ML20085H335

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Monthly Operating Rept for May 1965 for Saxton Nuclear Experimental Corp
ML20085H335
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 05/31/1965
From:
SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110280238
Download: ML20085H335 (7)
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S AXTO'l IRICU%R EXPERIMEllTAL CORPORATION OPE!MTING STATISTICS HONTil IbY YEAR 1965 NUCpgR Ul!1T MONTH YFJdt TO DATE TDES CRITICAL NO. 0 0 377 110URS CRITICAL HRS. 0 514.4 11 457.63 NO. 0 1 217 T11tES SCRA)'JED (MANUAL)

N O. 0 0 25 0 TIPE QCRA!DG (IllADVERTAllT)

THMd%L POJER GENEluTION 10lH 0 9,497.62 187,763 44 AVERAGE BJRNUP 10lDMTU 0 454 51 8,457 00 CONTROL R0D PCGITIONS AT U;D OF !!0 NTH AT QUILIBRIUM PCMER OF 0 , }&lt

} MIN COOLANT BORON 1049 pa{

RODS OUT - INCHES **

No.1 NO. 2 NO. 3 NO. 4 -

No. 5 -

No. 6 -

ELECTRICAL UNIT MONTH YEAR TO DATE GROSS ODiERATION FMH 0 1,595.00 31,241.00 STATION SERVICE )MI 66.41 560.29 7,091.85 STATION SERVICE  % -

35.13 22.70 l AVG. PUJiT EFFICIB10Y - IGul(e)AMl(t)  % 0, 16.79 16.69 AVG. GENEl% TION RUNNING ( liRS) IN O 3,103.11 3,313,37

! PIANT IDAD FACTOR -

(AVG. GEN. -FOR 110NTHAMX. IDAD)  % 0 12.43 25 86 l

! AUXILIARY STEAM SUPPLY - NUCLEAR STF/Ji SUPPLIED BY REACTOR HRS. 0 514.00 8,569.82 RWDF EVAP0MTOR OPERATIOil HRS. 0 0 15,588.00 l

0 RDIAMS;

" No operati or rescLor duriud the raonth of Hay due to the cleanup of the super-cri+ 1 cal loop t.ud fuel h oidling.

9110290233 910424 PDR FOIA PDR DEKOK91-17

. S!JE0 dperativa Report for ISy No $ . ._._ . . .- . //4 l 1

L . : n t i on pon nedt.ntion lla # dita 0.V.

Operatini: Dec); 1000 d/m/tmcar beta-canna Heactor Deck 189000 d/m/tmear beta-garna  ;

Prinary Compartnent (lower) 1310 d/m/ smear betta-gena  !

Prinaq' Com}artnent (lower) 22% d/m/cmear beta-ctu.a ,

Auxiliary Com) ir' mmt (lower) 3720 d/m/cmear beta-Cena 1.dquid and gaseous effluents fran the SIEC site for the month of P.ay 1965 were ne folleus '

(Curie) (Curie) (Curie)

Activity Activity Activity ,

Effluen Tyre Tnis lionth Yent t o Dat e Lut h3ve !!onthy; Liquid 0.000059 0.004368 0.010051 Air, Xe 0.0CC000 10.826235 48.0571')2 Air, I-131 0.000000- 0.000273 0.000825 4;. r , l' . F . P . 0.000000 0.674512 0.108263 Tnere was no waste drunned for teaporary storage and no waste was shipped from the cite.

Radiatica erosure for all S!!EO personnei as measured by film badges for the month of April,1965 were a mee:imum of 275 mrem with an average of 20.4 mrer.,

haciation exposure for till visi'.ing personnel i'ncluding persons working on j the supercriucal test loop as measured by film badgen for the month of April,19o5 were a maximxa of 460 mrea with an average of 44.7 tram.

Tae radiation exposure average for all personnel as measured by film badges for the month of April,1965 was 37.6 mrem.

I  :

4 9 -

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+r-- v v * - es *c oww se m-em,ur we e va-tre T-t-m+- - -' ewew y ww &,w+v w-, c w m- ..m ==--r w w ,w.,~m,.%+=ww--,-ee &% , w e -,-erm,,g---eyn we ww e +- -m-'yar-e--tw+w'v-wwm-=1***=t'w'ra

f>NEC verati$ . dej e t ise j thy 14M , . . . . g._ty 4

7:n n .pr it e 0 of olectrical nM nt ervinn in A. ed rep. e nl* ine U-f: tune I

- used ha n detector ulth one vf tW count roon seslers; reecnnecting the power hads l te 4 1 ; ornge .. ell ; r.p; r y a . r a n t, t ht: s:Litr whic!.is us% uitn tia ref Nlj bf) in .t.

the containacn; vescel; replacAng n pil cell in the water areatucnt pH !acter; repniring i the solu-briace on the water trent:.ent chuttle Mi:Ong tun .; checLnd cot. trol circuit l for au::dlinry crete", return val.ve li10-27V; replacing the cablee cn the head bolt i Leater; ;,anel; :alib:atinc prescuri;er level indicsting caannel LIC-2; r epa 3 r nc a portable beth-cn:r.n eurvey neter; arr.1.*cpairing the presc1riter heater eltetrial connectora.

Tne prerez rcr heater connectors were repnited by silver solder:nc the pine c: the :.a inf er the connector to '.ne partial 3y cut auny receptn:les in the

fetaale :annt:ter; (n;n ecnnector was then p tted uith a c;11:vnt rutber compsund.

i Ten aca DPS-9 :nble: wo r t, used. All pres;urizer beaters were ccnnucted for t.ervice exeyt two. One cf t he two is not repairable. The other will be used ne a spare.

5. Em!ST iY 9

Ine nain t oelnnt tyrten re aned in a cold shutdova condition throughout -

the ms.ith. Tne cht.tuown ecol ng ryste. wan in operution for removing recidual hcat j and canpl$ng, a twa.nry cf the andyses of camples taken from the snutdcun cooling ,

j system curiv ine nm.th are tabulatcd belcws  !

Sr'n down Coa b r 04 u + V u.i n n -

!bxinum t

pli 5.?? 6.25 i Jxductivit y, unhoe 4.12 14.6

%
a., pp' 744 1070
unierides, plc .005 005 l Potatriun, 9;r 0.4 0.7

'.itL'uu, prb 40 40 Sou:um, ppa 1.0 1.0 .

Jrm a t.n-Jur.n,15 Min. (degassed) ue/et, 2.0x10'3 2.57x10 ',

{

Inc decrente in hetivity in the nun coolant syctto was the recult of flooding the st.orage well t,cVeral tines during the month. An increase in the storage well a ctivity iron C.2 x 10-> to 5.2 x IC-4 ue/cc was experienced for the sanc period. T:.e cartridges in the storage well systea pre-filter were replaced. . A big ,

improvaner.t in the turbidity of the storace well unter was experienced due to a

, reduction in suspended colids which were 1.watly iron.

6. ItDIATION A"D UAS?E DISPOSAL Radiation curveying conciated of routine plant cite curveye, WDF, C.V.

(during fuel transfer, hela renoVal, and constructien) and fuel cask receipt and shipment. The following nLxinun readinge were taken:

Lxntion Radiation' Reading CSA Dutidig 4 Charging ftmp (conthet with chanber) 20 mrem /hr beta-gamma Sample Rcom (door of ste.ple panel) 10 urem/br beta-camma Can=ical lab flot, sink (1" fron drain) 0,8 neem /hr beta-gama Wate Drum 3.0 mren/hr bet,a .gama i

- - - - - . - - , , . ~ w , , . - - , - - . , , . , , - .,.-~.nn __n .,n_.,n-,-,n+.,m,,,._.-.--rvn--. _

,nw,-_,-nm,,,,-

t

. Gui.C 0,+ rat an ihT m foV ltw 194 .. . . _.a 70 l

l lo e n t,i on h olutino Ibe rg I.ES2f Evaporator (unde botton) 150 mrem /nr beta-gtmaa Evaporhter (centcet cutcide upper icvel) 12 nren/nr beta ~gt.nraa 1

Drum Storage Area (at HRA fence) 22 tarc ./hr beta-gama

-C.V. ,

3 Operatine, Deci: (over wen ) 20nren/nrbeta-gar.rm  ;

heacter Dech (at ailstruntnt perts) t'0 mrem /nr beta-gamma  ;

hen;te Dr.'h (ce" tact crating) ,!. uren/nr bet a-crena i Reacto. hm: (waist level) l'/ mrm/cr bota-cartma Primary Ccmpartner.L (S.G. bot tem) 20 mreta 'br beta..cannt t Prinary Compartment (pressuriner bottom) 20 rares/nr beta-cNr a Priury Compartner.t (!N pw.p volute) 35 nrm /hr bet.a-gh..a Prinary Compartncnt ( 13 mren/nr beta-c ena .

Pr r. cry Cou;.a2 inent (general upper lovel) regen.10l) 26 mrem /hr beta-cura Prjrary Compart:.cnt (ncn-regen. HX) 2.0nrcn/arbeta-gn:e.a Primary Compart:aent (general lower level) is trem/hr beta-g m A Aui21ary Equiprunt Conpartment (S.C.H.X.) 17 mrem /hr beta-carna k.s.111 cry Laut 2cr.t Compartment (D.T. top) O mrcm/hr beta-gema Aux 11.ary Equipment Conpartment (D.T. bottem) /.4 mrem /hr beta-gn:ma auxi.liary ihuipment Compt. (general lower level) 2 mrem /hr beta-gamma Fael WAu; '

Atraval dith Spent Fuel (contact) 2.5 mrem /hr beta-ganen Shipping b'ith No Fuel (contact) 2.5 mrem /nr beta-garna -

} tollaneou e

}

Reneter Vess i Head after Renoval from Vessel' (on storace pad) (at por s) 25 mres/hr beta-gamma nonctor Vessel Head after Removal from Vessel (cn storage pad) (under head) 50 mrem /nr beta-gamma ,

Reacter Deck (6" cver vecsel H2O with-head removed) 600 mrem /hr beta-gamma Pu239 Fu n Shipping Cach (contact) 0.5 mrem /hr beta-garna

~

Contamination surveying consisted of routine plant site surveys, survey s of fuel cask or, roccipt and chipment, C.V. during shutdown and tools used during constr ction. Tne c3 ean and cont rolled areas were generally within the " Clean Area" limite with the exception of pomanent. exclusion areas. All areas were cleaned period;cally, w2 thin practical linitutior.s, to nis.1 mice the amount of smearable conteanaticn. The following contaminrttion readings were takent I

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-m._--.,,--m-. . - - - - -,- ,,,,-,-,_,. - .,m - -r..m..~,--,,._,-._..~.m- -...c.,,,,,w.,,,,m-_,

__ - ~_ _ _ _ _ - _ . _ _. - ._. -

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o- U.XM IWdISH EXPLlW:DlTAL CO:d'OM PIO!! p -u 4 g(..

,e 0;wration HanoH. flcr thy 19t4 /

u/ 6 ". N o,Li 6' .'

, / ,,,.jf.,

n -

1, gmu

.pu ut w A

s. ,

Tne ;lant outage which was begun on January 22, 1965 wac continued throucaout tais re it ; oriod, Fa fSO h ad 1:v. 123, which had previously been in the reactor in Subacscmbly i ik. SC 3-L 23 was returned ic the cite in the spent fuel si.ippitt: cask fran the Vert;n :houde Pct.; Irranatwn Facility, and was inserted in Sut'assenbly 16 503.4-25.

(

On Iby 5th unile Sabascenb3y No. f03-4 ' was beint' transferred from the periph.eral :cre pa _d cn 1;-5 to the center core position N-1, the bottau ; ortion of the pe/ferated wrager or. tae subasu.nb3y became caught en the upper end 1,lat e of tre

.cnter h9 f t el au : ;c . 41 efferts to free the subasecably were without success.

Finall, or. May 11tn, a te nach fle.dnc, the perforated urapper Iarted at a ocetion just twicu the fu rt support grid from the top. When the top portion of the subatsmbly was renoved from the reactor vessel, en3y one fuel rod anJ a f2ux wire t hi::.bl e e tc.e .r. . h it . A rect or vencel h(ad renoval was made neeensary in order to r<nove tne renaining seven fue3 rods and the botten portien of the tubascenbly s tru c t .re. Tnese were rc;crea en May 20th.

was ;o;41ct.t.d on R:.;. 30th.

lleinctallatwa cf tue reactor vescel head On May ? u SabarcenMy Nc. 503-4-26 var received. Thir subarecmbly conttur.s cirht rods of ni;:ed FC 2-U3; fue2. Four of the redo contain pelleticed fuel a:.d in !cc cf ine rods the fuel it ut rat ory compaet td. The phtenium c.ri W cnt is t.6 u/o PaOp.

' . E:G'ERIl2:W.L Pn0TbM '

Tnc cleanup worr; on the capereritic,al technology test loop uns completed.

Mcd,faattons tc the "Telerlex" rycten were completed.

Tnis e ,uipv:a Tne inctallation of trancictoriced nuclear instrumentation was completed.

cannnting of a source range channel, an int emediate rance channel and a ;cuer rr.nge channel will be tested under actual operatang conditions.

3. OP'itATICNAL TESTE Ine radiatacn more toring system circuits were tested on May 28, 1965.
4. [iAIImC;A :q The principl itema of neehanical naintennnce during the uonth included rer.or ng and reinstalling the reactor vercel head; reaoving stuck and damaged sabasse::.cly Jio. 503-4-1 frota the reactor vessel; unloading fuel rod No.123 from tne epent fuel shirping cask; pinting component cooling system piping; repairing the couplir.t, en the ve.:uun p=p of radiat. ion monitoring cybten channel itIC-9 replacing the diaphracn on the vacuun regulating valve of L'DF gas comprescor; No. 2; cleaning the check valves in the inlet and discharge lines of both- K.(DF gas j.

u.rgrersort;-pinting the reactor vessel head and head bolt can; replacing the belt cn the :cnt.aintr.ent vest.c3 air nixing fan; reinntalling the filtere in containment vetael : 1r handlerc; and ;.laring the st.oragc well systen filters.

4 a

a. - w - o w .. .

.-,-r--<,,,7--wy--.r-y,y-w,.-,wg, ~ . , y .s % e,u,,y-99,-.-y,-.,--,r.,.y-,3-my+ ,--,,,,r,,,,g,y,y.,~,w,-, = -e+ r p rie,2 -ae,i-e.g.=,,w,-q,,, qye-gs-ew-.v= - -wm m-= ( -

l o MbC 4erai wo Nyert for

}Sy 19ss . . . . . . t in t

In c a '.it.n 4Aintion budits M

Evaporator (under botto:a) 150 nrem/t4r beta-ca:r.ma  ;

1;vaporator (centact cutcide upper level) 12 mren/nr bet-d. gena  ;

Drum Storage Area (at HRA fence) 22 mre 1/hr be -gura C.V.

! Operating Decn (over well) 20 nren/nr beta-gtcma hencter Dech (at utstruncnt ports) t'0 trem/hr beta.*danna ha; tor Do & (cetact gruting) 1.0 nrem/nr bet a-grana

leac to: bc r (vaist level) 17 mrem /Lv beta-catuna -

Prm.ary Ccnpartnent (S.G.botton) 10 mrcra 'br beta.. grana Primr;. Com;>artment (pressuricer bottom) 20 tarem/nr bet.u-ca. n Pri':.ary 'capartnent (MC ye.p solute)- 35 mrea/br beta-(;t ..u Prircry Conpartnent (cencral upper level) 15 mrem /nr beta-gamran Pr.r.ary Ca:.pc.i tr.cnt (recen. HX) 28 mrem /hr beta.. carra Trnary Compar2.cnt (tan-regen. HX)_ 4C mrem /nr beta-ca:c.a Pricary Cc.mpartment (general lower level) 10 mren/hr beta-gam:aa

. Auiliar;- Equi; cent Compartment (S.C.H.X.) 17 nrem/hr beta-greca Awliary Equip;ent Compartncnt (D.T. top) 8 mrcm/hr beta-gamma Ao:11.nry Equipnent Conprtment (l?.T. bottcm) 44 mecm/hr beta-carrn Amliary Equipment Conpt. (general icwer isvel) 2 mrem /hr beth-gamma Fm %, -

i Arrf.vai . lith Spent Fuel ( entact) 2 5 mrem /hr beta-gamma Shipping Uith Ho Ftal (contact) ' 2.5 mram/nr beta-gar:rna F1 r ellar.ecu Ret.etcr Vesse'. Head af ter Removal free Vessel (on rtorace pad) (at perte) 25 mrem /hr beta-gamraa Reactor Vessel Head after h coval from Vessel

(en ctorage pad) (under head) 50 mrem /nr beta-gamma l

Reacter Deck (6" cver vessel H2O with head r emove:1) 600 mrem /hr beta-gruama l Pu239 Fuel Shipping Casn (contact) 0.5mren/hrbeta-camma I

Contam1nt. tion surveying consisted of routine plant site surveys, surveys of-fuel cask on receli t and chipaent, C.V. during shutdown and tools used during .

c onstraction. Tne cican and controlled areas were generally within the Clean Area" -

linits with the exception of portaanent. exclusion areas. All areas were cleaned perioC cally, wa thin practical lim Lations, to minimite the amount of smearable contaminaticn. The following contrennation readings were taken:

mes v4,- -

_.--ea=w-ewe---w.e-.+-r,.,..w<a w w-., ---*---r-r, -

.w*-g-vp,c.w-, , , , r-* ~ g y-em y y-g -we ,yy

  • y rr gs-,wm % y -- g-y-rrg,y, ev y m -ysw,wwwe- wy=ng= y,

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