ML17037C490

Letter Submitting Copy of Report of the Advisory Committee on Reactor Safeguards Dated February 12, 1974 on Expected Performance of General Electric 8x8 Fuel Design for Reload Use

ML17037C490
Person / Time
Site:	Nine Mile Point
Issue date:	02/20/1974
From:	Skovholt D US Atomic Energy Commission (AEC)
To:	Raymond P Niagara Mohawk Power Corp
References
Download: ML17037C490 (14)

Text

v'EB 20 1974 Docket No.50-220 M.agar a R)hawk Power Corporation ATlM: R.Philip D.Raymond Vice President-sneering 300 Erie Boulevard West Syracuse, New York 13202 Gentlel1)en:

A copy of the report of the Advisory Committee on Reactor Safeguards dated February 12, 1974, is enclosed for your information.

The report reflects the Coamhtee's review of the design and expected perfora)ance of Genera1 E1ectric 8 x 8 fuel bundles to be used in part;ial and flQ1 core reloads for boilirg water reactors such as your Nine M.le Point Nuclear Station Urd.t l.You will be advised when we have conyleted our review of your request for operation with 8 x 8 fuel.Sincerely, Donald J.Skovholt Assistant Director for Operating Reactors Directorate of Licensing

Enclosure:

ACHS Report RNDiggs NDube cc: See next;page l4Jinks Bsch~f (ig)SKari SVarga HBoyd ECase Distribution Docket File AEC PDR Local PDR RP Reading Branch Reading JRBuchanan, OHNL 93Abernathy, DTIE WNoore, L DTSkovholt, L:OR TJCarter, L:OR RO (3)OGC VStello JGallo JSaltzman FLIngram HINueller JWagner, OC WOM.lier, DRA PCollins, L:OLB DLZiemann, L:ORB g2.82........

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Form hFC-318 (Rev.9.53)LCM 0240 CRI3 C@3 13 11423 I 320 204 II i;,'iagarn lfohawk Power Corporation February 20, 1974 cc w/enclosure:

J.Bruce HacDonald, Esquire Deputy Commissioner and Counsel.New York State Department of Commerce and Counsel to the Atomic Energy Council 99 Washington Avenue Albany, New York 12210 Arvin E.Upton, Esquire LeBoeuf, Larry, Leiby 6 HacRae.1757 N Street', N.W.Washington, D.C.20036 Anthony Z.Roisman, Esquire Berlin, Roisman and Kessler 1712 N Street, N.W.Washington, D.C.20036 Hr.Donald X.Gleason, Chairman County Office Building/>6 East Bridge Street Oswego, New York 13126 Hr."Robert P.Jones, Supervisor Town of Scriba R.D.II4 Oswego, New York 13126 Oswego City Library~~

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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS UNlTED STATES ATOM lC ENERGY COMMlSSlON WASHINGTON, D.C.R054b February 12, 1974 Hanorable Dixy Lee Ray Chaiznsn U.S.Ataoia Emmgy Gmni'ssion 54545 8dxJect: HEX'ORC CN GENEBAL ELECXREC 8XS PGEL XESX(ÃK)R HEZQAD USE'ear Dx'.Bays At its 166th meeting, XhhemLxy 7<<9, 1974t the Advisory CGHlAittee an Reactor Safeguazds campleted a gexxeric review of the design and ex.-pand peeiarxtlaxxce of General Electric 8xS fuel bunclles to be splayed in partial and full care reloads in boiling water reaclurs.These topics were discussed at the 165th ACRS meeting on January 10-12, 1974t 555'te',,~, 5574, and in Denver, Colorado, an January 24, 1974.During its ravines the Ommi.ttee had the bermCit.of discussians with representatives of the Genaml ZXa~ic Gxnpxxzy, the AEC Regu3atozy Staff, and of the docu-maxts listed beld.The General Electric SxS fuel assalhly consists of 63 fuel xocls plus one unfueled;water-f le@, spacex"~ptxxre xod in a sctuare Sx8 bundle array within a-squaxm channel box.The design of the fuel xcds and fuel xcd bundle in the SxS reload fuel assembly is, except far diffex ences in the length.of the fuel and gas plenam, the same as in the 8x8 fuel BSSHllbly used 3Il the~6 bo113LIlg water xitor concept referred to in the Caanittee's n~of Sex~her 21, 1972.The SxS fuel bundles are interchangeable in General Electric boiling water reactors with the peeviously used 7x7 bundles.Xh general, the thexual margins to fuel damage design bases are greater far SxS fuel than far'x7 fuel.%he design value af the linear heat gemmation rate far normal opexmtion is 33.4 kw/ft far SxS fuel and 17.5 to 18.5 lee/ft far.7x7 fuel specific power is slightly greater far the 8xS fuel than for the 7x7 fuel.The Genera.Electric Catapany believes the 3xeer linear heat generation rate and slightly greater ratio of clad tlxxc1cness to xad dieter shouM result in fewee failures in SxS ftxel than in 7x7 fuel.Although the hyQraulic resistaxxce of Sx8 bunDes is slightly greater than that of 7x7 buxxllm, the thecal-hydraulic pex-faxmance of boxes either partially or fully loaded with SxS assemblies is not chsgnlded relative to cares loaded with 7x7 assemblies.

Emeable icy Lee.Ray February 12, 1974 Since the U-235 enrichnents for the indivMmQ.fuel rods, the number l~t lh~l llggtlhd, Ith ratio are similax'n the SxS and 7x7 designs, the neutnnic behavior of the tsm designs is not significantly diffanmt.The intexnally located water xod in the SxS design reduces xod-to-xod power peaking.Since the nextmania and themal~rauLic characteristics of SxS and 7x7 fuel huxG.es are similar, thorax behavior under ahnoxnsl operatianal t'\PlbWbl.Ih~fl'hd cantxol xod drop,'uel handling, and steam line break acx68ents are nat exited to be significantly different for the two fuel designs.II~51'WWW,'l kU'tV~h~water reactors, and the Regulatory Staff have perfamtect analyses of the behavior of 8x8 fuel in several mixed and fully reloaded cca~under txansient and accident cxmditions.

These analyses ymBict that,, far boiling water mectxuw which have jet pumps, the peak clad temperatures during a po.~~ted large-break IQCA using the Xnterim Acceptance Criteria axe less for SxS than for 7x7 assariblies.

ERwmrer, for large postulated breaks in nan-)et pump plants and far small and intexaectiate size breaks far all plants, the pr~x8 peak clad temperatures are in the same range far both SxS a+i 7x7 fuel.Consequently, indivtitual reviews by the Regu-latory Staff of the equi perfarmmce of SxS reload fuel, incluKLng plantmpecific system effects azxl any significant core fuel loadLing il1b I If h I f w H th 8xS fuel to deteexnine limits an reactor operating conditiorm.

The Cce-mittee wishes to be irdhraed concerning the results of these reviews for the initial SxS fuel load:tngs in each of the several General Electric boiling water reactar product lines.The Regulatory Staff plans to use the results of recently canducted N~~~8~~~I'll analytical nedels far SxB fuel.The Qanaittee wishes to be kept infcemd.IlE!fS16 and hun31es whose designs brac]set the dimensians of the SxS fuel and an the perfarmance of cares cantaining mixbmes of assaablies with different rmobers and sizes of fuel rcds.Although mechanical tests have been perfaxned'an 8xS fuel assemblies anR campanents to daaanstrate their integri.ty, additional tests to vex'ify spacer grid strength have been requested by the Regulatory Staff.This matter should be resolved in a niner satisfactary to the RecpQatoxy Staff.

~~ly RIMmable Dixy Lee Hay Fehrum~12, 1974 The Aneeal Electric Caqxmy has planned a precgam of both pre-and post-inmHatian enauninatians to monitor the performance of 8xS fuel!!!!~!.1l program and wishes to be kept informed.The Hegulatory Staff is currently revhm9xg the treatment.

of uncex tainties in the establishment and mmi;toring of operating limits far boiling water reactors.The Ccxanittee wishes to be kept infarneQ.He-evaluation of care operating limits will be necessary as a result of the recently gcanulgated Accephmce Criteria for Emergency Core Cooling Systems.The Ganmittee vrishes to be kept infarrneci.

The~ttee believes that, with due reganl to the abave comments, incluQiLng the individual reload reviews by the Hegulatory Staff which will address specific plant features, the Genera.Electric 8x8 fuel assanblies are acceptable for use in the reload of General Electric boiling water xeactxam.&E.m.H.Stratton Chaixaen St Befezences attached.

Honorable DDT Lee Ray Pebruary 12, 1974 20 3Q 4 5.6."Dresden 3 Nuclear Power Station, Second Reload License Suhnittal", General Electric Co., Nuclear Puel D@lartment, SepteInber 1973@and SuppleIRRIt Ag RR%6her 17~1973~Supplement B~DeceH58K'p 1973 Supplatent C, Decanber 6, 1973;Supplement D, Deliber 17, 1973;Supplement Ec De~Mr 17'973'upplement Pr Januazp's 1974'upplement G, Januaxy 9~1974)Supplement H, January'23, 1974"Nine Mile Point Unit 1-Semnd Refueling", P.D.RayIImd to A.Giambusso, September 14, 1973'Nine Mi1e Point Unit 1 Safety Analysis for Type 5 and Type 6 Reload Puel g Niagara Hat'uvr8c Power~aratiang October 15, 1973"Nine Mile Point Unit lr Part lc Nan<<Proprietary Response and Part 2, Proprietary Respanse," Jamlary 15, 1974 Monticello Nuclear Generating Plalltg PexlIBnent Plant Changes to Accamncdate F~ilibrium Core Scram Reactivity Insertian Charac-teristics", January 23, 1974 NED0-20103,"Qerumal Design InfoxIoatian for General Electric Boiling Water Reactor Reload Fuel Camellcing in SpriIlg,'74", September 1973 H.E.Wi11iamsan aIld D.C.Ditmore,"Experience with.HWR Fuel 9hrough Septarher 1971", NED0-10505, May 1972 GEAP-4059,"Vibration of Puel Rods in P~el Plow", E.P.Quinn, July 1962 70 8 Letter, J.A.Hinds to V.Nmre,'ebruary 4, 1974,"P~lrietary Infoxmation, SxS Puel Wear Tests" X~.J A, Hinds to V Moore Pehnlary 4 1974 SXS Pue1 Sur-veillance PIugram NEM-10735,"Densification Cansiderations in HNR Fuel Design and Per foxmallce", D.C.Ditmare and R B.E13dns, Decaaber 1972/Supplement 2,"Response to AEC Questions, NEW&-10735 Apri1 1973"(Proprietary) g Supplement 2,"Response to AK'.Questions, NEDDY-10735 Supplement 1", May 1973'Proprietary), Supplement 3,"Respanse to AEC Questions, NEDH 10735@Supplement 1 g June, 1973 (Proprietary), Supplement 4 g"Responses to AEC Questions NEXT-10735", tuly 1973, (Proprietary) f Supplement 5'g', Densif xcatiaIl.Consideratians 1n HNR Fuel'g July 1973 (Proprietary).g SUpplements 6j 7g aIKl Sg Fuel DensificatiaIl Effects an GeneIzL Electric HoiUing Water Ppm~Fuel"~

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~~Q~Hceozab3a Dixy'ee Ray February 12, 1974, References

'contend)NEDO 20181'uppl6fMlt 1g December 3t 1973 (Pxoprj~~)

g~GAP III"A J4xM.for the Prediction of Pellet Conductance in BNR Fuel Rods" 10."Technical Report an Densification of Gm~Electric Reat'~Fuels", U.S~Atomic Entry Camaission, August 23, 1973, and"Supple>rent 1 to the Technical Report on Densification of Canexal Electric Reactor Fuels", December 14, 1973 11."Sensitivity Stay on~6 Fuel Bunts Response to a PoshQated IDGE, C.M.Maser and R.W.Grume, Deaeaher 1973 12.NEIPr 10801,"Mod~the E+/6 Los~&Dcelant Accident" Core Spryly and Bottxxn Floodix@Heat Transfer Effectiveness", J..D.Duncan and J.E.Leenaxd,'Maxch 1973, and"Response to AEC Ret:gmst for Additional Information an NEDE-10801", May 1973 9'mpa5.etary), 13,.ME0-10993,"Core Spray and Bottcm Flooding Effectiveness in the~6" g J.D.Durban and J.E.Leceard, Segteaher 1973 14."Core Tkmenal'Analyses of a Stainless Steel Clad Heater Rod Bundle", C.M.user and R.W.Griebe, December 1973 15."Status RepI~'n the General Electric Company Sx8 Fuel Assembly", January 18, 1974, USAEC Regu1atory Staff 16."Technical Report on the General Electric Oarttpany SxS Fuel Assembly", February 5, 1974, USMC Regulatory Staff~ff~~L~A 0