ML20236R969
ML20236R969 | |
Person / Time | |
---|---|
Site: | Cooper |
Issue date: | 07/21/1987 |
From: | Casey D, Earle R GENERAL ELECTRIC CO. |
To: | |
Shared Package | |
ML20236R958 | List: |
References | |
NEDC-87-153-ATT, NEDC-87-153-ATT-A, TAC-59084, NUDOCS 8711240141 | |
Download: ML20236R969 (10) | |
Text
, . - _- - _
.3
- c +
- .;;
,' N c u c- ' 5 't - pJ
~ ..., ,,, ,
.. f. ' , . , k Ya g,f m gv1 h k ,
n <
, j g .
l
, p. -
i i
i
..a. a+ *. - - - .- .
... _ ..., ... l I>_. '
~ . . . - - - - . . . . - . - .,. -.
I x' , ;y , ,s .. . . - . . . - - - . . - ..a~ a .. - -.- .-. . -
p ' + ;
'- PREPARED FOR NEBRASKA PUBLIC, POWER DISTRICT
- ,. u
.t. ;
' b
, COOPER NUCLEAR STATION
- 1 e ,
d JULY 21,.1987 !
t' i
1, 1
l j
1 E6c/LI R 4.-
I PREPARED BY:' R. T. EARLE' l
+ a 1 1
%. 4. 2 VERIFIED BY: D. F. CAS - .
l
- 8711240141.871118 >
i PDR ADOCK 05000298.' )
, , P . PDR4 -
)
1 l
a .. -
- RTE'87.01 t
't n , * . u'-_ -
, , y e o c '87- 153
'4.. A Huhme.,f k l l
DISCIAIMD1 OF RESPONSIBILITY I
- This' document was prepared by or for the General Electric Company. Neither the General Electric Company nor any of'the contributors to this document:
A. Makes any_ warranty or representation, express or implied, with respect t o~ the accuracy,- completeness, or usefulness of the information
't contained in this document, or that the use of any information disclosed in this document may not- Infringe privately owned rightst or, 6- B.
~
- Assumes any responsibility for liability or damage of any kind which l may result.from.the use of any information disclosed in this document.
1
= .
4 t
l l
1 i
l 1
_ _ _ _ , _ _ _ ___._m_mm------ - - - - - - - - - - - - - - - - - - - - - - - - - - ' - -
,,w- ,-
- h. q:
, N E 0e ' 81. 153 b)9p2
? * - ,
hadmLE k
- m. +ls h '
c: ,
-.o .j ' .g n >L-w . . . - - . . ..- --
i .t m iThis document > was [ prepared for Nebraska Public Power Distri c t to address the x :n 4 Lminimum concentration. requirements of ~ the Standby Liquid Control System (SILS) h.
'at the. Cooper Nuclear. Station. The plant specific values used to determine the . minimum SILS . sodium pentaborate solution. regtf rements are the same as the . minimum values provided in the system Technical. Specifications.
1 , .
- This report uses L the revised procedures for demonstra, ting compliance with the NRC equivalentLeontrol capacity concept. The plant-specific parameters used in
%;u.
..the analysis are minimum values rather than the nominal values'that were used in f ,, ' :l , s. .the' original: concept-derivation.
t {4 I
/$k ,
.i, f s ., <
.'I-
- ] ,
1 4 q (.. 5
> j.
- (;
I v
' Y 3 J, __________________O
'- - a, .f- .J'-
J ./ [+ / $ , ' '- '. , ' I T. ., ,:.: , f/."4 ,g+h,
, ' ' ', y ~ '
JR, g, .- . zg.
;})EOc. 8~l-}g3 )
hh h ,? f, ',' ' k} }sch~ rd k. ) ,w x , <.
~ r - .
..V +. . < : " [;%/f,,1r,4.L ,s
.u , ,, .,
- m. . . s.._ . .o ,
, ._.y ,
i t> l"c .);; u 1 I
; i
.SSO k., s pga4c,gg- i L , V4 @(' TABLE OF CONITNTS @- f= .
- 1. ,.
@ ~ 103 , c < 3
,$'i' , y, ' ! ! , ;. ; p; , . m_ '
y- . w ' '< p 3
,3.. .. e s i
nG; r
* < .. s ii o -
l
#;_, , : ~ +! ; , l Page m , ,
s,. .. 't f
,r h-.iI'f s s' s ;;.
- m. .
ABS'!11ACP 'Ii 3.- (
; ,a ., .
r
, y , , a r s , s. < - * 'e f W',}' ,' >
y :1g , INTRODUCrlON '
- 1-1 l
1 '~,_
, l' ;;p, my.. 3 , y l
i
,. > k , ,., '. , ,
X< j
,,3, . DISCUSSION 3
_2-1
.) + ~ ."3.',,.,
a . + J i.
- 2.1' Sif System Design Basis m 3 f,.i .
2-1 . a !
-t-l 3 ,, < ~
J2.2 NRC A'IWS 'Ru1e 2-1
-m ' % { ~
V .y,T - ,.- 3 .' . ANALYSISL 3-1 t b 1
- " t l
,,,e
[ T'-"
)
g
- a. ,
%1 3 4 , ,
1
- t f .
9
.y .K. :. .' 1 ' -e
- l 2
) &
l A i e A t N '.
-l ,
F a.' y. l [
;. ,ty j p , ;.. ' q f.
t - c ,- 1
' + '
a i
$g'li;;l.y bE ON Ol'ISI' p gg I. $ ,
- ,m ga j 1
- ,, 1 0 J* '
l ' ::t - tc.?4 c e? Lt . : L IRITGUCTION D ' g t! ;j. 1 n- ,i
! Netiraska'
}@fN 7 '
^ . Pubile. Power.? District - has. . requested - an ' evaluat ion of the. minimum Qs b,
Trequired ; concentration (weight. percent): of sodium . pentaborate . for the Cooper A. - Standby? Liquid . Cont rol L.Syst em. - The minimum concentration is to be . based. on- [p ' , 1 m y equivalency to the 86 gpm,:13-weight percent sodium pentaborate control capacity requirement 1. stated _ iri, the NFC A1WS rule '10CFR50.62. ~ Equivalency is calculated. y , J'
- .LusingLthe ratio:of specific' Cooper minimum values'to. reference plant values that ;
x > ~: the rule!!s based on.~
'we 3 x. .
y? , ForDCooper;4a minimum concentration.of 11.5' percent'is required. This is-based. m . J 7. d ., , : onithe assumptions ' thatL the. actual pump capacity'. Is equal to or exceeds the . R.$?
- total? min.imum pump? flow rate'.and ' the enrlehment of the sodium pentaborate. has b~ , . ..
1 Enot; changed.. "Also, it 9is assumed ' that : thef standby liquid control system has
.i 1
been properly modified.forftwo' pump operat' ion. 9; m .. '
.x ,
i
;i hk Ik. s l
5 .. , ! 4 .
.i ,;m *
' f . ,' . . .: 4. ; t 6 j . . .: 4: -: s s
. - 1 i
g ;) ,
' ~
R $ .h , , d: G
,()
b _J-'.,'
':.l. 'l ._ , ~
.-s
- i. . , 1-1 n, o; Off
l
%g:x
- y,? . ' '
;,; blE06 A7d/S3 s '
kNoh n V k ; _ .,4, n.:q , ygy'y'ggyggggy; g l &l 7, b&, m m 12;1G SIC System Design Basis Qh r.r u.i s
'l, U. .
lf gy " 1The generic. design basis for the SIC system is to provide a specified cold boron i I 4:; m #d9 1 b -'shutdowniconcentrationlt'o.th'e reactor vessel (described in NEDE 24222). The SIC f,' - .: r 5;.,1systemNatypicall'yjdesignedtoprovide.thespecifiedcoldshutdownconcentra-A) l d.i ., N tlon:. In jab'out - one . or: two L ho' u rs. . During. reload. licensing evaluations this l e.. ,l shutdown concent'rSilon;is verified by analysis to be adequate to render. the core s-i suberitical.: The; considerations in the reload evaluation are independent of-
', a ATWS and'lhjestion rate is not'directly considered.
h! - - - ThelA1WS rule' required addition:of!a new design requirement to the generic.SIE x f s sys t em1 design l basis., Changes Lto ' flow rate, solution concentration or boron ' t g&
.. . . i
- enrichment ,, toi meet J the 4 ATWS . Rul e , must not - Invalidate the original design l
, c. :. , ' tias i s'. + s ., , i o ,7- 2.2 :: NRC A1MS Rule ,_ (l ' ' \ '
- Paragraph 7(c)(4) of:10CFR50.62 states,. in parts i i
'"Each l bol_Ilng l water . reactor must have - a standby liquid . cont rol system i .'(SIG)'wlth:a minimum flow capacity and boron content equivalent in control 'capact ty[to,86. gallons l per minute of 13-welght ' percent sodium pentaborate 'solutlon." $
- The NRCj Staff has provided clarlficatlon- of equivalent control capactty
[(Reference 7)ss.follows:
'(!)?Thk " equivalent ~1n control- capacity" wording was chosen to allow , flexibility ' to the Implementat ton of the requirement. For example, the J equivalence can be obtained by increasing flow rate, boron concentration or !
- y boron' enrichment.
m, ;
,j.
y # lh, (
; .. 2-1 f $
g w '.. . . ; j e
*b m ' . _ _ _ _ _ _______________________________o
7,, zy , g ll Y'l h 61-IS3
. O G 0 C-gq.; )$ H n h e d A g' , ,
h ;'. 4 .. .> . > . ~ gj;;Y.". . (2).--The a86 gallons: per : minute and ,13-weight percent: sodium pentaborate-were 4'
'[ ; values used'in NEDE-24222, " Assessment of BWil Mi tigation of A'IWS, . Volumes I i+ :
and-11," December.1979, for BWil/4, BWR/S and BWR/6 plants with'a 251-inch. T ..)? ji. ' vessel 'inside ' diameter. That different values would be equivalent for pg - . smaller plants was recognized in NEDE-24222: 9n.
., :- m ,
Q ,' + ,
"The" flow rates: given here are normalized from a 251-inch diameter y Lvessel pirat~ to a .218-inch diameter vessel plant, i.e., the 66 gpm; , . control ~ liquid injection rate in a 218 is equivalent to 8? gpm in a- !
251. This Is done to bound the a Miss!s... (pp. 2-15 [NEDE-24222])." !
..(3) The .important parameters to consider in establishing equivalence are vessel M boron.concentrationLrequired'to achieve shutdown and the time required to c
a'hieve that vessel boron concentration. The minimally acceptable system should 'show. an equivalence in these parameters to the 251-inch diameter vessel studied in NEDE-24222. 0
'h a \ '9 e
J 2-2
. .. y i -4__.-. _ _ . , _ . __
y . o ... e , , l'?{q'li *x , W & G oc. g7,pgy I ts , y . i
' I.
s !l .(.. , h k;, ,j , '53 3 ANALYSIS .N
. 1 4 '
Thel NRC equivalent control, capact ty ~ concept of E the A'IWS rule is a' very . simple, . ]
- s .; ~ direct : criterion. It' . Is; not~ necessary ' to consider mixing etficiency or. to '4 3<
o d account.for plant-specific core nuclear characteristics, i 4 3
' 'e
- l
, < l Consequently', Cooper can dempnstrat'e: compliance withsthe equivalency requirement I j
y; W fi f.[thelfollowing/re'lationship.is shown'to be true: , a;
;4 b,. . . M 'q: 2511 C' E"' ' T E.:. , T ,..T T . ,.Tir.T >' 1 1)
I ' - (where the plant-specific parameters are defined as,. l
~
w
- Q.
=- minimum SICS flow rate.(one-pump:or two-pump as appropriate), gpm .
fj < mass.of water in the reactor vessel and recirculation system at a lM- .-= the hot rated condition,?lbs-I i
% LCS E=- 1 minimum sodlum pentaborate~ solution concentration, weight percent .-m ' .. E .. .=. . minimum expected B10" isotope'entichment'(19.8% for natural ^
bor'on)',4 atom percent g iThe' value of M251 (the: mass of water. In the: reactor. vessel and recirculation j system atirated conditions in the reference plant) is.628,300 lbs for a 251-inch .
~T : diameter el3WR/3/4~. (Reference 1);- This value- was ' calculated based on rated -{
temperature, rated void content, normal water: level, control rods fully wl.thdrawn, . expected minimum vessel . dimensions and nominal vessel internals dimensions. !
, 1 * .. Based on a; plant specific 'elculation of M, the Cooper Plant contains 489,993 J pounds.of water-(Reference 8).
I g i 1, d
, ; i . 3-1 ,
r <"'-............. .
w: , (Q .L,e g +' " wh
. N & D C-I ' 83 -I S3 0 j -
g
;j l d ; , ,.
@ :/ g , '
% X<
<y The:m NRC D requires c the: use.iof. minimum plant-specific' values toH demonstrate E ' compilan'ce with the1 equivalency; requirement.: Based on equatlon 1) with-natural - l ;bs on enrichment,-(the. ratio of--E/19.8 is equal to'one) Copper can demonstrate compila'nce'If the following. relationship is trues 7 ;.g Q, ^ M
'C > 13 T* 86 *-
ji ;Q", 628,300'
~
1
- J . >a
%y h,t Lwhere C inithis-:cas'e Is the:-minimum concentration (weight per cent) of sodlum j.;7 ," pekta' borate; and [Q j is the'... minimum allowed total. pump . flow rate (2 pumps
% Loperating). The . minimum fallowed' total pump " flow 'ratc, as obtained from (Reference'6 'E ls 2lx 38.2 = 76.4 gpm.- ~ ~'
%<- Usingithe current. Cooper. plant-specific values in'Eq'uation 2) gives a regulred-
, minimum,concentr'ation oft 11.5. weight' percent.. sodium pentaborate.
w S i 13 *' '86' '* _489,993
~C.>
L ,, 2 x 38.2: 628,300.- h ; ,Ci>.'11.412s11.5' - i a When;the; concentration.ls egual to or greater than 11.5 percent, Cooper meets or exceeds < the' NRC_ A'IWS rule equivalency requirements.
'The:same equation can be>used'to determine the minimum total pump flow rate for. =
afminimum' concentration.of 13.0 weight percent. 9 L , f i -Q> 13 * !M
- 86. l
' L E ~C M , 251 Q > .13
- 489,993
- 86 i
, ~ E .628,300 g 4 (Q > 67.07 m 67.1 gm At af minimum concentration equal to or greater than 13 percent, and a minimum L y. totali pump ' flow of .67.1 gpm, Cooper meets or exceeds the NRC A'IWS rule ; equivalency requirements. t .o ,
9 l .f; , 3-2
= _ _ _ _ _ . _ _ - -
. r . .y n y e oc. 87-1s3' (l'.n g ,.
jy s.w 1 A / /, d ,,,q p g c , .,
- 4. REFERENCES
{1l.- ' NEDE. ' 31096 - P, Response to NRC A'IWS Rule,10CFR50.69,, Dec.1985. p: ,; .
~
Y 2. gfS/N 275296, Union Pump . Pump Performance Data k, , 3.l lS/N 275297, Union Pump
- Pump Performance Data
, a .. ,
;l' 3,--
( 4. , 10CFR50.62, NRC A'IWS Rute, June' 1984
.p o
1 5.- 'NEDN-24222, . As'sessment of BWR Mitigat ion of A'IWS, December -1979 t
- 6. 22A2896AB, SICS Design Spec Data Sheet
.+.g- .~_
E' - 7 .- : USN11C Generic Leiter 85-03, Clarification of Equivalent Control Capacity T. , .
.for Stand y Liquid Sistems, January 28, 1985..
- 8. - NEDC-30857, Cooper A'Ih5 Assessment , Dec.1984.
1 4
)
q.. 1 i t t . 1 ><4 j l 4-1
$ _ . - - -a. a,_--.--.u-_-_-a._-}}