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<title type="245">Study of Incident Involving Fuel Leak in North Carolina State College Reactor</title>
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<author>Mann, Marvin M.</author>
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<p n="public">URL: http://www.lib.ncsu.edu/archives/etext</p>
<p>copyright 2000, by North Carolina State University</p>
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<date>August 28, 1955</date>
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<title>Study of Incident Involving Fuel Leak in North Carolina State College Reactor</title>
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<front>
<div1 type="summary" n="1">
<head rend="center">Study of Incident Involving Fuel Leak in North Carolina State College Reactor</head>
<p></p>
</div1>
</front>

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<body>
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<div1 type="report" n="1">
<head></head>


<p><name type="person">Curtis A Nelson</name>, Director, Division of <lb/>
Inspection</p>

<p><name type="person">Marvin M. Mann</name>, Assistant Director for compliance</p>

<p><title>STUDY OF INCIDENT INVOLVING FUEL LEAK IN <name type="corporate">NORTH CAROLINA <lb/>
STATE COLLEGE</name> REACTOR</title></p>

<p>SYMBOL:INS:MMM</p>

<p>I spent the day with <name type="person">Dr. C. K. Beck</name> in <name type="place">Raleigh</name> on <date value="1955-06-16">June 16, 1955</date>. <lb/>
As you know, <name type="person">Herman Roth</name> of <name type="place">Oak Ridge</name> had reported to us that the <lb/>
core of the <name type="place">Raleigh</name> reactor had developed a moderate leak; and that <lb/>
it was estimated at the time that about 100 cc's of fuel solution <lb/>
had made its way out of the core. After I had a short talk with <lb/>
<name type="person">Dr. Beck</name>, he took me over the reactor installation. We then spent <lb/>
the rest of the day (with the staff) constructing as best we could the <lb/>
chronological history of the incident, which follows:</p>

<p><date value="1955-05-06">May  6, 1955</date>:	On this date, <name type="person">Dr. Beck</name> himself operated the reactor <lb/>	
for several hours at a power of approximately 6 <lb/>	
kilowatts. This is the last date on which the<lb/>
reactor was operated at power.</p>

<p><date value="1955-05-06">May 9, 1955</date>:	It was noted that the pressure in the core had in- 
<lb/>creased over the weekend. Normal pressure was said 
<lb/>to be between 5 and 15 inches of water below atmos- 
<lb/>pheric pressure. In this occasion there was no 
<lb/>apparent reason for the pressure increase, so investi- 
<lb/>gation was begun. The core pressure was returned to 
<lb/>normal, that is, approximately 15 inches below atmos- 
<lb/>pheric pressure and on subsequent readings during the 
<lb/>day it was observed to rise slowly.</p>

<p><date value="1955-05-10">May 10, 1955</date>:	Pressure had returned to atmospheric by morning <lb/>
	Samples were taken from the gas in the aluminum <lb/>
	envelope that surrounds the stainless steel core and <lb/>
	evidence of fission products was found. Subsequently, <lb/>
	it was determined that the primary activity was <lb/>
	Xe-133 and its magnitude was estimated at one microcurie <lb/>
	per cc. It was presumed then that fission product gases <lb/>
	were leaking from the gas recombination system, there <lb/>
	being no evidence that liquid had leaked out of the <lb/>
	core vessel. Note: There is a small wire suspended <lb/>
	between the core and the aluminum envelope very near <lb/>
	the bottom of the two containers. When liquid enters <lb/>
	this space then the resistance to ground from this wire <lb/>
	drops off sharply.</p>

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<p> 
During the next few days confirmatory tests were  <lb/>
made of the activity and its magnitude. A detailed  <lb/>
procedure was formulated for disposal of the radio- <lb/>
active gas. During all this time the core was at  <lb/>
atmospheric pressure.</p>

<p><date value="1955-05-20">May 20, 1955</date>:	Execution of the procedure just referred to was begun  <lb/>
and consisted of the following: --- Gas from both the  <lb/>
envelope and the core was bled slowly to the main  <lb/>
exhaust stack for the reactor building. Normal flow <lb/>
to the stack is 20,000 cfm and the magnitude of the  <lb/>
active gas flow was controlled in such a way as to  <lb/>
maintain activity of the stack effluent at less than  <lb/>
10<hi rend="sup">-9</hi> microcuries per cc. This rate was based on the  <lb/>
conservative assumption that all the activity was from  <lb/>
iodine 131, although it had been shown earlier that the  <lb/>
ratio of Xe-133 to iodine 131 was greater than 1000.</p>

<p><date value="1955-05-28">May 28, 1955</date>:	A slight increase in the gamma activity of the cooling  <lb/>
water was noted. This is water that flows through coils  <lb/>
of 1/4" stainless steel tubing in the core. This is a  <lb/>
"once through" cooling system but there had been no  <lb/>
actual flow for some days. The activity noted was that  <lb/>
from a sample taken from a hold up tank, which is about  <lb/>
60 feet from the reactor. The next step was to insti-  <lb/>
tute flow for a sufficient time to obtain a sample which  <lb/>
had actually come from the reactor core.  It was found  <lb/>
that activity of this sample was about 25 times geater  <lb/>
than that of the first. The cooling coils were then  <lb/>
put under pressure of a  approximately 55 pounds and the  <lb/>
system was closed off.  However, no appreciablc drop in  <lb/>
pressure occurred over a period of several hours and it  <lb/>
was concluded that although a leak apparently existed in  <lb/>
the cooling coils, it must be rather small.</p>

<p><date value="1955-05-31">May 31, 1955</date>:	The presence of uranium in the cooling water samples  <lb/>
taken late in the evening of May 28 was established by  <lb/>
alpha counts.</p>

<p><date value="1955-06-02">June 2, 1955</date>: 	It appeared on this date that the purge was essentially  <lb/>
complete, that is, the activity of the stack effluent  <lb/>
was now approximately that of normal background.  However,  <lb/>
purging continued and is still going on.</p>

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<p>
<date value="1955-06-03">June 3, 1955</date>:	On this day, <name type="person">Dr. Beck</name> decided to execute a criticality  <lb/>
test as a check, via critical rod position, on both  <lb/>
earlier and current measurements which indicated that  <lb/>
the liquid level in the core had not changed. The  <lb/>
critical rod position was found to be normal within  <lb/>
limits of reasonable error.</p>

<p><date value="1955-06-06">June 6, 1955</date>:	It was found that the "wet wire monitor" mentioned <lb/>
	in the May 10th note, indicated the presence of liquid <lb/>
	outisde the core, that is, between the core and the <lb/>
	envelope. The liquid level was checked and found to be <lb/>
	low by about 4 millimeters, indicating leakage of <lb/>
	approximately 250 cc's of fuel solution into the envelope. <lb/>
	Samples of cooling water showed somewhat greater activity <lb/>
	than on <date value="1955-05-28">May 28th</date>. It was then decided that the situation <lb/>
	was serious enough to warrant transfer of the fuel solu- <lb/>
	tion to storage containers which had been placed in a <lb/>
	room below the reactor for this purpose. This was done <lb/>
	on <date value="1955-06-07">June 7</date>.</p>

<p>Between <date value="1955-06-07">June 7</date> and <date value="1955-06-10">June 10</date>, that portion of the concrete  <lb/>
shield immediately above the core and plenum was removed  <lb/>
and the shim rods and control rod drives and supports  <lb/>
were taken out so as to yield access to the reactor core.  <lb/>
Incidentally,  the tips of the shim rods, which in shut down  <lb/>
condition reside in the narrow space between core and  <lb/>
envelope are covered with a thin deposit which is quite  <lb/>
active.</p>

<p>On <date value="1955-06-10">June 10</date>,  the cooling coils were drained and analysis  <lb/>
of samples resulted in Wentification of a number of  <lb/>
fission products. It would appear that, in truth, at  <lb/>
least two leaks developed in this reactor system; one  <lb/>
in the cooling system, and the other in the stainless  <lb/>
steel core. On the basis of experience, one might feel  <lb/>
inclined to blame the leaks on faulty welds, although it  <lb/>
has been shown that a water solution of uranium sulphate  <lb/>
can actually corrode through stainless steel plate at  <lb/>
points of local surface imperfection.</p>

<p>My own view of this situation is that the safest, and indeed very probably  <lb/>
the cheapest remedy is that of complete  replacement of the core assembly.  <lb/>
At the same time, I think that a unique opportunity exists to learn from  <lb/>
this incident  and I would therefore recommend that careful and thorough  <lb/>
disassembly of this reactor core be made in some location, probably  <lb/>
0ak Ridge where adequate  facilities exist, for handling and study of <lb/>
highly radioactive equipment. </p>


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<p>
The other problem of the moment is that of formulating  a safe and  <lb/>
adequate procedure for removal of the reactor core, recovery of what  <lb/>
liquid has leaked into the envelope, and shipment to the point of  <lb/>
disassembly and study, I suggested to <name type="person">Dr. Beck</name>, that if he were  <lb/>
interested in calling on the experience of <name type="place">Chalk River</name> personnel in  <lb/>
this regard that I will be glad to arrange contact for him.</p>

<p><name type="person">Dr. Beck</name> has already  been in contact with  <name type="corporate">Babcock   and Wilcox</name>  and with <lb/>
<name type="corporate">North American Aviation</name> in regard to construction of a new core <lb/>
assembly and I believe he has also requested <name type="corporate">Oak Ridge</name> to consider <lb/>
building a replacement.   I think he is wise to look into the  possibility <lb/>
of a commercial supplier  for this  assembly, and at first glance it would  <lb/>
appear that both <name type="corporate">Babcock and Wilcox</name> and  <name type="corporate">North American  Aviation</name> are <lb/>
excellent choices. Personally, I think that <name type="corporate">North American</name> is parti-  <lb/>
cularly apt in view of their past and current experience  with water  <lb/>
boiler reactors.</p>

<p><name type="person">Dr. Beck</name> is writing detailed report of this incident to be sent <lb/>
to <name type="person">Dr. Roth</name>, and his agreed  to send us a copy</p>

<p>cc:	<name type="person">Dr. C. K. Beck</name> <lb/>
	<name type="corporate">N. C. State College</name> <lb/>
	<name type="place">Raleigh,  N. C.</name> </p>

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