergency Chiller, and +/-10% of setting for the other Additional margins in the existing analyses should loads.

not be applied to extend'the allowable tolerance of the sequence timing relays, without a careful evaluation of the integrated effects and specific accounting of the differences between test conditions and limiting design  ;

basis conditions. For example:

o CCW and Containment Spray pump response times can D21 be considered independently, because both affect the

m. same containment pressure events.

5 b

=mg

J i i March 24, 1995 o

CCW and Containment Spray pump response times can nat

' be extended based on additional margin to containment pressure limits, due to the potential' impact on the containment ILRT and the Environmental Qualification assumptions for in-containment equipment.

o Margin between the time for actual pump breaker close and acceleration to rated speed, vs. the assumed time of 4.4 seconds, should nst be used, because the 3 I

sequence times are also applicable to no loss of offsita power conditions (which are more limiting for bus voltage and acceleration time than when the bus is energized from the diesel generator).

o Margin between the time for actual diesel generator plus output breaker response, and the assumed time of  ;

l 10 seconds, can n21 be used, because the sequence times are also applicable to no loss of offsite power conditions (in which the diesel delay is not applicable).

o Case-by-case exceptions require concurrence of NEDO Electrical and Nuclear Fuels Analysis that additional delays are acceptable from electrical design and safety analysis standpoints.

Should you have any questions concerning the above or require further clarification, please call me at PAX 82078.

S. D. ROOT

- c:\netwp51\esf test.rev cc: T. R. YacEle A. J. Brough S. D. Root A. J. Eckhart K. P. Wells K. J. Johnson P. Barbour f ho J. Winslow asD.iStickney. ,

R. Neal /f<M V2f/vf C. M. Diamond J. Keelin 40 9pqqb N.'Hunstein F. Santa na Files: IPRE (SO23-8.3) $,mehk @7(Ut

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4 i

a System Impact Analysis [for NCR 93070031] by Kirk Wells, dated January 31, 1995 l

l l

- M W % o'TOOh\

, System impact Analysis Time Delay in Automatic Sequencing of ESF Loads

1. PURPOSE A system dynamic voltage analysis has been performed to verify the capability of the electrical auxiliary system when ESF (Engineered Safety Feature) loads are started out of sequence. This analysis is being performed to verify that starting in the sequence analyzed in the dynamic voltage study, E4C-082, revision 1 (table 5.1), will not create a

! new or unanalyzed functional impact on the ESF systems potentially affected by the delay.

i This system impact analysis is being performed to satisfy disposition step #2 of NCR 93070031. The revised dynamic voltage study, E4C-082 (revision 1), this system j impact analysis, and the non conformance report (NCR) evaluate a change to the basis

of technical specification 4.8.1.1.2.d.13. The technical specification currently limits the relay timing to a percentage of the interval between load blocks.

l II. RESULTS There are no previously unanticipated system interactions created by the starting sequence analyzed in design calculation E4C-082 (revision 1) table 5.1.

Ill. ASSUMPTIONS 1.0 Only one HPSI Pump per train receives an automatic start signal (P017 or P018 for train A, and P018 or P019 for train B). Starting two HPSI pumps on one train inadvertently during ESF sequencing is not postulated for the Agastat time delay scenario. The kirk key interlock selector switch ensures that starting the swing pump manually would only overload one of two safety injection trains.

2.0 The LPSI pumps are tripped on RAS (recirculation actuation signal). Failure of one LPSI pump to trip on RAS would affect only one of the safety injection /SDC trains.

IV. DESIGN INPUTS

1. The load grouping for various ESF loads is defined in Table 2.1.2 through 2.1.5 of E4C-088 revision 1.

2. The load schedule in table 5.1 of E40-082, revision 1 provides the timing of the delayed starting sequence.

1 -

_ -_--,_e-.. - - , . - , - - _ - , - . . -- - .- v - r- -

V. METHODOLOGY This analysis is an event specific single failure analysis which uses the guidance of the -

SONGS design standard for Single Faliure Analysis (TS-123-106, revision O). Loads which may start currently will be identified for each load group from design input. Flow l requirements (le NPSHA), potential flow diversions, and the availability of supporting l system components and equipment, will be verified for each load group potentially impacted by the longer time delay.

i \/l. REFERENCES 1.0 System Dynamic Voltage Analysis E4C-082, revision 1.

2.0 SONGS 2/3 UFSAR, revision 10.

3.0 Design Calculation M-12.2; titled: " Safeguard Pumps NPSH".

4.0 Design Calculation M12.1D, titled: "NPSH of ESF Pumps".

5.0 System Dynamic Voltage Analysis E4C-088, revision 1.

, 6.0 Non Conformance Report 93070031 Vll. NOMENCLATURE CS Containment Spray HPSI High Pressure Safety injection LPSI Low Pressure Safety injection NPSH Net Positive Suction Head is the pressure margin at a pump suction. This quantity is typically used to determine if the pump suction path will ensure safe operation.

2 .

. Vill. ANALYSIS

! A review of the load schedule (design input #2) shows that the potential Agastat relay time delay only affects equipment started in adjacent load groups. In each load group the safety related (1 E) 480 volt motor control centers (MCCs) are all started in load j

group #1 which is not affected by the Agastat delay, therefore, interactions between systems occur when major components (pumps, fans, etc) could be started together.

There are very few components affected by the potential time delay in back to back load groupings except for interactions between load groups 1 and 2. Interactions in

, load group 1 & 2 will be determined by use of a table. The other load group interactions will be analyzed separately.

i i

Load Group 1 & 2:

Potential load group interactions were determined by performing a table based analysis

.on Unit 2 load group A. A review of the loading calculations shows that similar tables are not necessary for the other train or Unit 3 because the ESF systems group assignment and logic are the same. Table Vill-1 shows that there are no unacceptable interactions if load group 1 & 2 start out of sequence or concurrently within the time delay defined in design input #2.

i i

O 3 .

Table Vill-1 .

Starting Load Group 1 & 2 Concurrently Load Group A Tag Equipment Supporting System Components Effect on System Comments Number Descripkm ,

4.16 KV 0; M-;:-- Bus 2A04 PO17 Train A HPSI Pump 1. Motor operated suchon and discharge No effect. NPSH from Design calc valves. M12.1d sheet 5.

Load Group 1 1. Pump can startin recirc or (no Sme delay, pump 2. Common suchon Ene (HPSI, LPSI & CS against open system MOVs start P &ID 40112A

• starts at time zero) from RWST) inload group #1 from 480V MCC .

t Bus 2BE with no time delay. Elementary 30643

2. Suflicient NPSH avaanNm to operate at three pumps concurrendy from RWST or sump.

3. HPSI start logic does not have an Agastat relay.

t 4

_.--_.-m.__.________.__-___m___,____ _ _ _ __ _ _ _ , _ _ _

i Tag Equipment Supporting System Components Effect on System Comments

• l Number Description .

l P015 Train A LPSI Pump 1) Motor operated suction and deduwge No effect. NPSH from Design cele -

l 1 valves. M12.1d sheet 5.

Load Group 2 1. Pump can start in redre or  ;

i  ;

2) Common auction Ene (HPSI, LPSI, & againstopensystem. MOVsstart P &ID 401128 CS from RWST) inload group 1 from 480V MCC bus 2BE witi no time delay. C.;. .a i30641 i 2. Suflicient NPSH aveEmble to i operate a5 gree pumps concurrently from RWST or sump.

3. Flow retumed to RWST unII ,

recire or SDC entry. System nEed, ,

no dvenson of flow to start.

480V Switchgear Bus 2004  ;

P191 Swing Train Charging Pookive esplacement pumpswith No effect. Assumed to trip and  ;

Pump pesaton dampeners. MuIiple sucton and restart, no time delay in Load Group 1 decharge paths prowded. Flow path is Concurrent starting and stoppingis startlogic.

normaEy not isolated by elecine F_;.d a normalmode of operadon for E/D 30748 .

valves. this system.

, P190 Train A Charging Posieve deplacement pumpswith No effect. No time delay in startlogic. ,

Pump pulsadon dampeners. Mulhple suction and E/D 30747 l Leed Group 1 decharge paths provided. Flow path is Concummt starting and stoppingis  ;

normaEy not itoleted by elecinc F ...d a normal mode of operaton for valves. this system. ,

A071 & Containment Dome Venestion fan wth no cooing water or No effect. E/D 31244 A074 Air Recirc Fan and other mudary equipment. E/D 31246 Stoney Recirc Fan No system interaction except ,

Load Group 2 electricalloadng.

a e

5

_ . _ . _ _ _ _ _ . . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ m -

Tag Equipment Suppor9ng System Components Effect on System Comments Number Descripton E399 & Contamment CCWisolation valves & CCW pumps must No effect. Delaytime assumptions E401 Emergency Fans restart to provide cooing. from table UFSAR table Waterisolation valves begin to 6.2-30 (page 62-219) open whee fan is starting. Fan can operate without fut flow for longer than delay from Agostat inaccuracy (by design).

480V Switchgear Bus 2BD E654, E.. -. ecp Diesel These are support system components for No effect. E654- 30345-2 E655, GeneratorAudaries the emergency desel generator. E655- 30345-2 EG002, Space heaters, khe AE of these components are EG002 30345-1 P996, oE heaters, fuel restartedinload group 1 whidi P996 30345-3 P997, transfer pumps, etc. does not have any Agostat delay. P997 30345-3 P093, P093 30324 P096 Nothing on Bus 2BD startsinload P096 30327 group 2, no addeonel from Agostat delay.

480V MCC 2 BRA AE load group i equipment. Includes A None. AE loads start in load group ESF system pumps 480V MCC 2BE Group Motor Operated Valves. #1 with no time delay. desegned with sufficient 480V MCC 2BY NPSH mergm to start against open system (refer to 4kV bus entries)

~

6

Load Group 2 & 3:

If load groups 2 & 3 started simultaneously or in reverse order a CS (containment spray) pump and a LPSI pump could start together.

No effect:  ;

I

1. ESF Pumps sharing common suction (HPSI, LPSI, CS) can start in recirc or i against open system. MOVs start in load group 1 from 480V MCC 2BE,28Y, and 2 BRA with no time delay. (NPSH from Design calc M12.1d sheet 5) l l 2. Sufficient NPSH available to operate all three pumps concurrently from RWST or l

sump.

3. Flow retumed to RWST until SDC entry or recirculation (RAS). System filled, no diversion of flow to start.

4. The ESF pump runup is time long enough that actual starting overlaps during automatic sequencing. Sequencing only mitigates severe concurrent " inrush" peaks and electrical insurges.

Load Group 3 & 4:.

If load group 3 & 4 started simultaneously or in reverse order, a CCW (component cooling water) pump and a Containment Spray pump could be started simultaneously.  !

No Effect:

1) These pumps, CCW and LPSI, do not share a common discharge or suction path.

The interconnection between LPSI and other systems is discussed in UFSAR 6.3.

2) The CCW system provides motor and seal cooling for the LPSI pump. The motor is designed to operate for a limited time without cooling. As discussed in UFSAR section 6.3.2.2.2, while the CCW cooling water supply will prolong the service life of the pump seal, the seal is designed for operation with the SCS fluid. A delay in providing cooling will not significantly impact the capability of the pump motor or the seal to perform the required functions. No potential radioactive releases will occur because the leakage past a damaged LPSI pump seal can be isolated without entering the area.

I l

l 7 ,

= ,-r - ._ _ m._-r_, _ _

Load Group 4 & 5:

If load group 4 & 5 started simultaneously or in reverse order, a CCW (component cooling water) pump and two saltwater cooling pumps could be started simultaneously.

No effect:

1) These pumps, CCW and Saltwater cooling, do not share a common discharge or suction path. The SWC system pump discharge valves fail open assuring a constant supply of cooling water. .

I l

Load Group 7 & 8:  ;

if load group 7 & 8 started simultaneously or in reverse order, a motor driven auxiliary feed water pump and the auxiliary building emergency chiller could be started simultaneously.

No effect:

{

1) These systems, Auxiliary Feedwater and Auxiliary Building emergency chillers, do not share a common discharge or suction flow path. The systems are located remote from each other.

Summary: 1 There are no previously unanticipated system interactions created by the starting sequence analyzed in design calculation E4C-082 (revision 1) table 5.1.

Prepared By: h(0 Kirk Wells i ~f/'l{

Reviewed By  % g e Steve Root kpw C:\WP\EDG.DGV 8 .

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