ML20085G936

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Monthly Operating Rept for Nov 1968 for Saxton Nuclear Experimental Corp
ML20085G936
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 11/30/1968
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SAXTON NUCLEAR EXPERIMENTAL CORP.
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ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110280084
Download: ML20085G936 (7)
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SA%TN !;UCBR FM"JWZ:T4t 00.PU ATIG!

Operatione Report for !!ove-ber 1968 .

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1. RFAC703 CPEMTIO! S r

The reactor wac in a cold shutdown condition throughout this '

report period for defueling of Core II.

l On llovenber 25 and 26 the facility was made available for reactor operator examinationf4 Seven Westinghouse customer trainees completed AEC written and oral exa .innt.ons for reactor operator licenses. ,

2. GCERAL The plant outage which v a begun on October 18, was continued throughout this report period.

At the beginning of the mom,h work was underway in preparation for renoval of the reactor vossel head. On llovember 8,llovember the reactor voosel head was removed and stored on the operating level. On 12, the upper barrel with the inctrument packago was removed and placed on the storago l

plattom in the storage well.

I The irraciated fuel shipping cask was received en llovember 6. Four plutonium 9x9 fuel assemblied were removed from the reactor, loaded into the shipping cask and chipped to the Westinghouse Post Irradiation Facility on llovember 16 The shipping cask was again received at Saxton on !!ovesber 19.

Three plutonium 9x9 assemblies and one Coro I 9x9 assenbly were loaded into

! the cad:. The cask was shipped on llovember 21. During the period 11ovember 13 thru 20 the remaining fourteen 9x9 asamblies and six control rods were removed from the reactor and stored in the fuel storage rack.

I Insulation was renoved from the main coolant systen piping on the suction and discharge of the main coolant pump and from the steam generator and t:.e presourizer as part of the main coolant system inspection. The areas to be inspected were wire brushed to renovo paint and oxides in order to get to the base metal. The secondary side of the steam generator wac inspected with no abnonnal conditions found.

Installation of a Recirculation System was started during this period. An additional check valve was installed in each safety injection line.

The E!ST level d/p cell penetrations were made into the tank during the period the storage well was flooded. The precouricer safety valve platfom was fabricated and installed and a section of the safety valve discharge piping was removed. The recirculation system level and pressure transmitters power supplies

- were connected to the vital bus and the energency bus. The MET level indicators and a control switch for a motor operated valve were installed in the control room on panel H. The additional control switches for the recirculation pumps and the motor operated valve will be installed efter installation of the l-pumps and valves.

I 93go;soos4 910424 l PDR FOIA PD' R DEKOK91-17

S!!EC Opera +1ons Report for '

!!cv rner 1968 . . . . . #2

3. EU'EitIlrfAL PRO'39!

Both the conductivity boron analyzer and the absorption boron analyzers were snipped Qom the site during the month for adc'itional testing and evaluntaon at c N I sites.

4. ERATIO!!AL TESQ The S!!EC fire and evacuation ahms were tested on llovember 1, 8, 13, 22 and 29.

The montM,v test of the radiation monitcring systam was comple.ted

' on llovember 1, Tne monthly test of the safety injection system was not condue:r due to the depressurized condition of the main coolant system.

5. 1'AIITH A!!CE The princips; items of mechanical maintenance during the month included repa' king the safety injection rumps; installing a new universal and repairing the shaft on the containment vessel rotary -trane; inspecting the EST internalAv; installing now condensate return lin s piping to the condensate surge tank; replacing the five micron filters .'.n the storage well filter; installing steam tracing on the discharge tatk piping; removal of the steam generator secondary side nanway and bandholes; and repairing d al:s in the containment vessel air handler stamm ~ all.

The major items of elcetrical and instrument maintenance included installing a new clothes dryer; calibration of the containment vessel pressure transmitter; relocating the watthou. meter relay abc n the VFU control cabinet; installing a new vacuum pump on site particub te monitor, RIC.3; cleaning the leak-off systcra d/p cell; repairing the BDF hotwell

'1c<el d/p cell; calibration of the pressurizer pu ssure channcl, PIC-3; repairing the purification filter d/p transmitter; installing reactor vessel head bolt heaters; repairing a portable CP-3 survey meter; replacing a transfomer on the stack radiation monitor, RIC-3; installing new hoses

-on the instrument air dryer piston and a new heating element in the drying column; replacing tubes in the computer indicator circuit for EfuF effluent ,

monitor, RIC-6; replacing the brake shoes on the containment vessel rotary crane; .and repairing the indicator on the RWDF tank bubbler systan,-

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S U:C Operations Report for November 1968 . . . . J3

6. CIF5:ISTRY The main coolant systea was in cold shutdoun and open to the stort go well throughout this report, period. A summary of the analyses

, perforr.ed on main coolant samples taken during this period is contained in the following tablo:

Ma n Coolant Samrles Minimm Maximum pH at 25 C 5.C') 5.65 Conductivity, umhos 5 82 8 55 Boron, pgn 1754 1875 Chlorides, p;ra 4 0.005 < 0.005 4 2 Gross Beta-Gumma (15 Min. Degassoc) ue/cc 7.52x10 3 3 46x10 2 Tritium, ue/cc 8.38xlO- 1.15x10-A camponent cooling camplo analy cd on November 21 showed the pH to bo 8.83 and the e The gross beta-ganma activitywas6.08x10gamateconcentrationtobe500pyn.

uc/cc.

7. RADIATION AND WASTE: DISPOSAL Radiation surveying consisted of routine plant surveys, C.V. duri.ng shut Iown and materials shipments. The following maximum radiation readings uere taken:

Incation Ridiation Readinn COA Buildinn l

Uaste Drum (baling machine) 1.2mran/hrbeta-gamma Char;;ing Pump (contact with chamber) 32mran/hrbeta-gamma Sample Roam (door of sample panel) 1.5 mraa/hr beta-gn=a Chemical Inb Hot Sink (l" frca drain) 11 mrem /hr beta-ga=a l %DF i

l Evaporator (underbottom) 17 mrcm/hr beta-gama Evaporator (contact outside upper level) 5 mren/hr beta-ga=a Drzn Storage Area (at HRA fence) 7.5 mran/hr beta-gn=ma C.V.

Primary Campartment (general upper level) 150 mran/hr beta-ga=2 Primary Compartment (contact M.C.- pump -

volute) 1100 mrem /hr beta-gama Primary Compartment (S.G. bottam) 450 mrem /hr beta-gama l

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SUFI Operations Report for llovember 1968 . . . . . #4 Iocation Radiation Readinn 150 mrem /hr beta-ga;na Pri:aaryGempartment Primary Cuapartment pressurizerbottom))

general lower .' , vel 75 mran/hr beta-ga=a Primary Ccapart. ment (Regen. HX) 450 mren/hr beta-Camma Prifnary Coapartraent (Non Regen. IDC) 35 mran/hr beta-ra=a Auxiliary Equi;nent Compartment (S.C.H.X.) 8 nrcra/hr beta-gn=a Auxiliary Equipment Compartment (D.T. top) 10 mran/hr beta-gena Auxiliary Equip 1cnt Compartment (D.T. bottom) 30 mrem /hr beta-garena Auxiliary Equipnent Compartenent (general lower level) 5 mraa/hr beta-gamma ReactorDeck(waterlevelatgrating) 50 mren/hr beta-gamma Reactor Dock (instrument ports) 700 mren/hr beta-gena Reactor Dock (waist level) 30 nran/hr bet.a-gn=a Reactor Deck (storage well railing) 35 mren/hr beta-ga=a Reactor Head (after ranoval - underneath) 1000 mr hr beta-carna Instrument Eack (top) 350 mr r beta-ga=a Contamination surveying consisted of routine plant site surveys, surveys of materials shipped, tools, equiprnent and C.V. during shutdown. The clean areas were within the " Clean Arca" 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" 1.inits. The exclusion areas were cicaned periodically to rindnice the amount of smearable contamination. The following contamination levels were observed:

Incation Contaminatien Readinn C&A Buildinn Charging Pump Chamber 21700 d =ncar beta-gama Charging Pump Chamber < 10 d smear alpha Charging Room Floor 951 d smear be+ .t-ga .:na Sample Room Sink 75000 d macar beta-ga.ca-Sample Rocn Sink <.10 s amcar alpha Sample Room Floor 355 d smear teta-gamma Chanical lab Hot Sink 11210 d, / smear beta-gn=a Chemical lab Hot Sink < 10 d/m/ anear alpha R'dDF Pump Room Floor 1010 d/m smear beta-ga=a Shipping Room Floor 4 100 d s:near beta-gamma i

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S!!EC Operatisns Report for 11ove.ber 1968 . . . . . JS Incation Conta-ination Readinn C.V.

Operating Deck Operating Deck <2400d/m 10 d/m/ smear beta-ga=a

/emearalpha Reactor Dock (head) 35100d/m/smearbeta-cama Reactor Dock (head) < 10 d/m/ smear alpha ReactorDeck(grating} 26000 d smear beta-ga=na

< 10 d smear beta-gn=a ReactorDeck(gratin Primary Com;nrtment[e) grating) 7000 d smear beta-gn=na Primary Compartment (grating) < 10 d /smearalpha Miscellaneous Puel Cask (11-15-68 1880 d smear beta-ga::ma Fuel Cask (11-15-68)) < 10 d smear alpha Fuel Cask (11-20-68) 1200 d smear beta-gama Fuel Cask (11-20-68) < 10 d/m/ smear alpha Liquid and gaseous effluents from the S11EC site for the month of 11ovember 1968 were as follows:

(Curie) (Curie) (Curie)

Effluent Activity Activity Activity Tyne This Month , Year to Date _ Inst Twelve Months liquid 0.001489 0.009021 0.013458 Tritium 0.928122 7.376117 7.573459

  • Air, Xe 0.001325 18.598395 23.219115 Air, I-131 0.000000 0.000494 0.000494 Air, M.F.P. 0.000013 0.185983 0.232191
  • Contains a 0.193 correction for August 1968 Seven barrels of waste were drunned for temporary storage. Thirty-one drumb were shipped from the site.

Radiation exposures for all S!!EC personnel as measured by fi3m badges for the month of October,1968, were a maximum of 515 mrem with an average of 95.3 mran.

Radiation exposures for all visiting' personnel as measured by film badges for the month of October,1968, were a mi-m of 0 mran with an average of 0.0 mram.

I The average radiat. ion exposures for all personnel as measured by film badges for the month of October, 1968, was 63.8 mran.

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SAXTCt1 NUCLEAR EXPERIMENTAL CORPORAIIg l

OPERATING STATISTICS MONTH I!m?'I m cr YEAR 19 2 l NUCLEAR UNIT MONTH YEAR TO DATE TIXES CRITICAL NO. 0 281 023 HOURS CRITICAL HRS. 0 2,375.49 22,948.49 TIKES SCRAIS!ED (liA!TJAL) NO. 0 122 449 l

  • TD:ES .$0RA!O ED (INADVERTANT)

NO. O H 42 THER)!AL PONER GENERATION INH 0 51,3c9.92 429,359.85 AVERAGE HJRNt'? }MD/MTV O 4,194.00 18,029 03 CONTROL ROD 'PCSITIONS AT DID OF MONTH AT QUILIBRIUM POWER OF 0 )Mt 1:AIN C00LAN" BORON 1861 PPM KODS OUT - INCHES l NO. 1 O No. 2 0 NO. 3 0 0 0 No. 6 0 NO. 4 No. 5 EIECTRICAL UNIT MONTH YEAR TO DATE GROSS GENERATIO: IMH O' 9,149.8 72,426.3 STATION SERVICE FNH 92.50 2,862.75 15,078,65 STATICN SERVICE  % 0 31.29 20.81 l AVG. PU.:C EFFICIENCY -lH(e)/)arri(t)  % 0 17.80 16.87 AVG. GENERATION PL'NNING ( 0 HRS) Dl C 4,451.85 3,461.11 PU.NT I4AD FACTOP, - (AVG. GEN. FOR MONTH / MAX. IDAD)  % 0 18.06 19.78 l l AUXILIARY STEAM St'FPLY - NUCLEAR STIAM SUPPI2ED BY REACTOR HRS. 0 2,108.65 19,259.74 

               .WDF EVAPORATOR OPERATION                                                                           HRS.         196.5                               S56.46                                    7,414.86
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