ML20085H201

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Monthly Operating Rept for Sept 1966 for Saxton Nuclear Experimental Corp
ML20085H201
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 09/30/1966
From:
SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110280165
Download: ML20085H201 (6)
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STAW lTQda E lPQIC;TA'. ':'>HPC3A,TTUl Opera ienf N mrt for Lept mber 16 l i. B / 'N:t JPL A?J d: -

1 T::o reactor wu operated at full licenced power, 23 5 in.'t during tne entire month of beptenber in continuation of the test program to develop Infomation concerning the utilization of plutonium enriched fuels in preocurized water reactors.

2 EXPi"1I!S;r A: Pa3TIA!!

Nring the rionth tests were conducted to study the change in the moderatcr tmperature coefficient with high and low main coolant pH at conttant reactor power conditions. In addition data was accumulated on the neasured dat power" temperature coeffi cient _. rod wurth, boron worth, flux distribution and the magnitude of reactivity changes due t o pH swings. To obtain the desired data temperature swings cf appruimately 100 F were made at five different positions on control rod d2 (all other rma fully watt.hawn) at both high and low pH. Four small boron dilutions of hpprodr.ately 85 pyn were required at low pH and four identical boron dilutions were made at high pH. Flu:: naps were nade at maximum and minimum rod positions at bcth high und low pH to nonitor flux distributions. The results of the series of tests made at tich pH were identical to those for the serica nade at Icv pH. Tnerefore it ,

e cor hdvd U at tmperature coefficient, boron worth and rod werth are pH indepen: lent.

Dr. beptmber 21st the average burn-up on the reactor core was 5200 !MD per MTF. An all reds out main coolant boron concentration was determined on September 23rd at a rea: tor power love 2 of 23.5 in!t, a main coolant temperature of $10cF and at equ211brium m.cn. The boron concentration for these conditions was 901 p;n J. OPI'TtATIONAL TESTS On Septmber 9th the radiation monitoring system circuits were tested.

A normal test of the safety injection system was conducted on Septmber 20th.

L. l!AI!!TE:JANCE The principal items of mechanical maintenance during the month included repairing the insulation in the containment vessel inlet air handler; replacing the belts. and eteam cleaning the. filters on the inlet air handlers for the radicactive waste treatment building; repacking the No. 3 plunger on No. 2 charging pump; checkirc and c3eanir.g the mechanical seal on No.1 plunger of No. 2 charging pump; installing ,

a shut-cff valve in the steam line to the MIDF evaporator feed eductor; installing a valve in the condensato return line fron the demister to the evaporator in IMDF; cleanang the drain line for the IMDF drum storage area'; cleaning the control and auxiliary building roof drains and repairing a leak in the roof; processing ten drums of MTDF evaporator bottoms; and acid cleaning the MIDF evaporator hotwell.

The major itme of electrical maintenance for the month included checking tne spe:ific gravity of the station batteries; replacing the coil on the evapcrator hotwell solenoid dump valve in MIDF; repairing a nitrogen regulator used in the enenistry laboratory; repairing the chenistry laboratory spectrophotoneter power supply; 9110230165 FOIA C'1 C PDR PDR DEKOK91-17 ,

..- 6 etM u V m ; for t w. h . W.....h ryan.y; t a c%n 2e on the filter ho1&r for the rtact: radioactive particulate "0:a

. t al , ree ,c.rW the ra:m cpectro.aeter in the count roomi checking and caldbrating the nuxihary W*nte r. to; pe:*nture recorder in the contml room; installing a sight

  • class on the EU,F e.:qoratur denister; calibrating the RUDF evaporator level proportional controller; replacing the noter in the computer-indicator for the radiaticn monitor on the DF evaporator hotuell; repairing the controller for the  ;

regenerative hcst enchtmcer by-pacs valve, TIC-24) checking the power supply for the portaole neutron survey noter; removing and cleaning the stack radioactive gas detector; repairing the ac3d flou meter in the water treating system; installing a new enubber and indicating pointer on the No.1 charging pump discharge pressure cago; adjusting the zero, proportional band, and the reset time on the pressuriser spray valve controller; repairing the conputer-indicator for site radiation monitoring channel, RIC-8; and repairing the decado unit of a cmnt room scaler.

5. CHD:ISTRY The nain coolant system chemistry was maintained for power operating ccnditions throughout the month. The lithium conecntration was varied in the range

< .01 ppm to 3.40 ppm for temperature coefficient measurenents at both high and low pH. Tne boron concentration was varied over the range 614 ppm minimum to 906 ppm me:inum. A sumary of the analyses made on main coolant samples taken during the month is contained 4n the following tables ,

Main Coolant Svetm Minimum hximum pH at 25 C 5.10 6.69 Conductivity, umhos 2 39 38.4 Baren, ppm 614 906 Chlorides, ppm < 0.005 < 0.005 Lithium, ppm <.0.01 1.40 0xygen, ppm 0.00 0.00 Hydrogen, cc/kg H 2O 30 59 Crud, ppb (one detemination) 19.1 19.2 Gross Beta-Gamma (15 Min. Degassed) ue/cc 1 30 ., 5.11 .

Tritium, uc/cc 2.59x10" 1.16x10'-

Gross Iodine, ue/cc (one detemination) 0.446- 0.446 Tne chlorides in the steam generator were maintained below 0.05 ppm. Tne average activity cf the steam generator during the month was less than lx10-8 ue/ce.

6. RADI ATIJJ AID LSTE DISPOSAL Radiation su* veying consisted of routine plant surveys, C.V. during shutdowr.

and materials shipments. The following maximum radiation readings were taken: i location Radiation Resdint-ChA RQ3 ding Maste Drum (baling machine) 18 mrm/hr beta-ga:r.a Charging Pump (contact with chamber) -70 mram/hr beta-gamma Sample Room (door of sample panol) 7 mren/hr beta gamma Chenical Inb Hot Sink (l" from drain) 2. 5 mrem /hr beta-ga ana -

r~r.+rs., -

me-,u--,-r -w e- --

%e+= , we g my,-eer -y ,.w ww - my ,wym,-.,.-.y.w..,, a- .-**"r * *----e 7-'ve-=-tr=w----v-w-*----W.p*+-w-*r-

-"9 do-'.- e'-*-'ee'-- C* " = '**P-*T-F

SIM S crations heport fo:-

bent-ter .19i6 ... . .g ,

l

)

In c ht i on Rsdi n t i on Hen d i_nf, InuP Evaporat or (under botton)

Evaporator (::untact outside upper level) 120 nrem/h r beta-garna Drun Storage Area (at HRA fence) 20 mram/hr beta-gae.a 2.5 mram/hr beta-ganma Pdero11nnnous lhiste Shipaent to N.E.C., at contact with sides of vehicle At 6 feet from sides 200 mrea/hr beta-gtmi 10 mrem /hr beta-ctnma Contanination surveying consisted of routine plant site surveys, surveys of materials shipped, tools, equipaent and C.V. during shutdown. The cican areas were wi thin the " Clean Area" limits. The controlled arcao were generally within the

" Clean Area" linito. The controlled area was cicaned frequently to keep and/or to return it to the " Clean Area" limits.

to r.ininite the anount of emeurabic contanination.The exclusion The following areas were cleaned contaninution levels periodienlly were observed:

.cention Contanination Reading, CM Nilding .,3 Charging Pump Chamber Chcrging Pump Chanber $92000 d/m/emear beta-gamma Charging Room Floor 100 d/n/runear alpha Saaple Roam Sink $*:i60 d/m/encar bett-gamtaa Sample Room Sink 1820 d/m/ smear beta-gamma Sanple Room Floor 100 d/m/emear alpha Uncnien1 lab Hot Sink 537 d/m/ smear beta-ga:ma Chenical lab hot Sink 12150 d/m/ smear beta-gamma 100 d/m/ smear alpha H'. .'D F ik.p Ro'r: Floor Shipping Roam Floor 11830 d/m/emear beta-gama 113S d/m/snear beta-ga:na Liquid and gaseous effluente from the SNEC site for the month of September 1966 were as follous:

(Curie) (Curie) (Curic)

Effluent Activity Tyne This Month Activity Activity Year to Date last Twelve Months Tritium 2.957817 15.617083 21 524530 Liquid 0.001005 0.010419 0.012636 Air, Xe 11.743709 94.236451 Air, I-131 94.821971 0.054501 0.104045 Air, M.P.P. 0.110010 O.117437 0.942364 0.948219 s

=

Sf1EO Operations Report for September 1966 . . . < i/4 Seven (7) barrels of waste were drummed for tmporary storage. Forty-five (45*) drums were shipped frot. the site.

Radiation exposure for all St.'EC personnel as measured by film badges for the month of AuCust 1966 were a maximum of 950 mran with an average of 87 7 mrm.

Radiation exposure for all visiting personnel as measured by film badges for the month of August 1966 were a maximum of 0 mrm with an average of 0 nrem.

The average radiation exposure for all personnel as measured by film badges for the month of August 3966 was 46.3 mrem.

  • Includes 22 drums of Westinghouse waste i

b D

SAXTG1 NUCLEAR EXPERIMENTAL CORPORATION OPERATIN3 STATISTICS l

MONTH , SEPTS:BER YEAR .1966 NUCIZAR UNIT MONTH YFAR 10 DATE TIMES CRITICAL NO. ' 21 476 HOURS CRITICAL MRS. 720 4,959.48 17,840.61 TIMES SCRAMMED (MA! CAL) NO. 0 20 282

  • TDES QCRAMMED (INADVERTANT) NO. 0 1 30 THERMAL POWER GENERATION MWH 16,672.48 108,298.62 3'7,548.44 AVEPAGE WRNUP (Pu Region) MWD /MTU 1,377.25 8,840 99 8,901.81 CONTROL R0D PCSITIONS AT DID OF MONTH AT ElUILIBRIUM POWER OF 23.5 MWt MAIN C001 ANT BORON 711 PPM R'DS OUT - INCHES NJ. 1 40 NO. 2 18.9 NO. 3 40 ,

NO. 4 40 NO. 5 40 NO. 6 40 ELECTRICAL UNIT MONTH YEAR TO DATE GROSS GENERATION MWH 3,022.00 18,974.00 53,a E 00 STATION SERVICE MWH 241.69 1,947 96 10,150.25 STATION SERVICE  % 8.00 10.27 19.06 AVG. PIANT EFFICIENCY - MWH(e)/MWH(t) $ 17.91 17.53 16.77 AVG. GENERATION RUNNING ( 720 HRS) }M L,197.22 3,977.78 3,292.80 PLANT LOAD FACTOR -

(AVG. GEN. F0h MONTH / MAX. IDAD)  % 94 U 64.93 30.50 AUXILIARY STEAM SUPPLY - NUCLFAR STEAM SUPPIIED E REACTOR MF3. 720.00 4,818.28 14,517.25 RWDF EVAPORATOR OPERATION HRS. 362.06 1,523.58 3,584 83

  • RDMRES :

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