ML20085H113

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Monthly Operating Rept for Mar 1967 for Saxton Nuclear Experimental Corp
ML20085H113
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 03/31/1967
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SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110280140
Download: ML20085H113 (5)
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SAXT0!i NUCLEAR EXPD1IMD;TAL CORPORATIO!1 Operations Report for March 1967

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

On March 1st the fuel shipping cask containing two irradiated rods enclosing zirconium alloy test specimens was removed from the containment vessel and returned to Westinghouse Post Irradiation Facility at Waltz Mill, Pa.

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. E2PDlIliE!TAL PROGRAM Two rods Nos. 18 and 19, clad with Zircaloy-4 having a nominal thickness of 23.5 nils and containing a series of Zircaloy-4 capsules were returned to Westinghouse for post irradiation examination. The rods had been in the center of the core for 2400 EFPH. Each capsule in the two rods contain one or more circonium alloy test specinens. The test specinens are portions of 0.016 inch thick grid strap material loaded within the capsule.

Work on the shakedown of the supercritical technology test loop was carried out during the menth. Many valve and instrumentation problems were encountered. By the end of the month the loop, with a short section of pipe installed in place of the pressure tube, was being operated at rated flow and pressure at low temperature conditions.

3. OPERATIO!JAL TESTS The radiation monitoring system circuits were tested on liarch 13th.
4. MAIllT2;A!!CE The principal items of nechanical maintenance during the month included cleaning the solenoid operated valves in the nP rogen purge syn e of the radioactive waste treatment plant; lapping all metal to metal sealing surfaces in the auxiliary system return valve, HIC-27V; fabricating retaining rings for the nuclear instrumentation--

detector cans; cleaning the bottom of the storage well; repairing the clothes dryer; blowing out the leak-off system 11nes and installing swagelok unions in the lines; cleaning the check valve in the discharge line of the RWDF sump pump; . painting the duct work for the operating area air handler, the wooden shielding blocks, and the reactor vessel head-lifting device in the containment vessel; repacking the main steam stop valve, V-1001; repacking the bottom blowdown valve, V-ll44; repacking six instrument shui-off valvec'in the cas phase of the pressurizer;--removing and- cleaning the intake and exhaust valves of the instrument air compressor; processing six drums of evaporator bottoms; installing a new seat and plug in the letdown system stop valve, HIC-23V; and-cleaning conoscals and instrument supports in preparation for reinstalling them on the reactor vessel head.

9110280140 910424-PDR FOIA DEKOK91-17 PDR

S!IEC Operations Report for March 1967 . . . . . . #2 Maintenance (Continued)

The major items of electrict.1 and instrument maintenance included replacing a fuse holder in the liquid scintilhtion counting system; resetting the alam points on the conponent cooling system surge tank level controller, LI-23; repairing the power supply for the spectrophotometer in the chemistry laboratory; repciring the paging phone in the control room; replacing a relay in the computer-indicator for the site radioactive particulate monitor, RIC-9; installing a new switch on the soleno:.d operated stop valve in the pressurizer sample line; restroking the deaerator overpressure steam dump valve, V-1050, to the condenser; calibrating the leak-off system flow recorder, FR-26, and setting the alam point; cleaning the air pressure regulators and calibrating the valve positioner for the main steam pressure reducing valve; replacing the G-M tube on the charging room area radiation monitor, RIA-2; calibrating the letdown system control valve positioner, UTC-21V; repairing and calibrating the steam generator level control system; cleaning and repairing the gas analyzer in RWDF; and remaking the water seals on the nuclear instrunentation power range detector cans.

5 CHD!ISTRY The nain coolant system was in a cold shutdown condition throughout the entire month. The shutdown cooling systen was operated to remove residual core heat. A sumary of the analyses nade on main coolant samples taken during the month is given below:

Hain Coolant Systen Mininum Maximum

pH at 25 C 5 19 5.76 Conductivity, umhos 5.38 7.88 Boron, pga 961 1441 Chlorides, ppa < 0.005 < 0.005 Gross Beta-Gamma (15 Min. Degass 4) ue/cc 0.495 0.727 Tritium, ue/cc 0.06 0.094
6. _ RADIATION AND UASTE DISPOSAL Radiation surveying consisted of routine plant surveys, C.V. during shutdown and materials shipments. The following maximum radiation readings were taken:

Incation Radiation Readinc C&A Buildinn

-Maste Drum (baling machine) 6.0 mrcm/hr beta-gn=a Charging Pump (contact with chamber) 22 mrem /hr beta-gamma Sample Room (door of sample panel) 3.0 mrom/hr beta-gnma Chemical lab Hot Sink (l" frca drain) 1 5 mrem /hr beta-ga=ma RUDF Evaporator (under bottom) 2200 mrem /hr beta-gamma Evaporator (contact outside upper level) 100 mrem /hr beta-gamma 3 Drum Storage Area (at HEA fence) 17.0 mrem /hr beta-gamma l

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SNE' Operations Report for March 1967 . . . . . . .#3 Raniation and Vaste Disposal (Continued)

Location Radiation Readint' C,;_h Primary Campartment ( 60 mrem /hr beta-gama Primary Compartment (general contact M.C.upper level) 350 mrm/hr beta-gama Primary Compartment (S.G. bottom) pump volute) 100 mrem /hr beta-ga=a Primary Compartment ( 50 mrem /hr tota..s;ama Prinary Compartment general(pressurizer bottom) lower level) 65 mrem /hr beta-gama Primary Compartment (Regen. HX) 210 mrem /hr beta-gamma Primary Compartment (Non-Regen. HX) 70 nrem/hr beta-gamma Auxiliary Equip. Compartment (S.C.H.X.) 65 mrem /hr beta-gn=a Auxiliary Equip. Compartment (D.T. top) 60 mrem /hr beta-ga= a Auxiliary Equip. Compartment (general lower level) 20 mrem /hr beta-gama Auxiliary Equip. Compartment (D.T. bottom) 450 mrem /hr beta-gamma Reactor Deck (water level at grating) 41 mrem /hr beta-gamma Reactor Deck (instrument ports) 320 mrera/hr beta-gamma Reactor Deck (waist level) 20 mrcm/hr beta-gamma Reactor Dech (storage well railing) 15 mrem /hr beta.'. gamma

!!iscellaneous Vestinghouse Cask Shipped to WAPD < 1 mrem /hr beta-gamma Contamination surveying consisted of routine plant site surveys, surveys of natorials shipped tools, equipraent 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 minimine the amount of smearable contamination. The following contaT.ination levels were observed:

location Contamination Readint' C&A Buildine Charging Pump Chamber -38400 d/m/ smear beta-gamma Charging Pump Chamber < 10 d/m/ smear alpha 1.

Charging Room Floor 1452 d/m/ smear beta-gar.ma Sample Room Sink 7090 d/m/ smear beta-gamma Sample Room Sink < 10 d/m/ smear alpha Sample Room Floor 295 d/m/ smear beta-g e n Chemical Iab Hot Sink 32200 d/m/ smear beta-gamma Chemical lab Hot Sink < 10 d/m/ smear alpha RWDF Pump Room Floor 17580 d/m/ smear beta-gamma Shipping Room Floor . 1963 d/m/ smear beta-gamma s

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S!EC Operations Report for Ma rch 1967 . . . . . . #4 Radiation and Waste Disposal (Continued)

Ioeation Contamination Read $nn 1.V.

Operating Deck 2050 d/m/ smear beta-gama Operating Deck < 10 d/m/ smear alpha Reactor Deck (head) 18850 d/m/ smear beta-gamma Reactor Deck (head) (10 d/m/ smear alpha Reactor Deck (grating) 28000 d/m/ smear beta-gamma Reactor Deck (grating) <10 d/m/ smear alpha Primary Conpartment (grating) 13590 d/m/ smear beta-gama Pri. nary Compartment (grating) <.10 d/m/ smear alpha Liquid and gaseous effluents fre.n the SNEC site for the month of March 1967 were as follows:

(Curie) (Curie) (Curie) '

Effluent Activity Activity Activity l Type This Month Year to Date- last Twelve Months Tritiun 0.864613 4.359294 26.327909 Liquid 0.001400 0.012569 0.019996 Air, Xe 0.029L29 11.053129 114.509674 Air, I-131 0.000007 0.000848 0.149392 Air, M.F.P. 0.000294 0.110531 1.145097 Eleven (11) barrelo of waste were drummed for temporary storage. No drums were shipped from the site.

Radiation exposure for all S!EC personnel as measured by film badges for the month of February 1967 were a naximum of 325 mram with an average of 47.5 mrm.

Radiation exposure for all visiting personnel as measured by film badges for the month of February 1967 were a maximum of 400* mrm with an average of 39.9 mrem.

The average radiation exposure for all personnel as measured by film badges for the month of February 1967 was 43.8 mrem.

O Principally construction and maintenance of STP by contractor personnel l

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SAXTCil NUCLEAR EXPERIMENTAL CORPORATION OPERATING STATISTICS HONTH lbreh YEAR 1967 NUCLFAR UNIT HONTH YEAR TO DATE TIMES CRITICAL NO. 0 0 495 HOURS CRITICAL HRS. 0 754.70 19,617.65 TIMES SCRAHHED (MANUAL) NO. O 1 292 O TIMES QCRAHHED (INADVERTANT) NO. 0 0 31 THDMAL POWER GENElt' 'ON HWH 0 17,665.02 357,749.89 AVERAGE BJRNUP WD/kW 0 1,441 94 12,183.74 CONTROL R0D POSITIGfS AT DID OF HONTH AT EQUILIBRIUM POWER OF 0 MWt MAIN COOINIT BORON _1050 PPH RODS OUT - INCHES NO. 1 0 NO. 2 0 go, 3 0 NO. 4 0 NO. 5 0 NO. 6 0 EIECTRICAL UNIT HONTH YEAR TO DATE GROSS GENERATION HWH O 3,367.00 60,842.00 STATION SERVICE WH 97.66 436.76 11,155.95 STATION SERVICE $ -

12.97 18.34 AVO. PIANT EFFICIENCY - HVH(o)/HRH(t)  % 0 19.06 17.01 AVG. GENERATION RJNNING ( 0 HRS) KW 0 4,462.85 3,398.53

".AH1 IDAD FACTOR -

(AVO. GEN. FOR HONTH / kAX. IDAD)  % 0 34.33 30.80 AUXILIARY STEAM SUPPLY - NUCIEAR STEAM SUPPLIED BY REACTOR HRS. 0 754.50 16,244.75-RWDF EVAPORATOR OPERATION HRS. 0 604.92 4,520.50 0 REMART.S f

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