ML20085G959

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Monthly Operating Rept for Sept 1968 for Saxton Nuclear Experimental Corp
ML20085G959
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 09/30/1968
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SAXTON NUCLEAR EXPERIMENTAL CORP.
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References
FOIA-91-17 NUDOCS 9110280090
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SA : TOM If.iCIEAR EXP1: METAL CORPO '.ATJC91 Heactor Cocratdens Reoort for Sente-ber 1968

1. ILACT03 O m ?IO::S At the beginning of this report period the reactor was in a hot shutdoun condition. On September 3, the reactor was utilized for operator trai ning. On completion of training,rcactor power level was increased to 22.8 !r! in acce>rdance with phase C of the overpower test procedure. This power wn naintained until Septenber 6 when the power was increased to 2 ~,.6 U. t in accordance mth phase C of the overpower test procedure. This pouer 3c"el was maintained until September 17 when at power modcrator temperature coefficient measurements were made. On September 19, reactor power war- decreased to 22.3 K,lt and then raisod to 25.6 ILit to measure the differcatial power coefficient. This power level was maintained until Septenber 21 when the reactor tripped due to loss of the 125V DC power supply unile attcapting to isolate a ground. The reactor was maintained in hot shuMcw until September 23 when it was taken critical and loaded to 22.5 ! alt.

On September 24., the reactor tripped due to lou flow in the main coolant vstem. The lov flow trip signal was due to a fault 01 the VFG magnetic cli, ten .011. Tne period September 25 through the 27th was devoted to training ,

s tart.-aps for the Ucstinghouse customer trainees and Three Mile Island trainees.

Tueng-+cven training start-ups vero conducted. The reactor was main',ained jw crit 2cd for lou power end of life physics =casurements until September 30 uben s t ripped due to a high temperature signal induced by electronic noise tax: tu cycling of the pressurizer heaters. Following the trip the reactor wp apin tal:en critical and maintained just critical for the remainder of the mor. ' .

., {jjg3Z1:TAL PRO'Didi Frysics measurcacnt. made September 17 indicated the at power moderator

+~ m eMre coeffic;ient wa: 2.83 x 10-4/*/0F at a boron concentration of 298 ppm.

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mr M, tne alfierenual povier ccefficient measured was 4.26 x 10-4M/ Git.

N tcrc cower all rods out boron measured was 683 ppm at 530 F and ne zer o r;ouer rederat.or t caperature coefficient measured was 3.3 x 10-4M/0F ui t n c on t ro2 r oc 2 at, 27".

Tne concuctivity boron analyzer proportioning pump was replaced on Sepicarm 30. Tre unit is stdl undergoing test, and evaluation. The absorption b^ron analy: cr functioned with reasonable accuracy but is still undergoing testing anc t a w ien.

A tined 1-16 failed fuel monitor was installed in the reactor Jona: nen; to obtain background readings for the original detectors. The rise t: cci indicated sinilar Cata as the original two detectors and reveals high p:aT; im.e> near the inlet piptng to the reactor.

Sao power transiente were made during the month to simulate the overpower vxe . or in the over power test subassembly. No abnonaal conditions were observed from cutnca tram i e nt, j 9110280090 91o424 PDR FOIA l DEKOK91-17 PDR l

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SI!DC Operations Report for Sertc"ber 1958 . .. #2 The radiation monitoring system circuits were tested on Septe bcr 6 A nomal test of the safety injection cysten was completed on September 16.

The S::EC fire and evacuation alams were tested on September 6,13, 20 and 27.

4. Mall:TC:A'!CE The principal itcas of mechanical maintenance for the month included installing new belts on the containment vessel exhaust fan; cleaning the coni al and auxiliary building sump pxnp piping; inspecting the E1DF evaporator tube bundle; draining the evaporator and processing eight drums of concentrates with cament; replacing the pre-filters and absolute filters in the control tnd auxilicry building cxhsust fan hou-ing; installing new cushions on the conference

. room chairs; replacing a valve on the hydrogen gas manifold; removal and shipping  ;

the variabic frequency generator clutch for replacement of the coil; and installing ,

brackets for the E43T level transmitters.

The major items of instrument and electrical maintenance included insta131ng a new G.,M tube in the charging roam radiation monitor; repairing the alpha canting System in the count room; checking the specific gravity of the r t*c ic- service battcries; calibration of the E1DF evaporator level column; repainns the liner cir:uit in the liquid scintillation counter; repairing the nach level G-U scaler in the count room; repairing the source positioning nochanism on the EiDF effluent. monitor, RIC-6; repairing a DC ground on No.1 charg!ng pump pressure alam circuit; repairing the D/P cell on the EiDF 3 notuell level control 3cr; checking the circuit and replacing tubes in the variable ficquency cluten c1cetrcnic control; installing a temperature indicator in T en b; cud oun line; repairing the solenoid valve on the air supply to the saf ey hjectica hot les d solat. ion valve; and calibration of the containnent vesac' gaaecas ac tiviby monitor, RIC-L

5. CHU:ISTRY ,

Tne main ecolant systaa cha11 sty was maintained for power operation during the period September 3 to September 23. Hot shutdown conditions were maintained for the remainder of the month after shutdown of the secondary system en Septeuber 23 On September 3, lithium was added and the pH was raised from

<0.% pp: to 3.27 ppa. Boron concentrations ranged from a low of 280 pga to a b;Cn of 694 ppa during power cperation.

J A sunmary of the ana2;/aes perfomed on samples taken fram the main codan+ system da contained in the following-table:

S!!EC Operatienc Report for Sente;3b er 1968 ..._/Q thin Coo 3nnt Systen _

Minimum Maximum pH at 25 0 5.41 7.16 Conductivity, umhos 2.27 14.9 Baron, prin 280 694 Chlorides, pyn (one deteruination) 0.005 0.005 Hydroge ., :/xg H;0 at STP 21 38 Gross Bcta Gama $15 Kin. Degassed) uc/cc 7.09x10-3 2.53 Lithium, p;n 0.01 1.27 Ch]orides in the steam generator were maintained at concentrations well below cpecifications except for a brief period after reactor start-up on Septenbcr 23. The average activity of the steam generator blowdown during this pericd was Ics: than 1x10-8 ue/ce.

5. RADIATION IND E1SnipJSPW A(

Rac's:Icn curveying consisted of routine plant surveys, C.V. during .

shutdo.m anu :nt erialc shiprnento. The following suiraum radiation readingo were taken:

,L;ent 1 or_, Radiation Readinr.

C&A Ba1lahr.

Haste Dru:n (bcling machine) 1.5 mrem /hr beta-ga=a Chargion Pump (contact with chamber) 15 mrcm/hr beta-ga=a Sample Roca (door of sample pancl) 2.5 mrem /nr beta-gamma Catrica;. Iab Hot Sird (l" frcu drain) 16 mrem /hr beta-gamma E91 Evapentor (ar. der tot tr.) 29 mren/hr beta-ga=a Evapcrator (contact, ottside upper level) 9 mrem /hr beta-gama Dn::a Storage Area f.at GA fence) 7 mrca/nr beta-gam a

_C,d,t Reatter Deck (water level at grating) 70 mran/hr beta-gama Reactor De:k (instrument ports) 400 mren/hr bota-gama Reaeter Deck (valSt icvel) 30mran/hrbeta-gamma Reactor Deck (storage well rail.ing) 36 mran/hr beta-gama l

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SubC Operations Report for l Sect cabe FL6 8 . ... #lt Contmaination curveying consisted of routine plant cite curveys, srveys of materiale shippcd, tools, equignent and C.V. during chutdown. The clean areas were within the " Clean Arca" Idnits. The controlled area was generally within the " Clean Arca" limits. The controlled arca was cleaned frequently to keep and/nr to return it to the " Clean Area" limits. The exclusion areas ucro cleaned periodically to minimize the amount of smearable conte.ination. The follouing contamination levcis were observed:

Location Contamination Readinn CM lbildinc Charging Pump Chamber 191000 C smear beta-gn=a Charging Pump Chamber 10 d /cmearalpha Charging Room Floor 35000 d / smear beta-gx=a Scap]e rot) Sink 15200 d_ / smear beta-ca=a Sample Room Sink 10 d/n/ smear alpha #

Seaple Rottn Floor 4420 d/m/ smear beta-gena Chaucal lab Hot Sink 29800 d/m smear bata.-gama Cher.ical lab !!ot Sink 10 d smear alpha R'. 'D F Pmp Room F]cor 2818 d / smear beta-g=ma Shipp1nc Room Floor 100 d smear beta-cc=a S db.

Operating Dcek 840 d/m/ smear beta-gn=a Operating Deck 10d/m Reacter boek (hr.ad) 18100 d/m/ smear

/ smear alpha beta-ga=a Reactor Decs (ncad) 10 d/m/cmear alpha laquid and gaceoue effluents from the SICC site for the month of September 1968 were as folloas:

(Curie) (Cune) (Curic)

Erfluent Activity Activity Activity Type This Month Year to Date Inst Twelve Months liquid 0.001166 0.007384 0.013401

"'ritium 0.296790 5.778877 6.389665-Air, Xe 0.832639 17.143360 z2.509438 Air, I-131 0.000083 0.000434 0.002082 Air, M.F.P. 0.008326 0.171433 0.225094

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SI.TC Operationo Report for Septenber 1968 - . . . //5 Ten barrels of waste were drummed for temporary stora6e. 1;o drams were shipped from .the site.

Radiation exposure fu all SISC personnel as acaoured by film badges for the month of August 1968 were a maximum of 250 mrom with an average of 28.2 nram. ,

Radiation c::posure for all viciting personnel as measured by film badges for the month of Aagust 1968 were a maximum of 60 mram with an average of 2.89 necm.

The average radiation exposure for all personnel as measured by film badges for the month of August 1968 was 20 31 mrcra.

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SAXTON NUCLEAR EXPERIMENTAL CORPORATION RERATING STATISTICS MONTH Septc,ber YEAR 1960 UNIT HONTil YEAR TO DATE NUCEAR NO. 31 232 774 TDGS CRITICAL imS. 562.7 2,261.89 22,834.89 HOURS CRITICAL NO. 10 101 428 TDfES SCRA)MED (MANUAL)

NO. 3 11 42

  • TDE QCRAMHED (INADVERTANT)

MWil 11,629 38 49,663.18 427,633.n THFJMAL POWER GENERATION WD/HTV 949 27 4,053.85 17,888.08 AVERAGE WRNUP CONTROL ROD PCGITIONS AT DID OF MONTH AT BlUILIBRIUM POWER OF _

0 Wt ppH MAIN COOIANT BORON _694 RODS OUT - INCL 2 NO. 1 40 No. 2 25.2 No, 3 ,,14 40 No. 5 14 NO. 6 40 NO. 4 ELECTRICAL UMIT MONTH IEAR TO DATE l

! OROSS GENERATION HWH 2,064.8 0,049.8 72,126.3 STATION SERVICE HWH 318.92 2,528.32 14,744.22

% 15.45 23.57 20.44 STATION SERVICE 17.76 17.82 16.87 AVG. PLANT EFFICIENCY - EdH(e)/)Ml(t)  %

f AVG. GENERATION WNNING (457 51 IIRS) KW 4,513.1 4,461.1 3,473 0 PIANT IDAD FACTOR -

% 60.25 21 36 20.20 (AVO. GEN. FOR MONTH / MAX. IDAD)

AUXILIARY STEAM SUPPLY - NUCLEAR STEAM SUPPLIED BY RFACTOR HRS. 466.8 2,036.82 19,187.?1 RWDF EVAPORATOR OPERATION HRS. 105.25 646.86 7,205.26

  • PF.APM : 9/21/60: Inar'vertent corsa caused by loss of power to the scram breakers.

he imi:Je suiter: betatoen the batteries and 125V D0 bus was opened unilo the battery charcer and inverter diverter t.ere of_f.

9/24/63: Inadvertcat main coolant pump trip out caused by a malfunction in the-

,y sep,, w ,,n.,g.v 1 ret,,,e + n.9,_

9/30/60: Inadvertent That seren caused by a spurious electronic noise signal fr u e, n .,._

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