ML20085H198

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Monthly Operating Rept for Oct 1966 for Saxton Nuclear Experimental Corp
ML20085H198
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 10/31/1966
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SAXTON NUCLEAR EXPERIMENTAL CORP.
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ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110280163
Download: ML20085H198 (7)
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SATT0!! UUC'JAll EXPDtiliE'TAL CQIlP0ilATION Operatinno llenort for October 1%6

1. RFAC1DR OPDIATION At the bedinrang of this report period the reactor was being operated at a pcwer level of 23 5 int in continuation of the test program to develop infomation concerning the utilitation of plutonium enriched fuels in pressurir.ed water roactors.

Operation at 23 5 isit wt.e continued until the norning of October 14th when the reactor was shutdown in preparation for a scheduled plant outage.

2. GDIUtAL Cooldown of the nain coolant syst e was initiated on October 14th and was coa.plet-i on October 16th.

C The primary purpose of this plant outage was to evaluate the as-built condition of the supercritical technology test loop components, bnd to continue construction and check-out work on the reaining unfinished loop systems. All constrvction work on the supercritical loop had halted in April,1965.

On October 26th the ^mriy assembly was removed from reactor core position N-4 and on 0:tober 27th a supercritical loop unfueled pressure tube was installed in position N-4 for piping fit-up.

3. pCPERIMD1TAL Pit 0GilAll The first few dayo of the month were devoted to completing the high pH serias (,f tests to datomine the effect of pH on moderator temperature coefficient.

At oore burn-up of 5200 IMDMTP, main coolant average temperature of 510'F, and main coolant boron concentration of 750 pm , the moderator temperature l coefficient vss founa to be indeptmdent of pH and was detemined to be 3.05 x 10-4 ok/x/ty. For tne sarae conditionr the differential boron worth was detemined to be 0.75 x 10-4 4k/k/pp boron.

The. period from October 15th through the end of the month was devoted primarily to work on the supercritical technology tost loop.

4. OPytATIONAL TESTS A nomal t'est of the safety injection system was conducted on October 14th. l On October 18th the radiation monitoring system circuits were tested.

T)}e #2 turbina. overspeed trip was testod on October 22nd. The trip functioned at 1925 IIPH.

9110290163 910424 PDR FOIA DEKOK91-17 PDR

1 b!T Operations Report for Detober 1966 . . . . . .#2

5. 14AI!ril":AEE Tne principal itcus of nochanical naintenance during the nonth included replacing the rupture disc on MQF spent resin storace tank lio.1; replacing the fan belt on the control and auxiliary building intake air handler; fabricating a new valve sten for tha vacuun regulating valve on IgDF cas conpressor lio. 21 cleaning tne check valv , on MOF gris conpressors !!o.1 and lio. 2; cleaning the seating surfaces on the vent valve, H0-22, on the purification system surge tank; renewing a pipe hanger on the storage well systen discharge pipe in the storage well; repairing the interlochs on the doors of the containnent vesnel personnel air lock; repairing the i acid flow neter in the water treating system; replacing the sight class in the level j indicator on the igDF cas conpressor manifold; procencing seven druas of evaporatur bottoms t rmoving the head on the EDF evaporator and opening 187 plugged tubes; preparing the reactor vessel head for the renoval of the dunny assembly fron core ,

position li-4; reaoving the dumny assenbly fron reactor core position H-4 and l inserting a supercritical loop unfueled pressure tube in that core position for i piping fit-up.

The uajor itens of electrical and instranent naintsnance included replacing the solenoid on the air control valve for safety injection valve FIC-22; repairing '

the count room alpha scalor and its associated preamplifier; repairing and calibrating radiation monitoring channel RIA-2 located in the charging room; checking the specific gravity of the station batteries replacing the phototube and repairing the premaplifier in the fission product nonitor, radiation nonitoring channel RIC-10; adjusting the unloading valve on the instrument air compressor; replacing a contant on the air circuit breaker for No. 2 charging pump; installing new vanes in the vacuun pump for the BOF hydrogen analyzer; replacing a defective diaphraga in a mercoid alam switch on the MDF gas compressor suction manifold; replacing the solenoid on the air control valve for shut-off valve, HIC-30, in the shutdown cooling system; cleaning switch contacts in the control rod position indicating circuits; cleaning and calibrating the 5 0F evaporator level column; installing a neutron detecting channel in the containnent vessel in preparation for fuel handling; repairing the alam on the labitron that is used in the containnent vessel during fuel handling operation; adjusting the zero, compensation and set point on the pressurizer level controller, LIC-2; installing new vanes in the vacuum pump for the southwest site particulate monitor, radiation nonitoring channel RIC-9; repairing the log nicro-nnneter in the nuclear instrunentation source range channel A; repairing the vacuum puup on the alpha monitor for the charging pump room; and installing a new BF3 neutron detector in nuclear instrumentation source range channel A.

6. CHEISTRY Tne main coolant systcn was maintained for power operating conditions until October 14th. During this period the boron concentration was _ varied over the range 580 ppm to 792 pFa and the lithium concentration was maintained above 1.3 ppm for the high pH phase of a test series to detemine the effect of pH on temperature coefficient. On October 16th the hydrogen concentration was reduced to less than 5 cc/Eg H2 O in preparation for opening the main coolant system.

I l

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Sh'EC Operations lleport for October 1%6 . .. . . r/3

, Chc .istry (Continued)

, A sunnary of the analyses made on the main coolant samples tal:en during i the month is contained in the following tablet l Main Coolant Systen Vdnimum 14nxi m m Conductivity, unhos 3.25 17.5 '

pH at 2500 5.52 6.03 Foron, p;n 580 1200

  • Lithium, ppm < .01 J.50 Hydrogen, ec/Kg H,0 <50 39.0 1 Crad, ppb (one determination) 44.1 44 1 Oross Beta Gamma (15 !!in. Degassed) ue/cc 0.546
  • Ileactor in cold shutdown Except for a short period on October 10th when a maximum detemination of 0.260 p 1 was obtained, the chlorides in the steam generator were maintained below 0.155 p;n. The steam generator blowdown averaged less than lx10-8 uc/ce during the month.
7. RADI ATIO!! AllD UASTE DISPOSAL Radiation surveying consisted of routine plant surveys, C.V. during shutdown and materials shipments. The following maximum radiation readings were tahent incation Radiation Readinn, C&A Baildinn Wate Drum (baling nachine) .

13 0 mrem /hr beta-ganna Charging Pump (contact with chamber) 36nrem/hrbeta-camma t Sample Room (door of sample panel) 5.5 mram/hr beta-gamma Chenical lab Hot Sing (l" from drain) 5 5 mrem /hr beta-grena RilDF Evaporator (underbotton) 120mrom/hrbeta-gamma Drum Storage Area (at HRA fence) 3.5 mrom/hr beta-gamma Evaporator (top of exposed tube sheet) 100 mrem /hr beta-garraa l

l I

S!!EC Operations Hoport for Oct ober 19% . . . . ,,/1 Radiation and Vaete Dioposal (Continued)

Ioention Radintion Readine

  • Prir.ary Compartment (general upper level) .

83 mrem /hr beta-ga na

  • Prinary Compartuent (contact H.C. pump volute) 400 mrm/hr beta-canma
  • Prinary Compartuent (S.G. botton) 120 mrem /hr beta-gtma
  • Prinar/ Compartment (pronourizerbottam) 100 hram/hr beta-grunna
  • Primar/ Compartnent (general lower level) 103 nren/hr beta-girna
  • Primary Conpartment (Regen. H.%.) 200 mrcn/hr beta-ganma
  • Primary Compartment (lion-Re en. H.%.) 430 mrem /hr beta-gamma

" Aux. L uipment l Compartment S.C.H.X.) 19.0 nrtn/hr beta-cama

    • Aux. L luipment Compartmnt D.T. top) 17.0 mrem /hr beta-gar:na .
    • Aux. L uipment Compartnent D.T. botton) 90.0 nrem/hr beta-canma t
    • ReactorDeck(waterlevelatgrating) 90 mram/hr beta-carna
    • Reactor Deck (inntruuent ports) 220 mrom/hr beta-carna Ronctor Deck (us.iot level) . 70 mrm/hr beta-garna '

" Reactor Deck (storage well railing) 36 mram/hr beta-comma

      • Reactor Dech (ll-t vacant) 500 nren/hr beta-ganma M3ticellaneous Clothing Shirnents to Interstate Industrial Unifom (at contact with shipping drun) 13 mrem /hr beta-gama Contamination surveying consisted of routine plant site surveys, surveys of materials shipped, tools, equirnent and C.V. during shutdown. Tne 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:

location Contreninntion Readdnn C&A hiildinn Charging Pump Chamber 69540 d/m/cmear beta-gamma Charging Pump Chamber <.10d/m/smearalpha Sanple Room Sink 3740 d/m/ smear beta-gamma Sample Room Sinh (10d/m/smearalpha Sample Rocm Floor 1270d/m/smearbeta-ganta Chemical hb Hot Sink 6680 d/m/ smear beta-gama Chemical lab Rot Sink <10 d/m/ smear alpha

  • 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after ehutdovi. *
    • 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> after shutdown
  • M 14 days after shutdown b.

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SNEC Operations Report for cetober 1966 . . . . . .il5 Radiation and Waste Disposal (Continued) incation Contanination Rendinn RWDF Shipping Roon Floor 100 d/m/ smear beta-garna C.V.

Operating Dech 2900 d/m/ smear beta-garca Operating Dec): <.10 d/m/ smear alpha Reactor Deck (head) 40120 d/m/ smear beta-gamma Reactor Deck (head) < 10 d/m/ smear alpha ReactorDoch(grating) 50490d/m/smearbeta-gamma i Reactor Dech (grating) <10 d/m/ smear alpha PrimaryConpartment(grating) 36830d/m/smearbeta-gamma Primary Compartment (grating) <.10d/a/;mearalpha Liquid and caseous effluento from the SNEC site for tM month of October 1966 were as followst (Curie) (Curie) (Curie)

Effluent Activity Activity Activity Tyr>e This Month Yent to Date IAst Twelve Months l Tritium 0.000000 15.617083 21.524530 Liquid 0.000068 0.010487 0.012625 Air, Xe 5 537289 99.773740 100 359260 Air, I-131 0.005863 0.109908 0.115873 Air, H.F.P. 0.055371 0.997737 1.003590 Four barrels of waste were drur.:med for temporary storage. No drums were -

ehipped from the site. 4 Radiation exposure for all SNEC personnel as measured by film badges for the month of Septscher 1966 were a maximum of 220 mrem with an average of 36.6 mrem.

Radiation exposure for all visiting personnel es measured by film badges for the month of September 1966 were a maximum of 300 mrem with an average of 12.5 mrem.

The average radiation exposure for all personnel as measured by film badges for the month of September 1966 was 27.9 mran. -

I

SAXTON NUCLEAR EXPERIMENTAL CORPORATIO!1 OPERATING STATISTICS _

HONTH October YFAR 1966 NUClJAR UNIT HO,NT)) YFAR TO DATE TIMES CRITICAL NO. 0 21 476 HOURS CRITICAL HRS. 320.50 5,279 98 18,161.n TIMES SCRAMKED (KANUAL) NO. 1 21 283

  1. TIMIB!}CRAHKED(INADVERTANT) NO. 0 1 30 THERHAL POWER GENERATION HWH 7,502.61 n5,001.23 325,051.05 AVERAGE IURNUP (Pu Region) WDMN 612.42 9,452.51 9,514 22 CONTROL ROD POSITIONS AT llND OF HONTH AT llQUILIBRIUM PGIER OP O HWt MAIN C001 ANT BORON 1276 P!H ,

RODS 007 - INCHES NO. 1 0 h0. 2 0 NO 3 0 NO. 4 0 NO. 5 0 NO. 6 0 E!ECTRICAL UNIT HONTH YEAR TO DATE GROSS DENERATION HWH 1,409.00 20,383.00 54,665.00 STATION SERVICE HWH 161.22 2,109.18 ID,3n.47 STATION SERVICE  % u.44 10 35 13.68 AVO. PLANT EFFICIDiCY - HWH(e)/HWH(t)  % 18.78 17 60 16.82 AVO. GENERATION RINNING (320.50 HRS) KW 4,396.26 4,003.57 3,314.24 PIANT linD PACTOR -

(AVO. GEN. FOR HONTH/ WAX. IIAD) $ 42.37 62.50 30.66 AUXILIARY STEAM SUPPLY - HUCIAAR STEAM BUPPLIED Bf REACTOR HRS. 320.5 5,138 78 14,837 75 RWDF EVAPCRATOR OPERATION HRS. 0 1,523.58 3,584.83

  • REMARKS:

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