ML20045C885
| ML20045C885 | |
| Person / Time | |
|---|---|
| Site: | University of Illinois, 05000356 |
| Issue date: | 05/28/1993 |
| From: | Caldwell J, Isaac P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20045C660 | List: |
| References | |
| 50-151-OL-93-01, 50-151-OL-93-1, NUDOCS 9306250051 | |
| Download: ML20045C885 (2) | |
Text
,
o ENfLOSURE 1 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-151/356/0L-93-01 FACILITY DOCKET NO.:
50-151/356 FACILITY LICENSE NO.:
R-115/R-117 FACILITY:
University of Illinois EXAMINATION DATES:
May 19 - 20, 1993 EXAMINER:
Patrick Isaac, Chief Examiner SUBMITTED BY:
sfr,y 8/?B/95 Pap-fy 1saet/ Chief Examiner Date '
APPROVED BY:
ht/f/
5/jty/13 James' L. Caldwell, Chief Date HongowerReactorSection Operator Licensing Branch Division of Reactor Controls and Human Factors Office of Nuclear Reactor Regulation
SUMMARY
NRC administered written examination and operating tests to one Reactor Operator (RO) and one Senior Reactor Operator Instant (SROI) applicant.
Both applicants failed the written examination. Operating tests were also administered to another SROI applicant who passed the examination and has been issued the appropriate license.
9306250051 930609 FDR ADDCK 05000151 V
pyg
.c f REPORT DETAILS 1.
Examiners:
Patrick J. Isaac, Chief Examiner 2.
Results:
R0 SR0 TOTAL (Pass / Fail)
(Pass / Fail)
(Pass / Fail) 0/1 1/1 1/2 3.
Written Examination:
An examination prereview by the licensee was conducted on'May 19, 1993.
As a result of the discussion during the examination prereview, the.
answer key to question C.13 was changed to accept both answers b and d as correct.
The written examination was administered on May 19, 1993 to one R0 operator and one Senior Reactor Operator candidates.
At the conclusion of the examination, the Chief Examiner immediately secured the master examination answer key and all of the candidate answer sheets.
A copy of the master "as given" examination with answer key was given to the Reactor Supervisor for his formal review.
The facility's written examination comments and the NRC's resolution to those comments are found in Enclosure 2.
Both candidates-failed the Reactor Theory and Facility Operating Characteristics Section (A) of the written examination.
4.
Operatino Tests:
Operating tests were administered on May 20, 1993.
There were no generic deficiencies identified by the examiner.
All three candidates passed the operating tests.
.]
5.
Exit Meetina:
Personnel attending:
Mr. Richard Holm, Reactor Supervisor Mr. Patrick-Isaac, NRC The exit meeting was conducted on May 20, 1993.
The facility
h b
examination comments were discussed as noted in Enclosure 2.
The Reactor Supervisor and the NRC discussed the responses of some candidates to questions about the Emergency Plan. When queried about.
actions to be taken in the event of an emergency, the solutions provided by the candidates, although in accordance with the Emergency Plan, were operator dependent and were not specific steps from a procedure.
The Reactor Supervisor acknowledged and expressed a concern about the lack of set guidelines offered by the facility's Emergency Plan.
The-Reactor Supervisor expressed his desire to upgrade the Emergency Plan.to provide more specific guidance to the operators.
9 s
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El4LOSURE 2 NRC RESOLUTIONS - WRITTEN EXAMINATION Ouestion A.07:
Immediately after a pulse [approximately 1 millisecond) where is the~
HOTTEST part of a. fuel element?
a) in the fuel cladding itself b) at the edge of the fuel elements adjacent to the cladding c) at the thermocouples, midway between the fuel axial centerline and the fuel edge.
d) the center of the fuel elements Answer /
Reference:
ANSWER - b Reference - SAR Pg. III-41 Facility Comment:
i The question.is incorrectly written for the given reference.
The reference listed refers to a time frame of I second after the pulse and also refers to scramming after'the pulse. This is a substantial amount of time for a pulse that has an average pulse width at half-maximum of 12 milliseconds. The scram also has an effect on decreasing the energy tail and hence the energy released during the pulse.
REFERENCE:
SAR Pg. III-41 RECOMMENDATION:
Delete question from examination.
NRC Resolution A.07:
This question will be deleted from the examination.
,--i v.
1 tNCLOSURE-3.
NRC Official Use.Only i:
F f
Nuclear Regulatory Commission Operator Licensing Examination i
This document is removed from-Official Use Only category on date of examination.
NRC Official Use Only.
i
c U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
University of Illinois REACTOR TYPE:
TRIGA DATE ADMINISTERED:
1993/05/19 REGION:
3 CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
Answers are to be written on the answer sheet provided. Attach the answer sheets to the examination.
Points for each question are indicated in paren-theses for each question. A 70% in each section is required to pass the examination.
Examinations will be picked up three (3) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 18.00 31.03 A.
REACTOR THE0RY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 20.00-34.48 B.
NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 34.48 C.
PLANT AND RADIATION MONITORING SYSTEMS 58.00 TOTALS FINAL GRADE All work done on this examination is my own.
I have neither-given nor received aid.
Candidate's Signature
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apf y:
l
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
j
- 2. After the examination has'been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have not received or given assistance in completing the examination.
This must be i
done after you complete the examination.
- 3. Restroom trips are to be limited and only one candidate at a time may leave.
You must avoid all contacts with anyone outside the examination room-to avoid even the appearance or possibility of cheating.
J
- 4. Use black ink or dark pencil only to facilitate legible reprodu'ctions.
- 5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.
- 6. Fill.in the date on the cover sheet of the examination (if necessary).
- 7. Print your name in the upper right-hand corner of the first page of each section of your answer sheets.
- 8. Each question is worth one (1) point.
Partial credit will NOT be given.
- 9. If the intent of a question is unclear, ask questions of the examiner only.
- 10. When you are done and have turned in your examination, leave the examin-ation area as defined by the examiner.
If you are found in this area while the examination is still in progress, your license may be denied or revoked.
l l
EQUATION SHEET Q - m c AT P,,,
Mw
=
p a(k f = 39 y sec k = 96 8 - 0.007 a = 1. 26 x 10
Q = m Ah SCR - S/(1-Keff)
Q = UA AT CR (1-Keff), - CR (1-Keff)2 3
2 26.06 (A,,,p)
(1-Keff)o 1
(B - p)
(1-Keff),
SUR - 26.06/7 M = 1/(1-Keff) - CR /CR 3
o P=P 10*"
SDM - (1-Keff)/Keff o
P=P e"'"
Pwr - W, m o
8(1-p)
P=
P, f, - 1 x 10'S seconds B-p (f*/p) + [(6-p)/A,,,p]
7 - t*/(p-IT) 7-p - (Keff-1)/Keff A,,, - 0.1 seconds
p - AKeff/Keff 0.693 E - 0.0070 A
DR D,2 - DR 0 DR - DR e'"
3 i
22 o
6CiE(n)
DR -
DR e
, Ci a Curies, E a Mev, R a feet 1 Curie - 3.7x10'0 dps 1 kg = 2.21 lbm 3
6 I hp - 2.54x10 BTU /hr 1 Mw - 3.41x10 BTU /hr 1 BTU - 778 ft-lbf
'F = 9/5'C + 32 1 gal H O = 8 lbm "C
5/9 ("F - 32) 2
A.
RX-THEORY, THERM 0 & FAC OP CHARS Page 2 AN5WER SHEET Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
MULTIPLE CHOICE 001 a
b c
d 002 a
b c
d 003 a
b c
d 004 a
b c
d 005 a
b c
d 006 a
b c
d 007 a
b c
d DELETED 008 a
b c
d 009 a
b c
d 010 a
b c
d 011 a
b c
d 012 a
b c
d j
013 a
b c
d j
i 014 a
b c
d 015 a
b c
d 016 a
b c
d 017 a
b c
d 018 a
b c
d 019 a
b c
d
(***** END OF CATEGORY A *****)
i B.
NORMAL /EMERG PROCEDURES & RAD CON Page 3
-ANSWER SHEET 1
Multiple Choice (circle or X your choice)
If you change your answer, write tour selection in the blank.
MULTIPLE CHOICE
~
001 a
b c
d
- 4 002 a
b c
d 003 a
b c
d 004 a
b c
d 005 a
b c
d 006 a
b c
d 007 a
b c
d 008 a
b c
d 009 a
b c
d 010 a
b c
d 011 a
b c
d 012 a
b c
d 013 a
b c
d 3
014 a
b c
d 015 a
b c
d
-016 a-b c
d 017 a
b c
d 018 a
b c
d 019 a
b c
d 020 a
b c
d 1
(****~* END OF CATEGORY B *****)
i
C.. PLANT AND RAD M0rilTORING SYSTEMS Page 4 ANSWER SHEET Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in _the blank.
MULTIPLE CH0 ICE 001 a
b c
d 002 a
b c
d 003 a
b c
d 004 a
b c
d 005 a
b c
d 006 a
b c
d 007 a
b c
d 008 a
b c
d 009 a
b c
d 010 a
b c
d 011 a
b c
d 012 a
b c
d 013 a
b c
d 014 a
b c
d 015 a
b c
d 016 a
b c
d 017 a
b
- c d
018 a'
b c
d 019 a
b c
d 020 a
b c
d
(***** END OF CATEGORY C *****)
l
(********** END OF EXAMINATION **********)
Section A R Theory. Thermo'& Fac. Operatina Characteristics Page 8
- QUESTION-(A.1)'
't Which one of the following statements describes the effect of an increase in fuel temperature _in a TRIGA fuel element.
a)
The probability.that a thermal neutron will lose energy in a collision 1
with an excited state hydrogen atom in UZrHx increases.
b)
The probability that a neutron will escape from the element before being captured in the fuel meat increases.
+
c)
A shift in the thermal neutron spectrum, towards lower energies, occurs in the fuel element.
d)
The mean free path for fast neutrons in the fuel element is decreased.
- QUESTION (A.2)
A kinetics model is used to understand the pulsing characteristics of TRIGA type reactors.
This model shows that:
a) peak pulse power varies as the square of the prompt reactivity insertion AkP
-l b) energy released varies as the square root of the prompt reactivity insertion Ak, c) average fuel temperature varies as the square root of the prompt reactivity insertion Ak, d) peak pulse power varies linearly with the prompt reactivity insertion Ak. -
y
i Section A R' Theory: Thermo & Fac. Operatina Charact eristics.
Page 9
- QUESTION (A'3).
The purpose of the beryllium in the Sb-12* neutron startup source is the following:
a) to convert the installed Sb-123 to Sb-124 b) to moderate the neutron; produced by Sb-123~
c) to convert to neutrons the y emitted spontaneously by Sb-124 d) to enhance the conversion of Sb-124 to Te-124
- QUESTION (A.4)
Reactor power decreases on a stable negative period following a reactor scram, following an initial prompt drop. The reason for this is the following, a)
All prompt neutrons decay during the prompt drop, and the subsequent-rate of power change is dependent oniv on the half-life of the longest lived prompt gamma emitter.
b)
This rate of power change is dependent' on the mean lifetime of the i
shortest lived delayed neutron' precursors.
c)
This rate of power change is dependent on the mean lifetime of the-longest lived delayed neutron precursor.
d)
This rate of power change is dependent on the constant decay rate of prompt neutrons following a scram.
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Section A R Theory. Thermo & Fac. Operatino Characteristics Page 10
- QUESTION-(A.5)-
In an operating TRIGA reactor, the effect of the xenon poison is different from that due to samarium becauss:
a)
The xenon poison will begin to decay twelve to 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> after reactor-l-
shutdown, whereas samarium poison will peak and its effects will remain indefinitely after shutdown.
b)
The magnitude of the xenon poison effect is usually much smaller than that for samarium.
c)
While both poisons decay with their respective half lives after shutdown, the samarium poison decays with a shorter half life, d)
While both poisons decay after shutdown, xenon decays 12 times faster than samarium.
- QUESTION (A.6) l A reactivity insertion of.2.2 percent is added to the just critical TRIGA reactor.
What is the equivalent insertion in dollars?-
l a)
$0.21 b)
$1.40 1
c)
$2.00 1
d)
$3.00 i
+ - + -
m
Section A R Theory. Thermo & Fac. Oneratina Characteristics Page 11-
- QUESTION.
(A.7)
. DELETED Immediately after a pulse [approximately 1 millisecond]-where is the HOTTEST part of a fuel element?
a) in the fuel cladding itself b) at the edge of the fuel elements adjacent to the cladding c) at the thermocouples, midway between the fuel axial centerline and the fuel edge.
d) the center of the fuel elements
- QUESTION (A.8)
Which ONE of the following will be the resulting stable reactor period when a
$0.25 reactivity insertion is made into an exactly critical reactor core?
a) 48 seconds b) 30 seconds c) 18 seconds d) 10 seconds
a 4
m Section A R. Theory. Thermo & Fac. Operatino Characteristics' Page 12
- QUESTION (A.9)
The fundamental design parameter which permits a TRIGA reactor system to operate safely during either steady-state or_ pulsing conditions is the large prompt negative temperature coefficient of reactivity.
The largest contributor to this-design _ parameter is:
a) doppler effects b) core leakage c) core neutron spectrum-hardening 4
d) formation of core voids b
- QUESTION (A.10)
The TRIGA has been operating at full power for one month'when an unscheduled i
scram occurs.
Eight hours later, the reactor is again critical and. quickly raised to full power.
Considering xenon effects only, to maintain a constant power level for the next few hours, control rods must tue:
a) inserted b) maintained at the-present position 1
c) withdrawn 1
d) withdrawn, then inserted to the original position 1
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Section A' R Theory. Thermo & Fac, Operatina Characteristics Page 13
- QUESTION
'(A.ll)
At the beginning of a reactor startup, Keff is 0.90 with a count rate of 30 CPS.
Power is increased to a new, steady' value of 60 CPS. The new Keff is:
a) 0.91 b) 0.925 c) 0.95 d) 0.975
- QUESTION (A.12)
Which ONE of the following is true concerning the differences between prompt and delayed neutrons?
a.
Prompt neutrons account for less than one percent of the neutron population while delayed neutrons account for approximately ninety-nine percent of the neutron population b.
Prompt-neutrons are released during fast fissions while delayed neutrons are released during thermal fissions c.
Prompt neutrons are released during the fission process while delayed neutrons are released during the decay process-d.
Prompt neutrons are the dominating factor in determining ~the reactor period while delayed neutrons have little effect on the reactor period
l Section A' R Theory. Thermo'& Fac. Operatina Characteristics-
'Page 14
- QUESTION (A.13)
With'the reactor.on a constant period, which transient requires the LONGEST-time to occur?
A reactor power change of:
a.
5% of rated power - going from l% to 6% of rated power j
b.
10% of rated power - going from 10% to 20% of rated power-c.
15% of rated power - going from 20% to 35% of' rated power d.
20% of rated power - going from 40% to 60% of rated power
- QUEST'0N (A.14)
- The purpose of the installed neutron source is to:
a.
Compensate for neutrons absorbed in non-fuel materials in the core.
j b.
Generate a sufficient neutron population to start the : fission chain reaction for each startup, c.
Provide a means to allow reactivity changes to occur in a subcritical reactor.
1 d.
Generate a detectable neutron source level for monitoring reactivity changes in a shutdown reactor.
Section A R Theory. Thermo & Fac.'Operatina Characteristics
'Page'15 l
- QUESTION (A.15)
Which ONE of the following is a correct statement concerning the factors affecting control rod worth?
a.
Fuel burn up causes the rod worth for periphery rods to decrease.
b.
Fuel burn up causes the rod worth to increase in the center of the
- Core, c.
The withdrawal of a' rod causes the rod worth of the remaining inserted rods to increase.
d.
As Rx power increases rod worth increases.
- QUESTION (A.16)
Which statement illustrates a characteristic of Subcritical Multiplication?
a.
As Keff approaches unity (1), for the same increase in Keff,.a smaller increase in neutron population occurs.
b.
The number of neutrons gained per generation gets larger for each j
succeeding generation.
c.
The number of fission neutrons remain constant for each generation.
d.
For equal reactivity additions, it takes more time for the equilibrium
.I subcritical neutron population level to be reached as Keff. approaches one.
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Sect' ion A 'R Theory. Thermo'& Fac.'Oneratino-Characteristics Page 16
- QUESTION-(A.17)
. The' ' shutdown margin (SDM),~ upon. full insertion of all control rods following a reactor scram'from full power, is the SDM immediately prior to the. scram.
a.
Equal'to b.
Less than c.
Greater than d.
Independent of i
- QUESTION (A.18)
During a fuel loading, as the reactor approaches criticality, the value of 1/M is plotted. Which ONE of the following describes the slope of the 1/M-curve?
a.
decreases toward zero-b.
decreases toward'one c.
increases toward infinity L
I d.
increases toward one i
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'l Section A-R Theory.'Thermo &'Fac. Operatina Characteristics
-Page 17
- QUESTION (A.19)
W Which ONE of the following is correct concerning the Resonance Escape 3
Probability?.
a.
As the number of voids DECREASES, the Resonance Escape Probability-DECREASES.
b.
As the temperature of U-238' INCREASES, the Resonance Escape Probabilit'y DECREASES i
c.
As the Broadness of the U-238 resonance peaks _ INCREASES, the Resonance-Escape Probability INCREASES.
- i d.
As the moderature. temperature INCREASES, the Resonance Escape Probability INCREASES.
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(*** End of Section A ***)
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Section B Normal /Emero Procedures & Rad Con-Page 18'
- QUESTION (B.1)
' The UIUC TRIGA reactor is not permitted to be pulsed from power' levels above
- 250kw. The reason for this requirement is:
a)
The additional fast' neutron flux from the_ pulse could dangerously embrittle fuel cladding.
b) 1he additional heat from the pulse could.cause pool temperature limits to exceed operating specifications.
c)
The additional thermal neutron flux from the pulse could dangerously embrittle fuel cladding.
' d)
The additional heat from the pulse could cause fuel temperature to exceed 1000 *C.
- QUESTION (B.2)
The Technical Specification term " Shutdown Reactivity" describes:
a.
the time required for the rods to fully insert-b.
the departure from K-effective - 1.00
- c.
the amount of reactivity obtained by the removal of the control ' rods.
d.
the amount of reactivity required to meet the shutdown margin.
e i
t b
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Section B Normal /Emera Procedures & Rad Con Page'19
- QUESTION (B.3)-
Which one of the following will be cause to stutdown the UlUC TRIGA reactor which is operating at 250 kw for training?
a.
Two experiments, each worth $1.35, are attached to a rod and suspended in the reactor tank 1 foot above the core.
b.
The ventilation exhaust blower is taken out of service for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to lubricate the filter diversion valve.
c.
The total of the absolute values of the reactivity worth of all experiments in the reactor is $3.25 d.
A fuel temperature detector is bypassed for 15 minutes to perform a channel check.
- QUESTION (B.4)
Which one of the following precludes operating the reactor in the PULSE mode?
a.
The reactivity worth of the transient rods is set such that'their reactivity worth upon withdrawal is $4.20.
b.
Temperatures of the fuel immediately prior to the pul; :
"B"-hexagonal - 225 degrees. Celsius "C"-hexagonal - 230 degrees Celsius "D"-hexagonal - 195 degrees Celsius c.
The shutdown margin with the highest rod fully withdrawn is $0.75 d.
The drop time of the shim rod from the fully withdrawn position to 90 percent of full reactivity insertion is 2. seconds
Section B Normal /Emera Procec ce's & Rad Con page'20
- QUESTION (B.5)
Which ONE of the following is the definition for a CHANNEL CHECK 7 a,
' Adjustment of the-output of the channel to within specific tolerances based on a known input.
b.
Qualitative comparison of multiple indications of the same parameter to verify acceptable performance of a channel.
Introduction of a signal into a channel to. verify operability c.
(particularly trip setpoints).
d.
A visual check of a channel to insure its output is within an acceptable range.
- QUESTION (B.6)
A reactor sample has a disintegration rate of 5 x 10'2 disintegrations per second.
Each disintegration emits a.6 Mev gamma.
What is the dose rate expected five (5) feet from the above sample (assume point source)?
a.
7 R/hr b.
19 R/hr c.
135 R/hr d.
162 R/hr l
l c:
k.
e Section'B Normal /Emera Procedures & Rad Con Page'21
- QUESTION
' (lB. 7 ).
You have been assigned to decrease the dose rate being emitted by a point-source. The dose rate is due to 1.5 Mev gamma. What thickness of lead will~
- be required.to decrease.the dose rate.by a factor of 10?-
2 Given:
Mass attenuation coefficient for lead 01.5 Mev - 0'.051 cm / gram 3
and the density of lead is 11.4 gram /cm a.
0.2 cm b.
2 cm c.
4 cm d.
8 cm i
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- QUESTION.
(B.8)
Which ONE of the following does NOT require the notification of. " UNUSUAL ~
EVENT"?
a.
The reactor fails to scram when the reactor operator. depresses the manual scram button.
b.
The reactor operator, fearing for'the safety of the. reactor, initiated a a
manual-reactor scram when he felt a tremor that was caused by an unexpected earthquake o
c.
A reactor operator received a localized dose of 27 rems to his. feet.
j d.
A radical group of Students Against Nuclear Energy (SANE) is ~ marching
'l toward the Reactor Facility.
It appears that some are. carrying weapons.
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Section B Normal /Emera Procedures & Rad Con Page 22
- QUESTION (B.9)
An area would be classified as a radiation area if:
a.
continuous exposure will result in a dose less than 2 mrem in an hour or less than 100 mrem in 5 consecutive days, b.
a major portion of the body could receive more than 5 mrem in an hour.
c.
a major portion of the body could receive 100 mrem in 7 consecutive days.
d.
a major portion of the body could receive more than 100 mrem in an hour.
L t
- QUESTION (B.10)
Which ONE of the following represents the 10 CFR 20 exposure limits for the skin?
a.
1.25 Rem /qtr b.
3 Rem /qtr t
c.
7.5 Rem /qtr d.
18.75 Rem /qtr l
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J Section B -Normal /Emera Procedures & Rad Con
.Page 23
~
- QUESTION-(B.11)
-Which one of the following meets the conditions-for a " Reactor Shutdown"?
-i a.
When the power to the control rod magnets and solenoids has been turned off and the key removed from the console.
b.
When the reactor.is subcritical by at least one' dollar of reactivity, and an SR0 is in charge of any work in progress.
c.
When the operable control rods are such as to make the reactor subcritical by at 'least 50 cents at all times even with the most reactive rod stuck out.
d.
When no experiments are being inserted into.the reactor core or no maintenance on-the control rods is in progress.
- QUESTION (B.12)
What is the MINIMUM exposure monitoring requirement for escorted visitors-to the' Reactor Laboratory?
l a.
1 film badge per person-b.
I neutron-gamma sensitive pocket dosimeter for the tour guide c.
I dosimeter for every 10 members of the group d.
2 dosimeters for every 15 members of the group i
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th
?
Section'B -Normal /Emero Procedures & Rad Con Page 24-
- QUESTION (B.13) e Which ONE aflthe following is the MINIMUM amount of time a licensed operator..
must perform his/her licensed duties to maintain proficiency?
a.
Four hours per month b.
Four hours per quarter c.
Six hours per month-d.
Six hours per quarter
^
1
- QUESTION (B.14)
An irradiated sample having a half-life of 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> provides a dose rate' of 200 -
mr/hr at 3 ft. Approximately how far from the sample must a' Radiation Area sign be posted?
a.
5 ft, b.
8 ft.
c.
20 ft.
d.
50 ft.
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Section B-Normal!Emera Procedures & Rad Con Page 25-
- QUESTION (B.15)
A survey instrument with_a window probe was used to measure an irradiated experiment. The results were 100 mrem /hr window open 40 mrem /hr window-closed.
What was the gamma _ dose?
a.
'140 mrem /hr b.
100 mrem /hr c.
60 mrem /hr d.
40 mrem /hr i
- QUESTION (B.16)
Whenever an abnormal condition occurs, the reactor operator must:
a.
stop all rod withdrawal and notify the.SR0 b.
scram the reactor c.
shut down the reactor d.
determine the cause and notify the SR0 k
Section B ' Normal /Emera Procedures & Rad Con
.Page 26
- QUESTION (B.17)
The' primary source of radiation release to the environment'through the ventilation system during reactor operation:is:
a.
gamma emission from activated structural members b.
Argon-41 from the activation of air c.
Nitrogen-16 from pool water evaporation d.
Alpha-Beta radiation from activation of air
- QUESTION (B.18)
The carrier in the MRL Pneumatic-System does not return at the end of the irradiation time and cannot be returned immediately by manual operation. The reactor operator must:
a.
perform a controlled reactor shutdown immediately, b.
scram the reactor and initiate repair of the. system.
c.
performed a controlled reactor shutdown.if the sample cannot be. returned within the next'four1(4) hours, d.
reduce power to less than 250 kw and initiate an' investigation of the-problem.
l
Section'B Normal /Emera Procedures-& Rad Con Page 27
- QUESTION (B.19)
Which property of water must be measured prior to discharging the' retention tank into the sewer system?
a.
pH and concentratior b.
temperature and activity c.
activity and concentration d.
temperature and concentration
- QUESTION (B.20)
Assume a' 10 curie point source of a 2 MeV gamma emitting radionuclide.
The unshielded dose rate (R/hr) at 10 feet from the source is:
a) 120 b) 2 c) 1.2 d) 0.2
(*** End of Section B ***)
i l
Section C Plant and' Rad MonitorinaSystems-
_ Page 28
- QUESTION (C.1)
The UIUC TRIGA is being operated at a power of 1 kilowatt in servo mode (Automatic). At this power level, the servo system adjusts the power demanded by which power. indicating channel?
a)
NPP1000 b)
NM1000 i
c)
NP1000 d)
The higher of NM1000 and NP1000
- QUESTION (C.2)
When you switch from steady state mode to pulse mode on the TRIGA console's mode control panel, the following_ changes occur to the reactor safety system:
a)
b)
DAC watchdog scram is bypassed.
c)
NP1000 % power and HV scrams are bypassed.
d)
One of the two fuel temperature scrams is bypassed.
F w
a s.
Section C Plant-and Rad MonitorinaSystems Page 29
- QUESTION (C.3)
Which-one of the following statements regarding reactor Period is TRUE?-
a)
The UIUC TRIGA. Technical Specifications require that the Period Trip'be set at greater than 3 seconds.
b)
The Period circuit provides an interlock.that prevents the upward movement of the manually driven control rods when reactor period-is too short.
c)
The Period Trip is allowed to be bypassed only when the mode switch is' in Pulse Mode.
d)
The Period Circuit will prevent the system from entering the Pulse Mode if reactor period is 20 seconds.
- QUESTION (C.4)
The reactor has been at 65% power for over 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The reactor. operator placed the controls in Automatic and the Lazy Susan is loaded with samples in polyethyleno containers. Which one of the following statements describes th-behavior of the control rods during this experiment?
a.
The selected rods would be moved downward due to -the increase in indicated power level and later, as the last sample moves past the chamber supplying power information, the rods would be returr.ed to their original position.
b.
The selected rods would be moved upward due to the decrease in indicated
~
power level and later, as the last sample moves past the chamber supolying power information,'the rods would be moved downward.
c.
The samples containers will add positive reactivity causing reactor-power to increase. The resulting fuel. temperature increase _ reduces reactor power back to the % Demand setpoint and the control rods will remain at their original position.
d.
The selected rods would be moved downward due to the increase in reactor power.
The resulting fuel temperature increase reduces reactor power and at the end of the experiment, the control rods will be at a lower position.
i 1
i~
Section C Plant and Rad MonitorinaSystems Page 30
- QUESTION (C.5)
During Square Wave. operations, which one of neutron channels supplies power information to the Square Wave software?
a)
.NPP1000 b)
NM1000 c)
NP1000 d)
The higher of NM1000 and NP1000 i
- QUESTION (C.6)
Which one of the following conditions will NOT allow the reactor control system to enter the Square Wave Ready State?
a.
Reactor power is less-than 1 Kw.
b.
The Shim rod is at the UP limit.
c.
Reactor period is less than 26 seconds d.
The Square Wave Mode button.is pushed in prior to positioning the ATR receiver e-y
24 i
Section C plant and Rad MonitorinoSystems Page 31
- QUESTION (C ~. 7 )
At _ the UIUC reactor, which one of the following areas has the poorest shielding-(higher dose).
a.
Juncture of the 3-foot upper portion and the 7.5-foot section.
b.
Outer face of beam port with all shielding in place.
i c.
Outer face of thermal column door.
d.
Directly at core level; outer face of the concrete shielding.
- QUESTION (C.8)
The purpose of the " Secondary flow interlock" is to:
a.
ensure that both the primary and secondary cooling systems are in service when operating above 1.0 Mw.
b.
ensure that' secondary system pressure is not less than primary system pressure.
c.
prevent a loss of heat sink due.to the loss of secondary cooling water while the primary cooling system is in service.
d.
prevent thermal shocking the secondary heat exchanger by supplying it with secondary cooling water prior to placing the primary cooling -in service.
7 Section C-Plant-and Rad MonitorinaSystems Page 32
- QUESTION (C.9)
What assembly component provides a "stop" command signal to the rod drive mechanisms at both the top:and bottom of rod travel?
a.
Electromagnet c.
Pinion d.
Limit switches
- QUESTION (C.10)
Which ONE of the following statements regarding the console lights for the rod
'l control system is FALSE?
1 a.
The DOWN light indicates that the control rod and rod drive 'are at their lower limits.
b.
The UP light indicates that the control rod ard rod drive are at their upper limits.
]
c.
While driving a rod up, the operator notices that the CONT light went' I
out.
If he releases the UP button, the rod drive will return to the down position.
i i
d.
Depressing the magnet light switch for an individual rod causes the rod to scram and that rod magnet light to go out until the switch is q
released.
j
Section C Plant and Rad MonitorinoSystems Page:33
- QUESTION (c.11)
Air contamination greater than the setpoint has been detected in the Reactor Room. Which-0NE of the following is the correct response by the ventilation system?
i a.
The exhaust system will automatically stop.
Dampers will swap to the charcoal. filters. The auxiliary exhaust fan will startLand purge the i
reactor room at 400 cfm.
b The' exhaust system will shift to low-speed.
Dampers will direct air-through the charcoal filters and purge the reactor: room at 400 cfm.
i c.
Dampers will direct air through the charcoal filters purging the room at~
400 cfm.
d.
The exhaust system will automatically stop.
Dampers will swap to the charcoal filters. The exhaust fan will restart and purge the room at~
1200 cfm.
- QUESTION (C.12)
With a normal system line-up and all automatic functions operating, which one of the following does NOT describe one of the possible results of opening the Core Spray Emergency Makeup valve (V-8) located outside the -control room?
a.
3 GPM of spray flow is provided.from the demineralizers.
I b.
At 5.3 inches above the 0" reference level, 5-8 GPM of spray. flow is -
provided from the demineralizers.
c.
City water is directly applied to the spray system, i
d.
At 17.0 inches above the 0" reference level, 3 GPM of spray flow is provided from the demineralizers.
w
1 Section C Plant'and Rad MonitorinoSystems
.Page 34
'* QUESTION (C. '13 )
j The TRIGA reactor is being operated in the square wave mode.
The adjustable transient rod is fired and power has stabilized at 500kW.
~
Which ONE of the following conditions would cause an automatic reactor scram.
a.
Primary coolant pump trip.
b.
A reactor period of 2 seconds occurs.
t c.
NM1000 High Voltage power supplies fail.
i d.
NP1000 channel fails upscale.
f i
i
- QUESTION (C.14)
Flow through'the purification loop is limited to 2-3 GPM in order to:
a.
prevent clogging the filter at the top of the resin tank
{
b.
ensure adequate-flow through the heat exchanger
{
c.
avoid excessive turbulence in the flow from the core d.
prevent pump cavitation
]
i
- 4-Section C Plant and Rad MonitorinaSystems Page 35
- QUESTION (C.15)
Which ONE of the following describes why lead is used in the outer core region:
a.
To minimize gamma heating of the concrete.
b.
To provide a radiological shield for lab workers.
c.
To improve fuel efficiency.
d.
To prevent neutron leakage from the core.
- QUESTION (C.16)
The TRIGA reactor is. operating at 550 KW with a primary forced cooling system-flow rate of 1500 gpm.
Subsequently, the primary centrifugal. pump trips off and cannot be restarted. Which ONE of the following will occur:
a.
The primary forced cooling system throttle valve will fully open to provide additional flow.
b.
The secondary flow throttling valve will fully open to provide additional cooling of the primary flow, c.
The reactor will scram when forced cooling system flow decreases to less
~
than 550 gpm.
d.
The isolation valves close, flow reversal is initiated and the core is cooled by convection.
.=
E 1
Section C = Plant and Rad MonitorinaSystems Page 36-I
- QUESTION (C.17)
Which ONE of the following situations _ will allow movement of the control rods? -
a.
The operator depress the UP push button for the shim rod directly-following a reactor trip on a loss of flow signal.
b.
The operator attempts to rapidly raise reactor power from 15-watts by simultaneously pushing the Up pushbuttons for the shim rod and the regulating rod.
c.
The operator attempts to raise reactor power from 15 watts following the loss of the NM1000 High Voltage power supplies by pushing the UP pushbutton for-the regulating rod.
d.
The operator attempts to rapidly lower reactor power from 250 Kwatts by simultaneously pushing the DN pushbuttons for the shim rod and the regulating rod.
i j
- QUESTION (C.18)
Which ONE of the following describes the operation of the adjustable transient control rod:
The Adjustable Transient Control Rod is -
a.
controlled by adjusting the position of the cylinder.
b.
inserted in the core except when air is removed from the cylinder.
c.
pneumatically inserted and withdrawn by adjusting the pressure on the piston.
d.
controlled by adjusting the position of the piston.
i Section C Plant and Rad MonitorinaSystems Page 37 1
- QUESTION (C.19)
Which ONE of the following describes the operation of the core isolation valves:
a.
When the isolation valves receive a signal to close, a metering valve retards the rate of air leaving the piston to provide a closing time of greater than 10 seconds.
b.
Upon the loss of air pressure, a metering valve retards the rate of air leaving the piston to give the valve a closing time of about 5 seconds.
c.
A solenoid valve on the actuator closes the isolation valves when 70' psi is supplied from the pneumatic system.
d.
At 20 inches above the top grid plate of the core, a high level trip sensor sends a signal to open the isolation valves to prevent the overflow of the reactor tank.
I
- QUESTION (C.20)
With the TRIGA reactor operating steady state at 250 kw on natural circulation Which one of the following statements describes the expected change in indicated temperature when changing from natural to forced convection cooling.
i a.
The indicated temperature remains the same due to the small net heat input change, b.
The indicated temperature increases since the peak temperature is j
measured in lieu of average temperature.
c.
The indicated temperature decreases due to the decreased fuel temperature from the increased flow.
d.
The indicated temperature will remain the same if the control rods position is not changed.
(*** End of Section C ***)
A'.
RX THEORY, THERM 0 & FAC OP CHARS Page'38
- ANSWER-
'(A.1)
~b
- REFERENCE (A.1)
UIUC Trng Materials pg. 1-5
- ANSWER (A.2) a
.i
- REFERENCE (A.2)
SAR Section III pg. III-35 Equation Sheet
- ANSWER (A.3) c
- REFERENCE (A.3)
UIUC Trng Materials pg. 1-23
- ANSWER (A.4) c-
- REFERENCE (A.4)
UIUC Trng Materials pg. 1-7 / pg. 1-60 #6
- ANSWER (A.5) a
- REFERENCE (A.5)
UIUC Trng Materials pg. 1-32
p- :.-
A.
RX' THEORY, THERM 0 & FAC OP CHARS Page 39
- ANSWER (A.6) d
- REFERENCE (A.6)
- UIUC Trng. Manual pg. 1-19 (8,,, = 0.0073)
- ANSWER (A.7)
DELETED b
- REFERENCE (A.7)
SAR Pg. III-41
- ANSWER (A.8) b
- REFERENCE (A.8)
T - (8,y - p)/(p A)
T - (.0~073
.001825)/(.1 x.001825)
T - 30 seconds
- ANSWER (A.9) c
- REFERENCE (A.9)
UIUC TRIGA Trng. Manual pg.1-45 General Atomics Trng. Manual Sect. 6.3.3
- ANSWER (A.10) a
- REFERENCE (A.10)
.2 UIUC TRIGA Trng. Manual pg.1-31 e
m_
A.
RX THEORY, THERM 0 & FAC OP CHARS Page 40
- ANSWER (A.11) c
- REFERENCE (A.11)
(CR /CR ) - (1-Keff )/(1-Keff )
2 2
(60/30)3 (0.90)(13Keff) 2 Keff, = 0.95
- ANSWER (A.12) c
- REFERENCE (A.12)
UIUC TRIGA Trng. Manual pg.1-19
- ANSWER (A.13) a
- REFERENCE Pf-Poe"") ( A.13)
= t=(ln Pf/Po) 7 in(6/1) > int 20/10) > in(35/20) > In(60/40)
- ANSWER (A.14) d
- REFERENCE (A.14)
UIUC TRIGA Trng. Manual pg.1-22
- ANSWER (A.15) c l-
- REFERENCE (A.15) l UIUC TRIGA Trng. Manual pg.1-6 Rod Worth cc ( "#)2 Oavg
A.
RX THEORY,. THERM 0 & FAC OP-CHARS Page 41
- ANSWER (A.16) d.
- REFERENCE (A.16)
UIUC TRIGA Trng. Manual pg. 1-3
- ANSWER (A.17) a
- REFERENCE (A.17)
UIUC T.S. Definition of SDM and Shutdown Reactivity.
- ANSWER (A.18) a
- REFERENCE (A.18)
UIUC Trng. Manual pg.1-26
- ANSWER (A.19) b
- REFERENCE (A.19)
NE390, pg 1-22 UI NRC exam 11/90
(*** End of Section A ***)
I
4 k'
l B.
NORMAL /EMERG' PROCEDURES & RAD CON Page 42 l
- ANSWER (B.1) d
-
- REFERENCE (B.1)
UlUf. T.S. 3.1.e Basis 3
- ANSWER (B.2) d.
- REFERENCE (B.2)
Volume 1, Training Materials and System Diagrams, Page 1-33
- ANSWER
.(B.3) a
- REFERENCE (B.3)
- ANSWER (B.4).
d
- REFERENCE (B.4)
Tech. Specs 3.3 and 3.1
- ANSWER (B.5) b
- REFERENCE (B.5)
Tech Specs Definitions pg. 3
.O
1 B.
NORMAL /EMERG PROCEDURES & RAD _ CON Page 43
- ANSWER (B.6) b.
- REFERENCE (B.6 l Curie - 3.7x10} dps==> (5 x 10 12 dps)/3.7 X 10'0 dps-135 Ci DR= 6Ci E-(n) l 2
--> DR - (6 x 135 x.6)/5 - 19 R/hr 2
R
- ANSWER (B.7)
C
- REFERENCE (B.7) 2 3
p - (0.051 cm /g) x 11.4 g/cm - 0.5814 cm
I - I, e*
--> In (0.1) - -(0.5814) %
X - 2.3026/0.5814 - 3.9672
=
4
- ANSWER (B.8) c
- REFERENCE (B.8) 1 Emergency Plan pg. 10
)
.J l
- ANSWER (B.9) j b
i
- REFERENCE (B.9) 10CFR20,202
- ANSWER (B.10)
C
)
- REFERENCE- (B.10) 10CFR20.101
. =.
B.
NORMAL /EMERG PROCEDURES & RAD CON Page 44
- ANSWER
-(B.11) b
- REFERENCE (B.11).
Tech. Specs Definitions pg. 1
- ANSWER (B.12) c
- REFERENCE (B.12)
UIUC Rules and Regulations (Procedure #1)
- ANSWER (B.13) b
- REFERENCE (B.13)
-10CFR55
- ANSWER (B.14) c
- REFERENCE (B.14) 10CFR20
- ANSWER (B.15) a
- REFERENCE (B.15)
Window closed shield beta.
40 mrem /hr must be gamma Y
1 1
a ~
.: > o i
B.
NORMAL /EMERG PROCEDURES &-RAD CON Page 45
- ANSWER (B.16).
c
- REFERENCE (B.16)
Potential Malfunction of Systems or Components Procedure
- ANSWER (B.17) b-
- REFERENCE (B.17) i
. Safety Analysis Report,Section XI.C.2
- ANSWER (B.18) a l
- REFERENCE (B.18)
MRL Pneumatic Transfer (Rabbit) System Procedure 1
- ANSWER (B.19) c
- REFERENCE (B.19)
Volume 1, Training Materials and System Diagrams, Page 1-42
- ANSWER (B.20) c
- REFERENCE (B.20)
DR - 6CiE(n) = 6 x 10 x 2 / 100 = 1.2 R'
I
(***.End of Section B.***)
l l
-V-F 4
i.
C.
PLANT AND RAD MONITORING SYSTEMS Page 46:
- ANSWER.
(C.1) b
- REFERENCE (C.1)
UIUC Digital Control Console Manual pg 1-20 and-Fig. 22 pg.1-40
- ANSWER (C.2) c
- REFERENCE (C.2)
U10C Digital Control Console Manual Fig. 20 Scram Loop f-
- ANSWER (C.3)
-d
- REFERENCE (C.3)
UIUC Digital Control Console Manual pg. 6-1 Prereq. 3
- ANSWER (C.4) b
- REFERENCE (C.4)
UIUC Training Manual, Modes of Operation, pg. 1-51 & 1-52'
- ANSWER (C.5) a i
- REFERENCE (C.5)
UIUC Digital Control Console Manual pg 1-41 R
i l
i l
l
}
C.
PLANT AND RAD MONITORING SYSTEMS Page 47.
- ANSWER (C.6)
C
' t
- REFERENCE -(C.6)
UIUC Digital Console Operators Manual sect. 5 pg. 5-3
- ANSWER (C.7) a
- REFERENCE (C.7)
Training Manual pg 1-43 (shielding)
FSAR table XI-I
- ANSWER (C.8) b
- REFERENCE (C.8)
UIUC Training Manual pg. 1-40
- ANSWER (C.9) d
- REFERENCE (C.9)
Training Manual pgs.1-48 and' 1-50
- ANSWER (C.10) b i
- REFERENCE (C.10)'
UIUC Training Manual pg. 1-48 & 1-50 o
6
)
.m
C.
PLANT AND RAD MONITORING SYSTEMS.
.Page 48
- ANSWER
(.C.11) c
- REFERENCE (C.11)
Training Manual pg. 1-42
- ANSWER (C.12)
C 7
- REFERENCE (C.12)
FSAR Sect. VI-B.2 and FIG. I
- ANSWER (C.13) i b/d
- REFERENCE (C.13)
UIUC Operation and Maintenance Manual pg. 1-41 and Fig. 19
- ANSWER (C.14) a
- REFERENCE (C.14)
Volume 1, Training Materials and System Diagrams, Page 1-38 T
- ANSWER (C.15) a
- REFERENCE (C.15)
NE390R, pg. 1-36.
l l
-i Y
(. '
C.
PLANT AND RAD MONITORING SYSTEMS Page 49
- ANSWER (C.16) d
- REFERENCE (C.16)
NE390R, pg. 1-37 and 1-39.
FSAR Sect. IV-C.3.a. pg. IV-43
- ANSWER (C.17) d
- REFERENCE (C.17)
UIUC Digital Console Trng Manual pg.1-39 and Table 2-1 pg. 2-5
- ANSWER (C.18) a
- REFERENCE (C.18)
FSAR, pg. VII-17.
- ANSWER (C.19) b
- REFERENCE (C.19)
FSAR, pg. VII-24 and VII-20
- ANSWER (C.20) b
- REFERENCE (C.20)
UIUC Training Manual pg. 1-46
(*** End of Section C ***)
L b
.. -. _ - _. - - -. -.. _. -