ML19210A285
| ML19210A285 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/29/1976 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Arnold R METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7910290522 | |
| Download: ML19210A285 (7) | |
Text
{{#Wiki_filter:.> DISTPIBUTION: overce r 29, 1976 Docket V NRC PDR Local PDR ORB 4 Rda. cc m.. B-c _) V. Stello T. J. Carter b P Q} [ D gg R. n ram GZwetziq a.r w,:1 i t.v. 2.:133 o '% " ry Guibert u. ' TT',: 'c. A. C. 3rnni. Attorney, OELD lica ' resident - 42necitic OI&E (3) . ;. 1.03 : :- D. Eisenhut n.: n ), Monsylvarit 19Q3 T. B. Abernathy J. R. Buchanan -eatie aa: ACRS (16) Gray File TF"EE 'ILE ISLU9 WIT ; 2. 1 T9e .C staf f has recently catained information "Mich ir. dica tr:s t'u t tission a3s releases fron fuel pellets vith tiah eurnua oay be m"'ar-needicted oy tne current industry mo:iels for fissian cas release. As a result, actual ena-nf-life fuel rect cressure '1y be nicher tW that ulich was considerM in the s3fety analysi; for your facility. 2ltMu.h this situation decs rot lead us to suspect that fuel cesien li.,its have neon or are currently oeing exceeced at your facility, the potential,1y exist for such an occurrence in the future as Siccer fuel t,urquos are reached. Conscauentif, ver; ara ree Je ster 1 to evalo3te tne 9ftects r.f increason fissica gas releases on t~e safety analysis for your facility in accordance..i t" . e scvule scecifiel celo i. !f tP,e esthat d date on '..hich any fool rod in yo'ir facili tu will reach a Iccal exeocur? (wrnno) of 20, 00 "e-'. rat.-rays Mr.etric t:n of Urani'r; ("l0/td) is sooner taan June i,1977, crovi a t'.s follevia7 infnr !sticq within D cavs of receiat of this letter. (* f tai s esti 1ated acte 1, later taan.'una 1,1577, ye'ir rc.woose m'" ce sim7itted witnin 'o dan of recei t of *:,is l at ter). 2. 79e esti.!stad cite en ihich any fl.:1 roe in your f acility ill reach a lacal excesur? ( 52rnne) of 20,t.]u "eg2 o t-niv-.ar ric ta n a f Ur t ri rr, ( r.,7/ ty ), Jsina the ccreection tec.1nicue nescribed in t"a attac %- orclos':re, "cdify t"o fissien aas release -oJel in
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Form AEC-313 (Rev. 9 53) AECM 0240 Q o. s. sove g eas t s.v==i eve or nec t' iste.sze.ies
Metropolitan Edison Company cc: G. F. Trowbridge, Esc. Shaw, Pittman, Potts, & Troweridge 1800 M Street, fl. W. Washington, D. C. 20036 GPU Service Cor: oration Richard W. Heward, Project Manager Thomas M. Crimmins, Jr., Safety and Licensing Manager 260 Cherry Hill Road Parsippany, New Jersey 07054 Pennsylvania Electric Company Mr. R. W. Conrad Vice President, Generation 1001 Broad Street .Johnstown, Pennsylvania 15907 Mr. Weldon B. Arehart, Chairman Board of Supervisors of Londonderry Township 2148 Foxiana Road Middletown, Pennsylvania 17057 Miss Mary V. Southard, Chairman Citizens for a Safe Environment P. O. Box 405 Harrisburg, Pennsylvania 17108 Government Publications Section State Library of Pennsylvania Box 1601 (Education Building) Harrisburg, Pennsylvania 17126 1487 146
EnclCsure I s Recent ANS standards activities (1-1) lead us to believe that high burnup gas releases are underpredicted by current LWR industry models. We have previously (1) 1:oxed for a turnup dependence and found none for LWRs in the burnup range from 400 to 18,300 mwd /-U. Thus, we incorrectly pre-sumed that the strong burnup dependence exhibited by LMF3R data (i) was not representative of LWR f;els during their shorter burnup lifetimes. New high burnup UC2 data centioned by Westinghouse to the ANS group (1) and discussed with the NRC (i) show, however, that the sharp release increase seen in LMFBR data cccurs also in LWR fuels. Therefore, in the absence of a complete analysis of high burnup LWR UC: data, we will assume tha :ne burnup dependence is the same in LWR and LM?BR oxide fuels. This assumptien, however, will be applied only in the high burnup region above 20,000 mwd /;U since the current industry nodels have been checked with the data base (1) ranging to 18,300 mwd /tU. The following correction has been derived to give an increased release fraction F'(3u,T) as a fanction of burnup and the uncorrected release prediction F(T). Burnup Su is the local burnup in negawa -d?"s per me:cic Ocn of uranium (mwd /;U), and T, wnich is not an explici variable in the correction, is temperature. (1 - exp(-0.436 x 10 "(Bu-20000))) l1-?(T)] (1) F'(3u,T) = ?(T) + (1 + [0.665/F(T)]exp(-1.107 x 10 *(Su-20000)]) 1487 147
. Figure 1 shods schematically how this correction would be applied to the GA?CCN gas release model, wnich is independent of burnup. In the even; an existing codel centains a burnup dependence, F(T) would be the predicted release fr2ction under the temperature condi: Lons of interest, but with the burnup variable set equal to 20,000 mwd /:U. Equation 1 is a replication of the Dut; and Baker (1) LMF3R correla-tion, wnich is an updated version of the correlation in Ref. 5 Equation 1 was derived by assuming a convenient functional form depending on F(T) and Su and fitting it to the Dutt and Baker curves using a non-linear regression procedure. No conserva:ls: has been intentionally added. Figure 2 shcas how closely Eq. 1 reproduces the Dut; and Baker curves. References 1. R. O. Meyer (NRC), memorandus to ?. S. Check, "Su==ary of Meeting of ANS-5.4 Working Group on Fuel Plenuc Gas Activity," February 25, 1976. 2. R. O. Meyer (NRC), cemorandum to ?. S. Check, "Suenary of ANS-5.1 (Decay Heat) and ANS-5.4 (Fission Gas Release) Activities," June 22, 1976. 3 R. O. Meyer (NRC), memorandum to ?. S. Check, "Su=cary of ANS-5.4 Meeting en Fission Gas Release," Cc cber 6, 1976. 4 C. E. Beyer and C. R. Hann, " Prediction of Fissica Gas Release frem UC Fuel," 3atte11e repcet, SNWL-1375, Novemcer 1974 5. D. S. Dutt, D. C. Sullington, R. 3. 3aker, and L. A. ? ember, "A Correlated ?lssion Gas Release Model for Fast Reacter ?uels," Trans. As. Nucl. Sec. 11, 193 (1972). 5. R. O. Meyer (NRC), memorandun to ?. S. Check, "Su==ary cf Meeting wi:n Westinghouse on Fuel Red Pressures," Sep; ember 22, 1976. ~.
- 3. S. Outt and R. 3. Baker, "Siex:
A Correlated Ccde f:r the Predicticn of Liquid frif. Oast Breeder Reac cr (LMF3R) Fuel Thermal Performance," Westinghouse Hanford report, HEOL-TME 72-55, June 1975 1487 148
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