ML20085H559

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Monthly Operating Rept for Dec 1969 for Saxton Nuclear Experimental Corp
ML20085H559
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 12/31/1969
From:
SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110280310
Download: ML20085H559 (8)
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SAXTOS NUCLEAR EXPERIMENTA1 CORPORATION 4

Operations Report for December 1969 1.

GENFRAL i

At the beginning of this report period the reactor was in a hot shutdown condition. On December 1, the automatic transfer of the SNEC alternate power supply was functionally tested under load conditions by de-energizing'the 13.8 KV' ~ ' ~ ~ "~

bus 1B.

~~

On Dect 10, SNEC received AEC authorization for power operation to 28 MWt with Core 1.1.

2.

REAC10R OPFRATIONS On December 11, the reactor was taken critical and the power increased to 7 MW:. The reactor was shutdown due to lack of indication on nuclear instrumentation power range channel B.

The cables and watertight can were replaced on power range channel B.

The intermediate range channels A and B and power range C detectors were repositioned to optimize the sensitivity.

On December 12, the reactor was again taken critical and the power increased to 12 MWt for low power physics measurements.

On December 15, reactor powcr was increased to 18 IMt over a six hour period. - On December 16, the reactor power was reduced to'10 MWt as part of the low power physics procedure.

The reactor was shutdown on December 17 due to leakage from the primary system.

The containuent vessel was inspected and power range channel B was again repositioned to increase j

sensitivity and powet range C detector was replaced.

Primary system leakage was stopped by tightening the vent and drain valves on the primary loop.

The reactor was taken critical and on December 18, reactor power was increased to 18 MWt.

Po er operating physics measurements were made during the remainder of the__ month.

The secondary system chemistry was troubled with high chlorides. The No. 2 condenser tubes were checked for leakage by splitting the condenser and approximately fif ty tubes were plugged.

At the end of this period the North side-of the condenser was still out of service due to excessive tube leakage.

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3.

EXPERIMENTAL PROGM.M At power physics parameters for Core III were measured during the month.

Preliminary results are as follows:

-1.2x10jf,Ak/k/Fc744ppmBoron

~

Temperature Coefficient:

-1.79x10 ' tk/k/ F at 540 ppm Baron i

~0 Pressure Coefficient: +1.4x10 Ak/k/ psi,at 485 F_

i Power Coefficient:

- 3.1x10-4 Ak/k/MWt at 22 MWt

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-5.3x10-4 Ak/k/MWt at 10 MWt 9110280310 910424 PDR FOIA 1

DEKOK91-17 PDR j

SNEC Operations Report for December 1969.

  1. 2 Xenon Worth:

.017 ok/k 0 to 11 FNt

.007 ok/k 7 to 19 MWt

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Boron Worth:

1x10 Ak/k/ ppm at 600 ppm Boron Rod 2 Worth:

.031 Ak/k The above parameters are subject to refinement during operation of Core III.

The peak line,ar power densities measured were as follows:

18.35 kw/ft Loose Lettice Fuel Load Follow Fuel

- 16.41 kw/ft i

4.

OPERATIONAL iESTS The SNEC fire and evacuation alarns were tested satisfactorily on December 5,12,19 and 26.

The monthly test of the safety injectioa and recirculation system was conducted on December 16.

1 The monthl.y test of the radiation monitoring system was conducted on December 6.

The annual reactor plant alternate, power supply aut'omatic transfer test i

was conducted on December 1.

The monthly calibration of the steam generator blowdown monitor was conducted on December 16.

5.

MAINTENANCE The principal items of mechanical maintenance during the month included replacing a rupture disc on the: containment vessel discharge tank; installing a new section of pipe in the steam heating condensate line in the RWDF; replacing.a rubber diaphragm on the RWDF number two gas compressor regulating valve; repairing the float valve on the RWDF number one gas compressor separator; installing new pre-filters on the RWDF air handler; fabricating a portable lead shield for the Co-60 source; replacing the check valve on the-control and auxiliary building sump' pump discharge line; installing a new diaphragm in 'the neutralized waste tank drain valve; checking the number two condenser tubes and plugging approximately 50 tubes; stroking the letdown stop valve, MIC-23V; flushing the boiler feed pump power. water coolers and replacing the gaskets; and draining four drums of evaporator bottoms for processing.

l 1

SNEC Operations Report for December 1969

  1. 3 The major items of elect rical and instrument maintenance included a functional test of the alternate power supply under load conditions; replacing vacuum tubes in the chemical laboratory pH meter; replacing vacuun tubes in the count room alpha scaler; replacing the meter relay on the number six control rod position indicator circuit; installing new detector cables and a watertight can in power range channel B; installing a new UIC detector in power range channel C; replacing a defective wire in the number two generator OCB closing circuit; installing new heating tapes and insulation on the safety injection system d/p cell instrument lines; overhauling the current to air converter and pneumatic drive on the pressurizer group three heater control auto transformer; installing a new motor in the RWDF evaporator room air mixing f an; installing new gears in the southeast anemometer station recorder; installing vanes in the RWDF alpha monitor pump-overhauling the charging pump pneumatic speed control units; replacing the m.ccoid switch in the RWDF evaporator steam control circuit; replacing the temperature compensator in the water treatment condensate conductivity sample cell; replacing vacuum tubes in the charging room monitor, RIA-2; and replacing the pressure switch on the site particulate monitor, RIC-8.

6.

CHEMISTRY The primary system was in a hot shutdown at the beginning of the month.

On December 8, the lithium concentration was increased to 0.54 ppm in t ep ration for power operation., Hydrogen overpressure was added to the purificatio.-

urge tank on December 11.

On December 25, the primary coolant activity took a step increas-and continued to increase slowly during the remainder of the month.

Seven hydcogen analyses were ma'de during the month.

A summary of the analyses performed on main coolant samples taken during the month is contained in the following table:

Main Coolant System Minimum Maximum pH at 25 C 6.08 6.80 Conductivity, umhos 10.20 22.4 Boron, ppm 632 766 Chlorides, ppm

<0.005

<0.005 0xygen, ppm

<0.005

<0.005 Hydrogen, cc/kg H O at STP 9

24 2

Cross Beta-Gamma (15 Fun. Degassed) ue/cc 4.54x10,2 6.61 -

Tritium, ue/cc 1.22x10,3 6.41x10,2 y

y 1-131, ue/cc 7.43x10 9.97x10 I-133, uc/cc 1.15 1.41 Lithium, ppm 0.46 0.54 Total Primary Coolant Activity, uc/cc 8.15 l

l

SNEC Ope' 'lons Report fo.

December 1369.

  1. 4 Except for brief periods, the steam generator chloride concentrations were maintained below 0.3 ppm.

The activity in the steam generator was less than 1x10-0 ue/cc during the month.

A summary of the analysis on the component cooling water is as follows:

pH Conductivity Cr04-ppm Activity, uc/cc

-5 9.01 774 310 3.26x10 7.

RADIATION AND WASTE DISPOSAL Radiation surveying consisted of routine plant surveys, C.V. during shutdown and materials shipments. The following maximum radiation readings were taken:

~

~

Location Radiation Reading C&A Building Waste Drum (baling machine) 0.8 mrem /hr beta-gamma Charging Pump (contact with chamber) 20 mrem /hr beta-gamma Sample Rbom (door of sample panel) 18.0 mrem /hr b.ta-gamma Chemical Lab Hot Si'nk (l" from drain) 4.5 mrem /hr beta-gaena RWDF Evap' orator (under bottom) 45 mrem /hr beta-gamma Evaporator (contact outside upper level) 10 mrem /hr beta-gamma Drum Storage Area (at HRA fence) 0.75 mram/hr beta-gamma C.V.

Primary Compartment (general upper level) 75 mrem /hr beta-gamma Primary Compartment (contact M.C. pump volute) 375 mrem /hr beta-gamma Primary Compartment (S.G. bottom) 175 mrem /hr beta-gamma Primary Compartment (Pressurizer bottom) 110 mrem /hr beta-gamma Primary Compartment (general lower level) 85 mrem /hr beta-gamma Primary Compartment (Regen. HX) 310 mrem /hr beta-gamma Primary _ Compartment (Non-Regen. HX) '

35 mrem /br beta-gamma Auxiliary Equipment Compartment (S.C.H.X.)

11 mrem /hr beta-gamma Auxiliary Equipment Compartment (D.T. top)

B mrem /hr beta-gamma Auxiliary Equipment Compartaent (D.T. bottom) 43 mrem /hr beta-gamma Auxiliary Equipment Compartment (general lower l

level) 2.5 mrem /hr beta-gamma Reactor. Deck (water level at grating) 40 mrem /hr beta-gamma l

Reactor Deck (instrument ports) 260 mrem /hr beta-gamma l

Reactor Deck'(waist level) 50 mrem /hr beta-gamma l

Reactor Deck (storage well railing) 45 mrem /hr beta-gamma J

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_ _ _, ~.,

SNEC Operations Report for December 1969.

. #5 Contamination surveying consisted of routine plant site surveys, surveys of materials shipped, tools, equipment and C.V. during shutdown. The clean areas were within the " Clean Area" limits. The controlled area was generally within the

" Clean Area" limits.

The controlled aret was cleaned frequently to keep and/or to return it to the " Clean Area" limits. The exclusion areas were cleaned periodically to minimize the amount of smoarable contamination. The following cont.anination. levels were observed:

Location Contamination Reading C&A Building I

Charging Pump Chamber 272000 d/m/ smear beta-gamma Charging Pump Chamber

<10 d/m/ smear alpha Charging Room Floor 450 d/m/ smear beta-gamma Sample Room Sink 185000 d/m/ smear beta-gamma Sample Room Sink

<10 d/m/ smear alpha Sample Room Floor 9450 d/m/ smear beta-gamma Chemical Lab Hot Sink 324000 d/m/ smear beta-gamma Chemical Lab Hot Sink

<10 d/m/ smear alpha

,RWDF Pump Room' Floor 375 d/m/ smear beta-gamma Shipping Room Floor

<100 d/m/ smear beta-gamma p.V.

'verating Deck 4750 d/m/ smear beta-gamma 0 trating-Deck

<10 d/m/ smear alpha Primary Compartment (grating) 62500 d/m/ smear beta-gamma Primary Compartment (grating)

<10 d/m/ smear-alpha Liquid and gaseous effluents from the SNEC site for the month of December, 1969, were as follows:

(Curie)

(Curie)

.(Curie)

Effluent Activity Activity Activity Type This Month _

-Year to Date Last Twelve Months Liquid 0.000467 0.010135 0.010135 Tritium 0.037083 0.937433 0.937433 Air, Xe 0.745670-1.244125 1.244125 Air, 1-131 0.000021 0.000021 0.000021 Air, M.F.P.

0.007456 0.012441 0.012441

SNEC Operations Report for December 1969.

  1. 6 No bart als of waste were drucued for temporary storage.

No drums were i

shipped from the site.

Radiation exposure for all SNEC personnel as measured by film badges for the month of November 1969 were a maximum of 1300 mrem with an average of 153.6 mrem.

g Radiation expos ure for all visiting personnel as measured by film badges for the month of November 1969 vere a maximum of 15 mrem with an average of 9.1 mrem.

The average radiation exposure for all personnel as measured by film badges for the month of November 1969 was 134.0 mrem.

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SAXTON NUCLEAR EXPERIMENTAL CORPORATION O_PERATING STATISTICS MONTl!

DECEMBER YEAR 1969 NUCLEAR UNIT MCNTH YEAR TO DATE TIMES CRITICAL NO.

3 364 1,187 Il0URS CRITICAL HRS.

453.26 671.51 23,620.00 TIMES SCRAFDIED (MANUAL)

No.

2 118 567

  • TIMES SCRAFDIED (INADVERTANT)

No.

0 4

46 I

THERMAL POWER GENERAT!ON hWil 7,379.88 7,379.88 436,457.41 i

AVERAGE BURNUP

}MD/MTF 437.70 437.70 10,396.90 Fu Loose Lattice Region MWD /KrF 1,394.80 1,394.80 18,343.80 U Load Follow Region

}MD/MTF 833.93 833.93 833.93 U Peripheral Region MWD /MTF 180.07 180.07 9,561.20 CONTROL ROD POSITIONS AT END OF MONTH AT EQUILIBRIUM POWER OF 18.5

}Nt MAIN COOLANT BORON 730 PPM RODS OUT - INCHES NO. 1 40 po, 2 13 No. 3 40 NO. 4 40 NO. 5 40 No. 6 40 ELECTRICAL GROSS GENERATIQN mm 1,006 1,006 74,535.3 STATION SERVICE MWH 350.93 2,127.20 17,300.60 STATION SEPVICE 34.88 ell.45 23.21 AVG. PLANT EFFICIENCY - EM(e)/}MH(t) 13.63 13.63 17.08 A*JG. GENERATION RUNNING ( 451.0551RS)

KW 2,230.35 2,230.35 3,500.93 PIEiT LOAD FACTOR -

(AVG. GEN. FOR MONTH / MAX. LOAD) 45.67 3.88 17.49 AUXILIARY STEAM SUPPLY - NUCLEAR STEAM SUPPLIED BY REACT 0E HRS.

433.3 433.3 19,693.04 RWDF EVAPORATOR OPERATICN HRS.

186.95 2,179.63 9,594.49

  • REMARRS:

Correct the Novereber 1969 Operating Statis a report as indicated below:

Change " Average Burnup" under the "To Date" column to read 9,959.2.

Delete the first sentence under " Remarks" and insert "The Core III BOL Burnup is listed opposite " Average Burnup"~under the "To Date" column."

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