ML20085H360

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Monthly Operating Rept for Oct 1964 for Saxton Nuclear Experimental Corp
ML20085H360
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 10/31/1964
From:
SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110280250
Download: ML20085H360 (8)
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  • cr Rerort for 0%r N64
1. RDOT 0?rKJ:0N At the beginning cf this report period the reactor was being operated at 23.5 Mdt in continuation of the che~.ical shim program and the defected fuel rods experiment. At 9:44 AM on October 2nd the reactor power level was reduced to 20 Wt.

Tweny Mdt operation continued until equilibrium Xenon was reached, and at 9:00 AM on Octoter 5th the power level was reduced to 10 Wt. Forth-eight hours later at 9:00 AM on Cctober 7th the power level was returned to 20 Mdt. Twenty Mdt operation continued until 0:00 AM on October 9th when the power level was increased to 22.5 Wt. Operation at L 5 Wt continued until October 13th.

On October 13th trouble was experienced with valve HIC-27V which is in the auxiliary systems return line to the main coolant system and is located in the ecntainment vessel. The valve could not be opened from the control room. After detemining that the trouble was not in that part of the control circuitry located outnce the containment vessel the decision was made to shut the reactor down and enter the containment vessel. During load reduction, at 10 Wt, an attempt was made to switch the nain coolant pump power supply free the normal supply to the variable frequency M3 set. A voltage dip occured and caused the inverter-diverter which feeds the vital bus to switch over to battery operation. A faulty relay prevented the inverter-diverter from automatically returning to the normal A.C. feed. In an effort to eliminate the heavy drain on the battery caused by the vital bub, an attempt was made to tie the vital bus to its emergency fee'd. The two voltages were out of phase and caused a low voltage on the vital bus and a reactor scram. The containment vessel was entered during the evening cf October 13th. The trouble with HIC-27V was found to

" be a stuck solenoid valve in the pneumatic control system. In as much as the defect test was completed, the decision was made to commence a scheduled outage. Cooldown of the main coolant system was initiated on October 13th.

During the period October 14th to October 29th the reactor plant was in a cold shutdown condition. The r.ain coolant system was fi? led, venting was initiated, and a cold leak test was completed on October 28th. On October 29th the venting procedure for the main coolant system was completed and heat-up was initiated. A hot leak test of the main coolant system was completed on October 30th.

The reactor was made critical on the morning of October 31st and a just critical rod pod tion measurenent was made. Overlap checks between intemediate and power range instramenta+. ion showed that power range detectors B & C needed to be repositioned. The reaeter was shutdown, the containment vessel was entered and power range ionizaGon chambers "B" & "C" were moved closer to the reactor vessel. The reactor wa: mods critical again at 3:00 E. The secondary system was started up ar.d the generator was synchronized cn the line at 5:00 PM. The generator was then loaded to produce a. reactor power level cf 20 Wt. Power operation at this level continued for the recainder of ths day.

2. - EXPERIMENTAL PROGRA1:

l Reactcr open nen at the beginning of the month was devoted to obtairdng further irradiation on the subassembly containing the defected fuel rods. A load swing from 20 W t tc 13 Wt and back t , 20 Mdt was made on October 5-7 to obtain base line data for sinilar power swings planned for the synthetic crud test.

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The rubassembly contu.ning thc defected fucl rode was removed from the core er 0 teber 22nc and placed in a failed fuc2 can. Samples were taken from the sealed can as time permitted during the shutdown.

The :.ixing and injection equipment for the crud teot were installed and crud mixing was co=enced.

Tne calibration of the loop differential pressure cells was completed during plant shutdown.

Just prior to shutdown, "at power." rod worth measurements were made as the main coolant b:r:n concentration was reduced frem 524 ppe to 349 p;n.

3. OPERATIONAL TFS;"'S On October 9th a normal test of the safety injection system was conducted.

The radiation monitoric.g system circuits were tested on October 15th.

Tne main coolant systc. was successfully hot leak tested on October 30th.

The #2 turbine overspeea trip was tested on' October 22nd. The trip fun:tien3d at 1950 RPM. -

4. K C "T2:ANCE y ,

"'he principal items of mechanical maintenance for the conth included the preparation of the rer.etor vessel head for subassenbly changes; removing the 3x3 subassembly containing the defected fuel rods from the center (N-1) core position; restcring '.e reacter vessel head to normal operating condition; installing a new belt er the EDF rvnperator roen air bandler; installing new insulation and weatherproofing en the safety injection system pnematic operated valves and on the stack fan drain line; processing eignt drums of radioactive evaporator concentrates; replacing the Uc. 1 charging p=p plungers with repold shed ones and repacking each stuffing box; replacing the bearing in the fan for the radiation monitoring syste cabinet; cleaning f and changing the c '. in the submersible pump being used as an WDF pipe tunnel sump pr.p; installing rm sea] s on shutdown cooling pump No.1; flushing the control rod drive mechanism rocn air handler; repacking the top shut-off valves on the steam generatcr level columne i.apping the sealing surfaces of the purification stop valve, HIC.23; repine!ng the de:sitant in the control air dryers; cleaning the storage well heat exchanger tube hnQ . repacking the secondary system saline addition pump; l cleaning the seway trea*,:ar- chlorine pump; and replacing a fan belt on the primary ecmpartment air handler.

l The major items cf electrical maintenance included the repairing of the main l st eam flow recorder chart. ar.ve; installing new GM tubes in three area radiation meniters and n ene portab'.e curvey instrument; installing special radiation detecting equipme:a in the containment vessel for fuel handling; preparing the instrumentation on the reactor vessel head for storsge well flooding; measuring the resistance of all nuclear ir.strumentation detector cables; cutting back the cables and reaking the connecticns tc the dete:ter in power range channel A; replacing the solenoid valve in

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the control a:r system for the auxiliaq system return valve HIC-27; checking the

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platera cn Ohnnnel B source range PJ3) cleaning and replacing the mercury in the manemeter cf the refueling water storage tank level bubbler; repairing a limit swit ch en the centainment vessel rotar/' Ora.ne; replacing three pressurizer heater cablee; reconnectind the pressuri:cr neaters making up dank #2 in open-delta in crder to discontinue the use of two heaters having bad connector pins; repairing the log microammeter unit in intermediate channel A nuclear instrumentation; and repairing the auxiliary contacts on the line contactor of the inverter-diverter.

5. P Wl? CHA!GES

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A new 9-rod experimental fuel subassembly was installed in the center core position (b1}. The rcdr have free standing cladding and are fueled with pelletized UO2 One of these new rods has sensitized of nominal Two 5.7% enrrods other cnment have inthe U-235. moisture contents of the fuel controlled to 50 pin cladding.

and 13 ppm respe:.tive:y. A new grid design is used in this new subassembly. This new design is of the " Egg Crate" type with interlocking sheet metal strips brazed together that is presently used but contains an inproved spring clip design. The new spring clip has age hardenable Inconel 718 instead of 304 stainless steel.

Equipmen+. for mixing and injecting crud (ferrous hydroxide Fe(OH)2) 1"t the reae.cr coolant system was installed in the control and auxiliary building. The diecharge cf the crud inje: tion pump was connected into the existing charging Lystem.

The bubbler system that is used for measuring the liquid level in the annuli v of the radica:tive liquid storage tanks and-the spent resin etorage tanks has been t:.dified and enlarged ec that it can be used to measure the liquid level in the inner tanks of the.e same storage tanks.

Many of the major components of the supercritical loop were placed in the acntairmc-

  • esse 2. The control panels and the switchgear cubicles for the super-critical experiment were installed in the control and auxiliary building. No tie-ins of this c>=crimen+ were made to the exieting plant system during this report period.
6. CHDCS"'RY 2e mai:. .colant system was maintained at operating conditions until C::cber 1? :. Tnt bcron concentration in the loop was maintained at about 524 p;ra until Oc :w ~_1 h wnen it was reduced by bleed and feed to 349 ppm. On October 13th the bore:. u pentra*.icn was increased to 410 ppm for main coolant systm cooldown.

Tne me:.n i:c.t sptem remained in a cold shutdown condition from October lath to 0:tober I.d. when heatup was initiated. Hydrazine was added to the main coolant on October 2 M and tydrogen was added on October 30th.

Daring the plant shundown period the resin in the purification system ccminerc?_f zer wa? repla:ed with 6 cubie feet of anicn resin for boric acid removal curir.g tr e cr;d test. The resin we checked for chlorides to insure that no chloride pr:slem w uld develcp when the cemineralizer was put in use.

One hundred and fifty :. oven grams of potassium chromate was added to the ecmoenent cooling system to bring the chromate concentration from 410 ppa up to 550 v

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'te bori aci; mu tar.ks was filled with a 127 boric acid solution on '

October 3Cth.

A su=ary of . .e mair. eoclant cheristry tnalyses made during the month are ,

containcd in the follcwing table Vain Cociant Srrtme. Minimum Maxdrum_

Conductivity, umhos 8.22 24.4 Soron, ppm .

349 777 li.thium, p7c.. .062 .255 Potassiu , ppm 1.20 7.08 Chloridee, p;n (0.005 .075 Q):ygen, ppm 4.005 )O.5 Crad, ppt 26.0 79.2 15 Min. 3ross Beta Gamma, ue/cc 0.109 1.17 Except for a d.rt period during startup on October 31st, the chlorides in the steam generator were maintainec below 0.155 ppm. The average activity of the stean g r:erater blewdevr. during the month was less than 1 x 10-u ue/ce.

The r.ixed bed demineralicer was regenerated on October 21st. The effluent was four d to have a low pH and a high conductivity. The trouble was found to be a lesky acid valve which was allowing acid to slowly drain into the mixed bed. The s conduct;vi'.y and pH retu ned to normal after the acid line was flushed with good water.

7. RAD 3 ATIO!! AND WASTE DISPTAL Radiatien surveying consisted of routine plant site surveys, RKDF, waste dm;.9.s for sterage and an incon ng shipment of fuel. The following maximum and de:ay reading wer= taken*

_Ic cat i ca Radiation Readinn MIDF Evaporater (under bottom) 100 mrem /nr beta-gamma Evaporator (contact outsid upper level) 50 m-c:/hr beta-gamma Vast e Dru::. (for storage - contact) 145 mrem /hrbeta-gamma War e Dram (fcr stcrage - meter) 12.5 mrem /hr beta-gn=a Drum Sterage Area (at HRA fence) 11.0 mrea/nr beta-gamma C&A Patidis Waste D.am (baling machine - contact) 13.0 mrem /nr be:.a-gamma Cr.arginr. Pump (contact with chamber) 140 mrem /nr beta-gn=a Sample Roce (at. door of panel) 7.0 mrcm/hr beta-ga=a Chemical lab Hot Sink (l" from drain) 5 0 mrem /nr beta-gne n i

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43 Heure After Shutdown Control Rod Drive Room (ams reach up drive mech.) 32 mrem /hr beta-gn=r.

Primary Compartment (MC pump volute) 110 mrem /hr beta-gn=a Primarf Ccepartment (steam generator - top) LO mrea/nr beta-gam a Primary Compartment steam generator - bottom) 60 mrem /hr beta-gamma Primary Compartment pressurizer - top) 200 mrea/hr beta-gama Primary Compartment 50 mrem /nr beta-gamma-Primary Co=partment (pressurizer - bottom) generalupperlevel) 33 mrom/nr beta-gamma Primary Compartment (regenerative HI) 70 mrem /nr beta-gama Primary Compartment (non-regenerative HX) 43 mrem /ar beta-gama Primary Compartment (general lower level) 32 mrem /hr beta-gama Auxiliary Compartment (discharge tank - top) 6 mrem /hrbeta-gamma Auxiliary Com?artr.er'. (discharce tank - bottom) 30 mram/hr beta-gama Filter Vault (emtact curif. syst em post filter) 1900 crem/hr beta-gamma Cit c Vault (:. enter of room) 160 arem/hr beta-gama Filter Vau'_t (at acor) 5 r m/hr beta-gemn l~d Heure Af ter Shutdog v Prita y Comparm ent (MC pump volute) 60 mrem /nr beta-gamma Prim ry Compr-r ment (steam generator - top) 11 mrem /hr beta-gnma Primary Cc=pa-tment (steam generator - bottom) 30 mrem /nr beta-gama Primary C =partment (pressurizer - top) 50 mrem /hr beta-gama Primry Compartment (pressurizer - bottom) 25 crem/hr beta-gamma Auxiliar/ Cerpartment (discharge tank - top) A mret/hr beta-gama Auxiliary C .: partner,t (discharge tank - bottom) 12 mrem /nr beta-gama Reactor De9 (contact with grating) 140 mrem /hr beta-gamma Darir;* Eeatur Prior to Startuo Priar.rf Cempartment (MC pump volute) 50 mrem /nr beta-gama Pri.ary Compartment (steam generator - top) 2 mram/hr beta-gamma P:imary Compartment (steam generator - bottom) 15 crem/hr beta-garna Primey Compartment (pressurizer - top) 15 mrem /hr beta-gacma Pr maq Compar+r.ent (pressurizer - bottom) 20 mrem /hr beta-ga a Prman Compartment (general upper level) 16 mrem /hr beta-garr.a Princ.ry Compartnent (regenerative HX) 80 mrem /hr beta-gama Priu y- Compartmer6 (r.on-regenerative HX) 90 mrem /hr beta-gama Prirran Compartment (general lower level) 37 mrem /hr beta-gamt.

Rea ner Deck (contact with grating) 100 mrera/nr beta-gamma Fi?.ter Vault (contact purif. s Filtel Vault (center of roo=) ystem post filter) 2600 mrem 260 mrem /hr/nr beta-gn=ma beta-gamma Filt er Vault (at door) 5 mrem /hr beta-gn=n J

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. . . , #f Jertaminaticn surveying corssist ed of routine plant cite surveys, surveys of the C.V. dur;ng chutdown, L*DF, tools, sources, waste drums, and new fuel assembly.

The clean and controlled areas were generally within the " Clean Area" limits with the All areas were cleaned periodically to exception of pemanent exclusion areas. The following contamination readings minimize the anonnt of smearable conta ination. .

were taken:

Contamination Reading Ireatien L'D F 820 d smear beta-gamma hmp Room smear beta-ga=a 370 d Evaporator Room 746 d / smear beta-gama

on:entrates Room C&A M1 ding 76000 d/m/ smear beta-gn=a Charg;ng Pump Chamber 3840 d/m/ smear beta-gama Charging Room Floer 2360 d/m/cmear beta-ga=a Sampic Roce Sink 1460 d/m/ smear beta-gama Sample Room Floor - 4600 d/m/ smear ceta-gama Chemical lab Hot Sink Within limits Scurces

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3850 d/m/ smear beta-gaza Operat.ing Deck (initial entr/-) 9200 d/m/ smear beta-gama Operating De:k (after reactor deck work) 390000 d/m/cmear beta-gamma Reactor Deck (befcre flooding)

Reacter Dc:k (after flooding and draining) 73500dh/smearbeta-gamma 7760 d/m/ smear beta-gamma

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Primary Compartment (upper level) 43800 d/m/ smear beta-gama Primary Compartrent (lower level) 1110 d/m/ smear beta-gama Auxiliary Comparment (upper level) 14950 d/m/ smear beta-gamca Aux 111a:7 Comparm ent (1cwer level) liquid and gasceus effluents from the SNEC site for the month of October were as fo2;cwe: ,

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(Curie) (Curie) (Curie)

Activity Inst Ef flucr *. A:*.ivity Year to Date Twelve Months

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ma Thf3 M .t3 0.000266 0.019604 0.020276 ,

L:. quid l 16.116778 16.721635 16.721635 Air, Xe Air, 1- Z. ( 0.000083 ( 0.000102 40.000102 37,552062 50.292062 l Air, M. F.P. 0.164163 l Ten barrels of waste were dru=med for temporary storage and no waste was shipped from tre site.

l Radiat1cn exposure fer all persennel as measured by film badges for the month of Sartmte: , 3964 were a maximum of 270 mrem with a . average of 28 mren..  ;

SiiXION NilCLEAR EXPERItu.NTAL CORPORATION OPEPJiTING STATISTICS MONTH Odober YEAR 1964

}DCLEArt UNIT @Q YFAR TO DATE TD23 CRITICAL NO. 2 30 267 HOURS ChITICAL HRS. 313.03 3,267.88 10,007 88 NO. 1 24 207 TIMES SCRA>MED (MANVAL)

C TD!IS SCRA)MED (INADVERTANT) NO. 1 6 25 THERRAL PCMER QENERATION FNH 6,083 40 62,120.98 163,122.46 AVERADE IURNVP HWDMN 209.67 2,114.34 7,186.92 CONTROL ROD PWITIONS AT DiD OF MONTil AT KUILIBRIUM POWER OF 20.0 )Mt MAIN 0001 ANT BORON 525 PPM RODS OUT - IN0HES NO. 1 40 NO. 2 40 NO. 3 40 NO. 4 40 NO. 5 16.71 NO. 6 40 EIECTRICAL UNIT MONTH YEAR To DATE V GROSS OENERATION INH 1,016.00 10,551.00 27,321.00 STATION SERVICE MWH 172.03 1,853.77 6,125.04 STATION SERVICE  % 16.93 17.57 22.42 AVO. PIANT EFFICIEN0Y - Xin(e)/WH(t) $ 16.'O 16.98 16.75 AVG. GENERATI0E RUNNING ( 310.67 HRS) KW 3,270 3,620 3,412 PIANT IDAD FACTOR -

(AVG. GEN. FOR MONTH / MAX ICAD)  % 31.04 32.76 27.76 I

AUKILIARY STEAM SUPPLY - NUCLEAR STFAM SUPPLIED Er REACTOR HRS. 3H.17 2,930.'2 8,055.82 RWDF EVAPORATOR OPERATION HRS. - 615.15 15,588.00

, gym , Scrma at 3:47 PM, Uctr>ber 13,196f4 due to low vital bus voltage caused ,

by tie!.ng the e.ncrgency feed in parallel with the Inverter Diverter v_thout ,

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