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ORNL-4191 - the Molten Salt Energy Technologies Web Site

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personnel access to <strong>the</strong> area where <strong>the</strong> filter is<br />

located. By <strong>the</strong> end of run 11 (May 1967) <strong>the</strong><br />

filter was plugged again, and periodic venting of<br />

<strong>the</strong> coolant system through an auxiliary line<br />

(L-536) was required to keep <strong>the</strong> loop overpressure<br />

below 10 psig.<br />

During <strong>the</strong> shutdown between runs 11 and 12,<br />

<strong>the</strong> filter was replaced again, and a minor piping<br />

modification was made to permit <strong>the</strong> coolant off-<br />

gas activity monitoring to monitor gas vented<br />

through line 536. Be€ore this change, any activity<br />

release would have been detected and stopped by<br />

ano<strong>the</strong>r monitor on <strong>the</strong> combined fuel and coolant<br />

off-gas, but identification of <strong>the</strong> source of <strong>the</strong><br />

activity would have been more difficult. No<br />

activity has ever been detected in <strong>the</strong> coolant<br />

off -gas.<br />

Cooling Water Systems<br />

A. 1. Krakoviak<br />

The cooling water systems performed satishctorily<br />

during this report period. The systems<br />

functioned relatively trouble free except for a<br />

few Leaks. In July a 15-gpd leak from <strong>the</strong> treated<br />

water system was detected and was traced to a<br />

faulty pressure-relief valve in <strong>the</strong> line leading to<br />

one of <strong>the</strong> reactor cell coolers. Replacement of<br />

<strong>the</strong> farilty relief valve restored <strong>the</strong> system to<br />

normal oper- ‘i t. Ion.<br />

Space Coolers. - As reported previ~usly,~ leaks<br />

have occurred in <strong>the</strong> reactor cell space coolers<br />

at <strong>the</strong> brazed joints on <strong>the</strong> brass tubing headers.<br />

During <strong>the</strong> scheduled shutdown at <strong>the</strong> end of run<br />

11, both space coolers were leak-tested. One<br />

cooler (KCC-1) leaked less than 125 cm3/day<br />

and was not replaced; however, <strong>the</strong> o<strong>the</strong>r (RCC-2),<br />

which leaked at <strong>the</strong> rate of 9 Iiters/day, was replaced<br />

with a cooler whose headers and nipples<br />

were fabricated of copper. Copper weldments<br />

were used on <strong>the</strong> new cooler instead of <strong>the</strong> brazed<br />

joints .<br />

Radiation levels around <strong>the</strong> removed unit were<br />

sufficiently low that it could be disassembled<br />

directly. The radiator was <strong>the</strong> most radioactive<br />

component, with readings up to 1000 rniIlirerns/hr<br />

at contact. (The radiation was very soft and<br />

caused no contamination problem.) This unit was<br />

discarded. However, <strong>the</strong> fan motor was retained<br />

71bid., p. 32.<br />

for possible future use, and <strong>the</strong> new fan, motor,<br />

and radiator were mounted on <strong>the</strong> original frame<br />

for installation in <strong>the</strong> cell.<br />

Reactor Cell Annulus. -- Sometime prior to or<br />

during run 11, <strong>the</strong> fill line to <strong>the</strong> biological shield<br />

plugged, and water additions to <strong>the</strong> reactor cell<br />

annulus were made through <strong>the</strong> level measuring<br />

line. Since <strong>the</strong> plug in <strong>the</strong> fill line could not he<br />

cleared, <strong>the</strong> overflow pipe from <strong>the</strong> cell arinulus<br />

was modified to also serve as a fill line.<br />

Steam Dome Feedwater Tanks. - Water is dumped<br />

automatically from a feedwater tank (FWT) to a<br />

steaiii dome if cooling of a fuel drain tartk (FD)<br />

is required aftet a fuel drain. During run 12, sr!iall<br />

amounts of water Erom FWT-1 had randomly appeared<br />

in <strong>the</strong> steam dome of FD-1, causing a temperature<br />

decrease in <strong>the</strong> fuel drain tank. To ensure<br />

that this drain tank remained available for a<br />

possible emergency drain, <strong>the</strong> water was removed<br />

from <strong>the</strong> feedwater tank, which is now in normal<br />

service after having a faulty temperature switch<br />

replaced.<br />

Component Cooling System<br />

P. 11. Ilerley<br />

Although some difficulties were encountered,<br />

<strong>the</strong> component cooling system operated satis-<br />

factorily during this report period. The two main<br />

blowers (CCP-1 and CCP-2) operated 1536 and<br />

2375 hr tespectively; CCP-2 has operated for a<br />

total of 3340 hr without a failure.<br />

The discharge check valve on CCP-2 was re-<br />

placed and <strong>the</strong> belt drive was tightened as part<br />

of <strong>the</strong> prevenf.ive maintenance program. There was<br />

no indication o€ any significant aging of <strong>the</strong> sili-<br />

cone rubber in <strong>the</strong> removed check valve.<br />

Trouble was encountered in <strong>the</strong> CCP-1 oil cir-<br />

culating system. First, a loose tubing connection<br />

caused <strong>the</strong> loss of ‘\2 gal of oil during run 12;<br />

this irregularity was easily repaired. Then, Fol-<br />

lowing <strong>the</strong> run 12 shutdown, intermittent law-oil-<br />

pressure alarms again occurred. An investigation<br />

indicated no significant 10s:; of oil, but a slow oil-<br />

pressure response was observed when <strong>the</strong> blower<br />

was started. The suspected oil pump and pressure-<br />

relief valve on CCP-1 were replaced with spare<br />

units to correct <strong>the</strong> trouble. The removed pressure-<br />

relief valve was found to be re1 ieving before <strong>the</strong><br />

normal oil pressure developed. In spite of <strong>the</strong>se

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