ML20085H002
| ML20085H002 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 05/31/1968 |
| From: | SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 NUDOCS 9110280100 | |
| Download: ML20085H002 (7) | |
Text
{{#Wiki_filter:_ / / / SA%TU: !!UCu%H E:PE1D7"TAL CORP 0'il.TIUI /,- Crerationt Herort fog h 1968 1. Rrl,CTCR OPERATH!!S At the beginning of thJs report period the reactor was operating at 23 51Elt. On thy 1,1968,.the react.cr tripped due to low flow in the main coolant systaa. The low flow trip signal was due to a tube failure in tne VFD set clutch centrol which was, supplying the main coolant pump power. After making receirs to the VFG control circu try the reactor van taken critical and loaded to 23.513!t until May 9, when the power escalation progra:a was initiated and the rcaetor power was increased to 26 7 f?lt. Power was again increased on May 4 to 28.410lt. On May 19, arcing in the VFU excitov caused an underfrequency scram. The exciter ccure.utator uas repaired and the reactor again taken critical. During startup of the secondary system the reactor tripped while atttre.pting to roll the turbinc. Tne reactor trip was due to closure of the PRV. The reactor was again taken critical and loaded to 23.5 ITit. On May 21, the power level was increased to 28.4 IDit and maintained unti.1 May 23 when power was increased to 30.4 Init. The power level was aSain increased to 31.4 lait on May 28 and maintained until shutdown en May 30 at 4:23 P!;. Ilot shutdown was maintained during the r(nainder of the month in preparation for reactor operator licensing exsminations. 2. EXPERECITAL PRO 3P,elj The elevated power test was irdtiated during this report period. The objoetive of this test was to obtain 19.1 kw/ft or a maximum power of 35 Milt. On May 3, a full core flux map and thermal hydraulic map was taken and analyzed to obtain a bsseline. Thepeaklinnarpowermoacuredwas14.3kw/ftat23.5Ifdt. The physics measurements were in good agreement with the predicted data. 1;ucit. ate boiling was measured and found to be 4% at 23.5 ) nit. On May 9, the pri:aary poacr was increased to 26.7 K t and the peak linear power measured was 15.6 kw/ft. The poict was increased to 28.4 init on May 14, and the peak linear pouer measured was 16.8 kv/ft. At this point the secondary system had almost reached its marimura output with the main stea:a pressure reducing valve full open. By increasing the core inlet temperature and decreasing the turbine inlet pressure, the reactor power was increased to 30.4 ILit on iby 23 At tMs power level the peak linear power meacured was 18.0 kw/ft. On May 28 the power was incre!.ced to 31.41 Cit and the peak linear power measured was 18.5 kw/ft. 3. OPE 1ATId;AL TUiTS The SI!EC fire and evacuation alarms were teated on May 3, 10, 17, 24 A.tormal test of the safety injection systcrn was conducted on May 15th. On May 3rd the radiation monitoring circuits were tested. 9110280100 910424 PDR FOIA DEKOK91-17 PDR
l ch0 Operatienc ;tepost for U M 1 R o,_ __...s.$ 4. U/J"7.ECE The principal ite::s of mechanical unintenance for the month included cinntalling piping for the antw.atic blowdoun onmpler; inctalling a Jadder at she east end of the control and auxiliary building; replacing the GM building inlet air 111ters; rep] acing the hydraulic reals on the fork lift truch; machining a new packing nut nul raaachining a stuffing box for the charging pumps; replacing the stuffing box on number two cylinder on number t.to charging pump; fabrienting a reconi storage rack for plant records; inspecting the tube tide of the evaporator condencer; prococcinc 4 drums of evaporator concentrates; lubricating the plant. ventilation fans.; rebuilding the control room air conditioner empacacor; fabricating an cmcrgency key holder for the key locker; i cleaning the control and auxiliary building sump pump discharge pipe; receiving and storing an unfueled 2x2 cubaccobly and cupport tube; replacing the centairnent veccel 20 ton crano brake dison, platto and solenoid; and replacing a to: tion of pipe in the vacto plant hotwell vent line. The major itcas of electrical and instrtracnt maintenance include enlibration of the charging pump pressure gauges; checking the circuitry of pouct rango channel A for intemittent arcing; repairing the chcaintry laboratory spectrophotmoter; repairing the count rom liquid scintillation counter printer circuit; installing a new photomultiplier tube in the alpha counting cystem; repairing the tachometer cencrator on number one charging pump flow indicator; repairing i.he make-up purification cysten recorder prjnting mechaniam; replacing the motor besrings in the chemistry laboratory alpha monitor vacuum pump; ecacuring the voltacc on the cathodic protection system; installing a new voltage regulator on the fork lif t truck; replacing intemodiate rance channel A nuclear detector; replacing the brushco on the variable frequency cencrator clutch exciter; replacing the valve operator on the doacrator steam valve; repuiring the high voltage eupp4 on power rare,c channel A; replacing the vanes, bearings and fan belts on the containment vessel radiation monitor pump for channeln RIC-1, 2 and 11; repairing the computer indicator circuitry for the steam generator b1midown raddation monitor, RIC-51 and replacing the carbon vanes in the site particulate monitor, RIC-9. 5. cHqqsTRY Main coolant system chmistry wau maintcined for power operation conditiena throughout the month of May. Doron concentrations ranged frm a high of L68 pTn at the beginning of the month to a low of 202 p;n at 31.4 Wt. The activity cf the main coolant increased to 1.41 ue/cc at 31.4 Wt, A summary of the anaVses on samples taken froa the main coolant tyctea during the month is contained in the following tabic l l l
l I f SNEC Operations Report for
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ISy 1968. f ! bin Coolant Syctem IMnimq 14uifs pH at 25 C 5.93 b.82 0 l Conductivity, umhos 2.94 4.74 i 202 468 Boron, pga Chlorides, p 4 0.005 4 0.005 Hydrogen, ce/pu nc ii 0 at STP 16 65 2 Crud, ppb $3 53 Oggen, pg3 4 0.005 0.005 Lithium, ppa 0.09 0.19 Gross Beta-Gama (15 l'in. Decanced) uc/cc 0.23 1.48 Tritium,uc/cc 6.15x10-2 1,$3x10-1 L A surenary of the analyses of the otorage well water and the refueling water storage tank is contained in the following table Analysis Storare W 12 IMST 9. Doron, ppm 2005 1768 Chlorides, pgn 0.075 0.080 Gross Beta.Gruxna, ue/cc 1 75x10-> 1.14x10-3 14ake-up water to the primary syntan contained 0.002 pga silica and less than 0.005 run dissolval oggen. Sodium analysis performed on the steam generator and the steam samples during the power escalativn program indicated i that there was less than 0.5% carryover of moisture. heept for a brief period after necondary syntan startup on May 20, the stca:n generator blowdown during the month was less than 1x10 ge ac the steam generator chlorides runained below 0.20 pps. The avera l uc/cc. l 6. PADIATION /J:D LSTE DISP 0 CAL Radiati n surveying consisted of routine plant surveys, 0.V. during shutdwn and materials shipaents. The following maxinum radiation readings were taken Ioentfen Radiation Readine, ffM_Buildig Wast.e Drum (baling machine) 0.5mran/hrbeta-camma ChargingPump(contactwithchamber) 30mran/hrbeta-gmna Cample Roan (door of sample panel) 1.8 mran hr beta-gamma Chanical lab Hot Sink (l" from drain) - 15 mran beta-gantna - i ,r,,vn--w -ev,.--e>+, ,n c r -y- - m,,. w,, n e m w www. n n,.. ee, w r n n.r y. ..n..,-, m n w, ,+,y- ,,wyme-,.e,,*~~~vsww- ~--***~~w w M ~ t* &'s rf
SUEC Operations Report for F.av 1969......_, #6 beation Padiation Heading RADF Evaporator (under bottcn) 19 mras/hr both-gana Evaporator (contactoutcidoupperlevel) H mras/hr beta-cama Drum Storage Arca (at RRA fence) 1.7 mrm/hr beta-camma 'l C.V. Primary Cmpartment (general upper Icyci) 75 mrm/hr beta-gama Priman Ccopartment (contact M.C. pump volute) 210mrm/hrbeta-gama Primin Ccepartment (S.O. bottcu) 200 mran/h' beta-cama Prinary Compartnent (pressurizer bottcc) 60mrna/hrbeta-camma Pr3 mary Compartncnt (general lower level) 40 mran/hr beta-gterna Prinary Compartment (Regen. HX) 210 taran/hr beta-gamma Pritnary Canpartnent (Non-Regen. HX) 35 mraa/hr bete-gama Auxinary Equip. Canpt. (S.C.!!.X.) 3 mrem /hr beta-gamma Auxilia:y Equignent Compt. D.T. top) 4mran/hrbeta-gamma Auxiliary Lluipnent Ocept. D.T. bottcen) 45 mrun/hr beta-gn:ma Auxiliary Eq pment Canpt. general icmcr level) 4 mrnn/hr beta-gama Reactor Dock water level at grating) 50mrm/hrbeta-gamma Reactor Deck instrumentports) 200 mran/hr beta-gama Reactor Deck waist level) 50 mrm/hr beta-greca Reactor Deck storage well railing) 18 mran/hr bota-gam:rA Rod Room (general area) 7 tarm/hr beta-gn=a Contamination surveying consisted of routine phnt cite curveys of materials shipped, toole, equipaent and C.V. during shutdown. The clean areas were within the "C1can Area" linits. The controuod area was generally within the "C1can Area" limits. The controlled area was cleaned hequently to keep and/or to return it to the "Cican Area" limits. The exclusion areas vcre cleaned periodically to minimice the amount of sacarable contemination. The following contamination IcVels were observed beation Contdetination Readinn C&A 1hildinn Charging Pump Chamber 50450 d/m/ smear beta-gama Charging Pump Chamber < 10d/m/cnearalpha Charging Room noor 390 d snear beta-gama Sample Room Sink 22270 d smccr beta-gama Sample Room Sink 4 10 d smear alpha Sample Roan Floor 610 d e'toar beta-gema C;atical lab Hot Sink 60530 d caear bett.-gaman Chmical hb Hot Eink .c: 10 d cacar alpha l f +r --*r
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l S1:50 Operations Report for ..... //5 i 1:ay 1968... Incation Contamination Readinr. L'D P Pump Rom noor 1760 d/m/Incar beta-grana Shipping Rocn noor 430 d/m/mcar beta-ga:na C.V. Operating Deck 5285 d /tracar beta-grena Operating Deck 4 10 d rnear alpha l ReactorDeck(head) 9305 d smear beta-camma I Reactor Deck (headJ 4 10 d mcar alpha ReactorDeck(grating) 20765 d encar beta-ga,*ma Reactar Dech (gratin ) <:.10 d anear alpha . grating)) grating 1415 d amcar beta-gamma Primary Ccnpartenent 4 10 d _ cacar alpha Primary Canpartment Liquid and gascaus effluenta frcr:. the Sl;EC site for the month of May 1968 were as follows (Curie) (Ourio) (Curic) l Effluent Activity Activity Activity t pe. Thi,e,, Month ,Y_ car to Dato Jnst Twelve Months Liq 2id 0.000303 0.002731 0.009575 Tritium 0.304600 2.6606',9 4.323114 Air, Xe 3,380976 15.052861 25.891394 Air, I-131 0.00014g 0.000321 0.001972 1.ir, M.F.P. 0.033810 0.150528 0.258913 Pive (5) barrels of wa,ste were dru:.cnod for temporarf storasc. No drums were shipped frm the site. Radiation exposure for all SNEC personnel as measured by film badges for the month of April 1968 were a maximum of 600 mrem with an average of 75.28 mran. Radzation c.xposure for all visiting personnel as measured by film badges for the month of April 1968 were a maximum of 205 mre with an average of 9.42 mran. The average radiation exposure for all personnel as measared by film badges for the month of April 1968 was 57.63 mrm. l _r ,__e_..,._ ,--,m. -,m..
t EAXT0t1 NttCIIAR EXPER1HENTAL CORPORATION I OPERA'!ING STATISTICS HONTH MAY YEAR 1968-ECIIAR Ut0T @HTU YFAR TO DATE l T TI)@ CRITICAL NO. 3 101 643 l 1100RS CRITICAL HRS. 676.4 1,M5 66 21,688.66 TIMPS SCRA)'JtED (MANUAL) NO. 1 39 366
- TILE QCRtJtHED (INADVERTANT)
No. 3 6 39 j TRERHAL PWER GENERATION WH 19,121.59 26,456.36 404,426.29 WDM 1,479 21 2,159 55 15,993 76 AVERAGE ILIRNUP 0 _ HWt C0!! TROL ROD POSITIONS AT IND OF HONTH AT IGUILI!RIUM POWER OF MAIN COOLANT DORON 230 PPH 1 I 10DS OUT - INC;!5 l 1 NO. 1 0 No. 2 10 NO. 3 0 l 0 NO. 6 Q,_, 1 NO. 4 0 NO. 5 EIEC'I?ICAL UillT }j0 NTH Y'.AR - TO DATE GROSS OENERATION WH 3,407 00 4,862.00 68,138 50 STATION SERVICE MWH 341 70 1,535 57 13,751.47 STATION SERVICE 5 10.03 31 58 20.18 AVO. PLANT EFFICIENCY - WH(e)/HWH(t) 16,8 18 30 16.85 AVO. GENERATION TfJNNING (670.90 HRS) - KW 5,077.60 4,730.90 3,441.13 l PIANT IAAD FACTOR - (AVO. GEN. FOR HONTH/ MAX. IDAD) 72.69 21.15 20.12 AUXILIARY STEAM SUPPLY - NUCLEAR STEAM SUPPLIED Ut REACTOR HRS. 707 30 1,069 47 18,220.56 RWDF EVAPORATOR OPERATION HRS. 58.0 283.26 6,741.66 May 1 - The reactor scre. mod due to under frequency (60 cycles) on the V.F.O.--
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Urderfrequency was caused by tub'e failure in the clutch excitation control unit, 15v 19 Serm due to itnderfremiency on V.F.G. Underfreauency was due to commutator. areite on the V.F.G. excitation M-O Set, h,- a n c + n pw 1 n.m en whi i n at +,ent i ne t.n voll t u rbi n e. Pnv n1nmire enunpd em en 4 sciam because 35 W ecrams were unblocked by excessive steam flow during attaapt to vnal + n chi n n. E l. _-.~.s._~,..-,,,._e_..__,.._r.-.._._,, _. _.. -... _ _ _. -,. _. -..., -..... ~ - - __-,,A.,.~,
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