ML20085H294

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Monthly Operating Rept for Jan 1966 for Saxton Nuclear Experimental Corp
ML20085H294
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 01/31/1966
From:
SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110280225
Download: ML20085H294 (6)
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SANT0!! !.'UCIEJJ1 EUTRIfSy' TAL CORPO!tATIO!!

,0perations Report for JanurtrL1066 l

l  !

1.

LtEACTOR OPDIATIO!E l At the beginning of this report period the reactor was being operated at a power level of 17 Mit in continuation of the test procrun to detemine the basic physics paranetere and to demonstrate the safe and stabic operation of the partial plutonium l

core (Core II) at power conditions.
E The basic rod configuration used during the month was control rods nos.1, 3, e 4 and 6 at 40 inches (fully withdrawn) control rod no. 2 at 0 inches and control rod 5
controlling between 27 inches and 40 inches.  ;

The power level was increased to 20 Mit on January 7th and after an on site analysis of a flux nap nade at 20 Mit the power level was increased to 21.5 Mit.  :

2  ;

On January 10th, at the request of the GPU load Dispatcher, the reactor power level was reduced to essentially zero and the No. 2 turbine-generator was turned over to Penelee for operation on boiler steam. The reactor was used to follow Xenon from 5:00 AM on January 10th to 7:00 AM on January 13th at which time it was manually ,

sermned so that the containnent vesse3 could be entered for ninor naintenance.

Power operation at 17 Git was resumed at 4:10 IH on January 13th. On January 15th the reactor power level was increased to 22 Ett and was maintained at that level until January 26th. The power level was reduced to 17 Mit on January 26th to obtain flux r, sos with control rod nos. 2 & 5 at 0 inche and then with control rod no. 2 at 0 inches and rod no. 5 at 17.2 inches. On January 27th it was dotemined that a leak had developed in the main coolant purification system inside the containment vessel in the 104 pressure part of the cystem. The '.eal; was estimated to be about 2 callons per minute. Since the leak could be isolated operation was continued. The reactor powoc 1cvel was returned to 22 Mit on January 28th. .

Operation at 22 mit was continued until the last day of the month when the power level was again reduced to 17 mit to obtain a flux map with control rod no. 5 at 40 inches and control rod no. 2 at 26 inches.

l 2 MPDtIMD1TAL PROGRAM

!!easurenents to detemine temperature coefficient, power coefficient and rod wortha were made during the month.

l Xenon was followed for a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after a reduction of power from

$1.5 M!t to 0 lalt.- The total defect due to Xer.on was detemined to be 1.73 percent delta K/ll.

  • Several flux maps were made and thermal and hydraulie data were obtained at a j power level of 17 ffdt, for various positions of control rode nos. 2 & 5, to obtain infomation for use in raising power to 23 5 Mit. ,

3 OpDIATIO!!AL TESTS-C The radiation monitoring system circuits were tested on January 14th.

On January 15th a nomal test of the safety injection system was conducted.

l l 9110200225 910424 l .PDR FOIA DEKOM91-17 PDR -

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S!!C Operations heport for Anu a ry 19'4 . . .__ _ . #

!. . MAIUfrAUCE The principal itens of mechanical maintenance for the nonth included installing a new neehanieni seal en the IMDF evaporator hotwell pumpi repairing the shut-off valve on the hydrogen hanifold t changing the oil in and cleaning the sample room vacuum pumpt repacking the !;o. 2 plunger on No. I charging pumpt installing a new sample line on the RWF evaporator denister; repacking the steam generator saline addition pumpt installing a new service water line to the magnetic clutch on the variable freluency motor generator sett cleaning the relief valve on the cuction line of No.1 chari;ing pump; making a new bolt for a etuffing box on No. 2 charging pumpt cleaning the diaphragm scaled valves on the inlets to the three RWDF gas decay tanks replacing the sight glass on the WDF evaporatort cleaning the check valve in the chlorine pump located in the sewage plant; disassembling and cleaning the varps pump in radiation monitoring systm channel RIC 9 installing new vance in the vacuu.t pmp in the sample room alpha monitor; and repairing the ground vater seal betwean th~e containment vessel and the pipe tunnel floor.

The c.3jor items of elt.ctrical and indtrament maintenance jncluded cleaning the air regulator on the containment vessel inlet purge valvel replacing batteries in and calibrating the water treatment pH meter; replacing the filter paper in the containment vessel particulate sampler of radiation monitoring system channel RIC-1; repairing the computer-indicator for the steam cencrator blowdown radiation monitor, channel CIC-5; replacine the G-M tube on the beta-cama portaole survey meter; calibrating the main st .- flow integrator; inctalling a G-M tube in the charging room area monitor, channel hi A-3; installing a 20 point printer on the radiation monitoring systm recorder; repairing the RUDF 1 ell alam circuitry; cleaning the contacts in the chmistry laboratory pH metert repairing the conputer-indicator for the component cooling uystem radiation monit or, channel RIC-4; and repositioning the detectors for the three power rance nuclear incirunentation channels.

5, CHWTS FRY The nain coolant sybtem cher.istry was maintained for power operating conditions throurhout the nonth. Lithium-7 was used for pH control. The boron concentration was varied over the range 160") p;n naximum down to 636 ppm minimum for physics tests at l power. A summary of the analyses made on main coolant samples taken durint ihe month is contained in the following tablet I

gin Conhnt Sant e Minimum Mayinun pH at 25 c 6.01 6.25 Conductivity, unhos 6.50 11.53 l Boron, ppn 636 1600

! Chlorides, ppm 4.005 4 .005 Lithium, ppn 0.40 0.74 Potassium, ppm 4.01 4.01 Sodiun, ppn 4.01 (.01 0xygen, ppm 4 005 4.005 Hydrogen, ec/kg H 2O 25 52.5 Crud, ppb 17 50 Gross Beta Gamma (15 Min degassed) ue/cc 0.169 2.8 I

Gross lodine, uc/cc 0.083 0.129 The steam generator chlorides were maintained at less than 0.130 ppm through out the month. The average activity of the blowdown continued to be less than 1 x 10-8 uc/ce.

SilLC Operation heport for
'qny r." J9% , , , _ . . d3 ,

i

6. RADIATINI A!iD WABTE DISP 0 SAL
Rn
:intion curveying contiated of routine plant surveys including C&.A Building, L"JF and yard areas. The following naximun radiation readings were takent locM ion Radiation Readinc

,CJA !.pildinn i Wate Drum (baling machine) 40.0 mrem /hr beta-gama Charging Pump (contact with chamber) 3.0 mrem /hr beta-gama Simple Room (door of sample panel) 2.5 mrem /hr beta-gamma  !

i Che~.ical IAb Hot Sink (l" from drain) 16.5 mrcn/hr beta-grena l Teleflex Cable Shirnen* (contact) 6.0 mrem /nr beta-gema

}n/DF, Ivaporator (under botton) 210 mrem /hr beta-grena Evaporator (contact outside) 90 naem/hr beta-gama

Contamination surveying consisted of routine plant site surveys in _the C&A building, HUDP, shipping containers, tools and equipment. The clean areas were within the " Clean Area" linits. The controlled areas were generally within the " Clean Area" linits. The controllod area was cleaned frequently to keep and/or to return it to clean area limits. Tne e;:clusion areas were cleaned periodically to minimize the amount i of smearable contanination. The following maximum contamination levels were observedt incation Contanination Readine ChA Buildint' Charging Pump Chamber 31005 d/m/cmear beta-gamma Charging Roon Floor 18250 d/m/cnear beta-gamma Sanple Roon Sink 1570 d/m/amear beta-garra
Sanple Room Floor 1670 d/m/ smear beta-gamma Chenical lab Het Sink $44700 d/m/enear beta-gamma HUDF i

Pump Room 300 d/m/ smear beta-gamma ,

Shipping Room 420 d/m/ smear beta-ganna Liquid and caseous effluents from the S!EC site for the nonth of January were as follows:

(Curio) (Curie) (Curie) i Effluent Activity Activity Activity Tyre This Month Year to Date last Twelve Mor.the Liquid 0.001522 0.001522 0.009880 Air, Xe O_.007171 0.007171 27.704281 Air, I-131 0,000056 0.000056 0.001640 Air, M.F.P. 0.000072 0.000072 0.277044-5

SliEC Operations lleport for Yahu*try 19# h .

. . . . f/4 One barrel of waste was drummed for temporary storage. !ia drums were shipped from the site.

Radiation expocure for all SEC personnel as measured by film badges for the month of Decenbe.1965 were a maxinum of 480 mrem with an average of 45 2 mrm.

Radiation exposure for all visiting personnel as measured by film badges for the nonth of December 1965 were a maximum of 90 mram with an ave w of 5 5 mrem.

The av3 rage radiation exposure for all personnel as measured by film badges for the month of December 1965 was 25.l. nrem.

t

u SAXTON NUCLEAR EXPERIMDITAL CORPORATION OPERATING STATISTICS MONTH J!d!UedlY YEAR _1966

!!UC"%R UNIT 110 NTH

, YEAR TO DATE TIMES Ch. 'ICAL N^. 1 1 456 l'a.!S CRITICAL HRS. 717 737 13,619.13 TIM 6S SCRAIED (MANUAL) NO. 1 1 263 j

  • TDIES SCRAMMED (INADVERTANT) NO. 0 0 29 THERMAL PGIER GENERATION MWH 13,029 75 13,029.75 222,274 58 AVERAGE alRNUP (Pu llegion) )MD/MTV 1,063.6 1,063.6 1,125 3 CONTROL Rob POSITIONS AT DID OF }!ONTH AT BlUILIBRIUM P0fER OF 16.87 MWt MAIN C001 ANT BORON _1598 _, PPM ,

RODS OUT - INCHES N O. 1 40 NO. 2 25.67 NO. 3 40 NO. 4 LO _ NO. 5 40 NO. 6 40 E.LECTRICAL U!GT MONTH YEAR TO DATE GROSS ODIERATION FMH 2,197 00 2,197 00 36,479.00

) S'"ATION SERVICE MdH 236.48 236.48 8,438.77 STATION SERVICE T 10.76 10.76 23.12

/ VG. PIANT EFFICIENCY - 1m(s', . m(t)  % 16.86 16.86 16.42 AVG. GENERATION RUNNING . (6 .g 'S) KW 3,375.33 3,375.33 2,945.20 PLANT IDAD FACTOR -

(AVG. GEN. FOR MONTH / MAX, LOAD)  % 75.33 75.33 22.75 AUXILIARY STEAM SUPPLY - NUCLEAR STEAM SUPPLIED BY REACTOR HRS. 681.50 681.50 10,380.47 RWDF EVAPORATOR OPERATION HRS. 218.25 218.25 2,279.50

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