ML20085H350

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Monthly Operating Rept for Dec 1964 for Saxton Nuclear Experimental Corp
ML20085H350
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 12/31/1964
From:
SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110280246
Download: ML20085H350 (7)
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Text

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h:CO:: TCLEAR EXPERIMENTAL CO?SOMTION Operat :onn Hegrt for December IM4 1

GEhTRA L The plant outage which was begun on Novmber 27th was continued until Decenber 13th.

During this period test fuel subassemblies 503-4-25 and 503-4-1 were rooved from core locations N-1 and N-5 respectively and were examined with the unde water periscope.for crud deposition.

Upon completion of the inspection the subassmblies were returned to the core locations from which they'were reoved.

On December 9th the main coolant system was filled and the venting procedure war commenced.

A successful hydrostatic test was completed on December 10th.

After completing scram circuit response time measurements on Deember lith, heat-up of the main coolant systm was initiated.

Normal operating conditiohs of temperature and pressure were attained on Decenber 13th.

2.

REACTOR 0?ERATIOh5 On December 14th and 15th the reactor was operated for reactor start-up' training for one SNEC employee, two Southcrn California Edison Company trainees and four French trainees.

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The reactor was made critical at 10:37 AM on December 16th.

systc= was started up and the generator was cynchronized on the line at 5:The secondary 08 PM.

A steady state reactor load of 20 M4t was established at 5:28 PM.

The secondary system was shut down and the recetor was shut down at 5:03 AM on December 17th wh apparent unexplained reactivity loss exceeded the specified limit.

evalwion disclosed a prediction error in accounting for pH effect.A subsequent Tha reactor was taken critical again at 12:

the day to follow the Kencn transient.38 PM and was operated at low power for the remainder The reactor was shut down by nanual scram on the morning of Deceber 18th so that the containment vessel could be entered to repair a leak in a service water line.

The reactor was'made critical again at 11:26 AM and start-up of the secondary system was initiated.

The generator was synchronized on the line at 1:54 PM.

Edt reactor load was established at 2:07 PM.

Twenty level was reduced to 10 Kdt. Operation at,20 MWt continued until Deember 21st when th Operation at 30 MJt continued fr the remainder of the month.Da December 23rd 3.

EXPERIME1TAL PROGRiK Test fuel subassemblies 503-4-1 and 503-4-25were removed from the reactor core and were examined with the underwater periscope for crud deposition.

subassenbly 503-4-1, removed fram core locatlon N-5 on the periphery of core showed no Tn e.

crud. The fuel rods in the subassembly 503-4-25, which had occupied the center core position (N-1) showed crud deposition in the general area between the second and thir grid as measured from the top.

surfaces facing the container walls. Generally, the deposition occurred only on the rod cod nor on the inner surfaces of the outer rods.There was little or no crud some of the crud for chemical analysis was not successful.An attempt to rmove and collect v

conditions were established in the core in an effort to detemine hideout occurs in a crudded core under nucleate boiling conditions, 9110280246 910424 PDR FOIA DEKOK91-17 PDR

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. #2 Tests to detemine tne effect of main coolant pH changes on reactivity f or a crudded core were conducted.

Noise nonsurements were made prior to each change in power and were alao made before and after pH changes were made.

4.

OPERATIONAL TESTS On December llth the response time from scram initiation to scram breaker opening was measured for all scram circuits.

The manual scram response time was 0.033 seconds. The minimum automatic scram response time was A l seconds and the maximum was 0.200 seconds.

leak tests on the main coolant syste for both cold and' hot conditions were conducted. Visual inspection revealed no external leakage.

On December 15th a normal test of the safety injection system was conducted.

The radiation monitoring system circuits were tested on Dece.ber 23rd.

5 MAINTZAZE Tne principal itms of mechanical saintenance for the month included removing two 3x3 fuel subassemblies from the reactor core, handlird them for inspection with the underwater periscope, and returning them to the reactor t: ore; restoring the reactor vessel head to nor:;al operating co'nditions; repairing a cable on the underwater periscope; repairing two breaks in the carboline coating on the storage well walls; enlarging the holes in the adapter used for storing single rods in the fuel storage rack; installing new and stronger chain and sprockets on the single rod handling tool; repacking the boric acid mix tank pump; replacing the cartridges in the boric acid mix tank filters; repacking the steam generator surface and bottom blowdown motor operated valves; repacking the autonatic valve on the air handler in the control rod drive mechanism room; replacing a disc in the liquid drain valve on Gas Decay Tank No.1; processing eight drums of RWDF evaporator concentrates; replacing the solenoid operated cump valve on the Rh'DE evaporator hotwell; replacing the top flange on tha acid flow meter of the make-up water treating plant; replacing a cylinder head gasket on charging pump No.1; replacing,the air pump on environment survey station No.1; cleaning the seat of a valve in the sample line for the RWDF liquid storage tanks; replacing the plunger and installing new C. Ice Cook seal rings in the No. 3 stuffing box of No. 2 darging pump; repacking all three stuffing boxes of No.1 charging pump; and changing tne ~ l in the transmission housing of No.1 charging pump.

The major it' ens of electrical maintenance included installing special raciation detecting equi;nent in the containment vessel for fuel handling; cutting back the cables and remaking the cable connections to the detector and'the cable seals to the enclosure for the detector in intemediate range channel A; fabricating a nuclear detector cable seal for tests; calibrating the containment vessel pressure transmitter; calibrating the storage well demineralizer flow meter; running a plateau on the BF3 in source range channel A; repairing the high voltage supply in the pulse height analyzer; repairing the calibration unit in the radiation monitoring system; repairing the function generator in the controller for the pressurizer heaters; adjusting the v

position controller on the pressurizer spray valve; repairing the low voltage power supply fer intemediate range channel A nuclear instrumentation; replacing the float on the MDF tunnel sump pump; adjusting the temperature controller TIC-23 in the purifix. ion system, and measuring th-scram circuit response times.

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TJ }prnticr.s Report for

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.h C.

PUGT CHW3ES A valve was installed in the inlet line to the volume tank hcusing the detectcr for radiation monitor channel RIC-6 which monitors the liquid discharged to the river fra the EOF discharge tanks and the monitor tanks.

This change facilitates the calibration of the detectcr and the decontamination of the volume tank.

7.

CHmISTRY The main coolant system was in'a cold shut down condition at the beginning of this report period for the purpose of inspecting two fuel subassemblies, one from

.he center of the core and the other from the periphery,- for crud deposition. _ On December 9th the main coolant system was filled ar' venting was initiated.

The boron concentration was 741 ppm.

  1. drazine was added on December 10th.. The boron concentration was reduced to 460 ppm by bleed and feed on December 13th.

Eydrogen was added on December 14th and 15th. The domineralizer containing the cation resin was placed in service on December 15th to remove ammonia. -

On December 22nd a pH effect on reactivity test was inij,iated. The potassium concentration in the main coolant was increased in three steps from a concentration o ' less than 0.1 ppm on Deec::Qer 22nd to 8.45 ppm on December 30th.

On December 31st the potassium concentration was reduced by domineralization to 0.2 p;n.

The boron concentration in the main coolant on the last day of the month was 389 pin.

y 7

A summary of the main coolant chemistry analyses made during the month are contained in the following table:

i Main Coolant System Minimum (

Maximum j

Conductivity, unhos 3 75 31.2 Boron, ppm 389 1019 (*)

l Potassium, p;n (0.1_

8.45 I.ithium, ppb (25.

113 Chlorides, ppm.

<.0.005

.010

%drogen, ec/Kg H O

<5

(*)

32.1 2

0xygen, pin (0.005 7 0.5 (*)

Anmonia, p;n 0.37 3.4 Crud,' ppm 0.054 3.28 (**)

l 15-Min. Gross Beta Ga.ma, ue/cc 0.046 2.36 (***)

(*)

' Reactor in cold shutdown condition-(**)

Main coolant water circulating coM -

(**) - Sample taken im.ediate'ly after attaining 20 L'T following start-up on 12-18-64 The silver activity in the storage well water was measured.to be 2.26 x 10-5 Except for a short period after secondary system start-up on December 18th v

l the chlorides in the steam generator were maintained below 0.290 p;n. The blowdown-required during this operating period was higher than nonnal. This is indicative of l

increased leakage in the condenser. The activity of the steam generator blowdown -

averaged less than 1 x 10-8 ue/cc above river water background for the month.-

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RAD"ATION At;D WASTE DISPIAL m.

Radiation surveying eensisted of routine plant site surveys, L'DF, vaste The drums for storage, containment vessel and a shipment of radioactive samples.

following maximum readings were taken:

Radiation Readins; location _

RWDF 110 mrem /hrbeta-gamma Evaporator (under ' ottom) 36mre./nrbeta-gamma Evaporator (contact outside upper level) 120 mrem /hr beta-gamma Waste Drum (for storage - contact) 8.5 mrm/hr beta-gamma Waste Drum (for :torage - meter) 15.0 mr e/hr beta-gamma Drum Storage Aret (at HRA fence)

C&A Building 17 mrem /hr beta-gamma Waste Drum (baling machine - contact) 50 mrem /hr beta-gamma Charging Pump (contact with chamber) 6.5 mren/hr beta-gamma Sample Room (at door of panel) 16 mrem /hr beta-gama Chemical lab Mot Sink (l" from drain) 8.0 hrem/hr beta-gama DrumContainingSamples(contact)

C.V.

80 mrem /hrbeta-gamma Reactor Deck (at instrument ports) 26 nrem/hr beta-gamma Reactor Deck (waste leve])

90 nrm /hr beta-ga=a Reactor Deck (contact grating)

Renoval of Detector from Instrument Forts (at l')2000 prem/hr beta-gamma Ya:d Area C.V. Exhaust Filters (contact - inside housing 7.5 mr m/hr beta-gamma at filters) i C.V. Exhaust Filters (contact - outside housing-2.0 mrm/hr beta-gama l

at filters)

At Fence (clocrst point to filter housing) 0.35 mren/hr beta-ga=a O.75 mrm/hr beta-gama 80,000 Gallon Storage Tank Contamination surveying consisted of routinc plant site surveys, surveys of the C.V. during shutdown, L'DF, tools, waste drums and a shipment of radioactive The follovir.g contamination readings were taken:

samples.

Cgntamin" tion Reading Iocation RWDF 8200d/m/smearbeta-gamma Pump Room 730 d/p/ smear beta-ga=a Evaporator Room 2900 d/m/ smear beta. gamma y

Concentrates Room 190 d/m/ smear beta-gama Pipe Tunnel

i Operaticns Report for mur m....

45 L: cation Contamination Rendinc CLA Buildinc Charging Pump Cnamber

$10000 d/m/ smear beta-gamma Chr.rging Room Floor 8150 d/m/ smear beta-ga.ma Sample Room Sink 7300 d/m/ smear beta-gamma Sample Room Floor 7300 d/m/ smear beta-gama Che-ical lab Hot Sink 10000 d/m/ smear beta-gar.ma One.ical lab Bench Area 800 d/m/ smear beta-gamma C.V. (After lowering of storage well)

Upper Operating Deck 4270 d/m/ smear beta-gama lower Operating Deck 6680 d/m/ smear beta-t,ama Bridge 13500 d/m/ smear beta-gama Reactor Deck 364000 d/m/cmear beta-gamma Liquid and gaseous effluents from the SNEC site for the' month of December were as follows:

t (Curie)

(Curie)

(Curie)

Activity Activity Activity Effluent Type This Month Year to Date last Twelve Months v

Liquid 0.001048 0.021025 0.021025 Air, Xe 5.628077 37.230957 37.230957 Air, I-131 0.000278 0.000552

,0,000552 Air, M.F.P.

0.056279 37.757153 37 757153 Sixteen barrels of waste were drumed for temporary storage and no waste was shipped from the site.

Radiation exposure for all personnel as measured by film badges for the month of November,1964, were a maximum of 165 mrem with an average of 16 mrem.

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F.evisior. 21 SAXTai NUCLFAR EXPERIME!!TAL CORPORATION OPERATING STATISTIC _S MONTH December YFAR 1964 1."JC LFAR UNIT HONTH YEAR TO DATE TIMES CRITICAL NO.

9 40 277 HOURS CRITICAL HRS.

371.19 4,203.27 10,943.23 TIMES SCRAMHED (MANUAL)

NO.

8 33 216

  • TDO:S QCRAMMED (INADVERTANT)

NO.

0 6

25 THERMAL POWER GENERATION MWH 6,129.17 77,264 35 178,265 82 AVERAGE W RNUP WDAM 293.31 3,330 52 8,002.49 CONTROL ROD PWITIONS AT IND OF MONTH AT EQUILIERIUM PCWER OF 20 MWt MAIN CCOIANT DORON 390 PPM RODS 007 - INClGlS NO. 1 40 NO. 2 40 NO. 3 40 NO. 4 40 NO. 5 -

23.27 NO. 6 40 EIECTRICAL UNIT HONTH YEAR TO DATE m

GROSS GENERATION MWH 973 00 12,867 29,607 STATION SERVICE HWH 197.99 2,268 37 6,531.56 STATION SERVICE 20.35 17.63 22.06

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AVG.PIANTEFFICIENCY-HWH(e)/HKH(t) 15.87 16.65 16.61 AVG. GENERATION ENNING ( 333.80 HRS)

KW 2,914.92 3,378.21 3,325.51 l

PIANT IDAD FACTOR -

(AVG. GEN. FOR MONTH / MAX. ICAD) g 39.27 33.29 28.23 AUXILIARY STEAM SUPPLY - NUCLEAR STEAM SUPPLIED E REACTOR HRS.

335.77 3,828.64 8,954.34 PMDF EVAPoiMTOR OPERATION HRS.

90.42 837.32 1,780.97

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