ML20085G993

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Monthly Operating Rept for June 1968 for Saxton Nuclear Experimental Corp
ML20085G993
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 06/30/1968
From:
SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110280098
Download: ML20085G993 (8)
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. S/J:TO::_1: WAR T?:P!pI:Z:Ti.L CMPOSTIO:!

hty t.1.one Report for June 1960

, 1. EfTOR CPr?ATIO:S At the bccinning of this report period the reactor was maintained in a hot chutdoun condition until co:apletion of AT;0 conior operator licence exam n:.tions for tuo 3:50 caployees on Junc 5. A ocheduled cooldoun of the main coolar.t systea van initiated on June 5 for maintenance and changing of test fuel cubascewlies. Fillint; and venting of the main coolant cysten was initiated on I June 25, heat-up of the nain coolant systen co=enced on June 28 and was completed on Juae 29.

2 GTA:"2Jr b Tne period frea June 10 thru June 15 was devoted pri:aarily to maintenanco  !

of the nain coolant system. Th9 period from June 17 thra June 20 was devotod to crndling tect cubasceablico. The fuel changes mado are as follows: The reactivity occillator vac reaoved froa core position U-2 and the plutonium oubassenbly was re.:oved from core position U-1 and both placed in storace. .The pH test subassambly unc transferrod fren core position U-3 to N-2. No cingic rods were removed frora the burnable poison cubasseably and replaced by two new internally pressurized fuel rods and the cubacscably returned to core position U-5. Two irradiated ,

Pu02 -UC2 cincie rods were installed in the overpower test cubassanbly and the cubascanbly transferred to core position N-1 in preparation for the forthecming over pouer test . Four internally prescurized fuel rods were installed in cubassenbly 503-4-25 and the cubassenbly transferred to core position U-3.

The core subacsm.bly status as of June 30 is as follows:

U-1 2x2 Over Power Test Asocably, 503-4-30, containing two Pu02-UO2 rods 503-15-1 and 503-15-3 U-2 pH Test Subacceably, 503-4-28 N-3 3x3 Eubacecably, 503-4-25, containing ranovable rods #715,

  1. 716, #717 and #718 U-4 STP loop Damy

!!-5 krnabic Poicon Subasscably, 503-4-29, containing renovable rods #719, #720, #1 and #2 i

Hine rods from an unirradiated subasocably wero returned to Westinghouse

. Atod.c Power Division.

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S ::C Operations Report for

/ June 1968 ,. . _ . u. ..@

i 3 g;Pinnz:TAL P20GP.!Ji Daring the month, approval was received from the AEC for Chando Urber 30, " Irradiation of Highly Prescurized Zircaloy Clad Creep Test Fuel Rods" and Change !baber 31, " Irradiation of an Overpower Test 2x2 Subassembly".

Test procedure, 309.7.1, " Reactor Oucration Daring the Overpower Test" was reviewed and approved.

Three c::perimental systens for the prompt detection of fuel failure ucre installed to penait continuouc monitoring of the main coolant.

1. Tac first syctan concirts of two ionization chambers, one on the reactor inlet pipe and one on the reactor outlet pipe for monitoring cross ga:xta radiation.

2 Tne cecond cyctam utihzes a G U tube for monitoring the croso cc:n activity after delaying the sempic for U-16 decay.

3. Tne third systen utilisco a BF3 neutron detector and monitors the main coolant for delayed neutrons.
4. OPERATIO:AL Ti3TS_

The S::LC fire and evacuation alams were tested on June 7,14, 21 and i 28. A plant evacuation drill was conducted on June 27 The monthly test of the radiation monitoring systo:a was completed on June 3.

$. PAII TE"A! ICE Tne principal ite's of mechanical maintenance for the month included work on the control ruct nir conditioner compressor; preparing the reactor vessel head for fuel handling; lapping the seat on the chen chim inlet valve, HIC-27, and the purification cysten stop valve, HIC-23; replacing the silica gel and the molecular swm in the instrument air drycrs and the vapoilsorb in the oil renovers; lapping the seat and disc on charging pump suction relief valves, V-362 and V-363; install-ing new seats and discs in the charging pump discharge relief valves, V-221 and V-228; installing unions on the discharge piping of the charging pump relief valves for future maintenance; repairing the pressurizer vent line spool picco; installing a new seat and disc on the regenerativc heat exchanger relief valve, V-53; lapping the ring joint fhngos on the stern generator safety valves, V-1046 and V-1047; lapping the ring joint flance on the regenerative heat exchanger piping; inctalling a new rapture disc in the steam generator safety valve discharge piping; retightening the main coolant pop flange bolts, and lapping the seat and disc on the pressurizer safety valvo, Va372 l

4.

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1 S"50 Cycrations Report for )

Jan c ?.96g . . , , . . . J3 l

l Tno La:.jor itmo of c1cetrical and inst? rent maintennnec for the month included checking the specific gravity of the station service batterics; rebuilding an air regulator on the deacrator stem supp3y valvo, V-1010, and calibrating the controller; repairing the count room liqaid scintillation counter scaler; repairing the vacuum pump in sito particulato monitor, RIC-B; cleaning the coarsc and fine rod position selector cwitch contacts; mcggering the main coolant pump, variable frequency generator ard motor and the two safety injection pump motor windings; calibration of the main coolant systm pressure controller, PRC-2, calibration of the eteam generator, main steam and feedwater pressure indicators; installing a new hoater in the instrament air dr/crat mcggering the nuclear instrumentation cables and detcetcrs; installing an interecu paging phone in the training room; repairing the high lovel 041 scaler in the count roam; replacing the carbon vanus in the charging room alpha monitor vacuum pump; installinc new tubing and solenoid valves on the safety injection .systen autcentic valves, FIC-22V and ,,

FIC-23V; calibration of the steam and foodwater flow instrumentation; installing new resin in the fission product detector resin colunns in RIC-10; and sampling and analyzing the 1000 KVA transfomer oil.

6. CE 35~?.Y
  • The main coolant system was mz intained for het shutdoim conditions at the beginning of the month. On June 6 the boron concentration was increased to 473 ppa aad the hydrogen conecatration reduced to less than 5 cc kg of water in preparation for cold shutdown of the reactor. Chamical specifications were maintained for cold shutdown conditions until June 27. Boron concentration ranged from 211 ppn at hot shutdovm to 1825 p;n after flooding the storage well for changing r.bassmblics. Hydracine was added on June 27 for om gen rmoval prior to heat-up of the main coolant system.

A sumar/ of the ana3yses performed on main coolant samples taken during the month is contained in the following tablet Main Coclant Systcm Minimum May32um pH at 25 C 5.43 6.62 Conductivity, unhos 2.22 9 75

! Boron, p;n 211 1825 l

Chlorides, pga 0.005 0.055 Or/ gen, ppn (Hot) 0.005 0.015 Hydrogen, cc/1:g H2O at STP 3 56 Grose Bota feca (15 Min. Degassed) uc/cc 1.65x10-2 5.23x10-1 Tritium,uc/c- 1.18x10-2 1.02x10-1 l

A compoacnt cooling sample analyzed on June 25 showed the pH to be 8.12 l and the t hromate concentration to be 310 ppm. The gross beta-gama activity was i 2.71x104 ue/ce. One hundred fifty grams of potassium dichrcoate and eighty grams I

of potassium hydroxide were added to the systen.

I

5::EC Operations Report for f.une 1 % f' . . _ . . . . . d4 Tac ana2ycio of the ctorage ucl1 unter and the refaeling water ctoracc tank nre co: .ained in the follouing table Anniveis Storare UcQ EST ,

pH 5.53 5.49 conductivity 9.25 0.65 Cnlorides, pan 0.060 0.045 Doron, ppa 1079 1059 Groce Deta-Ga:r.a, ue/cc 5 07x10-3 6.10d0-3

7. lEDIATIO" A'!D UISE DISP (DAL lhdiation surveying consisted of routino plant surveye, C.V. during shutdoun and materinlo shipncato. The folicnring maximum radiation readingo ucro taken:

Rndiation Read $nc

]pra t io2 OLd. Duildin~

Uncto Dru:a (baling maa.ine) 0.6 mren/hr beta-ga'r.a Charging Pump (contact with chamber) 19 mran/hr beta-gamma Sample Room (door of camplo panel) 5 0 mran4/hr beta-gamma Chaaical lab Hot Sink (l" from drain) 0 5 mran/hr bota-garna EDF Evaporator (urder bottan) 70 mran/hr bota-ccana Evaporator (contact outside upper level) 35 mram/hr beta-ganna Drum Storage Area (at hPA fence) 15 mran/hr beta-gn=a C . V .,

Primar/ Ccup:.rtment generalupperlevel) 80 mram/hr beta-ga:na Prirar/ Compartment contact M.C.

Prirary Compartment S.G. bottom)pumpvolute)150 210 mran/hr mran/hr beta gaena beta-gam, a Pri~.ary Ocepartment 50 mren/hr beta-ca=a Prirary Ccupartment (preneurizer bottom) 35 mrm/hr beta-cama Primary Ocepartment (general Regen. lE) lower level)170 mran/hr beta-canna Primar/ Ccnpart:nent (hon Jte en. IE) 17 nran/hr beta-cam.a Auxiliar/ Iquipment Compt. S.C.H.X.) 8 mren/hr beta-cama Auxilit.ry Equipacnt Compt. D.T. top) 6 mrcm/hr beta-gama Auxiliar/ Equignent Canpt. D.T. bottern) 33 mrem /hr beta-garna Auxiliary Equipnent Compt. ({ general lower3mram/hrbeta-gama level)

Reactor Deck-(water level at crating) 20 mren/he ).,ota-gn=a Reactor Deck (instrument porto) 210crem/hrbota-canna Reactor Deck beist level) 50 mren/hr beta-garna Reactor Deck (storage well railing) 20 mran/hr beta-gamma i

S::LC Operctione Report for

?_une 1968 ._. . . . . #5 Contanination curveying conciated of routine phnt cite curveys, curve /c of raterials chipped, tools, olu1}nent and U.V. during chutdcnm. Tne clean areas were within the " Clean Arca" linito. Tne contro13cd arca was general (v vithin the

" Clean Area" limito. The controlled area was cicaned frequently to keep ani/or to return it to the " Clean Area" limito. The celusion areas woro c1 caned period-ically to rininice the amount of cmearabic contardnation. The following contamination icycle were obocrved Iecation Contamination Readirm CM Pulldint Chcrging Pep Chcaber 2468d/m/cmearbeta-gara Charging Pcp Chamber < 10 d smear alphs Charging Room Floor 1768 d encar beta-gama Sample Room Sink 27218 d cmear beta-cc.m a Sampic Roan Sin); < 10 d cmear alpha Sample Room Floor 2228 d /cmear bota-gn=a Chemical lab Hot Sink 31668 d /cmoar bota-gamma Chemical lab Hot Sink < 10 d /c:near alpha RZF Pamp Room Floor 1740 d/m/oncar beta-ga.ma Shipping Room Floor 450d/m/cmearbeta-camma C.V.

Operating Doch 11400 d smear beta-gama Operating Dech < 10 d smear alpha ReactorDech(head) 18740 d /cmear beta-ge.=a Reactor Dech head) < 10 d /amearalpha Reactor Deck grating) 19150 d smear beta-gamm Reactor Dech (grati ) 410 d smear alpha Pri.~nry Campartcent 3830 d emear beta-gera Primary Compartment (grating grating 410 d smear alpha IAquid and gacoauc effluents frcra the SNEC site for the month of June 1968 were ne folloves (Curio) (Curie) (Curie)

Effluent Activity Activity Activity hmo This Month Year to Date last Twelve Months Idquid 0.000453 0.003184 0.010813 Tritium 1.378342 4.038990 5.494919 Air, Xe 0.741070 15.793931 26.632464 Air, I-131 0.000000 0.000321 0.001972 Air, M.F.P. 0.007410 0.157939 0.266324

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S!TSC Operationo P.cport for June 1968 ,_ . _ , , , , , #6 llo barrels of vaste were dru:xned for tar.porary ctorage. Pifteen(15) '

drano ucre shipped from the site.

Radiation exposure for all SIGC personnel ao measured by film badges for the month of thy 1968 were a maximum of 70 mrm with an average of 11.6 mran.

Jhd1ation expocure for all visiting personnel as measured by film badges for the nenth of thy 1968 ucre a maximum of 0 mrce with an average of 0 mraa.

The average radiation exposure for all personnel as measured by film badccs for the month of May 1968 was 9.95 mran.

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SAXTCt1 NUCIEJsR EXPERIENTAL CORPORATION OPERATING STATISTICS MONTH EE YEAR 1960 NUCITAR UNIT @ NTH YEJA [0 DATE TlFJS CPJTICAL NO. 4 105 647 HOURS CRITICAL HRS. 1.9 1,117.56 21,690.56 TIMES SCRA)ED (MANUAL) NO. 2 L1 363 ,

  • THE SCPJJEED (INADVERTANT) NO. 0 6 39 THDWAL PJdER ODERATIO'i MWH 0 26,456.36 404,426.29 AVERAGE IIJRNUP HRD/MTV O 2,159 55 15,993 78 CONTROL ROD POSITIONS AT DiD OF !!ONTH AT BlVILIBRIUM P0 DER OF 0 MWt MAIN 000LAN' BORON 1100 ppg RODS OUT - INCHES NO. 1 0 NO. 2 10 No.3 0 NO. 4 o No. 5 10 No. 6 _ o ELECTRICAL UllIT MONTH YEAR TO DATE GROSS GDiERATION KdH 0 4,862.00 60,138.50 STATION SERVICE MWH 140 34 1,675.91 33,893.81 STATION SERVICE  % 0 34.47 20.39 AVO. PIANT EFFICIENCY - SlH(4)/WH(t)  % 0 18 30 M.85 AVG. GDERATION R'JNNING ( 0 ups) gw o 4,730,90 3,441,13 PIlsNT IDAD FACTOR -

% 0 17.67 19.86 (AVG. GEN.FORMONTH/ MAX.IDAD)

AUXILIARY STEAM SUPPLY - NUCLEAR STEAM SUPPLIED BY REACTOR HRS. 0 1,069.47 18,220.56 WDF EVAPORATOR OPERATION HRS. 01.25 364.51 6,822.91

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