ML20244B881
| ML20244B881 | |
| Person / Time | |
|---|---|
| Site: | Neely Research Reactor |
| Issue date: | 05/03/1989 |
| From: | Karam R Neely Research Reactor, ATLANTA, GA |
| To: | Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20244B873 | List: |
| References | |
| NUDOCS 8906140021 | |
| Download: ML20244B881 (5) | |
Text
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ENCLOSURE 3 g g jggg f'
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Georgia Institute of Technology f[f 3
IN NEELY NUCLEAR RESEARCH CENTER (4
y 900 ATLANTIC DAIVE
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ATLANTA GEORGIA 30332-0425 May 3, 1989 Mr. Thomas A. Peebles, Chief Operations Branch Division of Reactor Safety U.S. Nuclear Regulatory Commission, Region II 101 Marietta Street, NW Atlanta, Georgia 30323 1
Dear Mr. Peebles:
With regard to the written RO Examination given Thursday April 27, 1989, I wish to make the following comments / requests:
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1
- 1. Question B-12:
" State the reason the D, O purifications I
system is connected. to the Da O overflow return system."
Answer: "Uses the developed J
head of the overflow return pumps as the 1
driving force.for the purification system I
flow."
I admit that the answer you chose for this question is taken from the SAR Sec.
4.4.9.2.
I also submit that the SAR answer l
is wrong and ambiguous.
Please refer to Fig 4.24 in SAR (A copy is enclosed).
The red line is add for ease of identifying the appropriate section.
Note that there is no head developed by the overflow.
There are however two pumps, MD3 and MD4 for taking by suction DaO-from' storage tank T-D1 through the purification system.
The output of purification system is connected to the input of the circulating pumps, MD1 and MD2.
The l
SAR words, " overflow return pumps" refer to l
the main circulating pumps.
This description is inaccurate and not in use.
The coolant outlet from reactor tank is certainly not an overflow as can be seen in SAR Figure 4.24 and the head developed between main coolant outlet and the point where purification system output is introduced, is working against the purification system pumps.
Consequently question B-12 should be deleted.
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l A Unit of the University System of Georg.a An Equal Education and Employment Opportunity institution l
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L 2.
-Question C-5 (b).
" Reactor operation is set at. 2'MW with equilibrium conditions established-when instrument supplying the reference power.
to the automatic control system-fails low".
Answers Reg rod will not move.
(.5) Automatic switch of the proper control system to manual due to > 10% set point to reactor power deviation.
Comment:
It-is possible for the instruments to fail in such a way that the. difference between the set point - and indicated position is within the 10%
allowed.
deviation; hence-the. system will not return to manual.
This in fact happened two years ago when the signal _to reg rod from chart recorder died.
This caused reg rod to move out and the power to increase-by almost a.
factor of 10.
Since the question was not specific
- enough, it is-recommended that either the question not be counted or that answers which correctly described the motion be given credit.
3.
Question E-3.
"Which one of the following practices is not one of the accepted methods of monitoring for proper. emergency cooling system flow?
~
Answer a.
Observation of a-slight temperature difference approximately 2-3 degrees between coolant exit area thermocouple and ambient coolant temperatures after system actuat ion. "
Comment:
The listed references for this question are SAR Page 81 and GTRR procedure 7211.
Neither reference specifies what the /iT should be.
It is stated however in the SAR that "these thermocouple will be used to sense the presence of emergency coolant at a
temperature significantly different from ambient."
This statement is correct provided that the reactor has been operating at high power for some time.
The statement is incorrect for our current mode of reactor operation ----
intermittent and low power.
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Additionally, our policy for all' staff' is j'"
contrary'to response'"C" -
"looking directly-I into.the.open port".
This is not allowed.
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..is possible that response "a" could be Tone'of the.
Therefore it accepted: methods of monitoring proper emergency. cooling flow' andL I
tit 11s definitely " improper" for any one torlook directly into open. beam ports.
Consequent I feel that we have a problem with' question E-3.-
I-respectfully' request -that this question ~ be removed.from the examination.
g 5.-
Other comments on specific questions follows-F-6: Duties.of Reactor Operators do not include notification requirements..
Emergency Director 'is the.only person who may initiate notification (Procedure 6100).
.A-8: '.The answer-given is contrary to our training.
Spontaneous fission neutrons in a highly enriched care
'and' cosmic' ray are not enough to start the reactor.
The-material in Training Manual does not' apply.
In fact itJis unsafe!!
D-1: TheJatatement.of the problem is not concise.
Entry to the pipe tunnel is'through the process room.
If NRC wanted.to know how many doors are there to~the process room the question should have been'so stated.
The -above are some. of my comments on the April 27, 1989 RO Examination.
I will appreciate your careful consideration of these comments.
Sincerely,
/0# (OJLo~v-R.A. Karam, Director Neely Nuclear Research Center RAK gef 3
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