ML19322C735

Evaluation of BAW-10062,Revision 1,BAW-10074,Revision 1 & BAW-10075,Revision 1 Re Multinode Analysis of Small Breaks in B&W 145-Fuel Assembly,205-Fuel Assembly & 177-Fuel Assembly Nuclear Plants.Repts Acceptable Per App K

ML19322C735
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Issue date:	01/08/1976
From:	Office of Nuclear Reactor Regulation
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ML19322C734	List: ML19322C733 ML19322C735
References
TASK-TF, TASK-TMR NUDOCS 8001220337
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{{#Wiki_filter:... Tf 7 ';, >;;[ (, j - A'l. O 6 1875 TOPICAL REPORTS EVALUATI0fl i TOPICAL P.EPORTS StntAftt The topical reports evaluated in this. review present results 2 0) from saml1 break spectrum '(AT. 0.5 ft ) analyses for B&W's 145 177(2), and 205 3) FA plants with internals vent valvis. The three repor s were reviewed hefntly because they use the same small treak model to perform the small break spectrum analyses., The small break colel consists of the three computer pro-grams discussed below used to analyze plant response to small breaks: '

1. "CRAFTI4): A afitinode representation of the plant primary system to compute blowdown hydrodynamics and water inventory in primary loop componentsfoiioningpiringruptures.

2. FONi(5): A' single node representation of the core to ccmpute average two-phase mixture height in the core 'when core uncovery is co.cputed .in the heterogenecus. reactor inner vessel volure of the CRAFT riodal. 3. THETA 1-B(6): A muitinode representation of the core hot pin fuel ~ ' and clad to compute temperature transierits duringthe loss-of-coolant accident up through core recovery based on average core coolant con ' ditions determined in CRAFT and FOAM. i I The multinode plant representations.in CRAFT for small break analyses { j typically contain approximately half of the nodal detail used for large break studics ( ~15 compared to ~30). The reduced medel has been ~ II) to provide results essentially identical to-those of.the large shown break model when using identical asstanptira, due' to the reduced'blowdowr] rates and internal pressure gradients computed for small' breaks. Most of the node u-3 ..;.. w.gL _ gafzzo337 3 a. m

p. ~ ,g, { '( ' JUI. O a ;074 ~ detail reduction is made by lumping the two primary loops simulated in the large break model into a single loop, and by lumping the reactor inner ' vessel regions of core, core bypass, upper plenum, and upper head into I ~ i ' single volume. In ad( Son to 'the nodal reduction, some large break analysis assumptions imposed for donservatism can be rela'xed because of. .the slower blowdown of the small break. These changes are: 1. flormal system low pressure reactor scram is included.

2. All injected ECCS water is assumed to enter the downcomer and is retained in the CRAFT calculations. Plo conservative removal of this water at the end of blowdown is used as

'T' ".7:7 -- .in the large break analyses.'

b. A heterogeneous inner vessel volume is modeled for tfie small 3:

Gi"= break in CPAFT compared'to the homoganeous volumes modeled for the large break' analyses. Results obtained from the topical reports for the small breaks CO: 7 considered for each plant are sw.v.arized in Table 1, and show that

rpeak clad hot-spot temperatures in any of the three plant types analyze ['

0 do not approach 2200 F. TOPICAL REPORTS E'!/.LL'ATION The sma11' break model programs used in the analyses in the three Veports reviewed here were evaluated in previous asssssments ~ for large break studies in the cases of CRAFT and THETA 1-D, and the FONI program was evaluated in the review of BAti-10064(5) App 1,ications e V.h ym, -- C Md (' "W" A.: a %.- q 3 3, i

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• i of these programs in the small break analyses reported in the topicals were performed in a manner which provides some conservatism in the calculations of peak clad temperatures; however. an assessment of the extent of*this conservatism was not sought because the tempera-

,tures obtainea were low compared to damaging temperatures., From'the results sucnarize'd in Table 1, it is noted that the analysis for thcl77-FA plant with raised loops did not include the core The* introduction of the report (BAW-10075)(2 flooding tank line break.- for this plant indicated that the results of the analysis for this break 2 would be esented in the SAR for ea'ch plant application. The 0.5 ft break for this plant tras also indicated in the introduction to be re-ported in CAN-10053IN., As this. report presents results for a 177-FAnon-vent valve plani using the large break model for the break analyses, it is conside ed that the 0.5 ft break for the177 FA plant with raised loops 2 C and. internals vent valves has been adequately considered. The'value shown in Table 1 for this break is consider.ed greater than can be con-servatively expected for a small break model analysis when comp"ared to 145'and 205-FA results. RErWI.ATORY FOSIT10:1 Referencing the appropriati! report of the three topicals evaluated in this revicw will be acceptable for sdall break spectr::m analyses for SARs with the exception of SARs for 177-FA vent valve plants with raised loops which require additional documentation for the CFT line break. The models and programs used for the str.all break analyses in these topicals predate issuance of Appendix K of 10 CFR 50, but are considered ~ in conformance to the requirements of that rula. n, r* ~ f - {$,,is E I Il,R

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• B&W PLA!!TS: SPALL 1:P.EAK SPECTR!T4 N

~ ~. PEAK CLAD !!07 SPOT TEPPERATURE "F 177 FA RAISED 2 _ Break Size - ft. I45 FA . LOOP 205 FA (Vuap Discharge) 3 0.5 1196 1533 1178 0.3 1030 1090 710(2) I.C.(1) 700(2) 710(2) 0.1 O.05 I.C. II) 710(2) 700(2) 0.04 * (PapSuction) 0.3 824 r 71/2) f I.C. II) 0.1 (CFT Line) ~ . - i 0.35 760 I i-0.44 a 1636 i s. .. l. .l l NOTES: I (1) - Initial condition - not specified (2) Same as initial condition l (3) - From Reh'erence 8 CFT - Core Flooding Tank n E.:..h+.t ....:.. r.-. a::. a.. :=.: s r=== . : =.a.=: t h.:.. g

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va v 9.s. i RLTEnr2rts f p 1. C. E. Pad:::, R. J. Allen, and L. R. Cartin, ";tltinod: Ir.21ysis of' Q, Small Drc2.s for act's 145-rec 1-Assedaly Muclear Pln=ts With Inte: ds Vent Valves," E7,*1-10052, Octch:r 1973 - 2. L. R. Cartin, J.11. !!ill, and C. E. Ps:ks,, "I111tinod:2 Analysis of Stall Dreaks for ac1's 177-R'cl-1.ssembly welcar Pktats With rai:od bcp Arrangc..=nt and, Internals Vent Valres," BT01-10075, Deca.-d:cr 1973. 3. R. C. Jones, B. :I. T>.2nn, and C. E. Parks, "}illtinado Jainlysis of San 11 BrerJ:s for BI.N's 205-Pc:1-Assmbly Ibc1 car Plant With Internals Wnt Valwr.," Di*i-10074, Nove.Thar 1973. 4. D. E. Binyh:m,1.'. L. Jcasen, and R. A. I! drick, "CFarr - D2scription of Fcdel iur I27111ihri'.m IICA Analysis Prog:rm," N9~-10030, 0 tcher 1971. 5. B. M. Dr.n, C. D. Ib.gan, cid L. R. Cartin, "I121 tin 4c Fr.21/ sis of Core Flcedi /J Li,no Ercah for Bcf's 255ft-I+.'t Intcznnis Vcnt Valve Plants," BM1-10054, April.1973. G. C. T. !!ocevar, sad T. W. Ifineinger, "'NE*ml-B'- n Caputcr Ccds for 16cicar.%~.:: tor Core cannal ;-r.alysis," n-1445, February 1971. 7. C. E. Parks, S. M. P.*:-n, and R. C. Jo._, "?C:lti.aodo Ralysis of .Smil Bres>.s for B&if's 2568 itit Ner'<ar Plants," Ef.'-10052, Septe:i>:: 1972. 8. C. E. Parks, I R. 'Cartin, a-d K. C. Shich, "P:ltir. css Analysis of Dcf's 177-Fual-fascrbly, Nca-V(n Valve Plant Caring IG," BAW-10053, June 1973. e ~, e e l 8 e e e G e 8 e g l l p ( - y M O \\ ; ! ',[>>; 3 m l p.Ih~ ][fD y, o ! <- - m

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