ML20092H973

Westinghouse ECCS Evaluation Model for Analysis of CE-NSSS & Results of Large & Small Break LOCA Analyses for Fort Calhoun Unit 1

ML20092H973
Person / Time
Site:	Fort Calhoun
Issue date:	01/13/1992
From:	Akers J, Schrader K, Matt Young WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML19344C364	List: ML20092H719 ML20092H738 ML20092H973
References
WCAP-13195, NUDOCS 9202240015
Download: ML20092H973 (121)

Text

/

4 e ._

- ~

'.: ). ,' '.

s ,

c

% i. '. . . '. '.

~

_ E, '

. . - '.. *. i p t, ' .- ,

,. ., . - ., ..' in

., - e. s

., . .y .

s

. . "si * -f* ' ..

- .... .;e- . . . ,, ;t'^' ' .. s ., - ' *

. - . a -,:* ' .;

',1

.i '. b.-

m- -

' s . .

l

.. , j ... }p. , .'; l7

, _,J... . . ,

. . . , ., . g .

- .

.- c '- '. ,- ., - . . . . - ,j < '

f.

.i' =.

• I p ' ,4

- ' = '- I

. . ' ' . . - , . 3 .. y - . .e, y. .T- 1

,, a3

,- 'l

. . ...,4 L

,..p

<N.?.

's.

.~ . '.. - ' ,'

• .+*.,.. . .:

.r . ,l

'I

~ '

.,.':o.. .

' .; . ' ,. .., . , . ._,. ...* J.

• y ,. ..-.

. g q, ', . - ,

4,,,

, - . _ ' -l . .-}.: ' . _' ,. _ ' - ..' * . ' '.s,. 2 ..

9... *' .. .

-} ;- gj ry' , . , . L.. e, s

..-..(. t

< . _.s .*; . ' =  :.... r : 'W

'*. T - .? s.

. ' .: ~. , . "  % .; <' ' .: '..- .;; ' , . .: '..;' /: .. i .. * . s,

'7, i. .y.., * . q*,.

.  ;, y.g. '. -, ,,: . j' ,

• - , .'; - .,i ,- .. .

, , j* - , .. .. -' ., . - - .g... ,- , . - ._,..e %. . * , , - t. ' $,

• 4 . ,

... l

.',. '. ; .g , , ' v. . , . , , - ., , , . ..a ( . , , , . .,. .. <

7-

. . , , . ..;*  :. ,, ;'.., ,...5, i 4.

. , y ' p:.

.*', . ,~ m, { 'e ' .. '  :..,.. . ', '..:.,*

t'

.s . .N*.*'.'

.m.,,3. ' :., , . ' ',K _ +. : ..( . ,L* ..iy.;....,.....,

,b- */ c. " D ,,y, ,.

,. [. ';,/ [g* ;f:;* wf -;' *- .7.' . _ ' . . . - !, .. li ?-'- ' ';, a -:

, '. .* . .i , e' . , .

y

. ' . .,g. ,

w

. ** ..+s.y .Q. .- ' . - '...of'.'..-

..v. * '. . , g.'. " .4 . g =. - . . r

. l *s l O. ,*, i

. l . ; *' . . ,&_," h_.&_&' . gj.,

. .. - d ,

r . A.,.,  ;

&'q ..S,-g g '&.t ... h.. d$:h_d_ 6., .- &. Ol, :g. 3 l',..

'

_ . . . , , ' , .,j.

. : f.fia- .. . _.,,.' -. .-,l , . ' . . ,y,.

. &. _ D&g...g &I ,$6 ,

.. ., f4 . . . , .

.. . . . ?

' , . ..4 . . %.y,.,,

. .. i f f . .. .

T'._:.'.- . :l l , *;' .., .

..\*r y _ a_.-l' ;

• ll . . .'

fiy.,.'..

" . .; ..(,.a . . .+

.'r . 3 ,,

. . .,3.. .

' M' g ' .; n : . ' . . . .

d . f f .E .'-, , hjg ' '

. <. , .' .  ; ' 3 i

.  ? . ^. ...y g .

i-

.' ..,y..

• *g.. , e .

, .-._ '. l'.s

. , . ,p,

.. I

] w.:. .-c . . c . ,. ~ . s.., , e o .

..

., , .. . .,. i N; * .

'.-7; -. -.;-. .: 7. . . . ; . y s .3 x g. g.3 . . _9- - . .- y. .. ,, ,y

,. . cr ~ ;<. , e

.,. 1- n- '. . i, . ' .. .. . . .; .,$yl l ,; y. ',p: . . r c -,' ',

.yy

,. -... ..*. .... .-., .':.. . . 4 c.?

lrs . f : , . , . ~.'.* .

• 1 .( , '. _; s '. '. , ' . .

. ' ' . b , &.. . . .

&.f*,

,'y"' l. . _ .<, :. , . ,

i..,. . 4,l, .'.y g , ., ,  ; sy: d4

,l ,'.s **

,-l y9*W ' ; . .- ' .'. .'. .\ ll - l $

.. 3. -

.s, ,_' . -

.*z'.,.. *

.,.s y g- .

- 3

p' . -.' .. .& ;q ! -S l, .

4. y 's . . '; ' . , ... .. ,. ,*

.k y.'

• -',:..*,...;,.- ,, ,.l y'- ').. ,.y 7 -. .; - . , .. -

.L,.,*.Q...'~*7"-

i

'

• _Z- .j

-8

.,,j,.3.*-, . .  ;,',t

' - i, ?

."[',  !

.q . . *?

., ij

,j ' . ; *#. f, ' .

'. .,e-s.

, , ; .~ . .p ., ,'.,,(1, ..- . .

' ;*f.

• .-'.;.* ,. . *

• feP . .- , ,_ , f4 '

,.a ..I.

g'.. .-; * .

9. #} .

' ..; , ,s-

, , , .p .'.'. -( .. .*.i . [f- *, .. ' ' , . .#,--. ,.-. ip .; ..i. -.

.. . . , i. W.,4 ' ./ .- . .. '.

-; .. g.,f',..,.

4'

. . , 's-

.%.,,.'..'. ,- i % p +l.j.

.., .l' , ,(* . -<c J,g.y.

• gs,,,,g 8.,p

. - ,. . .:-. . - .y . .. c, . . e .. v u q; ; - .. . .  :.. ~ . . .. .

, , . :,3, s n g , jW* .Q'ft .{sf,; r '.,y. ';. gg.q;'

.%,...,, . ?,_ . j, . . :.: ,. . . . .,.

-4,.

s.. f y A . _. .4: ,:_;.) \ _';..

., ,_ a: ~' -

.; -_. , ,  ; , ' a.*'.'. ,,

Vl . ..-*.

- . . . . _ ...; * . ',' - * ;' , ; ' -- ,;..,,, * . . . .p i,. , sa

j. y . . . . , ['f . , .,. 3,' .. ,

_ ,, ,:> ,!. . . '%.%( - , ,-}- ' f.,: . ' p :( ~"'i.3 - ,,- ., _ .; ,'

.?

.'.,.,7

. ,, '4: y ., ' _. : . . , f  ?'.

'*',.,,.'.._a

h'

..  :, . . #'.'.'.*,/' .- ..f-

.- .. s*;

• . . . - s  ?-

. ; .:., _._ ,.'s ., - '%. -.. ,. .;. * . .. .,. ., , . , ..,...,8 s,..

,.. ' . . _.,...s * . ' _. ;' .;. ., . ;, .', * * .. *_- .,,2 %V

-* ,: , . ... .., 44. . . ' , , . . .. - .. . . ..

t , . .: . .

74 f g.

e  ;

.s -

. ,. . . . .. ..,;. . . .. . m, + . . s . s. u: .e.

, . , ..',. ,-,,t.-. . .,' ;s,.. l',.,.i-..?.. , - . . ..

,  : . , . - 1. a

.., , ' . . , . . . . *... .. . . . . . .....,..s

.. i . ..- -

- , , . y..e

.' ..,o. . . . . .).,. ' "Q. :. ' .  :- ..  : ,.,;.' * . .x b -.,,. ..

,, .e

,,,:,,.6 g._

. .' ,, , ' . y *. . . . j- - ' .,..r-

. . ;[ 't - y[ ,' J .

'7

..s, - .

-a e j ' , , .,.; : ' .

• " _, ,,* *,( .' ,..Ec * '. ,, . 'll, .' -

h K., '. . .., .,' ,. [.' ' ' . J, ** @ .

,['+. y', , \ ,' . t * . .- * ' , . . ' '. '. .Y ' '

i', ., ) # '.."3

=...-"...i.'r.... '- . ,* , ' ' ' . . ". ' ,',..fe . . y i.. *'

?. .U I 3'. -.,.,,* ' -

..,.,.....,,...7,

.,...o,'.,.;..;,O.".','

j .

"'.p..,,.,..,.s.,

.. - ,,,,'.,.;' ,,.i,,,,.. .. . .., ,. * , ' , ,.',y'.,,.i 1*

, ' , , ' , , ' , , ,. g

.-sg,. .;.4. . . ' , . ' ' ',

' . ' '. g. . . .. ' . ;-' .- *'.

.a.

- ' e

,..y -

g,'. ..*%+ ._'.. ..

--g I.' ; , . . . ,,, ,-

' _ . ' . , . ..- *; 6 '.,- - .,., ;..'  :% .

' . . .' .' . ... .f*f . ..,- u

,7 d,..

.; g , , ,/

w

. - , - e.

..-- , y *, , , ; . ., . *.. .., . ,.

g. '* = , . . , . . . ,,-,s.,  ; , ,, . , .*, . . ;

. . , . . f - . ..- , ...... ,, . .. s g: ,

=~

,-- .., ,, t,g ,gy . -. ,. . . ,,;9.,.. . ,, ,,, , ,. ,. - ' _- ,,,, '

. . .i

,g, ,

• _ ,

a

,N.- *

',. o. . .

, 6- -

,- - g .A. ,.'.,...,,.p.7..f2. 1 . . . . .. ., .:2 .. ., .. , ,, ,

. , , , j .;. . ' . ,

.v c - . .- + .- .,. , ...

. . , ', -,*..,,.q- .l.,, .4 : -.~ ;..,,,,,,.7 ,,...., , - . . .' : ,, . _ . . _

. . . . r ,

*. . ,

. ' .' .n

.., . . . . , - < e

. . . . ' , . - 5.,,

.- . ;~-  % ._ r -

' . y . , . _. ..

. M.nj.a.T M. Nnge.5,. W d.y.*H.q N,Mv:p. . , . : ,,... Q.

..c,....

eb u:W.&..h4s

...,.. h. yQ*. .M.. ,

. @. . ,. %. . s%. $.

. + . . .r-m~.mWn~ @':w:m;+.a 4 . .,2

.. .. . . .v. y ; s:... .'. , . ',. ;

~. ;i,". .-c~- ,' -

.:< .  : i1 :s : . .. .. ., .  :> w. .; -

~

w . '.: . -

. . . ' ~ =* . ;,:^

%y . :e:

' T :...r: -

. . . J.- .

?. , P._ 'f.m.L' i.c~. . .2.e'.,.a.q: g, "..

~..pn.p,..'.'..'.y .' .w., 3 . n,,

..+, e. . .. ,, ,.: . . ?= ... .;.' .

c.,,.,,. ,- .

f .. .; 8\.,::

s .

... . - ., y. .

.. : .. i . . , -

s ,

• . F ,-; , ~ . . ,  : . .

.2 4:

.s.  :. . . . . ..- _. ,:,

..:/. .: b.:r._.,.. 7.:. .L ~.j  : .4 Y.' . <;e:. c, ' ;t

• .s ' .v , ; .. : i r

, ... ' :& -. '.,  ? ', , ,y '

. L ._. ... e: ' m. . ,z. ,. ...W . . .;:y . . . . \,.-:" ,. .

.h.- .

r . ..., . . . .

..

.: . . . ,. + ~

. : - . - s..

.. . .. . . . . ..- , . . .. .... . .. a. .3:..

.. r:. .. .x...

a. ......

g .- . . . . . .. w. . .

.;. .d.

l / .

,. c..,., ..

m4;,..a. 1 . ==

./,, x.y n . - , ; ;. , . j._ .

. .n. c.., .  :. .:. x w

._ . . p . . .; :. ., .,; e ., 7..;a.y.g.,z ;. .. . r .;,.y. m

, .  : .;.u w .,,

. ( . w. w . : . 34 f;,; . { *.

_ . ( , _ ; _. }.';:. , :' ' ' ': ; s .3. :s

' _' : ;.[ ';. l, '

,.c..>Q;-[..pl,h, m... . ,. qp ., .m.y ,& m.:( .. g , g q g,.},.3,__x$ Q

, ;_.;., y .,::: ,. 3: q'gQ+;

r g ;; .

. .. a, . , ., . ..;-

3 y ..

o- ',.

t.s ..:., c . -

. .. e (s . .<, a. .v. m...? g . : .7 ,,o. s : .c - .,

%., .,.. g....yc.y.c, y, m

e'

[ ,_ $ [ w% $w $w$w%o h n n ,e m

in Westinghouse Class 3 WCAP-13195 NRC Presentation Westinghouse ECCS Evaluation Model for Analysis of a CE-NSSS and Results of Large and Small Break Loss of Coolant _

Accident Analyses for Fort Calhoun Unit 1 January 1992 J. J. Akers K. J. Schrader APPROVED:/ 2kt'5 ft 'Y/ ear Safetynalysis Nucl aYoung7 tianager .

T Westinghouse Electric Corpc, ration Nuclear and Advanced Technology Division Engineering Technology Department P. O. Box 355 Pittsburgh, PA 15230-0355

• 1992 WESTINGHOUSE ELECTRIC CORPORATION ALL RIGHTS RESERVED

e illlE0DE1103 This WCAP contains the material :) resented by J. J. Akers and K. J.

Schrader of Westinghouse to Fran( Orr and Steve Blume of the Nuclear Regulatory Commission on January 13, 1992 at the Nuclear Regulatory Commission Offices at White Flint. This information was provided to the Nuclear Regulatory Commission to aid them in their review of WCAP-13027-P, " Westinghouse ECCS Evaluation Model for !.nalysis of CE-NSSS." and to present the fort Calhoun Unit I large and small break Loss of Coolant Accident (LOCA) analyses results. K. C.

Holthaus, W. O. Weber, and T. G. Therkildsen of Omaha Public Power District (OPPD) also attended the presentation and requested that this material be formally documented.

+

)

h I .; kEI -

1 I I

i/ [ ] -

\ \

/ '8

, WESTINGHOUSE LAEGE BREAK t AND SMALL BREAK LOSS-0F-COOLANT ACCIDENT (LOCA)

ANALYSIS METHODS FOR ANALYSIS OF A COMBUSTION ENGINEERING NSSS ANALYSIS OF LARGE AND SMALL BREAK LOCA FOR FORT CALHOUN UNIT 1 4

PRESENTATION TO THE NUCLEAR REGULATORY COMMISSION JANUARY 13, 1992

!\  ?

I

!  !\ '

/

l

- i  ;

..v---- - - , , , ,

,~na.--e...,,,4,.m,_ nnw ,.n ,, ,_ n,,,. ,w,_,.,,_.,, ,,_

W l

( hl]

l

!, PRESENTATION OUTLINE l

/

1. WESTINGHOUSE EVALUATION MODELS AND METHODOLOGY FOR ANALYSl5 0F A CE N$$$

4. BACKGROUND B. CE FEATURES (OlffERENCES) 9 l C. LARGE BREAK LOCA

l. LARGE BREAK EM - LICENSING - APPROVALS

a. The Westinghouse Evaluation Models

b. The BART for CE EM

2. GENE $15 0F THE MODEL - MODIFICATION $ TO THE WESTINGHOUSE EM

a. Modifications to Westinghouse versions

b. Modifications to existing models for analysis of a CE NS$$

c. Modificationt to other codes  !

d. Implementation of modeling features

e. Applicability of the model

3. APPLICATION OF THE MODEL

a. Break spectrum

b. ' Major

• sensitivity studies

c. Other sensitivities 9

4 f

a

\ /

x

?

\ j xf  !

I I$MALLBREAKLOCA T* l f j

1. $ MALL BREAK EM - LICENSING - APPROYALS i 2. GENE 515 0F THE H0 DEL - MODIFICATIONS TO THE WESTINGHO i

s. Modt?1 cations to Westinghouse versions

b. Modifications and implementation for analysis of a CE NS$$ )

c. Applicability of the modes  ;

t

3. APPLICATION OF THE MODEL l

a. Break spectrum j

! b. ' Major

• sensitivity studies

c. Other sensitivities E. REGULATORY COMPLIANCE

1. 10 CFR $0, Appendix K / NUREG-0737

2. 10 CfR 50.46 l

~

F. CONCLUS10H$

l i

t l

5 /

i x /  !

l i

~7 \ -

l

• We= -

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

l

11. APPLICATION OF THE MODELS TO FORT CALHOUN UNIT !

A. APPROACH

1. METHOD OF ANALYS!$ / RELATIONSHIP TO MODEL GENES 15

2. COLLECTION OF FORT CALHOUN-SPECIFIC DATA B. LARGE BREAK LOCA

1. ASSUMPTIONS

2. SPECTRUM ANALYS!$ RESULTS

3. SENSITIVITY RESULTS i

4. ACCEPTABILITY OF RESULTS L. SMALL BREM. LOCA

?. ASSUMPTIONS

2. SPECTRUM ANALYSIS RESULTS ,

I

3. SENSITIVITY RESULTS

4. ACCEPTABILITY OF RESULTS D. CONCLUSIONS 111. DISCUS $10N / QUESTIONS / COMMENTS

/

/ <

> ,/

j \ , / __

l l

~ -

l t

l l

h I I K

j l __ __

t

/

I WESTINGHOUSE EVALUATION MODELS  :

AND METHODOLOGY FOR THE ANALYSIS OF A CE NSSS t

l I

i 3.

\. ,/

I

.. j

\_ ,/ j L_.._.__._.____._____..____.___________._._._._.._

h I ,

(, h, l{

l

/

f BACXGR0M Q N_u N

/

WHAT INSPIRED THE MODEL DEVELOPMENT -

0 OPPD ACCEPTED A CONTRACT FOR THE WESTINGHOUSE COMMERCIAL NUCLEAR PUEL '

DIVISION TO PROVIDE "CE-TYPE" FUEL FOR FORT  !

CALHOUN UNIT 1. LARGE AND SMALL BREAK ANALYSIS IS INCLUDED IN THE FUEL CONTRACT.

HISTORY / EXPERIENCE O WESTINGHOUSE HAS PREVIOUSLY PROVIDED LARGE AND SMALL BREAK LOCA ANALYSES FOR ANOTHER WESTINGHOUSE-FUELED CE NSSS - MILLSTONE 2 LARGE BREAK - 1981 EM FOR CE WCAP-9528, SER CONTAINED IN WCAP-9220-P-A, REV. I (PROP.)

SMALL BREAK - NOTRUMP EM FOR CE WCAP-10054-P-A, ADDENDUM 1 (PROP.)

i k /^ i l \  !

'N ,/ ,

@ M MGCl l

I If X i

\ L*1~'

/ 'l

/ BACKGR0_UND N '

, j WHY NOT USE THE EXISTING APPROVED MODELS?

l 0 FOR SMALL BREAK LOCA THE NOTRUMP EM REPRESENTS THE LATEST WESTINGHOUSE TECHNOLOGY ADEQUATE MARGIN CONTRACT CALLS FOR USE OF THE NOTRUMP EM NOTRUMP WAS USED!

O FOR LARGE BREAK LOCA MORE RECENT TECHNOLOGY IS AVAILABLE IN THE BART EM AND THE BASH EM BART PROVIDES MORE MARGIN THAN THE 81 EM BASH PROVIDES MORE MARGIN THAN THEBARTEM CONTRACT CALLS FOR USE OF THE BASH EM I

i  !

i i I\ fl  :

lx j, x , .

@ m MLC

/ -

BACKGR01tND

/

ORIGINAL G0AL i

PROVIDE LICENSABLE LARGE AND SMALL BREAK LOCA ANALYSES l FOR FORT CALHOUN USING THE MOST RECENT, l

! APPROVED APPENDIX K METHODS i MODIFIED FOR THE ANALYSIS OF A CE NSSS AND APPLICABLF. TO FT. CALHOUN 1

1 x z o l

b I

b. b I i

,/

f CE_EEAIURES._IDIEEERENCES1 3_ _l t  :

l 0 LOOP LAYOUT  :

CE DESIGN FEATURES 2 CROSS OVER LEGS, 2 REACTOR COOLANT PUMPS & 2 COLD LEGS FOR EACH STEAM GENERATOR. COLD LEG IS SMALLER AND HOT LEG IS LARGER THAN W DESIGN. LOOP SEAL ELEVATION IS HIGHER THAN W DESIGN.

O CEA DESIGN ASSORTMENT OF CEA GEOMETRIES IN A GIVEN PLANT.

O UH BYPASS / UH TEMPERATURE NO DESIGN COOLING FLOW TO THE UPPER HEAD.

O LOWER PLENUM DESIGN CE DESIGN FEATURE PLOW SKIRT & RELATIVELY "0 PEN" LP VOLUME i

h ,

l\

,x

/ i

\ ,_

l

@ l[((l]

CLEEAIUJ1ES_(DIEEERERCES1 N l

/ X

, o CORE SHROUD BYPASS WHILE AN "UPFLOW" DESIGN, TYPES AND RELATIVE RI.SISTANCES OF FLOW PATHS ARE DIFFERENT THAN M DESIGN.

o REACTOR C00lNNT PUMPS SIMILAR, BUT SMALLER.

o STEAM GENERATOR INLET N0ZZLE ANGLE THE CE DESIGN FEATURES A GREATER ANGLE OF INCLINATION.

o SI / ACCUMULATOR N0ZZLE ANGLE CE DESIGN INJECTION ANGLES DIFFER FROM THOSE USED IN A W DESIGNED NSSS.

l 1

l l

L l l 1

x zi i

\_ ji L - - - - -

I CE FEATURES _(DIEEEREKES1 O SAFETY INJECTION TANK PRESSURE l

CE PASSIVE INJECTION MAY BE AT A I SIGNIFICANTLY LOWER PRESSURE.

O FUEL ASSEMBLY DESIGN "CE-TYPE" FUEL FEATURES LARGE GUIDE THIMBLES AND INSTRUMENTATION TUBES AND FEWER THIMBLES. GRID PARAMETERS VARY SLIGHTL'f.

O FUEL R0D / PELLET STACK ,

l THE "CE-TYPE" FUEL RADIAL CLADDING DIMENSIONS AND ROD PLENUM VOLUMES DIFFER FROM THE TYPICAL W DESIGNS. THE ACTIVE CORE REGION IS OFTEN SHORTER THAN FOR A W PLANT.

l l

l 1 l

l l

!i\ix 4

/ i

'\ - .

7

-~

j

@ m dLC p

/' 'S LARGE BREAK LOCA I

i 9

, /

';s l l N / / i,

, ,-' l

@ m GLC l 7 N l

1.ARGE_AREAK_EM - LLCINSlNG - AEER0YALS .

THE WESTINGHOUSE MODELS -

81 EM, BART EM, BASH EM 0 THE 1981 EVALUATION MODEL -

WCAP-9220-P-A, REv. I (PROP.)

• SATAN-VI SYSTEM BLOWDOWN WCAP-8302 (PROP.), SER IN WCAP-8471-P-A (PROP.)

• WREFLOOD REFILL /REFLOOD HYDRAULICS WCAP-8170 (PROP.), SER IN WCAP-8471-P-A (PROP.)

• C0C0 CONTAINMENT RESPONSE WCAP-8327 (PROP.), SER IN WCAP-8471-P-A (PROP.)

• LOCTA-IV Roo HEAT-UP WCAP-8301 (PROP.), SER IN WCAP-8471-P-A (PROP.)

'xi\

i

/

j

/

l

h 1 ,.

k, k, I ,

l 3

LARGE BREAK EM - LIffNSING - APlROYALS O THE 1981 EVALUATION MODEL WITH BART (BART EM)

WCAP-9561-P-A (PROP. )

SATAN-VI SYSTEM BLOWDOWN

• WREFLOOD REFILL /REFLOOD HYDRAULICS (INTERIM REFLOOD)

AMENDED BY WCAP-9561-P-A (PROP.) AND WCAP-9561-P-A, ADDENDUM 3 (PROP.)

C0C0 CONTAINMENT RESPONSE ,

• BART HEAT TRANSFER COEFF.

WCAP-9561-P-A (PROP. )

ADDENDUM 2 (NON-PROP.)

WCAP-9561-NP-A, WCAP-9561-P-A, ADDENDUM(PROP.)

3

• LOCTA-IV ROD HEAT-UP AMENDED BY WCAP-9561-P-A, ADDENDUM 3 (PROP.)

A l N / 4 l '\ /i j

@ l ((l i I

LARGLBREAK_EM - LICENSING - AEER0YALS O THE 1981 EVALUATION MODEL WITH BA.RT/ BASH (BASH EM)

WCAP-10266-P-A, REV. 2 (PROP.)

SATAN-VI SYSTEM BLOWDOWN WREFLOOD REFILL / CONT. M&E VERSION COMPATIBLE WITH BART (INTERIM)

C0C0 CONTAINMENT RESPONSE

• BASH REFLOOD HYDRAULICS WCAP-10266-P-A, REV. 2 (PROP.)

• LOCBART HTC / ROD HEAT-UP (SYNTHESIS OF BART AND LOCTA-IV FROM THE BART EM WITH MINOR MODIFICATIONS)

WCAP-10266-P-A, REv. 2 (PROP.)

ORIGINAL G0AL: MODIFY THE BASH EM FOR THE i ANALYSIS OF A CE NSSS, APPLICABLE TO FT. CALHOUN i

l l \ -

/

i\ 1 N .

j

- _)

) @ l[((l]

l f .

/

/ IliE_BART FOR_CI_EM 4

i 1

! THE 1981 + BART FOR CE NSSS LARGE BREAK LOCA ECCS EVALUATION MODEL

\

! (BART FOR CE EM) i i

i i

i

?

I I

, I\ )

\\ /

i /

/j!'

l _ I 1

, e I j i 4 SLOW 88 l

' l ttflLL tirtooc s l t08 gong!

/ I L M1Af f }

/

r ,

LALCluf t! Not 400. Wattllt 800.

/ #f AlllAILt 800 IWCurtats, ILorM&l. AND CALC A&ltl NOT $00. W Altri 4D0. AW edi RitmLT 800 f tAttkAtttis, ptocut!.

htAT f t.AA11tt (CtFFl!!!rtl.

L MT atatmL1 MAS ftL0t!TT a

OuALiff. As Pittaut! '

tataa I CAlcaAft1105. (Dal, Am MT 48DeLT FLW!O toelflous FLeelm uit i

Catt IILf1 f tMPiufVal g tant Pettsung 8All. [hthtf t!LU.it ht3 toe ffloal NLAI TU45#tt (AUFitl TNT!

Ilfft taufallemrt At te of 6Lamenes l

CALCULATES LUILL. FL880!W LAft AND M11. (mtest I aritair gAft Faun htJ DJtle tuloop (natricoc).

win nae re nte _j t.ALcEAf ts tarfalasuntf Patssai (tots)

CALcutAfts CarfalleIDrf Pet 1 Ant (ccca saf)  ;

FORT CALHOUN LOSS OF COOLANT ACCIDENT REPORT Figure 2-1 Code Interface Description for Large Break Model i

i I

, i i

i  !

I t  !

,  :\ A  !

;\ /!

, s

' ^ , 1 ,

N

x. , -

,.e l

e.

w--M.am ,--6e a w "me,

., a.,se--em m.-m=+mAa,--mwaa- As ms-o n mma 5--mAsAMJo,,wu OAo wm m 4,mMbu sns&A eke ab.r4A> AM^ ^'_

mea 4 TiiE BART FOR_CLEM 4

4 d

i I

WHY BART?

l l

I i

l t

I i

f i

l l

l

/

/ J i j N . -

N_ ,- ) i t

.,--...-,,,,,.--.,...,..n--,.

h I((l]

IllE_MRT FOR_CE_EM

R o ORIGINALLY, CODE MODIFICATIONS WERE INITIATED FOR THE BASH EM CODES o TEST RUNS WERE PERFORMED TO ASSESS PERFORMANCE OF THE CE VERSIONS OR USE OF FT. CALHOUN PLANT-SPECIFIC INPUT o SATAN & WRELOOD (INTERIM) WITH C0C0 PERFORMED SATISFACTORILY o THE BASH TES_I RtJN, USING SEVERAL THOUSAND HAND-INPUT, AS-YET UNVERIFIED, PIECES OF INPUT DATA DID NOT PERFORM SATISFACTORILY o OPTIONS:

1. DEBUG BASH

2. ASSESS WHETHER THE MARGIN WHICH BASH WOULD MAKE AVAILABLE WOULD BE REQUIRED I

l

\ /1 !

ix i.

'x  ;

_N

b (hNIU i ,

,e xl, l[ IHE_BARLE0LCLEM N 3 o THE MOST EXPEDITIOUS OPTION WAS THE \

l ASSESSMENT OF MARGIN AVAILABILITY USING THE ALREADY COMPLETED RESULTS Or THE WREFLOOD TEST RUN, S0 THIS OPTION WA3 PURSUED FIRST (IN ESSENCE - TRY THE 81 EM AND SEE HOW CLOSE WE ARE) o SINCE THE ORIGINAL PLANS WERE BASED UPON THE MODIFICATION OF THE BASH EM, THE VERSION OF WREFLOOD COMPATIBLE WITH THE BART EM (AND l BASH EM) AND THE LOCBART CODE HAD BEEN UPDATED FOR MODELING A CE NSSS THE 81 EM VERSIONS OF WREFLOOD AND LOCTA-IV

HAD NOT BEEN UPDATED AND THE EARLIER l VERSIONS USED FOR THE ANALYSIS OF l MILLSTONE 2 WERE NOT READILY AVAILABLE l

l CODES USED FOR i 8LEM T.ESLRUN

! SATAN-VI SATAN-VI

WREFLOOD WREFLOOD (INTERIM)

C0C0 C0C0 LOCTA-IV LOCBART

(WITH FORMAT FIXES) l f

.I e  ;

@ M ObD I 1 7 ,

7  !

f' IHLBARLE0RlLEli 'x o RESULTS OF THE TEST RUN SUGGESTED THAT ,

ADE0VATE LARGE BREAK LOCA MARGIN WOULD BE i AVAILABLE TO MAINTAIN PCT < 22000F WHILE STILL MEETING THE AGREED UPON LOCA KW/FT AND FR LIMITS o GIVEN ADEQUATE MARGIN WITHOUT THE BENEFITS OF THE IMPROVED BASH HYDRAULICS AND CONSIDERING SCHEDULAR RESTRAINTS ASSOCIATED WITH LICENSING REQUIREMENTS FOR CYCLE 14, IT WAS AGREED WITH OPPD THAT A VERSION OF AN EARLIER EM WOULD BE USED FOR THE FT. CALHOUN ANALYSIS o SINCE THE AVAILABLE WREFLOOD VERSION WAS THE ONE COMPATIBLE WITH BART (INTERIM), BUT NOT PREVIOUSLY APPROVED FOR USE WITH THE 81 EM, USING THE 81 EM WOULD REQUIRE SPECIAL i LICENSING CONSIDERATION SINCE SUCH A MIX OF i CODES HAD NEVER PREVIOUSLY BEEN APPROVED l  !

i s

.-..a _

i <

l

h-- l (, (,1 {

Fi ,e 's s ,i

' l f j! IHLBARLE0LCLEM 'x

! o THEAVAILABLEWREFLOOD(INTERIM)V COMPATIBLE WITH BART BUT THERE WAS N0 READILYAVAILABLEVEkSIONOFTHELOCTA-IV CODE FOR ANALYSIS OF A CE NSSS, AND USING i

THE BART EM WITH LOCBART, WHICH WAS AVAILABLE, WOULD REQUIRE SPECIAL LICENSING CONSIDERATION SINCE SUCH A MIX 0F CODES HAD NEVER PREVIOUSLY BEEN APPROVED o GIVEN SIMILAR DOCUMENTATION AND LICENSING j REQUIREMENTS, THE BART EM, PROVIDING MORE i MARGIN WAS CHOSEN l

! o THIS SEQUENCE OF CODES, USED FOR THE EARLY i

CODE " CHECK 0UT" RUNS, BECAME THE BASIS FOR THE BART FOR CE EM l

i l

\

~ ~ -

@ m MC i I i

,,7 'x 7

/ IHLBARLE0LCLEM xI N

/ '

THE 1981 + BART FOR CE NSSS LARGE BREAK LOCA ECCS EVALUATION MODEL WCAP-13027-P (PROP.)

SATAN-VI SYSTEM BLOWDOWN

• WREFLOOD REFILL / CONT. M&E VERSION COMPATIBLE WITH BART (INTERIM)

MODIFIED FOR APPLICATION TO A CE NSSS C0C0 CONTAINMENT RESPONSE

• REfBASH TAPE FORMAT AND FLOODING RATE INPUT TO LOCBART NOT PREVIOUSLY REVIEWED BY THE NRC

• LOCBART HTC / ROD HEAT-UP MODIFIED FOR APPLICATION TO A CE NSSS i

i j

li \

'N fjl

'N i;

'n

-,-,- --4. ,...,.m, - - . w. - ,.,.gy.---*- w-w - . - - - - - - -

l[((l]

I

/ GENESIL0ElHE MODEL- x MQDlfLCAIl0NS_I.0 TH ERESIIhG10#SE_EM

/ h MODIFICATIONS TO WESTINGHOUSE VERSIONS O MODIFICATIONS TO STANDARD W CODES AND METHODOLOGY SINCE PUBLICATION OF THE 10/88 REVISION TO 10 CFR 50.46 NOT DESCRIBED IN THE ORIGINAL CODE AND MODEL REPORTS BRINGING THE BASE CODES UP TO 1991 STANDARDS

REFERENCES:

LETTER NS-NRC-89-3463 (10/5/89)

WCAP-13027-P (APPENDIX A) i h 4

, l '\ c'l

,\ l l

'N

_..ae.

@ m m LGCl I

If

/

/ GENESIL0ETHE MODEL MORIELCAILON S_IO_Ifl E_RE SIING501S E_EM I

MODIFICATIONS TO EXISTING MODELS FOR ANALYSIS OF A CE NSSS o MODIFICATIONS TO MODELS AND METHODOLOGY DOCUMENTED AND USED PREVIOUSLY FOR THE ANALYSIS OF A CE NSSS SATAN-VI

• LOWER PLENUM N0 DING

• SI/ SIT INTERACTION I

WREFLOOD l

• SI/ SIT INTERACTION l

'

• METAL HEAT MODELING

• [ ]A,C .

C0C0 - NONE LOCTA-IV - NONE (USING LOCBART)

REFERENCES- WCAP-9528 (PROP.)

WCAP-13027-P 1

l s

--' - . , - , . , - - , - - . - me---.

uuaMs m A-ws5 A A. A 6M,..a~Oe_.m+s s. =.-%em 46WM+=M' ' ' ""' ' MAwohL &W aL A kd 4 '

d J

F I

I 1

e I

ami i

U i 4 i N

est 8

4>

T A

l.

i -

1 s

i I

I I

I L

l k

i l

d

(

! -\ /l '

N ,/  :

t / t

}

M l

• .. w

p .#_,-m_m-.A A .4. hu msA__ haame4-4a-#.mA.-.a-44 p_ JawM.- 4m.-m+aa*h5.Au+.-m'*, jim # 4 Mhh44 -e-OS. -.M ad e A.mMW w . a_ _e4 h ea 4 44. 4 mea-me=Ms--sp.e auskaMamm.en A m. sim .u-am um me--m w em e.ye.mm-e,~5 I

1 i

emumuss r

P i

l t.(A . i, N

9 \

h

.s E

+ (

8 l  :

I i  :

i l\ x

/

/,k

'N /

i\ .

/  ;

I L _ /

I ,

^ i

-,vw.-..i-., ewer---,--w.,.,-.g.,--ee,,--,~.2-- ,ww-, ,-w e e-mi-*,y- - - . . - ., . - , ,-.,w.-,e+-+

y ...----,. -,-w,,-=--m .w,,m--- - - * - v-- - - -- ----- ---- -- --'

h l , ((l{

RENESIl_0L llE_MODEL -

/' HQDIFICATIONS TO TH E WESTIbGHOUSE EM MODIFICATIONS TO OTHER CODES o MODIFICATIONS TO MODELS AND METHODOLOGY DOCUMENTED NOT PREVIOUSLY EMPLOYED FOR THE ANALYSIS OF A CE NSSS REFBASH

• NEVER PREVIOUSLY REVIEWED BY THE NRC LOCBART

• BART NEVER PREVIOUSLY USED FOR ANALYSIS OF A CE NSSS DIFFERENCES FROM MODELING USED PREVIOUSLY IN LOCTA-IV

• NODING

• CRACK AND DISH VOLUMES

• THIMBLE MODELING

• SPACER GRID MODEL

REFERENCES:

WCAP-9528 (PROP.)

WCAP-13027-P WCAP-10266-P-A, REV. 2 WCAP-10484 (PROP.)

LETTER FROM IHOMAS (NRC) To RAHE (W) -

'10484 SER'

\s

/!

• I ..

j' j

h l) l I

/

! GENESI.S OF THE_MODEL -

/ MODIFICATIONS TO THE WESTIRGLQUEE_EM REFBASH CODE O TWO FUNCTIONS READ WREFLOOD OUTPUT TAPE INFORMATION AND " REWRITE" IN A FORMAT COMPATIBLE WITH BASH OUTPUT FOR USE BY LOCBART ADJUST THE FLOODING RATES CALCULATED BY WREFLOOD IN ACCORDANCE WITH THE APPROVED METHODOLOGY FOR THE BART EM (WCAP-9561-NP-A, ADDENDUM 2) 0 INTEGRAL PART OF THE BART FOR CE EM SEQUENCE l

l I

l I\x x

/  ;

/

1 i

@ IbI I

N I!

1 RENESlS OF THE 30. DEL - \

7 MODIFICATIQNS TO THE WESTIbGFOUSE\EM 0 LOOP LAYOUT THE MODELING OF THE " AUXILIARY LOOP" IN TH SATAN-VI ANo WREFLOOD CODES IS PERFORMED IN THE SAME MANNER AS DESCRIBED PREVIOUSLY FOR THE MODELING OF A CE NSSS USING THE W 1981 EM (WCAP-9528). ADDITIONAL GEOMETRIC INPUTS ARE MODELED THROUGH USE OF APPROPRIATE PLANT-SPECIFIC INPUT.

O CEA DESIGN l

MODELED IN SATAN-VI IN THE SAME MANNER AS DESCRIBED PREVIOUSLY FOR THE MODELING OF A i

CE NSSS USING THE W 1981 EM (WCAP-9528),

USING PLANT-SPECIFIC INPUT.

O UH BYPASS / UH TEMPERATURE FLOW THROUGH THE ALIGNMENT KEYWAY IS MODELED IN SATAN-VI USING PLANT-SPECIFIC INPUT, 1

l 6

i I

i l

l

,I\s ,

/

N / l l

h I (hl{

l L_ __

GENESIS _0F I E_MQDL, MODIFICATI0ffSTOTHEWESTIsGi100SEEM l 0 LOWER PLENUM DESIGN r p.c l l l J O CORE SHROUD BYPASS THE CORE SHROUD MODELING IN SATAN-VI IS THE SAME AS THAT USED IN WCAP-9528. SPECIFICS OF GEOMETRY AND LOSSES ARE MODELED THROUGH PLANT-SPECIFIC INPUT IN BOTH THE SATAN-VI AND WREFLOOD CODES.

O REACTOR COOLANT PUMPS IOMP PERFORMANCE AND COASTDOWN

! CHARACTERISTICS ARE MODELED IN SATAN-VI VIA PLANT-SPECIFIC INPUT. LOCKED ROTOR, DUE TO HIGHER RESISTANCE, IS MODELED IN WREFLOOD THROUGH PLANT-SPECIFIC PUMP INPUTS.

N 4 .

'\ / l

'x '/ ,

N i ,- j i

@ m dbD GENES"S OF TRE_ MODE..

[40DIFICATIONS TO THE WESTIsG1033E_EM 0 STEAM GENERATOR INLET N0ZZLE ANGLE PLANT-SPECIFIC SG INLET N0ZZLE AP IS INPUT INTO THE SATAN-VI MODEL, WHILE OTHER N0ZZLE CHARACTERISTICS HAVE A NEGLIGIBLE EFFECT ON BLOWDGWN BEHAVIOR.

O SI / ACCUMULATOR N0ZZLE ANGLE THE NRC-SPECIFIED UNRECOVERABLE PRESSURE DROPS ACCOUNTING FOR LOW VELOCITY LOOP STEAM CONDENSATION HAVE BEEN INCORPORATED INTO THE WREFLOOD CODE FOR THE SI AND/OR SIT INJECTION ANGLES FEATURED IN THE CE NSSS DESIGN. THE APPROPRIATE 6P IS SELECTED THROUGH PLANT-SPECIFIC INPUT.

o SAFETY INJECTION TANK PRESSURE i

AS IN WCAP-9528, SIT MODELING IN SATAN-VI AND WREFLOOD IS APPLICABLE TO TANKS WITH INITIAL PRESSURES ON THE ORDER OF 200 PSIG.

I i

i l

l  !

l k /

i  !'\ /

!  : y j/

\ / l l

1

& l $$l

[ N _

q GENESI1_0LIHE_MODEL -

/ MDEIFICATIONS TO THE_WESIINGiOUSE_EM 0 FUEL ASSEMBLY DESIGN FUEL ASSEMBLY GEOMETRY AND PRESSURE DROPS ARE INCLUDED IN THE HYDRAULIC CODES VIA FUEL-SPECIFIC INPUTS.

O FUEL R0D / PELLET STACK DIMENSIONAL DIFFERENCES BETWEEN TYPICAL WESTINGHOUSE FUEL RODS AND THE "CE-TYPE" HAVE BEEN CONSIDERED IN RELATION TO THE ROD BURST MODELING. FUEL-SPECIFIC CLADDING AND PELLET INPUT ARE USED IN THE ANALYSIS.

l l1 l

, 'x .x  !

'! 'N ./ 9

]

l

_L GENESIS OF THE_MODEL -

/ RQDIFICATIONS TO THE WESTINGHOUSE EM '\

APPLICABILITY OF THE MODEL 0 RESTRICTIONS AND REQUIREMENTS FOR CODES A REVIEW WAS CONDUCTED OF THE DOCUMENTATION ASSOCIATED WITH THE BART EM, WHICH SERVES AS THE BASIS FOR THE PROPOSED BART FOR CE EM, AND RELATED REPORTS, PLUS THE DOCUMENTATION OF THE APPLICATION OF THE 1981 EM TO A CE NSSS. l O EIGHT PERTINENT RESTRICTIONS / REQUIREMENTS ASSOCIATED WITH THE PREVIOUSLY APPROVED CONSTITUENT CODES OF THE PROPOSED BART FOR CE EM WERE IDENTIFIED.

O AS AN EXAMPLE OF THE METHOD OF APPLICABILITY CONFIRMATION, EACH WAS ADDRESSED BASED ON THE CURRENT FORT CALHOUN UNIT 1 ANALYSIS

\s' '

/;l -

,N j ,

x-

@ l ,

(kI]

\

j f GENESILOLTHE_M0 del -

x

/ tiODIELCATIONS TO THE_WESIIAGliOVSE_EM \

BART MODEL RESTRICTED TO THE RANGE OF OPERATION BOUNDED BY THE DATA CONTAINED IN SECTION 2-7 IN THE NRC SER FOR THE BART EM. THESE CONDITIONS ARE:

PRESSURE (PSIA) 20 - 60 INITIAL TEMPERATURE (oF) 1100 - 1500 INITIAL POWER (KW/FT) 0.45 - 1.2 INLET SuBCOOLING (oF) 20 - 140 REFLOOD RATE (IN/SEC) 0.6 - 1.5 RESPONSE: THESE PARAMETERS SHOULD BE VERIFIED AGAINST THE FINAL LICENSING BASIS COMPUTER OUTPUT INFORMATION AND INTERNALLY DOCUMENTED.

PRESSURE ~50 PSIA INITIAL TEMPERATURE ~15500F INITIAL POWER ~0.8 KW/FT INLET SUBCOOLING ~800F REFLOOD RATE 0.95 < Vzn < 1.4 l (THROUGH PCT TIME) i i

?

I l l \

l

-]

h l ,

((l{

l

~

!l GENESlS OF THLF0 DEL -

MODIFICATIONS TO THE WESTIRGHOUSE EM BART NODES MUST BE LESS THAN 6 INCHES IN LENGTH.

RESPONSE: VERIFY BART NODES <6 INCHES LONG (0.5 FT.)

LENGTH OF ALL BART NODES 0.25 FT. 5 AX s 0. 5 FT .

0.5 FT. NODES ARE ALL LOCATED IN LOWER CORE ELEVATIONS, FAR FROM BURST AND/OR PCT.

ERRATUM: A SINGLE 0.6003 FT. NODE IS LOCATED IN THE LOWER CORE, FAR FROM BURST AND/OR PCT.

f l [\,

!lN -

ll '

'N /i l

h I

((l]

I if x\  !

/ GENESIL_0ElHLM0_D.El  !

/ MDDIFI_ CATIONS TO THE_WESTIh'GHOUSE EB BART APPLICABLE ONLY To PWR USING WESTINGHOUSE FUEL WITH ONLY COLD LEG INJECTION.

RESPONSE: CONFIRM CONDITIONS.

FORT CALHOUN IS A PWR WITH A 4/2 CE NSSS AND ONLY COLD LEG ECCS INJECTION (NO UPPER HEAD, UPPER PLENUM OR DIRECT VESSEL INJECTION). THE ANALYSIS PERFORMED ASSUMED THIS UNIT TO BE FUELED WITH WESTINGHOUSE DESIGNED /MANUFACTUk:D "CE-TYPE" FUEL.

I i

I i

, N ,. >

l \ ,

i s_ -g

__ j

~-

h I

((l]

I I / l l

/ MODIFLC TT GIl00SE EL4 BART MODEL REQUIRES THAT CONDITIONS OF NO SINGLE FAILURE BEING WORST CASE SHOULD BE CONSIDERED.

RESPONSE: WILL BE CONSIDERED AS PART OF BART FOR CE EM (WCAP-13027-P, SECTION 3.3.2.3)

MAXIMUM SAFEGUARDS CASES PERFORMED FOR FORT CALHOUN. MAXSI RESULTS ARE INCLUDED IN THE PLANT-SPECIFIC RESULTS

SUMMARY

REPORT.

l l

I l

l 1

i l

8 . i

^

s

-..s

'N l l

1 ..

I I , ,

Ib i

l I -

l GENESlS OF THE_MODEL -

/ MODIFICATIONS TO THE_WESTIRGHOUSE_EM SER FOR 1981 EM REQUIRES USE OF THE SKEWED POWER SHAPE OPTION FOR LESS THAN 12 FOOT CORES.

RESPONSE: SKEWED POWER OPTION WILL BE USED FOR THESE CONDITIONS.

FOR FORT CALHOUN, WITH A 128 INCH ACTIVE CORE LENGTH, THE SKEWED POWER OPTIONS WERE EMPLOYED IN SATAN-VI, WREFLOOD AND LOCBART, EVEN FOR CHOPPED COSINE POWER DISTRIBUTION STUDIES.

(

6 l

\k y

/

'x -

i l ,

t

_n....

@ m d&CI .

i_

l X __ _

ftENESIS OllREl0REL - \

R0]IFICATIONS TO THE WESTINGHOUSE _EM \,

1981 EM SER IDENTIFIES MODELING OF SI/ ACCUMULATOR INTERACTION.

RESPONSE: EMPLOY THIS MODELING TO CE PLANTS FEATURING THIS ECCS ARRANGEMENT.

INTERACTION OF SII/SI (COMMON INJECTION N0ZZLE) HAS BEEN CONSIDERED IN THE SATAN-VI AND WREFLOOD MODELING FOR FORT CALHOUN.

\

'Ns -

/ >

ii j-

,/'l '

l  ;

@M M %O 1 7 i GENESIS _0F T E_ MODE -

MDAIEICATIONS TO THE WESTIsGl10VSE EM A BURNUP STUDY WAS SPECIFICALLY REQUESTED FOR THE APPLICATION OF THE WESTINGHOUSE EM TO A CE NSSS (WCAP-9528).

RESPONSE: BASED ON SUBSTANTIAL EXPERIENCE WITH THE EFFECTS OF FUEL BURNUP ON LARGE BREAK LOCA RESULTS FOR A WIDE RANGE OF FUEL DESIGN, TRANSIENT CONDITIONS AND EVALUATION MODELS (INCLUDING BART), LIMITING CONDITION IS AT THE BEGINNING OF LIFE. THE PREVIOUS WESTINGHOUSE EVALUATION MODEL FOR A CE NSSS (WCAP-9528) WAS USED TO PERFORM A STUDY OF FUEL BURNUP EFFECTS ON LBLOCA. RESULTS (WCAP-9220-P-A, REV. I) CONFIRMED THAT BOL REPRESENTS THE LIMITING CONDITION.

BASED ON THIS INFORMATION, A SPEC 1'FIC BURNUP STUDY WAS NOT PERFOk'MED FOR THE BART FOR CE EM.

L N/A. ,

i l

\

is

! x -

\ ,

[--

l

l I I

l fiENESIS OF THE MORE x M0EIFICATIONS TO THE WESJJiGEQUIE_EM

}

SPACER GRID MODEL APPLICABILITY RESTRICTED TO THE CONDITIONS IDENTIFIED IN THE SER FOR THE SPACER GRID MODEL.

RESPONSE: VERIFY AGAINST ANALYSIS.

THESE CONDITIONS ARE ROUGHLY EQUIVALENT TO THOSE HIGHLIGHTED IN SECTION 2.3 0F THE BART SER (PREVIOUSLY CONFIRMED) l '\ ,1

\ ' '

/l 1

7 i

h I((l{

1 I

__L APPLICATION OF THE MODEL BREAK SPECTRUM O NO BASIS FOR ASSUMING A GENERICALLY ACCEPTABLE DISCHARGE COEFFICIENT FOR CE NSSS ANALYSES O SUBSTANTIAL CHANGES IN SI/ SIT PARAMETERS, SGTP, ETC. CAN RESULT IN A SHIFT IN THE LIMITING DISCHARGE COEFFICIENT CONCLUSION:

PERFORM BREAK SPECTRUM ANALYSIS FOR ALL APPLICATIONS UNLESS SPECIFIC JUSTIFICATION FOR EXCEPTION IS PROVIDED.

l 1

k

!x z'A, f ,

l

/ -

APPLICATION OF THE MODEL MAJOR SENSITIVITY STUDIES o BREAK LOCATION o POWER AVAILABILITY o ECCS AVAILABILITY o AXIAL POWER DISTRIBUTIONS o FUEL BURNUP o INTEGRATED FUEL BURNABLE ABSORBERS (IFBA) 1 i

l l

, 'N E

p

/

/ l

I 1

APPLICATION OF THE_R0EJ1 o BREAK LOCATION DOUBLE-ENDED COLD LEG BREAK BELIEVED TO BE MOST LIMITING BREAK LOCATION AND BREAK TYPE BASED ON BREAK GEOMETRY AND STEAM FLOW RESISTANCE.

SUPPORTED BY W SENSITIVITIES IN WCAP-8340 (PROP.) .

SUPPORTED BY CE SENSITIVITIES IN CENPD-132, REV. 01, VOL. II.

CONCLUSION:

RUN ONLY DECLG BREAK FOR LBLOCA USING BART FOR CE EM.

l i

l lx /

/!

.A '

z .' I

@mLLLC l

I :

APPLICATION OF TiiE MODEL

/

0 POWER AVAILABILITY i

IT IS NOT OBVIOUS THAT WESTINGHOUSE PLANT SENSITIVITIES, WHICH SHOW LOSS OF 0FFSITE POWER (LOOP) TO BE LIMITING BE JUSTIFIABLY EXTENDED TO A CE NSSS ,

COMPETING EFFECTS INTRODUCE HIGH LEVEL OF UNCERTAINTY FOR LIMITED DATABASE OF LARGE BREAK ANALYSIS APPLYING W METHODS TO A CE NSSS.

CONCI.USION:

EXAMINE BOTH LOOP AND NO LOOP ASSUMPTIONS TO IDENTIFY THE LIMITING POWER AVAILABILITY ASSUMPTION UNLESS SPECIFIC JUSTIFICATION FOR EXCEPTION IS PROVIDED.

I

\ /

x /

N l l

i h I . .

I

[7 O APlLICATLON OF THE MOD _EL ECCS AVAILABILITY "N0 SINGLE FAILURE" (MAXSI) HAS BEEN SHOW TO BE A MORE LIMITING ASSUMPTION FOR SOME W NSSS LBLOCA ANALYSES USING W METHODS.

"N0 SINGLE FAILURE" (MAXSI) HAS BEEN SHOW TO BE A MORE LIMITING ASSUMPTION FOR SOME CE NSSS LBLOCA ANALYSES USING CE METHODS.

CONCLUSION:

EXAMINE BOTH MINIMUM AND MAT' MUM SAFEGUARDS TO IDENTIFY THE LIMITING ECCS AVAILABILITY ASSUMPTION UNLESS SPECIFIC JUSTIFICATION FOR EXCEPTION IS PROVIDED.

\ l

,s j fl 1 N. j

i APPLICATLON OF THE MODEL 0 AXIAL POWER DISTRIBUTIONS WITH AN ELEVATION INDEPENDENT PEAK LINEAR HEAT RATES FOR CE PLANTS AND COMPARATIVELY SHORT ACTIVE FUEL REGIONS, TOP-SKEWED POWER DISTRIBUTIONS ARE EXPECTED TO BE LIMITING, BUT NO

" GENERICALLY APPLICABLE" DISTRIBUTION HAS BEEN IDENTIFIED.

CONCLUSION:

EXAMINE AXIAL POWER DISTRIBUTIONS USING THE METHODOLOGY IDENTIFIED IN APPENDIX B OF WCAP-13027-P TO IDENTIFY THE LIMITING AXIAL DISTRIBUTION FOR ALL APPLICATIONS UNLESS SPECIFIC JUSTIFICATION FOR EXCEPTION IS PROVIDED.

l

\ /} j

\ ,'l ,

\ /!

\ / g

b. l

@ M GGC l f

/

/ APPLICATION OF THE_MODEL

/

POWER SHAPE METHODOLOGY PERFORM SENSITIVITIES FOR A RANGE OF SHAPES INCLUDING CH0PPED COSINE (MID-PLANE PEAK),

SKEWED COSINES AND REPRESENTATIVE TOP SKEWED SHAPES.

ALL SHAPES MUST CHALLENGE THE PLHR LIMIT.

EXTEND PEAK ELEVATIONS TO CHALLENGE ASI LIMITS.

Shape No. Zo (ft) Normalized Ze - ASI (%)

1 5.333 0.5 0%

. 2 6.33 0.593 9.2%

3 7.33 0.687 17.2%

4 8.75 0.820 16%

\s ,

/

\ '

'N , i l

u --- .g -

.= -ee.._--_A- e- - - . - am- --r._m-.-- - .a.-- .

. -u.a ,.m-. _ ~ . - . -.-=.4,* *=s =+- +

dF I F 8.0 ,

1.5 ---

t 3

9

- \

. g 1.0 7

5 s

u o.s

\

, \ l

. io.. u.o EL1TETIEE-(PT)

Figure B 1.

l Coorw Pomr Shape,2b = 5.334 R., ASI = 0%

i l

l t

h.

\s -

/

I

's\ ,/

/

l f i

l l l

/

2.0 ,

_ l.5

!g s\

1.0 j

I f E

a 0.5 o

o 2.0 4.0 s.0 s.o 10.0 12.0 nasTInu -(rt)

Fo urs B-2.

Skewed Costie Power Shape. Zp = 6.33 ft, ASI = 9.2%

b A

/

! \, '

/ ,

,/'

l

~ , . - -~

@XMLLL C l

t.0

. 1.8 r m 1

3 ig 1.0

/

W t

o.s (

o e t.o 4.o s.0 .o 10.0 12.0 tuuAires -(Fr)

Figure B 3.

Skmd Cosne Power Shape, Zp = 7.33 fl. ASI = 17.2%

6 i

li I

\ s

/

s

\ /

\ s /

/ ,

\ / l ,

I l l

@hi ,

Y, W i i

~

[ l ,

i l

I i

l -185 AIIAL INOCI l-t.o ~ * -

i j

. 1.5 '

~

t E

E.

g 1.0 j t

W 2

0.5 y o 12.0 2.0 4.0 s.o s.o 10.0 o

11RATigli~(FT)

Figure B4 Top Skewed Power Shape,2p = 8.75 ft. ASI = 10%

s

\s -

/ ,

\ /

.\ /

i

'N ,/ j ,

l

', t r g 3 _

\,,

7  % ,e ...

ss . _ _ _ . _ .

l - Power Shape Study Zpeak vs PCT 'N 1

t

\

2.1

j. =

1st

! I i 2.05 --

+-- -

20'so ' 2nd 2

+ 3rd 2020 l E

• O

! T 4th

2013 I 2 -..

i 1 T

h 1981 o 1M5 1 as

• 1973

• 2-1.95 - issa - r < -

d 1848 s

E -

1918 1.9 - - - ~ ~ ~ - - - - -

+-

1.85 i i I i i

5.334 6.33 7.33 8.75 10.667 Case Height fit)

/,

N /

l

@ I , k k ll_

l .

I I

N __ _

AP_P_LICATLON 0F THE_MRDIL

/ I o FUEL BURNUP l 1

BASED ON EXISTING STUDIES (INCLUDING MILLSTONE 2), MOST LIMITING TIME IN LIFE CAN BE IDENTIFIED AS BEGINNING-0F-LIFE.

NO BURNUP STUDY PERFORMED FOR BART FOR CE EM.

CONCLUSION:

PERFORM ANALYSIS USING LIMITING BOL (TIME OF MAXIMUM DENSIFICATION) CONDITIONS UNLESS SPECIAL CONDITIONS WARRANT OTHERWISE.

! I'\

x /

/l

!  ! x ,I i

' s.

/;

I i

h I

( hl]

/

f- APPLICATION OF THE._ MOREL

/ 0 IFBA

[ ja.c l J MAY YIELD A LATER, BUT HIGHER TEMPERATURE BURST. THE COMPETING EFFECTS OF LOCAL ZIRC/ WATER REACTION AND HIGHER STEAM FLOW /ENTRAINMENT MAY YIELD IFBA PCTS HIGHER THAN PCTS CALCULATED FOR NON-IFBA RODS AT BOL (IFBA BURNUP FOLLOWS THE SAME TRENDS AS NON TFBA).

IFBA DESIGNS MAY VARY FROM CYCLE TO CYCLE.

CONCLUSION:

APPLICATION OF THE MODEL SHOULD INCLUDE EXAMINATION OF BOTH IFBA AND NON-IFBA FUEL TO IDENTIFY WHICH RESULTS IN THE MORE LIMITING PCT UNLESS SPECIFIC JUSTIFICATION FOR EXCEPTION IS PROVIDED.

'\ /

x ,/

'I \ f i J

@ m dLC N

APELICAI1ON_0f_IllE30 DEL

/

0 OTHER SENSITIVITIES ITEMS IDENTIFIED IN WCAP-9258 DISCUSSION IN APPENDIX C OF WCAP-13027 FOR BART FOR CE EM

1. Power 'hapes Discussed previously.

2. Core $hroud Region Nodalization Discussed previously.

3. Burnup Discusses previously.

4. Cold RCS Volume in SATAN

$ATAN-VI sensitivity study (WCAP-8341, Prop.). None of the changes to

$ATAN-V! would be expected to significantly affect the sensitivity results.

f A

. \ /

l 'N "

/ '

N , j-

a 1

I l

/[ APPLICATLON_0F THE_liOAEL

/

6. Sensitivity to Number of Nodes

[ ]a.c l I I I l I I I I I i l l I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I

~

l \

l I L J

\ /

x \, / .

i) / l l

i E l[((l]

! l l / h-y i

/

/ APlLLCAILON_0F THE30 DEL i

6. Artificial Pressure in the $ATAN Momentum Equation

7. Effect of Critical Flowchecks on SATAN Momentum with Momentum Flux

8. Cross Flow Effects <

l 9. Reactor Coolant System Thick Metal Heat Release in $ATAN I

)

i 10. D htribution Parameter (Co ) Study

11. Steam Generator Reverse Heat Transfer Effects l

12. Accumulator injection in the Broken Loop During Dlowdown Items 6 through 12 are $ATAN VI sensitivity studies (22). None of the changes to $ATAN-VI would be expected to significantly affect the

[ sensitivity results.

1 1

i l

i

? I

\s /1

.x ,

y 1

\ /j I

@ MMC . l I

AP1_LICAIl0N__0F IHE_MQREL

13. LOCTA Pellet Noding Discussed previously.

14. LOCTA Time Step Studies Item 14 is related to time step size in the rod heat-up calculation.

Definition of the iteration scheme ased in the approved Westinghouse version of LOCBART is provided in WCAP-10266-P-A, Rev. 2

16. Sensitivity of Peak Cladding Temperature to steam Cooling The BART code which is included in LOCBART has sufficient capability to accurately model heat transfer from fuel rod to fluid at all anticipated steam flow rates (WCAP-9561-P-A).

16. WREFLOOD Sensitivity to Reactor Coolant Pump Conditions Discussed previously.

17. Core Heat flow Rate during REFLOOD Core heat flow rate is a relatively insensitive parameter in WREFLOOD (WCAPr9528), & modifications have been introduced to WREFLOOD to alter this sensitivity, so the sensitivity for item 17 remains valid.

i t  ;

\s -

/

t i

. p' l

l

\

l

[ b I

/ APELI.CAU.0N_0LT11LM0REL ,

18. Containment Pressure

]

Changes to the containment code, COCO have not been implemented since this sensitivity was addressed in WCAP-9528. The item 18 sensitivity remains valid.

1-

19. $1ngle railure Criterion Single failure cri' vria a P.c areviously addressed for Westinghouse plants (WCAP-8240 WCli b . c or,. Ting that the limiting single failure for Large b. Q 1%4 4 l0P ct a single Low Pressure safety injection pump. Combustu e,gineuing Ms confirmed this assumption in '

similar studies for a CE N$$t desipi (CENPti-132, Rev. 01, Vol.1).

Consideration of no single ftliure being the worst case has been previously discussed. ,

20. Nitrogen Gas injection impact ,

The impact of accumulator ($1T) gas injection has been addressed in WCAP-8341. In the BART for CE EM, as in previous Westinghouse Evaluation Models, the effects of nitrogen gas on reflooding will conservatively be neglected.

t

.x x

'\ N- {

- J

. . . . - , , . , , . - - - - - , - - - - - - , - - .nn,-.. .,-r,-.. . , , . - - - ~ , . . , , - . . =

@ m diC AEP11.CAIl0lLOF THLMODEL

/

21. RCP Assumptions Olscussed previously.

22. Break Location Discussed previously.

23. Flow Blockage Considerations Discussed previously.

?\

l

\.  % f'

/

g i

e x y, ) i

1 N L_

'[ 'N

[ SMA.LBREAK_LQCA_ECCS.EVALVATION MODEL FOR THE A N A mYSI S_0 E_A_C.0M B U.SIl0N_E N GI N E E RI NL( C E LRS S S'_

REVISED NOTRUMP EM FOR CE - A SMALL BREAK LOCA ECCS EVALUATION MODEL FOR THE ANALYSIS OF A CE NSSS l

0 PRIMARILY BASED ON PREVIOUSLY APPROVED NOTRUMP EM FOR CE DEVELOPED FOR THE ANALYSIS OF MILLSTONE UNIT 2 AND DOCUMENTED IN WCAP 10054-P-A, ADDENDUM 1 o INCLUDES MINOR MODIFICATIONS TO PREVIOUSLY APPROVED NOTRUMP EM FOR CE WHICH HAVE BEEN IMPLEMENTED TO MORE APPROPRIATELY MODEL THE CE NSSS AND TO BRING THE EM UP TO 1991 TECHNOLOGY AND STANDARDS.

I f;4 , \.

x j  :

'N j

.d

b I NNIb

[ EREYLO.US_t10lRUMP_EM_E0R_CE \l i APPROVED IN WCAP 10054-P-A, ADDENDUM 1

/o h o DEVELOPED TO VERIFY THE APPLICATION OF THE WESTINGHOUSE SMALL BREAK EVALUATION MODEL USING NOTRUMP AND LOCTA-IV TO A CE NSSS MEETS REQUIREMENTS OF APPENDIX K TO 10 CFR 50 AND ITEM II.K.3.30 0F NUREG-0737 o BASED ON WESTINGHOUSE NOTRUMP EVALUATION MODEL APPROVED IN WCAP 10054-P-A AND USED UNALTERED CODE VERSIONS OF:

NOTRUMP (SYSTEM HYDRAULIC CALCULATION)

AND LOCTA-IV (FUEL R0D HEATUP CALCULATION) o NRC STAFF DETERMINED APPLICATION OF NOTRUMP CODE TO THE CE NSSS COMPLIES WITH REQUIREMENTS OF APPENDIX K TO 10 CFR 50, WITH THE EXCEPTION THAT A BREAK SPECTRUM WOULD NEED TO BE PERFORMED IF THE I

METHODOLOGY WAS APPLIED TO CE NSSS DESIGNS OTHER THAN MILLSTONE 2.

o NRC STAFF ALSO DETERMINED THAT WCAP 10054-P-A NUREG-0635, ADDENDUM 1 ADDRESSES CONCERT'S O II.K 3.30 I\ ,)

l\

x ,

l

@ l REVISED _NDIRUMP_EILE0R_CE 'N L DOCUMENTED IN WCAP 13027-P l CONSISTS OF:

o CODE MODIFICATIONS REPORTED IN 1989 AND 1990 ECCS EVALUATION MODEL CHANGES REPORTS REQUIRED BY 10 CFR 50.46 o CODE MODIFICATIONS MADE BETWEEN AUGUST 1990 AND MAY 1991 WHICH WERE REPORTED TO UTILITIES o CODE MODIFICATIONS TO MORE ACCURATELY MODEL SAFETY INJECTION CONFIGURATION o SYSTEM N0 DING MODIFIED TO MORE APPROPRIATELY MODEL ADDITIONAL COLD LEGS o VERIFICATION THAT CODE AND INPUT METHODOLOGY CHANGES REQUIRED IN PREVIOUS NOTRUMP EM FOR CE CONTINUE TO APPLY TO FORT CALHOUN UNIT 1 1

MORE DETAILS OF THESE MODIFICATIONS FOLLOW j1 x N_

j I

I hhI p

/

[ REVISED.L.NOIRUMP_EM_FOR DEIAL ED_ItLECES_EM CHA CE_

1988 THE NRC IMPLEMENTED REVISED ONOCTOBER17,NMODILREPORTINGREQUIREMENTS ECCS EVALUATIO THROUGli A RULE CHANGE TO 10 CFR 50.46 SINCE THAT TIME WESTINGH0ljSE HAS ISSUED DOCUMENTS DETAII.ING MODEL CHANGES FOR TWO ANNUAL REPORTING PERIODS (1989 AND 1990) o THE MODIFICATIONS TO THE WESTINGHOUSE NOTRUMP AND LOCTA-IV CODES IDENTIFIED IN THE 1989 REPORT WERE DETERMINED TO BE EQUALLY APPLICABLE TO THE NOTRUMP EM FOR CE o IT WAS CONCLUDED THAT THE COMBINED EFFECT OF THE 1989 MODIFICATIONS TO THE NOTRUMP AND LOCTA-IV CODES WOULD RESULT IN A NET REDUCTION IN PEAK CLADDING TEMPERATURE o THESE MODIFICATIONS TO THE REVISED NOTRUMP EM FOR CE ARE SUMMARIZED IN WCAP 13027-P o FOR THE 1990 PERIOD (AUGUST 1989 TO AUGUST 1990), NO REPORTABLE EVALUATION MODEL CHANGES OCCURRED.

i

@ I

. b b.Ib i

[ REVISED. _EM l0R_CE_

ADDIIIONAL]MODEL0IRUM h! 1

'\l PDAIES_IO_RE

[ REE0RIED_I lure IN JUNE 1991, REPORTS WERE ISSUED TO UTILITIES WHICH ARE CURRENTLY LICENSED WITH WESTINGHOUSE ECCS EVALUATION MODELS IDENTIFYING CHANGES TO THE VARIOUS EVALUATION MODELS IMPLEMENTED BETWEEN THE TIME PERIOD FROM AUGUST 1990 TO MAY 1991 o FOUR MODIFICATIONS WERE IDENTIFIED WHICH EFFECT THE CODES WHICH CONSTITUTE THE NOTRUMP EM o THESE MODIFICATIONS ALSO APPLY TO THE NOTRUMP EM FOR CE AND THEREFORE WERE INCLUDED AND ARE DESCRIBED IN WCAP 13027-P i

1 iN j

h I((l]

i I

NOIRUMLMODELU) 0F tie _E0RT CAL {0JJ LURII_1_CE_h DATES E0L. SSS ANALYSIS x

\

IN WCAP 10054-P-A, ADDENDUM 1, THE DIFFERENCES BETWEEN A WESTINGHOUSE AND CE NSSS WERE EVALUATED TO DETERMINE WHAT MODEL CHANGES WERE REQUIRED. AS A RESULT OF THESE DIFFERENCES, SEVERAL MODEL CHANGES WERE REQUIRED THESE DIFFERENCES AND MODEL CHANGES WERE REVIEWED TO ASSESS THEIR APPLICABILITY TO FORT CALHOUN UNIT 1 THIS REVIEW IDENTIFIED SEVERAL ADDITIONAL MODIFICATIONS REQUIRED FOR THE APPROPRIATE MODELING 0F FORT CALHOUN UNIT 1 WHICH WERE BEYOND THOSE DESCRIBED IN WCAP 10054-P-A, ADDENDUM 1.

THE NSSS DIFFERENCES AND ADDITIONAL MODIFICATIONS ARE SUMMARIZED BELOW l i 1 .

i l l i i'

[\x  ;

,N -,

@ - UU[

i! -

NOIRUMP_ MODE 1.U' DATES _EDR ANALYSIS ~

0.ElHE F0RI_ CAL 10ULUNLLllE_NSSS_C_0N h- -

,o LOOP LAYOUT REPRESENTATION \

IN THE PREVIOUS MODEL, THE STANDARD WESTINGHOUSE SYSTEM MODELING WAS MODIFIED TO ACCURATELY REPRESENT THE CE TWO HOT LEG, FOUR COLD LEG DESIGN BY [

3..e

[

) ..c FORT CALHOUN UNIT 1 HAS A " TRIP-2 LEAVE-2" REACTOR COOLANT PUMP TRIP EMERGENCY OPERATING PROCEDURE FOLLOWING AN ABNORMAL CONDITION WITH NO LOSS OF 0FFSITE POWER IN ORDER TO EXPLICITLY MODEL THIS PROCEDURE FOR THE NO LOSS OF 0FFSITE POWER SCENARIO,

[

).C lix

)\ /

z' i

N. . j ', ,

l 6 .

h' I I

l A, C Fgurs +1 Fort Calhoun NOTRUMP Nodng Diagram

/

, N j g l

h I

. hNI I i x i i/ HOTRUM) MODEL UPDATES _E0R ANALYSIS 'N l 0F THE_E0lLCALH0BILUNILLCE_NSSS_CONL N ALSO IN ORDER TO EXPLICITLY MODEL DIFFERENT COMBINATIONS OF LOW AND HIGH PRESSURE SAFETYi INJECTION INTO EACH COLD LEG FOR FORT CALHOUN UNIT 1, [

]..c o LARGE DIAMETER HOT LEG ACCOUNTED FOR VIA NOTRUMP CODE INPUT o HOT LEG SG INLET ANGLE AND PLENUM FLOODING CORRELATION FORT CALHOUN UNIT 1 SG INLET N0ZZLE INCLINATION E

]ac PERFORMED IN WCAP 10054-P-A, ADDENDUM 1 o LOOP SEAL BEHAVIOR l THE FORT CALHOUN UNIT 1 ANALYSIS CONTAINS N0 -

i CHANGES IN LOOP SEAL N0 DING OR CODE INPUT METHODOLOGY FROM THAT DEVELOPED IN WCAP 10054-P-A, ADDENDUM 1 i

. + -

l

..__..__.______)

h I

((l]

N 0F TjIRUMP_ MODE.mVgDgES_E0_RE ALYSISh -

E FORLCAL:.0ll LLLCLLSSSl0NL

'o CONTROL ELEMENT ASSEMBLY DESIGN FORT CALHOUN UNIT 1 CEA DESIGN IS SIMILAR TO THAT ASSUMED IN 10054-P-A ADDENDUM 1.

THEREFORESAMEMODELINGASSUMED.

o UPPER HEAD BYPASS FLOW AND TEMPERATURE FORT CALHOUN UNIT 1 BYPASS FLOW AND TEMPERATuliE IS SIMILAR TO THAT ASSUMED IN 10054-P-A ADDENDUM 1. THEREFORE SAME MODELINGASSUMED.

o SAFETY INJECTION ANGLE THE FORT CALHOUN UNIT 1 ANALYSIS CONSERVATIVELY ASSUMED A VALUE OF [

] a.c EVEN THOUGH THE ACTUAL PLANT SI ANGLE IS 75 DEGREES o SAFETY INJECTION FLOW GE0 METRY THE FORT CALHOUN UNIT 1 SAFETY INJECTION FLOW GE0 METRY IS SIMILAR TO THAT ASSUMED IN WCAP 10054-P-A, ADDENDUM 1.

\s -

l

\_ , j,

h ,

l NOIRUM LliODELU 'D

[0F TifE_.E03T CALii0hL}IES_EDR ffLT_1_CL5SSS ALYSIS\

CONL O

/ X o POLYTROPIC EXPANSION COEFFICIENT

[

3 . *.c THE FORT CALHOUN UNIT 1 COVER GAS PRESSURE OF 255 IS WITHIN THE BOUNDS OF THE EVALUATION.

o REACTOR COOLANT PUMPS WCAP 10054-P-A, ADDENDUM 1 CONCLUDED THAT THE E 3 . a.c FORT CALHOUN UNIT 1 HAS BYRON-JACKSON PUMPS WHICH ARE SIMILAR IN DESIGN TO CE AND WESTINGHOUSE PUMPS. THE USE OF FORT CALHOUN UNIT 1 PUMP HOM0LOGOUS CURVES AND PARAMETERS PROVIDES REALISTIC MODELING.

1 l\ '

/

j 'x j

.N i,

__._-,.__,,..-.-..--.._,m._,. . , _ . . . _ _ . . . _ _ . _ , _ , . . . . _ _ , , , . _

I b I b, b, I l

1 NOIRUMP_MODEL_U'DAIES_E0.R AsALY.SISs I QF THE_EQRT CALH0ELU. flit 1 CL)S1530XK o FUEL ASSEMBLY DESIGN \

THE STEAM COOLING CORRELATIONS USED IN NOTRUMP AND LOCTA-IV WERE DETERMINED TO BE APPLICABLE TO FUEL ASSEMBLY HYDRAULIC DIAMETERS OVER A RANGE ENCOMPASSING BOTH CE AND WESTINGHOUSE DESIGNS. THE FORT CALHOUN FUEL HAS A HYDRAULIC DIAMETER WITHIN THIS RANGE o R0D BURST CALCULATION ADDENDUM 1 DETERMINED THAT WCAP FOR FUEL10054-P-A, BEING LOADED INTO THE CE NSSS THE PRESSUREDIFFERENTIALREQUIREDFORBUR$ TAT A GIVEN TEMPERATURE WAS [

] .ie THE FUEL FOR FORT CALHOUN WILL ALSO BE MORE RESISTENT TO CLAD BURST.

CLAD BURST IS A PCT PENALTY FOR SMALL BREAK LOCA. [

3.a c

\ /

y z'

'N /[ i

@ l b b,I b l

! I

/ NOI w I

/ q

/ DE_L41_RUMR MODI LU?DAIES_F.0R.A

/

o FUEL CRACK AND DISH VOLUMES STANDARD WESTINGHOUSE VALUES WERE REPLACED WITH FORT CALHOUN SPECIFIC DATA FOR LOCTA-IV '

INPUT 4

1

! '\ e x ' '

I, t N.  ;

I

b I

. NNIU

!APlLICABILIIY OE_REYlSED_N0IRUMP_EM_E0ii'0E I

[ASSTATED.NWCAP10054-P-A, ADDENDUM 1,NRC \j! '

STAFF DETExMINED APPLICATION OF NOTRUMP CODE TO l THE CE NSSS COMPLIES WITH REQUIREMENTS OF APPENDIX K TO 10 CFR 50, WITH THE EXCEPTION THAT A BREAK SPECTRUM WOULD NEED TO BE PERFORMED IF THE METHODOLOGY WAS APPLIED TO CE NSSS DESIGNS OTHER THAN MILLSTONE 2.

l REVISED NOTRUMP EM FOR CE j IS BASED ON 10054-P-A, ADDENDUM 1 MODEL I CONTAINS ONLY MINOR CHANGES TO LOOP N0 DING AND CODE ERROR UPDATES REQUIRES BREAK SPECTRUM TO BE PERFORMED l THEREFORE REVISED NOTRUMP FOR CE MEETS PAST NRC REQUIREMENTS AND WILL COMPLY WITH REQUIREMENTS OF APPENDIX K TO 10 CFR 50 j i

l l Ix 1 i

@)

REVI S ED_NDIRUMLEfLEORlLS ENSlIIVIISIS -

o BREAK SPECTRUM ANALYSIS WESTINGHOUSE EXPERIENCE HAS SHOWN THAT IT IS DIFFICULT TO IDENTIFY A " GENERICALLY LIMITING" BREAK SIZE THEREFORE APPLICATION OF REVISED MODEL REQUIRES BREAK SPECTRUM TO BE PERFORMED FORT CALHOUN UNIT 1 WAS FOUND TO HAVE A LIMITING BREAK OF 3" o BREAK LOCATION WESTINGHOUSE EXPERIENCE HAS SHOWN THAT THE LIMITING BREAK LOCATION FOR SMALL BREAK LOCA IS THE COLD LEG.

THIS WAS CONFIRMED FOR THE APPLICATION OF THE NOTRUMP EM TO CE PLANTS IN WCAP 10054-P-A, ADDENDUM 1 SIMILAR STUDIES BY COMBUSTION ENGINEERING ALSO SHOW COLD LEG BREAK TO BE LIMITING l

['x

b I

. NNlb I '

REVISED _H0 HUMP _EM-F0RCE_SENSHLYHfES.

, ((POWERAVAILABILITY o

SENSITIVITIES FOR THE WESTINGHOUSE NSSS DESIGN HAVE SHOWN THAT THE LOSS OF 0FFSITE POWER SCENARIO RESULTS IN THE LIMITING PCT IN ORDER TO CONFIRM THE LOSS OF 0FFSITE POWER ASSUMPTION IS CONSERVATIVE FOR FORT CALHOUN UNIT 1 A SENSITIVITY WAS PERFORMED ASSUMING NO LO$S OF 0FFSITE POWER. THIS SENSITIVITY INCLUDED THE REACTOR COOLANT PUMP TRIP STRATEGY CONTAINED IN THE FORT CALHOUN UNIT 1 EMERGENCY OPERATING PROCEDURES THE RESULTS OF THE SENSITIVITY CONFIRMED THE LOSS OF 0FFSITE POWER ASSUMPTION IS CONSERVATIVE i

'x .

@MCG G C .

I f  !

[ REYlSED_N0IRUMP EM_ EOR _CE_S_ENSIILVIIfES x

! FUEL BURNUP

/o THE LIMITING TIME IN LIFE OF FUEL FOR SMALL BREAK LOCA DEPENDS ON WHETHER CLAD BURST IS CALCULATED TO OCCUR. THEREFORE A BURNUP STUDY IS REQUIRED TO DETERMINE THE LIMITING TIME IN LIFE.

SENSITIVITY STUDIES FOR THE FORT CALHOUN FUEL DETERMINED THAT BEGINNING 0F LIFE FUEL WAS LIMITING AND NO CLAD BURST OCCURS.

o INTEGRAL FUEL BURNABLE ABSORBERS THE LIMITING TIME IN LIFE OF IFBA FUEL ALSO DEPENDS ON WHETHER CLAD BURST OCCURS.

THEREFORE SENSITIVITY STUDIES ARE REQUIRED TO DETERMINE LIMITING TIME IN LIFE AND IF IFBA FUEL IS LIMITING WITH RESPECT TO NON-IFBA FUEL.

SENSITIVITY STUDIES FOR FORT CALHOUN DETERMINED BEGINNING 0F LIFE IFBA FUEL RESULTED IN THE SAME PCT AS NON-IFBA FUEL.

i j

N i

s / I

\ I

@ m GLC REGHLAIRRLCDMELIANCE o 10 CFR 50, APPENDIX K NUREG-0737 THE WESTINGHOUSE ECCS EVALUATION MODELS USED FOR THE ANALYSIS OF A CE NSSS ARE BASED ON WESTINGHOUSE EVALUATION MODELS WHICH ALREADY COMPLY WITH THESE REQUIREMENTS.

MODIFICATIONS FOR THE MODELING 0F A CE NSSS DID NOT CHANGE ANY OF THE

" BUILT IN" APPENDIX K MODELING FEATURES.

N y

(.

@ m dLC

~

REGULA10RLCOMELIANCE X

K\

o 10 CFR 50.46 PEAK CLADDING TEMPERATURE MAXIMUM CLADDING OXIDATION MAXIMUM HYDROGEN GENERATION C00LABLE GE0 METRY LONG TERM COOLING 4

.xiN

\ /I,,

' 3 y i ,

@ INI i

/.- NI  !

,/ REGilLATORY C00MELIAMCI PEAK CLADDING TEMPERATURE CRITERION: THE CALCULATED MAXIMUM FUEL ELEMENT TEMPERATURE SHALL NOT EXCEED 22000F.

PEAK CLAD IEMPERATURE IS A DIRECT OUTPUT OF THE LOCBART CODE IN THE BART FOR CE EM AND THE LOCTA-IV CODE IN THE NOTRUMP EM FOR CE, AND IS A REPORTED ANALYSIS RESULT.

i f\ d I\ /

i

'N ,'

I \,. j-j

h l[(dl]

1 I

i7' g1 '

1

/

REftU1AIDRLCOMP_LIANCE  ;

/

MAXIMUM CLADDING OXIDATION CRITERION: THE CALCULATED TOTAL OXIDATION OF i THE CLADDING SHALL NOWHERE EXCdED 0.17 TIMES THE TOTAL CLADDING THICKNESS BEFORE OXIDATION.

THE LOCBART AND LOCTA-IV CODES CALCULATE LOCAL -

CLADDING OXIDATION THROUGHOUT THE LARGE BREAK AND SMALL BREAK TRANSIENTS RESPECTIVELY. THE '

GREATEST LOCAL CLADDING OXIDATION (USUALLY AT THE HOT ROD BURST LOCATION) IS A REPORTED ANALYSIS RESULT.

I lI\s

) N '

/

/

'u ^,

c'

~% _ ,/ l

_ i

I .. NI K

I REGULATORY C M I.IANCE N\

MAXIMUM HYDR 0 GEN GENERATION \

CRITERION: THE CALCULATED TOTAL AMOUNT OF HYDROGEN GENERATED FROM THE CHEMICAL REACTION OF THE CLADDING WITH WATER OR STEAM SHALL NOT EXCEED 0.01 TIMES THE HYPOTHETICAL AMOUNT THAT WOULD BE GENERATED BY ALL THE METAL IN THE CLADDING CYLINDERS SURROUNDING THE FUEL, EXCLUDING THE CLADDING SURROUNDING THE PLENUM VOLUME, WERE TO REACT.

LOCBART HAS RECENTLY BEEN UPDATED TO PROVIDE A CONSERVATIVE ESTIMATE OF HOT ASSEMBLY WIDE AVERAGE ZIRC/ WATER REACTION REPLACING GENERIC VALUES PREVIOUSLY REPORTED FOR CORE WIDE ZIRC/ WATER. A CONSERVATIVE ESTIMATE CAN ALSO BE CALCULATED BASED OH LOCTA-IV OUTP'IT. THE CONSERVATIVE ESTIMATE IS COMPARED TO THE REGULATORY LIMIT FOR VERIFICATION, UPON VERIFICATION, A VALUE OF < 1.0% IS REPORTED.

^

I\x l c

,/

'iN ji I

^

l I I .

REGULATORY CQMP1IANCE C00LABLE GE0 METRY CRITERION: CALCULATED CHANGES %N CORE GEOMETRY SHALL BE SUCH THAT THE CORE REMAINS AMENABLE TO COOLING.

AN ACCURATE GEOMETRIC REPRESENTATION OF THE CORE IS MODELED IN THE BART FOR CE EM AND THE NOTRUMP EM FOR CE. THIS MODELING WILL INCLUDE PREDICTED ALTERATIONS IN CORE GEOMETRY RESULTING FROM A DESIGN BASIS LOCA (HYDRAULIC FORCES) AND/OR SEISMIC EVENT AS REQUIRED AS A CONDITION OF THE PLANT LICENSE. IT IS NOTED THAT THE BART FOR CE EM AND NOTRUMP EM FOR CE DO RQI CALCULATE CHANG ~~S IN CORE GEOMETRY (OTHER THAN ROD BURST),

BUT USE INFORMATION SUPPLIED BY THE NSSS VENDOR OR UTILITY AS INPUT TO ACCURATELY MODEL THE EXPECTED CORE GEOMETRY. GIVEN AN ACCURATE MODELING OF CORE GEOMETRY, CALCULATION OF A PCT NOT GREATER THAN 22000F CONFIRMS THAT GEOMETRY'S AMENABILITY TO COOLING.

x _

,/

l l

l I l

REGULATORY COMPLIARCI LONG TERM COOLING CRITERION: AFTER ANY CALCULATED SUCCESSFUL INITIAL OPERATION OF THE ECCS, THE CALCULATED CORE TEMPERATURE SHALL BE MAINTAINED AT AN ACCEPTABLY LOW VALUE AND DECAY HEAT SHALL BE REMOVED FOR THE EXTENDED PERIOD OF TIME REQUIRED BY THE LONG-LIVED RADI0 ACTIVITY REMAINING IN THE CORE.

LONG TERM HEAT REMOVAL BORON PRECIPITATION

\x \  !

x

,/ i

/

h I b ,I I

I I f -,

REGULALORY CMP 1IANCE LONG TERM HEAT REMOVAL l THE WESTINGHOUSE COMMITMENT FOR ASSURANCE OF LONG TERM COOLING IS IDENTIFIED IN WCAP-8339.  :

THE REACTOR CORE IS RECOVERED BY BORATED ECCS WATER HAVING A HIGH ENOUGH BORON CONCENTRATION TO MAINTAIN CORE SHUTDOWN. FOLLOWING SWITCHOVER TO THE RECIRCULATION PHASE, THE MIXING OF THE VARIOUS SOURCES OF BORATED AND UNB0 RATED WATER (I.E. RCS, SIRWT, SITS, AND OTHER SOURCES DUMPED ,

DIRECTLY TO THE CONTAINMENT SUMP OR INTO THE BROKEN RCS) MUST PROVIDE A SUFFICIENTLY LARGE BORON CONCENTRATION TO MAINTAIN THE REACTOR CORE IN A SUBCRITICAL STATE. NOTE THAT THIS EVALUATION OF LONG TERM EFFECTS IS SEPARATE FROM THE SHORT TERM CALCULATION PERFORMED WITH THE BART FOR CE EM AND NOTRUMP EM FOR CE. BECAUSE THE ABILITY TO MAINTAIN THE REACTOR SUBCRITICAL ON BORON ONLY IS LARGELY RELATED TO THE SPECIFICS OF THE CYCLE ENERGY REQUIREMENTS, THIS EVALUATION IS PERFORMED ON A CYCLE-BY-CYCLE BASIS, INDEPENDENT OF THE PCT, CLADDING OXIDATION, AND HYDROGEN GENERATION RESULTS.

/

'N /Ii i

'N  ;

~ l 1

REGULATORY COMPLIANCE  !

BORON PRECIPITATION ANOTHER FACET OF ENSURING LONG TERM COOLING CAPABILITY POST-LOCA IS TO PRECLUDE THE PRECIPITATION OF BORON FROM THE HIGHLY BORATED INJECTION WATER. PLATING OUT OF BORON ON THE FUEL ROD SURFACE CAN DETERIORATE HEAT TRANSFER, OR BLOCK CORE FLOW PATHS, YIELDING A CLAD HEAT-UP TRANSIENT BASED ON THE REMAINING DECAY HEAT. TO PREVENT STAGNATION IN THE CORE REGION FOR A COLD LEG BREAK WITH COLO LEG SI FLOW TRAVERSING THE DOWNCOMER TANGENTIALLY AND TRAVELING DIRECTLY OUT THE BREAK, THE RECIRCULATION PHASE IS SWITCHED FROM COLD LEG INJECTION TO HOT LEG INJECTION. THE MAXIMUM ALLOWABLE TIME FOR THIS SWITCHOVER IS A FUNCTION OF BORON CONCENTRATION REACHING THE CORE FROM

[ THE SUMP, CORE INITIAL POWER, ETC. AGAIN, THIS -

EVALUATION OF LONG TERM EFFECTS IS SEPARATE FROM THE SHORT TERM CALCULATION PERFORMED WITH THE BART FOR CE EM AND THE NOTRUMP EM FOR CE. ,

l l

l \ /

\ /

I

! \ ,/

'i\ j/j ,

l l

T h I

((l]

I CONCLUSION OF WCAP 13321-E THE REPORT PRESENTED THE DESCRIPTIONS, APPLICATIONS, LIMITATIONS, AND LICENSING HISTORY FOR THE WESTINGHOUSE ECCS EVALUATION MODELS FOR THE COMBUSTION ENGINEERING NSSS. ,

THE LARGE BREAK MODEL, THE 1981 + BART FOR CE NSSS EVALUATION MODEL HAS BEEN DEVELOPED BY MODIFYING EXISTING LARGE BREAK ECCS CODES TO INCORPORATE FEATURES OF THE CE DESIGN. THIS NEW CODE SEQUENCE, INCLUDING THE MODIFICATIONS FOR CE NSSS DESIGN, CONSTITUTES AN EM IN COMPLIANCE WITH THE REQUIREMENTS OF 10 CFR 50, APPENDIX K.

THIS MODEL IS ACCEPTABLE FOR USE IN FINAL SAFETY ANALYSIS REPORT (FSAR) LARGE BREAK LOCA ANALYSES TO DEMONSTRATE ACCEPTABILITY OF THE ECCS FOR THE CE NSSS.

THE SMALL BREAK MODEL, THE NOTRUMP EM FOR CE NSSS HAS BEEN PREVIOUSLY DEVELOPED AND REVIEWED FOR THIS APPLICATION. REFERENCE INFORMATION RELATING TO THIS MODEL HAS BEEN UPDATED TO REFLECT CURRENT TECHNOLOGY. THIS EM SATISFIES l THE REQUIREMENTS OF 10 CFR 50 APPENDIX K, AS I

WELL AS NUREG-0737, ITEM II.K,.3.30. THIS MODEL IS ACCEPTABLE FOR USE IN FSAR SMALL BREAK LOCA ANALYSES TO DEMONSTRATE ACCEPTABILITY OF THE ECCS FOR THE CE NSSS.

I\

x -

/, -

( ,

f

h I

((l]

MIXED VENDOR CORE DATA LIST (MVCDL

/ A DOCUMENT WHICH CONTAINS ALL FORT CALHOUN UNIT3 1 DATA REQUIRED TO PERFORM THE LARGE AND SMALL BREAK LOCA ANALYSES THE DOCUMENT MET Tile QUALITY ASSURANCE REQUIREMENTS OF BOTH WESTINGHOUSE AND OMAHA PUBLIC POWER DISTRICT EACH ITEM IN THE LIST CONTAINS THE SOURCE DOCUMENT FOR THE ITEM. THE SOURCES FOR THE DATA INCLUDED DRAWINGS, VENDOR TECHNICAL MANUALS, THE FORT CALHOUN UNIT 1 TECHNICAL SPECIFICATIONS, THE FORT CALHOUN UNIT 1 USAR, AND WESTINGHOUSE AND OMAHA PUBLIC POWER DISTRICT INTERNAL DOCUMENTS.

WESTINGHOUSE ENGINEERS SPENT SEVERAL WEEKS AT THE OMAHA PUBLIC POWER DISTRICT OFFICES IM OMAHA TO BECOME FAMILIAR WITH THE PLANT ANC ASSIST IN THE COLLECTION OF THE DATA. DURING THIS TIME, OMAHA PUBLIC POWER DISTRICT PERSONNEL WERE ADVISED OF THE INTENDED APPLICATION OF THE DATA AND NORMAL WESTINGHOUSE PROCEDURES USED FOR DATA COLLECTION. THIS INSURED THAT THE DATA PROVIDED WOULD BE CONSISTENT WITH THAT USED IN STANDARD WESTINGHOUSE LOCA ANALYSES.

A SAMPLE PAGE OF THE MVCDL FOLLOWS I

!\x ,

/

iN j j

E A f t @N RE\ il

1. V LM A. War ams t area atraat 4 l

• l A gameter vanner Enrnwn  !

i wet nome ism-il e Vouma pw nome ift') 10 996 SEC Sail 3564-C2 11'9 0 Meat transfer area (ft'l NA c Maximum eievete from vessel 24 341 SEC SAll-3584-C2 11,90 bottom ifti

c. Mnmum e.evation from vesset 24 341 SEC SAll 35H C2 11 90 '

bottom Iftl f

e. Flow area ttt') 3.142 SEC Sall-3544 C2 11 90

f. Tranant length (ft) 3$ SEC SAll 3584-C2 11 90

g. Hyoreunc diameter (ft) 20 SEC SAll 3664 C2 11 90 h Lees coeffletent See Secte J 0-C A 054 11-86

6. Metal rnese {tml 6046 E 232 412 k Metal surface eres (ft') 22.54 E 232 412

2. Downcomer repon from top of cold leg to Dottom of cold leg IS&2)

a. Volume ift') 34 030 SEC SAll 3544-C2 11/90 b, Heat transfer ares (fte) q A.

c. Maunum eestation from vested 28.341 SEC SAll 3&M-C2 11190 bottom (fti

d. Menrnum elevation from vessee 24 341 SEC-SAll 3544-C2 11/90 bottom (ft)

e. Flow area (fte) 18.990 SE C-SAtt-3544-C2 11/90

f. Tranest lengtn tft 1.893 S E C-S All-3864-C2 11/90

9. Hydraube Sameter (ft) 0 977 SEC SAll-3564 C2 11/90

n. Lose coeffwent See Section J 0-CA-064 11,88 i Metal mese (bm) 20481 SEC SAll-3544-C2 11 90

1. Metal surface area (ft') 125.97 SEE-SAll-3564-C2 11 90 3 Downcomer regeon from bottom of coed leg to top of enseed (343)

e. Volume (ft') 77.28 SEC SAtl-3584-C2 11 90 D. Heat transfer area Itt*) N.A.

c Mammum oneverion from vessel bottom ift) 24.341 SEC SAll-3544-C2 11190

d. Menemum onevation from veeses Dottom (ft) 21.112 SEG-SAll 3584-C2 11190

e. Flow area (ft') 23 927 SEC-SAtl-3544-C2 11'90

f. Traneet length (ftl 3.229 SEC SAll-3544-C2 11/90

g. Hyoraunc someter (ft) 1.385 SEC-SAll-3644-C2 11190

n. Lose coefficeent ses Section J 0-CA-064 tute

4. Metal mese ihm) 40079.7 SEC SAll-3544-C2 11/90 L Metal etainee area (ft*) 223.1 SEC SAu-3544-C2 11/90

4. Downoomer region from top of tnormal em to bottom of ttiermal arteed (Sb4)

a. Volume (ft') 247.02 SEC-SAtl-3544-C2 11 90 D. Heat trenefer area (ftel N.A.

c. MAasmtets eievetsen from voosei bottom Ift) 21.112 SEC-SA41-3584-C2 11 90

d. Mesmum esevation from vessee bottom (ft) 7.445 SEC-SAll.3584 C2 11/90

e. Flow area (ft*) 18.074 SEC SAll.3544-C2 11 90

f. Transet lengtti 13 647 SEC-SAll 3564-C2 11<90

g. Hydrausic samster (ft) 0.527 SEC-Sali-3584 C2 11'90

n. Lose coesncient See Sect w J 0-C A-064 11/99

1. Metal maad temi 206381. SE C-S Ail-3584-C2 11t90 l, Metal arface area (ftel 1874 68 SEC SAll-3844-C2 11#90 Page 1 of 18 /

\, /

xN /

/

l i \ --.6

/ j  ;

@ l I I

l 7 LARGE BREAK LO_CA ANALYSIS METHOD OF ANALYSIS o 1981 + BART FOR CE NSSS LARGE BREAK LOCA ECCS EVALUATION MODEL LOCA EM (BART FOR CE EM)

WCAP-13027-P

./

/

oN /i l

@ l

((l{

l

[ LARGE BREAK ANAliSIS LIMITING RESULTS AND LIMITING A

,/ X ANALYSIS 10CFR50.46 RESULT LIMIT o PEAK CLAD TEMPERATURE 2066 22000F MAXIMUM CLADDING OXIDATION 5.77% 17%

TOTAL HYDR 0 GEN GENERATION <1% 1%

o LIMITING BREAK - DOUBLE-ENDED COLD LEG GUILLOTINE (DECLG)

CD = 0.4 BASED ON SPECTRUM SENSITIVITY STUDY EXAMINING 0.4, 0.6, AND 0.8 DISCHARGE COEFFICIENTS.

CONSISTENT WITH BART FOR CE EM METHODOLOGY DESCRIBED IN WCAP-13027-P.

o BREAK LOCATION - COLD LEG BREAK >

CONSISTENT WITH BART FOR CE EM METHODOLOGY DESCRIBED IN WCAP-13027-P.

'\ /

\ /

j 'N /

@ I Ib l

LARGE BREAK ANALYSIS

[ LIMITING RESULTS AND LIMITING A N

/ 3 O POWER AVAILABILITY - LOSS OF 0FFSITE POWER CONSISTENT WITH BART FOR CE EM METHODOLOGY DESCRIBED IN WCAP-13027-P, A SENSITIVITY

STUDY WAS PERFORMED TO EXAMINE LOSS OF 0FFSITE POWER AND NO LOSS OF 0FFSITE POWER ASSUMPTIONS. RESULTS OF THE STUDY SHOWED THAT THE NO LOSS OF 0FFSITE POWER ASSUMPTION YIELDS A HIGHER PCT (~600F) FOR THE LIMITING FT. CALHOUN Cn = 0.4 CASE.

O ECCS AVAILABILITY - MINIMUM SAFEGUARDS CONSISTENT WITH BART FOR CE EM METHODOLOGY DESCRIBED IN WCAP-13027-P, A SENSITIVITY STUDY NAS PERFORMED TO EXAMINE ECCS-AVAILABILITY ASSUMPTIONS. RESULTS OF THE STUDY SHOWED THAT THE MINIMUM SAFEGUARDS (LOSS OF A LOW PRESSURE SI PUMP) ASSUMPTION YIELDS A HIGHER PCT (~340F) FOR THE LIMITING FT. CALHOUN CD = 0.4 NO LOSS OF 0FFSITE POWER CASE BREAK. j O LIMITING TIME IN LIFE - BEGINNING 0F LIFE (0 MWD /MTU)

CONSISTENT WITH BART FOR CE EM METHODOLOGY DESCRIBED IN WCAP-13027-P.

d

\x /

ix / i i 'N ,/'I i

= ,

@ l (hl{  ;

LARGE BREAK ANALYSIS N LIMITING RESULTS AND LIMITING ASSUMPTION o LIMITING AXIAL POWER DISTRIBUTION -

8.75 FT. PEAK, FRT = 1.80, ASI = -0.16 ASIU CONSISTENT WITH BART FOR CE EM METHODOLOGY DESCRIBED IN WCAP-13027-P, A SENSITIVITY STUDY WAS PERFORMED TO IDENTIFY THE LIMITING LB POWER DISTRIBUTION FOR FT. CALHOUN.

RESULTS OF THIS STUDY APPEAR IN APPENDIX B OF WCAP-13027-P.

o LIMITING FUEL TYPE - NON-IFBA CONSISTENT WITH BART FOR CE EM METHODOLOGY DESCRIBED IN WCAP-13027-P, A PLANT-SPECIFIC, FUEL-SPECIFIC SENSITIVITY STUDY FOR FT. CALHOUN EXAMINING IFBA AND NON-IFBA FUEL WAS PERFORMED. RESULTS DEMONSTRATED THE NON-IFBA FUEL TO BE LIMITING (~150F).

'\ /

'N /

'l /;,

FORT CALHOUN LARGE BREAK LOCA ANALYSIS

\

INPUT PARAMETERS AND ASSIN TIONS

\

NSSS Power - 102% of 1500 Nt 1530 Hwt Peak Linear Heat Rate - at 102% of 1500 St 15.5 Kw/ft Radir' 'mking factor (f/) = 1.80 Haximus A1lowable Peaking factor (f ) = 2.545 Axial Power Distribution See figure 3-2 Reactor Coolant System Pressure = 2l00 psia Reactor Coolant System flow Rate = 196,000 gpm Reactor Inlet Temperature = 54 5 *f Reactor Trip Signal (including uncertainties) = 1728 psia, Pressurizer Pressure LOW SI Signal (locluding uncertainties) = 1578 psia, Pressurizer Pressure LOW-LOW l Safety injection Tank Water volume = 825 f t*/ Tank Safety injection Tank Hinimum Pressure = 255 psia .

Steam Generator Tube Plugging Level = 6% (Uniform)

? l

.w 1,0 j -

x

' 0.90 /

O'.80 / \

a 0.70 / \

E 0.60 C 0.50 I \

2 h

0.40 0.30 l \ p 0.20 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Helgnt (f t)

Fort Calhoun Large Break -0.16 ASI Power Shape FORT CALHOUN LOSS-0F COOLANT ACCIDENT REPORT Figure 2-2 Large Break LOCA Power Shape

\N /

/

!'N ~/ii ,

l I

l E Ml}j(IM f "

FORT Call 100N LARGE BREAK LOCA ANALYSIS N

flREAK SPECTRUM SENSITIVITY ANALYSIS Rest 1LTS HIN. SI FLOW HIN.Sl FLOW HIN. SI FLOW f'. = 1.75 F'. = 1. 7 5 f'. = 1. 75 DEf t G Cm=0.6 DECt G Cm=0.8 REST!LTS DECt G Cm=0.4 1869. 1815.

Peak Clad Temperature ('F) 1981.

9.25 9.25 9.25 Peak Clad Temp. Elevation (ft.)

113.9 98.3 86.8 Peak Clad Temperature time (Sec) 2.98 2.88 2.38 Max local Zr/ IIA Reaction (%)

<l.0 Total Zr/HA Reaction (%) <l.0 <l.0 47.4 69.5 61.1 l Ilot Assy. Burst Time (sec.)

8.75 9.00 8.75 flot Assy. Burst Elevation (f t.)

41.0 35.2 38.8 I .. Blockage on Hot Rod (%)

I .

w h

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

y

'. l)QQll

~

FORT Call 10UN LARGE BREAK 10CA ANALYSIS

/ LARGE BREAK LOCA RESULTS HIN. SI FLOW, HAX. 51 FLOW, Mt.i. 51 FLOW, F,,' = 1.80 F,,' = 1.80 F,,' = I.80 NO LOSS OF OFFSITE LOSS OF OFF5ITE LOSS OF OFFSITE F0hTR, POWER, POWER, DECLG C,.=0.4 DECLG C,=0.4 DECtG Co=0.4 RESULTS 2006. 2066. 2032.

Peak Clad Temperature (*F) 9.50 9.25 9.50 Peak Clad Temp. Elevation (Ft.)

94.4 117.1 Peak Clad Temperature Time (Sec) 118.5 3.38 5.77 3.66 Max local Zr/II,0 Reaction (?6) l

<1.0 <1.0 Total Zr/II,0 Reaction (%) <l.0 51.1 51.2 -

llot Assy. Burst Time (sec.) 51.2 8.75 8.75 8.75 Ilot Assy. Burst Elevation (f t.)

39.0 37.6 38.8 Blockage on flot Assembly (%) .

i-

l ll.ddl5-FORT CAtl100N LARGE BREAK LOCA ANALYSIS LARGE BREAK SEQUENCE OF EVENTS MIN. 51 FLOW MIN. 51 FLOW HIN. 51 FLOW DECLG C =0.4 DECtG C =0.6 DECtG C.=0.8 0.0 0.0 0.0 Start 0.60 0.59 0.59 Rx Trip Signal 0.97 0.77 0.67 5.1. Actuation Signal Is 22.80 16.80 14.00 3.1. Tank injection 31.87 31.67 31.57 l

Pump Injection Begins 28.92 20.59 17.48 End of Bypass 28.92 20.59 17.48 End of Blowdown l 39.34 31.73 28.52 Bottom of Core Recovery 94.92 90.14 88.01 S.I. Tanks Empty l

• Note: All times are in seconds.

l 1

l _-

60.O N N . - - . _

50.0 7

m

$ A0.0 w

g 30.0 s .

Y f

20.0 0

5 v

10.0 0.0 0.0 50.0 100.0 150,0 200.0 250.0 TIME (SEC) l FORT CALHOUN LOSS OF COOLANT ACCIDENT REPORT Figure 2-8 l Containment Pressure i No Loss of Offsite Power l DECLG (CD.0.4) l

/ .

I .\. ,/ j 1

@ m dLC l l i

i i

2249.

' l 1:00, 1

l l I

1750.

3 3'

h 'b j I

ale. 1

y, n ._

E, , [, I N I l '

,,, ' > I i x i i l I I X i  !

0 l I N i

0. 6. 10. 15. 20. 25. 10.

ftnt t1ECl FORT CALHOUN LOSS OF COOLANT ACCIDENT REPORT Figure 2-4 Core Pressure Transient No Loss of Offsite Power DECLG (CD-0.4)

/

i

'i- fi>

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

d, N .i it.

i I j j .

i  ! l l l 11.1' i

lr-Co' WW C.NE A.I l i l l l i l l l ,

, it.

b

- 12. t . ,

7,1 ft ..

i.

i

'ac. d. ... . i . i,.. ... i... i 2... 2,.. .... 2. 2... i .. . n . .

finC iSCCI FORT CALHOUN LOSS OF COOLANT ACCIDENT REPORT Figure 2-11 Reflood Transient Core and Downcomer Levels No Loss of Offsite Power DECLG (CD-0.4) t

/

\\

s - ,

x__ ,/ l ,

l l I l

l l 2200. v- --

I i l

l

- m ,.

l ,\

8000. A' I,

i l

sen.

1600.

1400.

=

/y N

!!00.

E

- 10 0 v .

3 000.

600, 400, 4 200. -

0. 50. 100. 150. 200. 250, 300, 350.

TIME IS1 FORT CALHOUN LOSS OF COOLANT ACCIDENT REPORT Figure 2-18 Peak Cladding Temperature No Loss of Offsite Power DECLG (CD.O.4)

I\x

/

x - . i

! g p l

@ OGC

/ .SMALL BREAK _LOCA ANALYSLS \- -

/ 'N METHOD OF ANALYSIS o NOTRUMP (SYSTEM HYDRAULIC CALCULATION)

WCAP-10054-P-A NOTRUMP SB LOCA EM FOR W PLANTS WCAP-10054-P-A, PREVIOUS NOTRUMP SB ADDENDUM 1 LOCA EM FOR CE PLANTS WCAP-13027-P REVISED NOTRUMP SB LOCA EM FOR CE PLANTS O LOCTA-IV (FUEL ROD CLAD HEATUP CALCULATION)

WCAP-8301 LOCTA-IV CODE DESCRIPTION WCAP-10054-P-A, ADDENDUM 1 PREVIOUS NOTRUMP SB LOCA EM FOR CE PLANTS WCAP-13027-P REVISED NOTRUMP SB LOCA EM FOR CE PLANTS I /1

\'N -

/ i I

xN - j

/ '

@ m dLC I N L 0 0 T C E

CORE PRESSURE CORE #

U M

RN.W1XM N AND FUEL R00 POWER P

HISTORY O< TIME < CORE COVERED V m r

I FORT CALHOUN LOSS OF COOLANT ACCIDENT REPORT Figure 1-1 Code Interface Description for Small Break Model l

.s , ,

i

\ / <

E U M LJ w

I I

/

\

FORT CALHOUN SMALL BREAK LOCA ANALYSIS INf.d PARAMETERS AND ASSUMPTIONS

= 1530 Mwt N555 Power - 102% of 1500 Mwt

= 15.5 Kw/ft Peak Linear Heat Rate - at 102% of 1500 Mwt RadialPeakingFactor(F,l) = 1.80 l

Haximum Allowable Peaking Factor (F,) = 2.545 See Figure 3-2 Axial Power Distribution

= 2100 psia Reactor Coolant System Pressure

= 196,000 gpm Reactor Coolant System Flow Rate Reactor Inlet Temperature = 545 "F Reactor Trip Signal (Including uncertainties) = 1728 psia, Pressurizer Pressure LOW

= 1578 psia, Pressurizer Pressure LOW-LOW 51 Signal (Including uncertainties)

Safety Injection Tank Water volume = 825 f t'/ Tank

= 255 psia Safety Injection Tank Minimum Pressure steam Generator Tube Plugging Level = 6** (Uniform)

MSSV Setpoint Uncertainties =13% Nominal setpoint pressure 23*4 Valve accumulation pressure

<f M

I I vv

--~

FORT Call 100N SMAlt BREAX LOCA ANALYSIS SHAll BREAK SEOUENCE OF EVENTS COLD LEG BRCAK COLD LEG BREAK COLD LEG BREAK

.022 50 FT .049 50 FT .087 50 FT 0.0 Sec 0.0 Sec 0.0 Sec Start 23.0 Sec 10.6 Sec 7.2 Sec Reactor trip Signal 36.6 Sec 17.2 Sec 10.5 Sec SI Actuation Signal 67.5 Sec 48.1 Sec 41.4 Sec Pumped 51 Begins 2178.5 Sec 1095.1 Sec 710.7 Sec Top of Core Uncovered NA 932.9 Sec S.I. Tank Injection Begins MA 3015.8 Sec 1898.0 Sec 1022.1 Sec PCT Occurs 4713.8 Sec 3100.3 Sec 1368.9 Sec .

Top of Core Recovered

' - - - ~ - - - ----

7 ~'--' -

W

~

~

llO 01' FORT CALHOUN SMALL BREAK LOCA ANALYSIS SMALL BREAK RESULTS BOC IFBA BOC IFBA BOC IFBA COLD LEG BREAK COLO LEG BREAK COLD LEG BREAK

.022 50 FT .049 50 FT .087 50 FT RESULTS l

1076. 1444. 1166.

Peak Clad Temperature (*F) 10.25 10.25 10.00 Peak C1 id Temp. Elevation (f t.)

3075.8 1898.0 1022.1 Peak C14d Temperature time (Sec) 0.05 0.40 0.03 Max Local Zr/II,0 Reaction (%)

Max Locai. Zr/H,0 Rxn Elev (Ft.) 10.25 10.25' 10.00 Total Zr/II,0 Reaction (S.) <l.00 <l.00 <l.00 NO BURST NO BURST NO BURST Hot Rod Burst Time (sec.) '

NA NA NA Hot Rod Burst Elevation (Ft.)

l l

w

. . . . - ' . .. . . === y

~= ,

i

. i l 1

. e. m.

I l l 2200.

f 2eaa.

7

/ 1928.

g1600.

w 14es.

a i

, y12se.

5

- tees.

N R

e \

g saa.

_ sea.

\ -.s 4es. -

y  %

2sen , saa, isee, isse. seen. msaa, saae, ssas.

TINC (SEC)

FORT CALHOUN LOSS OF COOLANT ACCIDENT REPORT Figure 3-9 Set 11 Break LOCA (.049 ft2 )

RCS Depressurization i

\

/

/ 1 i \

/ i!

I _. l

i @ m dLC l sa. 7 1 N 58.

28.

25.

Y -

d g24.

E e

w 22.

g h TOP OF CORE (19.8 feet)

29. _

18.

,/

I. EM. 1900. IGM . 2000. 2500. 8000. 5G00.

T!!C (SEC)

FORT CALHOUN LOSS OF COOLANT ACCIDENT REPORT Figure 3-10 2

Small Break LOCA (.049 ft )

Core Mixture Height l

\ /

/

e \ ,'

/ h  !

o . , - ,

. I llec.

1800.

1800.

1800. -__m

, 1800.

g

/ \

1900.

/ _

. E *)D. --

~

$00.

/

700.

600.

$00. g th00. 1200. 1400. 160 1000. 2000. 2200. 2400. 1600.

FORT CALHOUN LOSS OF COOLANT ACCIDENT REPORT Figure 3-11 Small Break LOCA (.049 ft2 )

Peak 01 adding Temperature l\ /

,ix x x  ! l fi. )

i i

IhI I l l 1 7 _SMLL BREAK ANALYSIS RESULIS 7

/ ANALYSIS 10CFR50'46 '

v RESULT LIMIT \J; O PEAK CLAD TEMPERATURE 1444 22000F l MAXIMUM CLADDING OXIDATION 0.40% 17%

TOTAL HYDR 0 GEN GENERATION <0.4 % 1%

0 LIMITING BREAK - 0.049 FT2 (3 INCH DIAMETER) COLD LEG BREAK THIS IS THE LARGEST BREAK SIZE WHICH RESULTS IN PRIMARY PRESSURE EQUALIZATION ABOVE THE SAFETY INJECTION TANK AND LOW PRESSURE SAFETY INJECTION CUT IN PRESSURES.

O LIMITING TIME IN LIFE - BEGINNING 0F LIFE (0 MWD /MTU)

NO CLADDING BURST OCCURRED FOR LOW AND MEDIUM BURNED FUEL. THEREFORE, BEGINNING OF LIFE FUEL WHICH HAS THE SMALLEST PELLET-CLAD GAP IS LIMITING.

O LIMITING FUEL TYPE - IFBA AND NON-IFBA SAME SINCE THE LIMITING PCT WAS LOW AND NO CLAD BURST OCCURRED, BOTH NON-IFBA AND IFBA FUEL RESULTED IN THE SAME PCT.

l i

\

l

_________.__-_m - _ _

h El ((l]

-[ \ q

, ADDITIONAL SMALL BRE_AK SENSITIVITIES i

o POWER AVAILABILITY - LOSS OF 0FFSITE POWER SENSITIVITY WAS PERFORMED ASSUMING NO LOSS OF 0FFSITE POWER.

SENSITIVITY INCLUDED THE REACTOR COOLANT PUMP TRIP STRATEGY CURRENTLY CONTAINED IN THE EMERGENCY OPERATING PROCEDURES.

STUDY CONFIRMED THAT THE LOSS OF 0FFSITE POWER ASSUMPTION IS CONSERVATIVE.

O BREAK LOCATION - COLD LEG BREAK SENSITIVITY STUDIES FOR THE NOTRUMP EM AS APPLIED TO THE CE NSSS (PERFORMED IN WCAP 10054-P-A ADDENDUM 1) DEMONSTRATED THAT THE COLD BREAK RESULTS IN THE MOST LIMITING PCT FOR A CE NSSS.

SIMILAR STUDIES PERFORMED BY COMBUSTION ENGINEERING ALSO SHOWED THE COLD LEG LOCATION TO BE LIMITING FOR SMALL BREAK LOCA.

A

\xix y

-7i i

l l_. l

I N$lb ii e 1

/ CONCLUSIONS x'N -

! RESl!LTS AND SMLL BREAK LOCA ANALYSES HAVE DEMONSTRATED OF THE FORT CALHOUN UNIT 1 THL W OUACY OF THE ECCS SYSTEM AND MEET THE APPLICABLE REQUIREMENTS OF 10 CFR 50.46 PARAGRAPH (a)

(1) PEAK CLADDING TEMPERATURE THE CALCULATED MAXIMUM FUEL ELEMENT CLADDING TEMPERATURE SHALL NOT EXCEED 2200 DEGREES FAHRENHEIT (2) MAXIMUM CLADDING OXIDATION THE CALCULATED TOTAL OXIDATION OF THE CLADDING SHALL N0WHERE EXCEED 0.17 TIMES THE TOTAL CLADDING THICKNESS BEFORE OXIDATION.

(3) MAXIMUM HYDR 0 GEN GENERATION THE CALCULATED TOTAL AMOUNT OF HYDROGEN q GENERATED FROM THE CHEMICAL REACTION OF THE CLADDING WITH WATER OR STEAM SHALL NOT EXCEED 0.01 TIMES THE HYPOTHETICAL AMOUNT THAT WOULD BE GENERATED IF ALL 0F THE METAL IN THE CLADDING CYLINDERS SURROUNDING THE FUEL, EXCLUDING THE CLADDING SURROUNDING THE PLENUM VOLUME, WERE TO REACT.

t I,  ;

.\  ;

s j

, l

l l .

l l

i _

[ C0NCLLLS10NS. 'y - -

/ O C00LABLE GE0 METRY

\

BASED ON THE MAXIMUM HYPOTHETICAL FUEL GRID DEFORMATION RESULTING FROM MAXIMUM LOADS WITHIN THE DESIGN BASIS FOR FT. CALHOUN, INCLUDING LOCA LOADS, CONSERVATIVE ASSUMPTIONS WERE INPUT INTO THE LARGE BREAK LOCA ANALYSIS CONSERVATIVELY TO REFLECT CORE GEOMETRY. AT UPPER ELEVATIONS OF THE A PERIPHERAL ASSEMBLY, CONSERVATIVELY ASSUMED TO BE THE HIGHEST POWERED ASSEMBLY, HYDRAULIC LOSSES WERE INCREASED TO SIMULATED THE LOCALIZED GRID DEFORMATION. THE RESULTS OF THE LARGE BREAK ANALYSIS BASED ON THESE ASSUMPTIONS DEMONSTRATED PCT NOT GREATER THAN 22000F WITH CLAD TURN-AROUND OF THE CLAD HEAT-UP. CONSISTENT WITH THE WESTINGHOUSE POSITION ON C00LABLE GEOMETRY (WCAP-8339), THIS CRITERION IS SATISFXED.

i 4

l '

x  !

s s i

)

l

y, -. .

@ l[ ( l[

[ C_0ElllS10NS l

0 LONG-TERM COOLING

/ ,

\

RECENTLY, STUDIES HAVE BEEN COMPLETED TO ADDRESS POST-LOCA LONG-TERM COOLING FOR FT. CALHOUN.

AN EVALUATION OF THE AVAILABLE BORON IN THE CONTAINMENT SUMP FOLLOWING A POSTULATED LARGE BREAK LOCA VERIFIED THAT A SUFFICIENTLY HIGH CONCENTRATION OF BORON WOULD BE INJECTED TO MAINTAIN THE CORE SUBCRITICAL FOLLOWING A POSTULATED LOCA.

A CONSERVATIVE ANALYSIS OF THE POTENTIAL FOR BORON PRECIPITATION FOLLOWING A POSTULATED LOCA WILL BE PRECLUDED IF SWITCHOVER TO SIMULTANEOUS HOT AND COLD LEG INJECTION AT 8.5 HOURS AFTER THE EVENT.

AN EVALUATION OF THE AVAILABLE ECCS FLOW RATES FOR THE VARIOUS LONG-TERM POST-LOCA SCENARIOS WOULD PROVIDE SUFFICIENT SI FLOW TO MAINTAIN CORE LEVEL AND PROVIDE ADEQUATE LONG-TERM COOLING FLOW.

CONSISTENT WITH THE WESTINGHOUSE POSITION ON C00LABLE GEOMETRY (WCAP-8339), THIS CRITERION IS SATISFIED.

I >

j\\ /

! i

'x - I j _ -

G

s