ML20085H098

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Monthly Operating Rept for Apr 1967 for Saxton Nuclear Experimental Corp
ML20085H098
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 04/30/1967
From:
SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110280137
Download: ML20085H098 (5)
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SAXTON NUCLEAR EXPERIMENTAL CORPORATION Operations Report for April 1967 I

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1. GENERAL i The scheduled plant outage which was begun on February 1st was continued throughout this report period.

Miscellaneous maintenance work on the main coolant loop and the auxiliary systems was performed concurrently with shakedown work on the supercritical technology test loop.

2 EXPERIFENTAL PROGRAM Work on the shakedown of the supercritical technology test loop and training for the loop operators was continued throughout the month. A problem of cavitation in the condensate pumps was experienced when the deaerator was operated at 2.2 psia pressure and 130 F temperature. The problem was corrected by relocating the condensate pumps to a lower level in the containment vessel and increasing the pipe size between the deaerator and the suction of the condensate pumps from 1" to l}". All functional testing during the month was performed with a short section of piping installed in place of the pressure tube.

3. OPERATIONAL TESTS The radiation monitoring system circuits were tested on April 14, 1967,
l. . MAINTENANCE

( Tne principal items of mechanical maintenance during the month included replacing three rings of packing on No.1 safety injection pump and two rings of packing on No. 2 safety injection pump; cleaning and flushing the cooling water jackets on the packing glands of the safety injection pumps; replacing a section of the piping supplying cooling water to the packing glands on the safety injection pumps; replacing the rupture disc on RUDF spent resin storage tank No. 1; cleaning and painting the two shutdown cooling system pumps, the two discharge tank pumps, the two storage well system pumps, the two component cooling system pumps and the hydraulic ends of the two safety injection system pumps and the two charging system pumps; installing a new mechanic ' seal on storage well system pump No.1; repairing the insulation on the top of the pressurizer and on the main coolant pump volute; painting the insulation on the main coolant pump volute, and on sections of the main coolant system piping; painting the pressurizer safety valves, the containment vessel vacuum breakers, and the water meter in the demineralized water make-up line to the purification system surge tank; replacing the l fan belt on the switchgear room exhaust fan; fabricating a test stand for testing the I

high pressure steam relief valves on the secondary system; checking the set point of the relief valva for the high pressure steam piping in the secondary system; repairin6 the extension handle on the stem of V-1809, sluice valve to the resin storage tanks; installing new fan belts on the containment vessel exhaust fan; replacing the diaphragm l and plug in valve V-1399 on RWDF gas decay tank No. '3; flushing the RWDF gas compressor l manifold drain to the sump; repairing the pump for the portable alpha monitor in the chemistry laboratory; processing seven drums of evaporator bottoms; steam cleaning the filters for the control room air conditioner; repairing the pump for an environmental air sampler and opening the RUDF evaporator condenser for inspection.

9110200137 910424 PDR FOIA DEKOK91-17 PDR

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W C sparations Report for swr 3 W7 . . . . . . #2 The major items of electrical and instrument maintenance included checking the specific gravity of the station service batteries; repairing the river water meter in the steam generator blowdown cooling line; sampling and testing the oil in the 1000 KVA transformer; cleaning contacts on the chemistry laboratory chromatograph; checking the automatic control circuits of the electrical switchgear for proper performance; repairing chart drive mechanism for the nuclear instrumentation power range recorder; replacing the solenoid valves in the air suoply to the pneumatic controllers for the charging pump drives; replacing three diaphragms in the pneumatic controlle on the drive of charging pur.p No.1; installing new temperature indicators on the deaerating water storage tank in the secondary system; cleaning the breaker cabinets in the electrical switchgear room; repairing the area monitor for beta-gamma radiation in the chemistry laboratory; sampling the desiccant in the instrument air dryer; calibratir6 the level controller for the steam generator; replacing two time delay relays in the automatic switching circuits of the inverter-diverter; repairing a decade unit for a count room scaler; repairing the pH meter in chemistry laboratory; replacing batteries in and calibrating the pH meter on the make-up water treating panel; repairing the paging phones for the primary compartment and the operating area in the containment vessel; repairing a type CP-3 portable radiation survey meter; calibrating a main coolant system pressure monitoring and recording channel; calibrating the containment vessel pressure monitoring and indicating channel; and calibrating the pressure gauge on the discharge of the safety injection pumps.

5 CHEMISTRY The main coolant system chmistry was maintained for cold shutdown conditiow throughout the month. A summary of the analyses made on main coolant samples taken during the month is contained in the following tables Main Coelant Samples Minimum Maximum pH at 2500 5 78 5 98 Conductivity, umhos 6.15 7.27 Boron, p;n 955 1052 Chlorides, p;n 4 0.005 < 0.005 0xygen, ppm (one detemination) 4 33 L.35 Gross Beta Gamma (15 Min. Degassed) ue/cc 0.451 0.662 Tritium,ue/cc 6.41x10-2 6.57xlo-2

6. RADIATICU AND WASTE DISPOSAL Radiation surveying consisted of routine plant surveys, C.V. during shutdown and materials shipne:. s. The following maximum radiation readings were taken:

location Radiation Reading 1

CAA Buildinn Waste Drum (baling machine) 30 mrem /hr beta-gamma Charging Pump (contact with chamber) 35 mrem /hr beta-gamma Sample Room (door of sample panel) 5 mrem /hr beta-ga=ma Chemical Iab Hot Sink (l" frce drain) 8 mrem /hr beta-ga::ma 3

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SNEC Operations Report for April 1%7 . . . . . . d3 location Radiation Reading RWDP Evaporator (under bottom) 370 mrem /hr beta-gamma Evaporator (contact outside upper level) 100 mrem /hr beta-gamma Drum Storage Area (at HRA fence) 35crem/hrbeta-gamma C.V.

Primary Compartment (general upper level) 90 mrm/hr beta-gama ,

Primary Compartment (contact M.C. pump volute) 360 mrem /hr beta-gamma l Primary Compartment (S.G. bottom) 200 mrem /hr beta-gama l Primary Compartment (pressurizer bottom) 90 mrem /hr beta-gamma l Primary Compartment (general lower level) 80 mrem /hr beta-gama Primary Compartment (Regen. HI) 160 mr m/hr beta-gamma Primary Compartment (Non-Regen. HX) 100 mrem /hr beta-gamma Auxiliary Equip Compt. (S.C.H.X.) 37 mrem /hr beta-gama Auxiliary Equip. Compt. (D.T. top) 22 mrem /hr beta-gama Auxiliary Equip. Compt. (D.T. bottom) 200 mrem /hr beta-gama Auxiliary Equip Compt. (general lower level) 20 mrem /hr beta-gama Reactor Deck (water level at grating) 42 mrem /hr beta-gamma Reactor Deck (instrument ports) 42 mrem /hr beta-gamma Reactor Deck (waist level) 14 mren/hr beta-gama Reactor Deck (storage well railing) 31 mrem /hr beta-gama Contamination surveying consisted of routine 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 areas were generally within the " Clean Area" limits. The controlled area was cleaned frequently to keep and/or to return it to the " Clean Area" limits. The exclusion areas were cleaned periodically to minimize the amount of smearable contamination. The following contamination levels were observed:

Iocation Contamination Reading C&A Building Charging Pump Chamber 970d/m/smearbeta-gamma Charging Pump Chamber < 10 d/m/ smear alpha Charging Room Floor 5470d/m Sample Room Sink 100500 d/m/amearbeta-gama/ smear bet Sample Room Sink < 10 d/m/ smear alpha Sample Room Floor 919 d/m Chemical lab Hot Sink 7140d/m/smearbeta-gamma

/smearbeta-gamma Chemical lab Hot Sinx < 10 d/m/ smear alpha RWDF Pump Room Floor 17580d/m/smearbeta-gama Shipping Rocn Floor 1963 d/m/ smear beta-gama

SNEC Operations Report for

_ April 1967 . . . . . . d4 liquid and gaseous effluents from the SNEC site for the month of April 1967 were as follows:

(Curie) (Curie) (Curie)

Effluent Activity Activity Activity Type This Month Year to Date Last Twelve Months Tritium 0.144062 4 503356 26.424971 liquid 0.000112 0.012681 0.019316 Air, Ie 0.000582 11.053711 101.557835 Air, I-131 0.000002 0.000850 0.148399 Air, M.F.P. 0.000006 0.110537 1.015579 Thirteen (13) barrels of waste were drummed for temporary storage.

Twenty-seven (27) drums were shipped from the site.

Radiation exposure for all SNEC personnel as measured by film badges for the nonth of March 1967 were a maximum of 670 mrem with an average of 109 54 mrem.

Radiation exposure for all visiting personnel as measured by film badges for i the month of March 1967 were a maximum of 260

  • mrem with an average of 20 mram.

The average radiation exposure for all personnel as measured by film badges for the month of March 1967 was 85.66 mram.

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  • Insulation contractor for Westinghouse STP 1

5 SAXTOLNUCLEAR EXPERIMENTAL CORPORATION OPERATING STATISTICS HONTH April YEAR 1967 NUCLEAR UNIT HONTH YEAR TO DATE TIMES CRITICAL NO. 0 0 495 HOURS CRITICAL HRS. 0 754.70 19,617.65 TIMES SCRAMMED (MANUAL) NO. 0 1 292

  • TIMES QCRONED (INADVERTANT) NO. 0 0 31 THERMAL POWER GENERATION HWH 0 17,665.02 357,749.89 AVERAGE WRNUP (P' u Region) WDM 0 1,441.94 12,183 74 CONTROL ROD POSI'TIONS AT END OF HONTH AT EQUILIBRIUM PCWER OF 0 Hwt HAIN 0001 ANT DORON 955 PPH RODS OUT - INCHES NO. 1 O N0. 2 0 NO. 3 0 NO. 4 0 NO. 5 0 NO. 6 0 _

EIECTRICAL UNIT HONTH E TO DATE GROSS OENERATION HWH 0 3,367 00 60,842.00 STATION SERVICE HWH 93.76 530.52 11,249 71 STATION SERVICE  % -

15.76 18.49 AVO. PIANT EFFICIDiCY - HWH(e)/HWH(t) 5 0 19.06 17.01 AVO. GENERATION ENNING ( 0 HRS) KW 0 754.45 17,902.42 PIANT IDAD FACTOR -

(AVO. GEN.FORMONTH/ MAX.IDAD) $ 0 25 75 30.30 AUXILIARY STEAM SUPPLY - NUCLEAR STEAM SUPPLIED Bf REACTOR HRS. 0 754.50 16,244.75 RWDF EVAPCRATOR OPERATION HRS. 188.5 793.42 4,709.00 0 RD{ ARKS :

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