ML20085H008

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Monthly Operating Rept for Apr 1968 for Saxton Nuclear Experimental Corp
ML20085H008
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Site: Saxton File:GPU Nuclear icon.png
Issue date: 04/30/1968
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SAXTON NUCLEAR EXPERIMENTAL CORP.
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FOIA-91-17 NUDOCS 9110280103
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/ s SAXT0" InlCL"AR E P *tI]=TAL CO:TOMTIU!

21erations Report for Anril 196!1

1. GDE!yd The primary work offort, during the first seventeen days of this report period uas devoted to repiiring and testing the preocurizer safety valveo. The msin erlant systen wac cooled down four tines to facilitate work on these valves.

A Ncpecteu crack in the sett of valvo V-373 finally enlarged to uhcre it was pininly viribic. Upon the recommendation of the valve manufacturer the stollited i por tion of about 3/32" of seat material was removed. The seat was then rechaped and hppen fht. A service engineer for the valve manufacturer was precent for the work on valve V-373 and he also cupervised lapping the seat and disc and reacccably of valve V-372. Both valves were adjusted and tested and eventually ucro nade leak tight at 22CO psig.

Yne inverter-diverter was taken out of service on April 18th. Iow

? c:iutanet te ground on the field windings 1cd to failure of the DC voltage regulator and a reverse current relay in the control circuit. The AC-DC/DC-AC noice generator eet was sent to an electrical apparatun repair shop for general overhaul. It neu voltage regulator and a reversu current relay were procurrod and installed. The inverter-diverter uns reinntalled, tected and placed back in service on April 26th.

Da April 23rd the nain coolant system was cooled down to 225 F to f acilitak rcraire to relief valve V-53 on the purification syctem recenarative

, hes'. cahangn . Reheat of the main coolant systca, ucing the punp and proccuriner hen'.:n to ACM F and nuclear heat from 4000F to 4850 F, was conpleted on April 24th.

2. OCTOR OF'nATIO!S Daring the period April 10th to April 26th the reactor was used W.cm! Ltenav for main coolant systam heat-ups, lou power physics teacure".cnte
and rcactor operator training. Threo SHEC coployees roccived reactor start-up tra
cant.

The reactor wo made critical at 5:10 Pd on April 26th. The secondary cynm uar started up and the reactor was loaded to 23.5 !!..'t. Operation at a rw or power level of 23.5 IMt continued until the morning of April 29th. ,

At 9:i,0 AM on April 29th the reactor scrammed when a mercury switch in inc ik. 2 turnine aute ctop oil sycte was inadvertantly bu: aped by an engineer who was measuritc turbine bearing vibrations. The incrcury cvitch is part of a "Tarcine Trip" ceram circuit installed for the power eccalation program. The ren:.t or was maintained in a hot shutdown condition for the retainder of the day.

The containment vessel was entered and maintenance work was perfonned on the nuclew instrtaentation. The uncompensated ionization chanber in intenaediate range enannel A was reaoved, dried, and reinstalled.

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9110290103 910424 PDR F01A DEKOK91-17 PDR

L J Cp retion:,.:cport for t.pril 1 %!1 ,._.,,. . ._. 72 The recctor uc.c :ndo critien1 at 9265 Ali on April 30th. The start-up of the sc:endary cystaa vac interrupted when the reactor sermxned due to closure of the prescure regulating valve (PRV) below the 23.510!t pocition after it had opened beyond that position during the initial roll of the turbino. The "PnV" position scrn:n is automatically unblocked when the valve opens beyond the 23 5 I;lt position or uhen the stca a flou exet '

. the 23.51;lt value. Both the PP.V position ceran and ston:a flow unblock wc. 3 installed for the power cocalation procrun. The reactor was nado critical acain at 2:15 P!1. Tbc Ilo. 2 generator was cynchronized on the line at 3:58 PM and the reactor power 1cvel was inerenced te 23.5 Init. Reactor operation at 23.510!t continued for the renainder cf the ::.onth.

3. "ZPZ m I:TAL LOO 7PA:

The tencrature coefficient no detemined frcen ::cacurcacnts inde at zero power on0 April 19th uas -2.5 :: 10-L e h/h per degrco Tahrenheit at 005 ppu 1 oren and 495 F zzin coolant tenperatua m The core cubasceably status did not change in April. It is as follouct Core Position Subassenbly 1:-l  !!o. 503-4-26 (Plutoniu:2 - Reaovabic Rode 1 J, R:,

JO and Cl;)

1:-2 lio. 3 Reactivity (Flux) Occillator Rod

!!-3 llo. 503-4-28 (pH Test) 1:-!. Stain 1 css Steel Plug 1-5 ho. 503-4-29 (Durnable Poison Tect - Ranovabic Rods #703, //7C4 and tuo unfueled poison rods)

The total offective full power hours (EFPH) of operation for Core II ic now 7546 and estimates of the fuel burn-up as of April 30, 1968 are: Core II avc nge 800010!D/G ; plutonium region averace 14,5141;iDAmi; peak plutonium rod 10,3221;iD/l:21; peak plutonium pellet 24,L 51;lD/Iml.

4. OPERATIG:Al T31TS The pressuricer safety valves were tested on April 16th. Valvo llo. V-372 opened at 2499 psig and roset at 2228 psig. Valve llo. V-373 opened at 2484 psig and reset at 2373 psig.

-The radiation monitoring system circuits were tested on April 13th.

( On April 26th a nomal test of the safety injection systaa was conducted.

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S C Operation Report for Anril 19V ,_. < . . . W3

5. Itu"~T A::~fE Tne principu ite.c of mechanical n intenance during the month included replacing the pre-filters on the EDF cxhauct air handicr; lapping the seat and plug in the purification cyctea runote operated ctop valve, llIC-23; . lapping the ccat and disc in the regenerative heat exchanger relief valve, V-53; proccasing coven drce of EDF evaporator bottams; c1 caning chech valvec on the three EDF cpent recin storage tanko; repairing the pressure gage line on !!o. 2 cation recin tank in the make-up water treatment systua; draining the EDF evt.porator and rtran cleanin~, the level column; tightening the thrce bolto on the steam generator cafety valve, V-1046; cleardng the ElDF comprescor cuction manifold drain line; inctalling a new air conditioner in the C&A building office arca; repairing a etcam loah in the heating unit located in the west stairwell of the C&A building; fabricating a gag for the safety injection system air operated valves; cutting nincty milo off of the scat of pressurizer safety valve, V-373; and lapping the coats and dices and adjusting the set pressurec of both proccuricer safety valvec, V-372 and V-373.

Tne major itcas of elretrical and instrument maintenance during the ucnth included checking and cetting the temperature controller for the containment vocac1 inlet air handicr; repairing the tachtecter generator no lio.1 charging pump; replacing the cooling water ret.*ulatinr, valve for the magnetic clutch of the variable freauency LG set; repheing the coil on the solenoid valvo in the contrcl air line to the chutdown cooling systen stop valve,11I0-29; replacing the

'linphragm in the vacuum regulating valve on EiDF cas compressor No.1; replacing the uncc pensated ionization chamber, connectors, and one cable in nuclear inc+rcentetion poucr range channel A; replacing a D.C. voltaco regulator and a roverse current rehy in the control circuita for the vital bus inverter-diverter af t er it had been overhauled in an electrical apparatus repair shop; repairirc t.nd calibrating the gc:ma energy spectrometer in the count rec. ,

replacing the uobble dice in the steam genera:,or blovdown meter; replacing the va.vc pmp in the hydrogen analy cr in E1DF; replacing the motors on two fanc an t he jnstrment and control cabincts for the radiation monitoring system; replceing the vacuum tubec in the dilute acid meter in the mahc-up unter treating cycLam; inctalling new strip heaters in the box covering the nuclear instrument-ation cable penetrations in the containment vessel; c1 caning a rectrictor in the controller for the auxiliar/ etcam pneumatic operated relief valve; repairing the i

liquid scintillation counter in the count roau; and replacing the carbon vanco in the air pamps for cite air particulate monitoring channels, RIC-8 and rig-9.

6 ClLTISTpJ At the beginning of the month main coolant system ebemistry was being j maintained for hot ehutdown conditions. For the next three weeks the chmistry wac alternately maintained for hot and cold shutdown conditions itr maintenanac of safety valves. liydrogen was added in preparation for power operation over the wecacnd of April 20-21 and the secondary system was started on April 26th.

! Power operating conditionc were maintained throughout the remainder of the monta.

Boron concentration varied from a high of 956 pga during one of the valve maintenance periods to a low of 468 pga for power operation at the end of the month.

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S::rf Operationo Report for ArrM 10(S gg. ... JL A cumary of the analycco perfomed on ocnples taken from the main coolant system in contained in the follouing tables 1:ain Coolant Svottr3 M nim, lip;inam pH nt 2500 5 44 6.11 Conductivity, inhon 2.60 6.67 Baron, pga 468 956 Chlorides, pga < 0.005 A 0.005 0xygon, ppa < 0.005 0.050 Hydrogen, ec/kg 11,,0 at STP 8 48 Gross Beta #samma Ils Min. Deccesed) uc/cc 9.98x10~3 2.70x10~1 l Tritium,ue/cc 2 37x10~' 4.02x10'

A component cooling sotaple analyzed on April 22nd showed the pH to be O.10, the chrr.ates to be 450 ppn and the gross beta-gn=.a activity to be at background or less than statictical error.

Analyses performed on primary make-up water on April 22nd and April 23ni choucd chlorides to be less than 0.005 ppm, oxygen to be less than 0.005 pga and silica to be 1ces than 0.002 ppa.

Stenn cencrator chlorideo rer.ained well within cpecifications for tho l operating period execpt for a brief period during start-up on April 26th. 7hc averare activity of etcan generator blowdown during thic period van icos than lxlCJ n:/c .

7. RADIATIO:i A!!D '.lASTI: DISPOSAL Radiation surveying conoisted of routine plant surveys, C.V. during "hacoua and mater 4.ais shipped. The following maximm radiation readings ucro teer. :

lt. cati on Padintion Readinn C&A Duildin-Ha m Drum (baling machine) 0 5 mran/hr beta-gar.a Charging pump (contact with chamber) 30 mrem /hrbeta-ganaa Sartle Room (door of sample panel) 1.8mram/hrbeta-gamc Chemical Inb Het Sink (l" from drain) 0.6mran/hrbeta-gar.a ElDF Evaporator (underbottom) 35 mrem /hrbeta-gar.a Evaporator (contact outside upper level) 19 mram/hr beta-ga=.a Drum Storace Area (at HRA fence) 1.3 mram/hr beta-gam.a i

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S LC Opccationn Report fur ice ', 19l t' . ,, ,, ll5 I

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td M ion Readin" Jccation C . '/ .

Primary Ocepartacnt (general upper Icyc1) 100 mren/hr bota-gama Primary Crepartnent ( sntact !!.C. pump vo." ite) 450 mren/hr beta-gera Primar/ Cmpartnent S.G. bottom) 250 nran/hr beta-gena Primry Ccepartncnt preocuricer bottan) 150nrea/hrbeta-gmra Primar/ Compartment generallowerIcyc1) 60 mrm/hr bota-gama Primtry Compartment Regen. !!X) 400 mrtn/hr beta..cana

Primar;* Canpc.rtment Non Regen. HX) 50nram/hrbota-gena Auxiliary L;uip Ccopt. S.C.ll.X.) 6 mrc /hr beta-gtrna Auxiliar/ Equip. Ccept. D.T. top) 5 mran/hr bota-gmca Auxiliary Ec.dp Caapt. D.T. bottcn) 25 mrem /hr bota-gn=a '

Auxiliar/ h iui general louer Icyc1) 3 mran/hr bota-gn=a Reactor Doch (p. Ccept.uater Icyc1 at grating) 50 mran/hr beta-guna Reactor Doch (instrument ports) 450 mrcn/hr beta-gama Reactor ree': (vaist1 cycl) 100 mren/hr beta-cmma Reactor Doch (storage well railing) 75 tran/hr beta-cana Contunnation curveying consisted of routino plant cite curveys, curveys of materials chipped, tools, equi}nent and C.V. during shutdown. The cican arcas ucro within the " Clean Arca" limits. The controlled arca was concrally within the

Clean Arcs" limits. The controlled area was cleaned frequently to keep and/or to return it to the " Clean Arca" limits. The exclusion arcas were cicaned periodically l to minimite the amount of cmearabic contamination. The following contmnination levc2s ucre observod t locatien Contamination Readinn I C' A Da11d nr l

Charging Pump Chxnbcr 50450 cmcar beta-gm=a Charging Pump Chamber 4 10 d ancar alpha Charging Room Floor 390 d smcar bota-gamma Sampic Room Sink 22270 d smear beta-cama l Sample Roan Sinh < 10 d /cmearalpha

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l Sampic Rocn Floor 610 d smear bota-gama

Cnmical lab Hot Sink 6053 d smear beta-gama Chemical lab Hot Sink e 10 d amcar alpha R'DF l Pump Roca Floor 1760 d /amear beta-gama Shipping Rocn Floor 430 d / smear beta-gama f

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i S"E0 Operations Report for-D ril 1968 . . _ ,... J6 location Conte:dnation Readinn C.V.

Operating 'Jeck 2810 d /smearbeta-gama Operatin; Deck 10 d /zicaralpha ReactorDoch(head) 41200 d /cmear beta-ca=a ReactorDeck(head) 10 d smear alpha Reactor Deck (grating) 39210 6 / smear beta-gema Reactor Dech (gratig.*,) 10 d /smearalpha 6030 d smear beta-ge:m Prhary Compartment Pritacr/ Compartment (grating))

(grating 10 d .sacar alpha Liquid and gaseous effluents frcet the SMEC site for the mouth of April 1960 ucre as fcllous:

(Curie) (Curie) (Curie)

Effluent Activity Activity Activity .

T:me This Konth Year to Date List 'iwelve Monthe Liquid 0.000962 0.002348 0.010697 Tritium 0.723950 2.356048 4.109530 i Air, Xe "ch92550 11.671885 22.510608 Air, I-131 0.000000 0.000173 0.001824 Air, 1:.F.P. 0.074925 0.11671P 0.225106 l

Ten (10) barrels of vacte were drummed for tc
porary storage. No drums vero sMpped from the site.

Radiation exposure for all SMEO personnel as measured by film badges for the month of March 1968 ucre a maxim = of 510 mrem uith an average of 126 mrcm.

Radiation exposure for all visiting personnel as measured b'/ film badges for the month of March 1968 vere a marirms of 195 mrem uith an averag: of 14.5

r. rem.

The average radiation exposure for all personnel as measured by film badges for the taonth of l' arch 1968 was 92.8 mrem.

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SAXTON. NUCLEAR EXPERIMENTAL CORPORATION OPERATING STATISTICS MONTH APRIL YEAR 1968

_NUCIEAR UNIT S TH YEAR TO DATE TIME CRITICAL NO. 14 98 640 HOUR *> CRITICAL 95 92.4 439.26 21,0M.26 TIMES SCRAVJED (Mt.NUAL) . 3 38 365

  • TIME QCRAMMED (INADVERTANT) NO. 2 3 36 THERMAL PONER OENERATION MWH 1600.08 8334.77 386,304 70 AVERAGE BJRNUF WDMTU 137.14 68C.34 14,514 57 CONTROL ROD PCSITIONS AT DID OF MONTH AT B)UILIBRIUM POWER OF 23 5 wt MAIN 0001 ANT BORON 469 ppg RODS OUT - INCHES 40 NO. 1 NO. 4 40 NO. 2 26 40 NO. 3 LO 40

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NO. 5 NC. 6 's EIECTRICAL U NI" H0 NTH YEAR TO DATE GROSS OENERATION MWH 266 1,455.00 64,731.50 STASION SERVICE WH 242.98 1,193.87 13,409 77 STATION SERVICE  % 91.30 82.05 20.72 AVG. PIANT EFFICIDiCY - WH(e)/WH(t)  % 15.83 17.46 16.76 AVG. GENERATION RUNNING ( 71.85 HRS) KW 3,702.15 4,078 71 3,381.91 PIANT IDAD FACTOR - .

(AVG. GEN FOR MONTH / MAX. IDAD)  % 9.28 11.68 26.89 AUXILIARY STEAM SUPPTJ 7; NUCLEAR STEG SUPPLIED BY REACTOR HRS. 72.6 362.17 17,513.26 RWDF. EVAPORATOR OPERATION HRS. 120.26 225.26 6,683.66

  • RDMPJM April 29 - Reactor scram was due to an operator inadvertantly bumping the turbine trip solenoid wnile measuring turbine bear 1ng vibration. U> M Scrams were inserted).

Acril 30 - Reactor scram was due to PRV closure. Steam flow increased over 80,000#/hr _

while attempting-to roll the turbine. Tnis unblocked the 35 W scrams and when the PRV was losed the reactor scrammed.

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i AVERAGE ItEACT0ll PGIER - }N (UPPER CUltVE)

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