ML20085H346
| ML20085H346 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 01/31/1965 |
| From: | SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 NUDOCS 9110280245 | |
| Download: ML20085H346 (8) | |
Text
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.SAXTO'; F.'0!IAR PXPl?iCTA' C0t 1 P.A!! 7 Operations Rennrt for Jnnunry 1%5
_. .:V.C':0 OPDtATIONS At the beginning of this report period the reactor was being operated at a power le el of 20 )Mt in continuation of the chmical shim progrren and the synthetic crud tee . Twenty Wt power operation continued until January lith when the power level war, reduced to 10 Wt. On January 14th the power level was returned to 20 Wt.
Operation at 20 )Mt was continued until January 22nd when the reactor was shut down to begin r. s:heduled plant outage. Imediately following reactor shutdown on January 22nd contrel rac drop times were measured.
.: . GD;ERAL Cooldown of the main coolant systm was initiated on January 22nd. During tha p3 ant outage it is planned to emplete the installation of the supercritical tecnnology test loop) remove subassmbhr 503-4-25 fr m the center core position and exrane it for crud deposition with the underwater periscope; view by means of a <
bcrescope the center row of fuel rods in the center fuel assmbly in the reactor
-orel ship four irradiated fuel rods to the Westinghouse Post Irradiation Facility,
- .nd perfom general plant maintenance.
On January 28th subassembly 503-4-25 was r moved from core position N-1 and was examined using the underwater periscope. On January 29th the four irradiated fuel rods .<ere placed :Ln a can which in turn was placed in the fuel shipping cask. Three of tne rods, 503-4-24. The #101 fourth (defect),#754, rod, was taken from subassmbly#321 503-4-25. Fuel (defect), rod #102and #33 v was transferred from subsssembly 503-4-24 to subassembly 503-4-25.
- 3. EXPDtIMENTAL PROGRAM Tests to deternine the effect of main coolant pH on reactivity were continued during this report period. The pH was varied by changing the potassium concentration in the main coolant. The pH effect on reactivity was found to be non-linear. The reactivity change per unit pH change becomes larger as the pH is decreased.
Tor.perature coeff :ient measurements were made with the reactor operating at 10 MW and again at 20 Elt.
A power coefficient nensurment was made during the reactor plant shutdown on January 22nd.
Some flux wire irradiation and flux oscillator data acquisition was accompliehed.
Test fuel subass mbly 503-4-25 was examined with the underwater periscope fer crud deposition. The crud was found to be more evenly distributed and in general heavier than that seen on the same subassembly when it was examined in December. '
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.. OFDU Nlt i TE Cn Janurv 15th a normal test of the safety injecticn system was conducted.
The radiation monitoring systm circuits were tested on fanuary 18th.
Centrol roc top time from 40" to rod bottee.in:; was measured for each control rod cn January 22nd. The maximum drop time for any rod was determined to be 0.900 seconde.
- 5. MAlliTDU f;0E The principal itta:s of mechanical maintenance for the month jncluded removing 3x3 fuel subassembly 503-4-25 from the reactor core, handling it for inspection with the underwater periscope, and placing it in the fuel storage rack; transferring four fuel rods, three from subassembly 503-4-24 and one from subassembly 503-l. 25 to a fuel can, placing the loaded fuel can into the fuel shipping cask; transferring a fuel rod from subassembly 503-4-24 to subassmbly 503-4-25; processing five drums of h*DF evaporator concentrates; repairing the top flange on tne acid flow meter in the make-up water treating system; installing a service water hne to the anti-foam tank in RWDF eentrol room; cleaning the two IMDF monitor tanks; installing new bearince in 15/DF gas compressor No. 2; installing a new disc in the valve in the line from nas decay tank No. 2 to the hydrogen analyzer; cleaning the control and auxiliary building sent11ating air ducts; cleaning the water meter in the discharge line of the INDF discharge tanks; replacing a leaky fitting on the hydrogen regulator in the calibrating system for the hydrogen analyzer; and polishing and repacking the s three plungers on th.1 charging pump. '
The major items of electrical maintenance included repairing the energy spectrometer in the count room; removing two pressurizer heaters from service and reconnecting the remaining heaters so that each standby group has four and the control gnup has six beaters; replacing the carbon vanes in the air pump for radiation monitoring channel RIC-8; calibration of main coolant flow measuring instruments, channel FR .-l. fabricating and installing extensions on the float ams of the high level akrr. :.eters on the RWDF diceharge tanks; installing the instrumentation required for refucl.ng,in tne storage well and on the operating floor of the containment vessel; :utu ng back the cable and remaking the cable connections to the detector and the cable seals tc the enclosure for the detector in source range channel B; repairing the heaung wire on the out door piping -for the RWDF monitor and discharge tanks; repairing the pre-amplifier in radiation monitor channel RIC-9; and repairing the wiring in the alpha scaler in the count rocn.
6 Pw!T :NGF4 Wor- en the installation of the supercritical technology test loop was resumed near the end of the ncnth.
Valvo, which will be used for drawing samples from the RWDF gas decay tanks, were installed in the line running from each tank to the hydrogen analyzer.
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'29t r it. deteruine the effect of pH on reactivity were conducted during the early par'. of the manth. The potassium concentration in the main coolant was increasec from 0.2 pin to 3.85 ppn. The borou concentration in the main coolant at the beginning of the month wu 394 pga. On January 18th the boron concentration was reduced to 371 ppm for shin adjustment. Just prior to initiating cooldown on Janua:*/ 22ni the boron concentiation was increased to 872 ppm and after cooldown was completed on January 24th the boron concentration was 730 ppu.
The ioline cencentration increased from an equilibrium of 0.151 uc/cc before shutdown en Jan2ary 22nd to 2.02 ue/cc four days after shutdown. The I-131/I-133 atomic ratie a measured after a power swing on January 14th was 3 04.
A su:rmary of the main coolant analyses made during the month are Main Coo) ant Svstem Minimun Maximum Conductivity, unhos 4.80 17.5(*)
boron, pga 371 872 -(**)
Potassium, ppa 0.2 3.85 Lithium, pga 068 .198 Chlorides, pga .010 .010 Hydrogen, ec/Kg H 2O .
T5.0(**) 33.0 Or/ gen, ppa 4 005 > 0. 5 (*)
Ammonia, ppa 0.25 0.82 s Cmd, ppm 092 0.1f9 (***)
i 15 Min. (degassed) '. Irons Beta Gamma, ue/cc 0.49 2.08
(*) Reactor in cold shutdown condition
(**) Reactor in hot shutdown condition
(***) Sample taken immediately after reactor shutdown on 1-22-65 l Tne chicrides in the steam generator weu i ipt below 0.220 pu during month. The activity of the steam generator blowdo.m . <eraged less than 1 x 10jheue/cc above river water background for the month.
- 8. RADIATION AC WASTE DISPOSAL Radiation surveying consisted of routine plant site surveys, waste dru=s for stcrage, ami the containment, vessel during shutdown. The following maximum readings were taken:
Imation Radiation Reading RWDF i
Evaporator (under bottma) 18 mren/nr beta-gamma Evaporator (contact - outside upper level) 3 mrem /hr beta-gamma Waste Drum ( 130 mran/hr beta-gamma WasteDrum(forstorage-uontact) for storage - moter) 6.5 mran/hr beta-gamma
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lo m...n" Radiation Readinn ;
- Yard Area Drum Storage Area (at HRA fence) 9.5 mrem /hr bets-gam.a C.V. Exhaust Filter (contact outside) 1.7 mrem /hr beta-gamma Fence (closest peint to C.V. exhaust filter) 0.5 mrea/hr veta-gamma
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Pire Tunnel East Side (behind HRA gate) 90 mrm/hr beta-gamma C&A Buildine Chemical Iab Hot Sink (1" from dmin) 9.0 mrem /hrbeta-gamma Charging Pump (contact with chamber) 40.0 mrem /hr beta-gar.u Sample Roem (at door of panel) 6.5 mrem /hr beta-gam.a Sample Storage Drum (contact) 13.0 mrem /hr beta-gamma Waet e Drum (baling machino - contact) 27.0 mrem /hr beta-gamma C.V.
l Hours after Shutdown .
ControlCompartment Primary Rod Drive hoca (M.C. (ams pump reach volute up) drive mech.) 130 mrem 37 mrm/hr beta-st=a
/hrbeta-gamma v Primary Compartnent (steam generator - top) 10 mrem /hr beta-gamma Primary Compartment (steam generator - bottam) 70 mrem /hr beta-gamma Primary Compartment (pressurizer - top) 100 mrem /hr beta-ga=ma Primary Compartment (pressurizer - bottam) 50 mrem /hr betg-gama Prinary Compartment ( 50 mrem /hrbeta-gamma Primry Compartment (general upper regenerative HX) level) 105 mrem /hr beta-gamma Primary Compartment (non-regenerative HX) 80 mram/hr beta-gamma Primary Compartment (general lower level) 45 mrem /hrbeta-gamma Auxiliary Compartment (ehutdown cooling HX) 16 mrem /hr beta-gamma Auxiliary Compartment discharge tank - top) 9 mrom/hr beta-gamma Auxiliary Compartment discharge tank - bottcm) 17 mrem /hr beta-gamma Auxiliary Compartment lower - general) 5mrm/hrbeta-samma Filter Vault (contact - purif. system post f11ter)3200 mrem /hr beta-gamma Filter Vault (center of room) 300 mrm/hr beta-gamma Filter Vault (at door) 13 mrm/hr beta-gamma Reactor Deck (at instrument ports) 150 mrem /hrbeta-gamma Reactor Decx (at insulation can) 90 mrem /hr beta-gamma Reactor Deck (at waist level) 110 mrem /hr beta-gamma Reactor Deck (contact with grating 200 mrem /hrbeta-gamma 72 Hours after Shutdown Control Rod Drive Room (tms reach up drive mech.) 25 mrm/hr beta-gamma Primary Compartnent (M.C. pump volute) 95mrm/hrbeta-gamma Primary Compartment (steam generator - top) 2 mrem /hr. beta-gamma v Primary Compartment (steam generator - bottom) 24 mrem /hr beta-gamma-l l
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Ir w sen Radiation Hend!nc fj. 7 72 Hours after Shutdown (Cont'd)
Primary Compartment (pressurizer - top) 11 mre/hr beta-gamma Primary Compartment (pressurizer - bottom) 40 mrm/hr beth-gamma Prirary Compartment (general upper level) 25 mrem /hr beta-gama Primary Compartment (regenerative }E) 105mrm/hrbeta-gamma Prinar/ Compartment (non-regenerative IE) 80crm/hrbeta-gamma Prinary Compartment (general lower level) 35 mrm/hr beta-gam a
!.uiliaryCompartment(shutdowncoolingfE) 130 mrem /hr beta-gama Anilia.ry Compartment (discharge tank - top) 35 mrem /hrbeta-gamma
/.uiliar/ Compartment (discharge tank - bottom) 23mrm/hrbeta-gamma Auxilia y Compartment (shutdown cooling pump -
cneck valves) 400 mrem /hr beta.camma Filter Vault (contact purif. system post filter) 2800 mrem /hrbeta-;amma Filter Vault (center of room) 260 mrem /hrbeta-gn=ma Filter Vault (at door) 10 mr m/hr beta-gamma Reactor Deck (at instrument ports) 100 mrem /hrbeta-gamma Roa: tor Deck (at insulation can) 27 mrem /hrbeta-gamma Reactor Deck (at waist level) '
23 mrem /hr beta-gama Reactor Deck (contact with grating) 80 mrem /hr beta-gamma 0:..tamination surveying consisted of routine plant site surveys, surveys of t
the containment vesscl during shutdown, diums for storage, fuel cask upon receipt, laundr/ crums, radioactive sample shipment and a rented boroscope. The clean and controlh4 2.reas were generally within the " Clean Area" limits with the exception of permaner.t (xelusion areas. All areas were cleaned periodically to minimize the I
amount of cmearable contamint. tion. The following contamination readings were takent
' mention Contamination Reading i ETF Pump Room 5220 d/m/.rment beta-gama Evaporator Room 690 d/m/ smear beta-gn=a Concentrates Room 1390 d/m/ smear beta-gamma Pipe Tunnel 400 d/m/amear beta-gamma C&A Bti2dir.R Chenical Iab Hot Sink 37800 d/m/ smear beta-gamma Charging Pump Chamber 58000 d/m/ smear beta-gamma Charging Room Floor 4100 d/m/ smear beta-gamma Sample Room Sink 22200 d/m/ smear beta-gamma Sample Room Floor 1000 d/m/ smear beta-gamma v
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Conta-ination Read $ nn C.v.
Upper Operating Deck 1325 d/m/ smear beta-gamma lower Operating Deck Bridge 2580 d/m/ smear beta-camma Primary Compartment-Upper Lovel 7580 d/m/ smear beta-sama 1790 d/m/snear beta-gn=^
Princry Compartnent Iower IcVel Equi;nent 74500 d/m/amear beta-gamn.a Primary Compartuent -Iower IcVel Floor 27000 d/m/ smear beta-greraa Auxiliary Equirnent Room Iower level 3460 d/m/cmear beta-gamma Roacto" L ek 132000 d/m/snear beta-gamma Lignit - . gaseous effluents # om the SIEC site for the month of January 1965 were as ft -t.'n : ,
(Curie) (Curie) (Curie)
Effluent Activity Activity Activity Tvr>e Th!n Month Year to Date last 12 Months Liquid 0.000830 0.000830 0.019619 Air, Xe 8.610411 8.610411 45.841368 Air, I-131 ** 0.000219 0.000219 0.000771 s Air, M.F.P. 0.086104 O.086104 36.911153
- Minimum Instrument Sensitivity F;ve barrels of waste were dru=med for temporary storage and thirty barrels were shippe: from the site.
Rt,diation exposure for all personnel as measured by film badge for the month of Deceber,1964, were a maximum of 370 mrom with an averap of 21 mrm.
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l SAXTON NUCLEAR EXPERIMENTAL CORPORATION OPERATINO STATISTICS
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MONTH Januury , iLAR 1965 l NUCLFAR UNIT MONTH YEAR TO DATE TIME CRITICAL NO. 0 0 377 HOURS CRITICAL HRS. 514 4 514 4 11,457 63 TIMES SCRAMMED (MANUAL) NO. 1 1 217
- TIME QCRAMMED (INADVERTANT) NO. 0 0 25 THERMAL POWER GENERATION Mk'H 9,497.62 9,497.62 187,763 44 AVERAGE BJRNUp WDATV 454.51 454.51 8,457 00 CONTROL R0D POSITIONS AT D D OF MONTH AT EQUILIBRIUM POWER OF 0 MWt MAIN COOLANT BORON 734 PIH RODS OUT - INCHES
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ELECTRICAL i' NIT MONTH YEAR TO DATE v
GROSS GENERATI0E MWH 1,595.00 1,595.00 31,202.00 STATION SERVICE MMI 194.55 194.55 6,726.3.1 STATION SERVICE % 12. .~.J 12.20 21.56 AVG. PIANT EFFICIENCY - MWH(e),%nt(t) % 16.79 16.79 M.62 AVG. GENERATION RJNNING ( S14 !!RS) NW 3,103.11 3,103.11 3,313.37 PIANT IDAD FACTOR -
(AVG. GEN._FORHONTH/ MAX.IDAD) % 60.56 60 56 28,85 AUXILIARY STEAM SUPPLY - NUCIEAR STEAM SUPPLIED BY REACTOR IUE . 514.00 514.00 8,569.82 RWDF EVAPORATOR OPERATION llRS. 0 0 15,588.00
- RD{ARFS Manual scram at 10:24 AM on January 22, 1965 for echeduled shutdown.
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