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) | |
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'- PREPARED FOR NEBRASKA PUBLIC, POWER DISTRICT
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, COOPER NUCLEAR STATION
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I PREPARED BY:' R. T. EARLE' l
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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.
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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.
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- This report uses L the revised procedures for demonstra, ting compliance with the NRC equivalentLeontrol capacity concept. The plant-specific parameters used in
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..the analysis are minimum values rather than the nominal values'that were used in f ,, ' :l , s.
.the' original: concept-derivation.
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,,3, . DISCUSSION 3
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- 2.1' Sif System Design Basis m 3 f,.i .
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. 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.~
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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
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been properly modified.forftwo' pump operat' ion. 9; m .. '
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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
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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&
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- enrichment ,, toi meet J the 4 ATWS . Rul e , must not - Invalidate the original design l
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- 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.
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h ;'. 4 .. .> . > . ~ gj;;Y.". . (2).--The a86 gallons: per : minute and ,13-weight percent: sodium pentaborate-were 4'
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; 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.
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"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
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Thel NRC equivalent control, capact ty ~ concept of E the A'IWS rule is a' very . simple, . ]
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~ direct : criterion. It' . Is; not~ necessary ' to consider mixing etficiency or. to
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y; W fi f.[thelfollowing/re'lationship.is shown'to be true: , a;
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I ' - (where the plant-specific parameters are defined as,. l
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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
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.. E .. .=. . minimum expected B10" isotope'entichment'(19.8% for natural
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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. !
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* .. Based on a; plant specific 'elculation of M, the Cooper Plant contains 489,993 J pounds.of water-(Reference 8).
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<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'
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%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.- ~
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%<- 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
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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
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, 251 Q > .13
- 489,993
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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. t
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- 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. , 10CFR50.62, NRC A'IWS Rute, June' 1984
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1 5.- 'NEDN-24222, . As'sessment of BWR Mitigat ion of A'IWS, December -1979 t
- 6. 22A2896AB, SICS Design Spec Data Sheet
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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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