ML20085H062

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Monthly Operating Rept for Sept 1967 for Saxton Nuclear Experimental Corp
ML20085H062
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 09/30/1967
From:
SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110280122
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_ _ _ _ _.

o SAXTON NUC L R EXP (IJ') [ M E S 2 Operations Renort for Sorte2cr 1967 O

1.

ItFACTOR OPDIATIO!G The reactor was made critical and loaded to 23 5 Mit on September let to continue the plutonium program and to complete the final phase of the pre-fuel functional test program for the supercritical temperature and pressure (STP) test loop.

Operation at 23 5 MWt continued until 11:00 All on September 6th when the reactor was manually unloaded and shut down.

Cooldown of the main coolant systen w: s initiated on September 7th to facilitate maintenance work on a einnering relief valve, V-373, on the pressurizer and on a shut-off valve, GX,,

in the bleed line for reactor vessel head nozzle, N-4.

On Septenber 8th and 9th the main coolant system was reheated to nomal operating conditions.

The main coolant pump and the pressurizer heaters were the cources of heat. During the following several days the reactor was maintained in a hot shutdown condition while the STP test loop was operated for training purposes.

At 4:30 Pli on September 15th cooldown of the main coolant system was initiated to commence a scheduled plant outage for the purpose of replacing the unfueled STP test loop pressure tube with one containing a fuel subassembly and to replace two 3x3 fuel subassemblies and the assembly containing the flux oscillator rod.

The reactor was maintained in a cold shutdown condition during the O

re-inder of this revert Period.

l 2.

E:0GIl0 MAL Ph;yg4, The pre-fuel functional test program and the operator training progrwn i

l for the STP te7t loop were completed during the first half of the month.

The operation of the test loop during this period was intemittent because of probims enecuntered with seal leakage in the positive displacment loop pumps

  • leaking valves in the cooling system for the reactor vessel head nozzle contalning the locp pressure tube; level control on the loop head tank; and simmering relief valves on the pressurizer for the reactor main coolant system.

On Septa ber 15th the test loop was shut down to prepare for replacing the pressure tube containing a du:any assembly with one that contained a fuel pubasJembly.

On September 20th the following test units were received at the site for installation in the reactor vessels STP Test loop Subassembly No.1 (Chang.* No.16) pH Test Subassembly No. 503-4-28 (Change N. 27)

Ihrnable Poison Subasambly No. 503-4-29 (Change No. 28)

Flux Oscillator Rod Assemb]y No. 3 (Change Report No.13)

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o SNEC Operations Report for Septmber 1967....

2 1

3 OPERATIollAL TmTS On September 29th the radiation monitoring system circuits were tested.

The #2 turbine overspoed trip was tested on Augue: 91h. The loop functioned at 1950 RPH.

L.

1%1tJTE'!ANCE The principal items of mechanical maintenance for the month included lapning the seat and disc of pressurizer relief valve V-373; removing the component cooling system heat exchangers and cleaning the tube bundle of each; processing 10 drums of evaporator bottoms; fabricating and installing a seal on the reactor vesnel head nozzle bleed valve, GX-1; replacing the rubber matting on walkways in the controlled area of the C&A building; installing a sump pump in the manway to the RWDF decontamination room liquid storage tank; replacing the fan belt on the chemistry laboratory hood air handler; replacing the pre-filters on all of the air' handlers in the containment vessel; checking the stem of auxiliary system return valve HIC-27 for straightness; lapping the coat and replacing the stem packing in valve HIC-27; repairing a leak in a buried service water line; preparing the reactor vessel head for replacing subassemblies; and cleaning the drain line, the level column and the level sight glass on the RWDF evaporator.

The najor items of electrical and instrument maintenance included O

ca11bratiac the 1evet controller en the icroF evaporatori renairins a circuit board in the computer-indicator for the component cooling cystem radiation monitor, I

HIC.41 repiring the remotely operated latch on the door in the main entrance to the C&A building; repairing the air pump in the southwest site air particulate monitor RIC-9; replacing the manometer across the filters in the exhaust air handler for the ILIDF building; repairing a cable temination in the pressurizer henter junction box in the containment vessel; calibrating the recorder for the main coolant system hot and cold leg temperatures; removing and checking the I

operation of the pneumatic operator on the auxiliary systems return valve, HIC-27; replacing the galvanometer in the resistance bridge in the instrument shop; cleaning the solenoid operated valves in the RWDF evaporator feed line and in the evaporator hotwell drain line; repairing the capacitance probe in the chlorinator control for the sewage plant; repairing the high voltage circuit in the charging room area radiation monitor, RIA-2; cleaning and calibrating the differential pressure cell in the valve and gasket leak-off system in the containment vessel; calibrating the secondary system steam' flow recorder and the steam flow integrator; adjusting the ratio totaliter on the boiler feed pump control; and installing underground cable for two sumo pumps in the yarsi area.

5 CHD4ISTRY The main coolant system chemistry was maintained for power operation during the period September 1st to September 7th.

Doron was added and hydrogen was removed during system cooldown initiated on September 7th for maintenance purposes.

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3 32, azine was aGaed to the main coohnt wate-on September 9th for oxygen control d

Q cr pr-aratic. f.a system heat-up.

Hot shutdown conditions, with low hydroger, and

. r A. cont. trations, were estrblished on September 10th and maintained antil

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j 16th vhe.1 the main coolant system was again cooled down to ambient.

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.. e & wn che' was raintained for the remainder of the month.

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The b m a y sntration in thi main coolant was varied during the month v,

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l' s can aum of 56U p;n during power operation to a maximt=a of 731 p;n for cold

'down.

The gross oeta. gamma activity in the rain coolant attained a maximun of y

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/cc. A surnary of tha analyses perfonne un main coolant samplas taken

. the month is conta h in the following table:

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Main _ Coolant System glinimum Maximum N

o pH at 25 0 5.32 6.45 d

4 Conductivity, umhos 2.'i3 9 02 Boron, p;n 566 731 Chlorides, ppm 4 0.005 0.00:i t

Oxygen, p;n

< 0.005 0.0 10 Hydronn,cc/kgHOatSTP 4

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2 Gr ss eta-camma (15 Min, degassed) ue/ec 0.036

3. 8

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6ur,uc/cc 0.055 0.089 u

.Y, system on

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September {.xceptforashortperiodafterthestart-upofthesecondathe chlorides in the steam generato y

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' ', ', }. ',, p averr r,e activity of the steam paerator blowdown durin6 the month was less than

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Q l x.LO-8 uc/cc.

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6.

R.ADI ATION A!ID }]ASTE DISN) SAL J. '

Radiation surveying consasted of routine plant surveys, J.V. during

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shutdown and naterials shipments. The following maximum radiation readin;s were

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taken:

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.e,

E ocation Radiat,, ion Reading

..p.

.6 C# A Bailding 4

'y 1.2 mrem /hr beta-gcmma Waste Drum Charging Pump (contact with chamber) 2; mrem /hr beta-gamma k

Sample Ecan (door of sample panel) 6.0 mran/hr beta-gamma av 4 ',. *

,, ?

Cnemical I.ab Hot Sink (1" from drain) 0.5 mrem /hr beta-gamma

's

.t RUDF j-o Evaporator (under t - tter i 36 mrec/hr beta-gamma 4

Euporator (contact.aute de upper level) 25 mrem /hr beta-ganm Drum Storage Area (e.*:

fen:e) 5.;.nrem/hrbeta-gamma i

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. SNEC' Operations Report for Santenber 1967..... L O

uc stert neeiettee ne sia 9.v.

Primary Compartment (general upper level) 60 mrem /hr beta-gamma Primary Compartment (contact H.C. pump volute) 2' > mrem /hr beta-gamma Primary Compartment (S.G. bottom) 110 mrcm/hr beta-gamn Primary Compartment (nressurizer bottom) 100 mrm/hr beta-gamma Primary Compartment weneral lower level) 50 mrem /hr beta-gama Primary Compartment (Regen. HX) 170mres/hrbeta-gamma Primary Compartment (Non-Regen. HX) 75mres/hrbeta-gamma Auxiliary Equ4 c. Compartment (S.C.H.I.)

18 mrem /hr beta-gama Auxihary k-

p. Compartment (D.T. top) 15 mrem /hr beta-gn=a Auxiliary Eq u p. Compartment (D.T. bottom) 38 mrcm/hr beta-gamma Auxil$ary Equip. Compt. (general lower level) 5 mrm/hr beta-gamma React. Deck (water level at grating) 18 mram/hr beta-gar.m t

Reactor Nck (instrument parts) 90 mrem /hr beta-gamma ReactorDeck(waistlevel) 20 mrcm/hr beta-ga:re.,a Reactor Deck (storage well railing) 18 mrem /nr beta-gama

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Contamination surveying consisted of routine plant site surveys, surveys of materials shipped, tools, equipr.ent and C.V. during shutdown.

The clean areas were within the "Can Area" limits.

The controlled area was generally within the " Clean Area" limitt, The controlled area was cleu.ed frequently to keep and/or to return it to the " Clean Area" limits. The exclusion areas were cleaned periodically to O

miriimize the amount of smearable contamination. The following contamination levels were observed:

kcation Contamination Reading

/

C&A Nilding Charging Pump Chamber 30400 d/m/ smear bet. ramma Charging Pump Chamber

'10d/m/smearalpha Charging Roca Floor 1495d/m/smearbeta-gamma Sample Room Sink 155000 d/m/ smear. beta-gamma M

Sample Room Sink

< 10 d/m/amear alpha Sample Room Floor 470 d/m/ smear bata-gama Chemical lab Hot Sink 4360 d/m/ smear beta-gamma Cherical lab Hot Sink

< 10 d/m/ smear alpha EOF Pump Roct. Floor 1205 d/m/ smear beta-gama Shipping Room Floor 179 d/r./ smear beta-gama O

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, SNEC Opsrations Report for Sentmber 1967....

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toe ti a ce#t:=t" tie" ne eim" C.V.

Operating Deck

< 10 d/m/ smear bata-gare.a 1660 d/m

/stacar alpha Operating Dock steactor Deck (head heactorDock(head)

D300 d/a/ smear beta-gamma

)

  • 10d/m/smearalpha Reactor Deck (grating) 66000d/m/smearbeta-gamma A

Reactor Deck (grating)

  • 10 d/m/ smear alpha Primary Compartment (grating))

6800 d/m/ smear beta-gamma Primary Campartment (grating

< 10 d/m/smeer alpha Liquid and gaseous effluents from the SNEC site for the month of Sept aber 1967 were as follows (Curie)

(Curie)

(Curie)

Effluent Activity Activity Activity Tfpe Thi;3onth Year to Date last Twelve Menths Tritium 0.843736 5.645050 13 205532 liquid 0.001199 0.017744 0.020385 Air, Xe 4.447667 16 526356 32 342069 Air, I-131 0.000C00 0.000853 0.049720 Air, M.F.P.

0.044477 0.16529 0 323421 Thirteen (13) barrels of waste were omaa for temporary storage.

Twenty-nine (29) drums were shipped frczn the sitei Radiation exposure for all SNEC personnel as measured by film badges for the month of August 1967 were a maximum of 260 mrem with an average of 32.4 mrem.

Radiation exposure for all visiting per ennel as measured by fila badges for the month of August 1967 were a maximum of 200 mrun with an average of 5.5 mrem.

The average radiation exposure for all personnel as measured by fihn ondges for the month of August 1967 was 24.1 mre=.

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SAXTm NUCLEAR EXPERIMENTAL CORPORATION Q

OPD1ATING STATISTICS MONTH Sectember YEAR 1967

}iUCIEAR

. UNIT MONTH M

TO DATE l

TIMES CRITICAL No.

1 W

535 HOURS CRITICAL HRS.

123.06 955.34 19,818.29 TIMES SCRAMMED (MANUAL)

NO.

1 31 322 O TDES QCRAMMED (INADVELTART)

NO.

0 0

31 THERKAL POWER GENERATION MWH 2,782 7 21,177.42 361,262.29 AVERADE BJRhVP (Pu Region)

MM 227.24 1,728.65 12,470.44 CONTROL ROD POSITIONS AT DID OF MONTH AT RUILIBRIUM PCWER OF 0

mit MAIN 0001 ANT BORON 730 ppg RODS CUT - INCHES NO.1 0

No. 2 0

N O.,,,,, o l

NO. 4 0

NO. 5 _. O NO. 6 0

O stECrRICA'.

UN1 HONTN.

_TEs TO ni:E GROSS GDERATION MWH 507 4,008.00 61,483.00 STATION SERVICE HWH 181.24 1,273 71 11,992.90 STATION SERVICE 35.74 31 78 19.51 AVG. PIANT EFFICIDiOf - WH(s)/HWH(t) 18.22 18 93 17.02 AVG GEGRATION RtNNING (119.1_ HRS)

KW 4,256.93 4,371.49 3,404,22 PIANT IDAD FACTOR -

(AVG. GEN. FOR MLaTNAfAI.10AD) 1.61 13.47 20.27 AUXIIIARY STEAM SUPPIY - NUCLEAR l

STEAM SUP; LIED Bt REACTOR HRS.

122.4 929.80 24,420.05 RWDF EVAPORATOR OPERATION HRS.

29.8.9 1,251.57 5,I67.15 o REKARXS

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