ML20059G126
| ML20059G126 | |
| Person / Time | |
|---|---|
| Site: | University of Iowa |
| Issue date: | 08/31/1990 |
| From: | Jordan M, Hironori Peterson, Wetzel B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20059G106 | List: |
| References | |
| 50-116-OL-90-01, 50-116-OL-90-1, NUDOCS 9009120138 | |
| Download: ML20059G126 (4) | |
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NUCLEAR REGULATOPU COMMISSIONL REGION 1II.
-R'eport No.: 50-116/0L-90-31' Docket No. 50-116.
License No._Ra59; Licensee: JLlowa State'Un.iversityl Nuclear Engiaeering'. Department' Research Nuclear Reactor 261 Sweeney Hall l
Ames',tlAL50011' p
Facility Name:
Iowa State Universitys Examination Administered Att Ames, IA Examination Conducted:- l July 19 and '20',1990.
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HQS Examiner, fp d
P.s /- 90 B. _ kTetzel V
Date i
Chief Examine 4//hN J/-76'
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' N. Wettir' son' Date
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Approved By:
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M.. J./@rdan, Chief Date Operft6r Licensing Section #1 Examination Summary Examination administered on July 19 and 20,1990 (Report N). 50-116/0L-90-01)
Operator licensing examinations were administered to two Senior Reactor 0perator (SR0) candidates, one SR0 instant.and one SR0'upgride. Only one.
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written examination was administered to the SR0 instant. Tte SR0_ upgrade was waived.from taking the written portion of the' examination.
Results:
Both candidates successfully passed the'operatir.g portion: of the examination. The SR0 instant successfully passed the~ written examination. -No generic weaknesses were identified 2in the licensee's training program during 4
i the administration of this licensing exualattion.
a 9009120138 900905 PDR ADOCK 05000116.
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REPORT-DETAILS' 1.
Examiners H. Peterson~ Chief Examiner, NRC, Region III'
- B, Wetzel, Examine', NRC, Headquarters r
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Facility 1 Representative f
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- R. Hendrickson, Reactor l Manager;'
- Denotesthosepresentatthemanagementexitmeetingon1Jul[20,1990.
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. 3..
Summary of Results Written 0perating' 0verall Pass / Fail Pass; Ui11 Pass / Fail-SR0' 1/0
-2/0
-2/0-1 J(NOTE: The SR0 upgrade receive'd a waiver from'the' written exam.).
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. Exit Meeting A management exit-meeting was conducted at the Iowa State' University Research Nuclear Reactor-Facility 'on July 20, 1990..
representative who attended lthe meeting is listed.in~ Paragraph 2The facility (abl of this report.
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1 The following items were discussed during the exit' meeting, a
a.
.The examiners -had extremely -good cooperotiun from the facility
'i personnel, including a thorough' tour prior to the administration =
of the' exam.
b.
No generic weaknesses in training were iioted during the: exam process.-
c.
One candidate displayed unfamiliarity with the Rod Worth Procedure.
Although this procedure.is only performed onceLa year and'therefore the. candidate hod not had the-opportunity to observe it:being
.I performed, as a SR0 the candidate could-theoretically have.the responsibility for. directing the performance of this surveillance, a
He should have a'. thorough working. knowledge of this procedure. even though he had not yet performed it.
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-Enclosure 2
' Facility' Coments' and' NRC Re' solution 'of Coments~.
- 1. -.
Facility-Coment: L.QuestionA'.002. -Answer M.5.1 inches..
Facility Justification:
Af.= '-5 F * -0.00384 %.A k/k/F +l. 5 (%>vSid);* -0.172l%A k/k/(% void)
- Af = 10,0668. % A k/.k J
j So 0.0668 %.d k/k"is needsd.; hrefIre,
<'t WithdrawalL= 0.0668 %-: A k/kLdivhed by 0.0132' %M k/k/ inch Withdrawal = 5.06. inches
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. Recommended Resolution: Delete the; question since.theLcorrectianswer.
.is not among: choices.
NRC Resolution:
Coment accepted. : The question ' willi be delete' ifrom the d
exam..The key was incorrect.
y 2.
Facility Coment: Question.A.004'.n CorrectLanswer is;"B'".
- Facility Justification:
The'. listed answer on the answer key isla
. typographical error.
' Recomended Resolution: Accept answer "B only.
t NRC Resolution: Comment accepted. Answer ' key changed..
s 3.
Facility Comment: Question A.012.. Answers "A". and:"B" are correct.
Facility 00stification: A prompt critical reactor is supercritical..
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Recommendt d Resolution: Accept both answers "A" and "B".
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l NRC Resalution: Comment noted.. Answer "A" does not need to be accepted for this exam because the candidate chose the correct' answer, "B";-
The question will be reviewed for a possible rewrite prior to uploading to the exam bank.
4.
Facility Comment:. Question A.014. The answer 'is correct, but the
'i reference is wrong.
Recommended Resolution: Change the reference to "ISU-l Operations Projects", P. 11.
NRC Resolution:
Comment.noted. References will'be changed prior to uploading to the exam bank.
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'5 Facility C6 ment:. Question' A;015. The; answer is' correct, but the
- reference is not
- relevant.' -
, Facility Resolution: ' Change' reference to general know~ ledge.--
NRC' Resolution:L Coment noted.. References will;be changed prior to
= uploading {to the' exam bank.
- 6. M Facility Coment: iQuestion A.019.
None,of'the listed / answers are' Ecorrect.:'
Facility Justification':: The gross: current produ'ced by neutrons is:
independent of the. voltage applied to the compensat.ingl.section of.a compensated. ion chamber (CIC)L-.The. net current produced by a CIC is reduced by overcompensation. ;The cause of the reduction is an increasesinL the compensating current procedure per gama ray interaction in the.
compensating region of the CIC,Lnot a reduction >in the number of neutron:
-interactions.
Note that a short, yet complete,, answer for Question A.019 is difficult to phrase.
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Facility Resolution:
Delete.the question.
j NRC Resolution: LComent-accepted. - Qubstion deletedh 7.
Facility Coment: Question B.001,-Part 4.
The answer-should be "Anyone in the Nuclear Engineering Lab.";
l Facility-Justification:. all holders-of outside Nuclear Engineering Lab
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keys are trained to initiate the Emergency' Response Procedure upon
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observation of an emergency condition.3 All;of them are capable'of; 1
turning on the evacuation bell switch.
Reference:
Emergency! Plan Response Procedure, P. 1.
Facility Resolution: Delete the question.
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NRC Resolution: Coment accepted.
Part 4 of qiiestion is(deleted.
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Facility Comment: Question C.007.
"B" is the correct answer for the
- 1 question as stated, but "C" is acceptable.:
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l Facility Justification: - The Technical Specifications' state that~the drop L
time shall not exceed 600 ms, but the drop-time' includes the' delay time.
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Delete the phrase " excluding the delay time" to make'"C" the correct i
answer.
Reference:
Technical Specifications _, P. 1-1.,
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4 Facility Resolution:
Accept both answers "B" and "C".
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b NRC Resolution: Question deleted. The phrase " excluding the delay time"'
l made answer "B" incorrect and the question confusing'. Both answers could; not be accepted as correct for this question.
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