ML20126E020

Operation Rept 18 for June 1962

ML20126E020
Person / Time
Site:	Yankee Rowe
Issue date:	06/30/1962
From:	YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML19284B310	List: IA-92-403, Final Response to FOIA Request for Documents.Forwards Documents Listed in App a Which Are Being Made Available in PDR ML19284B309 ML19284B311 ML19284B316 ML20126E004 ML20126E020 ML20127H449
References
FOIA-92-403 NUDOCS 8011120363
Download: ML20126E020 (12)

Text

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i YA!OIE NUCIIAR KT<ER STATION f

OPERATION REPORT NO. 18 For the month of JUNE 1962

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Submitted by YANKEE ATOMIC EIECTRIC COMPANY Boston-Massachusetts July 20, 1962

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,a inic report covers the-operation of the Yankee Atonic -lectric i

"e :Eny.lc.nt at itcve, Massachusetts for the nonth of June 1902.

I

• i tnc teginnin; of the period the reactor was in a ccid, depressur-l

< d and r e m t d condition with preparations continuire fcr ',he actual reactor -

.. clin >.

<r:n June 1 to June 5 prinary plcat activitica.. ~c centered on

t. ira in-:cre instrunentation connections at the reacter nu u, r = vin; the m.r.1r.irg centr;l rod orive nochanisn coil stacl:c, cleanin; tc; sr.icld ta:.,:

tavity and eneching out tac operation of the fuel handlin; sy::ter.

Followir.g utse operations the pressurizer water level was lowered and the renairdng reactor vessel head closure nuts and studs ucre renoved.

Cn.'une 6, the reactor head was lifted and boratec.::..

i:. - i r re-d::cd into the chield tarG: cavity. The head was renoved fror ;*m v..er con-

..tner tnrou;n the equipnent hatch, vrapped in a plactic cav r:.; :.nd plaecd en a flat car fcr tenporary storage during the reacter refur.lin;.

'ollowir.; the head renoval, the core hc1d down p r.'.e, c':ntrol roc dr h v s.iaf t s seid centrol rod thinbles were rer.oved.

On June 13, preparations were made to lift the upper core support barrel and in-core instrunentation eggerate. At this point the unde water

'.~.7. cancra vos found to be inoperative and interference between the upper c re tarrel liftire rig and the instrunentation eggerate was detected. A delay cf appro:cinately two da;,s was incur red while these di"#iculties were t:.::en care of.

F.cocir of a defective cable connecter restored the T. !. cre. ora t.o c: ration while the lif ting rig interference was elininatei.:y ;ri din; five clets in the ir.ner circunference so as to provide adequcte elecrance.

~ n <.ur.c 1h, the upper core support barrel and in-co n ins.r.r "nt;.tf on re fi.ed fren the reactor vessel fo lovin:; whic:. sp nt futi :, ?.oved

rc; hne 15, eighteen spent asser.blice had t een :

eved ~r:

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-.; - ' the core alorg with enc c:ntrol roc.

.cruater e m.-

t nntral rod disclosed cone rect betucen the c's..ler:

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.c c - ;rc l rod drive scaft latches and the stainic..:

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. ancorrer section. Fossible wear in this na

-4 Le c n tic-a c.:.d cer.:r:1 rod drive shaf t and absorber sections of 2 yrcved accign u.; ree- -rocured.

.: car wcs also detected at the.i.cint betunen the rirecloy r ection c.nd stainless steel adapter on the abscrber.

'. a res.it. rg.-

r.

ro.; 'oll ow rs will also be replaced.

?cllouin; detection of wear on the follover joints, a occisien was

- 'e te e,rnlc.e the reactor refueling and insert the new c ntr:1 re:c r.t e:rter

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Sy-two abscrber sections of revised cosign a :

u:o : N. rt-. ;. - e r-

ncre c.' *.he Core I design were placed in the. enet:.r.

. ent a; ich vr ry

~cm rc, the Core ! followers.:cre returned.c run e r u r.n arscrbcrs.

Ane N, the new absorber sections hnd been

' cc ' in

.t.e

.c:.cter

.ne e i, ei wd rair rods had been reccved, inspecte:

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=t..~"d in re:: tor.

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.4 4 qutdrant by quadrant unloading-1cading schene allowed craninstion cf it.e bottc~ core support plate and source vanes af ter complete]y unice. ding

- a q:1drar.t and rrier to its reloading sdth new fuel assc..blies.

By the er.d of tr.e period t:rts::;ie exanination of the core support p3 ate and ce.:rce var:3s tad been c rn;1+ v c in three quadrants. In all cases no unusual conditions were eted.

Sps nt fuel renoval and new fuel insertion proceeded through the final tys of the pcriy2 relatively sncothly. The fuel handling systen functict.ed well except fcr or.e crief " hang-up" of the fuel carriage on its return fron the spent fuel pit.

A t t r.2 end of June the status of the reactor refuciirc was ss follows:

..:a rant 16 spent assemblics renoved,18 neu assenblies Sert.tist installed,1 assembly carryover from Core I.*

Southetst 19 spent assemblics renoved,19 new assemblics ins talled Southscst 19 spent assenblies renoved, lb new asser.blies installed (loading in pro 6tess at end of month)

Ite11r.irttry underwater exa tination of spent fuel assemblies has dis-cleted r,c di::ernable distortion of fuel assemblies or significant crud buildup.

klhile c catailed exanination of all control rods had net tecn ncde by

": cf mur.0, i:rctcher on sone of the absorber section surfaces were cc.ected.

.ted.es ;;r. cbsorbers are provided with rubbing straps wnien snealc elin-a ~

cr : '_ e 1 :. :reatly alleviate this condition durin; Core !! operctien. The

. ; e '. ;1mt;:c cr :cceral abscrter sectiens was observed to have actcriorated

.:-. n;;<el platirq flaking off in rene areas,

i. cr.enical antlysis

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- cric' dicelesed that it was prir.arily r.ickel with traces cf

'..tr al:: n u nt.

Se::rry ;1:ct operations proceeded during the pcrioo witn the r :.ni.: r.trater issrecticn essentially completed.

'.'ith the ex epticn cf

..v crecien o.

cu.ti g of a few low pressure turbine bladire stellite strips and sone nin r eresion in the area of the inlet impulse section the condition turrir.e.ns fcund to be good.

ne

..sec_:e cnly ninor repairs were required on the generatcr.

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f Jure b tn the turbine cnd generater usre te: q reat.rer..ed.

e r.< r; Juel asse..blies will be used in Core :I fer an exteneca 4

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c results cf a detailed underwatcr ext inctior. of the spent

. Oc ine:r s aitioility for such an cxpe riner.t.

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".aintenance Following is a listing of the major naintenance activity t.ri:g.Nne:

1.

Tested the low pressure surge tank safety valves.

2.

Repatred underwater 7.V. camera in the shield tar.r. cavity.

.?a te r had leaked into the fitting through which the 7.*.'. entle er.ters the caner. enclosure causing a short circuit.

3.

Conpleted an inspection of Ho.1 loop safety injection valve, drain valve and bypass valve.

L.

Inspected ' x overhauled the pressurizer solenoid and r.cter operated rt.

.f valves.

5.

Inspected and overhauled the stop valves in the waste disposal ecver gas systen.

6.

Renewed the primary drain pump shaft bearings.

7.

Rough cleaned the reactor studs and nuts.

8.

Inspected the station vital bus.

9.

Repaired the underwater viewing borescope.

Lif ting of 'Jie silvered backing on a prisn in the borescore necessitated its repla cenent.

10 Installed a new steam heating ccil in the safety

,jec.or tan <.

11.

nstciled new seals in the No. 1 stripper betto- : 1~.r.

II.

Installed a new diaphragn in No. I waste gas cer. pre sser.

13 Ferf or..ed calibrations on prirA7 plant instrurentatier.,

ie:r.iary Flant 1.

Cor.pleted nodifications to No. 2 feedvater neater ar.a c:nductec a hydrostatic test on the heater.

2.

Eer.cVed generator field and conducted tests en teth st;ter and reter insulation. Following the generator Onspec tier tte f.e'.m was reinstalled.

3.

J:nducted r.agnetic particle inspection of the turt.,*:.

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Cleaned bladire on turbine rotor and diaphragns.

E.

ade :'.iscellaneous repairs to turbine.

Fifteen stellite strips on the low pressure spindle blades were replaced as a result cf erosion. A stca. cut area on No. b turbine control valve inlet flarge was repaired. Seal strips in the area cf the governer cnd 1. pulse wheels were repaired.

6.

Reinstalled the turbine low pressure rotor.

7.

Inspected ard everhauled the stean dump valve.

The valve disc and sten were replaced.

8 Inspected secondary side of No. 2 steam generater.

The general condition of the steam generator was good with no visible pitting l

or corrosion evident.

Cne.istry C?eration of the modified waste disposal evaporator has indicated a slight baron volatility (~ 0.2 v/o). A polishirg ion excharger vill be required to nake reuse of the distillate possible.

!'.ain coolant and shield tank cavity water boron concentrations re-nained at 1160 to 1190 ppm throughout the period.

The nain coolant crud IcVel ranged fren 0.11 ppn to 0.39 ppn while the shield tank cavity water crud level was ~ 0.7b ppn.

i l'u'ly in June the nain coolant specific activit~y ir. creased from

~ 2.c x 1C-3 nc/nl to 3.7 x 10-2 pc/nl. The increase occurred t.f ter tern-irst.cn cf f1r.e tnrrush the cation excharger. Concurrently, the nrin ccelant r.ieml cenecr.ratien increased to $ ppn -- the presence of nicel beirc a.tricated oc c:rrosien in cold, borated, oxygenated water ci undiffused nickel

2ne er. int rcactor centrol rods. Resunction of purificatic tnrou;r the at.r

. exent.rc< r decreased the nickel concentration to belo : tin point of dettetten t, de end of the period. The predoninant contributer to nrin

..nt spc:Vic activity during this period was 00-55 whien is carried with r.e m...de r.icac1 in t he coolant. The decrease in nickel cencentratien was rr 'i cc ci in.re nain ecolant specific activity which decreased tc 1.9 x 10-3 p:/n1 V. m c une, I

^/ne cnield tank cavity water specific activity which rarged frcn

-.c x 10 3 refnl to $.6 x 10-3 pc/nl at the beginning of the period increased x 10-3 pc/nl by the end cf June with Co-58 the najor tetivity centri:;utor.

une 10, a cr.ro. ate concentration of 1.5 ppn was detected in the shield ;ar.k rea r.

' " ak n;a fron the unde:.ater T.V. camera coelire coil was sus-a as.

.;c-.rce of the chronate. Follorire isclatien of.ne coclirg coil i

n s J'r :

n ce were negative.

Late in the period the spent fuel pit

~rcr m neantration reached 12 pp..

liixed bed ien exchange cf the pit

,. : r r.in ern at this tine.

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5 Cher.ical and radiocher.ical analysie of flake material from tne control rod absorber sections indicated the follovirg:

Nickel 100% + 0.5%

Silver 0.37. T 0.1%

Co-58 1.5 x 10b epn/rc Ag -100n 2.h x 105 epn/rg Reactor Plant Performance Ter.perature coefficient of reactivity results deternined at varyirs core and coolant tenperature conditions during testing at the end of Core I operation indicated the follovirg t 1.

Peak xenen, O ppn boren Tave, b280F, 2000 psi

-1.69 + 0.0L x 10-b d(3/0F 2.

Xenon free, 195 ppn boren Tave. E20F, 0.000 psi

-0.7010.C6 x 10-b gjoy 3.

Xenon free, 220 ppn boren Tave. 507 r, 2000 psi

-2.36 0.05 x 10-h 69/or Turbine Flant Perferr.ance With the plant shutdown during June no secondary plant perfornance data were acquired.

esign Charges The followira charges in plant design were co.pleted durirg Jene :

1.

A welded, s' ainless steel pipe connection fcr a hign accuracy r.ain coelant pressure gace was installed. The connection cricinates at a newly installed tee connection cuttoard of the rect valve for the high pressure line to the wide range pressuriter level d/p cell.

It teminates at the pressa e reasurira gage located in the primary auxiliary building.

Appropriate valvir6 for isolation of the newly installed line was also provided. This installation is in accordance with Proposed Charge No.16 sub.itted on January 18, 1962, and approved by the A.E.C. on March 26, 1962.

2.

?.co valved and blanked connections were instailed in the Safety Injecticn Systen piping -- one in the safety injection pu.p suction header and the other in the safety injection pur.p dis-charge header. Based en the possibility of authori:.ation to

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operate the plant at higher power levels and the atter. dent necessity for an additional safety injection punp, tnis enange has been effected to facilitate future installation cf the punp. By virtue of the suction and discharge taps now in place it will not be necessary to shut the plant caen sr.d cool and depressurize the main coolant systen for installation of the additional punp. This change is in accordance witn Propcsed Charge No. 20 submitted en March 12, 1962, and apprcved cy the A.E.C. on May 16, 1962.

3.

The electricalsupply for the radiation nonitoring and feedwater cor. trol systens was changed from the existing 120 volt AC vital bus to a station service bus (hBO volt bus M;Cl-Bus No. 1).

This feeder presently supplies equipnent including the valve operators for the safety injection system, the control rod. selection and progran controls, No.1 main transformer and other essential 120 volt AC instrumenta%or. which are vital to reliable and safe plant operation. Operation ur. der this arranger.ent steuld effective-ly reduce the exposure of the AC vital bus to electrical grounds and consequent spurious reactor scrans. Since a brief inter-ruption of the radiation monitoring and feedwater control syster.s can be safely permitted dt.-ing a loss of power condition, the change does not adversely affect plant safety considerations.

This charge is in accordance with Proposed Change No. 21 submit-ted en March 23, 1962, and approved by the A.E.C. on June 13, 1962.

L.

A stainless steel isolation valve and tee connection have been installed in the pressure equalizing line between the p:inary systen safet) valve discharge header and the low pressure surge tank. The tee connection is located on the safety valve header side cf the new isolation valve with a capped line and snut off valve connected to the tee. The newly installed conr.ections wil' simplify primary system safety valve and cennecting piping naintenance by providing a means for purging the safety valve headct without purging the hydrogen fro.. the low pressure surge tank as had been required prior to the nodification.

This enance is in accordance with Proposed Change No. 22 submitted en April 15, 1962, and approved by the A.E.C. on June lh, 1962.

5.

Twenty-two of the twenty-four control rod abscrber sections were replaced with slightly modified. absorbers. Incorporated in the nodified design absorber sections are longitudinal, segnented, stainless steel rubbing straps on each of the eight vane sur-faces. The rubbing straps are intended to reduce wear and abrasien of the rickel plating on the surface of the abscrber sections. This change is in accordance with Proposed Change No.

13 subnitted on January 5,1962, and approved by the A.E.C. - en April 9, 1962.

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External and internal modifications were nade to No. 2 feed-water heater. An additional stean supply inlet to the up;cr section of the heater shell was provided by extendirg tre i

xistirg stean supply line and adding an inlet no::le.

A further external modification was the addition of a secenc heater L

drain connection with a tie to the existirg drain lir.c.

Tne internal nodifications consisted of replacirg secticns of the hori:.ontal baffles previously cut away, cappirg the internal vent and addirg a deflectirg baffle opposite the new stece. inlet nocele. These modifications were nade to improve the ther.al perfor.ance of the heater and also to increase the heater capacity for anticipated higher power operation.

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7.

Minor design nodifications have been nade to the turbine during

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the current turbine inspection. Steam strainers have been e

installed in the four turbine control valves to ir. prove the flow distribution and alleviate vibration in the control valve b

bodies.

t Tnirty-tuc,13/h inch diameter r.oisture drainage

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holes have been provided in the low pressure turbine casira l

durire the outage. The draina::e holes will increase n01sture

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renoval capability in the low pressure stages of the turbine.

f-Health and Safety

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Liquid waste with a total activity of 1090 pc was discharged fron 5

the plant durira June. Thirty-five drur.s of solid waste containirg 36 n.illi-7 curies were shipped fer off-site disposal while eighty-four barrels cf solid X

waste centainira 670 r.1111 curies were dur.med durirg the sa.e period.

At all

,1 tir.cs the concentration of waste products discharged or shipped frcr. the site f

was well belew :he r.axi..un pernissible.

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o casecus waste was discharged from the plant durirg Juv.

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7ne f cilowire contact radiatien levels were r.easured durirg June with the clant n a cold, borated, depressuriced conf.ition:

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L Location Radiation Level en Centact i

i No. 1 Chargire Pap 35 re/nr No. 2 Chargir.g Pep LO rr/hr No. 3 Chargira P=p 35 ry/hr

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Cnargire Line (in pipe chase) 15 rr/hr 5

!hin Coolant Bleed Line (in pipe chase) 50 nr/hr i

Activity Dilution Decay Tar 2 50 r /rr - a r/=

)

.;aste Heldup Ta.k 10-100 rr/rr

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3as Iu ge Drur.

0.02 rr/rr 7

Snutccrn Coelire Punp 1.5 r/rr Sh;tdcrn Coelirg Excharger 150M 0 rr/rr 5

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Location Radiation Level on Contact-Low Fressure Surge Tank Discharge Line 250 ex/ttr Low Pressure Surge Tank Botton 7 r/nr Ion Exchange Pit

0. 2-0. 5 rr/h r Pressuri:ct Shell O.h-20 rr/hr 1:o. 1 Loop Funp 00-90 r.r/hr

!:ain Piping 50-250 nr/hr 1:o. 2 Loop 7;as s V alve LS rr/hr

!ain Fipirg 60-lCC rr/rz

.' c. 3

• mcp bypass Line 30-50 rr/Pr "ain Fipira 80-10,0rr/hr t

!:o. h Loop Check Valve 20 rr/hr P.ain Pipira LO-LOC nr/hr Radiation levels in the workira area during cutting of instrunen-l tation seals on the reactor head were h0 to 60 nr/hr with tenperary 3/L inch thick lead shieldira in place around adjacent control rod drive nechanisn housirgs. Conta.ination on the reactor head and in the control rod drgve techcnisn area as a result of the operation was 3,000 to 30,000 dpn/f t.

e.cval of the renaining control rod drive mechanisn ceti s. ace.s increased raatatien levels by a factor of two at the reacter stud annulus c.rd by a fcc.cr of fcur in the general area of the shield tank ccvity. 'mle cc11 i

s.-d renoval nad been scheduled for conpletion early in the reacter nead rencval preparations, they were left in position until their chieldirq cffect i

for nearby eperatiens was no longer needed.

Radistion levels at the inside edge of the vessel head flarge during

'S tial lif tirg and prier to floodir.g the shield tank cavity were:

Head raised 2 inches 1 r/hr Head raised 12 inches 1 5 to 5 r/h-Head raised 2h inches b to 8 r/hr "easurenents nade by dosineters inserted under the center of the r. cad ir.dic:.:>d the tctai radia-a fron the head plus that fron the ccre.:as t tc 5

- e tn :ne nead raised to 2h inches.

Durin: tne descent of the reactor head through the varer c:ntair.cr ecj:i;.ent hatch to tr,e railroad flat car, the follovirg radiation levels were

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neasured at crcund level:

Measured Head Location Height above Ground Radiation Top of Equipnent Hatch 65 feet 2 rr/hr Sotton of Equipm nt Hatch 33 feet 20cr/hr Eclow Equipm nt Hutch 12 feet 50 cr/hr Follovire flooding of the shield tank cavity radiation levels of 15 to 30 cr/hr were measured over the edge of the cavit. General area levels on the chargir; floor at the same time were 0.2 to 1 ry hr.

Radiation levels increased in the vicinity of the jacking pump on the charging floor as the punping of contan-inated water progressed.

Radiation icycls of 100 to 200 rr/hr vere neasured at a distance of tnree feet from the puno. The pump was partially shielded by stacking concrete blocks to a height of four feet (thickness of eight inches). This reduced the radiation level outside the shield to 2 to 5 rr/hr.

At the sane tine, a source of uncontaminated water was provided.

General area contamination levels of 200 to 20,000 dpm/f t2 were measured on the chargirs floor.

Isolated locations on the chargira floor exhibited a higher degree of centardnation as a result of temporary placement of contaminated articles on the chargire floor.

Ir. two areas maintenance on contaminated equipnent removed fron the shield tank cavity produced contamination IcVels of 50,000 to 200,000 dpm/f t,

2 At the end of the period general area radiation levels on the charging flocr were 1 to 5 nr/hr with levels of 10 to 30 mr/hr measured near the edge of the shield tank cavity. Ogneral area contamination levels on the chargire flocr were 2,0?O to lb,000 dp:/ft By the end of June a radiation icyc1 of 20 to 30 mr/hr was reasured cver the edge of the spent fuel pit. The radiation level on contact with the side cf :ne f 41 pit cooler was 50 to 80 rr/hr.

Radiation IcVels measured after drainage of the secondary side of !'o, 2 c tec.n ccneratcr were 80 rr/hr at the nanhole opening and 2 r/hr at the hand hole epenirg s.

The naxinum personnel exposure as neasured by filn badges for the nonth cf Mr.y 1962 was 300 rr while the average was 10 rr.

Dosineter readings for the month of June 1962 indicated a naximun exposu-e of 910 er with an average personnel exposure of h80 rr.

June 1962 filn b:.dp results.till be reported in the July 1962 Operation Report.

Tne exposures indicated for May and June include all statien personnel ms ten tenperary personnel assigned at the plant for the refuelin; cperatien.

Continuous nonitoring of off-site airborne activity durirc Jane indi-

> kvels consistent with pre-operational values.

1

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.In I'lant Training Cne craineer from the Solni nuclear project completed an assign,ent at the T.lant duritu June while two Selni representatives continued in their plant an s ignnents.

Cte Stone & 'riebster ergineer and four sponsor conpany ergineers term-insted plant assignments during the period. One sponsor company engineer rerdaned 1

in trainire.

Flant Operations Attached is a su:-.ary of plant operating statistics for the ncnth of June 1962. Since the plant was shutdown throughout the period the plot of daily

' werage plant load has been c~,itted.

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IA1;KEE ATOMIC EIICTRIC COMPAllT - OPERATI?C, SU!C'aiiY JAT 1962

'0 NTH TEAR TO DATE El ECT7 ICAL L11 0

369,173,700 1,330,$21,000 Sta. Service (While Gen. Incl. Losses)

L11 0

30,028,3h9 107,560,L31 Gross Generation L11 0

339,E5,351 1,222,960,569 C

6.13 8.Oti Ilet Generation Sta. Service (While Not Gen. Incl. Iosses)

Gli 363,$h0 1,309,391 11,601,109 Station Service n

0 Ave. Gen.

For Month O

Ave. Gen.

Running PIArtT PERFOUfAIICE 28.78 Net Plant Efficiency 11,8$8 Btt./FA Het Plant Heat Rate E.OS Lbs. Stean/ Net Gli Circulating Water Inlet Temp.

• F Maxinum 0F 0

$$.9h 6h.68 Minimum Plant Operating Facter MOhTH CORE I TO DATE

'!UCLPAn O

262 267 IEtS O

13,2b7.b 3 13,2hT.L3 Tires Critical Hours Critical O

30 30 HRS O

6628.5 42:i; Tines Scramed Equivalent Reactor Hours @ LS$ Bit.

MD/ntU O

83h?

i3k:

Average Burnup of Care Control Rod Position it Month End Equilibriun at O

Group 1 Rods out-inches Group 2 Group 3 Shu t, <foun Sroup h for refuelim 3roup $

3rour &

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