ML20085H069

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Monthly Operating Rept for Aug 1967 for Saxton Nuclear Experimental Corp
ML20085H069
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 08/31/1967
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SAXTON NUCLEAR EXPERIMENTAL CORP.
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ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110280124
Download: ML20085H069 (6)
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SATION NUCLL. 'JtI!G%TAL CDPJORATION Operations Report for August 1967 g

1. RFACTOR OPERATIONS At the beginning of this report period the reactor was in a hot shutdown condition, brop times i,.r all six control rods were measured on August let and 2nd, The reactor was made crit: cal at 11:28 AM on August 4th for the first time since February 1, 2967. During the period August 4th through August 18th, on the 8-4 shift, the reactor was ocerated for reactor start-up training and operator licensing. Two SNFL employees, one Metropolitan Edison Company employee, six Rochester Gas and Electric Company sployees and five Nordostschwertzeriseke Kroftwerke A.G. employees were given start-up training. A total of forty training start-ups were made. On August lith 'wo SNEC employees completed Atomic Energy Commission administered examinations for reactor operator licenses.

On the 4-12 and 12-8 shifts during the period August 14th through August 18th the supercritical technology test loop was operated for training purposes.

'he main coolant system was cooled down on August 21st so that repairs could be made to a simmering relief valve on the supercritical loop.

On August 23rd heat-up of the main coolant system was initiated. Tne nain colant pump and the pressuricer heaters were the source of heat. Operating conditions of 515 F and 2000 psi pressure were attained on August 25th.

The reactor was made critical at 5:13 PM on August 28th. The secondary system was started up and the reactor was loaded to 17 Mwt. On August 29th after a partiti flux map was made and analyzed the reactor power level was increasef to 23 5 MWt.

i..,cr operation was discontinued and the reactor was manually shut down c' August :dth. The main coolant system was cooled down to 260 F so that rellei have V-53 on the purification system *egenerative heat exchanger could be 1

re W red and reset.

The reactor was mace critical on August 3?st and was used to heat the main coclant system from 2600 F to 515 F. Upon completion of the heat-up the reactor was shutdown.

2. FlPERI!TJTAL PROGRAM With the reactor shut down and thc main coolant system at normal operating-temperature and pressure, the supercritical temperature and pressure test loop (STP loop) was operated at various pressures and temperatures tc determine the adequacy of the loop for use in possible future experiments in connection with the steam cooled breeder reactor concept.

The STP loop was operated for start-up and shtt down training on the 4-12 and 12-8 shif ts on weekdays during the period August 14th c.hrough Augur, 28th.

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SNEC Operations Report for August 1967 1,1,3,. . . d2 High pressure relief valves PSV-1 and PSV-2 on the STP loop lifted when the loop was inadvertently pressurized during a start-up operation on August 20th.

Valve PSV-1 did not completely seal-off when the pressure was reduced. A cool duwn of the reactor main cooked system was necessary to effect a repair to the valve.

On August 29th and 30th the STP loop was operated at supercritical tenperatures and pressures for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period with the reactor at a power level of 23 5 MWt. Operation was curtailed when the reactor main coolant system was cooled down to repair leaking relief valves on the purification system.

All functional testing and operation of the STP loop during the month was perfomed . tith a dum:y assembly installed in the pressure tube.

3 OPERAI1,0NAL 1 TFSTS The radiation monitoring system circuits were te,ted on Angust 17th.

A successful test of the safety injection syceem was completed on August 25th.

Drcp times were measured for all six control rods with the main coolant system being maintained at normal or . rating conditions of temperature, pressure and flow. The minimum drop time revo.ded was 0.830 seconds and the maximum was 0.991 seconds. Cont rol rods No. 2 and No. 5 were dropped a total of ten times each from the full out position, 40 inches. Each of the other four rods were dropped five times. The mavinum drop time recorded for control rod No. 2 was 0.903 seconds and that for controA rod No. 5 was 0.918 seconds.

4. MAINTEMM!CE The principcl items of mechanical maintenance for the conth included lubricating the bearings in all outdoor air handlers; installing new sheaves on the containment vessel exhaust fan; cleaning the inlet air handlers to the control and auxiliary building, the containment vessel and the radioactive waste disposal facility building; replacing the absolute filters and the prefilters on the exhaust air handlers for the radioactive waste disposal building and for the chemistry laboratory hoods; installing an eductor on the HWDF evaporator demister drain line; cleaning the sludge frm: the bottoms of the two RWDF liquid monitor tanks; replacing a shut-off valve on the RWDF evaporator anti-foam addition tank; replacing the plug and diaphrag; in the shut-off valve in the pressure gauge line to RWDF gas decay tank No. 2; eaning check valves on the RWDF gas decay tank; lapping the seat and disc in the p afication system low pressure re?ief valve V-60; replacing the 0-rings on the packing nut for plungers No. 2 and No.1 on No. 2 charging pump and plunger No. 2 on No.1 charging pump; replac4ng the che k in the auxiliary steam line check valve, V-1007; replacing the ruptui4 i se an the caustic pump for the RWDF liquid storage tanks; disassembling the m= :.,. tic clutch for the variable frequency motor generator set for inspection and transporting the disassenbled clutch to the Pennsylvania Electric Coil Company r.1 Pittsburgh for repair; painting the outdoor gas manifolds, instrument cabinetn ar.s other metal surfaces; installing discharge piping for a yard area sump pump; replacing une gaskets on the prepost filters in

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SNE0 Operations Heport for August 1967 . .. . . . #3 the purification system; lapping the seat and machining the disc in relief valve V-53 on the regenerative heat exchanger in the pur4 fication system; and procescing five drums of K@F evaporator bottoms.

Tne major itens of electrical and instrument maintenance included cleaning the level probes on the EGF liquid monitor tanke; checking and replacing vacuum tubes in the power supply for nuclear instrumentation source range channel A; rmaking a cable connection on nuclear instrumentation intemediate range channel A; replacing a vacuum tube ir. the log microammeter for nuclear instrumentation intemediate range channel A; cleaning the flow meter which measures the effluent from the R@F discharge tanks to the river; measuring the scram response times for the three reactor scram circuits originating in the supercritical test loop; repairing the chart drive on the nuclear instrumentation start-up range recorder; replacing a defactive decade unit in the ga=ma '

spectrometer in the count room; repairing the hand monitors in the moniter room; replacing defective resistors and a battery board in a CP-3 portable survey 1 eter; repairing a decade unit in a G-M scaler in the count room; cleaning the air regulator on the pneumatic controller for pressurizer heater group No. 3; repairing the arc?. radiation monitor in the charging room; calibrating the pressure gauges on the boiler feed pumps; repairing the computer indicator for the steam generator blowdown radiation monitor, RIC-5; c. leaning the contacts on the selector switch in the radiation monitoring system recorder; cleaning the G-M tubes and resetting the high voltage en the stack gas radiation monitor, RIC-3; and repairing the instrument air line to the speed controller for- 2 charging pump.

5. CHD!ISTRY period.

The reactor was in hot shutdown condition at the beginning of this report Until hydrogen was added en August 26th in preparation for power operation., oxygen control in the main coolant system was accomplished by means of hydrazine edditions, as required, to keep oxygen content below detectable limits.

The main coolant boron concentratien ranged from a high of 1117 ppm before heat-up to a low of 581 p;n later in the month. Crud level in the main coolant after heat-up wan detemined to be 53 ppb. A su= mary of the analyses perfomed on samples taken from the main coolant system during the month is contained in the following table:

Main Coolant System Minimum Fjaximum pH at 25 C 5.45 6.18 Conductivity, umhos 2.33 Boron, p;n 11 74 584 1117 Chlorides, p;n < 0.005 0.010

. Lithiu=, ppm < 0.01 < 0.01 0xygen, p;n < 0.005 Hydrogen, cc/kg H 2O 0.015

<5 35 Crud, ppb (one detemination) 53 53 Gross Beta Gamma (15 Min. desassed) ue/cc 0.0184 3.68 Tritium,ue/cc 1.06x10-2 5.27x10-2 The chlorides in the steam generator were maintained below 0.230 ppn. The average activity of the steam generator blowdown during the month was <;lx10-E ue/cc.

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SNEC Operations Report for Aucunt 1967 . . ...o #4,

6. RADI AHON AND WASTE DISPOSAL Radi,ation surveying consisted of routine plant surveys, C.V. during shutdown and materials shipments. The following maximum radiation readings were taken:

locati or. Radiation Readir.e C&A Building Waste Drum (baling machine) 1.5 mrem /hr beta-gama Charging Pum- (contact with chamber) 25 mrem /hr beta-gama Sample Room (door of cample panel) 6.5 mrem /hr beta-gamma Chemical 1sb Hot Sink (l" from drain) 0.25 mrem /hr beta-gama RUDF 1

Drum Storage Area (at HRA lence) 6.0 mres/hr beta-gama C.V.

Primary Compartment (general upper level) 45 mrem /hrbeta-gamma Print.ry Compartment (contact M.C. pump volute) P90 mrem /hr beta-gar a Primary Compartment (S.G. bottom) 100 mrem /hr beta-gamma Primary Compartment (pressuriser bottom) 90 mrem /hr beta-gamma Primary Compartment (general lower level) 50 mrem /hr beta-gamma Primary Compartment (Regen. HX) 150 mrem /hr beta-ga=ma Primary Campartment (Non-Regen. HX) 38 mrem /hrbeta-gamma Auxiliary Equip. Compartment (S.C.H.X. ) 13 mrem /hr beta-gama Auxiliary Equip. Compartment (D.T. top) 11 mrem /hr beta-gamn Auxiliary Equip. Compartment (D.T. bottom) 105 mrsa/hr beta-gamma Auxiliary Equip. Compartment (general lower level) 10 : rem /hr beta-gama Reactor Deck (water level at grating) 20 mrem /hr beta-gama Reactor Deck (instrument ports) 2 50 mrem /hr beta-gama Reactor Deck (waist level) 12 mrem /hr beta-gamma Reactor Deck (storage well railing) 20 mrem /hr beta-gama Contamination surveying consisted of routino plant site surveys, surveys of materials shipped, tools, equipment and C.V. during shutdown. The clean areas were within the " Clean Area" limits. The controlled area was generally within the

" Clean Area" limits. The exclusion areas were cleaned periodically to minimize the amount cJ smearaole contamination. The following contamination levels were observed:

Location Contamination Reading C&A Foi] ding Charging Room Flecr 1133 d/m/ smear beta-gal::a Sample Room Floor 125 d/m/ smear beta-gamma Chemical Iab Hot Sink 9300 d/m/ smear beta-gama Chemic 11 Iab Hot Sink < 10 d/m/ smear alpha i

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SNE0 Operations Report for August 1967 . . . . . . d5 Liquid and gaseous effluents from the SNEC site for the month of August 1967 were as follows:

(Curie) (Curie) (Curie)

Effluent Activity Activity Activity Type This Month Year to Date Last Twelve Months Tritium 0.000405 4.801314 15.319613 Liquid 0.000148 0.016444 0.020096 Air, Xe 1.024586 12.078689 39.638111 Air, I-131 0.000003 0.000853 0.104221 Air, M.F.P. 0.010246 0.120787 0.396?81 Six (6) barrels of waste were drummed for te=porary storage. No drums were shipped from the site.

Radiation exposure for all SNEC personnel as measured by film . idges for the month of July 1967 were a maximum of 910 mrem with an average of 55 7 mrem.

Radiation exposure for all visiting personnel as measured by film badges for the month of July 1967 vere a maximum of 230 mrem with an average of 16.4 mrec.

"he average radiation exposure for all personnel as measured by film <

! badges for tnc nonth of July 1967 was 41 mrem. '

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4 SAXTG1 NUCLEAR EXPERIMENTAL CORPORATION OPERATING STATISTICS MONTH AUGUST YFAR 1967

,NUCI?AR UNIT  !!QNE YFAR TO DATE TIMES CRITICAL No. 39 39 534 HOURS CRITICAL HRS. 77 58 832.23 19,695.23 TDZS SCR/J220 (MANUAL) NO. 29 30 321

  • TDCS QCR/J'JTD (INADVERTANT) NO. 0 0 31 THERMAL POWER GENERATION MWH 729 70 18,394.72 358,479.59 AVERAGE BJRNUP (Pu Region) WDM 59 56 1,501.51 12,243 30 '

CONTROL ROD POSIYIONS AT SiD OF MONTH AT BlUILIBRIIH POWER OP O MWt MAIN CO3IANT DOP,0N 730 PPH RODS OUT - INCHES NO. 1 _ 0 NO. 2 10 NO. 3 0 NO. 4 0 NO. $ 10 NO. 6 0 LLECTRICAL UNIT MONTH _YEg TO DATE OROSS GENERATION MWh 134.00 3,501.00 60,176.00 STATION SERVICE MWH 246.72 1,092.47 11,811.66 STATION SERVICE  % 184.12 31.20 19.37 AVG. PLANT EFFICIENCY - WH(e)/MWH(t)  % 13.36 19.03 17.01

,cp. GENERATION RUNNING ( 39.3 HRS) KW 3,409.67 4,410.71 3,398.56 PIANT IDAD FACTOR -

(AVG. GEN. FOR MONTH / MAX. LOAD)  % 3.98 13.22 28.46 AUXIIERY STEAM SUPPLY - NUCLEAR STEAM SUPPLIED BY REACTOR HRS. 52.9 807.40 16,297.65 RWDF EVAPARATOR OPERATION ES. 13.0 1,022.67 4,938.25

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