Text

May 23, 1975 - Final Summary Report Unit 2 Startup
	ML060720253
Person / Time
Site:	Browns Ferry
Issue date:	05/23/1975
From:	Gilleland J; Tennessee Valley Authority
To:	; Office of Nuclear Reactor Regulation
References
	BFN-100, BFN-63B, TAC MC3812 TVA-BFN-431
	Download: ML060720253 (228)
	v • d • e

ENCLOSURE 4 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 1 MAY 23, 1975 - FINAL

SUMMARY

REPORT, UNIT 2 STARTUP BROWNS FERRY NUCLEAR PLANT

I MAY 23B75 2i

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~131?I MAR MAN? MIT 2 Abesaet mhe flail milut of the startup too pflepsm Pwtogad aIt Irm".

reI lbet fl "a" i d& ai to ~waw4 in this. ptart: () Utt"edwlose fs W) 3iw, a" (3) wats"9. % . 11101 Cmv. P&78iCs, 9Uslml-hydf4llCG ftl spun PWrfsuu tests aft posseste Sub that ase sestal Oupinrl" V0,m0 ObtaIsi an uCOMM"e 46"Ust .O.cto4o desigs vols. VMSeu devia-11m.fitoWm teds reas"titsa or carractiw. adjoin an. ala deacrb"Ol Us pupaM of twos roepr, la to .. '.smt a coast emeary aed poerti datai"e resale. he%&IS" toal polftuWom of starup cest. at Irma VoW17 besar FIMa ftit 2. 21e statrtu test Prmrn mbrae4 airs

404ssthermlauhydraules giftsreuwemaa - ral sstem dymi.s LI JMf~~tf b Ws UiY 24640s Plai %ft 3 I~s a hS11 vmWe bleyl reateg doomod'u by comsI4 flsui.W coolml (40CS)t the ?inaasg Valley ANOhevit (WA) is Uh Oa smsed of a tbtssmU site to be goomu tosrvs the plua is )as~gw as use lossmi River to btcal A3m. the4sa puss eletrissi GOuP"t iON "be olulud tram a 00""im pawr Of lba tie trep f1 tsRm of -pip inm-Tuustts the Ucoprgale lees prora begis. W s h& isWsisusle - thaem tI of e tea p -, -

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-a-FINAL SUWAIAY aRT - Bil? MNT 2 1.3 StartP Test Con tinued)

VuTag tug period t W Plant s taus to Its dsWied full-power opewating coaditto Ina safe. coatrollsJ. gradual fashion. Futaasive testing In performed _mdef selected, controlled oweratt coeditios to deraftotrate safe. efficient perfogmce of pleat .asposeets.

Te startu toot progvam heai with fuel loading oa July 2, 1* ,

and cmatlaued through cepletion of the warranty cm aid 1002 power testing.

Commrclal opertion began oe lach 1., 1975.

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Stortqu Toot DewittRp Dcuents sach an the Operating Ucese (l 52), Tedhical Specift-cattos,

elat Oper ting Procedures, ead equipet Souala, cntrol operations during tee plait sarcup teat program. Two doe- to are supplied by 0E-UND for Implemntetion of the startup testing of the equtpmest it supplies; the startup eost specificat os ad the startup test Iatructzi (T),.

TM Startup tet Specificution is a .. cuient Issued for rvi w and approval by CZ Management and i used for plammisapd scheduling tast.

Te basis for the cosss teaet is that they are required either to daeastrate it 1I safe to PtO4Sid, to damotsrate perfornmnce, or to obtain saminsring data. This docent defasas the ainim test progrea weded for safe, efficient startup. The urpe", description, end criteria are giase for each teat, together with a sequential gdo for pozformaws of the taste.

Te startupe-st Iatruct toeis a doct written for use in the control rom by qualiffAd CC persoosel and for trained TVA personnel workiug with GE technical direction. It contains sufficient pertinent Infoz.tctos to Permit such personnel to properly performsa d avalata ach startup test.

TVA Division of FAgIeTeriug esign (D); Dision of Power Production, Pleat Engineering Branch; end Irows Ferry engineers reviewed the GE Startup Fast Speciftcatic and Startup Test Inatructinns; and with appro-priat. revistao, specific browns Ferry Master Not Factionl Tust fostructlon (MMF I). laster Startup Test Instruction (NST!), sad Startup Test Instructions (STI's) vera issued.

Th flt and 4SU coordinated and documented a11 teat activities from tnitial fuel loading to the completion of all startup tests. Thes instructions provided guidance for sequence of *evnts,and control points for satisfactory test completion and review before power ascension.

The (E-supplied STI's vere revised for clarity, to reference plant Instructions. ed to tAclude specific listrument numbers on data sheets. These STI's were finally reviewed by the Plant Operations Review Coaictce (PORC) and approved by the TVA plant superintendent and GE site operations manager.

£ V~MM OWAURT 510? - U111 MTl 2 LS It~ etAs sf fe 2hm atw Tom Imectim tow *ea "A" tat Ceotains criteria for ecceptsac of resetl, of that test. tetr afe cm levels of criteria Ud tiflsi, mug a,,lIeCls. as te"e I i Lovel 2.

us level 1 criteria Inulude the Values of Paces. veriale, mmslad la th dea4 of the Plaint *i equipwat. It ae wl I euiterio, S not satis NW. the plut is PUece Ie satisfactory held edulties intil a resolution to _is. Tmtseqeeilal with this MU coaUtim my be coetImmed. reqtire- 7llow-US asltim, OVI^sabl ests va be repeated to, verIty that the nme of th lowe 1 urteutm wes sulaftad.

te level 2 erIteri ae assceted with eaetattas In rapd to "Curee of the syst" If a UWe I *uiteuto sot satisfied, oPerstima

_A tetsIa plais iwlA Mt aecesattly be altored. bvestigtlona of the ma1m ts -nd *at the eortical tecbiqus no tor the Predltions woul be started.

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Safety liits, as Mt fonb IS Plant Techla SPectticatGSO, are

&at Included alma there are so Plaed oPeratioma of sf talig at such levels.

(by mestIa th euitaule, Start te d true atredt MA aproved by N C ad tO plaet euertateaesat _i are uadergoig a final review ad evalnasti by TWA OM i.0 *_y of Yts levate 2.1 roeaot of Etei ?euia Th* estlee pressue la tabular tfrm the si drflne dates of the starsup teat Progra. Tabl 2-1 gives the dates, of mjtrevets La the ualt 2 startup. TAU 3-2 given CM dtes, by Ahch ech Cast or majar part thereof yes mpleted. tle 2-3 ew a powe flow sa *nm the varos tet caditloa.

2.2 "he It - 1qkm esel and Coll Tteat 2.3.1 SIT-I. ostco aoa lock a Chesical teats of e primary coolant van mda prior to heatup and ilde the folliag result a Conductivity (Cuuolcs

25 C.) 0.25 Ckloride (Vpb) 'SO Turldittyp (VP).06

( icrca (ppb) (50 Silica fppb) 1S All criteria vero eattufted.

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I 2.2 _ees f m cod Tessing (Conadued) 2.2.2 Ss1-2. UaiistiM lmureMt A complete #lest Ommy mm tahee with the coare fuy loaded

_d al eawol to"s ful1 lasened. AU wadiatios levels wer. blow lastrast mImlm detestable limits, so aU criteria were se.

2.2.3 57-3. 1"A tordift Sl loading beowa Jme 29, 19P with the *oadinr of the opereaional sou65, Md MO an tUlI ciyupleted e11 9, 1974.

At *hat ti_ aU mm operasal *seres were installd, all four t'sware C ected and fmctiomal, al 764 fuel eseflaes were imstalld ed thetort veuificat is colated. PartWl caen abtdom SaOs tests War Performed partidleall daring fuel loedis , satisfyinp 2.2.4 m-4. Cam shutdeu mhuui

' After the functional tast of the 13'a 'Ut-6) the butdom Margin test mm coedected. Th emalyticelY *ste t Vod, 26-07, ma fully withdraw, sad thee the edjaceat ew, 2203, se sotched to Position 14. SubcrIzicalIt7 me verified by the 53'S _ it mm demostrated tht reactivity mrgis a0.38Z WIZ eisced.

The Cl_ critical test dstrated that th, core %ad as "all tros 1 kff of .933.

AUl test criteri ar e.-atisfied.

2.2.5 m-s. CqMt,.l %a brim 9ws"M Al cetrol rods at the aritette of the tests parforsed.

CID 10-23 failed to set the SU02 scm tim ledt durw inta cm testing, but we retest" setiafactery AU the required tests wre performsd ties an each CID, during o following feel loadig.

2.2.6 St61. SIM Perfoom e he S3. were tuctiosally tested before f.d after td Initial eriticality. The signl to oitse ratios of the fully inserted M's ware greater than 2, and the cinim Count rato was neater than 3 cp.

The RM mm dmnsrated to be operable, and all tes criteria were

.- tisf led.

2.2.7 M-10, Tin Perfogmace

Overlap between CMe IR's mad M's was verified for all M"t'*.

All tIM's shovwd response to chaages in the nucton flux. Nerap between the IRMs ad AOiVl's ralned to be performed at higher powar levels.

-4 PUL DSMART U - NO VW 2 2.2 Pnse I - asMl d bet s ca tiveed) 2.2.8 811-13. P-oe.

~.cbsit sensems 51.mals n prou~m Wme Performed OR let. w s ant pstmst tontleg oepts jamr 2u Gim1ficat pm. levls of prasuo tb 332 are etatame. nm citjedA m No apUclcue to GP" mes"s tasti4.

2.2.9. :ill Smi iing this Vbse Of tling, bas MmT MA WTVVle4 *AO 84d MO MTGStor SWAbSIUSI" M Id. 1tX MttUG W laftaW M calibrated tod puerartim for -bwst baaw. Alo, mowinl sius iaePcht mrs mst detect correct peteial intsrte e r.

Criteria PpClie to tug Cold eomatif Nei au mt.

2.2.10 _te

_1-5 3.tclte lCIbaiq lb. jet p_ trassmitten mg cdaU batol as leop sug bom prsdam. pes d out of th ele e d ,

d Ajduswtmts wra wis se oscessar to give m". reawsmse. riteria ara "o aPPle to this test.

2.3 2.3 811-1.a ul Luz Oc60a tests of the Pri Coolant m mid dueg the "Itial. beatw. s re~ts miss Codutity (Imll 25U C.) 0.53 2"ibtdf (flU La murift wb)p) imem (PPb) la Silica (ppb)10 leactor Water coiduttuity we wIthi the 10 ho.ea IIt teceeial specificatin li1dt throsbut tidtl hetup testing All toot criteria we" sattsfied.

2.3.2 M-2. Rsdnttei pbasurenst A colets Plant sM was taken at hot StIMib SW all crteia were met.

FTAL SMIt £RIP=t - no 1NIT 2 2.3 Pbise II! - Initial U1tum (contiaaa)

LII.3 3-5. MtrTl 3od 0ut &Itm te _e perIe at ao0, No. m 1.4S ^p eactor Pieesars. All do ctre1 rod 4rivee Mt the Criteria of the tee rev ued co thee dur"S beetup testing.

2.3.4 M11. SM E!!Lasmece NW Control As the weetor Me bsted to rated t_"serturs the rod pattea Xm readls, mertor taurat bpus valve raeltliofss WA e rat. of Cheap of the Uderaer temerture wer neode for each no red STO Withhav 4 Ae. abl to" criteria Satisf"e.

2.3.3 n-to. e lbeIB p lIfiars were adjusted tfr cstiIty betweeni Cause 6 al. P1Mg de AM Toadiaro, the Vol valas mm adlueted so that 120/US of stale as ronp 10 equals 2A p-n:. _eoqet ow-lap with SW'o mm varife. An criteria W_ me.

2.3.4 m-12. ANM Calbtio S law pews alibation of tle _UE ws oecesefully com-plate a tl the VOsa ee met t road ireatar th or eque to the actual core PW a determised by th low Pon. beat balme eqlatliss.

Anl applcab tDot criteria se met.

2.3.? m-i). roess amwer AU csew lisla Wm Verified from the to amen sad CS-I

_s operated to verfy the oIftu. kowr 1ev" Wm elver ffiuiast durtag beatw to perform perdtest teetinl. Ibe criteria are net applicable at this P-Ny lavol.

2.3.8 UL41. Isc Y~tamwe Brfrgm durin initial reactor pressurias"tiom to pe 1ao0, NO, and I0 Vlg. Ai tests were perforwed with IC taking suction from eel dischareg to the toodeusate &torae

Al1 teot criteria ware satsfied with the eeltion of tbe level 2 criteria for bla st*= flow Isolation setpoists. aeesal. Pressure drop aeres the elbow taps gives a highr thou etpectd digal to the stm flow Instrunt switchee. Therefore, thee mitche Could oet he t at the calculated 3002 rated stem flew due to hadted iatnuimt nge. Th switchee remain set at the preess t seeifcaglon lit dchcsl of 45D0 1ahs of water, pending rsolustion by TdA -MD, sd C?, Controller setting were satisfactory for GlU Phaetit testing.

2.3 rkaee IIIn Isistel Sesta (Ostleed)

Test.ms gvPerformed &ulaLIstIal fteacterg pe- artsatioes to 1so. M~ mld two0 pes. All test. wes poerfored with hPC "%"ar section trm Ol disergiag to the eedmeusst staw twaL6 AU toes criteria WEs Mt and Cootruller aetiag mWs saatisfactory for Phse Its 2.3.10 S5I1648 leleesd ?~M., Tasertur ont" menos tu" dtht Abhvd the drian Use Whrmul adequately mietoma bottom drals llse texpersture, erstera o temperatur dif ferences b.1mm she irpor MA UV"i "raims gm sat 51 2.3.31 -1 Sstem ZOmAi Use.w valtag dIi ferestiul tuassitten sa nee15C0?dirs lustatld to determine the inwmsts of the saet stsSIm Uses.1 uretreale-tio, Lines. anl feedwaetr tin"S. is order t0 uIReti the fneedo for 1e3as-.

toii of the variempps PIP asodo""ated ""utp" etosmepta. "ies" measurement yft wdo delta heastp of the asit to roatd tsmpsratioe NWd pTEswun, maditties sd &else daring coo1do. ~wa et was recorded

In X sod 2 directeass an the gais stew mad feedwseW Jimes M& Is the I, T, sad I directiome as the wscduealatou Itsm. ~se tsmtdIns were, Compaeud with predicted svmests for the Variues Firm Uises. ?be"e records won coupled with & vheel Isseplesr. of the upstinml reedinage of selected basger sad lydroulle sluoeksh wasy 81reat5 posItdeas durtalt beetup.

All restuictions of sowm for the vadsov pipisg van resolved.

2.3.12 M1-23. lkInt Item Iselatiom YaWe TMu peformance of Wei test at coeditmes typical of theonly eastup phase Is eerely to dumostatrse the overability of the M""V. ThS applic~ahl criteria at this test tosuitimi Ls tha? anl NMYs gloss withIs the 3-5 second lialt. All eISMt va1es satatfactoulty set the gloom time criteria.

2.3.13 MF-28. ftlief Valve Aduatiom Manual actuattom of eli valves mes perform at a rseator pressure of 250 psig. Valves fuscttoed as expetted with 2 exceptiosa.

Valve 1-181 had a failed tai Pute tborerouP a and 1-Il tau PILpe failed by 133 F. to returm to vithis 1L0 7. of its initial teustat~e. WhenOft

MIAL SUMOA UPMR - DM V UIt a 3.3 Phse III - Ia1Uial flestap (ftstiarned) 2.3413 (Cstiined) vailve 1-23 failed by 3. P. tofrn1I retum to retested, walve I-IS mw aaadteoevat" . valve 1.3)2 sucess passed Ulghi 10 F. of Its laitta ressatiat entervi dwial Phae IV testing.

2.3.14 M~-70. *WasteT Ifter C20MUP Swots the heat eapIttes -

Tkgm tests were "flow to tdauat, Ert test of th reaembe NW seweam wmattW heat .ashIem. TMflaw was sds thic% al deale me ceemeed Is the Net Stf with a lamu ftlo *f retwmio the reactor with e bype" fele. of 1.3 a 1P 3tm/r. we Obtalasi b . e mt mal face 6.h of 0.14 a10 1b D rMs Ims ~ wall, with the dehi fits 15.8 a tI The aeemld test Mgma ton dte Ofweal' "As Is With all 9 to the veatter wath so bgu w, MO~

sleamu noaw wa retwmed 1£ 1bs/m.0 a heet Comm"e vet o 1 a 10 alsasup flow of 0.13 a we hi eemave Wel with the desi 91es of USte/h ebtas 0.14 V M INA 15.6a11 St./t.

uh all _ls*Um trid test Mae no tohe *Utauium' ewe La Th " sltea dcharsd to Sta or ase gedme. ah e.

VP ftl we x W lbft.4, a hbea "tos 1 osslo1.

flo aue of 0. 02 wel with Oh dsp fSe-- of 0@.0) a 10*

we. ebtatmi. 714m camps OAS Ml 22.5. 1aI sta/b.

ftug Islas tesmetura V" 1ag On thres leatS dsesarmted the sla "a to So 3n et" m_ the islet hed be 1300 V. the w rwemptied to the hh** me

_W stlat toypIratarm of the msIagdl treteu".

1eldVitulsa. s_ eatisfpta m-1. _i Neat _dm , into 2.3.13 the residal best ruwesi system Ms upwated to athe supastom to have suf(last beat evehaevaestnuwwal mapseity to pool cesIta'm and lown, All few of the M het all satisfy dealpg cmlitls.

citeria (18? no Ste/hr.).

M-72. !Mil Agvesebeut fhltAe $Men 2.3.18 at sah Pgaes dWim

rywell tampeatura w"smistern an Criteria wih Vth Is the *ty"11 laltial heatup All csoedlta top of the Gauuftsial A . "h het ezstiss of two peints at d*11U the matfd removal eapabIlity of the Colrs Mt criteria it temperature and prusure.

a FIMA SCHK&m 1"PM - PIP VMI 2 2.3 Phaes III - b1It ta Plastl. (CMsste) 2.3.17 004129 VAtor-*Fvt0%

go Isentac bml~utgt 4 cthel" water syst e~m mem balauced to New dee180 e"ltl~ms. Itse bees leed en she us"a = heat mhi&Nfn IMeWM wthie Mheinizii dee1f SPOCeitiatIOe. All crIteri assoasb Liewit WSh test waro Mt.

2.4 PasmI in ee Losf 101 he4aw 24.1 ff1I. 9iniAU 0- ftMj1mhe aai~

Thrmt stheeats test ,eoem, AMChoee &V cediocbsoiel" asmr.Ud Mt Malys" Wmr asf.a mSatas ad Special eest bIsis.

aulsemilMance of tho reestr as et. s eet foehetet, ansmwhaswrmes tof d~ty.ahisido eameamt twulbdty be'. ies. Item dhe peista. c ie eAufflasea ly hI etemla ad"im. *=WU tettieg gm degl is -mge to ases the Tat". mms the, aua osture radialngto Samoases aisatem. segem miuwty low"$a cml purtrmias., of the off-us $pten.

hatstbW Of SCOM GOPete mg *dSw Performance at Slrams Perry

Consisted of -p of WI sOd 1oft PM plates") twejimeo of sllma saillbate, in" gm resets. "an to irnioes the esauitivit7 of fe.U4 ce'yosv iaer WAt the 1oseser atesu systG& au

-b of service, Reasto vat" ceaei"VISY embeede 2.0 u0ftg IOco 25 platea, due to the for 4 bowrs as December 4. 1914, at 40 teuting at she 0m roaster cl"mp systes bet"g bypeesed detag cm preufrmsec et&~* teet.

eeso thrmmg~. m~1aslhn r withi a stab1iswe lIais during the startop testing. Gge seas et rInArY water dLIGW amdth expeeted serm~s sadm astivetios produete All test GrIterla Wmosaifid 2.4.2 $TX-2. NW&Hleog hsta At 25 ead 505 poua MW1sts SuwvO us" .ON~tae With all locat Lat but. au within the ritert", nhe locatitol which "go"e coocern la mibad neor~diftly to prous: wexessive azpoures.A%aile "Lialted 6hisldiOt ml asCes. esexol MeaSUe eWeis bealg cftPlete1.

test coaligios (511 pown) wth O*U I10utig

&UrveY" ms performd at Writeria.

ezcept the Ome Previously mentioned Meians the test 66cgteane R

cm"~- AMKP MIT 2 a DMA BM~WR 2.4 I2 - P&-Radig tignt of 1a01mt Coinuedt evr I yes of U br sam t PMUSIbU bacioud dos late wae defind m wikad acdiftly at this and the ?revo*s teat coodttion 5n poist. Te COlsza SUrvy as codected at the test comaltto 41 (9ff pt.:) with al locatioss eting the &cPtaac criteria except

w. Oe of tes mu Lbe previously matiomed best ionsd tb. ne am heims a aimIlar previously umoticed loeatioa. Ibe does rates foz the two locaioms were 550 a.mhr. ad 520 msmIhr. Typical dos rates for this condition were has thad I arslhr. gamm with a fev locatame exceedin this rat. am other locatLom ieb approached the test criteria level was Placed g fr frequet survellanc.

Instly, special precautions aft ia effect at the Problm location to prevet inadvertent parsainl overexpS re A proposed stbeut to the technical specificatios iS beig considered by the IlC to alleviate the tIng brier pb: -s i t et OC0 r r s for the relatively Inaccessible locattio. mantioned ahich did ut met th. test criteria.

2.4.3 gwrol Rod DrL fracas Sram tUwe of the lowr sloat iLa.Seque e WUs were masured duriag planned turbogameratm tripe at 100 pM All four in-sequaen rode performed Isacordamm with th applicable acceptance criteria.

2.4.4 f-6._ SM erfarmme mdaCtrol d Sgouget

?m UN Increased to 251 rated is seqmme 'A'. e UICS wWs tested at 01, 20. _d 252 by attemip g to select Ona MC out-of-eemncc grw, m ws showse to be operating properly lter tCe I= $equec 16" aS Stilt to iCeSe pmrs ea the ICI me f( to be operable at the smpown as above.

Te LM Is soK required to be -perable abm 10 Powr. At apr1aately 30. thermal power pressure teihes at the let stage turbine will atmatically bypss the I= logic.

rwing the startsp ia both sequences, tbh operation of the core wa closely observed ftot rregllaritite or reactivity amuli5 5s a result of the rod sequences. Boa performd satisfactorily.

UI-6 deonstrated that power could be raised with rod vith-drawl in a safe md orderly fahion. All taut criteria were met.

i tINAL SLW y REPMT - BtuP uwr 2 )

2.4 Phase IV - Power gEraocon of IO-1007 Rated Octout (Continued) 2.4.5 Sf1-9. V*cW Level Hbumrefa Calibratcios of the farvay and C Wc weter ltev Lstramntao tions vore verified to aaceertis accurate reactor water level indications at all times. DOata ere also recorded at M 502 and I00 test condi'tons as reactor water loevl was varted Il 6-lnch increments betceen the lblk and low level trip points, to obtain kwl~se of the tracking perfor-mance of those level systems. Adjustments to calibrations were ma" a seen necessary. There are ao criteria associated with this teat.

2.4.6 flJej!rforsa T-1-&

At 16% power the Wi's were adjusted such that a readtuS of 120125 of full scale oan range 10 was equal to or less than 301 pmr as indicated by the APRM's. A second calibration was requlred at 19.o power to calibrate UN'. C and B wbich were inoperative durLg, the previous calibration. SWII overlap was verified on a subsequeat startup. All criteria were satisfactorily mat.

2.4.7 =_I11 LPHClbai Using the process computer, calibration of the ht system was performed at the 25, 60. S0, and O%power levels. All operable LER2N's were adjusted to rea" proportLonal to the eutron Mmx in tle oarrow-narrow water gap at the height of the cbber WIch satisfied required test criteria.

2.4.8 ITI-12. APRN Calibratiom At each major test candition, the AiX'sa were calibrated to read cqual to or greater than the core thermal power. tbe calibration was repeated after each LP&M ,alibration. The ability of the A 6l' to maintain sufficient accuracy over large power changs wa also vrl-fled. A power scrom clamp was set 202 over the highst load line ia each test condition before ascending to that condition. All test criteria ware satisfied.

2.4.9 STI-1-. Process Campneer The process computer and oscillary equipment performed welt durLng the startup phiase of the test program, Some minor problems were encountered li both the SLA and NSSS progras. The dynamic system *t )

case (DSTC) vas performad and all system programs were checked out. All

M5..

c VIMA S1IR lI-mi - VWP MIT 2 2.4 MOOs auT qevtIGG Of 102-100%1 Rated- SWt (COatbliid)

POW 2.4.9 3-1.. Frets" 2MOM (anut~ed) toat esitori Wme sat, ISIC eUnits br boem s"at to~ La Ian sonio LEa & detailed evairnties. 09inMdP rmp

'Fo ahemm Seed stammat wIth off-Ulmnc m s~~m ase reactor Wmr Isolatift Cooling sutM V tested in the Iijoectiem mods at 21 powr and 45 51w. taiats: reemse was satiufactory and teat stitera gme Not Minepwt gm the Mig stemn froo Isolations etpoints. wblcb rmnls Ceosezyatiwly met.

2.4.11 5-145. ]MC Sstemg PrIor to a"teists tbs propoutioait '-V an she amI Cestlollr ans tocroased tram 400% to 10001 USIm left at 100 1.1l flow was raclhed In 23.5 seenda. Te gmC tublaa du m Mt CC 1agb the teat and the tnblm *lamd s"aI codeas napeble er od possi Instemn c leakage to the tos~pboese thus satlsfying all crIteria.

The cbrervatiam of selecet proces. teqertures soenni-ted at three operatiag conaioins. I~e., at the loze ad of doe 50. 150. eat and 100t lo"d Unes, ueaeOttely. AU test aritada--no edowutely at each test COMMtON of Itatuest.

2.4.13 &U17.11 Iwrst JWMSIe

?ee , ttr lsesma M catiomly miattred WMt VW0 Isetraiwa tattoo to detarline it doe thasnl.SWa gm eatie factory. Thesm Sytalm satisfied £ll applcable teat criteria.

2.4.14 111.1. Crs Poam" DhAtributies TS W reproducibility tests VWi Perf"W" A haOsS, emall am at test coedItIas to the Oh at test codittao. ML Te results of both tests were withis Me establIsh criteris aI reo&Asbility ws satisfactouily verified.

IC Th core Per distribut oLo was determind at several powr levels using TIP data nd tshe off-limn computr.

FVAL SUM Itf EY

BI? UtT 2 2.4 Mse TV -- Nwv Oieratiov of lO1-lOOf Rated Outout (Continued)

1.4.35 m~-i". Coe Nyfoge the significant care psrtrCaes Perintas" such maimuia treetLo or tmitift pavr density OWLD), minia critical heat t1=

ratio GRn), core the l po , mintom bundle critical pwnt rtio O%1I)

m1zIm werage pleas: linear heat Beastacton rsto (KAPIUI) and mazima lUnar heat g&nratlon rate (kitj were mtored thraSgh.

out the test *rog at eac of the operating plateau.

tes .puter cicauluttio lwere la close -pT t Wi mantalnd off-Jim campter calcalatiom At eCh teat Cae1its the reactor response to rod inmees wa satble sod well dimpede Al1 test criteria wr set 2.4.16 ffr-20. _getrical CRgt ad ?feet lbe 30bow gross lectrical output w rtx I dustrateae wa conducted om the 3W boar interval grow *104 hoae an februy 23.

until 0100 hasrs a Marc 9, 13 Data fram a 17*83 p*erio of reduced pwr operatio a eiued froilthe test mlysts. Is al*

302 read Lgsat ssbour Intervls were cotected fm tele pleut pwocsa ".

%camputwe or by dt*t observstion of pleat

special test ' t a Except during mne ncAasquesntal pmir trasiant, all teat ctitstt vera satistied.

Generator estw!

Ceneretor terminai oupat WmdeterAid ft.te d mit mater m corrected to rated conditions of eondmeser backwpressme genetor losses and generator piert factor.the Msaab test istrismte Vero used La all cases 6ith me exteption: sMratot bS&water we actepted as the teat standard) to provide corroetim "Retore statian Instrumant actually tdu throu^ibut the tet*

Core Themal Ostwt Core thermal output ws datazued by pr it e c eq calcutatiaon (W-3).

2.4.17 STT-21. r11axRespsel goftto the stability of the cre local reactivity feedack macherfa.

vas verified for emalt perrurtatoos La reactivity due to rod movemete at several points during the startup test progras. All test criteria Were Mt.

i i

I C LFM stA*y URV - U= till 2 2.4 Pbas* la - Pomr fratlon of IbIOOt1 B eaptont (Continued) 21..18M-22 tLIUM Iubtor Seroint OCbnte Us following tests ?* performed ea the U syct to verify the Pressure rgulator pertoe with do rse"Mt fto 11Mw .otrollSru met Ine mm l

at each of the test CoM ove Presented La Table t.2.

At each test casfittom a ttoaltt record was ake of patiasat teector pop555s ariables.

1) rositive an negative 10 poi set point chans Using first one, them the other Pressure reglator as the primary ceplator con-rolling presUre LS the 1t ollov1 UamTu a) with led limiter set MOtoa ssthe nIre transient wmg banded by control valves.

b) With the load limiter set so that beeh the control vatwes and bypass valves acted duin the ttrm t.

c) Vith the load f tar sct 1" amoo that the sntire transient ws handled by the by'pasu wives.

2) lb* regulator acting a primary me "falleW, to allow the 1e ulatow to take vet Coatrol. Ths "a wfnou uing first

-. then th other - the bask-up regulator.

As a result of liformation obtalied Irow uit I testin of on-22, the vat a uit 2 Was greatly eieplified. A Match filter we added to the MC circuitry prior to startup ehish smblad premsure wgulatoer opetasation dories tiitial testing. W test cwiterat mwr eatisfact£rily me at all teat uomitiom.

2.4.19 In-l1-) ar ato Tw types of teats Ws per formed as tfadwter systm 1) t lvel astpolat chadps of +/-S to iaes waes ade ia both 3-alamat WLOI-s .mat control La met" Uel flow control mod at vanians test e4tlo.

2) A Leedwater p_ trip was perfom at test Couditimo 41.

Vor each test a traiaat rcord of re l Poss variables Ms sadw.

level 1 sat"int chw"e resulted la mdno erana ts with a slight cecillatOry behavior noted in only a few cases. lb reactor crim could be directly attributed to feedvatar control system trasient response. The leel sutpoint -hanges for each cast comditiaa satisfied

-iS-

-lF-0a S

In MIAL £3UARV 319? - IV" 33I!I 2

- w - -In IA4 Iass. lv - FBm meraIt of 101.1001 PAted ~alga (Csctuzm4) 2AA9) M7123. 1"Ooste IWMt (Coottome)

Ofe ewlicahe test eitewIA, Imcfeeu'VW. trp ft" test comet 43 1momm9A sanfh txmnimt vII moeat eamtro of Toeater mtev level. soe trip yseftad IS a vesitrelat PMiehc I % &U-.h eatv*lie react.,

pom suchs that the twon tme~ela ftesuotur PM"e mid WISIuaI dhe proper WSWe level tho preesmlia a UVwinte level mssm.

..4.20 31.4 ia alves Testu kwgbe"s competed on the bypos vaIve threUg Ime 2b& test results astablah witbost esatift the by""n Vowve GM be tested at my Powr legl In the Haster Hama flw somul mode. nun spikes, VW. Ia" this 21 sad praseur, spikes less, thas 3 got at eau "at eid~tirme. Th bypass voeiws partemsee asetmd 4us. 1 level I a 2 criteriA base bee mat for all test conditions.

2.42It 310-2f. Bit Ites IsgItacgLVAlves Cloing Allt n tested 6y todividoelbt fIII ws Cal 6 u sand the i measured. All velvo* Wm seither Vitusas Unaig 21. awtri ow edjisked to met CMe erite"Is. ftesuefe trealatems Awl"n siagls valve gleuraes Wm *MI, DWI" hwaimal Mtet"n, sas valves - slomed 10 (I Goe")

to check watiam. hiniesae were mat detestable Awl" ng this at bhase.

hA 3811 full Isolation owazed at I PM" and test uttagga 2.4.22 37-2. ale VI vhisMtt

£11q~tya Al resesatimSg rttsrafo lb/hr. ase elmiet delay cLim was Im3 """is and eli SIlpip UNW&a tures retaaas4 to within Ir P. of their laitisi tempratmme 1.4.23 53127. Tighim 6ocp Edi Castrat Valve WMl Vest clasat, af the wia turbime stop valves vas demonstrated at 1001 of rated reactor camliitims. Vast clams of the mse tabias control valves Mas dMastrated at 251 and 1001 of rated reactor sow ditionS. lbe level 2 eriterL& uhich requires Mhat the feedwater smlevel J'.

I rJIAM OEMAR "Z?T - am Lyn 2 2.4 ames IT

Pit ertiom of10HUM0 Satel gti (co.Miam) 2.4.23 StI2i. Twubt Its NWd CM161 ve %av costluani)

£OMMI 3e1r U lowuto hwl otelazes VW ag, got W Sid" 9 avmMe of the IOU1m Itvo Wo. All6k oter g uiesta move emot fw ash geet.

SA.24 fI~ lsmatsiu b"tiIA99" par trite gmi putemd at sm twMt,~ mi I00 Of Razed resezW CGUisjerns 124sIles both owml po twls.

frowtesz "CM OaMIAwlm nmelt* la valmm d14 Mtn FM" ash uutterta 6Isattefstert. is iUi...s gramoe5 atlume "vStu" Two on"i calaUlata gm do"m he tugs$ Shut iq"ls a gumtea melje. AII trips dbzusd 6eits, moonl to am %.asMCI' u.su use tm rp. tutp trm 1001potmz me she ant timusS Sit voSate.

1ftorwew~ dataeuls tb at wulrn own tavels deitm tb ohs" oefl9It s. sofalaw. mmu usmdslasd 0eutitcsat06 that avMUasM did on *NW thdo Tsi*wlWaSU ystem me peffm~i by £ssestq Gost"I Iods 0util mm de resstrmlai vrekA we mswomzeie. Wsltaly OaiSO aus essistwm at e~m~euey 21 p n tho. mmh etsasw we "aes a he Semo Ii dies peitacm. Sant aui eses she '0A m41 us a Oemser a apsaatay22.31 pt.bssatteaftm of sersou" well p*ssne oitaither tees 2.4.25STII W- lsee ?M-btm' razow Ed 0fSuit hSU tes was pbmed vigh satsto oppa$M St 31Z qpews Boot howagsh ait a 11.aItes eiSIV a mdshaI ad She M

puwzs euia swus*s Coald one fies shm Ow 346w the ernys of eiWa gloaetiou e1" 14 ta1$

hwu 0.00 amt tublan-sma~tor CHO .mlty $Alttaz C 0.0 stom Control valves clomiag

'I

20-MItL, SvRI NM

I ?

2.4 _abe gm _ of 10 ?Ated am (Cki_1ed) 2A.25 I n _fLEt, _Ivmy 0.10 -step wavse1s A.

beebe fmImeI . sm I

4.hV ul: boeov broakWr UIV 5.30 _ 4-%? eOutdm bond C ftsds bWd twt 1.40 No Heist Punot C _nuft PON to Mit 2 ehmtin l tutst 31.15o MtU ""astog te4leiS

ISeIN&SIs latioa dUtmaeo mwd All issueI.-o pamto" wulmed Us4 mte theoe 41e"Un its d1w tdo she aast Ad all mocit *Uotvitl vtehiq uw omia.

2.4.26 __-__.WLa MsUrMh DA&

WMble at valves wats iWOUIvtdull dine at M3. 601. Me1 so atgae penurbuttesta as obwa, and Mo ro ve IS.

opexaltia peings, were soes, asa sellt of do valve sloSue. Al 0 test gritexi Wm me.

2.4.21 111w34. Itb gos h esssmg I vratita dat as Owned tis vtu WM* As =*U.

latios twmip (5130) aSn-XM, . ain, p U1.

" AS requirma ew for at wttb giqOSIM valve ags d6gW o a to the ONG1 .5 gb u.Q-Ue hypes. 14n" .

flut euattm by a qsallfidd spsLaltst .11 ibe so"

Ibtet Eate.

2.4.25 la, Onft Itmemic cooling Iwot_

PRwIM twatsri v# mAtaer a. IM gpmt Al1 tnpratum La t U Mat et eCtetria withtb

Om I" 05 Paints a the op of &bs swxtftalai skId. 11 s qali het to" Vs

,:ob* to tho dauip wils. AItboq* uTu9la, woe . with tbatws excptI=W, the UNC llat tam8ZntZ5 A$ Uvet Mani ts e ie" vale of 1,S° 1. aD will Eagerulm If funbar teatt" is "qufed awlor If ths tiperaetUh aU accapcah. InIa GValQ4Uos Inlic4Wed thAt the tCaUeut"u vat acce table.

0

sooas -& A ss - e -

o .

VL~ hns1 EEVWowW t n~mo W 940 Utidwe(Cotm

£YfMW ktwm

__ ~fl ,g,

'.':~ bs as do." 4t~ ~O

.34 .U.*ESI~a2~

~' ~mu.,~ ~~y b~ L mI~busu7.

Il-l VINAL SIMU IPMe - _P1 I a

L1 3I I Wdt l d "d offllst1Ws to tie fen cme aim

&S.,;

-US-a Mt tUs putsily ledal cm aum be wadittlea tw at )Ism @4.=. aWut the sloemt"Clly uuueset tsd

,tuy wiartuS Awl Iell" bom so a 2a. 1974. Witt the 140183 of the oetalesal syt Isee meur cesasfuy Compted so Ja y. 1974. &a tha ai au P estimlo

_eueus Me laoss1.4. au,4 - uIW s mmtstod NW tftiftS~alo .kU 184 ha ee6MMIes mrs imesald aid the cm wrtio"Inft o"Ietef. f*tta cme shwtf miglas sa lsalpe ""a to the loean" PfORSeSO gmr mdmtrsted *dat th ls d. sattatyi S ut" to" l. b ts teal loel* ibobs is 4damn ob Ie_. Uh we#s ti tUsaglee Ss lo blade _aoe.. s olpew of a&

a O. %too " thu th ebe u '0 deteete"mgo war hoeled to be am The MM pek nle Iwee VW*

tse Plant am ls"Coms ml th slad to ml.. mte" was Aldhee %a settl ot terUhe rMd sal ad tgrus mstle of Os Lc' s gmsevtoome by sumisha tuftr somwtl tm t'e ad moss the m that Wit a *n? of Yh Gatmatifm mla sums tlearom the IgtI*m

-mess stle. de an ewio at a lesh met les 1i s 1n of lthe W "et s estialeowny on. I* emt.ss 0b* SW uso" dame Na ag its aisl ta sw wa sh l'We earls Isa to , th at tobu. o e4#90ts Wm sod so mosw existed

'so but he AtW a eaMs ass as . .

U SAethals S bo a'. .s

5 fr man asmusta I a _so" gm r deesuwise La th startup tost "sahrest=a.

e

- MMWMMMWM 11n 3.8 FeIts (cmtiawd) 3.1.1 s- be tiam (MUMe AneIreiS (Coatteesi) fel la dia few Mit I wa vertsAd vWm the S-b oPeratlamal &mme lo~ted la the me.. Vitb Nearly GOcO cui tot &Mce Strowg at taltiautu of fuel 10"adt. -the 1's were "oatioee a ulafwt dtistaf fcom the fast tel boodle locattes ls oGrit to avid a sc*rm. he the geovatry of the boes pattern eSCOepusm the LCss, thy ware movd to arpriate ooUUMs &?aIto to rdue the VeebilitV ot a *erin.

rfue *Lai Proceeded framea yitrcal Peters shot the ramler Seorce troug

ospial cooftPuration, fetmi a "pia-wheel" cluster etered *road tde ematral atMo rod. Do FlW were *esloyi troo* 420 abawUl lomad two the SIM it-cove detectos em ut to the cMPe~lm of laad"Se Safe loading We accomplishd by Mokla* sborItlea and tfaetlnal checs hefore ad after loadinp the costrol calls (2 a 2 fItl asmbly also). 1 *Mttm. t nequt 4 _atdweMarxis checs made at wart..core ass" d eaAtrad that the core ws sucuitIcal t al time by at least 0.362 Ax wtlh the tsmetrically ettoeput red ftuly witr.

Ths mudo4s by fully vItlwi the aWoMet td ad vltwhdrawa, &Aadjcent Control rod to atdlh 14 MA Veuify Los bubcrtticslity. taveas MlCpliaetift plote Wrt inaiatcs d from FMcowl"M taew with Al rod tasre to predict subcuittallty before lo"adX additiamsl Cme "ad11lis. la Certaim easee,GMth " _rt a fue.lassebly wasrlaa&d arby - operatiol rsaer of as FT, becAuse of asonetwt effectt, special Int"psetatuft of these plts ware rqulred to predict "to loadb of the Next fetl assembly. these guoesric effecte won eaettd.

The fully loae aore was verifieao Ju1y 19, 9I4.

for prop.: scating 4d orioatation of fel asmblies" md for ftel bundle aeri ninbr& MW core UcstlS (gsm fUR sn 3-1). Seriad eers,wer= dcked fair pr*e selection of low eawicheent "d hlg gaz-c! t ffel per f ivre S 32.4 All

in ST-3. FuTl todia& wire samifeatorly completed and the test program proceeded to the fuli core shut4own margtl test (O14)as sheduld. All critari* w?.

et. 0

UW s 3.1.1 *r_ 1'd;lLt~d 041t Vol/1 Ana I *isis ( '.o.1r I .ed .

Ot$NS FEMY UNIT2 MAP X lb NW4.-

CORE POSITIO 19frotlo *.4, a l 9 _. _,l 4rf. .

414 WA A4F f-":1 C4 :lp _~hI wo" lwwpF4w I .

.. lbo now 0W Db J-hitwps W-"W,"- .

v "1 1w I-o"f *Olnrz vlam U.

A A.

.+ 41 Li.I r _

11, *.'",prit;

.v;Tr .1*

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_ F _ _

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44 . A *. I- _ . 0,.. w; .: ::, ..,#tp

'a . ;; F` +7 , *""-_

,-t 6S-

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A; s!J OT

_1_- IF, I_.1R I l'~-_4

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7Ar. +,',.' r7 I 1.1

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-t F.Xj 1s,4

>110 44.1, \... V 4 :

..'l , , t.

,;Ap

-_rl I

e F,-I f_

bl w .C.1 ,11. 95::

VIL-C +,, )~I J' I-

-A

."I

_-]

112: L . +4-.,

] 1 tD I-

+.1 'L, oil . '-IiI-- - 2..,.

.+,_,L" 1 31 " hj

,1 I .

W-v+.'.If .- Il-l 1-l v - I - -

. j '. _- I- -1 u-I =J:L .,

l'I - - -

.kill, . 71 _114e I

_VT__- _. I, I

[.11"o '14,1..., ...

- - l W A-2 '"fall:-, -, Ec41

I

..E. ^s ;d

H . +,',- - a . ,I ..

A:'tso

.r I I< tlo" 12 Vt

... i4foolf? to* ,T.+.*'IL

- s 11 - .. ., I .1

,.El', I tbiEtB-.X : +f"? ,Tlyi-,_;,, ~_w ,+ ,..,+:. , I

'sol A>-

.iez

[.xt, 1w+ X xL.., a '. +11AI

'-1" 1 .

$+'

It_ _ _ a '-1e . ___4 AS A

1T2l1+l 1_-.4-,

i 111+i-i .

1.

p db

vI I @ I . .

t

-~~~~~~~~~~~~~~~~~ r 1^ll1f l . .. 1-;-..*Ir+l".I

..-AtJAI l

^ l !LI1! ot-l

lvz [ SIL2S"JIHIB *EfI WAm III l a#

<-l1;-

-ATlIIEX181W1eIJ.IS Fl,:ure STI 3-1

11-4 3.0 %suits (Cottawd)

3. 1 fas" 11 -- 1o ese n Cold >ftottm (Ctfbw)

Id-. b) taemu (onstamm!)

0*

up_

"2 ' I fit tea a aia glI lv SII

21 I'!33 " 1 S 1 1't a A1T

2313 au 3356 355 33) 333333 3+3 351 WS lii 32 +

2+ 9 23+ 1331t 1 41 1+9+3 " 4 eel12 J_212 1+3 a1 l a2 _

2+21 2+2 3+ 1}

M 3gS1+1 I I4+

3***t+ M,2l2lS1 4+4 $1+

307 I2 1+ 1+ 1+ 3+1 8 1+ .l@! 3+ *l3t +

n +,,,,12t2 l w or +Stwww Ua f"1231" w fl * .1+1~ l U 11- I1I1+ as 1 1 I1 1l2 1 13 O~s 3Z Ms 1 3 I +x3 a s +2 I

$ ,,st l as 152"I P1*_

112 I 2 i _

til I 2 If 04 =

02 - -2 _ I KMAI3EMMOf FML ASIUES - 764 MUM OF CMJ ROL OD - IM I LOW (LI) EMICIM ASSE.UES - tu 2 INCHU(2.5) £XNICKJt1D AS5t.SIXISLIfS 0P4ERIRtY - V 4 O4 ROS) 3 IG 12.51 ENRIC 1LO ASILMUUES -U3 £ S G$4 RDS fipure STT 3-2 Fuel sacmbly Locations

11-5 nwU. SMntART MO "I - sVW uT 2 IC 3.0 ow] L a (CO sLt a'aj) 3.1 goe pe p . of this teat toato emastvae tbat, tha Teene~r UIi be embewlflcal tbueaboat ido (first fuel cycle WIth NW eawl* gesinI am fully vutbdiramm.

lb. ebetdsi "W U of t e fully Iowa eore mat be at least 0.3a BZIK at the "ai eaniwe RSt"la the fuel tyals.

(.

the ebeidM $Mfau test am conducetd for the fully te4660 core b. aMaltimAfly utz141ut rod is the cast, 2l47W, was fully wIthdirmas Meit 22-0) we nottebd to poeltIft 14. 546110tcalitty 0t this pouat me ant filsiat to guarsetle a esiitdm sups of a leest 0.Sf S. clog ctclaldwa pertevsed by pdllia teds ina a pieeeribe eeqwwas V~all 6 441 daem th, as"""sc sad the aMa1iue w ith of each SW , With lb. Modowsaloof at g0 Fey the comeat"wm alteal so -thm 1th Sat.h, t1e f18b VW. . TO derT tD Obtala a MUSTte Prid MOS uremat 9.. ftagns 31 4-1 nL M1 4.2), It mas method =a pootlica' fasther, th tetal with of She Ultiram frym the vol, ma 6.?S2f AUL faigSh ameriod ftnemt crttuials it UN deolumise thet mhe cone bad on %al Tod0 ilk" %jg of 0.t33 +/- .001.

A ll tont critaria for £1 4 I re SAStafol do S

I i

1"4 a.

a aI 4,

49 iit a

35 Si 21 23 it Is 11 07 0

0S

U610 14 IS 22 26 30 34 3s 44" 46 60 54 W TAb to~ %;I 4-1

.. 7

..11

- 1 Gt1ffemt~l Reactivity (Uek/k) of' emjWrt 1(m rWISAli pads Is

i. I-,

Cm* -f .,;.

.C - -:

JAL 3 30,. 6.30 3.25 4.63 3641 a 6.74 4 4.32 *J5 S 504) '.95 7 s"4 13 .7.04

UI-7

.UtARV p~ii'tg~i--

F3:1. .

a i

. a no le:o 1 i r

- r**. I . I i-I *4**

. TA a I4U4 8

z iem a In sees.'

I t II I

I I 41 i

.. r i

.. *I. I-i I

. - t...

Ii I

I I.

.1.

t..1 I

j *i I Iba ta-- . --

II

.i.

i I..

0 A... .-. . I

. I .1:

isgur M~t4.14 I.II i Om1 cot late

... I iI live a.a ..1 el I I

in C(f 9 120 1Vs0 ') 2PA22440 214 274 tttce (liccnnast)

,ilel rea

.., .H, f.A ,

-4, s~,-

-- !--I a

p I 1.;.1-I. j

t. DA-.

I I 1**-1' I

I on I PA 214 24M 274 12n Fmlu leR-nCtUls)

. - II I I1 I FWAI. It3IAI 'KPMM - SMU MM21 2

.. t.

3.0 RSUemts CbstUA~)

A.%!

3. Phs nI - Vj Ybuae VW Wad TesaturP (CAmtluuad) 3.))3 IWO~ barn1 So Drivos no tuos aof tI.e Owtre) td frivo OPSye teat gng: (a) go dogmalrte thet the Cmtrol Rod Drive (CI) upatem operates p~eo~ry avir the ftul rants of PHUse7 to op.en1afs.

cod"S. temperstues anM PVC&Caro frm amblaum of cae Cow90euta MM partilailpwl that therm)l expastom bass sat bud ar silrificanhl, sum cosirol wod movemuita md (b to datetuit teA&Initial operaetfr ebaracteristles of she entire El) system.

(a) Uch driwe speed to eib direction (Onsrt or withdraw) mat be 3.0 +/- 0.6 la per. aft. Itodieted by a

fmdl l-ft. stroke to 40 to 60 "Co.

C .

(b) lbs rega scram inset tom time of all operable control rods, bed an the dsinriat4ic of the sear pilot vave dolenotds an time so, shell be go PVM07 tWa:

I laserte ft"r Aarw te ame luse utia 0.90 so So Soo (S) So at4etg Of the SUM tS _IMS tiM toT te thwe* fastest castrol rods of al ofsIs of four Castrol wae to a* W-by-tw a*ny s*bll be is #usster thmt I Insetted fham Average LuCn Iseertios lbill ewlgb -T&Om ("C.

S 0.398 la 0.954 so 20120 5.3 C ~

3.0 ftmIts (CM.IMOD 31.1 ObM U - ~sYae e 4 si~ (feu*.ed)

Cd) lb* us iisem INWIrIM. ti.. for OW.

luetle ofmy Operahla emiast god doall Met exceed 1.00 scm*.

(a) V~tb rempet to the contrel red drii friet ioe tests, it the differential presser. variation excaeed 1S paid for a ceetinusas drive-fs, a seulio es rmt ige peirftvmdg la 'iebi came, the diffeamtial rattling pre"Vers Should "at be lues than 30 Folds ma" shmud St vary b7 note OMza 10 P.14 ever a t.11 stroke. "VWt differestil Fresaure Irn the settliag tests are Indicative of afessiuae frictiam.

(b) Scram times with wvarl acewUlter charts shoold fall within prescribed tine limit.

All the control ta. Met the requftwtoeaS of the '

tests patfonued ontho during asro-rsactet-pzeaate teattAR.e Poltiza isdicati~oat rod tisissg. stall clme, coup~lap cheeks, med frict ion tests woes perforr*d twice an each CRO: dudag amt flollMs godue loading. gme raslts repoirted ber& &re those of the latter testing peried*

the Tod poeltt" Imfornuttee sysam was lextensively dioecked MO was operating properly.

The sarsel. god sat~twrl, ard tosert diuess together with ONi stall (lawas sate Measured. Ros of Cho drives were edjuated sothat their times were within the above criteria.

4

tZ-1I FINAL XMMY gT - l? MT 2 3.0 3sults (Continued) 3.1 ",A" - he IM1 a d (Continued)

i. T-5. betel WRd es (CuaLii)

AM V.s Cotne) bis. gek we perfomd duriag fuel loadio

__eve a rod ma fully withdram to pusitta 48. All lod gmis esq d to their drives.

ftlett{6 t-OU All of the C's were frictlon tested by continu-ouly Isserti the fras po*Itio. 48 to posltan 0 nsid Vhtogqrapia the Inserion presso e throughout the insert process.

o frictios teat data wre at. uiua asng a strain gau di*ff tial pressure Cell and a storag OSCLIlSCOP&.

Polaroid photognaphs of the oscilloscope traces were taken to record the data.

A11 control code passed the contoimau inerton Va'm IJ criteria.

ULM keting; Siag opes vessel testing all control rods mrs H1 ys tested'. IU aeass sr thus fell well within do level usyalmte. (See table m 5-8) ftum tese dam the fure slowst la qeacse control rod drives mrs chosen to be scraud thrc tims sash with adahm ecemilator press"e. lbsan sera tHINs to 90 imrtion Ma fewd to fall withi. te limit.,

set by vier sIn s-. Table Sn 5-1 gives the scm tUses for th slest drives with normal dminimu serm laselatwr pressures.

C

AM12 3.4 (OCI-14 3.1 Pbo IS -. A headWse ml 2 ftatift (Ctimn~d) s.1.3 aw1.. onI md Dimm (On"WOO S1 t tou lnSn 10tr em~e -- pamai atmIc UmmlMslo VjwwAtim wamtaks toz tram Ries pool isr tMe subs41 dedmpbwvle66w 1t.as.a wr vxm aamlmmi olo wits* tr Wagp1o9mbl

3- O krsut.ts (to~ntinwdj)

,.! sv.sne t. ,' ._ _. '., . " -,* _ '! . . - -

_.1. 3 _T !-5, Cot'rol F[od . rivvs(:3 a~n 3.5 4_'-w*s'. t w'-';e 1

' ' . . -s t . ,_

,wt;,,1tEi

_ t .1

_ t .

jlib41 '

't-t - . * § 1 w 9 , 1 ' '

sVm1 DPMTII MO Ml 3.01 . _-: , ._ _, 9 -. J>, e- ,*

0 . . t ,.... ,... . . 1.Aceletor preasneg i.T.," .. . I ._ . I I ' ' !

.. , . . .; .si..

.. i . -1, o ,6 t' , ,

': ; X,;; 'vl; 5'S5/535 psig at jOCe I 1'll

1 . 4 4 t..4.. t .vt

.I.-

- 1 jI' It 't' 7

.*-s X ; S . (3).9/41.2 kg/ciX At 200C)

I

>:411' IT .r _1T 1 2. Iteewtor Watr side

-g e w

iI,4.-If w j t

J

_ tS L.__ti iii;' r-l _x_ __ 16l0psig,(105.3 qjn a".t} I 44t w It " +1 J 4'I_

4.,j 1-ji. ,t..*_.: . I 1390psig. (97.J kg/arfl min.

l-

_I T r1

,4 z , 4

-I t TIr t tP-:_

. - . . . - . - . . . . -, -r-r 3. Screm valve air DresUrt I i 4 iz 4 70/J5 Fs1q. (4.9j$.3Q^g/al4)

!!I-' 'Ir t.11II Tjg .5ALi. I 1

!I .r -4.

_T9;t

-It 1I0- - r ;w4-I T' 1

I 7!..x 1 4 1

_* A 4 i4-,tl 11 I veto aptttCabe~ to singl CRO 1.0 i~ T-r

_t j4 4ilq t+-i-w4 1#!+,

T-;:i -+ scroas with chargin~g valve

' -ST . .- ... .. 0 = _ . Closed (V-1131 or full rerc~ar

J.A, ; Ii . -0

-9 . 4 SCeM With Charging valve t> - t ! -. :4 I . I 1.-4 --.- I'I, . open.

4 4 . J t i4 4 r mr 1

4i ti i.

4 4 1 Scra ttbe Is the tir 4 fro*

.,t f. t J.,

I 4 .

loss of voltage tx crfert air Milt v61Me to 90% insertion 2GO mR Tpi1ku of 1101!.

G SW¢ 1000 VESSE PnKSSLtE4 p:1g S>>R.M P£1OW.1 FQ i C C'. '; FORt WMCE 7MId44A2 land ;2l44Ul Cl~s FIguro sM 5-1

[1-14 flRA SamIR NuZT - 311 UEU 2 3.0 &P.V (COasUssd) 3.1 zhme at

9.u Yanait owd Cold 20tiat1. (Coutiuumad) 3.MA £T1. 3M forwsge .4 Cbatrol vod Ismon~

t~so oatiraama o this test to to' demetrate that dw axtrmstntatiae. aNW god WMsta I

dra" ica t y :o eems *" tomr nu to acblew SAI-o Sm&$*roa isa vare and elfficient Gritcali7 mr. VAeetof tjfpIcal, ca ,tm otiscs cra*ctow vemr WUl be datemised.

(a) fther vast ba a neutrom atgmaltoosnotue rat to Of at 1aast 2:3 On the c"reo[ed opevbl. SM's ov fuel (b hMCO SAsW be a sIsiM= c~uat Mae Of 3 GP$

Go sh, required oprarible ftt' or foot Joedft dshbsrs.

(a) the [Du's mast be an scala behnr tm e&3' exceed the cad block set iiataat.

(d) The RSCIS shall be Vocmeable "segmetfia to the toeaical Qpecifications.

se operationaal souresa wwr loamud Se a maer cMisasa t with Sf1-3. Inal Wading. Saume Rese Lam Ire shbm to IUra TIn 6-1.

lobran dbe C' wt inserted IUDe the core 4MIC Count cata" were oh..rvd to -Temuasan theta beftroan" Woad LWs. After fully atrivia tf- !;&Ml' Impo Osb Wer their CarnaL rat" wan again facor~ed to insur that go. sigual#

to-noise6 W&uTIaon was met. This data Is cant~ in tabhe SIX 6-1. uL4 the 41scrld~nator anl IA to Votage *stitap for am axt units are 4&table -SiT 6-z.

fte, USCS was 6sbonI.i.rat6A LO Opsr~te sqqGrstty by the Inability to ;s.1cct out-GII-Gequeata ro"s.

IT-Is

('

3.0 &219i (eatitmed)

.p i A. (CoaLnuaad) 3.1.4 Lpi4. On Nfri. sIC-,*itr1 tud jtMW~ (CosftoWid) 1AIni (Centimad)

U weactor wa Lrought to czeitcatity Sa sequeno as tbs 19th aotch of the 53,d rod. Thm iolerato tepr

&tes. wa ori.

afte. SRWUM overlap wys wrified Iq STIn10.

do am' ead M's zes ranwd ras th mcolmg~eat eSO no". and the SI bthi level blacks set a their mIal polat of I a LO0 Cp. It va. also www that the Mn's r capale of momitoraSu 7.5 a 10 cp Witbhot saurat15.

All test citeria wer satisfied.

Table s11 6-l

(

S FullyIeahrted 4 MC Ul Full Ratracted dt 0. 0.2 Got 8PAel-M-EoisRaWU 49 39 74.3 19

,table onI 4*

Ii Bi Tlip 5 u0q sCp a 10S cp S a.IDS ep ..S a I1i Alars I a t0ocps Iu t CS 1 t10o C" I is to C" Imp. Voltage 30 vdc 37S ic 335 ide SIS WC High Voltage 386 vic 403 ie 350 icd 319 WCe

. actlalnator I turns 7 togu 5 III ttrnS 5 III tuM C

tt-t6 FINAL

SUMMARY

RF.PUt - lFNP UNIT 2 1.0 gejulti c'jumt uucd)

.1 c.o Ot - 4sI% Yedsel and-Cltd Testing (Cant iusd) 3.1.4 t1-6. SRM Potormances and trcratl qtJqLnce (CinttLnw1)

BROWNS FERRY UNIT 2 x U

____ ____CAM I POSITIO MAP a - - X ml Uw4-

+$ + + * -- e i a

+

aS + + + + + r+ + ow"

+'l +

a N--F ++ +1+I+1 ++T+T+ i+r+i+i'+ I+

C 3-ft

-- ++_ -

+E +d + + + +[+

_ . . ~

-+

U

+ + + + + + .F::+

a-h

+ + ++

a _ _..

+ +

U-

-I I-I I I as I I.L aB -

-T S-I 11 S

I+I I I IIIIL9-

- S I.II U* m - I - -

1+

I U- .1-S

-1 1T 1 T1 I - aa

-1 '1T-[

4.a n- ++ ++ ++ +T + _ + + + +

+ t+

- + + + _ _ _

_ ++)

- + + + + + + + _+ +) -+;

,+W

- a a I

+G+ S + +

a a a I

l S4 a 1s l fglure STI 6-1

MEAL sUnURV I 0

5.0 knits (I M. hamv Y~eIS. UWI tm 541.1 o ipsu ioi tb son to St., dimes the luster man"low , Walte ssem" to d~wasi Op"We Ousitsp witth M AaAMU systm.

UAs KU samml nt be adjoeted so that mvulap with the aUm's sad Owe' la &ssuged.

I* two mant gnawsc a "Wm at13/125 of full IM V IrKeadla. 12w112!of fulsct of au. go Iraug lb.. 3M Tated pamt.

10 to will beaa equal to ofto"a i

VW mm pIMmue"is ittelI as' to .al0 saft, VAs DM sum gautsmu tbvmui" Iplet te eahd Alse "00"epsticaI Q&Us. sAd ane aalata1.a4 smeolawt In at IsUMMU of tblm umths. Soe tolIne~ h bess IPl408d to a ema'eslostdoso wsu Owes psw~ fhet towIP4. At W t Ms as. Mh wa5se do lift de "1l1al w ~ls? daa was thatioge With4 masetis wue" at 5 a 15CPS. Mlns.

DuM" assaaAmi eda Wobe smp ape.

gSIe Ant".

2aa&WA we"s ssmslxe to lgs "sflla vatlue.

6W. mars VIObdawy to5~9@ sowso 01* to~sWM "Motia. All gme TWO' WM a. "ofI $fm, thbe

""ws tke eeaw mlxw lSW$.

tie IR'a tespomw to *smws 4D she MM~, f Sco.All. mdlups goashd gSista glas.

Aft"s the 115 fesa in4 tIWSN~aw~p ww m"Iflod. as SUS'4 sd UN's wrs* taken Mt of pop p9a, ajshwe oscm sudis.

AlI ealteria qVpp~lcil to tha GPMn Vessel teal 0 lba"a mire mt.

a Un,

.. 1 Audu (OmttmsI).

. a . at d.

s w

-.. e -f

_A_*_

.*_ . Xm 3Mm S

IQ

$a~

0

ut-i VIAM SMgA u1M - VW VW_2 L0 -4 Camassl) 3.2 ft... R - mbWJ We~t" 3.2.1 M-,_ strtl -d 4My VW I-iAI of ta catbol SWil d6vi system tcst (CUD) was e -to dammate that th emivel, reidofdrive P.1m:

_so Proeriy ovea tau WM#s twe" reto mad pfesara. taw ambiat to opewatlg.:

-63.t , of co coomeaes mE partu"arly tbt tbermal expe eotrol rod ammatat dee met bUe or *altifcatly Alew

_o Cb) to detemi tb. "Itil Ogeatst charateustics ef CM "inU CmD ystm of RaCim drive speed to either diroectfm Ciseout by a lull withraw) mat be 3.0 +/- 0A ". per m. taicated 1-ft. stroie la 40 t@ E0 sC.

VW average as. l ni time of all "puabla tioasm eustrol codes based an the dme glsstiee of tb. oafrs pilot valve solemelds an tis *se. &WI e so p ester tbass Table MT5-2 I Imsee fr*m Awrue Sarm Guaer

' 20 0.10 10 5.0 rag averae of the aim Imseutt estrol tifes for au bre VW& la a fastest desttl rOs of al $rowpffo" twbrtm sw4ry *hl be sb peater tbas Tablo 31 .3 s -

a taertd, inos Avrae amstafioin 4

'Rims 0 (e.-

5 CM39

' 0 0.95 so :1.120 g0 5.3

11t-2 o MSMTI .

2.0 &!IE(O mo M

uMW =mt 2 2.2 am I? - 1*1 2.2.1 aML VW vmnlinsum "swum Wiin for 107 Lusrtlaf ePTAeb) mctrol n dw~U Mg I. 7.00 eaods.

2mu Vigh fepe"t to the secat" rd drIVe Moticon toaste, it the differeatma pisasm' vai"lauts excees Is PMi 1., a costf'wsm driw:., a inetubw test in0utpressaur ta porfesumd. to 11ich cues, the dilflsrtial settlift ebsud Mt be Usee than 3 Po"d mer sh"Ild It may WY mrov than to told Overa full straoe. 1maw diftfemital pressures i tOa settlimS tests are ftAdictiw of emassive fwiettom.

Srms gifts with agree) aeealstorOharp shmudd 0 fall wichis prescribd it"m limts.

falld*

" tarfew lvsassi hs"Of Control to" wore tstd at maed taeeratmr sad Pressure W assislastowy.

eand 102). 14-07, 46-f1, and lslflMIS fitutem tesed at cam Oslo resters dam 1pressre. wase of the VWd We poesars. vau&Imsas an a castissous lasneumo """"ai.

"IS feav at". rde yre SONOM AMr $ble. St se s made paig vwexe presswre. See tsbles 51 54 caD t

Ut-S 5.2 hu..In

Inital(" (alin a TameM lOP asy frn b Uam ssvn im f"h~

all to" v2uuA" An $arnUirn gm.

won Vtus~ us n Tausgem sn oum ui swi SUl $amiito* kl. ~3Ii 4iul

II!-4 nVAL BUNKUM 510 - SI IUI 2 3.0 t (Costmnd) 33 Des" nt - leta baw (Csstsed) 4.2.1 .

M-S. Omtvl RW WVa (costind)

Tabu m 5-4 G00 rds kis ?lest - foVslut uis alatele Mc-mndaair

_ Test ts % . Se.

raft Isafttlw. T .ime, Lwstlam a e ps e 202 302 70 I 400 1098 0. 14 0.6" 1.40 2.732 2 G00 1098 0.343 0."9 1.440 2.956 3 ao 1098 0.20 0.610 1.34 2.150

.h 0.31 0.648 1.401 2.81

- -i .- - a - - -

c I 600 1100 0.194 0.629 1.416 2.842 2 600 1100 0.29 0.626 1.388 2.794 10-23 a -a U 0.2W 0.612 1.380 t.820 3 No100 1 O.Of3 0.112 1.395 2.820 1 400 1093 0.312 0.61? 1.312 2.633

- a l

. 600 1098 0.3n 0.437 1.36 2.653 3 400 109 0.321 0.424 1.336 2.642 0.321 0.626 1.44 to.644 1 G 1098 0.321 0.1? 1.508 2..9" 2 00 1098 0.33? 0.687 1.516 2.914 46-11 alea 1.492 1.941 0 1098 0.332 o.a8

__r 0.330 0.683 1.505 2.913 I

K -.5 FrULI SImma SIPlM? - V mWlD 2 0

S.0 RMICS (OstMed) 312 nM- M - !a1tS1IMIS CeosImi) 3.2.1 Sn-S. Otrel Ibd wim (cwtiaued)

TabuS "- S am eels Satur Tastm tow Suvitoftb St Rtre . Iota ur srs in lectio .l paig 52 2V¢ 50?

7 I I0N 1100 0.341 D. 1.94 2593 I goo lin0 0 .J9 0.6A 1.540 2.218 3 am 1100 O.W)4 0.698 1364 2.748 2 0.33 0693 .loe 2.716 C VIA 1100 0.322 0. 1.596 2.257 2 NO 1100 0.314 0.63 1.632 2__8 1023-3 2 1100 0.33m0.716 eSSm 2.1 n6 1mu 0.313 0212 1.55 2.254 340 an_ 1100 0.34 817" 1.624 2,.XX I 1100 0.331 0.212 1*612 2.894 2 NO 1100 0.340 Ot74 I.SU 2.756 O0.34 0.269 1.620 .

'I

111-6 MUL S lwm2moRt - IW2 MIT 2 c 3.0 Usomato (1ftiasa) 362 JhM II1110 fa (Cmtau) i Is L2.1 511. _atEl M _e (Cawtiad)

TA STE m 54 la" less scan tes - 0 Acw.late. ?m..t.

row Iloveat ade owactor Msumalator termn 1oovzts turn. see.

Driw Toot 9'tnssure. FV tuou 7 laltcs ambe t p.S pan 51 212 102 I 10o 0 0.361 0.748 2.60 2 1000 0 0.46_ 0.143 1.56 2.61 4 -11 -a 3 1o0 0 0.310 o.m 1.50 2.65 C _____ 0.3S9 0.156 1.36 2.64 I lowt 0 0.354 0.M IS9 2.71 2 10o0 0 0.332 0.711 I.4 2.40 30.27 a - - -

0 0.316 0.716 1.52 1.5?

a3 1000 -

Nam _.0n 0.33_ 1.52 _ 2.S 1 1000 0 0.535 0.742 14.0 2.76 2 1000 0 0.330 1.40 2.76 34-07 .- a -a 1 1000 0 0.315 0.7% 1.0 2.72

_ __ 0.32? 0.141 10 2-.15 1 1000 0 0.340 0.134 1.57 2.69 2 1000 0 0.324 0.732 1.54 2.63 v 10-23_

3 1000 0 0.335 0.156 1.63 2.79 NM _ 0.333 0.141 1.5S 2.72

I "mm .3. t 3. bmws i et 3

IL# *my& aem8$ hism £it? h,"Ilia ba"M1. -- - I "a

" p- ft=bMlm" on mmadeujflj -P "M 0 1 VA I la So~i-" OSWil -l L LaL I -47 o.Ma SM4 1.5 LII3 CIL0.5 GAN4 3.43 8L"

- 133L5 LE1 0.UUSA~l3.48 8.1 WuA *.%if I4.419 S." 8.16

-- 10 .33UL LM42-1 31 .324447 L.1 31 w8-3 - LR .i2L 2LL 331 .36 .51 A. LL.

24-41 0. IL 0.am i.U .1 o.1 q.M .6qIi P 11 3441 uG 0.519l &.a o.n jo-Il 6 t3 *4tLkiD J1 L.. O ml *1 ~~4. we O."? 30 34

$2-23 __ ji. .&j4 4.044 1.32 LES 1 .414t.

UI*_S CIN3 0.443 3. Lu.

ill 42 .6* 3.6 3 11-St 0.3 U4 .If9 I.1 8.3~

E.1 4.3)9 0.ft I.-IF 8.85 I 143.4) 4.13V.I L1.6

- - 8516 8.14% .4? .3*4

&1I.L *1- 0 7 .4* 1- 1.44 i4-1 "3I a.44 3.41 0.137 O.5P" 3.&3 8.41 224 .311 5.3r0 3.41 8.4, U4 . 1 p.419 3.42 8.44 0.33'

- .126 8,440 3.4 it 0.A3216.33-1 1-.1 ISAOP ,con4 i.r_.

la- IL..,_.

8.817 - 4.313 *."I S."

A. a. n L-Y A" 64 .132*~a.43 MO M.41 2.46 O$,.112

!..+/-L E."

MeX L -

.as -- - hts*I SM a - bums wo V _ _a som a" a

a -tr4-ic

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a_*f - - ,-- Am LX 1.3 L..

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_e~ - &vfo _VA "sa W Pa 4 Yr

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-t. ___*UI l1 101

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1! , s* .* -

WV? .*

1.42 1.44 I.U a l $:- X X1!-ibla-" . asz _ _ . U6 v.P 1-56 1.11

'-m- 11 *,~} L.41 WI? 6-st

'b As_

'ht.s I.n

_P-*41 *. 9._44t 1 .6 _-1 _. . __ *. 154g .l 1.3 . MU W. 3H16> _...

! I"- w, SA 1.41 61 ,5.4

-- "-it I - 1t"* . '*t -t t- - -1 us --- l" I.-a "x >l ." 1 0 w[ -- .8 "a >t. 1 t* .65 .

I ts CU 1- 11 2e^&'>l t ".u-M-_.11...

J li

I

'its-s I-.v 3.3. -- fw2 d bt lo f14 2awin 60mu S Id mmi bue * $uSw 31 no*E~IN~~

S - iI 1. L.5 L U2 w1 IL= 0.2 LU LOS S-P 1.33 1.8 W L 6 L IS U.1lft44 em er L a LIM 3 D-1 __ n. &rU LUf LIS 1 34 1 13 56W L U LO )

'LIU.3 51.U3LU LA5 41.165) 5.1 L U8 L a Wm e L ILM .aa Lw U-i __ Sm m L.o LAS ek 3" SM 1.6 1.44 2.3 C.

1111-hEaL mmhIarm - 31MMliVW -

2.0 IM~m1 oan) 31-2 a= U1 - tattlal B!M (OMUWOi 2.2.1 a"74 be RN ftkiwo cobsUad0 I

_"~~of Ai O185 0.286 0.503 0.91 1.642 M_ 4 0.331 0.50 1.101 1.890 600 smal 4' OAU1 0.645 1.411 2.614 SW won" 4* 0.335 0.f"s 1.00 2.5U 1o0w *2.w ' 0.339 0.743 1.515 2.64 14rM 155 in 0.321 0.092 l.a" .4 Fw fla owsns t.asquma ro"

11-12 Cit PiM" 6LIMM R - MCA=WT 3.0 Anr (Ommalmed) 3.2 a... ni

laa

-mj u I &LI. SWAM~ Nsw*im mmd imwt34s.

WPMofO toot ts Wdwlotfuls ha "

mwo - Iftelmgatals, slaasblsev W width bin) gmeOa pslostds 80096s tutouinitmso etisi4ity SWIto eisuO pow A Se salsf Min la5JAS msaw. Ibs offset .1 typlost ted uSnws so touter ImUlu be hudetisei p ir 14 (a) "Wmt out be a ""asir .psl-too~oaia utti f at lsest 2i1..0 the ltegaft owsibim twsot fuelPO (b) Set most be a misMa =met rawe of 3 op.

asodtetaftmd epuabla SUi'S oftfuel loiafa bsohas&s (s) te nu'. wast be es s"au e fore the twos GMu abs lod blobk got p01st..

(4) goe IM shall be ""eable qesifted is CMthe oshlasa 8alesfitaU90 I

"*1

.Uit 2 was be"te to fated tuapsst.e to selpsin

A. bUssM b~Suwmatifs ma WMfdlp =Sitots tO lamm afe t hemasu was sd PM" asSomim.

ase oaf awa of the bad winid I= pes-waled 4m aofreein tod WMaMas ths amlaabisa doe oft elltes*

T1iii i

lae ""Mues "". the no50 La osesd of for~

major tmg gup I A133 43. M1. wA Me 1i~aS 51 62 I

19 II sabov she An. AM n ad oes Elva"a514 6 M of i I 64 mistas doe EU2 53 as a~mbea smAbpeup.

ft heat! ag up and :asSager gwAsnt.ib procedure Ea tod vitbhitavat is am Millw for wAwqem "A'. Any red In

3U~T* WIt31?

fUIAL3U~A~

33 ~ag m"

Kaita Itm(~m qeetfe mp so betmerSW othe Ibs ax.*o1Ssbe 1 tlnUvoly to doe SU =qtie dmltyo b- ofwof basirl"saetwm. Omly after bth A£23a AX4 an ft) Mut so a" go-upbe m~imi On %" MM wci -

am" la doe peepo matc muds* ioo.a all dw rods uithft my sly.. no stoup mat be withia mthpeta of *ach otbac. of ftrth., gea UP"wespoibtd MAmr t be temistese with she- ups m a 9ema MU. 0e MGd pempeO maE wsweM IA .SOOMMO "I"us aeiam. AUl gut: situ. mm mat*

ItK- 14 FINAL Sela*A. RtEflqT _SlNip lMIT 2 C 3.10 Resulto (couclamad)

Ibas.o tiK - Imitsital 1ftat~m (Cmtittae4) 3.2.2 I 6r1.

?r ocau ad4 CoaTOl ftolsea e (cmontu.)

St C-nf are 871 6-2 AM NMd Grous A12 mW A34 c

Mrir-i F IN4AL SUb@NA1Y RENAT - KRTN UNIT2

.5.0 Results (Continued) 3.2.Z j:1- GSRM rectomife sadCntrol Rod Iegi'sen.e IV I

ai l Il l li lA l l

1. I I I I I I I 4 Fidure rlU6-3 U'S du~d Croup 512

III-"f VflhL SLWfiAr ll!OIT . Ad11 aft 2 I 1.0 meulti (Cootlum) 3.2 (hsp U-littal btm(o me) 3.2.2 T 1.W ros3c fdC tr1Rd8 uij

..- - NEU TM-21DM-1r - 1-tt I L- _ _ m _ A -z-

"I -[V 14 - _

3I 1 1_

(

atxl}- is is 14 _ _ _ _ is 1

w._ -

=7- _ - -

___I I flsure STl 6-4 WSS "o Group 534 C

11247 MA1 SVMARtm- IM ll 2 3.0 ft" 01a

=_ l _ = - V.wt__

3.2 nm . W L.L.S mV

- s "ro of this tmat to.*at tbe b e" witt" am" .a to sas a opim .ws - ..

W,' a m adm ta.'

(a) la& _W oumi mat be jste so tan CtaP with th W. MA AP. to mowed.

(b) "a IW* not PC S U*5gQI of feil ".b.

(s) ase Wm radift 2UD5 of1ba MIs30 Scaleeas ZOfot ,

Ira to wilt be "t "t to i Is gmat. 'id psifw. .W a ias o 11 teat.

Uo*mw ;ftthe eaibti voawees solualt" d1seMW.

Oas ett ~a shWe bby hevpst.

~l h*a" b" ae tp ..

_. the"X131 t' utd5

, da u4asw fQ i am In d"* Im to mmu rw Owl 1v dP;fhI te 4440l 1ut to 1Uv th bRA 13 saiw AUbl a beft "a to tu m4uuM, rev" u no1 wp w vutlW fStu thssllbi4ts Th WI. 60 #

ma oa i5 of ll saGo. .o inf8 Wm 4stfud Ar

11 -is PlUIAL EIUNIAUY 3flMP o 31P MIT 2 s

S.0 IMulA (cmlme)

S.3 Phaft Tim

teti*). Ilest" (OsAUX"n)

I 024. IMAI- A 9!mtftwma#

a s --

So prpme, of ths tes b to caibrate to "mAS POWr gume inltruw ejim.

(a) ase Am shinets _mat be calibraed to reA equAl tour Peate: am the aetvel eoe themal pow:.

(1) fthlsat v-Peciftgauionm huet wereasty limits co AM grm ad god bik shall ot be exceded.

(a) U th startup Ewe, SUi AM cshmes maot proam. a "TM at Ues t1aa or equal to 15I of rated themal Pm:.

(A) Realibratto f the AM syst- wl.t sot be essauy ftom safty sIA-vat! It at eat tw AM shun. Wp trip cercut have seadiag Poster th a or sqau tO sOreWp M .

(a) I the abov Offteris we satisfied the the UIWdhala will be smetierv4 to be reaift woeetely It Uhe awres with the bea balawsa to withis l of rated pme.

. wM. GIbrate usa tOe 1bw po heat 1.1ms based as the heasu r"te. After the batup ats& kw tahiud at tw 1. Par lei Oh AM#$ wre set to rad .nSthemat pwin. ts ealitatilWe sed wait*a we smcwte ean balaga comU be Wform.d at a MOM PWv Welt All optliwhi test erst"l e wave "gutftd.

U149 MDAL SSH.AT UP tIN WT 2 3.0M at (Coatlms) 3.2.

agg .1M.WA am *N="

Us Insp of AUI test to to Veifly the prpes

""stie of tmhe cmrnsoitolasi cooling sstma vem (a) So this timd aetuatiM sigmu to rewsind fbw mat be Inss One 30 "coeds at my atw pressure betwev 150 paig MA rated (1020 polo,,

(b) With..e discharg at r" pressure betwam 150 Pots sad MO2 pets, the required tom5* spap. OMSh lImit of I=2 pelt lacludes a snmioally h1.g% wise of 100 Pat for tisa losses. I Mbeasured votes of so pots my Sue. be seed.)0

(.3 The RCIC twibiti mast Wt trip off &Wias (4) It aitber of doth int two level I eriteria, Is O not$mdlo nmear will Oftly be allowd to upeat*

at a retricted paws level.

(a) "W~ tablesS Blend Ceal ladwes.r "aom Baul be Capable cS prevstagsi tem leakage to the altaphero

i. TI? AP iteb low the SCIO stem Supply 11*.

M2gI flOw LI"oIatS twig' Shall, be adjusted to astuateea 500 of the muirn Tepaire stesty state atom now.

anDnM All testie UrN Comboted Oris this Oas with 111 taus Sueati fanK samd4larsu to the Mdsmeeat$

storale tank.

At 150 96ig Misiel vessel pressure, the. UCI teat W"e ewMplIahe with a discharge pressure of 210 peig.

U -

fUL ani M.3.Mdb.4 IA 3.LS #

As gel"is uss" emS) t Ia h 302o09 moniefy ~Sat 61asbap pnmee of Uzo tmet lb~ Mt o as U) tost1as all smfou~ll data setles one goidsan estislstMy snUsWI.. getioat to gi~semt to tabl tbusaet lies the", test tbxoo* 62 14-4.

weroee to dwmlaIsflipe $T WI.

AlUtet UtiteWi 1791. eeUSUe MMt the aCeP.

atuteria IS, "1 stem Elm Isolatift elm of the UV*% de *lbw tape setsesms. Umaliw Igesew die aes" Oth ueseted elIel to doe ate=cm le aftm a Mb1 the"se ultme eamu an lInumest eultebe. Ihetelm

&w to

( set at the maslatad 300 rate h~~~e biiedoetmat r~.

stem £3.m of.oulubes "ust set at ibs imems teedwlel speefisttUs limit E. of £440 ladses 310 POMUOa INSOlsAtu by 2VA Ml MA

(

I , . 1,

. . :. :7.1 ovwav a -- evsm Wwqm-2wov . IM a 36o MM& 06tm4 5.8~h~g *lutia baus(owin~a) 54.25 3!! 1a ~m (mmU6)o *I 2" = W pussafts 3stloam X -

onoW sa ISO W l_ &Go 3m W"4 3402 on 142 am 923 3sM us Us USR 3m2

- m U.

0m Go LCD Ms J Up W 4/2 3MD usX 4w 40 U.O

= do W . *1U

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' : It £

I

;\ ¶ flW&LSIM(ARYWcR?.

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0. I I'I't,i -- I

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- - - . - e C . .. 4

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IXALI 6t*WLT tUP=T .4 3.0 knbiS (Coutiws) f ~~322 nUIb matte(Csl

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£, ! If I III FINAL. gIhamy 22m t?

3A His"~LnOot O.~

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MW

~ ~peof thi tst to to wrlty the prole qs'stm f sh hIFrossawes,*MU Weajtiom mystue sbudo ,INe of resbai Presswo =sot" a) ts~ ftos astmutas 0i18" togw w tiw 01t be leso thasas 25essoi at me gesmta r ess=*

beUGm rolep "al voted (I=01e (b) vith pop disebarv at SA Premau bet-ees UA1 lots ad U20 pig, tho fU1* dwsA beeat least SW0 am. (the Unit of 1220 poll tuelades a maially b1o wale. of 100 PoI foc Usa losses. S noes masm Valo may also be ue54. LI uveilabloo Cs) soe gC ubm taa,mu ans off d&ubg (a) ase subthi steel" emeee oft sytate gAds be sapabls of peto lUS stem leakage thed atemepiocs (b) "ae AP' euteb for dw an atom eupIy lses hi 11M Isolatiom Mri sdolt be adjusted to actuate as 225 of the madam elaws" stes*-ssss suem tim.e tre sai diodwainlg to the Coo5ussts stamp W6.

At 15 rem. so N pi$ eidos1 toasts Vessel ptesa gm m Ws tested euccestaully Vick diesbaugs pressures of 32 Po' n Mi 2 pU ig rsestimely.,

Mitk a low0 pei& soinfu Vessel Pressuwe VaK Va tested sucessfuully with iLacbavg presmues of 1IUD Paug ead Liao pots.4

m1*0 I

l 5.1t0 (o In ti*I afta at.(osia

- Id~t ms(iim.

- Au. mite atet8 aui coimI.UZSl tos n tbin Iso

~st Iswind a tbi.51 lotS~ la W pbmt 154 tbrosn t 154 . LII0aii taN_

uUea mgi""a ted t hlf I

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pyuLatftf~t" 23M" ofl ISM I 34o untb antim*Ktil av Cugi Z". In 251 co~mmue I"a t ft"a Uwe.- I-M ..Ims fl I mm- rum-,

ftmfft qmhma #Not&%

34~ua .rn wt-2m0 m0 Us MM17 2W 1734. 31n 15.

m .5 15 mon on 3400 V's.5 =1 15.2 UAO 570 do 87= 15.3 255 M2 JMm .5O 100 l UN5

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so . pu. was L To .etfll*m US -. nI us eW the -

"w Umit en de cbs gsistt- ,~*

2. To pww ""roo diaetht dos min- baoot budl dials toeeiats emaps - -- ta. bettM be" moami tonwtwodaS me mmmIl .pr - 0l V

Im vnter mu"Iwlai be Mtpahl eauld was" ise suqam IMoSata1S ts gmS upr ad .55t low wasten of gm. ""el asve itha t to of ec so bosrn hel osrn tupaqevs by doe utet diet It" shmUe~ bi as MUMMAwe be with" 50 it P 4 of we&" mewn eatweIto equ.

A Mes VW S*M to wvttp 2-- ohqwqof She baomr draft S.mstiedo toumnml lbsetam WMe Soontuo.o .

as

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1. gSealto"* M Met4 slabm VW eP"*l ..r5,. '

tabue 61 WI V

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Om2 SW P. sup1.' 3 P, re 0

WI-40 MnAL sWo B a 3.0 ~Iisi (Co am ,

IIT-3 III?_ smd M

32IS t)

Iof %butest to to

.a(ft iain Ia nosnuale us lusou131t spelfad sum 2u te t hereo i ha esdat fewlisaceo.9ts" of hofr tim Iwl dlae la etand w ulsw str

.t sn ed b u C boShal Met be ~weefl on or U the Orue ftull s~tregwd, Ij'bamIe oh4 ofi am Wresetus she l be "as

~ thv a 1 of she d leeu mtsa s .

ftosam$ aeess -*AUl -t "ay ftes ugm galuatad values SW of sbla vlow As bsraslug as te Mt-WWI of nemt If MGM " dl"A nla ms. de gI met thins ra ttt he sys Itedaslems SMet be cotstwod to U "a mhe daua Mith I to ampl ensues..

04 t Uoo S She l t nst Nd"ut derl m the direction of tim el te y l s. mdS o s e seou wale, gasn se bsiIa1 pofsitc.s. th .oppsita dietso tdo calcaulaed Taboo.

Cf

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W...O~t ~*uS I8 tt~ixd) 3.S ? Az. lysm Agm~aiam SMKS (Catir; taO &=I 2^_e""t "

shuell be t.o thei 1 e l4rws114 shoc d sVMY arretos duall be withIn thir Opevatu raw (btves the bet acdm ettemt in),

Odmit eamegii stall aine flozbe (a. tIO li r or a al &Mstm) frior tO intil mela44 eaP. hmp h d bf WA (

4ZJW11 p~ift list" belm. Tbes radIns to l Mt* be cmaei Wi readfi takes witiu a futre shstdo_ tlwt th 9ipia eUNa to Its besi* poeitim.

stem Cue sa

aa lby*amus spm 3atur Urns-s

ll PIPI In emaws WImpeste" foc testrIctiow to gmeM ' res tvaled wtua *im tIml UezASS. EIM, geattietloes mgt 068geetad Icorrected.

Ri*ts" UMAX Voltage differeatial tra"Isittar CLD'.) mr lustaltad In ike d)Well to reor thaml s of selected Piin. Dhe aVs vroid a *ostiummga (Outaide drrwdl) radout of _vnsits dm to tbsl erpamm. Tabla S1 17-1 Illustgets rsetat tve data trm these scal instrwastS.

IUl4" 3.0 ~IMIu (CMoMStm) aduas (0"sedtuei b ins ball be Is theft opemtiag wasp (betwem the b: amO 3.ld eshtIm).

~4m~ashet am mm avvstor doall be vidbia theti operting is cmem noe b et ."id sotls. toI)*

cgct ineom shall Usaft OWNbi (in. USta Usu.rQCal jgastlsm).

Prior to imittal UMml eantop. bowp adib4~

Us kwkad sw aymestor creail g I'wm Ie xege irYwell O" lislted below. Uen vesdia .tlI be camer" WIth beadims tsm dwift a ftutu shotiom to uearn twa th PIPISS rutwas to its basis peelism.

haei.eulttm Imesco van cleemp stem soe 67Spay *mmIno"

&Afttha c Wlems t Iym sedmm Urn' Caramlb.m mclpi~guto gm abotl ma iorested ic "t~ta Umeer Vol"" differential czmittuo hm (VW$*) usee lastalled 9* the 4VWUs w 'md aIne

~~t of eae461 bff?

riOeCwtsis dAl Igadout moIemupa, du to ibsius sapemam. Able taatat. M? U7s. ItIM644* tepasegtatiwe dmt Emthese speIia

I11-42 C VIRL SUWHAIY R2PCRI - SIVN 3.0 results (Costimued)

MNT 2 3.2 Ihs Si! - Initial lkate (Coattiad)

S*2.6 31 17. swstinm bwaosso" haLU1i (CoatWoed)

DrwmlP1.1 t lbeumal 1 at (Continued)

Is osais thO ftr1ll 1pipin moed i the correct direction duming hstup ad returned to Lts bow mettlag after sooldown. Ra"eer, the tecIrculatiao yteem loops both experienced lazerfereace problem and did noe met test criteria. Soveral drywall ntries won required to locat and rn theae pmoblm and asoetala. free anid unrest ratoed inwant capacity. Iv.. after rnvLa all visible ter-feareces, both recirculation loop experienced tbhewl expanaio not mettng the level II critesriO. After scer-talisa tde *ystem to be fre'. _ad uestvtaed, the LVDT i _asurts were sent to O.. system designe for analysis of the dta for the possibility of odens etresees on th systems. ?heir responee ma positive and the 67stem were declared "operables 2hose Lterferemees aIong vith those found on other system and the corretive actions taken are described to table STI 17-2.

Oustig the fiat tw heatq-coodowm cycles, all major iquwll piping bagesU sad hydraulic shock said sway arve tnto Vstually Iaspected W*e fami to return to their cold settings, dicatbi a* dnfoation of the major dry-well piping system. lor a sary of the hanger and hydrau-lie shock sad any arwestor deflectios dta got the f£rst two heatup cygles, am tables 5? 17-3 and ST1 17-4. 1rywl emery inspections during beatup Indicated the selected bangers ad hydroull shock ad away arrestors vere vithit their operatiag rangas. See table sU 1I-5 so table SE 176 fot a sp of thi data. Alt levels I tt Ct citeria were satisfactorily Mt With regard to hange end hydraullc bock and mey arrestor readings.

Onamll Inspection at Various btecire Teens.

uing the first beatup, several drpll inspec-tions VWre unde (i.e., bient, W P., r*ed coolant temratube) to perform the follownSg

1. visually ispect selected has and hydraulic shock and sy arrestots to verify expected performance.

C

1II-"

fINA §HMi LIM -* $M VINK? I s.0 blsa (CMuUM")

3.2m8n aw"4mtm sU-Kita M omf rm-tia,-w. otd 3.S S1"?Iwt 2.visully weui theIwem amq'au eoastgalaft of

3. Isuu $doted %ow pealiims.

4. laseid seletetd hydimU*be f ma M argtaro poitime.

meo diag 4ea to vuf S. RImpact Ouh MD 4laplit It la fmastlam"u pawely.

tuft.

G. IN we the sp ulasts, I 12 a "Iaclemts has

1. eek the flozdble couht cameastUs to th e ut a lae to assure that "ysun beat mi ezpmis1thebagfeil Say Ilmar asr per~peadladarcma. as camlata.

reamlawg Wiamyr IPaM awlmU. to cold dout-adthe cold asulass reOrde dam doMrsUweinttte mm anewn Step" 14 W.uretpeated.

I

III-"

5VIML SO<MNA 5RMi - _B1W MIT 2

( 3.0 Iunto (Cntmw) 3.2 ZIM Ut *- itist REctM (C.ttam4)

3.2.6 cm A. ff_.t bmleft (Wosumumi)

S

_b 1._a t-,

itoxed Calaolatad HSeauta Aboolat 1_sIAtzlom a ndf " Ot acire x -0.012 0.09 .05 i" - -ltU -1.14) -%Am 0.309 1P.? it" t-

,__, _ dim.

(154) 2 -0.92 -0.383 0.545 n.plasmat t- ____ ___ isc us slo See16 D.X 1Sl lo p St5 x . IO ..... U.~ ....... .9 1 .... L.. S 20e+ Discus to20.

e(322 )

Nain I2 - +2.520 40.59? 4017WY_

109

-. .- o Y.0.2l_ *1 =

A4 (23) a 41.074 - anDo Rte_ __ _-. .

" (71) * +1.161 4t.1 0.001 S.

man I 41.51 "T_4 c stee I .

VO (34) & O 4.5

-. 0.M 35i Vodvsto I 41.20 M m01 C M) 13S se We _.-_tog Z 40.95 40.321 0.221 4XA V.

(#41)

Ve.dmat 1 40.712 40.459 0.269 37.0 S"tm

_ I stun AM6 z 2 -0.2t9 --0.24U 0.031 Il.1 M 32CP r

'U-.s ItIAL MMNAR MM~* anP MIT 2 3.2 Pame III -sital Mastto (Camtimmd) 3.2.S M?IL, usim (Cossmasi)

~tfIvuzm table 1? 11-2 launteuemgsd. Cosectte Attie" latrsufsm Cervective Action lWuI Steam ue lmiSteom Lins,

.ClIt" bad Inmulatione mo alt 1. Air duct modified duct iscerf~yece Oa Walet Volvo

2. V' Urne kWd iSuoatiou VWd relief 2. Iaoulattis modified

'"h~ line WAd itaslattou and lalt Moified lasulatiom,

1. Reactow Weate Cleam" eyeu I. Catleg*modified bad 40sulaties, arnd grating intterference

2. Tervey colm bad mecksiel" shock 2. lovesi amw mchanical shock Oi ressora locke e susetenmrs- 192talm.

hcirculatioe wes Rocinultption Bygtf A. General A. 0awm

1. Seosmie cables arouad the 1. Lenphened cable,

2. IeaalagSoe amd spece beariag 2. Modified spacer bearing plate plate* tmider both eganetc S. 'A'0 Line S. "O Use I. Valve on bypass line got dis- 1. S24IfIM immaUtioz Charge Volve kaW gots fore betwum Insulat ion ad catwalk

2. Bottom seiseic ring on dLs- 2. amboved choker C. '0 Uine C. 03" Uine

1. Discharge valve had interfer- 1. Modified catwalk ence between Imaulatima and Catwalk__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

M131 I

6 5.@.

H1,'

FINL halsaE.m t -31 MMr

,i I

i f.

. K a I .: .1 ml-3.3 snsm-tat Et Ualm(s m~ .. . w.: .

. * . - : i . .

a Ua Atto

~ uq ma tsom 2.'S$7Io& -dpmovss. m LmUMod= hak upe UAWadd" ileI~ sU ~c UTIi m

1.

0 4.

1 A

r 0o

11-47 gmWA £=UY ?3 aUt?

3.0 bIalft ms 3/4' 2.2 SM- dom1

ttlalgay(@mlud otawl '

9.. : ( ... mt - -n. .e nis sn 1*7.

IRWTS eysa I cyou I ~4"~

w119w174 wiwkf 10113JO174 -$letts Ssela.wOW W 21314 33112 3 2114 l ln. p Ws 2a 3 24 ds stem we 34 1 a2W 1 /4 1314 we ftm or Ul 1 314 31/

12/4 13/4 gas Stem *42 1- I 71 7/S mumn stem n 54 1'1/2 7/5 V*V./5 /PA 1 us 1515.

V. W.MrF S IU4 I lUs ISIS vur 541 15 11 1/ 16..

us2 3 L S. s" m2 I U5 1/ t 12.'

,. S. Ws I Us 31 S l' 34t.2 131 I IW I214A CID S 3 .

"at& Not tae

2It14 113*1 LUART -?3P - SIl OMI 2 s.t a... (ma*tufS. Uaum(bli i m.M It Bienm bOufitn(Omem TiAU M111-4 ust cow &wiin Ciseu 1 CYst, a ~

"uzmU 8119/14 1011W14 setpohint

~ a I IJ114 2~l 25/Sa 2314 l IIllS.

ssAA.e so a U/IS a 3/0 314 a W1/1 leers 13 h~ SS25US 3 2518 4 314 45$16 4 5/4 4 314 o

H.$ O 3 3 US 3 3 IL, n CI 3 14 S3314 3314. 33/14 331M 31/2 sill 3 112 321/8 o

W.V S 31/2 311 S 31/2 Fe. 33 31423 3 V14 314 33/4334 M s.84 a

&at 4 4 1/ 4 4 Co.i.A 3/4 3 314 233/4 3 3/4 Cxa3 2 a1/2 23$14 a C=

45 S 51/4 I 3C a av1s a S/$ t 7is at WaIG IuhIus. SAW as 2 21us1 us1 :2 halzs.3 or

1t349 MIAL LHAff gm? DM? En? 2 3** nMIt (CMttM")

3.2 Pam -U *- attias1 a. (OuLO)

.2. S1 Tm Mtm)

Dual1bUty m r VAta mq ltd COlU CMu at f'by wte

_ tpIft ate NU Data Setpolut

' 5-3 a314 2 114 41s 7U114 7 4 "cite. m 5-3 2 U4 2114 4/U 6 2 7 314 Katals ce'AP W2 13/4 15/ I us 1us 1 3/8 ntomS or WM I 7/ I34 13/4 1112 I1/s Mihoe8tam%1 C-4-2 718 1 118 3/8 318 Nolasum W.4 U/ 1 314 318 318 Ve. zez'A 35 t15/ 15/ iii 3/4 9,1 Fee"w OA- FS z I 51 I UsIUs V4 WIG

ed"ter*-*11 or 1 518 I 5/3 1114 38 9116' mm Uatuu 00 34-2 IIIU S1 314 W1 WIG an etrn* 3I-lb us2 III us 3/4 3/4 NM stem ly 346-2

3114 2 U4 2314 CIC Itei upply -S

2 I2 2 4 +

Care spray 3o11it 11S I U 1 I/8 W/1 GOre spray o 3-S 1 I8 34 3/ 13116 Cleih Ws 1t314 1 34 1112 1s1I 1 1u CRD .

S 4I1I 2 11

+IspossIbla to read during bat operatios

llo hot and/or cold Wetpots visible an scale

T13-50 MURA Emtm 1m* Wm=I?

3.0 IMC (Coatns4) 5.2 Vi ! af astmbb (CmStUmoi) 3.2.0 IiU ie ine (.antind)

Tbub In 1146 srpat btr~4bck me m nuwt on& snow syse. tgers. obd tow 3w F. SW0 to Doha setpoat W amst.AW) 211/1 2 1sun 21/ 2 2a 1agStru."'*AM 213/ 6 a313 1 3 3 14 31 ft lg. )5 211/ll31a /16 sill 21/4 253 3s.ir.3 or 2 3 a3314 3 41 4 314 43 c IL8* S 251 2510 3 gm3 4 3/4 4 W4 4 314 3 12 a33 sLUG)ft 3 3 31us 43/4 41 IL. ~"r ml a5/ 25/u 4 4 3/4 41 F..APg 3112 31us 37its 3 4 you o 3 31/3 31its 4 4114 4 iLS.L* 7 3 314 3 W4 31314 4 3!

CA.Ia 1123 33/4 4 41us 4 3/4 CS. a 308 3 3/4 33/4 33/4 4 C UD 34 2 2 2114 2 /2 3 egm 34- S 5 5 ftga lbt TOMs

a , 111-51 m mN& ~ .au=uut=It I S20 39 m e I l ai l l h a a m&~i

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3oL I ftemlow f

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nit*3n 3 LI Mdf&i I!?* ft*1bamC~tdn

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p no=, on 17-3 1wamm UN* A

M-s4 om ommSUHE I I Wsun"*

6 3.6 IMU(o~m

3. 2 n a. . I

a h a - t . ( g i i

3. 52 M I~ . -m -t ~ ( 1 5'

lawnt ml 17-4 Iowduwe Mmsa

m-55 mumy iSA Lj tNT?

lEG mum (cotbole) 2.2,0ai &Towl~~a um(sa.gj

. . . . I r 46 , - .

I uw owmi *0 -

flpr 11 17 w1s8m,Ml~a I

e ?4L ALUSURY 3aE?* W I?

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C 22 Seti* h jmnle(Amj mi.

SL wibmi(5) I

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fImI swA3 ma UW g7 I 6

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msn uSo mm - . gm a 5.0 Blau tlns 3A 3dtis\

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Ml4 uua vim. HE ut gm 3.0*2~ 5s SOL-$i .111~fu btIisI 9

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Lilt~no ul V*-SutS am Bigs SWIU I

(

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i&SOknm a~~

IM 34Ibm.. w--3.10* ba URZ.JniEmus (cumalos e

a fv"p on 31.15 an bgg1y "d utun

. I . .

mu" S

vmi.amm ML-IL t I U' em .

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r now m 4n-2 r

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me0 irni. MOW Moff-o ar wit 5.0 ma1u (ac1on

S a "Mime v9

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9 e I

non on 17.

maw%",

S.2 lbaft JLn *_ xitatIa JUM (castimso) 3.L9 m., UsaIo tsai ALu tu pIsusoof this cost we tat (a) tmateosllyforYForm~

GM& tas mus steftua, 140149400, waives senatiftat So me'd psur levels (b) 4elrn reatgM tal"bYml dwmad s6110inmsue i ml ~to etaim 1Imastum Volvo .0g the.

Rimmt, be wsatu aim S a" tea thus Cieeug S one. Seastor yessau dull be saimalsod below 1220 psig (the asporttato the nage m&isty Volv) &MI the Irmas Deal 9eiledag elawmu of SU valves.

soe ums tomor rmlse *Ml be 119 poseg 4 pat balmw de firt, safety valve ntpdat falowift slow=r of au1 valvs this 9. a must& of safttyvolves. for safet" valve mpF". balm fII slonsts of i~taftl I e iset be 909.1 bsluw Sweem mumtn fim -a be IMl beloW ean6 ad GteOM 1lM La IOUVWMI Uie mat be belsw she tzp Piat.

~iie sthat eI ofV'6305 testMas $*"4 SO eSa a am~Ems$. So1 25.1 imfieabee =1esgmat W teast of the Is11s dwif the Llhald bostop lgha. ou% of mhe volves, eatafstswily Met the beSWUetMU Go swids by the duea ia tabu sn1 wt-.

.'Ct*)

Ku.'?

IDIA! VBAT - us an 3.0 mlalat (Cointtu..)

a 3.2 ~a 1;L ta ill MM!.C~e S.LS9 m..Ii k lut laYl as ~.

MILM n -taffial IKA TAMAI uhat 1013 0 31 (5-2 "as)

NO 1531 e Ism (6.1OM 10 151 Sam (5.1, a ,,)

101.31In 9GW n ism Good

.37ctm

W14 10 1537 b 1'SS 1GW Vmt (2A4 am ,)

KGW 1527 ke1.21 1GW N 3

12f"?

£11 cz.m ttms o..a U-"

10+144 (IA)

N10+15 (24 .44.

ft061-M £13 4.4

.1C141*v (2S 4.1 WCV.l.) (to 4.14 104.136(6 4I2 10441 (1) 4 49 10+53 (8)

'p 4

0

Itt*"

3.0 MAINM (CzOSl_)

3.2 Uft italu 5.2.10 ,,136 batY6

&LB Wst dm to to why tWmt all ea" uvie ae gnaw ".M tha thy - ftlaa af t WIa aIir m he

'te Up v. s thC. 't

,1a 2usz .a. ea beathe wahemnupe Spend. i.

01~s glh l &She wae geturme gmwti 0*1 56.

AU as em Mtom C"lla- "a ml.604ono VOM "A 804 M.s. m. ValM tw h a m.1 t .Is to .at eawae dbo £i hed _ -;- t.* h waiv 8UStlaS .

~ ~S .W.A Ea"bb mtd i'*_ .xJ uen a te * ;m shei mlUNw* OM ." we 1* ha 4.5 a g bSa Vg it,Ml3al -

~.'-1

tZ'-69 MTAL momv Wa *E NM~wtI Ism.

no l w of tdo m toa (t t dsintrate dbe ofs. sedmoaa .Wa1l~tu of tbib espnul. u wCm Issasus mm sum ssm a ta

... eseUGma

q. wamt laida.aie mt st.

abls eo she 1 mc (b) Do raw~ man (0)o Of ma ansh to. doass (

emUV* Is iWd (aU1 tbe( it*" ausstim Au Rebi rs do rpmesng to~pe the

--i u #so m~andi st. %s.

sa" o.Is 5h El"10 d w ib./he.aheat mM i vas lstow.~ pu ofh.4ai3UP S-A. wA . xW1jb lbs...~teat Wm cmIs (a s Owwe1' w4s to she mawao vlVt

'Alab an.Sumpin flow mam "etan" of 043 u.lmivo *. boa.

bims. Urn. Vick sI1. oleau flaw uMIM Saoe of a 103 Iguwh. mms *sam /1k.

£~zsswa ith tb. dasiv f1.wsm of 0.4ka

-13 aw1ba/k.

III-"

L3.0 WI (Cestid) 3.2 f It

meal Et(GOMLm)

3ILU 311.1. UMetow' Vatot di (Ctmisvd) go thiN test MW 1l the %lohiWmso" in 26U8b au2 sRq Elm vsdidu sto radts gr she

_i. With aelaq guy ge .of.0a100b. ihi..

a Nst "mml UN of R. 310' usibs. W aind o demo a1 dpad 0.053 x jO6

Ib~ht. _ 22.S *1h J.

asn tGewgaw value mor tap t toee"e.

two la so la blow the dlas,

_Iesm the place" dia.

ga weis .of SW F. an andla the easlzifs of a L 'aa t 'e cmszvatiue es . ?*.1019 V, OS OM a (1094003) lb./Isa 1 M.26 fth a 50 ft. *Usu . s n? ft*.

buu all these testas ate lamop "It*ei 'alet

-a e ba helm ad UP IV. do an me detald.

b Sb S 4 tad doles8sSOuzt t1e of ft

-0slyft Iowa a t *ps e s it ta ata s b__t eate b tlom mt tw. ad pressav.. It VWe gM that the etvsbs auhiMf saeqtt we 29.1Ia i# stows. *1*1M of 1.3UVlb.jbz.

12s x b a - et of AU wae). simm 4ws to Cho isese 44aPs Talmosu me s stisfactmt with the wresl and bladmu test Voss bhet - 1 _

3.0 DmAsa (ama1ina):1 3.2 ~I f aia .u ba 3.LU M..~eae li O~ii hb~aVWX?

b1 AU Ibm mssi Im.o p

In -n n m~j SWMSARY Utm - AMII 13? 2 c 5.0 3j ts (c mt mei)

. III a mIk

at a t s (a0i un gaqeso a Ws toot 1ast dommtrato tke akluy of the ,aWifa hbut rwmam amP yspm tot (a) gmmin x*1&" mg dewa hea tm tdo malw~systm that fuusUg ad mwiae eyats muod"" can be PUe ta~ ~ (b) hea gas de smia wuce peeI va ne.

e S cqwup of sub an ha"

-thdlai m"c the wouff )s I_ 1a' be 1*.? if W kuhu_ M .0 941A. e) fros glfssui &tnp" Wm Oak to domsutrats the coesI" et Os hea "*hG bw U"Q the lhetdo Oman IBois hi 4 .to PPM M saiElaefas dets to e ~~ t a h uq slty *I he Meat ama~a~

swinegza do to co.eld =ae Unist of IW9 1F.I w..

usSkIt f* f lto b e aO ea Io to s 1 s M m t o£ the th heaet~~ m' eap u lt i~e {eu e . ,* . a ea u . t a 1 I0sl ot l U t1 AU nt a" ~~~ U ~ ot.

orn E t fl_4- S

~lN l1 a 15 ? 10? N u/hz.

C 218 18? Kku s.

293.5 ~~18 ? . u7z 0 MM

1tt-13 VIML Sa Y~ - UIw ~i 3.0 ka (Q1inud) 3.2 Thai. IK*tita el (*w1i) 3.IS t :

s me of ste tat to t verity the dUt,.

of de 6ydmU _sinqhm emsas ouym to mlstala i nodo emsi is the *1ju diq eeatis emftless; C() so we e of the dell menre ABUl be afor~ile pSI a to UNIhu (b) heM 1ml o 1a be 4 staft.

wipslity of XM .I the deag beat mum) capbIltty.

C.) so eigwI (e}

dlqqsnall) isuft mnatals d" 1

sa daft Ms s -at SW I. 0? C.) aepi tbzwm$ *Pwlu so WC.) 7- ~d~ e~ I4 ~ O690ttU~ ~

OX J.IG ~A ~ :,

2 V. (DA C*) uui eu the censmaS _.g :.

IMUS. 5.IP W0.) ofuS . d al M -'

- V.-S_ _ te bs,:-

tw t a l awbeea . the vemeeguwo b ul, -

I

Int-.

1RWAL £ThHAR? ?

11W Wi? I 6 a A 26 e i21bmh

. ..,.'A 1.1.-

. br.,

A=

3.a C.)~te d~fsit l maw"u at 1111ch do "a sP V. psstse"Iu oat beusla" INIMtaSa mlah p"w m u90 & ptOIUW4 wae raerne deu'tm hsuebptae tam all am Um WU* Blase no a e jeauma theme int tol Getwat thug test IftIeL

.(j she I gwf.

so I -el ofthis "at to t sedtbe "am ise vealelUilisdae allion of elelIalimerSwais.

eel u"e of 5)1. - Stw/hi. to ade to SniM 5splumma.

l"wntevastue to 1W .ma *wt i swulng) Wu" Islet twomewo? of SP V.

0

£sua1* as de on turdo (4bst ~f1L.e li. aft 0

~she ted a"' too soms tm w Itoo the 3do walsMmnIs gmes us.

. vs.1 amn muto Guiam" the PyWe Of tas t"Sle.

mwl S MaW !!Mflp IC5 !MW am PhmtY-mibe) 3605jf I 3.3. au,4 Befel ml ugge zM

~Sa,~1 bjueftlue, of tuge utm met

.s is -eve faftom - sh ebuatly ml 3.L lmGUevdinI tan t the i to WOWe us~m ml emft* 0 ite im go dt t.iM 3 te t

-ds 1t" myt mgo" the .mIU *.sa oleo

3. SewS 11 13Ge45 of the "a pogtram ""fts O~mu .t t..S prwfterim. sueluesb of duelasrUse

,I -

quas...by alusa lulisme usISb ML vasreMa of

~egsa" h at ps iftof m*fom ptsuetui eraSWin 0 cailffaa 9lbee atlas of .ah~

M uhewst to Osenal o

pem tasVUsU4.o

. e I ej". um "

fgt" L

'*1.

thes 4vpsss w "Is "S" "tawlt" "DU awosmsa Il~sbdoted mamumace of apawls anude, ad (a) bmdea (atets data" i to e taseteu epeeuadet"saw s be miaiaOae vith S.he lIASO O"Oft~eE.

I-I (b) rte* esswY of somems ad 1414 eiflants am adb"to. Una" uldtatlaee. 1 1

. I lb&a qWeUty uest to &mm ad *eel toiad ': , m ulISMA the gPideause of CI water qwSuty su'upe"CIeMe.

O

ntv-fLXA!. UW3AST Rt? 15' 1ff

-2W-M c.-q 3.3 pe" ... IV bmmTht Castau4 Tabl 11 1.1 1tmwee ebe neaua of tha ebodua M radi~sbileal s. possf- ui n u s~ta~haltim.

toble 8?! 141 l - .- -

Ida"Ar Waggg a Ra 5 PPamir. 155 1 1026' cmedetStyy oiea ISO 5.5 0.20 0.23 l .fo-Ilu, ClA 1.4R-0 1.1 146' 1251-06M .5S3 0-ft odinae-Ill3, CAI II.@- 20S V- 3.006' a- 4.9 3.0 Gross *At~vtty

~- - -w

-fIttrate. c",ai. 2 b"Z. 9.61.*03 1.93340 1.43 3*0 2.14 ON

- w.n. epali -aa k . 4.26*@3 7 .4303 S.4" IM0 1.54 SM0 Cross ActIvite

-tiltvago, CMu/ad, lii 4.5 3Not 1.951*02 2.4302 M 3.4l 3 crud, cpu/i re. 14 3.0 3105 so? a1 2. 1 101 _ZS 10.,

Sili S.C m 4.060M 1.240 3.42 10 3.31 .402 borai, ppb SOP . 1.15104 I4M0 6.I PM A0 M0

IY3 US mWA1? iVOt - VW WI? 2 c

3.0 , t (OM u-mm) suI...)M

.1 CCI'm-laSl I e sm m -' a_ Y1 -

2 S btfstw yaw (owMo2) nman r_

-_ _ _3.

102Ze43*

_U be i xU ita i

t n . =sl .m = =

OmeatSal 0 -ta 5.U o2rU"7.0 U(0.0 3.9 SpctalA ftaf 0.a27

_ . = = U

-d= =w <.

-~

U AX Z 1.?

md as t Imuijee_ :-

Spea)

_ P. . _

_W5 _

- - -n.. r_-

ameldee z24 fs-V eu- e dla 1e4 4l 0 3a 4itS 0 , he t.58

MA-FilAL EM RD_ - )- VW SOT 2 3.0 !6MIL (Cnsluins)

Tal En 1-s (

XI'-r 40402 .632 95100 "mol mme 1 e .+/-ILL 9llf1 JJLZ2LZL jiZll/

t 206 5" 55 la"

.3 t-1 crb51 cr41 4 e-5S lb.54

_- .i23 40 0-8 4 cVW 9-3-is ii-n ub4S60 l3-18 a,15 OD-"

Or,15a*- (~0 Za-65 r?

Um95 _ffiA476 Zro~b-9 2t.w-9 Zr.Ubr.9?

Zr.1b Ib-b -1S? AV-7S 1t59 V.'124 coad"Mate 1N. tafimt aort. I "3W. 4.0. .. i Insoluble Im,. PO- ~ 6 3Za&L. !.!.L.-.-

Condensate Dl. I ffrn-

.X ConduettvItv. bam43 .iz1 0.L1 0.L...P 006 -0.0 Iolu tn , 1.6 _ U 3.1.L

-ab l L Cmwwetditu. Maee 0.1* 0O J09. alga Ifon taae1b1e. 2.0! 6.01 1,2t

- Solule. 3* x 0.5) .E.!L.

lucel-JMmmS x -p

- olule, P . 049 IX Symbol signifes data sot required by the test instructIms

a FINAL £-O(ART 31 1 a mlKUNIT ?a S0 hiatt. (Cwtiould) 2.3 MM LF *- mw T"ts (CatZaiud)

Tau 1-1 (cstum

_mw Pt PWT 1 -. bare. -a am Date 221714j 12j191Z 1_tr (Cantiwmd) 10. 9 55 12 r -2 0.01 k -- - ae ActivIty

5.1* , VCtRaine. 9.3 44 44 47.4 415.4 pas6s) ,_

a13 LIAs R. _l .1. . 2 . m2 Flw tat*,Z "

LF2-4 0 _f 1_ _

amltago - a1f. Cfa ~ J 12 L ~ 1JL la's2.4 Aetl rt leas A tre 1a 3.2.

Atvftity term at stu b .Ma. i

-191)" st} ,.

at _t - . _a@t 0§ _ , H ^

Of f-Ca Ualter A . ., . h 1.

Iadi1g. MAT Stack A" M_ .0 2e

- aling, cap 20 - so Cl) Ccmbaw activity fi.. wits 1 sa 2.

Z sybaol eipiffe data sat reind by the teat iagrwtd"a.

- M

IV-6 3.0 Rsults (Continued)

3. Phave TV Power ?entinm(Continued) 3.3.1 SU_-l. Chemical and Padiochemical (Continued)

Analyasi Reactor wter Reactor water conduetivity was within the 10 usholca at 25 C.o technical specification maxinm limit, throughout thu startup. The conductivity exceeded the opaertlonal technical specification liSit of 2.0 umho/ca

25 C. for 6 houra from 10,3174 until 10/4174 because of aodium injection at 602 powers.

hRector water chloride concentration was within the I ppm technical specification maxlmum limit throughout the startup. The chloride concentration was within th-operational technical specification limit of 0.2 ppx throughout the startup.

Yuel Cladding TntearitZ Tables BTI 1-2 and .3 show representative off-gas and iodine dte'obtained during the startup. ine*

the off-gas release was low and no evidence of spikina was evident during startup, a great deal of effort wa tot expended in determining fission gas release distributions.

tI

- MOMMINSIN

I.

3.0 Reainto (Ccmtitnnd) 3.3 h~.1 M !!idealaSRfehwel (Continved)

Table STX 1-2 1114/74 OM 0445 68.2 82 5.7 1.4 1.3 0.8 98- - 84 24 1214 1230 2094 100 47.0 21L4 4.7 1.2 2.7 0.9 78- 24.6 80 23 1L118174 0719 960 10 89*6 20.9 5.5 1.6 1.2 1.1 =22M s&8 62 42 13.25f74 0800 2325 14.7 105 16.3 4.6 1.3 2.0 0.9 40 - iA 76 28 :1 1212n7 0708 99 100 53.9 24.9 5.4 1.4 1.0 . 0.8 77 - 22.9 80 23 12f9/74 0730 389 10 12.9 15.6 3.0 1.2 1.4 0.8 35- 147 80 6 12116/74 1055 3110 153 75.8 17.6 7.0 2.0 4.0 1.3 108 - 52 41 122374 0706 19 105 74.8 13.1 5.0 1.6 2.4 0.9 100- 4.5 76 32 1213074 0716 71 10 44.5 23.3 2.4 1.8 4.4 1.1 7 22.2 50 30 116175 0M813267130 44.9 1A9 5.9 1.6 1.9 1.4 75 62 44 I13173 0706 Z189 140 51.7 18.2 5.6 1.8 2.4 1.3 a1- - 57 59 1115/75 0922 2783 135 74.6 2L3 6.3 1.7 2.5 1.0 107 16.7 60 73 117/7n 0843 0 100 3.6 7.8 3.1 0.7 0.6 1.0 29- - o 19 12/75 1701 0 65 5.5 6.5 2.1 0.7 0.4 0.5 16- 23 4 l124t73_ 0705 575 25 33.5 27.6 10.3 3.0 1.9 1.7 78 - - 29 65 2127175 070 2219 I"O 65.7 17.2 5.9 1.7 3.1 1.0 9 - - 61 34 l129175 0724 2433 210 26.8 10.9 5.4 1.7 1.5 1.1 47 - - 73 15

!i II

~2)

IM1 s W se

..; - . . . . - - $;. A"'.

. - , , " .- C

-t- ; , .. - - -

I . '.. , - , i - :, ,;:, -,, . , .:L-, '. , ,

. .. '.I. . . .. . :I..:....,

- - , ... ; I r:.- , , ."1. , .:,, .

VMM-M.MMWRTr=PR - UP?" rMW 2 3.0.!!MaemUISd Table STl 1-3 Zroums Fwx 2 Reactor Vater I~

+ UMd mm. PetloW UAM. v8 201JX7i W0 198D 0.X2 Q.6Q3 0.3n i-7 2.3, 10r4n 2230 1980 3non) __ .-

mu 1- Wam 0.1 o.M S o. J.e o. 3 i.o.2 arJIm tw 0 0.0140 1.70 0% .4, 002 2272974 X500 3267 0.2(2) - _ - .

,121, 240 2742 - 0.0702 3.38 L.l 1'9. - -- 3.97 213M 0615 2854 0.051 2.30 0.743 32.3-3 .'5s (1) Pr02-Pmr - No cleanup -test (2) 002 wm?-~s o tl m te at POWi

- OWN,

Iv-9 FINAL SUMMOARY MPOR! - BTHP U~NI I I 3.0 Resulti (Continued) 3 3 Phase IV - Power Testinst (Continued) 3.3.1 aU-1. Chemdial and Radiachemicat (Continued)

Analysis (Continued)

Condensate The cond nsate pump discharge and condenuata deminexalizser offluent conductivities wers only slightly high during the initial heatup and startup conditions, however.

they were within established limits throughout the remainder of startup testing. The following table, STI 1-4, sbQws the plant conductivity listory during the startup testing.

Table STI 1-4 browns Ferry 2 Startup Conductivitiss Cumholcu)

Condensate Condensate Derineralizer (t Date Fover (Thermal) pump Discharge Combined Eff luent Reactor Water 7114 - 7119/74 02, No Neat 0.74(l) 0.12 0.28 815 - 819/74 12, Ueatup 0.15 0.07 0.13 - 1.40(3) 911 - 9/2174 15 - 352 0.26 0O1 0.90 2104 -1015/74 50 0,10 0.06 0.3 - 2.6(2) 9130 - 9131174 40 - 602 0.12 0.08 0.50 11/22 -11/23/74 701 0.084 0.065 A.G0 12/18 -12/19/74 %93X 0.06 0.058 0.23 12/28--12/29/74 49sX '0.606 %0.08 0.15 - 1.(2)

(1) No vacuum on condenser (2) No cleanup test (3) Range of RI R2 0 conductivity during August 1974 SaMpLng 6ystem Prior to startup, a root valve verification program was conducted to ensure that the origin and approuimts length of sampling lines was known.

C-

zy-10 VIM SUKMY RIPOR? - BI MIT 2 3.0 Results (Continued) 3.3 Phase n - Power Testing (Continued) 3.3.1 ST-1i Chemical and Radiochemical (Continued)

Jnalbmi (Continuad)

Radwaste Both the liquid and solid radwaste systems performed satisfactorily during the startup period even though inputs to the liquid system exceeded design values.

Condensate end Cleannu, Demineraliuirs The condensate demineralisera were Initially placed into service in late 1973 and were subsequently used to clean wator during construction and prooperational testing.

Both the condensate and cleanup deminaralizers parformed satisfactorily during the startup period.

3.3.2 STI-S, Control Rod Drive System Purpose The purposes of the Control Rod Drive Systen test are:

(a) to demonstrate that the control rod drive CCRD) system operates properly over the full range of primary Coolant temperatures end pressures from anhLent to operating, and particularly that thermal expansion of core components does not bind or significantly slov control rod movements: and tb) to determina the initial operating characteristics of the entire CRD system.

Criteria (a) Rech drive speed in either direction (Insert or vithdrav) must be 3.0 + 0.6 in. par see., indicated by a v full 12-ft. stroke in TO to 60 ses.,

(b) The average scram Insertion tiN of all operable control rods, based on the deenergination of the scran pilot valve solenoids as time sero, hall he no greater thean

- M

Iv-U

& VIfIA SUM0Q1 REPORT - UfrAP UN~IT 2 3.0 Results (Continued) i..

3.3 ise IV-Pow Dr Testint (Continued) 3.3.2 STI-5 Control Rod Drive systen (Cbntfnue4)

Criteria (Cout146ed)

.%, 1*

&W a Cont~lnturd) 2 Inse.ted from Average Sirax Insertion .,

Pully Withdrawn Times (Sec.)

5 0.37S 20 0.90

- 50 2.0 90 S.O (c) The average of the scram Insertion times for the three fastest control rods of all groups of four control rods in a tvo-by-two array shell be no greater than 2 Inserted from Average Scram Insertion Fully Withdrawn Thims (see.)

CI S 0.398 20 0.954 so 2.120 90 5.3 (d) The maximm acrae insertion time for 902 Insertion of any operable control rod shall not exceed 7.00 seconds.

Level 2 (a) With respect to the control rod drive friction tests, If the differential pressure variation exceeds 15 ps14 for a continuous drive-lan a uettling test must br performed, in which case the differential sattling pressure should not be lose than 30 psid nor should It vary by more than 10 pold over a full strkae. Iever differential pressures in the settling tasts are Indicative of xcessIve ftiction.

(b) Scram times ith normal accumul=tor chart should fall within prescribed ti. limits.

(Y f

let PhaseI Pvv Tat~f Cdn))'

S.)?B~t'5.Coiitroi Uo&DrIFM. System 1toi~

~~IZ~L1..

L ... .:2 WS1m 'URc~~iAWtOR~kt OA t. SAM cauO4~btJ tX~R. O J tiwb~tuIatLQ I1And.. 8*4 x fl

0-FINL SMMW MCI= - NVU IM!T 2 3.0 'Result (CoatIrzued) 3.3 "hos IV - ftm ifa dwen) 3.3.2 _M-5 Cmtrg~o Rod 'Drie &gtM (Cmttaced)

Table CMT 5-8 4O~tirol red Scram Data oact s Reactor pop steactem.

(:erm -Rated) ) 52 2_ 02 - 02 lI 1002 980 30-27 0.302 0.663 1.400 2.435 Turblue T!4p T a

&M stop 10-23 0.300 0.66 1.498 2.58 valve clasure 34-07 0.322 0.692 1.552 2.676 46--U; 0.300 0.679 1.488 2.556 2f1V5 =w2 1002 1000 10-23 a.294 *.66 1.51 2.63 i i, *, 34-07 .300 .0676 .1.51 2."

02=u 46-11 -0.303 0.68 1.51 2.6 42 0.302 0.46 1.50 2.57

.... . .2 .. . -

.. .. :, ,.-.. ~.. .. ,

IV-14 TNL SDMMAUR REPORT - 3FP MIT 2 3.0 hsulto (Continued) q 3.3 Phase TV - Povar Tostin (Coatinued) .. I. '

- r- -.i 3.3.3 STE-10, 1R4 Parforvance !Y 1......

7 " .

PuPose The purpose of this test In to adjust the Inter- -

- I mediate rage monitor system to obtain an optimm overlap with the RS end APMR systes.

Criteria (a) Each WI channel must be adjusted so that overlap with the SRP's and APRN's Is assured.

(b) The 110's must produce a scran at 1201125 of full, Scale.

(c) The MI reading 120/125 of full scale on range 10 will be mat equal to or leso than 302 of rated power.

(

Analysis The IRH's were adjusted such that e, rea4Sng of 1201125.

on range 10 was equal to or less than 301 power. The APRKl.

had been calibrated using a powr range heat balanc. The results are sumiated In tubli STI 104.

Table STi 10-1 A Ti-1 Avg 16.0 1_____ 16,.0 16.0 16.0 16.0 16.0 16.0

-_ - _ A r..- - . r - E, *. i.

IRH JB 10 _ - 1:_; t IeAdInR 102 103 113 86 92 -hOP11a H0O-REnE 10 10 10 la 10 to 10 0 OAP .74 .?7? .708 .930 :.870 .667 .. :

Reading go, a 78.6

C' PnlIL GUMMY uRRPOtr - SFtOP unT 2 3.0 Results (Continued)

.34 PaeI t = Pmm Ta = tf Contiznwd) 3.3.1 BSI-0m. I Performance (Coatinuod)

Anafyd (Continusd)

WIl. would;.unt drive and ZI I- ahd a suspected.

law gain. Theme IRl's were repaired and *uccessfully calibrated In accordance with STI 10. at 19.57 power. The BPRH/l overlap was verified on a subaequent startup. The results are *uumarized In table STI 10-2. The scram sot-points are checked every three months by normal plant surveillance test, All tout- crLterLi were met.

I IAble STI 104 --. - --

- M/S 1 OFerinl.r - -

IEM Channel A B C D I 1 C UH Readin 75 10 75 _23 75 4 10 75

0. Position 2 1 2 1_1 I S 2 sRH Channel ,,,, I C , 0 Rueading 3.5x 10x 2.3s 104 2.0 x 1O4 4.0 x 106

, Nadinq* 6.0 -15. lo! O

1511 P data takeu separately

(

p

MENAL SOWY REPOX - IN? UNIT 2 3.0 Results (Continued) 3.3 Phowe IV - Power Testin (CContinued) 3.3.4 M-l. L Calibration PNrpose

4 The purpose of this test i. to calibrat the.

l power me Wualtor "yste ocal Criteria The aster readings. of each RIP chazler will be proportional to the neutron flux in the narrow-narrow vator gap at the height of the chaber.

Level 2 None i Analyls The URM's wtra calibrated at powr levels ot approxiuately 25, 60,. 80, und 100Z. Table ST1Uu-1. euSarIA.

the calibration.

I Table ST 11-1 Maxm Pavower Variatlons Nutbr of.

Test Condition Powr Level Ibuing TIP eMonoepbl; I-R'tls 1 25 1.71 6 Si 21 60 1.2 S. 'S 35 80 1.71 . --.1 4 100 1.0X 1

Sen-.

11-17 CFINAL

SUMMARY

REPOR? - PNP UNIT 2 3.0 Results (Continued) 3.3 PhL .6 IV - Power Testing (Coatinued)

3.3.4 6TI-ll,_ IRM Calibration (Continued)

Analysis The largest number of Inoperable TPRM's that ware encountered during any of the calibrations was six and at all times thero were more than 14 operable LPRM's per APRH! channel which is the minimum number required for any APRM channel to remain operable.

.The process computer programs which are used to determine the gain adjustment factor (GAP) were verified prior to using the computer calculated CAP's. This was done using an off-line computer and manual methods. The GAP's from the process computer were compared with the GAP's calculated by the off-line computer program (BUCLE) at the 25, 60, and 80X teat levels and these calculations were in very close agreement (within approximately 12).

Additional TIP sets were required at the 25 and 60Z

( levels due to minor problems with the process computer. At the 252 level it was found that the process computer wae not seeing the proper reading for LPRM 32-49D. This was corrected and an additional TIP set was run. Problems ware found with the TIP scan program software and corrected, requiring a fourth TIP set at this level. A third TIP set was run at tha 602 level when a correction to a bad feeduater temperature caused the fraction of rated power (PAP) to change on OD-1 during the

-sccnd TIPset.

Changes to the TIP system between the first and second TIP eate at the 60 and 100% levels caused the GAF's calculated after the calibration for the associated LPRM's to be slightly off from 1.0. The core top limit was changed on some channels at the 602 level and the drive speed was chanted at the 1002 level. Both of these changes caused small shifts of the TIP trace, thus affecting the AP's.

In the few cases where the LPRM GAY varied from 1.0 after the calibratioa, the process computer corrects each LPRI reading using its corresponding WAP. Therefore, the core calculations are still valid and the core monitoring iL not affected.

t

IV-le FINAL SUHHART REPORT - BDX IUNIT 2.

3.0 R azult(ConttIued) 0 3.3 Those TV -- ower TeStinM (Continued) *1 3.3.4 SU-l1.1, RH Calibration (Continued)

Analyss (Continued)

The calibration was performed according to the plant ourveillance instruction, SI 4.1O1-3. This involves adjusting the motoe rgadulas of each VWN thambea by the appropplate AetXs adjustment factor. (CAY), thereby uetting the IPRN to read proportional to the neutron flux in the narrow-narrow water gap at the height of the chaber. This satisfied all criteria.

S.3.5 ST-12, APRH CM1ibratio-

'urDosS The purpose of this teat is to calibrate the average paver range monitor "stew (APRM).,

Criteria Leval -1* O (a) The Ao channels must ba calibrated to read.

equal to or greater than the actual core therunal power, (b) Technical specification and fuel warranty limits.

on APRH scram and rod block shall not bo exceeded.

tc) In the startup code,. all APRM ehannels must produce a scram at less than or equal to 131 of rated thermal paver.-:i (4) Recalibration of the APRM pyste. will not be neceasary from safety considerations it at leas two APIR channel per RPS trip circuit have radings greater than or equal to care power-14aVE 2 If the above critorga era satAstio. than thC APR.11 channels will be considered to be r4nS iccuratol.y if they.

agree itS th, heat balance to withlAi 7 of rated pmre.

a M

P IW-19 V FINAL SIMWkY RFPORT -

3.0 (Continued) aasulta DIMP UNIT 2 3.3 Phase TV - Power TestipR (Continued) .7 I

I"I 3.3.5 STI-12, APRH Calibration (Continued) 1:'

Analysis At test conditions 1, 21, 3!, aid 41, the APRM'a were calibrated to read equal to or greater than core thermal

1 power. The core thermal power was obtained from the procesa computer heat balance ((-3),,which had been verified to be accurate previously by a detailed manual heat balance. 'me APRM'o were also recallbrated after each 1PRH calibration.

In the startup mode the APRH scram .etpoInt was enot at c 152 thermal powers and the rod block at c 121. A scram clump wai set for each teat condition 20! above the test land I

line.

To verify the accuracy of the APR's over large power changes, the gain adjustment factors of each APR?

channel were recorded during the "2" recirculation pump trip of STI 30 -and the subaequent recovery to teat condition 4!.

C Typical results of this APR! tracking teat are shown on figure STI 12-1 for a specific APRH (F). The worst error '4I i

observed for all the channels vas 4.52, much of which Is attri,-

buted to an approximate steady state background error of + )-1132 present In the APM system. All test criteria were matiaiyed for STI 12.

I II

"'1 71 O

e I- C

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11-21 Ab FINAL GWIMY1 REPORT - B MP UNIT 2 3.0 Results (Continued) 3.3 .%ase IV.- Pot kr Testins (CO~tIuui 3.3.6 STI-4. -Rezc stem I

I i

i The prsoi of tbi4 test its tov*:f: F the operati 'ns of the reactor core isolation coolug system ihi the injections".

mode.

Criteria Lvel 1 TM time from actuating dsial to req durd flac must be less than 30 secouds at any reactor prassun I between :

1l50 psig and rated (1020 pag).

With pump discJarge at any pressure ' Betweon 150 pugt 7 and 1220 poLg. the required flow Is 600 Rpm. 4 sha lait of 1220 psig Includes a nominally high value of It 10 psi for line 1080s.,

(7 Th RICC turbine vust not trip off dvIrin$ startupe.

i i

Ii It either of the firat two Leval I ce'iteria Is not.

set, the reactor will only Se allowed to oporat e0ata restricted pqvor level. t *t *.. Ii'.t I

The turbine gln4 seal condenser oyat an shall be CApUblS of pleventing steam SlalSoe e Otm ,epher .

tho it The A vItch for the UIC gteap epp ly lJne hl i flow Isolation trip shalt be adjuste4 to ictat e at 3002 of the maximm required steady state steam flow, -

Analysis II A cola quick start was conducts4 on t :h RCC yetim WMth the pump Aliped to t4ke suction f(V tho condsow$ ". .-

storase to%and discharge to the "ouel. ft tl vesasl injection attempt, erratia ol4latPnU4 -

no fno controller vW rcest which resulted In I

opetatfon. Pertbnent data from the test ts con, table ST 14-2. Transient ramponso to pramente d on figT ure 0 8TI 14-5. All criteIS were satisfied with the exceptia oat.

t 0I

a IV-21 FJMaL SUOIRY WEORT - INWlUNIT 2 3.0 Results (Continued) ... . ..

i 3.3 ,a MV - Power Testift (Continued) 3.536 TI-.16. RCIC 8ntam (Continued)

Anlyis (Continued) the hilb steam flow Isolation setpointe discussea i B * .'

phse IlI teatinsf.

Table STI 14-2 RCIC Injection Data IDates Septenber 3, 1974 Ti=u: 1215 nlours Reactor Pressures 930 Vale Discharge Pressureo 1000 pal Turbine Speedt 4000 rpm 0

Discharge Flws 625 "pa Suction Pressures 30 psig Controller Setting$

PR m2000 m ta Plo lUne to Rated Flow 19 sec. * ., .

1 1I . Is i

'0

A

-otal Steam MMo 1

Total p&&&a+/-f Fi -td Sq . -

5

. t-.-ra...t. ...

.w... .

- SA-uh.O Racoatoustput - ........-........ t

__ oupFL_..............................

_ *- * ~ - -pa - , ... *-

-'5

--. 5 -..---------

a a- A_- - _ ,- _ 3J . -_.

-s . .'.._-._:

__'x. 'reJ Dom

. -- S .. .

4ae W. ..

q.W Ub W@1l

~ .~ .....-

PIPWS SIM 14-5

=IC vessel Tajectcas N

X Chra" 122C)

J. eeond "r divicom l!

IV-24 FINAL BUH= WPORT - Dm MT 2 3.0 Ra"suls (Continued).'*

3.3 P'ase TV - Power Testta&(ContInued) 3.3.7 8SI-15. MT? Sstem, P~rvos '

The purpose of this test In to verify the proper operation of tho hial pressure coolant injection system in the Injection mode.

Criteria .

Level 1 The tias from actuating signal to required flow must be less than 25 seconds at any reactor pressure betwemn lS0 psig and rated (1020 pig),

With pump discharge at any pressure between 150 psIx and 1220 pals, the flow should be at least 5000 sp.

(The lilt of 1220 paig includes a nominally biga value of 100 psi for lUne losses).

The HPC turbine must not trip off during startup. 0 Tevel I The turbine gland seal condenser system shell be capable of preventing steam leakage to the atmosphere.

Th. A? switch for ths UPOr steam supply line high

flow isolation trip ehal2 be adjusted to actuate at 1251 of the maximum required steady-state steam flow.

Prior to this test, an incrkas. In te proportional band setting (600 to 10001) vas made to the flov controller. ^.:I.

A cold quick start. vas conducted with the, pup aligned to take auction from the condensate storage tank and discharge to the vessel, Pertinent data from the text ti contained tn table 8OT 15-2.2 The trmnilent response to pre-eanted in figure iTT 1l-5. Specified criteria were satisfied.

. ,.0

IV-2S

IMAL SI8MMYK 9RP01T - 37W UNIX 2 50laule (ontlnued)

'3.': these IV- Power ?eatkia (Continued) 3.3.7 RTM.15.,WO! Rteft (Contnued)

DateI

-C Tablet Ad 15-2 Iojeotion Data 0ctober 6, 1974

.1 Timl 2110 bour Reactor pressures 940 pals Discharse Pressures 1030 paig Turbine Spaedy 3500 rpm Disebarge PLOWS 5000 sps Al C- ucticn Pressuret 32 paig controller sattingal

.Ma 20002 Riau 100 ft15 to now: 3.5 see,

_ated

' I

0) I t

I

-- I

etA~fM Ck'W. ) .

r*n w T.ea #U 40

?1gwe ~..-. 25 ST m~W.

gmv~fl I Seconco ioJ

r I

% 4 ! f6 ZV-27 I FINAL SU19~ARY REPORT -w I I MM. .- 02II 2 I

3.0 Pesult* (CQnt~nuud) j I LS3~a *Z ?.s&wTesfW U *'.I 1 CT"

1. I 'I - n -

F- . *t*, '

1 teca vi, I; AI

' p1 I

I .. . .1 ?1

.,I 0

21 II

I

'I C)

S .q I, I II h

4.

I

I *. ,*

I .1 il

1 ,

11 i

!! 1C,.

7, I.

U 0*6 I .

,. 1 ,

(I I It F

I ..

Pt I: .4,,

I

FrUi St N UNtT 2H 1MO- .-

3.0 Results (CObttiutd) 3,i asMS4 1 tn (Continue) 3.5.8 STI.16, seleted Proces Tamrattwel The purposes aces

1. To establish the proper settiug for the low speed limter for the reclrculation pumps.

2. To provide assurance that the measured bottom head drain temperature corresponds to bottom bead coolant temperature during normal operations.

Criteria The reactor recirculation pump shall not be operated unless the coolant temperatures in the upper and lover regions of the vessel are within 14S° W. of each other.O The bottom head coolant temperature as measured, by the bottom drain Uine thermocouple shoud be within 54P .

of reactor coolant caturat1,on temperature.

Awnalysis Test data was taken an the 50. 75, an 00 p.rcet load linos. Sho data La table TI 16-2 shows the p;p discharge temporaturs and bottom drain emperature oeaure during these tests. The 50. 75, and lOOpercent load Una date was taken during natural circulation. Tba dat Ows that with natural circulation ncly, the tewp etuq in the boteom bead remained within 1450 I. of the saturatioz Y temperature as specified in the criterIa. The :U-difference was 450 P. which occurred on the OOZ flow Ma.e At the 751 and 100l load lIns, renlrculation pump "A" was tripped and "'"was allowed to conmtinu runuil.

This was to verify that the temperature within an idle loop ,

woutd remain stablB within 50° . of the active loop,

°. dtfference was also observed an the M51 mnxImu of 10N load line. 0

IV-29 FZWAL SWAY REPOR&T - WIP n1T 2 3.0 Iesults (Continued)

' PM.3e I mos BeUn (Coutinu'zd) 3.3.8 STI-16. Beleeted Proceis Temperatures

&U!lsis (Continued)

Also at. tho 7 5X 40. 2002. Xo04 linas. recirculatton ptws. "a"was WPM and "Al valtmm4 to continue running. -

A&. = QE 1Q U. di4 ehec* w4g also observed on th.

753 load line

- ~Table 8TI 1{6 24 Bulected PCOc*a& Tpextuers.

Test Condition llcirc. Pump Saturation Bottom Drain Date Tim In.kiM Radhayb im. T ,,,>#

,, Smy A

10-26-74 2200 50

5250 . 520° P. 532° P. 500 F.

11-18-74 0415 751 5100 F. 5050 F. 5350 P. 5360 P.

1-1-75 0625 1001 510° F. $10° . 530 P. 49D0 P.

11-18-R74 0017 75XX 510' 1. 5 e V.. 530° P. SW° P .

11-18-74 0210 752** 5200 P. 51so P. 539 P. 519° F.

12-31-74 0440 00* 5W°W. T53 1I 7 500P 12-31-74 0650 1OQ1.** 53w W. 5170 1.. 7° 1. 4990 P.

-*Pump "All weped

- Pwp "B" trped 1e S-f

IV-30 FI=A BUAY RPORT - SPNP MI? 2 3.0 j~u (ContInued) 0 3.3 Lhase IV- Lowtr eattn (Coutituue4) 3.3.9 LTI.18..-COre 9.0e? IBSIMutton 1130. pIuQrpoe. of this test erG: (a) to confirm the ?poub tYQf, the TW sysat readingss (b) to doterawne the 0o0th PQVS 4JSristr1ORtio- three dimension 1 (a) to dotaZmine core powr ayiuatrYa CrItterill Not applitable.

lnve~l2 In- the TIM pprop?4u;bilttY. tOst, OSl TIP tr4ce should be reproducible withinI .L5% ralAtLve. arar- CM 40.15 Luch (3.&P) bslteroat eaph axLAi poamtp

'OhIchaver 4s gp0tero.

TIEP BREarduatibtllty

'Ii. xopultq QZ. tl.e TVP 'poiiTwvqwk e4M 4w'-

uariga4 In table $'fl 1841. The te.*t. c;iti4 v# A~tlfe-IW at, both teit; qPLtApM T.QI en& w

-. -'ta~. ~t~r~u 8upuary of TI.P Reproduoi~lIty 34.4 No,. Relative T~sI QvTM.:'

Erro/acghtne UrErro/Mhine Iglative__-- AbiaoLut ftes Don4LI4L0q 1 I 23Z Power 8.51/B 2.51p48 46.6% Flow

$351 M Test COndition 2X 6O% Pawq 4.41/B I.&=

104% Ilov I

IV-31 FINAL

SUMMARY

REPORT - BFNP WNIT 2 3.0 Rosults (Centinued) 3.3 Phase IV - Power TestLR (Contlnued) 3.3,9 STI-18. Core Power Distribution (Continued)

Analyss (ContLnued)

Cl PMwr Distribution The core power distribution was calculated at each appropriate test condition following a completa set of TIP traces. The results at 95t pmer are shown La figure Sr 1-1 and table 18-2., Figure SIT 18-1 shows the radial power distribution (bundle powers In Nllt) for one quadrant of the core. Table STI 18-2 shows an axial (Z) distribution for each of eight radial (R) ring, the core average axial distribution, figure STI 18-2 shows the locations of the iG*ht radial rings.

9SU &Z- Power Alptribution

( 1I ' 3 4 5 6 7 8 Avg L'L Core Top 12 0.671 0.604 0.569 0.547 0.508 0.433 0.324 0.192 0@302.

11 1.290 1,IS6 1.423 1.ll % 0, 82. 0,673 0.402 0.706 10 1.530 1.371 1.343 1.341 1.243 1.001 0.907 0.562 1.003 9 1. "3 1.389 1.380 1.401 1.321 1.196 1.030 0.662 '.095 8 0.872 1.281 1.320 1.331 1.227 1.236 1.126 0.740 1.106 7 0.698 1.061 1.074 1.06i 1.109 1.182 1.148 0.769 1.034 6 0.61B 0. 937 0,939. 0.94 1.003 1.175 1.166 0.787 1.006 5 0.662 0.995 1.00£ 1.012 1.137. 1.269 1.245 0.834 1Q76 4 0.800 1.213 1.231 l. j9 1.3" 1.471 1.4Q. k.94L 1.152 3 0,947 1.447 1.465 1.418 1.415 1.542 1.475 0.957 1.340 1 0.876 1.368 1.195 i.318 1.467 1.36Q 1.164 0.778 1.128 Core Bottom 1 0.610 0.992 0.853 0.948 0.823 0.957 0.769 0.402 0.172 AVE 0.927 1.151 1.125 1.138 1.115 1.150 1.037 0.676 1.000 C

1 IV-32 FINAL

SUMMARY

REPORT - DFWP UNIT 2 3.0 Results. (Continued) 3.3 Phase IV - Pmer Testing (Continued) 3.3.9 ST -18. Core Power Distribution (Continued) la 2.SS11.67 3.9s S .U j3 14.2 3 3.f7T3.84 4.014.54 4.37 4.66 4.3 i4. 34 29 _ _

+

27- 2.4 5.651 3.13 4.U 4.40 4.1 14.77 4.9914 5 4.53 4.85 4 9 4. 4.24 26 2S- - -- z 4,3} -- .

4.S0* 1$ 4 .9S4.934.74.4X19:

4670 .6 "......... .*

24 2.42 13.S 4.00 4.60 4. 8414.9 4.70 14.62 4.90 14.81 4.05 13.93 4.65 14.92 4.15

.2 2.717i317 3.26 4.35 4.70 4.51 4.33 4.80 5.10 4.3. 3 4.09 4.64 4.454.29 21-_- _ __

2 1.99 3.02 3.26 4.64 4.66 4.50 4.541 5.08 .34 14.55 4.91 4.52 4.48 4 4.141.

18 1.56 2.64 3.39 1.45 4.471 4.88 4.[96 5.. 6 5.0 15.00 3.04 4.U 4.71 2.15 3.j L4.56 4.62 4.49 .5 4.9614.95 4.704.69 l4.93 4.6 3.7i 36 12.4213z1.4 °4.0713-5 3. 4. "3 41 4.9944.10 3.2 12 184 215 3.63 319 355 4.41 4.8914.31 4.4014.96 5.04 1424 4.0W 7 3.1 4.331r461. 4.69 4.74 4.79 4.99 4.99 09 -lll-2.49 2.1 3.93 4.27 14.62 4.614.71 4.944.19 5.1t ol OC 1.73 2 1 3 .06 333 3.21 3.23 14.07 4. 3 1.14 3.

U3.5 1993. 3.67 13.39 2.61 04I §1 PSIIgsfi I I I I I

l~j2.71,

'q201 12. I' II 52 12_

02 1L.$ l l 1.52e21S U2522.5

.4 2.-

00 02 07 06 08 30 12 1t 1.6 1 20 22 *2 .6 A8 30 01 03 05 07 09 31 13 15 17 19 21 23 25 IT 29 figure STE u-I Fws (*W) Map at 951 tfav ndAals

IV-33 rim SMR qPORC - nP!i 5.0 Reaules (Continued) 3.3 Ehse IV - Power Teetiwif (Continued) 3.3.9 SU1. O@ O? lt!btiI (Continued)-

a. ,

A

"-+ +/- _:

at- *_ ;**-

0 US -- . ! U a gw.I _- . Ih,

.U--- .~ I! _ i l, +

_ ~~~I _E i.

a- - - T ---- T T _

newa!i5 A84 1ng. (NIB) Hip

IV-34 FINAL SWOMARY REPORT - BF WNIS 2 0 3.0 jqosult (Continued) 3.3 1 ha.a IV - Power Tesatin (Continued) 3.3.0 5T? 19. Core Performance Evaluation The purpose of this test is to evaluate the core performance parameters of core flow rate. core thermal paver level, core minimu critical heat flux ratio ()CHYR)o the core uinftum critical power ratio OMf), the mazla= averO&

planar Linear heat generation rate (PIIGR), &adthe maxima linear heat generation rate (WIGR) of any rod in any fuel assembly.

Criteria (a) The maximum inear beat generation raet of any rod during steaibaatate conditions uhall not exceed the limit specified by section 3.5.J of-the technical specLfi-cations.

(b) KCHFR shall be maintained at or above the flow dependent minium, fuel warranty ECHYR limit (line 'I",

figure 19.3-2).

(c) Steady-state reactor power shallbe limited to 3293 )Wt and values on or below the design flow control.

line (defined as 3440 Hit with core flow of at least 102.5 x 106 lb./hr.).

(4) Th minimS critical power ratio OM) shall be maintained greater than or equal to 1.20 times f.

(a) The maximum average planar linear heat genera-tlon rate (HAPUGIR) shall not exceed the limits of the plant technical specification 3.5.I.

Analysis ho significant core performance parameters such as maximum fraction of Limiting power density (WLED)s minimum critical heat flux ratio (HCHIM, minlm critlal power ratio (HCUR), core thermal paver, maximum average planar linear heat goneration rate (KAPZUGR), and madm linear heat generation rate (K1wft.) were monitored through-out the test program at each of tho test plateaus. Table STI 19-1 contains a suary of the behavior of these 0

Iv-35 FINAL

SUMMARY

REPORT - IFWP UNIT 2 3.0 Results (Continued) 3.3 Phr e V - Power Testing (Continued)

I 3.3.10 SOUT19. Core Performance Eval Lusation (Continued)

Analysis (Continued) parameters. In addition, the teat criteria for acceptable performance at each test condition to presented. Figures STI 1941 and 8TI 19-2 show the NCSYR and XCPR data plotted, compared to the limit lins. The test data shown on these figures Is from the test condition on the lOOZ load line.

Extensive effort vas expended to verify the procoss computer calculations. Heat balances wern verified by both hand calculations and off line computer calculations.

The off liue computer program UC=E was used to calculate the core performance parameters which were compared with the process computer calculations. Close agreement was seen betweeA the process computer and these independant calculations.

As indicated by table 8TI 19-1, all teat criteria wore satisfied.

C

FPMAL SIQQM VZPM- - 8W 2 3.0 R"3un (Cond) 3.3 Phase IV - fower TestJtuR (Comtie) 3.3.10 SlU-39. Come PerftMc Evaluation (Continued)

Table STI 19-1 8ay of the Behavior of Core Parformoe PasrmtA=

CI Test Pa Fow VWlU LIMI ICevkdltoan Z T Value TAmit Valu JtdL Im/ft kIEWIf MIpl ft lwiff 1 31 47 8.63 2.82 2.575 1.362 3.85 14.51 .266 4.92 18.00

8.65 2.484 1.362 *3.91 *14.51 *p,274 *5.07 *28.00 2E 60 04 10t .4.41 1.90 1.855 1.20 7.89 15.0 .535 9.90 18.33 'A 2A 23 %28 9*73 4.10 2.352 1.446 3.55 15.05 .*244 4.51 27.95 2D 42 75 05.03 2.17 2.172 1.218 *6.90 *.47.0 *8.70 *17.96 3C 48.7 S0 4.73 2.74 1.763 1.344 7.45 1S4.49 15.07 *500 9.25 18.35 3D 64 .67.5 5.45 2.30 1.515 1.257 9.31 I5-0f .622 13.51. 18.33 E B2.2 3.03 3.14 1.90 1.480 1.,20 10.75 1L5.10 *74.3 IvSM 18.35

3.3 1.480 1.20 *20.87 *14.46 *.745 *13.78 *18.35 39 33. S.47 3.30 1.510 1.430 6.34 35.10 .432 7.99 16.33 4C 67 49.5 3.41 2.75 1.4s 1.341 9.93 15.48 .658 12.&7 18.35 4D 78.7 70 2.89 2.75 1.374 1.248 11.25 15.49 .746 13.80 18.35 4A 95A 105 2.69 1.90 1.324 1.20 .12.37 15.27 .830 35.36 18.35 4k 43.6 33.6 *5.34 3.30 1.809 1.430 *6.71 *i4.43 *.443 *8.20 *18.33

S= 8mats

£V-37 69 p &AL SMIARY PMORT - BFP -UNIT 2 3.0 Results (Continued)

3. Ease IV - Power Testlim (Continued) 3.3.10 STI-19. Coar Perforfnau. Evaluation (Continued)

III.1iilfii-11hhl gM W4444RW4*1;1111;4141!!FiiliHffli!EHi IfII bUUM111tIlp_ llii1!1VultFi -R I.

fIt 3; 1,-. t!li*lil jp#11 14 itt* t .mRh1 m.-~aflS HEX EH f, ,,to I!'t~

tti! . wr1:rIIT~[tEIf:~i~i~UL ~~4~k1~1~

U I

.H

'Cut F. ;M i

5 or!S.

I I

0 to to 4 l a To Q P so RATfl FLOW (I)

CHCR Cute for Fuel WarcantY DeteGulmtion Figure STI 19-2 Ct

IV-38 FI&AL SUMb0AY RERAT *- II UItEfT I 3.0 Results (Continued)

O 3.3 Plasb TV - Pwer TestluR (Contliued) 3.3.10 SlU 19. Core Performanc Rvaluation (Continued) 1.9 1.8 .1 . .* Limit 1.7 :':". ... l , xCa C: r Test Data 1.6 j I-IM 1.5 0

1.4 1.3 2.1 10___ 720_ 40 7 . 6_00j 5

1.1 10 20 30 40 50 EO 70 so 90 .100 core glow (O)

PLaure TIT19-2

)iCM Test Data

p.

IV-39

. FINAL SMHIARY REPORT - BFNP WNIT 2 3.0 Results (Continued) 3.3 "base IV Power Testion (Contlaued)

-M 3.3.11 JT-2. 1PlUXR anSemstOe td5e *

?urpass The purpose of~thil test is to demonstrate the stability of the core local power-reactivity feedback mechantis with regard to small perturbations In reactivity caused by rod movemet.'

t ~Criteria..

, . ve I A The decay ratio must be less than 1.0 for each process velabl that cxhibits oascillatoMy response to -.

control rod movemnt.;

Level -2 The decay ratio sust be less than or equal to 0.25 for each process variable that exhibits oscillatory response to control rod movemnut when the plant le operating above the lover limit of the master flow controller.

The stability of the local core powersreactivicy feedback mechanism was proved by observing the local and macroscopic effects induced by contvol rod movements.

Cenerally the rod was moved wear a location ithJ the most lmiting thermal conditions. The local Power deviation was monitored Wains the nearest LPRN. Other gross core.parameter, as control valve position, dame pessure, water level, core flow, stem flow, ad AMl indication were also recorded. Table STI 21t1 sumarixej-the text results. Except for the URN flux, no discerible oscillatious or instabilities were noted for the observed pvocess variables.

The LPBH flx, upon rod sovement, moved promptly to a- na.;

steady valho, showing only a minor wll-daped ooil~lttoh:

tmaedately following the rod displecoment. he test tcrQtia were met.

I

ElmmP D 2 3.0 A.uts (CmtAnued) 3.3 PhaseV - Pwer Testi (Continued) 3.3.21 A- et= otods (Continued)

Table S=I 21-1 Sgmy of theFly Response to Rodx Data HIe-t Doe Ratio Rod Rod local Power of Aeasured

- Monitored _ulVables 22-47 1L2 -mi 10 24-49D . .25 10 -- 12 Sb 2! 30-55 42 - 36 32-49k -7 '.25 36 - 42 3!. 40_- 36 24-09A, I .25 36 -- 42 az ft-23 40 _- 36 08-25k -10% 4 .25 36 -442 4q201 1- T a= us only v2Abe abowics any oscllation

, ~.! .:. I ~ .- f-.

IV-41 FINAL SUHMARY REPORT - BFNP UNIT I 3.0 Esults (Continued) 3.3 Phase IV - Power Testina (Continued)

M.3.12 ATI-22. Pressure ReRulator Purpose TS4 pupoases of this teat ares

1. To demonstrate the optimum settings for the pressure control loop by analysts of the transients induced In the reactor pressure control system by means of the pressure regulators.

2. To demonstrate the take-over capability of the back-up pressure regulator upon failure of the controlling pressure regulator and to set spacing between the setpoints at an appropriate valua.

3. To demonstrate smooth pressure control transition between control valves and bypass valves when reactor steam generation exceeds steam usd by the turbine.

Criteria Level I The decay ratio must be leas than 1.0 for each process variable that exhibits oscillatory response to pressure regulator changes.

LAvel 2 (a) In all tests except the simulated failure of the operating pressure regulator, the decay ratio is expected to be 0.25 for each process variable that exhibits oseilla-tory response to pressure regulator changes Uhan the plant ts opertins above the lower limit aetting of the aster flov controller.

(b)Pressure control dadband, delay, etc., if any shall produce variations in steam flow to tha turbine no larger than the values of rated flow specified In the foUtviag table, as measured by gross generated electrical powers percent of Full Power Percent of Rated Flow 30-1001 0o.5.

( 70-90 :L.5 to +/-0.5 70 and below +/-1.5 I

XV-42 FIWNA SMU*MAX REPORT - BFNP UNIT 2 3.0 Results (Continued) C 3.3 Phase IV - Power TestinK (Continued) 3.3.12 STI-22. Pressure Regulatol (Continued)

Criteria (Continued)

Cc) Optimum gain values for the pressure control loop shall be determined in crder to give the fastest return from the transient condition to the steady-state condition within the limit of the above criteria.

(d) Durtng the simulated failure of the primary controlling pressure regulator, if the setpoint of the back-up pressure regulator in optimumly set, the back-up regulator shall control the transient such that the reactor does not scra.

(e) Following a +10 psi pressure setpoint change, the time batueen the setpoint change and the occurrence of the pressure peak shall be 10 seconds or lose.

AnalYsis Table STI 22-1 summarizes the pertinent data con-cerning each of the pressure regulator tests. Figure STI O

22-lA/IH shows the transient recorder traces for test con-dition 4E, 95-1002 rated power, lOOX flow. Using built-in test switches located on the EHC pressure regulator cards, positive and negative 10 psi oetpoint changes were made on each pressure regulator. A test switch which simulates a pressure regulator failure is also provided to test backup takeover.

As a result of the information obtained from STI 22 on unit 1, the unit I testing was greatly simplified. A notch filter was added to the EHC circuitty prior to the beginning of startup testing which allowed the initial adjust-ment of the pressure regulator to provide the feat response to step changes observed only after the 30Z load line testing on unit 1. The pressure regulator settings were initially set at approximately the same point as unit I and did not require further adjustment at any test condition. Th EHIC pressure controller tings were left as followst psi regulator s 3.1 tu.na (3.3X valve travel/psi) 148 pot - 2.0 turns (6.0 ago.)

lead pot - 1.4 turns (1.0 see.)

A FINA SIUAKY RRM - MMP 13m 2 3.3 am. Iv - ?oem ME&US~ (Caumdus) 3.3.12 -

MT-22, Preasum bUnpator (I Toble ST 22-1 p reasst Rea~uetat Test Data Coe I-mlent care .am bo? 11 Elec Dotes St10eI Yae To.

ex) (imbsh.) vimb 25 43 9/2/74 x 16 823 45 . :;. 9R 2.5 188 21 04 60 104 9/30/74 . X a 29 1976 106 5 : 7.5 630 75 . 97 Z1717/4 a' x 48 2470 , 98 '971 0 -9.8 805 4C 59 47 12V23174 a Nm 65 1937 48 . 93 IS 7.4 621 74 7.5 S1919/74 x E 56 2411 72.3 96 794 43 96 1220174 s z 61 31.6 103.8 98 3 22.8 1065

.-. 'vT.znZr.xrwr

A 0 FIWAL

SUMMARY

RPOWRT - BFNP I'IT 2 3.0 Results (Coutinued) 3.3 j'se IV - Powet Testing (Continued) 4 3.3.12 8SI-22, Pressure Reaulator (Continued)

Analvsjl (Continued)

At test condition 1, a fast respousa to stop changes was observed which was greatly Improved as compared to simdlar testing on unit 1. Slight oscillatory behavior was observed in the reactor vater level and At power transient, but the required 0.25 damping criteria was met in all cases.

Test condition 2e and 31 netted similar results as compared to test condtion 1 except that the response tima was slightly longer, as expected for higher power levels.

to Reactor water level and APRN power transients continued be the parameters with the highest decay ratio, although at all times the 0.25 damping criteria was adequately met.

Prossure regulator testing on the 100l load line was smooth and performed as expected. The parameter observed to have the largest decay ratio was in all cases, total feed- ()

water flow, however, ths decay ratio of this parameter remained much less than 0.25. Steady-state limit cycles produced an observed variation of +4HWe (0.003t) at test condition 4E however this remained well below the J0.52 criteria for 90-1002 of rated povar operation. Limit cycles bai at all other test conditions if any were not measurable ordinary means thus are considered non-existant.

As a result of the installation of a notch filter.

the pressure regulator was capable of being optimixed to produce a fast response to setpoint changes. The time between pressure setpoint change and the occurrance of the first on pressure peak qas measured to be between 3 end 7 seconds the 100l load line which was a satisfactory response when compared to the acceptance criteria value of 10 seconds, Pressure regulator testing on the 1001 load liUe satisfied all test acceptance criteria. A sumsary of the worst transient cases for test condition 4C, AD, and 4*

is contained in table 8TI 22-Z.

As a result of testing the pressure regulator at all test conditions listed, It was possible to plot the relationship of control valve position versus total asm flow, This plot li found in figure STI 2-2. PFro tS graph it can be seen that aB 100 stesam flow (13.38 SWA.Thr.). S control valve position li 452.

1 an swKum REMM -P U- 2 3.0 s (contined) 3.3 roas IV - -ower Testing (Cantinued) 3.3.12 _

-Pres.ure -

Rlaeor ()

Table STl 22-2 Trauet SU=aLY, 100% Test Plaeat Test Cow .on 4C 4D 43 Trace N. 65 56 61 J*1 Lo Steppot ut G1 -10 psi -10 DeiI -10 Ms -10 pot -10 psi + I RegulatoA B -AIBA AI I A- I B . I BB

_ Master Master ceter mster Iarter mte? master master meter

.Maimal Manual Manual manual Manual Manual Manual Mavd Manual_

valve CV/BIV DIV 3V CC C7 CV IV DM CV DBPV

__ ___ __ _ __ _ _ ! r.ient __ _ _ __ _ _ _ _ _ _ _ _ _ Incipient _ _ _ _ _ _ _

initI D Pressure 938 lt 98 926 ps 957 ail De1 9i 4 pSiR_ 982.5 . 8394i Dome Prespre -928 isi- 938 MtR 936 Psi 4 955 pasi M 97_3 vi% 973 puI 983.5 wil TA to Flsit (1) 3.5 3.0 3.5 5.0 3.5 3.5 7.0 5.0 6.0 Presst Peak see. . sec ee. see. see. see. see, at ter of Highest (2) Total FW Total NW Total FM Total Total FW Total FW Total FM Total Total PW Decay Ratio (ratio) Flow rim Flow Flow rim Flow Flow Flow Flow

(<_2_____ _ _.25___ f25( _ t..2525) (5))

(542 ( (<251 (425%

St C.,- 40%

- - 0%.o +o .z I- t0 .+ *0% 0.003 iw-e .003) +/-0.003--

otes:

(1) levl 2 ertt limit In 10 me.

(2) Seel 2 criterfa 2hmt Ls 0.25 (3) Jevel 2 erwtexa lftit 40o.51 (dUlt cy1e to nssurd b1 indtad total ste* flow at steady-state conditions)

IV..6 3.0 Results (Continued) 3.3 'Dase IV-- Pover 'testingt (Continued) 33.3.12' 8_1.22, herssure Regulator (Conttuued)

Ap AP= B A

_Core dP To=g 1Z Parametew

_am f-51.9 Total Steam Ilow xtput 8ignal No.

2 -91 6

=3 0r iZltial*

Value 9X

..... J3,.

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13.9 5

value Per Division_

1%

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-A;

-Y: tel x ater Level - - 33.5 0.5 inch f- 4

-Total Core Flow 8 _.:r 1 Q 1 b/ -;

Control ve ition, l 9 47 IM Recile. Drive Flow AI 1 km EHC OutPut 12 - 2%7 :

Ix Dome Pressure NR 13 i83 0.3 pal :. ,

Recire. Drive Flow B 14 49.5 1.0 t pas Valve I.Position 2S 2. .

Weasured with "A" togulator In BPY control 0]

lagmd Ifor 18gure 8TI 22-. . ,

.N ,';

Recorder Calibration Data .. ;.

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IV-53 FINAL SUam=R IU~polT

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IV-54 FINAL SUWMAY REPORT Ma 3.0 Results (Conztiued) 1PMtN!?

0 3.3 Phase IV - Powr TestipA (Continued) 3.3.11 UT -22. Iressure Ragulltot (Conetaued) 120 110 I%

A 0 I

I4 30 40 50 I 60I 70I 80 90 100 CV PoaLtLaaon (percent) liguze SIZI 1222 CV !oaitton va Total Steam Flow I

IVTt P7AIML IDU&RY REPORT - BFNPEI? a2 5.0 Regults (Continued) 3.3 nt -sa IV - Power TestIMR (Continued) 3.3.13 8TI-23. Feedwater Syste.

Tbe PUXPO$B of this teat are:

Zo 4juui the (~Oedater control system for T.

ccOpt4bo r*4ttr W4tor level contsl.

2t. TQZo4 Agtgata stable reactor response to subcoo~ing phW8ge.

3. To deRMtrte the capability of the autanatic core flow runbacc feature to Prevent a lo Water level acus follming the trip of on feodwater pump.

Criteria Level I The decay ratio must be less than 1.0 for-each proceos variable that. eibits osctllatory response to faed-water system changes.

evel 2

(#) To Oey r4tio is wpcte4 to be less than or equal to 0.25 for hA process variable that xhibit, obcillatory zspons eq Cesvatqr system changes when the plant is operating above the lower limit of the =ater flow Go Q 4ller.

(b) bollwing a 3-tinch 1v.l atpoint stop adjust-u4t In QIq, th, time from the setpoint thr,"lreuqt

top chom untSl, the Worm lovol

ocurs shall bo 1hg; than 3$ 44c*40 RLthqY0 Oqa4iV f4edwater swings 8 in feadvater flw greater than 25Z of rateA flod).

Cq) au qe tic recite flow ruha featweo shall prevent a ocram from low water level folloving 4 trip of one of the oapraktig f~efater pumps.

(4) With the oQPIAnets systam operating uorm1lly.

the turbine speed limt shll prevent pup damae du to gavitation .

IV-56 3.0 Results (Continued))

3.3 Phase IV - Power Testing (Continued) 3.3.13 sT1-23. Feedwater System (Continued)

Ainalysis The capability of rahe feeduater systez to satis-factorily control reactor water level was demonstrated at the test conditions swtmarised in table STI 23-1. Transient recorder traces were taken of the specified maneuvers while in alternative modes of system operation.

Due to problems associated with maintaLning opera-tion within the preconditioning interim operating require-ments (PC1OM) the automatic mode of the recirculation flow control could not be used. As a result testing of the feedwater system in the auto uode had been deleted midway Into the startup test program on unit 2. Plant operating procedures were written requiring that the recirculation flow control system be operated La the master manual (MK) or local manual (1H) modes only, therefore the auto mode was not tested. in the event the PCana limitations are relaxed such that the auto mode of operation becomes po5si-ble, special testing will be performed at that tine, upon 0 approval of the NKMB, to demonstrate the operability of that control mode.

Water level setpoint step changes were performed at various teat conditions, and a one feedwater pumptrip was performed at test condition 4E on the feedwater system.

Level Setpoint Changae Experience from unit I startup testing of the feed-water control system provided valuable data which could be used to minimize the "tune-up" procedure on unit 2. Approxi-mate controller settings could easily be determined which provided acceptable system response at test condition 1.

The intial controller settings were as follovst Proportional Band a 3601

, essets 0.4 3/lin.

During testing at TC-£, the controller proportional band was reduced to 3001. Plus and minus 3-inch setpolnt changes ware inttoduced in the 3-clement mode, and +/-5 Inch changes in single element. The time to respond to the set-VoLat change and the time to the new steady-state level were shortened with the increased gaLn (decreased proportional band).

rMNL SMWAK MM~ - U1PM MIT 2 3.0 Results (COut1ivued) 3.3 Phase- IV - ?omtTstn (Couti*ue8) 3.3.13 511-23. Feedvater System (Cont:inued)

Table S1 23-1 Feedvater System Test Data Reactor Recire. Datae Tpasent core cove Reator VW At-left As-left Rewirke Power flar Performd Trace Theral Flor Prssure rlow POPO ona1 meet

) ) Powr Onlbr.) (Ps1g) (1 /br.) Dana 1 25 - 912174 - 9 790 1X _

30092.5 = 4

. 60 104 1016/74 32 1950 106.8 942 7.6 300 0.04 Recirc in 60 104 10/6/74 33 1950 107.8 945 7.6 300 0.04 Recire In Auto 3 75 97 11/17/74 47 246 99.1 969 9.8 300 0.04 4C 59 46.8 12/23174 67 1938 48.0 938 7.4 250 0.04 4D 7.7 70.5 22119174 58 2360 72.3 955 9.2 260 0.04 4! 95.6 101 12/2074 63 3181 103.8 984 12.8 250 0.04_

98.2 98.7 2t/30174 71 3233 101.2 985 13.1 250 0.04 He pat trip

IV. 58 FINAL

SUMMARY

REPORT - BFUP UN1T 2 3.0 Results (Contlaued) 3.3 Phas- TV - Power Testint (Continued) 3.3.13 STf-23. Feedwater System (Continued)

Analysis (Continued) leval Setaoint Changes (Continued)

Test condition I was the only time the feedwater systmt vas tested In the auto recirculation flow control mode, since the deletion of this mode had not yet been finalized. Transient response in the auto twde, when subjected to a +5 inch level change produces an unexplained minor excursion of about 6 kgpn in recirculation driv*

flow'W"(caused by pump "A" speeding up for several seconds).

The cause of this anomaly cannot be further investigated since future testing in the auto mode has been prohibited by the Nuclear Safety Review board (KMfl). Testing of the feedwater system ln the master manual flow control mode was satts factory and did not produce the tran lent response witnessed in the auto mode. Plus and minus 3-lnch setpoint changes were made in the 3-olement mode using both the "A" and "B" water level reference column, and +/-3 Inch changes were made In the single element mode again using the "A" and "RI column. No further controller adjust-ments vere necessary to improve the response of the feed-water system.

At test condition 3E, +3-inch setpoint changes were made in the 3-elemant code, and +5-inch changes. in the mingle element mode in both cases using the "A" water level reference colum. No controller adjustments were made. All test criteria had been satisfied for the tests performed.

On the 1001 load line, testing was performed at the test conditions summarized in table STI 23-2. Mhen +3-Inch changes were made in the 3-element mode, a fast response was noted and the water level attained its naw satpoint value without overshoot, Only a minor overshoot was experu-enced ln the singlo element tests. All test criteria for level setpoint changes have been satisfied on the 1001 load line tests. All process variables which exhibit oscilla-tory response had decay ration of '0.25. The time to water level peak following a 3-inch level setpoint change waso35 seconds.

-s.

~AL -- RAEP= - W8P MMT2 3.3 Rhase-XV - PoveT Testlu (Continued) 3.3.1. MT-23. Feedwate S"se (Couti.uued)

Table 8?? 23-2 Test I I Tine to Timn to1 TIMe to lfr-w 0ontrallex IF? NeW as Boax. at mmax NV TIM Traeo KaWD~f~lmI= Urael min. IC." I C!"Me Cr1terta No. PB l RH !f Deft ISeconds 5Secodsa I econds (% of Nannl~y Ply pip 250 0,041 3el/A/-3' 2.2 32* 32 13.2 P P

4'67 250 0.0EL U27 29* 29 10.5P 250- 0.04 I A-50 2.0 42. 26.3 .3 Pp _

&vL 0.01. eIA+5" 2.0 46529 18 U' 260 0.00 3 i 2.9 2*32100 P P 4D1S8 260 0.0Ot 3e B-3" 2.5 19* 19 13.0 p p 260 18/4/ff" 3.0 42 28 19.8 p.

260 0.01 lel/81-5" 2.0 5 - 24.5 23.0 p 2501 0.04 3elt8i+311 2.25 _19.25* 19.5 25I 250 0.04 3el//-3" 2.5 1 31.5 6.3 ZZ9.250

_ 0 1.1 l 2.0

/i 44.0 34.0 1 §i__ P =

250 0.04 1.1 B -5 2.0 44.5 - 30.0 15.7 p P OMo~verwoot expeeienced p - Pas" r a rail

.- ' . ,-I.-

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IV-60 FINAL 8MAQMRY REPORT - BNP UNMT 2 3.0 results (Contiuemd)

()

3.3 ?ase TV - Power Testing (Continued) 3.3.13 STI 23. Feedwater System (Continued)

Analysts (Continued) evel Betpoint Changes (Coutimued)

Adjustment to the feedvater controller during this erie of tests resulted in final controller settings as follow s PropoctIonal su4d 2150 Resets - 0.4 R/siu.

Figura STT 23-Ls, B. Cs and V shw the transient response for tests perfoazed at test condition 41.

Trace Initial Value Per II No.

w Value Division Il, l I APRIl A I 97 APRH B I 90 1.0% 1 Core dP 3L 20.1 2-.0 Pat

Rx Dome Pressure _K- 4,. 984 4.0 val Total FW Flow 5 12.6 .. 4nb th Total Steam Flow 6 14.0O 0.4 MtIbhr, Rx Water Level PR 7 32 0.5 £tMh Total Core Flow B _105.0 1.012MM PW Controller Output 10 80 1.0-.

Recirc Drlve Flow "A j St _ 1.0 _M one tlutgut -- 12 -2,0Xt Bypass Value71 Positon Closed 2.0 Tegend for YLuSre STI R.

Feadvater LYval Stpoint Changes CalibWation Data Ip

0 .i: .

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IV.65 e FINAL SU0 Y RIPORT - BFNP RiT 2 3.0 Results (Dontinued) 3.3 'harm TV

Power Testing (Continued) l 53.533 STI-23. Feedar System (Continued)

Analhsis (Continued)

Ofto P-11012 - ::

The feoWater pump trip from test c ondition 43 was performed by tripping the "B" feeLwater pump fram a con-,

dition with all three fee4water pumps operating and the feedvator controller in the 3-element mode. Following the pump trip initiation, th 4equnca of events wVra as follow4:

(l) Feedwater flow began dzopping In ubout one

@~scond.,.

(2) The feedtwter controller at the same tine began responding to increass the speed of the two remaining pUMps.

(3) At sbout 3.75 meconds following the pump trip.

feedwater flow reached a minimum of "10.1 Hlb/hr.. a drop of 3.0 Hlb/hr.. and began increasing at 4.0 saeonds.

(4) Water level began a steady 4ssceat at the time of zinimum feedwater flow and decreased to a minimum of t2.5 inches at %30 seconds. which was a drop of .1.5 inches.

(5) NautroA flux decreased to about 61 at 13 seconds into the transient due to changgS in inlet aubcooltng and continued dropping after a seml-equLibrium condition t s the recirw pump runback olrquitry took hold and began decreas-Lag recirculation drive flow.

There was only u I inch overshoot, an4 equilibriu :

conditions were reached ln about 5 minutes. The capability of the automatic recirculation flow runua4 feature was satiufactorily demonstrated to pevent a low yater level scram following a one pump trip. Riactor power decreased 39.3 percent of rated to 78.9 percent due to tho reoirci4l-tion flow runback.

The overall tranalsat was s9ooth end the system response was excellent, and le eumaarisUd in tble 233.;

Figure 23-2 uhohm the transilnt response for the one pump trip test.

C

zV-66 FVaL sUW4AY REpOrT - MPfl UriT 2 3.0 ResultsL5 tt~U 3.3 Poweg~. lec~tf (Cauti=0a4).

3O.3)) 5k3i.0 LU~ Co~nua4)

AnIalysi (Coat4=~4)

Om~%,UV T4w DAMR 8mary Water I~volpop (IUttAI-~40uip) 11.5" 4: to1.5 Levelt Ovtahabot 2"1 Time PV ploy start Isaroaaius 3.5 secorids Time to level 4i4 Flow 40a471-8t~w "5 .iwmtcs

IV-67 C VIMAL SWMOMY REPORT - WUtIT Z BFNP S3O Resultn (Continued) 3.3 Phase IV - Power Testinr (Continued) 3.3.13 5TI-23. Foedwater Sstem (Continued)

Parameter Trace Initial Vatue per Name No. VJouel. D.i vi.fl oL APRH B 1 97.5 1.01 I.PRI 24-25A 2 92 1.01 nW Pump A Trip 3 Scram Indication . -

8 Total W Flow 5 13.1 0.4 Nlb/br.

Total Steam Flow 5 14.2 0.4 ilb/hr.

Rx Water Level NR 7 34 0.5 inch 100 1.0 lb/hr.

C Total Core Flow 8 9 52 1.07 Control Valve Position, All NW Controller Output 10 1..Z Lx Doma Pressure WR 11 985 10 psl Rx Water Level WR 12 "30 10 inches Rscirn Drive flow a 1* 49 1.0 kapu Recirc Drive Flow 1 14 47.5 1.0 kgps WPump Trip 15 Recitr MG Speed A 16 86 2.0.

lRcitr Mk Speed B 17 86 2.01 NW Pump C Trip IS - _

Lenneud for Figure STI 23-2 I Feadvatar Pump Trip Calibration Data C

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3.0 Results (Ccmautndw) c V o 3.13 W wa.elnt wont ).

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IV-70 FIN4AL SMWY REYum RT BFNP UNIT 2 o 3.0 Results (Contiuead) 3.3 to IV - Power Testinz (Continued) 3.3.14 OT124. vnass Valve1 The purposes of this teot ars:

(1) To demonstrate the bility of the pressure regulator to smila'as the reactor pressure disturbacs during an abrupt change In reactor stam flow.

(2) To demonstrate- that a bypass valve can be tested for proper functioning at rated powr without causing a high flux rscr.

Criterta.

Level I The decay ratio must be lass then 1,0 for each process variable that echibits oscillatory response to. by pass valve changes.

(a) The decay ratio is..ewcte4 to-be Use than o--

equal to 0.25 for ech process variable that ehilbits. osoillav' tory response to bypass valve chatnes. wbO the plant L' operating above the Ivr limit setting ofS te,&mster flw.

controller.

(b) To avoid &pproaching st*e line low pressure isolation, the maxuda pressure deocrse at the turhb* inlet.

during valve opening shall not sxce4 50 PeA.

(c) Th4 reu44tow sabll lLt the pressure d4l.'

turbance during valve roqlosur. so that a margi of at lea1t 5X shall be maintained boloy A high flu scram, l rach A stey-atat%.

(4) System pressuro shalw value within 25 seconds after. the bypass valve has been opened or close.

Analvsii' The ability of the pressure regulator to u!ni -

the reactor pressure disturbance during the functional test-Log of a bypass valve as well as the capability to functionally

v-7l t 1L SWOY =MT - amUP IT 2 3.0 Reault (Continued) 3.3. Lhaa,. V verLee is (Continued) 3J3.14 §TI-24. ftePas- Valves (Contlmsd) fnal~as (oAt uawd)-.'

taust 4 bypass valva. at rated powor without calsing a high f1ux coram was demonstrated uatlsfactorily at the test con-ditionsg listed in table STI 24-.

For test- purwuesi the BPV openlng time was adJu4tad so thAt the valve would opew in as short a time as possible.

The esuro4 valvik timewes as ollows:.

SPY oai in tLs Z 3.0 mecods BPYV OloV.Aau 8.5 seconfs The mtsIured: bypass vAlve c; city in percent rated steal flow was 4pproximately 2..'.

Table Sn 24-2 coqt44m ik .umary of the bypass valve teat trasaient datk from &11 test cOitioS.

v In addition, figure STX 24-l& ai4 U show the traslent'recordep. '

traces from test couditip 41.

DW to problw&. 41Q%4tel vit m 4 fRt~izg operae-.

tiou within the .preconini ineri opei rqqy4ts a4 -.-,

(PCIQC), the autoia a$ th rclu lo flow c.-

trwl cvul4 not boed. 4.As AS Vt 8 - l tBkt.- the bypp v^ve4 in tho auto.Wdp40t . bq 4q atd fga th' unit 2 startup tVt. ptoSgrI. P1 t 9pOItitig pPacguediw vere wrltten raqu4rina th 4t thW rptirculatLon flaV Qortorl eyst4t be operate in tth. .tay......4 a4..l.c l. al,31 uos -,

only, therfoe the h to mode. Was; not teaed., Iq t AvOe:

th* wia.> U .e.eq*. a ir$-4M such tht thosaiu 44 of opr4tlo. beCoc* poueO.b, special tp#tipj w1$J ba P..

fonwd 4t thst tlzw, qpopapproval of th NM, to 44z $to t -.i tp operbility of that coqvrol mq..-

Bypsas V4lv etesting a; 411. teot cQ44W044. 1B.t4A; La table STI 24-1 Sstisfed all test soeptp CPltP.PL4 Througbot th Alan!;p! ttst pPgxrq, d W4 tV*a to strapola;. for- ths flu*

i

ruiPto - .

s=r wbea oprpatlng at 100l rqt_4 pr. The Srap 1 GIMt"-4ro al. pPOIt is shIown i iu;* STI 24-1. 161 EafiC tet. cwtts results which ahowd this .. rgin. to be L of rof s4pk" whicl satisfies thq level 2 cit*stle.

Finn ShIREPOl~RT mL - MMN IflhT 2 3.0 Reevts (CoUtluned) 3.3 Phase Iv - DM etiAM (Cout~nud) 3.3.14 S=I-24.Bwes Valves (Contimed)

Table SU1 24-1 BRypass Vave Test Data Core RatrRecirc.. Translut; Thermal cove Reactor 1w Power Flow Date Mma" Power Flow Pressure Fauv In a)l 4'r Perform" no. gMt oab/br.) _irks Ror.

1 25 44 9746 19 2.5 I

2A 20 EC 10/26/74 42 659 30 940 1.9

_ 104 .9/3074 30' - 3978 1" 945 7.5 In Manual, Bat Transient Trce IRc

.E 60 104 10/f/74 34 J976 104.6 945 7.6 Rect ihAUTO.

- 56 104 10/2/74 j8 1844 146 96 ReeitBIre n aual.

3 75 97 3W 717 I" 2470 98 973 9.8 4A 44 N0 1/ 5; 75 1451 35 930 5.4 4C 59 47 1223/74 66 1938 48 938 7.6 72 70 1212914, 57 2373 72 955 9.3 00 M96 10122/74 62 3169 103 984 2.9 a 0

IV-73 EIMAL S8iRY REPORT - BFNP MIT 2 3.0 Results (Continued) 3.3 Ph,* IV - lowerTesting (Continued) 3.3.14 STI-24. Bypasa Valvea (Continued)

Parmester Trace Initial Valu6 per Name woo Value Division APRH A 1 96.5 1.0O LPRM 48-41A 2 91 1.01 Core d? 3 20.5 2.0 pal Bx Dome Pressure IR 4 984 4.0 pa£ Total VW Flow 5 12.9 0.4 HlbIhr.

C .

13.9 0.4 NlbIhr.

Total Steam Flow 6 Rx Water leval NR 7 $3.5 0.5 inch Total Core Flow B 19) 1.0 Hlb/hr.

Control Valve Position, All 9 48 1.0O lecitc. Drive Plow A 11 50 1.0 kapm RUC Output 12- 2.0Z lictrc Drive Flow a 14 49 1.0 Us8P Bypass Valve #1 le C1Qs8 2.01 C, LageM for FLguza STI 24-1 Recorder Calibration Data

FINAL S*KRY PEI'I?

MalL 3.0O Uutoni. (Vwatluuo4) 4 .3 K)

I 3-4:4SV Ar3.3.-*

-, I

'9

9.'. 1rt.rtSqsWi

t4 I

II

'I.

II I I

.r I

r1*

'I i i

I it I.

I 4.

i j%. I-i I S.

I *. i I I

SI

.1&.:

,. ,. . ,, I.'

- - -- l

IV-?,

a FINAL SMMNAY REPO~RT - C-.

FurA

. : 3.0 Results (Contlaued)

I 3.3 Mtffe IV ~- Boor-

.. ; I Leatigaf .(Cont.)

.1, ..I 3.344. STrI-?A4~

I...- .",

II., ; 1.--c'o, ..- -L - ... I .V (cona

,.Z.: i .. I I iI

. . 4

.I

., , I- ; .

I I P-ij Cn)

.4

1. . . . q

. I k I : I ..

..I I .i I t I . . . I .

a

-4 I.

.i

% I I

-0

. , i iI f I

'U. I

'I I-

. i I

I II i

I I

I. . i (7) I I11 aV L S

L SM E WR -M V 3.0 Results (Coutfuned) 3.3 Phase IV - Power Tetm (contiued) 3.3.14 StM-24. !ZMss Valves (Contiued)

Table STX 24-2 bypas Valve Translent Data Smuy Test CondItIon Ludt 1 2A 2E S 4 4C 4D 4E Recir_ Mode* __ Htz 1 .NC N N NC.

W MK N. .JHH_ ___

Wn-_2S- - -7 I- I tIgeal APrg QI. --- MA 20, 55 7 58 70 96.5 Mra ted FM(l 3 51 15 16 16 1.6 16 6 16 16 masi t-S-a M- - -

Eniie ( --- 919 940 920 973 930 938 955 98A DI an =pftim -1 1 2 1 2.5 2 0.75 G .8 Dec-eas (pit) -AS -P--I Dome Pre sure O Closing 1 2 1 1 2 0.75 0..8 ighest D ) _ ._ 0.25 '0.25 '0.25 'c0. 2 0.25 '0.25 '0.25 40.25 Ratio :t!pen ) ' (AP30 ( ~ Presst Vtr Lvi) Vtr ti) . ) L Highest DecaY 0.25 40.25 0.2 0.25 '0.25 '0.25 I°'0O,- , o.25 1i Ld~mis) Aft Press MI wtr lo) (ft Vtr ilv Vr Lv1T Li2I) pr settling Time 25 se 6 20 9 8 3 4 2 4 (Aftem roeu (Me) _____

_. ae2 5 U1 7 7 3 2 2 5 TM a LoWl Manua mC a watuna ccuutum 0.- ... O O

EINL SM9MMR REPORT - BMW UNI 2 3.0 Results (Continued) 3.3 Phase IV - Pawer TestinR (Centimued) 3.3.14 ST!-24. Bypass Valves (Coutlnuied)

APRM4 Scram at 100% Flow Level 2 Criteria ari n7 -A

-i7 !E-ii: 1.:

V-

I-

- i I

I I

30 40 so 60 - 7 80 Filure SU 24-2 Bsma va1w, yll Margin to Scir at 100% Rated PHeur

lV-78 MNAL -UIARY REPORT 3 n? UNI 2T 3.0 Results (Continued) 3.3 Thase -1d - Power Teutint (Continued) 3.3.15 2 Main SteamLine Isolation X a=ve:

Purpose The purposes of this test are to: (a) function-ally check the main steam Una isolation valves (HSIV) for proper operation at selected power levlso; (b) determine reactor transient behavior during and following sfzultaneous full closure of all MSIV and following closure of one valve; c) deterine isolation valve closure tim; and (d) deter-mine the maxlmum power at which a single valve may be closad without causing a reactor scam.

Criteria leve I1 Closure time must be greater than 3 and less than S seconds. Reactor pressure shall be maintained balow 1230 Paug (the setpoint of the first safety valve) during the transient following closure of all valves.

eve 2 .

The maximum reactor pressure should be about 1190 pugl, 40 psi below the first safety valve setpoint follow-Lig closure of all valves. This to *argtn a of safety for safety valve weeping. During full closure of individual valves, pressure mst be 20 psi below scrams, neutron flux must be 101 below scram, and Steo flow in lndivtdual llnes must ba below the trip point.

Analyis-MSIVy "Udivlidual Closures the HSIV IMUvidVAlU 4osrO test Is pow depdeAt only, therefore the tests at condition 21 (40-601 power,

~104% flow) were performed at test condition SC (411 power, 44X flow) to facilitate scheduling. This test was performed on November 6, 1974, and all valves closed wIthic the required 3-5 seconds.

The peak reactor pressure following valve clogures was 9p9 palg. The steady-state reactor pressure was 920 psig. Main steam line pressure was not affected by M9IV closure. Main steam line flow, reactor water level, an4 tur-bine Inlet prossure were slightly perturbed by MSIV'e closing.

lV-,9 MIAL BU)*(ARY REPORT - 8FNP UNIT 2 C 3.0 Results (Continued) 1.3 Phase IV - Power Testing (Coatinued) 3.3.15 STI-2S. )Ialin Steam Une Isolation Valves (Continued) a Analysis (Continued)

For the testing at teat condition 4, the power was reduced to '70M to perlor= the teut. At this condition the maximun reactor pressure was 1I010 puig, a rime of 50 psi over the pretest condition, and the maUimua power spike was 1'81. No isolation trips from high steam line flow occurred. All level 1 and 2 criteria were met for each of the 3 MSIV'e.

Table 81I 25-3 gumnerizes main steam isolation valve closing tiasa for all eightH2ISV's at the three test plateaus of tuterest. After appropriate adjustments where required, all valves met both level 1 and 2 teat criteria.

MSIV Simultaneous Closure On December 21, 1074, a simultaneous full closure r of all HSIV's occurred from 98. power due to vibration of high steam line flow inastrumantation. Transient recorder data was obtained for all pertinent parameters and all level 1 and 2 criteria vere mat.

Table STI 25-3 HSIV Closure Times C10asre Times - 8ecoudu

. .. . TC3C

. .I., TC-4D ISIV Valve 1OX. 42X1 70Z nber 8-26-74 11-6-74 1.1-7i TCV-1-U4 (1U) 4.4 4.2 4.2 yCV-i-IS (IA) 4.1 4.2 4.2 YCV-1-26 (1B) 4.1 4,1 3.5 ICV-1-27 (13) 4.4 4.3 3.4 VCVy--3) (1C) 4.1 4.1 3.7 VCV-1-38 (IC) 4.1 4.2 3.7 4.1 C ICV-1-SI (ID)

ICY-i-SI (6D) 4.2 4.5 3.6 I ~ .

IV-814 FIAL StY EPO - SINP UNIT 2 3.0 Reult (Continued) 3.3 Phase In

Power TeotIgI (Continued) 3.3.16 8TI-26. Relif Valves Puruose8 The purposes of thsI test arai To VerIfy the proper operation of the primary uysteO rellef V41Wvs.

To determine the capacity and response character-utict of the rlief valves.

To verify the proper seating of the relief valves follovia operation.

Criteria Level I Rone 1eyl 2 (a) Relief valve leu!ago wut be low enough so that the temperature easured by the thermocouples in the discharge side of the valves returns to vithIn 10° F. of the temperatc recpd.d before the valve was opened.

(b) Sun total of capacity measurements fram the eleven r9Uef valves shall be equal to or greater thant 8.2 z 10 lbs./hr.. porrected for M iulet pressur. of 1112 puig.

(a) Delay ttwes measured vith tht Ultrasonic trqnslator probe during relief valve manual ¢atuations shall be not greater than 04 seconds. Dslay tt io defined a the elapsed time from electrical initiation signal to the tise thd main disc starta to opel,, Thqr. b411 be at least I hour elapsed from any earlier actuation of the ;aliat valve of interest for this crLter4a tQ #ppjyI

wolvs is All valves mat timing, 4pacity r.4 reaeating criteria for this test. Table STI 26-1 sauouri4e the test data. The total measured capacity Va_ 8.7 S 1O0 lb./br.

compared to the criteria of "8.2 x 10 lb./hr. the slowe*t M

TV-81 LimA CemOmy LF..POT

BVE? UIflT 2 3.0 Result (Continued) 3.3 Phase 1

Low? ._sttina (Continued) 3.3.16 8TI-26. Relief Valves (Continued)

AnAlSIS (Conttned) delay toe vas 0.32 'scoad on valve 14 compared to test criteria of 90.4 secoQd. All tailpipe toverature raturm,"

to within 100 1. of their lnitial temptratures.

-Table CTI 26.1 pelliet VAlve Hanual Actuation Daa Corrected ReseatUng Measured Delay Initial Pinal Acceptable Rulief Cpacity Tim Temp. Tp. (PPass)

. ata Valve No. (10" lb./hr.) (sec.) (OP.) TamOfpA ( lfa _

9/ 74 1-4 .732 .3Z 260 265 F 1-5 .Os0 .27 256 250 P 0 1.18 .84 .23 240 248 P 149 .811 .26 250 255 P 1.22 .764 .24 230 230 P 1-23 .787 .27 223 229 P 1-30 ,796 .25 251 262 p 1-31 .787 .25 ISO 350 P 1-34 .804 .26 230 2

P 1w41 .777 .g8 .240 213 P 142 .796 .26 264 371 P Total Capacity - B.678 x 106 (1)Capacity *orrected to design pressure of 111 pats C.-

II

IV-82 UMMAY REPORT Yfff MIL - IBIN UNIT 2 3.0 Mault (Continued) 3.3 2hasa-X - Mr Tse (Continued) 3.3.17 STI-27. jurbine StoP and Control Valve TMiDS Purpose The purposes of this teat ara to (a) determine the r!oponso of th reactor system to a turbine stop or coatrol valve trip and (b) evaluate the response at the bypass, relief valve and reactor protection systems. The pdramntric responses of particular interest are the peak valusa and the vate of chang, of both reactor power and reactor stoam dome pressure.

Criteria IPVSI I (a) Reactor pressure shall be maintained below 1230 psig, the matpoint of the first safety valve, 4uring the transient following fast closure of the turbine stop end control valves.

(b) Reactor thermal power, an indicated by tho 0 simulated heat flux readout, must not exceed the safety limit line defined in section l.l.h of the technical specifications. The turbine control valves must bogiR to close before the stop valves during the generator load rejection. The turbine stop valves muat begin to close before the control valves during the turbine trip.

g t) Eeedwatar system settings must prevent floo4v Log of the steam lines folloWing these transiontu*.

Level 2 (a) The maximu= reactor pressure should be loen than 1190 psLg, 40 psL below the first safety valve sotpolat, during the transient following fast closure of the turbin stop and control valves. This pressure margin shoul4 pret vent safety valve weeping.

(b) The measurement of simulated hoat flus must not be signtficantly greater than pro-analystoe alculations.

The pressure regulator aust prevent a low pressure reactor isolation.

(c) The feedwater controller must prevent a low level initiation of ths IWCI and HSIVIs as Iong as feeod water flow remalns available.

I I

S-IV-83 FINAL S[EQ4ARY REPORT - BffP UNIT 2 e 3.0 Lesults (Continuad) 3.3 MesaTV -Powr Testin (Continued)

3. 3.17 STI-27 Mhvbine f top and Control YA~ve TEiUs (Continued) grEferia (Continued)

JAJy I~(Coutinuod)

(d)-tho load rejection within bypass capacity aust not cause a scram, The tcup scram function for blgber power levels must moot US~spacifications, Analysts last closure of the main turbine stop valves was dewonstrated At 100% of :ated reactor uQ~4tt~tqa soqisqnca of wevats, m4 the tines respectiva to the turbine stop valve trip are preaento4 is-table 5TI 2741 baby.

Table MT 27-2 4uwiArtxoa the pIruxolpal qra=%ere go~ue IC genceTaine M~b274It Seuse o Vonts anTrbn 3o_g Vaivn Closr Time

(see.) Wot, -

0 Tuvbtno 'tp

.1.5 Start Of eV CboAUwe

.1.9 IM;r of QY PbouIWOM.4 4TV OpeiAUS

.-21. Reactor scram

.25 MAUai HosaUt Ft=

.39 eV roll MbOWo li/A 39? lostI ()poii MIS Va1% Reao0oT preesew i5sgec. minion 140Rator VOTr 1*V*1 apaptou alsotion 0 gs90 usz~mt Ua1ptor V$*4k UeVe C,

I

Ea MM NI XVT'84ip 3.0 Results (Continued) 3.3 Phase II.- Power TastiIM (Conttnued) 3.3.17 f1 r-7. _pblee 28o and -Otr_0i VLSVe £M (COj~tIOU6d)

Table mT 27.2 Siumaxy of 1MnIpal Panametens Turblae Stop VAlve Txip from 100 Is Parameter Zogt. Actual Peal R04otoT ftOSaur* .4190 Ps& Was~

flux BotumHat Inc£Ures4O

)~uumReactor Water level. no.J.TrtP (-~3%. 5) .35 inches HM4x2m Reactor Water IAVeL Cateam liue (NI30") 64 tuchua Control Valve, Closure TUrn02Oq.41 of Lunalysi (Continued) : -

Past cloture 9f the main turbtroi poatiol ve4XVe vats demoai4t~qd gt 45X- e#W l00et rate#4 reontor cond~ttov.

At the~ %SS rSqOtQIF pond~t ton. tii tran~euIt VA4 .,l within th; capacity of the byVpass vatv. system its the s . i valves open fast g#ovel tg viz uel1Y o1l znate 4 p?0584? ' -

spike.,

&low-low s~tqr Zqvel insolatioa Qrcpfre4 diuiss both ST14X7 trip; #rq IOQ7 pwowe, Tt waj not withStu the evnth capabilicy of the fe#4vator controlt systopio low wate; l~vql cpu~t44op Ikoia QQQwring as rqquIred by .,

the lqivot I c;Lteris, for the generato; l1W reje49tqa the te t vg., ptzrpos#Cyly otar;** fro 7"1 hith rtAni~ i level to provent the tuolatkon. Hawvovrs the 4nitia 4gop A, V0. tog myo ;nA tQo #V~fq for the (pee~4vtgr eystem t9 QW.

pausat.. since a reacto; 1t40latign 40as not QOnAttitt is s6jqity Vphlj.q th*. Xa;'4;; of thi; %*a%were aeoca s4 a : :

ct ry.

satsf Th .lw le e slattan problem in betas . .

reviewed by GE and TVA, I)RD SO I

1V485 FMNL SWMARY REPORT - SFNP UNIT 2 3.0 Lasult (Coutiunua) 3., Phale R --Awes Teptin (Coutinutd) a(outivwod) 3.3.47 SI-,&7 MO-Ula BOm MA MA-L Y~ VaOei UIbl* $TX 27-3 CloSUre, of Msiu TusrbUpo CntOIC Vgkv* DOM last Saeoniu !veut -

)

0.0 Intiate Generator Trip (OULn fteak~r-f

-D.0.7 start of CV Closure, 4n4 SPY' (Vwengn

.184 CV Full Cloxe4 0.53 iaaccor Scram 0.37 InV Full Open

'U3.5 Peak Reactor Treaaur&

solatIOQ U3.86 Minim=u 2laactw Water T4vql RAaCt0T "3.S YAxdmu RoatorQ Water iAVOl 3.3.18 LTI.P30. Reciroulation Svataa O4 To elu~t& tho raci#il~tAiu fjw 4p4 Pow: 1Y1 turips afLon ov bgth of ths cq;ircuLon ttaueteuts following To QbtOu rOCIrCU14t~qp sys pfamnio 4049 04vi4tiew To voztfy Oot up r4qf4q~t4u System po0£1p0'iw, will occur in th4 Qpe*14 :Oi4 Q 04 4uwiog the pr C MMn xi*11 be geatar thua L.

trip trauie at..

ZV-86 ZIMAL SUMfARY REPORT

ZYMP UNrr 2 3.0 Results (Continued) 3.3 Phase IV - PEr TestieR (Continued) 3.3.18 STI-10. Recirculstion Systeo (ContnucOd)

Criteria (Continued) level 2 for each pump trip teat, tho minimum transieat KCR based on operating data divided by the corresponding minimu trasient HC)FR evlu4ted from dotosa values is expected to be equal to or.pester than 1.t.

Rocrcuatton Syate pSTrmPA M ta was tOUan on the 50% flow pontrol Une At various mbinuattoA4 Of pump cpeeds as welt as At oacUand of th 75X 107 flow control line8. Perfoimance of the system wa. *attistBQ7oy at all conditions.

A test for cavitation La the iToroItiQR $Ist4m was performed on dt 501 flow control lito Iby erttn eon'2 trol rods in the roverse of the Pgkioall uo sequence "A",

while recirculation Pumps were mainta,104 at A speed to SWi apPra*Wttely 104 Hlb.o/b. total-core 19w. I1rtaelyltho recirculation pump runback was a;owuntarq4 At approxmiaotly

26. power. Tha tw*& eotpotat Wei 1oV9#*4 a48 V4g performed again, In this reca4t, the ToUzback w °qAQTpweVr4 at Approximately 22.51 power, lo izI4i4t00nF qE 4aVAtM N were seen Ig either test. During thtie ;o tttpu of th4 W-back 4etpolit,

pvyitattoi #*arih Wag p#trftMd doM to approximately 201 power, with tho fee4vateT runbac4 intat lock jumnpered. Ka cavitation opufw4q i#ptrq4stLon. pv~p t4ps wars ppforsmd at 507.,

74., gpd tQQ7 poWer Vith t0D7 flpV# bIy $Tpptng the pump drive motor . Single pump trips wqrp p Fos4 at SOX and 1001 power with 100% flpw by trIpping the dr4v motors, Ing ppp tip Vat perfP0pd At 501 power With 100% pOw by openin the generator fila braaler on pump 115,1S A tFan5qtpg 1ptmi fpttip$ 1 £pa;ruttp tK0iWK) *UaIysth l'

wa; 44ae OF tPQ 502 ;in t2P poWer tvP pUptrLp4, an4 (0 the I-pump trip initiated by opening thp gorptov f4914 breaker. The analysis was parfqMd pd QMg4appad4 tfv44a during the transient by using the off 1U* tWm 04ra Mt*

puter (BUCLE), Although paP required by ces; ;rit$OT4 transient minimum critical power ratio (O1CP) 4naly494 WOO parfozl4 FrT Af qSmu tosto as wore the RICER enqVyjs,#

-I

IV-B7 g FP U. UOMMARY REPORT - BNFP UNrT 2 3.0 Results (Continued) 3.3 PhW 3 LV S ower TestLnU (Continued) 3.3.18 STl-30. )Lecirculation System (Continued)

&Analysi (Cpntinued)

MCMR remained wall above the 1.05 limit during all analyzed transiento. )M(CR remained above 1.0 during all the transoents. This satisfies the level I criteria, The level two ctiterik requiring that the ratio of the minimum transient operating NOHYR divided by the vainimu transient HCHfR be greater than 1.0 was aatiasfactorily mat for all analyzed transients. At test condition 22

("507. power) the steady-state MCHP= was 4.10, while the predicted erperinental NHMM was 4.25 for the I-pump generator field breaker trip. The steady-state XCyi is a function of the rod patteran prior to the Initiation of the pump trip, mnd does not violate the criteria, MCWPR imediately began to rise in magnLtode during thq transi-oet and was above the predicted values during tha transi-ont, therefore the level 2 criteria were satisfactorily (7 'lat.

Figures STI 30-1 through STI 30-3 cqmpare plant paramster nd MCHJR, as calculated froq the trazsient traces and WUCIE, with the px*4icte4 behavior for kll analyzed trips. Tble Sri 30.-k sxhpw IW6PI M a4 HC behavior during the two pump trip fra 100I pqwr. This tast was the son; £i1ting casa, of the n=lyzqd trips.

C.

I I

MML S' D=Y REPOR'r - B,:T MUT62 .X 0 3.0 n tesults (Continued) 3.3 P)Ga~e T1t - Powar Tes:.inc (Continued).

3.3.18 lE.4: $

MT-30. g*circulation

. : . 4 . I .. . ,.. ..... ..i.

isVtem (Coatinued)

-~-~S~--Core Cr oe F10Wer

H::.

M:"--!-.T

-.t:.:

I

_I_ .i.. A - '.rive FloW A l3

t. 3 r ' .1.. Drive FloW Bti7D -..

7

, J_; II - .. ! .. . Generator Speed x~

1I:

1. 2l _- tn ! 1 _ 1_ _ ,,,HFR B: I.:... I l r22

.~~~~~~~~~~~~~~

@ .;.II-; .I. .

___0d1:71. -T_

.t .. I .

2i i..i ~....

I... 1*; -.f; I_1.

I0 :0 7!. O EE:; tI.z. :_ ... Mtml. r 82

-1 .

I a

6 3 U o , ; . .- ,.t . ,f .,,. . * .i..i . ... { A .. ... .i.

la 0

i6i 1411 i

1.d 0

~

O~~~~r-1-\1 ~ ~ ~

j..,. ~ ~ ~ ~ ~~. ... .... ..1:1.,.I';Il$li1i L_1 1.,i1'1

.,:................... .... ... .... .... .... .... .... tnl 5 r.

0 A T!

0 -Li* $,1 81 9 , ;. I .! ;: :'.:. FI. .. j.- ...

... 1. : -I I 0.4i

,X 14 b.

..t. t-.!-.-l1m,-r S.1.

0-r:m.21 ........... .. ..... .................. I .:..

!.;11

?

. I i -°--- --- . ..I. . .!.I. ..........

I.. } .; .. , l l; l l. l 4

0 .0 . ... ....' L :- 5,- l: . 'l. ;7:.l '1;:1 il51 ,l I , l 5l5i ,,illili..l I Ili'!.-. li511-..*s6 '..i.'is 15 fi WZ1.I150SUIe: I.;il W I1

p 1 g? 4 5 6 a 10 T~mfterGenrator Fiel Tri (Sacnd)

F~igurez STI 30-1 3293 Mt Pln Bedr & s yst Perforne ato. . .. . _ . ^ _._

FLSVW 4 ARY RMW~ - KWN US~t 2 3.0 P1eaults (,oatLizao) -__

3.3 Ph...s. r - Paor Testint (Continued) 3.3.18 STI-30. Recirculation System (Continued)

I T

VS1

1 0-4 0

'a "d i, I. 0-I lad :0 0

'-4 A %0 I1 I

0 *1 2 3 4 5 6 7 8 9 I TIME AFTER PUTW TRIPS (SECOND$)

Figure STI 30-2 3293 HIt Plant Recircu1ltiu System Performance Following Trip of Two Drive Motors - 502 Power

F NA'7 Z' ^m*%: ;-- - :T17N -_ 2 3.0 Z._:s v;:: _

3. 3.1: 'utin (Conts . md )

1 1.43 . ..... ........... ... -.-.-.

~~~..-.- _ ..._............. .-....... ... .......0

-- _':.----------ore Flow X

. ..~ ... ........ -. r.veF 1 . .

Generator Spee 1.2=-;_;;;~~~~~~

_ :.:.;. ;.. -. ... j- ;M:. ......

1.ls - .. i. -. *I_ . -.. *- r£-!" i s9jj j-jjj ;sj i.- *.c*w . -l,-H j ' :'1jtj FR s s 2

n a-s -44 C

%A.

C 0 la r- I-04 30 TIME AFTER PUlkP TRIPS (SECONDS)

Flgare STI 30-3 3293 Nut Plant Recirculation System Performance Following Trip of Two Drive Motors - 1001 Power

IV-91 r- VIlRAL

SUMMARY

REPORT - BW M 3.0 Results (Continted) 3.3 Ph~aa IV - Lowe Testing (Continued) 3.3.18 ITI-S0. becitculatiom eyateam (Coutiuiued)

Tale STI 3Q-1 Transient KCMR and4 Mc Two Pumg TrlP Time Uter fargfn Waitn Trip MCPR to 1.05 mom to 1.0 (See.) value Linit PhF Value Value Y/P 0 1.257 0.207 P 2.63 1.65 P 1 1.251 .201 P 2.64 1.64 P 2 1.223 .173 P 2.63 1.63 P 3 1.188 .138 P 2.67 1.67 P 4 1.116 .066 P 2.77 1.77 P 5 1.180 .130 P 2.96 1.96 P 6 1.lB5 .135 P 3.14 2.14 P 7 1.189 .139 P 3.33 2.33 P 8 1.214 .164 P 3.60 2.60 P 9 1.222 .172 P 3.76 2.76 P t0 1.241 .191 P 3.96 2.96 P 3.3.29 8TI-31. Loss of Turbine Genarator and OE.ite Paowr To kavestigato the mectot tmazuient peaforance during the lose of the main generator and all, qf fut power.

to dmonstrate the acceptable ParfO of the station electrical supply sypteM during tM lox* of the main generator ad all offEit. ponw.

Criteria (a) goactor prasmure ula,1 be maintained below 1230 pstgs the uatpoWt of the fgrst safety valve, 4uriag the transient.

(b) 1.1 safety systems, such " the WeaqtOr pro90 tection system, RCICHPCI, and diesel generators, must function properly without mnuxal assstance.'

I I - -

IV-92 FM SVMAY REPORT - BOM~ EnZ -2 3.0 Results (Continued) 3.3 Pbans; IV

oEr-Testina (Coutinued) 3.3.19 L-31. Lose of Wig$ Generator and Ofisit L4=e (Continued)

SLItell (Continued) ;1 (a) the maxfmum reactor pressure should be losse than 1190 pui, 40 psi balo the first safety valve oet.

paint. during the tralent. This pressure margiz shoulM prevent safety valve wseplq.

(b) NoMl reactor cooling systems should be able to maintaln adequate suppression pool wate. temperature, maintain adequate drywall cooling, and prevent actuation of the auto-depresaurization system.

The test was succegufully performed oa Septeber 8, 1974. The reactor was at 91%l% power with the main ganerato:

output at 277 NW. Prior to the test, the plant electrical system was aligned so that the only source of power to the 0 unit 2 auxiliaries was the unit 2 station service transformer and also, so that the test vould not affeot unit I. operation, Thte awiillsy elecctrtal ahut4oma system was alind so that only 4-kV shutdown board "C" was feeding from unit 2.

The unit 2 480 volt shutdown boards and motor operated valve boarda ware isolstea so that thaei sob source of power was 4-kV shutdown board IC", In this configuration, all unit end shutdown auxiliaries for unit 2 wee being fed from tha unit 2 main generator and could not be supplied by unit t or the plant ccomon electrical system*

The reactor was operating at steady-state, cOnVi4 tlans with normal fesdvator control for one reactor feed' water pump operation 8 when the tmarbia generator was trjpped by anual operation of tha generator negative phse*sequeone relay.

Raetor Response As antielpated9 the reactor screed due to con- A trol valve- fast closure when the turbipp tripppd. Tbh reactor feedwater pump tripped ixmadltplty due to the loss of NtSH which was gaused by the automatlc tripping of the condensate booster pumps , The reactor woter reclrculation pumps also trippedtmmdlately on undervoltage. U a .

1

XV-93 l VINUAL

SUMMARY

REPORT - BlNP UNIT 2 3.0 Results (Continued) 3.3 Phase TV - Power Testing (Continued) 3.3.19 8ST-31 .31oa- of Turblne Generator and Offaite tower (Continued) hag!ysis (Continued)

Reactor ResPonse (Continued)

Thirty seconds after the reactor scram, the reactor Isolated by MSIV closure due to the RPS X-C acts tripping on undervoltaga. The reactor water level continued to fall until the RCIC pump was manually started six Ln-utes after the scram. The water level at that tiup was 27 inches below normal operating level. The level dropped six more inches before the ZCIC pump began restoring cool-p ant inventory.

Peak reactor pressure (1084 pafg) was reached eight minutes after the scram when three relief valves automatically operated. At that time scram recovery opera-tions were initiated with reactor level and pressure con-trolled by RCIC and manual operation of relief valves.

During the turbine trip, reactor scram, and reactor isolation, the reactor parameters followed their expected Increasing and decreasing patternsa Drywoll and suppression pool temperatures and pressures remained essentially unchanged during the transient.

Electrical Response Following the main generator trip, the unit and reactor recirculation pump board feeder breakers Imeediately tripped on undervoltage, resulting in a loss of voltage to al1 unit and shutdown auxiliaries associated with unit 2.

4-ky shutdown board '"C automatically isolated itself S.4 seconds after the generator tripped and voltage was auto-matically restored 1.8 seconds later by diesel generator "C". All other automatic tripping and switching operations occurred in the time sequences expected.

3.3.20 STI-32. Rcirculation Sgeed Control and toad tollowiwa purpeym fo deterolne correct gain for optimm performance of individual recirculation loops.

C:

I M

IV-94 FINAL SEhAY REPORT -YN? WT 3.0 Results (Continued) 3.3 Paes TV - Prwer TastiMn (Continued) 5.3.10 §1I-32. jecirculetion 89eed Control and Load Followlyn (Cunt.)

purpose (Continued)

To determine that the recirculatiov loops are correctly oet up for desired speed range and for acceptable variations In loop-gain.

To demonstrate plant response to changes in recir-culation £low, To determine that the load following loop operates acceptably over the desired range of recirculation flow.

Criteria Ieve} I The decay ratio must be leoss than 1.0 for each process variable that exhibits oscillatory response to flow control changes.

0 Level 2 (a)The decay ratio should be less titan 0.25 for any process variable that exhibLts oscillatory response to 102 speed change inputs in local ox master manual modes.

(b) In automatic mode the flm control range limits will be set to include that portion of the total flow range over which the decay ratio is less tban 0.25.

(a) Steady-state limit cycles, if any exist, must aot cause turbine steam flom to vary in ecess of *0.3Z rated flow as measured by the gross generator elaotrical power output.

The recirculation flow control system ws set n

up during the Initial heatup for good stable operation.

grlsting diode type demodulators La the Sailey poeitioners:

wure replaced with a trausletorixed type and the slave driver remainad as a part of ths system. These unite were fine-tuned for maximum tracking ability and their perfor-mance won aceuptable. The initial settings of the system O

IV-95 FINAL SUMYART REPOR? - BPNP UNMT 2 3.0 Results (Cm=tLnued) 3.1 ::%.s IV - Power Testing (Continued)

S.3.20 ST1-32. Recirculation Speed Control and Toad Followins (Cont.)

Analysis (Continued) controllers were as follow.:

Loop "A" D10001 P.D. 15 R/'

Loop "I

1000 P.B. 15 KIh Master 2000 P.D. 2 RfM An power was increased to the various test condi-tions, it was noted that the two loops performed adequately, however some problems were encountered In that the two loops did not track each other as desired. More adjustment and sawe component replacement on the Bailey positionera improved this condition but never completely relieved it.

On the 100l flow control line at rated conditions, it was found that the *etting. on the system loop controllers must be changed to 2000X proportional band to maintain the

( rate of power change to less than 151 per minute on a larger step change in speed caocand (101). This meets the restric.

tions of the PCIMR. Under these conditions, all of the criteria of the test were met. The system response was stable but heavlly damped. The "A" loop did tend to drift a small amount under steady-state conditions but within the tolerance of the criteria. Representative results of test step changes for the Initial and final controller settings are shown in table STT 31-1.

The H-G set scoop tube poslitoner gain curves are shown In figure STI 32-1, It can be seen that the curves are slightly exponential which results in better speed con-trol capability.

The portion of the test which required operation In the automatic mode was not completed and was carried as an exception on the final teat report. Wls part of the test can not be accomplished until the Nuclear Safety laviaw Board approves the automatic mode of testing.

(

V,-96 MDIAL MURY IEPORt - ISn UNIT 2 3.0 Results (Continued) 3.3 Phase Iv- Power Testini (ContwLzud) 3.3.21 1 RecirculationlWdet)eedControl Ccoued)

Table SU 31-1 Representative Rasultm of Recitculation Controller Systems Teamt:I Test Plw Power Controller Total AP Rx fflux Condition Mlb/hr Ift Settings vli psi X step, X 1B=2000

.Master IE 104.5 1938 A P3.1000 -10 a -2.5 I PB-1000

_ _ B 1/AmiS 31 t9 2470 sam as Test Coad. 28 " -1 -3

_P12000 Waster 43 100 3262 -10 -_ -8

.B*2000 WHOM 0

_I

07m

SUMMARY

REPORT - BFM MUNT 2.

3.0 Results (Continued)

3.3 h I 1 (Continued) 3.3.20 WTI-32. Recirculatiot Sead Control and Load pollaeing (Continued)

I I I WI it lt f I II t i fsf S.i

-1AA I I .

IAt I

- I I _

1.

I - _- - - - --

I Y _

i_,:Hi-

.;iL>lI 1T111-j tire

, I -

I... .,4-...: LIA

... H . . -1

; : 1,

.I Z_.-,-r+---. --

Controller Output (ma)

(Input to Stoop Tube Positioner)

Fligure ST% 32-1

nV-ss FINAL SCHWWY REPORTr - IPP UNIT 2 3.0 Results (Continued) 3.3 Phase IV - Power Testint (Continued) 3.3.£1 571-33. Main Turbine Stop Valvo Serveillene, Tost Purpose The purpose of this test La to demonstrate acceptable procedures for the daily stop valve surveillasne pro-testing at a power level an high an possible without ducing a reactor scram.

Criteria Ilevel 1 Bot applicable.

Level 2 (a) Peak neutron flux must be at least 5Z below remain the scram trip setting. Peak vessel pressure must o high-pressure scram setting.

at least 20 psi below the (b) Peak steam flow In the vain steam lines must remain 10% below the high flow Isolation trip setting.

Analysis selected Turbine stop valves were closed individually at levels. The design of the main steam lines provides power large cross ties upstream of the stop valves, which prevent Table perturbations as a result of the atop valve closure.

the STI-33-1 summarixes ths test results. Included are peak greatest interest: Peak Mutron fluxt parameters of perturba-vessel pressure; and peak steam line flow. Sittle peaks the valve closures, and the tion was observed due to table STI 33-1 are not such different than on&would listed In steady state. STI-33 observe as background variation at demonstrated that the stop valve surveillance criteria test may be satl-test wer* met.

factorily performed at full pouer. All 0

771W. SUX~tRY MOM~ - IM! UMI 2 3.0 Pim~tle (Ccutinved) 3.3DMT Powe~.r TesŽ!R& (Cmtiuued) 3.3.21 STI 33 Madin Turbin~e St Valve Surve111mkee Test (COutivued)

Table 971 33-1 S MInmof 7wwbve, Stop Valve Closure Mata Reactor Power 252 59.5? 74.9? 99.U Peak, 1kutran Ylu 262 60.32 792 __________

flargin to L in t __ __ __ ____ __o%__ _ __ __ __ __ __

yeak essl Pteeawne 91.9 PSI 95 970 2gi 989 EdI peak Stea LIM Flow L.0eb 2.25~n 2. &Mb- .

Er Pr Br __ _ _ _

Ennto Uvdt 752 48? 402 iofot that; data deow mw Peaec va7gve at each test Zepe?. 2%ie mmvin to Umfte am' d.$vamd by the falowfng trip 1"wta:

Weutron Fnii - Dependst on peakinig factor set Ln Vessel Pressurs - 1055 posg Peak Stem flow - 140? rated flow., 4.7 M0b/lw

Iv-l00 FINAL 5MMRY REPORT - BYNIT 2 3.0 Results (Continued) k) 3.3 Phase TV - Power Testing (Continued) 3.3122 M-34. Vlbsation easurements Pupose-.':

The purpose of this tast Is to obtain vibration measurements on various reactor components to demonstrate ths mechanical integrity of the system to flow Induced vibrations and to check the validity and accuracy of the analytical vibration model.

Criteria Th vibration criteria, used to judge the results of the vibration measurements, is the pracalculated vibration amplitude at each seansor when the maximum stress in any one of the internal's structures or components equals 10,000 psi including stress concentration factors. This stress represents approximately one halt the stress liilt given In ASH! Code Section III for 40-year Uft. Because of their complexity the criteria are not presented here but will -4a evaluated by the CE vibration test engineer conducting the taSte.

Jlnalysis Vibration test data was taken in conjunction with the recirculation pump trips, one pump at a time and then both pumpa siultaneously, Theme tests ware conducted at 50, 75, and 100 percent power levals.

The General Electric Vibration 3peoialtst states that the vibration amplitudes are well within criteria U.imits. A final evaluation will be sade at a later date by the TVA central office staff or by an Independent consgltant-M

FAL 8MMRY RUMT - FNP WIT 2 3.0 Results (Continued)

.1 Pzhase IV- Power Tostin (Continued) 3.3.23 911-35g Reirculation SLaUM Flow Calibration Purposs The purpose of this test Is to perform a complete calibration of the Installed recirculation system flow instrumentation.

Criteria Level I Not applicable.

Lavel 2 (a) Jet pump flow Instrumentatton shall be adjuated such that the jet pump total floaw reorder wil provide a correct core flouW.ndicatton. at rated conditions.

(b) The hIN/IZ ftowbisa AnstruantAttntz shall be adjusted to function properly at rated conditions.

nalvuis Racirculatton 6y7teu flow data wse taken on the 5OZ 751, and lO0X flow control Una.. ledmdat data was taken at each test condition end calculetionu were =4 on each set, atiliaing the vendors' comPutor aytem (JPUWPS and RMPUPS prograna). The reaulta wVe analysed at each test condStion; howewvr Lgt.v4 uot npgassaiy to make any instrument adjustments until ate4 cn4ittonu wvore attained. At this point the data analysis revaed thit thQ indicated recirculation flow was approwimately JQX hiAO than calculated Values. Nov flow nUazia coefftoienta WV.

determined basso on the caloautae vaves of flow UsuxR 9um chIractertstisu. Proa the nw nosale cost fiwinte, 5 am flow transmitter calibration range was detormtns4.

Final caibration ofth cr ow m wiftea nx spce-s was based on the date taken at rated anIitioPs . CompUOR of the double tap jet pump flow vith the *eisn1 tap jt puoP flows slow that they mrs within apprpoubtoly U of 04b ahtv:,

ft a4dition, the -ratios acrc wit~un Oe bond of # 0tP4 theoretical values. The gin adjustant L4ntor 4Pn th-as-left ains are ts followst

.1-0

P1-102 FWEAL SUQARiTRERT - B71 11211?I2 3.0 Rout (Continued) 3*3 PhaseLtVV- LLwr L~singi (Continued) 3.3.23 STZ35, Recirculation System Zlow VAlISrTSOB (Coatlaued)

Analysis (Coutinuad)

Inatruasut 04an Adjustment An lieft Imp mAMSSUUL A 1.041 0.5205 a 1.04 0.52 The APMR)I/R) flow bias iustnw'muatation was fowid to perform it.function adequately at rated conditions*

IROWAvar an unresolve4 problem was oncountc:.d ft this area. It was found that a non-41uea~1ty exists betwoan the raoirculat$on flaw (drive glow) and the cote fMm vhitch causes prawature rod-Mockmi at low powev levlel. The (law bian instrumntationto,~S Set up at rated candit lonot Uhou the flava are reduceds the nonw14neevity causes the 4ilve flow to decrease at a faster rate than the core flows creatino a rod-bloc%~ condition. The, problex Uas not 4been solved at this n.". kovevers the vendor hasi PTOPive. a notution and to prasoutly wm4srgoin vlain

.noevauato0

'V-103 FINAL SI Y REPORT - 8PP UN:S 2 3.0 Results (Coitlnued)

Mes TV Lm TetC (COntilhumd) ',

3.3.24 STK.72. Drill Atmospherfe 6oollail 8Iuate The juse oU6thie teot evCtiy t0e 4141ty 2 of tb4 dM6l1 40108PUr4 4001114 47501 tO VAIM010,.:

desin condLttions 1 the drpoll 4ulr opetattus candittia".

' Nbn*#

(a) The b6t TronVul 0pabtlttf Of the doVM11

. coolit omhil To opptmy4uAte1y S,9 X \ Stu/hw.

(b) ThM dr U goq1tag gyotim thaet bt*tv at^4dby j ( 4ZapabtJ12ty of >~35S the 4,.p boat Wr~i4^ qBp a U~tv.

C()The dry t coooing oete,. design hall vaInt4ta e

-tvTp Ii the dimvU boiw he fo2Io0wS0 v&u* 4'avlrs gpim oporattoiI.

JTlaaagml ftasctoy 0UtlI;

'13S5 V. (57' CJ ) asva . itb Vdwout 4fwf-

.. '50 4tv bui14 AX91lM the nTocia PV ,

'. ):89 it 019*" go) "2da

1

'US'1 Ft (fill O) "40s" ao4t' the U11whe" I tburs After thutdogW M ISOuwe (8,3' C,) of 01PRo^ qQ0149R.

V~tfl ~t #tP~R'tVC IA RU *TeSe bsM*th the v^uss.to!twpgll bu14lbd, .

U -MM

ZV-104 FINAL SnKMARY REPORT - BPNP UNIT 2 3.0 Results (Continued) 3,3 Phase TV. Power TdstiejU (Continued) 3.3.24 LTI-72. Drywall AteosphePIc Coolian Oysteim (Continued)

Critera (Continued)

Cooling Water SOpplyt Uniform Circumfoeisuttel ;emperature at WJhitt~ thel Refueling DaollowsnBulkad Asnsm H1 ut La

. Anlaalnedt

Within 25 P. maximum point-to-point variation Analysis At .002 power a1. points within the drywall wet the 1SQ' P. maximum cepereture Criteria with the exception of TE-80-13 and TE-S0-14. The avorale drywall temperature van 124' 7. It alould be noted that RUCM temperature into the drywatl vas 83.4' P, It to expe4ted that the Inlet temparature of RUC Into the drywall will approach lOS' T, during the sunmar months. At these conditions it in doubtful that dryuatt te"p#rst;re4 waoud meat design criteria.

BED will evaluate and resolve thU problem.

The drywell heat loa4 was measured to be 6,11 x 106 Btu/hr at 100% pover, Thin coampres favorably with the design heat loa4 at 6,09 X 106 Btu/hr with the drywall ausp pump cooler out of service.

Date vas taken before and after one of the fult power scravs to ittustrato the ability of the RBCCV nystea to handle scram heat loads, Although at tan hours after the scram the average drywell temperature had act decreased to within 15' P. of bhe BBCCW tote% temperaturea only a cooling coafs and fans ware in servie -during thit time, Ten coils an4 fans ware placed in oparitt# n and the temperature decreased to wsthin 15S F. of the RIUWCW inlet temperature,

,I

, FINAL BiJMAMIR RWORT -BnIP UNtT I 3.0 Resultm (Continued) 3.3 l- Ws Vov~erseli (Continued)

3.5.25 SI-73. Caoliua water 523teuB The 5purpoIs of this test to to verity that the performeauc of the reactor bufldiug coseid codIluIR vate:

(RDccu syateD La adequate, F level I Von&

(a) Verification that the platex perform'ance meWl the cooling requiirements constUituts satisfacotry comu'je iCR of this test.

(b Ri'sCW woo dodlimod tip trsitofor m~a 1W5 -

load of 313 x 106 Iltus/r to ardor to ji4it sI114~ppot iLOU1~

vtrtoinparoturo to lO00 u' it -4paii~R a ott~i~e (i;sv goog~ig) iitet LAW vmerstuva Pt 09~ Fe Tho hean land as mepawrOd a ths RPMV dolb #1A*

loAd on thpe~p pppl toolhet -- th-S-re. the RaCV p ewohannsv Imit venufor rate wuld 4a vWt4n 32 of the Oaa4Ra valve of 31t3 x t0 144thrt NOu to atoept.a tp UU4P ae IMOM V SOP IrA 4419 ofthedrpol p ente itfp vtek usk~4%iw §Ms e v p 'oe4nvet dv~nedov tlVAI Joprtr teupeRutur WM' flw,14 rvef fl ewu Ts ofO 0tfuI dMf tT oM.tp' A Moitmo4Ors-~ 4 9115VST I

v-i P JMMUR REPJ - 5?NP UNIT 2 3.0 Results (Continued) 3.4 Phase V- arranM Tests 3.4.1. OT*9?R EleUtricstA..Atut ..

and ftel tt Feat Ratei--

mhe purpose of ths test Is to demonstrate that th requirements of t - pose electrical output warvanty e satifpod wethout exceedingzeetor r level warranty.

of 3292 )0t and to demonstrate the not plant beat rato.

Citeria, level 1 (a) The demonstrated gross electrical output must be greter tho or squ4 t.o-1098.4 Wq-at rste4.

conditions* -J Cb) The reactor power laewl oust be equal to ot less than 3293 HWt at a gross eoletdci4 ouput. of.

1098.4 WeeW (a) The tet plant he4t rate must be equal to or.

less than 10359 BtulkWh at a reactor pmrjlvel qual to or less than 3293 thebrmi mewgavtte.

Analnsis Tout results Fa s arw.Ax intpal~q BTI ZO-,s, vhch show thnt J$vy 1 qr1tqrAx (b) -AMd. Co) war Utiad-Qviterion (a)was satit.fft4. exo c k t-otav.r b 1e .w;,

raduotton ep ~QUlpvs... This br1qf tra"pio4 t wts otuo consaquece to the dowansatiron¢ of gross.41*4tia4 6quration. -;

Date Time Interval Cause 3/6/75 0310 - 2100 PatIa muantQI t flow.

o4vnr caugg4 by-d4 pump trip. Powe.:

was :qduosd to 70w-I.,

I

V-2 JI FTINAL SIICAY REPORT - BPNP UNIT 2 3.0 Results (Continued) I-3.4 Ph.se V - VarrPnt Testa 3.4.1 SsT-20. U ectrteal OutPut and PrelimInary Vlat Rate Table STI 20-1 ULecttLcal Output and Meat Rate test Teat Intervml 300 Er (IJ Corrected gross electrical output at 1114.2(2) generator terminals COM)

Assumed auxiliary load (coutractural-M#W) 24.4 Net generator output (KWe) 1089.8 Core thermal output (Ot) 327?

Not Plant Seat Rate (Btu/k'h) 10262 C

Net Plant EffiSciency (2) 33.26 (1) Aming the J00-how wmntj intemlrVc, on *inweqstia paw vduatie oaorwd.;

COveOHiMa0 42 OaWuIe 4.0t XM meter 1'e fo, tq Mah I9Aee va the OrmoP asuasred on the ientMoaZ unit I imtaRatQi*on o Sd by voleag, tme r48 II oa the fOtIiO*s deVfanatin fr rated turbioenert0V Warranty Condition Aotu 2 Condenser Lckpresuure (in Pfg abs) 1.47 t.

Poaer Pactor (mnitless) .9996 0.9 Cenrator Stator Coolant Pressure (pais) 49.44 55

(

v t e Letter Sequence Other
TAC:MC3812, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request Acceptance, Acceptance, Acceptance Supplement, Supplement, Supplement Administration Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting Questions 19 September 2006 29 December 2004 30 December 2004 6 January 2005 3 October 2005 3 October 2005 22 December 2005 22 December 2005 19 January 2006 7 March 2006 25 May 2006 2 June 2006 26 June 2006 26 June 2006 19 July 2006 19 July 2006 8 August 2006 10 August 2006 7 August 2006 10 August 2006 1 September 2006 6 September 2006 1 September 2006 15 September 2006 21 September 2006 27 September 2006 20 December 2006 17 November 2006 17 November 2006 26 January 2007 Answers 28 February 2006 28 February 2006 23 March 2006 23 March 2006 31 March 2006 19 October 2006 Results Approval, Approval, Approval Other: ML041980222, ML042370100, ML050590036, ML051150191, ML051160036, ML051320148, ML051430036, ML051570381, ML051660602, ML052290397, ML060530185, ML060670304, ML060680586, ML060680590, ML060680596, ML060680599, ML060720253, ML060720272, ML060720273, ML060720281, ML060720293, ML060720295, ML060720298, ML060720303, ML060720354, ML060880464, ML060880469, ML061040217, ML061660002, ML061770163, ML061840027, ML061910705, ML062050056, ML062090482, ML062090555, ML062120411, ML062130163, ML062130343, ML062200277, ML062210102, ML062220647, ML062270240, ML062360160, ML062400472, ML062510022, ML062510371, ML062510374, ML062510382, ML062510385, ML062620064... further results
MONTHYEAR2005-02-28 [Table View]

ML060720253

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