ML20236R969

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Attachment a to Standby Liquid Control Sys Control Capacity Equivalency Rept
ML20236R969
Person / Time
Site: Cooper Entergy icon.png
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)
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L-w i .t iThis document > was [ prepared for Nebraska Public Power Distri t to address the m c h. Lminimum concentration. requirements of ~ the Standby Liquid Control System (SILS)

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x '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, .the' original: concept-derivation. s. {4 t /$k I .i, f s., .'I-

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1g, INTRODUCrlON '

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3 y l i k,,., '. ,,3,. DISCUSSION _2-1 .) 3 j X< + ~ a. + J i. ."3.',,., f,.i

2.1' Sif System Design Basis 2-1 3

m a -t-l J2.2 NRC A'IWS 'Ru1e < ~ 2-1 3 { -m ~ V.y,T - ANALYSISL 3-1 3.'. t b 1 l

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1 J* l ' t - tc 4 c ? Lt. : L IRITGUCTION D .? g ;j. 1 e t! }@fN - Netiraska'. Pubile. Power.? District - has.. requested - an ' evaluat ion of the. minimum n- ,i 7 ^ Trequired ; concentration (weight. percent): of sodium. pentaborate. for the Cooper Qs b, [p ' - Standby? Liquid. Cont rol L.Syst em. - The minimum concentration is to be. based. on-A. 1 equivalency to the 86 gpm,:13-weight percent sodium pentaborate control capacity y m 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.~

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y? ForDCooper;4a minimum concentration.of 11.5' percent'is required. This is-based. m J 7.

onithe assumptions ' thatL the. actual pump capacity'. Is equal to or exceeds the d.,

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total? min.imum pump? flow rate'.and ' the enrlehment of the sodium pentaborate. has b~

. "Also, it 9is assumed ' that : thef standby liquid control system has .i Enot; changed. 1 been properly modified.forftwo' pump operat' ion. 1 m.. 9; i .x

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y,?. l blE06 A7d/S3 %g:x s kNoh n V k ; .,4, n.:q, ygy'y'ggyggggy; g l &l 7, b&, m 'l m Qh u.i 12;1G SIC System Design Basis s r.r U. lf gy " 1The generic. design basis for the SIC system is to provide a specified cold boron i 4:; m # b 'shutdowniconcentrationlt'o.th'e reactor vessel (described in NEDE 24222). I The SIC d9 - 1 f,' 5;.,1systemNatypicall'yjdesignedtoprovide.thespecifiedcoldshutdownconcentra- -.: r A) l d.i N tlon:. In jab'out - one. or: two L ho' rs.. During. reload. licensing evaluations this l u e.. ,l shutdown concent'rSilon;is verified by analysis to be adequate to render. the core i suberitical.: The; considerations in the reload evaluation are independent of-s- ATWS and'lhjestion rate is not'directly considered. a h! ThelA1WS rule' required addition:of!a new design requirement to the generic.SIE x f sys t em1 design l basis., Changes Lto ' flow rate, solution concentration or boron i t g&

enrichment,, toi meet J the 4 ATWS. Rul e, must not - Invalidate the original design l

s , c. :., ' tias i s'. i + s ,7-2.2 :: NRC A1MS Rule o \\ ,_ (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

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7,, zy g ll Y'l h O G 0 C-61-IS3 gq.; )$ H n h e d A g' h ;'. 4 gj;;Y.". ~ sodium pentaborate-were . (2).--The a86 gallons: per : minute and,13-weight percent: 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. ..)? ' vessel 'inside ' diameter. That different values would be equivalent for Tji. 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 boron.concentrationLrequired'to achieve shutdown and the time required to M a'hieve that vessel boron concentration. The minimally acceptable system c 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__.-. _ _., _.

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i k;, h !l.(.. ' I. s ,j '53 ANALYSIS 3 .N 1 4 Thel NRC equivalent control, capact ty ~ concept of E the A'IWS rule is a' very. simple,. ] s 3< ~ direct : criterion. It'. Is; not~ necessary ' to consider mixing etficiency or. to '4 d o account.for plant-specific core nuclear characteristics, i 4 'e 3

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j ' W f [thelfollowing/re'lationship.is shown'to be true: i f. y; a;

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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

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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 iThe' value of M251 (the: mass of water. In the: reactor. vessel and recirculation j g 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 i g 1, d i 3-1 r

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d @ :/ g, % X< The:m NRC D requires c the: use.iof. minimum plant-specific' values <y 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,

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628,300' 1 %y >a 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 ls 2lx 38.2 = 76.4 gpm.- 'E ~ 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 ~C.> 13 *' '86' '* _489,993 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 M251 Q >.13

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~ 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.

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. r..y n y e oc. 87-1s3' (l'.n.w . jy s A / /, d,,,q p g 1 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

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( 4. 3,-- 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

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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.

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