ML20085H134

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Monthly Operating Rept for Feb 1967 for Saxton Nuclear Experimental Corp
ML20085H134
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 02/28/1967
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SAXTON NUCLEAR EXPERIMENTAL CORP.
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FOIA-91-17 NUDOCS 9110280146
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SA7.T0!! UUC2AR E7ERIMDITAL CORPORATIOU Operations Report for February 1967

1. RZA0 TOR OPERATI01]}

The reactor was shutdown at 10:40 AM on February Ir.t to cor.ence a scheduled plant outage for the purpose of completing construction and shakedown of the supercritical technology test loop.

2. GENQ Ccoldown of the main coolant system was begun on February lot and was conpleted on February 2nd.

Ucrk on the supercritical technology \ est loop was started on February 3rd and was continued throughout the month.

On February 24th the irradiated fuel shipping cask was received at the site and was placed in the storage well in preparat!on for loading two reds containing Zircaloy-4 test capsules.

Daring the work week beginning February 27th an inspection team, assigned by t he Savannah River Operations Office of the AEC, rade an inventory of the special nuclear naterial on hand at Saxton; reviewed the procedures for computing nuclear nat crac1 censuned, and audited the lease material records that are kept at Saxton.

On February 27th fuel subasser.nly 503-4-25 was removed from reactor core po:dtion IL 1 and was placed in the fuel storage rack. On February 28th two rods containing :'ircaloy-4 test capsules were removed from subassembly 503-1-25 and were placec in the irradiated fuel shipping cask. Two fuel rod: Nos. 781 and 782 were insertca in rubascenbly 503-4-25 and the subasoc:,bly wr.s returned to reactor core position U-1. Also on Februaq 28th the dummy assemb.ty was removed from reactor core position L4.

3 E"'F2RI13!TAL PROGRAM The najor work effort during the month was devoted toward completing the

inctallation of the supercritical technology test loop. By the end of the month-construction work on the loop was essentially completed.

Core changes nade during the nonth were as follows:

f Suhasseably 503-4-25 was renoved from core position U-l and placed 1n the fuel storage rack.

Two 2ircaloy-4 rods, Nos. 21 and 22, containing a series.of Zircaloy-4 test capsules were removed from subassembly 503-4-25 and were placed in the irradiated fuel shipping cask.

Fuel rods Nos. 781 r d 782, which had previously been in the core in subassembly 503-4-2' from April 6,1966 to August 3,1966 were inserted in subassembly 503-4-25. These two 5.7% enriched UO2 rods are clad with 304 SS and are internally pressuri::ed to produce a maximum I in-pile clad 0.D. tensile stress of 23,100 ps$.

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Sli3C Operations Report for )

Februa rv in67 . . . . . #2 i Core changes (continued)

Subasse.ibly 503-4-25 was retumed to the center core position H-1.

The supercritical test loop dummy assembly was rr.oved from core position N-4. l

4. OPERATIONAL, TESTS The radiation monitoring system circuits were tested on February 24th.
5. ItATUTT;.uUCE The principal itens of mechanical maintenance during the month included replheing the filter cartridges in the storage well system pre and post filters; replac.ing gaskets in flanges on the exhaust piping for the pressuricer relief valves; servicing the containment vessel air mixing fan; lapping the seat and plug in the letdwn flow control valve, IRC-21V, in the purification system; removing, cleaning and reinstalling the tube bundle in the storage well heat exchanger; lapping the seat and plug in the charging system stop valve, HIC-24V; lapping the seat-and disc in the regenerative heat exchanger relief valve, V-53; repairing a leak in the cooling coil in the tir handler for the operating floor area in the containment vessel; repairing the heating coil in the air handler for the drums handling area in MIDF; machining the plug for the auxiliary systems return valve HIC-2?V; repairing the handle extension on a valve in the sanple panel; servicing the valves in the main coolant sanple line in the sanple panel; checking the drive on No.1 charging pump for alignment and worn bearings; lubricating No.1 charging pump; repairing cracks in the carboline on the walls of the storage well in the containment vessel; cleaning and lapping the seat and replacing the nylon disc in relief valve, V-217, on the discharge head for the charging system punps; repairing the elevating cabic on the underwater perioscope; cleaning the solenoid operated dunp valve on the IMDF evaporator-hotwell; preparing the reactor vessel head for the renoval of subassemblies; receiving the irradiated naterial shipping cask and transferring it to the storage well; and handling fuel for invento17 and core changes.

The major items of electrical and instrument naintenance included replacing the sensing elenents in the hydrogen ' analyzer in the E!DF control roca; calibrating the containnent vessel pressure transmitter; replacing the carbon vanes in the air punp for the charging room alpha particulate monitor; repairing the floumeter on the nixed bed denineralicer in the make-up water treatment system;-replacing the carbon vanes and bearings in-the aiv pump in the sample room alpha particulate monitor; replacing the floodlights on the underwater periscope; replacing the carbon vanes and bearings in the air pump for the " Northeast" site particulate monitor, RIC removing and cleaning the leak-off system relief valves; replacing the filter paper-in the containment vessel particulate- monitor, RIC-1, and 'in the site particulate monitors RIC-8 and RIC-9; removing for- repair. the flowmeter in the cooling water line to the radiation detector, RIC-5, in the steam generator blowdown- system;-installing a-neutron detecting channel in the containrent vessel in preparation for fuel handling; E

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Sl'EC Operationo Report for l Febrmry 1%7 . . . #3 l

neggering the detectors and cabics for the nuclear instrunentation systen power rance channels and renoving the detectors for channels A & B for naintenance, replacing a transforner in the paging system phone located in the containnent vecsel auniliary conpartnent; calibrating the differential pressure gauge acrosc the pre-filter in the storace well system; repairing and calibrating the steam concrator stean and feedwater precouro monitoring and recording channels; and calibrating the fission product detector, channel RIC-10, of the radiation nonitoring system,

6. CHD!ISTRY Except for the first three days of the month the nain coolant system chordstry was naintained for cold shutdown conditions. On February 2nd the rain coolant hydragen concentration was reduced to less than 5 cc/kg of water in preparation for opening the systen.

a summary of the analyses nade on main coolant sampics taken during the nonth is contained in the following table; hain Coolant Sannles Minimum Muimum pH at 25 C 5.33 6.13 Conductivity, umhos 2.40 8.21 Soron, pFa 586 1467

  • 34.0 Gross Beta Gamnr. T15 Kin. degassed) ue/cc 0.0342 3.21 Tritiun,ue/cc 0.0863 0.17
  • Cold Shutdoun Conditions
7. 1DIATION AUD UAST2 DISPOSAL l

Radiation surveying consinted of routine plant surveys, C.V. during shutdown and naterials shi Faento. The following maximum radiation readings were taken:

a> cati opn, Radiation Readinc C&A Buildinr+

i l Waste Drum (baling nachine) 9.0 nren/hr beta gamma CharginE; Pump (contact with chamber)- 27 mrem /hr beta-gatna Sanple Roca (door of sample panel) 3.0 mren/hr beta-gamma Chemical lab Hot Sink (l" fram drain) 0.7 mrem /hr beta-ganna hvJF Evaporator (under bottom) 70 nrem/hr beta-cama Evaporator (contact outside upper level) 19 mrem /hr beta-cama

Drum Storage Area (at HRA fence) 18nrem/hrbeta-gamma l

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SliEC Operations Report for February 1967 . . . . . #4 location Radiation Readinn C.V.

Primary Compartuent (general upper level) 100 mrem /hr beta-gama Primary Compartment (contact M.C. pump volute) 440 mrem /hr beta-gama Primary Compartment S.G. bottam) 150 mrem /hr beta-cama Prinary Compartment pressurizer bottom) 120 mren/hr beta-gamma Primary Compartment 75 mrem /hr beta-gaw a Primary Compartment (general lower level) regenerativeH.X.) 330 mrem /hr beta-gamma Primary Compartment (non-regen. H.X.) 75 mrem /hr beta-gamma Auxiliary Equip. Compartment S.C.H.X.) 500 mrem /hr beta-gama Auxiliary Equip. Compartment D.T. top) 200 mrem /hr beta-gamma kaxiliary Equip. Cmpartment D.T. bottom) 600 mrem /hr beta-gamma Auxiliary Equip. Compartnent general lower level) 18 mrem /hr beta-gamma Reactor Deck (water level at grating) 20 mrem /hr beta-gamma Reactor Deck (instrument corts) 290 mrem /hr beta-gama ReactorDock(waistlevel) 30..r m/hr beta-gam a Reactor Dech (storage well railing) 15 mrem /hr beta-cama Miscellaneous Samples Shipped to VAPD (contact with container) 50 mrem /hrbeta-camma Two renovable rods which were not irradiated were returned to WAPD (contact) < 0.15 mrem /hr beta-gamma 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 -

"Clenn 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:

Location Contamination Readinn C&A Buildinn Charging Room Floor 670 d/m/ smear beta-gamma Sample Room Sink 34000 d/m/ smear beta-gamma Sample Room Sink < 10 d /smearalpha Sample Room Floor 380 d / smear beta-gama Chemical lab Hot Sink 105470 d / smear beta-gamma Chemical lab Hot Sink (10d/m/smearalpha RWDF Pump Room Floor 2510d/m/cmearbeta-gamma

( Shipping Room Floor 235 d/u/ smear beta-gamma l

Si!EC Operations Iteport for February 1967 . . . . . r/5 location Contamination Readinn C.V.

Operating Doch 2620 d/m/encar beta-gama ReactorDeck(head) 18850 d/m/ smear beta-ganna Reactor Decl: (grating) 28000 d/m/amear beta-ga:ama Prinaq Compartment (Crating) 6760 d/m/ smear beta-ganna Liquid and gaseous offluents from the S!iEC site for the month of February 1967 were as follows:

(Curie) (Curie) (Curic)

Effluent Activity Activity Activity Type This Month Year to Date Inst Twelve Months Tritium 1.651710 3 494681 26.299296 Liquid 0.007362 0.011169 0.021861 Air, Xe 10.616422 11.023700 120.72080-Air, I-131 0.000822 0.000841 0.153636 Air, II.F.P. 0.106164 0.110237 1.207208 lio barrels of waste were drummed for taaporary storage. IJo drums were shipped fron the sito.

Radiation exposure for all S!JEC personnel as neasured by film badges for the nonth of January 1967 were a maximum of 525 nrem with an average of 37 30 mren.

Radiation exposure for all visiting personnel as measured by film badges for the nonth of- January 1967 were a maximum of 170 mren with in average of 17 75 mrem.

l The average radiation e::posure for all personnel as measured by film badges for the month of January 1967 uns 31.50 mrem.

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SAXTCri NUCIIAR EXPERIMENTAL CORPORATION OPDIATING STATISTICS l

MONTH Februarv YEAR 1967 N1'CLFAR UNIT HONTH YFAR TO DATE TI)ES CRITICAL NO. 0 0 495 HOURS CRITICAL HRS. 10.70 754 70 19,617 65 TIMES SCRAMMED (MANUAL) NO. 1 1 292

  • TIMES QCRAMMED (INADVERTANT) NO. 0 0 31 l THERMAL POWER GENERATION MWH 241 50 17,665.02 357,749.89 AVERAGE IURNUP (Pu Region) WDATU 19.71 1,441 94 12,183 74 CONTROL ROD POSITIONS AT ED OF MONTH AT IQUILIBRIUM POWER OF 0 MWt MAIN C001 ANT BORON 1467 PIH RODS OUT - INCHES NO. 1 0 NO. 2 0 NO, 3 0 NO. 4 0 NO. 5 0 NO. 6 0 1 ELECTRICAL UNIT HONTH YFAR TO DATE GROSS OENERATION MWH 46.00 3,367.00 60,842.00 STATION SERVICE MWH 96,82 339.10 11,058.29 STATION SERVICE  % 210.48 10.07 18.18 AVO.PIANTEFFICIENCY-HWH(e)/MWH(t)  % 19.05 19.06 17 01 AVG. GENERATION RUNNING (_ _10.45 HRS) KW 4,401.91 4,462.85 3,398.53 PIANT IDAD FACTOR - ,

1.56 52.38 31.33 (AVG. GEN. FOR MONTH / MAX. LOAD)

AUXILIARY STEAM SUPPIX - NUCLEAR STEAM SUPPLIED BY REACTOR HRS. 10.50 754.50 16,244.75 RWDF EVAPORATOR OPERATION HRS. 8.42 604.92 4,520.50

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