IR 05000057/1985003
| ML20138E672 | |
| Person / Time | |
|---|---|
| Site: | University of Buffalo |
| Issue date: | 10/08/1985 |
| From: | Dudley N, Keller R, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20138E613 | List: |
| References | |
| 50-057-85-03, 50-57-85-3, NUDOCS 8510250078 | |
| Download: ML20138E672 (50) | |
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U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO. 85-03 (OL)
FACILITY DOCKET NO. 50-57
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FACILITY LICENSE NO. R-77 LICENSEE:
State University of New York at Buffalo 521 Capen Hall Ar.herst, New York 14260 FACILITY:
State University of New York at Buffalo EXAMINATION DATES:
September 4-5, 1985 CHIEF EXAMINER:
M eb
.h hts
/O-3 -85 w
Noel F. Dudley
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Date Lead Reactor Engi er (Examiner)
REVIEWED BY:
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/0M/F
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Robert M. Keller, Chief Date Projects Section 1C
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APPROVED BY:
Harry B. Mster, Th\\ef, Datie' J '
Projects eclanch No. T SUMARY: Written and Oral examinations were administered to two reactor operator candidates. One candidate failed the written examination. One license was issued. Some reference material provided for preparation of the examination was found to be outdated.
8510250078 851017 gDR ADOCM 05000057 PDR
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REPORT DETAILS TYPE OF EXAMS:
Replacement EXAM RESULTS:
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1.
CHIEF EXAMINER AT SITE:
J. D. Smith, PNL 2.
EXAMINATION REVIEW MEETING
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At the conclusion of the written examination, the examiner met with Mr. P. M. Orlosky and Mr. A. Adams of the State University staff to review the written examination and the answer key.
The facility comments and the resolution to the comments are contained in Attachment 2.
3.
EXIT MEETING At the conclusion of the site visit, the examiner met with members of the facility staff to discuss the results of the oral examinations. Those candidates who clearly passed the oral examination were identified in this meeting. The examiner made the following observations concerning the training program, a.
No generic weaknesses were found, b.
The candidates displayed excellent control room behavior including procedures, logs, and operation of the reacto _.
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DEFICIENCIES Facility training material does not reflect the present condition of the
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facility. Numerous changes to the examination were made due to t
inadequate _or incorrect facility information being provided for
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examination preparation. The facility is to provide to the NRC the
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corrective actions which will be taken to improve the accuracy of the facility training and reference material (open 50-57/85-03-01).
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Attachments:
1.
Written Examination Answer Key:
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2.
Facility Comments on Written Examinations made after Exam Review l
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e U.S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION i
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Facility: STATE UNIVERSITY OF NEW YORK
Reactor Type:
POOL Date Administered:
September 4, 1985 i
Examiner:
SMITH
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Candidate:
Answer Key ( M A S T6R)
INSTRUCTIONS TO CANDIDATE:
Use separate paper for the ar swers. Write answers on one side only.
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Staple question sheet on top of the answer sheet.
Points fur each question are
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indicated in parenthesis after the question. The passing grade requires at l
least 70% in each category and a final grade of at least 80%. Examination
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papers will be picked up six (6) 1ours after the examination starts.
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Category
% of Candidate's
% of Value Total Score pat.Value Category
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14.5 15.0 A. Principles of Reactor Power
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Operation 14.0 14.5 B. Features of Facility Design
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j 13.5 14.0 C. General Operating
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Characteristics
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13.5 14.0 D. Instruments and Controls
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13.0 13.5 E. Safety and Emergency Systems
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15.0 15.5 F. Standard and Emergency Operating Procedures 13.0 13.5 G. Radiation Control and Safety 96.5 TOTALS
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Final Grade
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i All work done on this examination is my own; I have neither given nor received
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aid.
t Candidate's Signature
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STATE UNIVERSITY OF NEW YORK September 4, 1985
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A.
PRINCIPLES OF REACTOR POWER OPERATION (14.5)
Points Available 00ESTION A.1 The reactor is operating at a high power level when the reactor
cooling system primary pump fails. List the sequence of events that follow this occurrence.
(1.5)
ANSWER A.1 i
The reactor trips on low flow (slow scram) (+0.5),
flow stops and reverses when flapper valve opens (+0.5),
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and natural circulation is established (+0.5).
Reference (s)
i 1.
SUNY SAR, p. 83.
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STATE UNIVERSITY OF NEW YORK i
September 4, 1985
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l Points Available QUESTION A.2
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a.
If the SUNY Reactor were increasing power with a period of 25 sec, how much time is required for the power level to increase by 2 decades? Show your calculational procedures.
(2.0)
b.
If the mean lifetime of neutrons in the reactor were 8 x 10-2 sec, what is the reactivity of the core?
(1.0)
ANSWER A.2
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a.
T = 25 sec l
P/P = 100 = e /25 (+1.0)
I t
o
in 100 = t/25
{
t = 25 in 100
= 115 sec (+1.0)
= 1.92 min
'#
b.
T - t /1k--
(+0.5)
( :-
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I+A AN T
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._
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-ui
.0073
,
4 x 1c-2 g 9.bd W* '(T)
uz
"
i 2 '.,
m-O. z S Z Ah v3.2 x 10 3 (+0.5)
g Reference (s)
1.
Technical Education Research Center-Southwest, " Nuclear Technology." pp. 12-1-13 to 12-1-18.
2.
SUNY NSTF Reactor Operator Training Manual.
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- Section A continued on next page -
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STATE UNIVERSITY OF NEW YORK
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September 4, 1985
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i Points
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Available
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OHESTION A.3
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Consider the " doppler broadening" effect that takes place in the
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fuel of the SUNY Reactor.
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a.
Explain what causes the phenomena of doppler broadening.
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Include which isotopes are the main contributors.
(1.5)
b.
As the temperature of the fuel increases what parameter of
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i the six-factor formula predominantly is affected and what i
impact does this have on k,ff?
(1.5)
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ANSWER A.3 An increase in the fuel temperature causes a broadening of a.
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l the neutron absorption peaks (the resonance peaks); on a graph
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of neutron absorption cross-section as a function of energy
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the cross-section peaks widen and the peak value becomes t
r smaller (+0.5).
The broadening is due to the increased vibra-
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tional energy as the temperature increases (+0.5).
The peaks
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j in the absorption cross-sections of U-235 and U-238 are the primary contributors to the effect in the reactor (+0.5).
a
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t). 2 2 e p o-r W//* D t">' t e os t ofe r A,vrw sti.
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b.
As the fuel temperature increases, the widening of the resonance
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peaks causes the resonance escape probability (+0.75) to decrease and hence for kegg to decrease (+0.75).
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l Reference (s)
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1.
Technical Education Research Center-Southwest, " Nuclear l
{
Technology," pp.12-7-8 to 12-1-9.
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Generic.
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STATE UNIVERSITY OF NEW YORK September 4, 1985
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Points
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QUESTION A.4 A nuclear reactor is shutdown by 7% ak/k when the neu-tron detector is recording 20 cpm. What would this detector read when k,ff = 0.98?
(1.5)
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ANSWER A.4
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ak
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1 = 0.07 j
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t 1-k
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g = 0.07
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k
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1=kg + 0.07 kg i
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I 1 = 1.07 k g i
j kg = 1/1.07 = 0.93 (+0.5)
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1-k CR CR -
>
1-k ' CR (+0.5)
=
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1
CR2 = (20)(3.50)
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f i
j
= 70 cpff (+0.5)
l Reference (s)
[
1.
Generic: " Academic Program for Nuclear Power Plant Personne),"
i Volume !!, pp. 5-6 through 5-13, General Physics Corporation.
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SUNY NSTF Operator Training Manual.
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STATE UNIVERSITY OF NEW YORK September 4, 1985
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j Points i
Available
00EST10N A.5 l
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j Why is the worth of a control rod dependent on the position of that control rod?
(1.0)
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i ANSWER A.5 (
The reactivity ef fect, i.e. worth, of a control rod depends on i
j the impact that the material of the control rod has on the absorp-
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tion rate of neutrons (assuming a poison-type of control rod).
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The reactivity worth of a small-sized absorber can be expressed I
as dependent on the (relative) neutron flux in the vicinity of the absorber and the impact that a change in that location will have on the total neutron population. Mathematically, the result j
is that the effect is proportional to the square of the neutron
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flux at the location where the change is made in absorber con-
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centration. Hence, changing the amount of absorber material near
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the center of the reactor core will have the largest effect on
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reactivity.
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The essence of the above (+1.0).
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Reference (s)
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1.
Stephenson, R., McGraw-Hill.
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STATE UNIVERSITY OF NEW YORK September 4, 1985 i
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Available
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00ESTION A.6
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Indicate whether each of the following statements are TRUE or FALSE.
(2.5)
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i (a.) An increasing concentration in the reactor core of Xe-135 j
reduces the thennal utilization factor, f, and hence the j
l multiplication factor, k,gy, of the reactor core.
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(b.) The thermal-neutron microscopic absorption cross section of
Xe-135 is greater than that of uranium, i
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j (c.) Xe-135 is produced both directly as a fission product and as l
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the result of a decay chain from other fission products.
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(d.) A good approximation for determining the production in a reactor core of Xe-135 is to assume that the Xe-135 is i
produced fre the decay of Cs-135.
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(e.) The removal rate of Xe-135 is due to the neutron absorption l
t rate in Xe-135 atoms ar.d due to the radioactive decay of j
Xe-135 atoms.
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ANSWER A.6
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l (a.)
TRUE l
l (b.)
TRUE
(c.)
TRUE
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(d.)
FALSE
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(e.)
TRUE
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(+0.5 each)
i Reference (s)
j 1.
Generic: Academic Program for Nuclear Power Plant Person-
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nel, Volume 11, General Physics Operation, pp. 4144f.
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2.
Technical Education Research Center-Soutnwest, i
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" Nuclear Technology," pp.12-7-12f.
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STATE UNIVERSITY OF NEW YORK -
September 4, 1985
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l Points
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Available QUESTION A.7
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Specify the nuclear reactions-that are responsible for functioning of the nonregenerative neutron source.
(1.0)
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ANSWER A.7
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Pu
92
+ 2"'
U
+
l (source neutron)
He
0
- n
+4e
o
+
The alpha particle from the decay of plutonium (Pu238, Pu239, Pu242)
f causes Be-9 to become C-12 and release a neutron. (+1.0)
I Reference (s)
1.
SUNY Training Documents: Nuclear reactions of interest
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to reactor operators.
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September 4. 1985 L
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Points L
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j QUESTION A.8 l
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statement fran those given below.
(1.0)
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(a.) The unit (of measure) of the " barn" is a measure for the macroscopic neutron cross section.
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(b.) Delayed neutrons have at birth a harder energy spectrum f
than neutrons produced from the fissioning of U-235 by thermal neutrons.
+
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(c.) The microscopic cross section for neutron interaction
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depends upon the isotopic composition of the material-l and of the energy of the neutron.
j (d.) The reactor rate for neutron absorption in a given material j
is inversely proportional to neutron flux.
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ANSWER A.8
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(c.)
(+1.0)
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Reference (s)
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Generic:
" Academic Program for Nuclear Power Plant Person-nel," Volume 1, General Physics Corporation, pp. 4-25f.
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STATE UNIVERSITY OF NEW YORK
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B.
FEATURES OF FACILITY DESIGN (14.0)
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Points I
Available
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QUESTION B.1
Outline the method to determine that a beam tube is flooded.
(2.0)
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ANSWER R.1
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c Check that the overflow petcock is open and that tubing I
a.
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extends from the petcock to the trench.
(0.66)
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Open the supply valve in the BT trench.
(+0.67)
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j Water should come out of the petcock almost immediately c.
after opening the supply valve.
(+0.67)
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Reference (s)
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OP #43, p. 2.
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STATE UNIVERSITY OF NEW YORK
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Points
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l OUESTION B.2 l
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Which one (1) of the following statements about the Rabbit System i
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(1.0)
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(a.)
This system is used to convey the Rabbit to a central core location of maximum flux.
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(b.)
There is no contact with the reactor coolant; therefore.
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(c.)
The Rabbit is a hollow plastic cylinder containing about 50 g j
of cadmium to ensure it will never insert positive reactivity.
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(d.)
Argon gas is used to operate the Rabbit in order to minimize
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corrosion in the tube, t
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l ANSWER R 2 i
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(b.)
(+1.0)
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l Reference (s)
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l 1.
$UNY SAR, pp. 45 and 65.
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STATE UNIVERSITY OF NEW YORK I
September 4, 1985
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Points l
Available
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QUESTION B.3
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,1 What design feature helps reduce the dose rate at the
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top of the pool from N-16?
(1.0)
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ANSWER B.3 Holdup tank (+1.0)
DOWN wA at p r L 8 W (f D.5)
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Reference (s)
j 1.
SUNY SAR p. 49.
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Ot1EST10N B.4 Oraw a simplified sketch of the pneumatic tube system (Rabbit).
l include valves, filter, and prime mover.
(3.0)
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l ANSWER B.4 See attached figure.
- Reference (s)
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1.
OP #42, p. 4 i
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STATE UNIVERSITY OF NEW YORK
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September 4, 1985 q.
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STATE UNIVERSITY OF NEW YORK
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September 4, 1985
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Points 00ESTION B.5
I How is the pool water prevented from mixing with the secondary
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water during reactor operation if a leak should occur in the heat exchanger?
(2.0)
I ANSWER B.5 Th: m nd; y sid: wier is rainteir.cd et k!;5:r pre wer: 1.rieg m.
e -14:- e= m -(rI.o) Pgo,u y At et e e n u. e4 n/a a r w" Wo nsaa> Qt.,)
t s woT Potrv Entn l
l Reference (s)
]
1.
SUNY SAR IV E p. 49
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00EST' ION B.6 l
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I 1.ist the four (4) functions of the Reactor Cooling and Purifi-cation System.
(3.0)
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ANSWER B.6 i
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i 1.
Maintains low conductivity of the water to minimize corrosion
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of all reactor components, particularly the fuel elements
i 2.
Reduces radioactivity in the water by removing nearly all I
particulate and soluble impurities
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3.
Maintains the optical clarity of the water
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Provides a means of d hsipating the heat generated in the
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i reactor
)
(+0.75each)
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i Reference (s)
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SUNY SAR, p. 49.
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STATE UNIVERSITY OF NEW YORK September 4, 1985
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Points
Available 00EST10N B.7 List the conditions that would inhibit rod withdrawal.
(2.0)
ANSWER B.7 i- = - i-..--
_t an_ m mai u t.,-
my s t w rod
_ Si t2..et. w.
__ witch-eithe:n1
"Opacete"
"L ; " :.-J;tBTt"
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gfc 44#4 Ty X &, a oFF (+8.d)
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Low count rate Switches Relay Inhibit of rod
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<2 cps, >9800 cps withdrawal
or chart drives / log-
" Start up
i N <4 watt inhibit"
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(+1.0)
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Reference (s).
1.
SUNY: SAR, p. 63.
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STATE UNIVERSITY OF NEW YORK September 4, 1985
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.
C.
GENERAL OPERATING CHARACTERISTICS (13.5)
Points Available
,
QUESTION C.1 After four (4) days of full-power operation a scram occurs.
l a.
What would you expect to see while monitoring the nuclear instrumentation for the first five (5) minutes?
(1.5)
i i
j b.
What difficulties would you expect associated with a reactor j
startup three (3) to eight (8) hours after the scram?
(1.5)
I
l ANSWER C.1 i
.
a.
Prompt drop (+0.75) followed by an ~80-second negative
{
period (+0.75).
,
,
)
b.
Xenon will peak in -3 hours, then decay adding positive reactivity over the next sixty (60) to seventy
(70) hours.
(+1.5)
!
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Reference (s)
i 1.
Stephenson, R.,
McGraw Hill,
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STATE UNIVERSITY OF NEW YORK
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Ssptember 4, 1985 1-
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I Points
Available
j QUESTION C.2 I
Explain the function of the Plenum Flapper Valve.
(2.0)
!
i ANSWER C.2
,
A hinged, counterbalanced safety flapper valve is located on the
-
,
side of the plenum. When held closed by pump suction in the
'
plenum (operation over g KW), all coolant ter must flow down j
through the fuel, if, however, a power of KW will not be j
exceeded, the primary pump need not be operated, and the flapper i
valve will remain open to allow cooling of the fuel by upward
I convection of water, it also provies for convection cooling if
the pump fails.
!
(+0.5 for each underlined item)
,
!
Reference (s)
f I
1.
SUNY SAR. p.29
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00ESTION C.3
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a.
What is the maximum excess reactivity allowed by the SUNY
!
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Operating Licente including experiments?
(0,5)
'
b.
What types of reactivity changes occur which require
{
excess reactivity to be loaded in the core?
(1.0)
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ANSWEP C.3
.
l
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j a.
5.2% ak/k (+0.5)
f b.
Fuel burnup over core life. 4+he) (+ 0.*D IV## #^'# 3 b O*
(
Reference (s)
i i
1.
SUNY Tech. Spec. 3.1, p. 8.
,
j 2.
SUNY NSTF Operator Training Manual.
- Section C continued on next page -
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STATE UNIVERSITY OF NEW YORK September 4, 1985
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Points L
Available l
00EST10N C.4 What is the maximum steady state thermal power level allowable by the Technical Specifications?
(1.5)
ANSWER C.4
.
1,. 0-3r4 MW (+1.5)
.
I Reference (s)
L 1.
SUNY Tech. Spec. 2.1.1, p. 5.
.
b OUEST10N C.5 i
The regulating rod is worth about (1.0)
I (a.)
$2,00
.
(b.)
$5.00 l
(c.)
11.00 (d.)
$3.00.
ANSWER C.5 (d()
(+1.0)
( b)Reference (s)
L 1.
SUNY SAR, p. 52.
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STATE UNIVERSITY OF NEW YORK S2ptember 4, 1985
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Points Available QUESTION C.6 If the reactivity addition rate of a regulating rod is adjusted as per the SAR, how long would it take to insert one (1) dollars
worth (-0.7% ak/k) of reactivity? Select one.
(1.0)
l (a.)
10 seconds (b.)
20 seconds
,
!
(c.)
40 seconds (d.)
60 seconds
!
ANSWER C.6
(,)T)
(+1.0)
'
(c.) Reference (s)
!
1.
SUNY SAR, pp. 52-53.
!,
Ot!ESTION C.7
,
What is the maximum worth in %ak/k for movable, unsecured and secured experiments allowed by the Technical Specifications?
(1.5)
ANSWER C.7
,
.
I Movable 10.3% ak/k Unsecured 10.6% ak/k Secured 21.5% ak/k
(+0.5 each maalem, +0.25 for t)
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Reference (s).
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SUNY Tech. Spec. 31, p. 8.
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STATE UNIVERSITY OF NEW YORK Saptembar 4, 1985
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Points
Available
QUESTION C.8 r
i What three (3) neutron absorbing materials are used in i
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the six (6) neutron absorbing blades?
(2.0)
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J ANSWER C 8
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i 80% silver, 151 indium and 5% cadmium
'
(+0.66 each)
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Reference (s)
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SUNY Tech. Spec. 5.6, p. 26.
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STATE UNIVERSITY OF NEW YORK September 4. 1985
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i D.
INSTRUMENTS AND CONTROLS (13.5)
l Points Available 00EST10N D.1 List the five (5) functions for indications provided by the switches on the rod assemblies.
(3.0)
ANSWER D.1
-
1.
When magnet is in up position 2.
When magnet is in down position 3.
When magnet is in contact wi,th control rod armature
Rod not seated 5.
High excess K Limit upper and lower travel.
(+0.6 each)
Reference (s)
1.
SUNY Training Document (Control Rod Mechanism;.
QUESTION 0.2 What type of neutron detector is used for the count-rate channel? Briefly describe the constrution of the detector.
(1.5)
ANSWER 0.2
,
The detector type is " fission chamber" (+0.5).
A fission
chamber is a cylindrical can lined with highly enriched y*2#)/
V03 8 with a high voltage potential between center electrode and can (+1.0).
Reference (s)
Generic.
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STATE UNIVERSITY OF NEW YORK
September 4, 1985
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Points
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Available OUEST10N D.3
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a.
How and why is gamma radiation compensated for in a compen-
[
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sated ion chamber (CIC)?
(2.4)
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b.
How would the output of a CIC be affected if it was sig-i nificantly under-compensated for low power operation?
(0.6)
!
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j ANSWER D.3 a.
Neutron countrate is sensed in the outer can by interaction j
with boron paint. Gamma radiation is sensed in both the
outer can and inner can. The lack of baron paint in the j
inner can causes only gamma interations to take place. A j
compensating voltage is applied to the inner can to exactly j
balance the gamma current being sensed in the outer can.
l (+0.8 for each underlined item)
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b.
Detector output would read high.
(+0.6)
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Reference (s)
)
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Radiation Protection Training Manual.
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STATE UNIVERSITY OF NEW YORK September 4, 1985
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Points Available 00ESTION 0.4
.
List six (6) system conditions that would automatically scram the reactor. Specify the limit values, if any, that would cause the scram.
(3.0)
ANSWER D.4 1.
Power level channel, >120% full power
,
2.
"0::t er i,e ri c,4 der acl. '* - tec. - per t ^A - ogy otAeJM A * * * O M^'
3.
Ion-chamber power supply failure
Low flow logo gpg 5.
Water level 6.13 Nf7 EAT
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6.
Temperature >MG'F iff'F F '2. * f.
y'
PL APFfA
" (+0.5 each) 4 y y g,
Reference (s)
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SUNY SAR, p. 63.
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STATE UNIVERSITY OF NEW YORK September 4, 1985
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Points Available OUESTION D.S
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List the six (6) streams in the cooling system that are monitored for temperature.
(3.0)
ANSWER D.5 1.
Reactor Tank Core Inlet 2.
Reactor Tank Core Outlet 3.
Primary Heat Exhcanger Inlet
'
Primary Heat Exchanger Outlet 5.
Secondary Heat Exchanger Inlet
Secondary Heat Exchanger Outlet (+0.5 each)
Reference (s)
1.
SUNY SAR, p. 57 End of Section D -
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September 4, 1985
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E.
SAFETY AND EMERGENCY SYSTEMS (13.0)
00EST10N E.1 For building evar.uation:
a.
Where is the switch located that activates the evacuation alarm?
(1.5)
b.
What other means are available to evacuate the building?
(1.5)
ANSWER E.1 a.
The switch is located on the radiation monitor panel in the Control Room.
(+1.5)
b.
Building fire alarm (+0.75)
P.A. announcement (+0.75)
'
Reference (s)
1.
EP #1. p. 3.
OUESTION E.2
,
Who is to be notified (called) first in the event of a medical
.'- '
emergency?
(1.0)
[
ANSWER E.2 The first call should always be to the public safety department dispatcher. (+1.0)
Reference (s)
- ;1. EP #2, p. 3.
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Points i
Available 00ESTION E.3
_
Draw a simplified sketch of the Secondary Cooling System.
(3.0)
ANSWER E.3
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Attached Reference (s)
1.
OP #21, 22, p. 4 l
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J OP f 21,22 (6/85)
SECONDARY C00LIl0 SYSTEN
.
Cooling Tower Float Valve Spray Headers
i i
Removable
.
Standpipe
.
(Drain)
3,4{
.
x x (+1.0) piping N--
(+0.5) each for pumps,
{ S-6
Basin
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heat exchanger
.
and chiller m
condenser.
__
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valves not required for full credit m
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S -5 8c Ha**
F 8 'I S-3 l
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g Exchanger 2.
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Supply
Valve
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Pump S-ItX O
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a5 Drain -
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Puarp Floor
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700 gpm ANSWER E.3
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STATE UNIVERSITY OF NEW YORK September 4, 1985
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Points Available OUESTION E.4 Provide a description of the operation of the following instruments, and specify the type of radiation for which each instrument is tsigned to monitor.
a.
Pencil dosimeter (1.0)
b.
Film badge (1.0)
c.
Cutie pie (ionization instrument)
(1.0)
ANSWER E.4 e pocket dosimeter used at the SUNY Reactor Facility,d-leaf is a.
dir t reading and operates en the.. principle of the g,ol elect scope. The detection system consists of a small quartz-fiber ele _roscope, which forms part of the col etting elec-trode. The strument case, which is insulat from the fiber system, serves the other electrode. The ollection volume is small (2 cm3 most often contains ir at ambient pressure. The quart iber is displac d electrostatically by charging it to a potentt4 of about/200 volts. By adjustir the voltage on the charger, e cafi bring the image to zero-scale reading. The scale may ' measured in terms of image move ent. The light for ters through a window at theendofthedevice.,,A)vewing n image of e fiber is focused on the scale and is vie,w,ed through a lens the other end of the instrument. Esposure of the dosimeter o radiation dis-charges the fiber, thereby allcwing it to ret n to its original posi on. The amount discharged, and sequently the change n position of the fiber, is proportion to the radiatio exposure.
(Commonly-used direct reading dos %ters that e commercially available have a range of 0-200 nR, hnd t
reaf within about 15% of the true exposure for gamma-ray er(ergies from about 50 kev to 2 MeV.)
(+1.0)
NDW s~ftf AfApid A ?'
&W A ccEs r n os ~ f /--
7 H A-7 s Ale u e va S
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Ctwitove
% Jt fo 7;t w T M L, O!JfhW<'fd
By s"> P aftst C sur A FAP ed A AEADid (+ l. c)
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STATE UNIVERSITY OF NEW YORK September 4, 1985
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Points Avail abl e ANSWER E.4 (contd)
b.
Film badge dosimetry is based on the fact that ionizing radia-tion exposes the silver halide in the photographic emulsion, which results in a darkening of the film.
The degree of darkening, which is called the optical density of the film, can be precisely measured with a photoelectric densitometer whose
,
reading is expressed as the logarithm of the intensity of the light transmitted through the film. A typical film badge
<
consists of a packet of dental-sized film wrapped in light-t'ight paper and worn in a suitable plastic or metal container.
.
The film for X and gamma-radiation includes a sensitive
.,
emulsion and a relative insensitive emulsion. Such a film pack is useful over an exposure range of about 10 mR to about 1800 R of gamma rays. The film is also sensitive to beta-radiation if the beta energy exceeds 400 kev.
(+1.0)
c.
For beta and gamma radiation levels of between 5 mrem /hr and 500 mrem /hr, ionization chambers are generally used for both detection and measurement. A commonly used instrument is called the cutie pie meter. An ionization chamber is a gas-filled detector that is operating in the Ionization Region.
Such detectors are accurate but low in sensitivity.
(+1.0)
Reference (s)
1.
Radiation Protection Training Manual, pp. 30-31.
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September 4, 1985
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Points Available OUESTION E.5 Nine (9) fire alarm pull boxes are located throughout
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the facility, Where does it alarm if any one (1) of the nine (9)
a.
are pulled?
(1.0)
b.
How is the alarm turned off?
(1.0)
c.
Explain how the alann could be activated without pulling one (1) of the pull boxes.
(1.0)
4-
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AN5UER E.5 Public 5afety Depar'tment (+0.25), Klaxons throughout the a.
building (+5.26), and the Buffalo Fire Department (+0.25)
'
for all pull boxes extcpt the one (1) outside of the building, which alarms only 0*. the Fire Department (+0.25).
b.
Automatically after three (3) minutes (fl.0).
c.
Ceiling mounted flash-fire sensors. (+1.0).
Reference (s)
1.
EP #6, p. 2.
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F.
STANDARD AND EMERGENCY OPERATING PROCEDURES (15.0)
Points Available OUESTION F.1 What should be an operator's response in the event a scram annunciation and a scram occurs?
(3.0)
!
ANSWER F.1 stram Signals In the event of a scram annunciation, the operator will immediately back up the automatic scram system by pressing the console scram button and ensure all rods have dropped. Do not reset the annun-ciator until the cause of the scram has been determined. The shift supervisor will be advised of the specific annunciation. Under no conditions will the reactor be restarted without investigation by a senior operator of the cause of the scram.
(+0.5 for each underlined item)
Reference (s)
.
1.
OP #6, p. 2.
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STATE UNIVERSITY OF NEW YORK September 4, 1985 l
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i Points I
Available 00ESTION F.2 By normal operating procedure, whenever withdrawing any control
,
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rod, the stable reactor period should usually be limited to:
(select one)
(1.0)
!
(a.)
greater than 30 seconds (b.)
less than 30 seconds (c.)
greater than 20 seconds (d.)
less than 20 seconds
,
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ANSWER F.2 (WI)
(+1.0)
(CdReference (s)
l 1.
OP #5, item 9, p. 2.
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September 4, 1985
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.
Points Available 00ESTION F.3 List the six (6) minimum requirements that must be met to
'
place the reactor in the shutdown condition.
(3.0)
.
l ANSWER F.3
a.
Safety rods must be fully inserted.
b.
The console key must be removed and either be locked up or in the possession of an operator.
.
c.
The console recorders turned off.
,
l d.
The cooling system placed in an appropriate condition.
e.
Before leaving the control deck, the operator should confirm that the drives are full down and the control blades are fully inserted.
i f.
Tend to any experiments that may need attention due to the changed reactor status.
(+0.5 each)
Reference (s)
,
1.
OP #7, IIE.1, pp. 1-2.
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STATE UNIVERSITY OF NEW YORK
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September 4, 1985
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Points Available
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OUESTION F.4
l In the event of a fire, what three (3) conditions, if they cannot be met, require that you turn in a fire alarm?
(3.0)
l i
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1;f the fire is small (+1.0), and does not involve radioactive l
material (such as a fire in a wastebasket or instrument chassis),
'
!
and if the appropriate fire extinguisher is readily available (+1.0),
l fight the fire ji f you are able (+1.0).
If you attempt to fight the j
'
fire and cannot control it quickly, turn in a fire alarm.
,
.
q If any of the above three conditions are not met, do not fight j
the fire. Turn in an alarm.
1 j
Reference (s)
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EP #1, IVB.1, p. 3.
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STATE UNIVERSITY OF NEW YORK September 4, 1985
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Points
Available QUESTION F.5
,
i You, as the operator, identify a minor leak in the primary coolant system. What is your appropriate response?
(2.0)
' ANSWER F.5 Minor leaks
,
1.
Notify shift supervisor or senior operator on call, and request immediate instructions (+0.5).
If possible, isolate the leak (+0.5).
If necessary, add water to the pool (+0.5).
2.
Notify the highest available Emergency Director candidate b (+0.5).
.
Reference (s)
]
1.
EP #4, IVB, p. 3.
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STATE UNIVERSITY OF NEW YORK September 4, 1985
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Points Available 00ESTION F.6 While operating at power, a reverse signal occurs:
a.
What should be the operator's response to this event?
(2.0)
b.
Under what circumstances could the operator continue to operate the reactor after receipt of a reverse signal?
(1.0)
ANSWER F.6
'
Reverse Signals a.
1.
Acknowledge annunciator 2.
Manually scram the reactor 3.
Notify Shift Supervisor l
Determine cause before reactor restart (+0.5 each)
b.
Operators may continue to operate the reactor after
receipt of a reverse signal if the condition causing the reverse is kJmwn, and has reset itself.
(+0.5 for each underlined item)
Reference (s)
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1.
OP #6, p. 2.
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STATE UNIVERSITY OF NEW YORK
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September 4, 1985
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G.
RADIATION CONTROL AND SAFETY (13.0)
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Points Available QUESTION G.1 A target has been irradiated in the SUNY Reactor, a.
You anticipate that the target contains only one stable iso-tope of one low-Z element that has undergone a neutron absorp-tion [(n,y) reaction]; you anticipate that the radioactive decay of the resulting radioactive isotope is a one-step decay to a new stable isotope. What type (s) of emissions would you anticipate would come from the radioactive target after it is j
removed from the reactor? Justify your answer.
(1.5)
!
l b.
If, after you have removed the target from the reactor, you record over a period of time the countrate from a detector
placed next to this target, how would you determine the half-life of the radioactivity?
(1.5)
ANSWER G.1 If a stable isotope of an element absorbs a neutron, it will a.
form a new isotope that is above the line of stability (+0.75).
Isotopes of low-Z materials which are above this "line" usually
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decay toward the "line" by S~ emission. Such 8~ emissions may be preceded by or may include the emission of one or sev-eral ys (+0.75).
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,. - - _ -. -, -
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37 STATE UNIVERSITY OF NEW YORK
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September 4, 1985 i
Points Available ANSWER G.1 (contd)
f b.
The radioactive decay of a single radioactive isotope will follow the exponential decay law.
g = A e-At
)
(+0.5)
A n
!
A2*Ae
l o
j A
_1
,-A(t-t)
y 2 l
A2
i
}
in Ag - 19 A2 = -A(t -t I t 2 r
in A - in A
!
2 A"
(+1.5)
,
t -t g 2 then, a
1/2 *.693 t
A
'
Graphically, you can plot in A(t) versus t and the slope of the i
graph is -A.
(+1.5)
!
(+1.5 max)
Reference (sl 1.
Technical Education Research Center-Southwest,
<
pp. 1-7 to 1-12.
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September 4, 1985
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Points Available
4 00EST10N G.2 l
if the target of Question G.1 had been placed in the SUNY Reactor
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j,
and the reactor brought to 100% of full power, sketch the activity
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of the target as a function of time.
(2.0)
+
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ANSWER G.2
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a
,
A c t.
__
A = I6(1-e-At)
!
e
i e
l
)
(+2.0 for shape or equation)
j Reference (s)
+
]
1.
Technical Education Research Center-Southwest, pp.1-15.
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STATE UNIVERSITY OF NEW YORK September 4, 1985
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Points Available 00ESTION G.3 In the event of a radioactive material spill and airborne contamination is suspected, what immediate action (s)
should be taken?
(2.0)
ANSWER G.3 All personnel shall vacate the area (+1.0) and notify HealthPhysics(+1.0).
Reference (s)
1.
SUNY EP a3, p. 1.
QUESTION G.4 If two centimeters of lead placed at a certain location in a beam of gamma rays would reduce the gamma radiation level from 100 mR/hr to 50 mR/hr, what thickness of lead placed in this beam would reduce the gamma radiation level from a.
400 mR/hr to 50 mR/hr (0.5)
b.
50 mR/hr to 25 mR/hr?
(0.5)
ANSWER G.4 a.
6 cm (+0.5)
b.
2 cm (+0.5)
Reference (s)
1.
Technical Education Research Center-Southwest, pp.1-24, 1-25, 2-1, 2-2.
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STATE UNIVERSITY OF NEW YORK
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September 4, 1985
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Y Points
Available 00ESTION G.5
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If the gama-ray radiation level from a pump (point source) had been 30 mR/hr 1 foot from the pump, what would be the radiation level 10 feet from the pump?
(1.0)
ANSWER G.5
,
Neglecting gama-ray absorption by the air, distance factor = (f)2 (+0.5)
=
rad level (10) = rad level (1)/100 i
= 0.30 mR/hr.
(+0.5)
Referente(s)
1.
Generic: Nuclear Energy Training, Module 5, " Radiation Protection," pp. 3.3-1 to 3.3-4
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September 4, 1985
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Points Available QUESTION G.6 If a man had been exposed to 0.01 R gamma radiation, 0.04 rad of beta radiation and 0.02 rad of fast neutrons, what is his total biological dose in rems? Show your work.
(2.0)
ANSWER G.6 j
0.01 R of gamma x 1 QF = 0.01 rem 0.04 rad of beta x 1 0F = 0.04 rem 0.02 rad of fast react x 10 QF = 0.20 rem Total dose = 0.25 rem (+0.25 for dose equation, +2.0 for answer, +2.0 max)
Reference (s)
1.
Geiieric: Nuclear Energy Trstning, Module 5, " Radiation Pro-
tection," pp. 2.1-1 to 2.1-3.
2.
Technical Education Research Center-Southwest, pp. 2-3.
3.
SUNY Radiation Protection Training Manual, p. 43a.
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September 4, 1985
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Points Available
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00ESTION G.7
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Explain the procedures to be used at the SUNY facility to prepare radioactive material for shipment.
(2.0)
ANSWER G.7 The essence of the following paragraph: Most solid (dry) waste is compacted into 55 gallon drums for shipment and burial. To collect such waste, recyclable containers are provided to lab-
oratories. These are repackaged and compressed for shipment.
i Liquid waste must be solidified before packaging and burial.
Distillation of liquids is another possibility, but problems in disposal of the products remain.
(+2.0)
A c c c e r-my R e nos A W G u.*L h 4 AI A To w of FA A Po4Ane t (* M NCt S A A S A ' f" 5 #~
.
Reference (s)
1.
Radiation Protection Training Manual, p. 83.
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END OF EXAMINATION t
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$5. -AN S.U.R. - 26/t
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de r
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N - N,e HVL = 0.693/p t
t s = 0.693/ A N = S/1-K i
eti P = P e /t t
A = AN
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A=Ae P = P,(10
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Stay time = dose rate
[p[
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STATE UdIVERSITY OF L'E'., YORK AT BUFFALO - FACILITY COW 1ENTS GEPEPAL The facility staff stated that the SAR sent with the facility technical infornation was outdateo ano that nuch of the infornation contained within is no longer applicable and as such is not a satisfactory reference for written examination questions.
FACILITY COM.'iENT RESOLUTION Answer A.2 Answer A.2 E* = Proapt Neutron Connent is correct.
Lifetime not nean Answer changed to:
p = 1 37 (+0.5)
Sh(+0.5)
= 0.25%
Answer A.3 Answer A.3 U-235 insignificant cooparee to U-235 not needed for correct effect of U-233.
answer added to answer key.
Answer A.7 Answer A.7 Sb/Be source used in reactor.
No change to key.
Pu/Be source available to experimenter.
Answer B.2 Answer B.2 Part (b.) is best, out it is No change to key.
possiole for tne rabbit tube to leak.
Answer B.3 Answer B.3 Holdup tanks (decay tank).
Added 60wnward flow for partial Prinary purpose is to reduce credi t (+0.5) to key.
radiation levels in pump roon, r.ot at top of poo _ _ _
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Answer B.5 Answer B 5 Is not true.
Primary pressure Key changed to read:
is not i
higher.
Issue corrected during prevented (+1.0) primary at
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re-licensing by frequent sam-higher pressure than secondary j
pling of secondary cooling.
(+1.0).
Answer B 7 Answer B.7
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Log-N selector switch not on Key changed to: Recorder turned
" operate." Inhibit no longer of f (+1.0).
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l exists.
l Answer C.2 Answer C.2
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Value no longer 100 KW.
Now Value changed to 250 KW.
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250 KW.
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i Answer C.3b Answer C 3b Also: Xe override, experiment The key word in the question is
>
requirements, temp, changes.
" loaded." Answer key changed
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to: Fuel burnup over core life (+0.5) experiments (+0.5).
I Answer C.4 Answer C.4 i
2 MW max licensed power.
Key changed to 2 MW.
Question C.5 Answer C.5 i
No rod is designated as a regu-Rod #4 currently used as
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lating rod. They are all the regulating rod.
same except for its worth.
Worth 2.9% ak/k = $4.14.
-
Also we use % ak/k instead of S.
Key changed to part (b.)
Trainees should know approx.
closest to valve.
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l value of all rods.
Question C.6 Answer C.6 I
No rod is designated as reg. rod.
Based on current drive speed.
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Reactivity rate is a function Answer key changed to Part
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l of starting position. Student (c.) closest value.
must make many assumptions.
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Answer D.2 Answer D.2
Will probably say U-235.
Key changed from U 0, to
U 0,/U-235.
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Answer 0.3 Answer D.3 i
D.C. device not pulse.
No change to key, l.
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=
Answer D.4 Answer D.4 Period scram no longer exists.
Deleted period scram from key.
Added " dry chamber door open ADD: Manual scram dry chamber and flapper open."
(+0.5) each door open flapper open, for any 6.
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U.I.C. cable open circuit.
Question E.4 Answer E.4 i
Pencil dosimeter not a self-Answer key changed to read:
reader.
" Accept answer that includes Cutie pie term not generally charging to a potential, used.
discharged by exposure and read on a reader.
(+1.0)
Answer F.2 Answer F.2 No consnent.
Key found to be in error due to semantics. Changed to part (c.).
Correct answer.
Answer F.6 Answer F.6 (2. Manuall'y scram the reactor)
No change to key.
not required if condition is
,
corrected.)
(4. Determine cause before reactor restart.)
If shut down.
- Answer G.1 Answer G.1 This topic not stressed in No change in key.
training.
Answer G.7 Answer G.7 Operators are not expected to (Accept any reasonable ship activa s terials. Staff explanation of preparing for members are selected and trained nuclear shipment). Added to in this area. Most active key.
shipments are isotopes and not waste.
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