ML20085H330

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Monthly Operating Rept for June 1965 for Saxton Nuclear Experimental Corp
ML20085H330
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 06/30/1965
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SAXTON NUCLEAR EXPERIMENTAL CORP.
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FOIA-91-17 NUDOCS 9110280235
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  • 1 SAXTON IfJCIEAR EXPERIMENTAL CORPORATION

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'k Op.erations Report for June 1961 M[';

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1. GCERAL At the beginning of this report period the reactor was in a cold h b condition in continuation of the plant outage begun on Januar,7 22,1965. e fu t s '. f On June 1st the structural materials irradiation capsule assembly was inserted in reactor vessel head port N-6; the 2x2 fuel subassembly (503-9-1) was inserted in port N-1; the nine thimble assembly containing the finx oscillator rod was inserted in port N-2; the 3x3 plutonium fuel subassembly (503-4-26) was inserted in port N-5; and the superheat dummy assenbly was inserted in head port N-4. .

On June 2nd fuel rods No. 701 and No. 702 were inserted in the 3x3 fuel subassembly 503-4-25. The subassembly was then inserted in head port N-:... The removable fuel,mds in subassembly 503-4-25 for the next operating period are Nos.

701, 702,123 and 102.

The filling and venting procedure for the main coolant system was commenced on June 5th. A successful cold leak test of the main coolant loop was conducted on June 7th and heat-up was h~un.

2. REACTOR OPERATIONS The reactor was made critical at 9:31 AM on June 9th. On June 9th and 10th during the 4-12 and 12-8 shift, and on June lith during the 12-8 shift the reactor was used for training purposes. On June 10th, with the mai . coolant system in a

.non-borated condition, the main coolant temperature was raised frca approximately 0

2500F to nomal operating temperature, 530 F, using the reactor as a heat source.

, A successful hot leak test on the main coolant system was conducted at a pressure of 2300 psig.

The secondary system was started up and the reactor was loaded to 15 Wt on June lith. Power operation at 15 MWt continued until June 17th when the power level was increased to 20 Et for a period of eight hours for the purpose of making a flux map of the core and thermal and hydraulic measurements, and then was returned to 15 W t.

Due to a loss of power to the No. 2 turbine-generator auxiliaries and tc the reactor plant water treating motor control center the reactor was shutdown on June 21st. Power was restored and the reactor was returned to 15 Wt operation nine hours after shutdown.

Power operation at 15 W t was continued until June 25th. During the period June 28th to June 29th the reactor power level was increased in a stepwise fashion to 23 5 Wt. After 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of operation at 23.5 Wt on June 29th the reactor was unloaded and shutdown to begin a scheduled plant outage for the purpose of changing two fuel rods in the 2x2 fuel subassembly 503-9-1. Cooldown of the main coolant system was in progress at the close of the month.

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1 SKEC Operations Report for Ju n e 1965 . . . . . . . #2 s

3. , EXPERIMENTAL PROGRAM On June loth a nuclear heat start-up was conducted. With the main coolant system boron concentration at less than 10 p;ra the reactor was used as the source of heat for raising tre temperature of the main coolant from approximately 250 F to 5300F. A heat-up rate sf approximately 800F/ hour was maintained.

The major effort during this report period was devoted to detemining the maximum power level at which the reactor can be operated within license and not exceed a peak power production of 26.5 Kw/ft in the fuel rods of the 2x2 subassembly +

located in the center of the core. Flux maps were made and themal and hydraulic data was taken as the power was increased in steps from 15 Wt to 20 Wt with less than 10 p;n boron in the main coolant and from 18 Wt to 23 5 MWt with 315 ppm boron in the main coolant. At 20 Wt and unborated the wt-n power generated in the' fuel rods of the 2x2 subassembly was calculated to be 22.1 Kw/ft. At a reactor power level of 23.5 Wt and borated the peak power generation in the 2x2 was detemined to be 25.2 Kw/ft.

Amonia was used for pH control during most of this report period. An ammonia depletion test was conducted and pH reactivity effect due to changes in amonia concentration were studied.

4. OPERATIONAL TESTS On June' 8,1965 a nomal test of the safety injection sy mn was conducted.

The radiation monitoring system circuits were tested on June 9th.

The response time from initiation to scram breaker opening was measured for the " main coolant pu=p trip" scram circuit on June 8th. The time was determined to be 0.115 seconds.

5. MAINTENANCE The principal items of mechanical maintenance during the month included the transferring of three fuel subassemblies, the materials irradiation capsule assembly, the nine thimble assembly containing the flux oscillator rod, and the superheat dumy assembly, from storage to the reactor vessel; restoring the reactor vessel head to nomal operating condition; painting the insulation on the volute of the main coolant pump; lapping the acat and plug of the regenerative heat exchanger relief valve; adjusting the stroke and the control air pressure on non-regenerative heat exchanger by-pass valve TIC-24V; replacing the absolute filters and the pre-filters in the exhaust air handlers located in the WDF and the C&A Bailding; acid cleaning the WDF gas compressor manifold drain; installing a new rupture disc on the WDF decontamination roaa liquid storage tank; repairing several leaks on the C&A Building roof; installin6 new belts on the C&A Bailding exhaust air handler; replacing the diaphragms on the vacuum regulating valves on both WDF ges compressors; and cleaning the vacuum line to the water treating acid measuring tary.

1 .

S!E Cierations Report for June 1965 . . . . . . . ?),

Tne mahr items of electrical maintenance during this month included ad$ .ing the brakes on the rotary crane in the containment vessell repairing the

' control circuit of charging pump 110, 2) tecting thJ purification syste flow controller, PRO-223 measuring the response time for the " main coolant pump trip" circuits: removing, drying, and reinstalling the detector for the stack gas radiation monitoring channel, RIC-3; repairing the coant room energy spectrometer calibrating the recorder measuring steam generator flaw and uteam generator pressurel repairing alam swi+,ches on the IMDF gas compressor suction ranifold; decontaminating and recalibrating the detector from containment vessel radiation nonitoring channel RIC-1; replacing batteries in and calibrating the water treatment pH meter; replacing shert4 relay csil in the control circuitry of the pressurizer pressure '

controller PRC-21 repairing the rod drop nlaru circuit; repairing two count room scalers; and fabricating parts for new seals to be installed on the nuclear instrumentation detector containers.

6. ,PIM? CHUGES Fuel subassembly No. 503-t-26 containing 8 rods of mixed Pu0 2-UO3 fuel was inserted in the reactor on June 1, 1,65. Four of the rods contain pelletized fuel and in four of the rods che fuel is vibratory compacted. The plutonium enruhment is 6.6 w/o Puo2+

The 2x2 test fuel subassembly 16 . 503-9-1 which had p eviously been located in a periphery core position was inserted in the center core position on June 1st.

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  • The main coolant system was in a cold shutdc n condition at the beginning of this report period. Hydrazine was added to the main coolant on June 6th and again or. June 7th for oxygen control prior to syste heat-up. The boron concentration in the main coolant was reduced to .N. p;u by bleed e.ad feed and then to 2 p;n by demineralization. A dmineralizar containing a cation resin was placed in service to remove potarsium in preparation for an ammonia stability and pH effects on reactivity tests. Sufficient ammonium hydroxide was added to the main coolant on Jur.c lith to raise the ammonia concentration to 9 3 pin. The ammonia concentration

) decreased to 3.4 pin by June 15th at which time the concentration was further reduced to 0.7 p;n by domineralization. Ammonia was again added to the system on June 16th to a concentration of 11 pyn. This had decreased to 2.8 ppm on the 22nd.

An addition of ammonia on the 22nd increased the concentration to 11 ppm once more.

At the time of reactor shutdown on June 29th the ammonia concentration ha,d decayed to 1.6 ppm.

, A oummary of the analyses made on the main coolant during the month are shown in the following tablet -

Main Coolant Syst m Minimum Maximum

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Conductivity, umhos 1.25 , 49.0 Boron, pin 1.5 1052

< 0.010 0.084

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SNLC Operations Report for Jene 196$ . . . . . _. . #6 Main Coolant Systm (Continued) Minimum Maximum Potassium, ppn 0.03 0.94 Chlori 6ee, ppa <0.005 0.005 (kycen, pin 40.005 ~ 8.0

Crud, ppm 0.035 0.66

  • Armonia, pgs 0.4 11.0 Sodiun, ppa < 0.60 0.60 Activity,15 Min. Gross Beta-cama, uc/cc 2 32x10-3
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  • Reactor in cold shutdown condition Except for a short period after the start-up of the secondary system on June lith the chlorides in the steam generator remained below 0.185 ppn. The average activity of the steam generator blowdwn during the month was less than 1 x 10-8 ue/ce.

J. TRDIATIOM At:D WSTE DISPGA(

Radiation surveying consisted of routine plant site surveys, new fuel M shipments, shipaent of samples and C.V. during shutdown. The following maximum readings were measured.

Ioeation Radiation Readinf, n C&A ruildinn Charging Pump (contact with chamber) 31 mrun/hr beta-gwnma Sample Room (door of sample panel) 30mrm/.rbeta-ganna Chemical IAb Hot Sink (l" from drain) 5.0 mrm/hr beta-gama

\ Waste Drum (baling machine) 10.0 mrom/hr beta-gama Sample Shipment (contact with box) 20.0 mram/hr beta-gama

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TMDF Evaporator (under bottm) l}0 mran/hr beta-gama Evaporator (contact outside upper level) 10 mran/hr beta-gamma 3 5 mram/hr beta-gama

' Drum KasteStorage Area (at IBM fence))

DrumsforStorage(contact 150 arem/hr beta-gama Waste Drums for Storage (meter) 10.0 mran/hr beta-gama 9.V. - 4 Hours after Shutdown Primary Compartment general-upperlevel) 25 mrom/hr beta-gama Primary Compartment contact-MCpumpvolute) 150mrom/hrbeta-gamma Primary Compartment contact - regen. HX)- 90 mram/hr beta-gama Primary Compartment contact-non-regen.HK) 40 mram/hr beta-gama Auxiliary Compartment (general-lower level) 2.0 mram/hr beta-gama t

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S!'S; Operations Report for Jun e 196 5 . . . . . . . #5 beation Radiation Readinr.

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C.V. - 16 Hours after Shutdown Reactor Deck instrument ports) LO mr m /hr beta-gamma Reactor Deck waist level) 25 mrem /hr beta-gama Reactor Deck contact-grating) 40mrom/hrbeta-gamma

!!cw Fuel Pu Fuel Asambly (contact) 8.0 mrez/hr beta-gar:rsa Contamination surveying consisted of routine plant site surveys, surveys of C.V. during' shutdown, new fuel, waste drums for storage, and shipsent of samples.

The clean and controlled areas were generally within the " Clean Area" limits with the exception of permanent exclusion areas and other areas used for decontamination or temporary maintenance and testing. All exclusion areas were cleaned periodically to minimize the amount of amcarable contamination. The following contamination readings were takent loention Contamination Readinn Crd Nildinr.

Charging Pump Chamber 154000 d/m/nmehr beta-gamma Charging Roon Floor 2230 d/m/ smear beta-gamma Sw.ple Room Sink 52]O d /smearbeta-gamma Sample Room Floor 710 d /amear beta-gama Sample Room Sample Panel Tray 109500 d /smearbeta-camma Chemical Inb Hot Sink 5350 d/m/amear beta-gamma TMDF Evaporator Room 666 d/m/emear beta-gamma Pump Room 1920 d/m/ anear beta-gama C.V.

Operating Deck 3070 d/m emear beta-gamma Reactor Deck 232000 d amcar beta-gamma Primary Co=partment (upper) 5000 d emear beta-gama Primary Compartment (lower) 40000 d /*mear beta-gama Auxiliary Compartment (lower) 26300 d /smearbeta-gamma l

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S!E Operations heport for June 19 M , , , . . . , #6 Liquid and gaseous effluents from the SNEC site for the month of June 1965 were as follows: c (Curie) (Ourio) (0ario)

Effluent Activity Activity Activity

?vre This Month Yent to Date Jast Twelve Months Liquid 0.001009 0.005377 0.009867 Air, xe 1.202197 12.028432 49.259389 ,

Air, I-131 0.000058 0.000331 0.000883 Air, M. F.P. 0.012022 0.120285 0.686534 Seven ba' acls of waste were drummed for temperary storage and no drums were shipped from tiio site.

Radiation crposure for all SNEC personnel as measured by film badges for the month of May 1965 were a maxhum of 800 mram with an average of 75 mrm.

P.adiation exposure for all visiting personnel as measured by film bad Ees for the month or May 1965 were a maximum of 250 mrem with an average of 25.5 mram.

Tno radiation exposure average for all personnel as measured by film badges for the month of May 1965 was 49 mrm.

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SAXTON !!UCIEAR EXPERIMENTAL CORPORATIO!1 OPERATING STATISTICS HONTH JUlm YFAR 1965_

wc!rAR pfilI rgId gag TO DATE

.IMES CRITICAL NO. 15 15 392 ll0')RS CRITICAL HRS. 439.52 953 92 11,897.15 TDE SCIWXED (MAliJAL) NO. 7 8 224

  • TD2 4CIWMED (INADVERTANT) NO. 1 1 26 THERMAL P0 DER GENEMTION IWH 6,889.26 16,386.08 194,652.70 AVEMGE 11JRNUp )MD/HTU 331.78 786.29 8,789 20 CONTi10L ROD POGITIONS AT DJD OF 110 NTH AT IAUILITAIUM P0 DER OF 0 )Mt MAIN C001 ANT BORON 278 PfH
    • RODS OUT - INC}D NO. 1 NO. 2 -

NO. 3 -

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NO. 5 , -

No. 6 -

ELECTRICA L UNIT HONTH YEAR TO DATE GROSS GENERATION )NH 914.00 2,509.00 32,155.00 STATION SERVICE }NH 198.04 758.33 7,289.89 STATION SERVICE  % 21.67 30.22 22.67 AVO. PIANT EFFICIENCY - PldH(e)/KdH(t)  %, 13.27 15.31 16.52 AVO. GENERATION RUNNING ( L2L S7 IUts) _

NW 2,157.85 2,676.07 3,234.75 PIANT IDAD FACTOR -

(AVO. GEN. FOR HONTH/ MAX. IDAD)  % 35.86 16.32 22.98 l AUXILTARY STEAM SUPPLY - NUCIIAR

! STFAH SUPPLIED BY RFACTOR HRS. 392.57 8,962.39 906.57 RWDF EVAPORATOR OPERATION HRS. 251.83 251.83 15,839.83

  • REAR};S Manual acram on June 21 at 9:55 AM due to the anticipation of a hot leg scram and loss of emergency feed supply.
    • Reactor shut down June 29, 1965 w

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