ML23109A161
| ML23109A161 | |
| Person / Time | |
|---|---|
| Site: | Reed College |
| Issue date: | 04/21/2023 |
| From: | Travis Tate NRC/NRR/DANU/UNPO |
| To: | Newhouse J Reed College |
| References | |
| 50-288/23-02 50-288/OL-23 | |
| Download: ML23109A161 (1) | |
Text
Jerry Newhouse, Reactor Director Reed Reactor Facility 3203 SE Woodstock Boulevard.
Portland, OR 97202
SUBJECT:
EXAMINATION REPORT NO. 50-288/OL-23-02, REED COLLEGE
Dear Jerry Newhouse:
During the weeks of March 13 and March 20, 2023, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Reed College research reactor.
The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.
In accordance with Title 10 of the Code of Federal Regulations, Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact John Nguyen at (301) 415-4007 or via email at John.Nguyen@nrc.gov.
Sincerely, Travis L. Tate, Chief Non-Power Production and Utilization Facility Oversight Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation Docket No. 50-288
Enclosures:
- 1. Examination Report No. 50-288/OL-23-02
- 2. Written Examination cc: w/o enclosures to GovDelivery Subscribers April 21, 2023 Signed by Tate, Travis on 04/21/23
ML23109A161 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME JNguyen MDeSouza NJones TTate DATE 4/21/2023 4/21/2023 4/21/2023 4/21/2023 U.S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-288/OL-23-02 FACILITY DOCKET NO.:
50-288 FACILITY LICENSE NO.:
R-112 FACILITY:
TRIGA EXAMINATION DATES:
March 13 - March 22, 2023 SUBMITTED BY
__________John Nguyen_______
_04/12/2023__
John T. Nguyen, Chief Examiner Date
SUMMARY
During the weeks of March 13 and March 20, 2023, the NRC administered operator licensing examinations to eleven Reactor Operator (RO) candidates. All candidates passed all applicable portions of the examinations.
REPORT DETAILS 1.
Examiner:
John T. Nguyen, Chief Examiner, NRC 2.
Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 11/0 N/A 11/0 Operating Tests 11/0 N/A 11/0 Overall 11/0 N/A 11/0 3.
Exit Meeting:
Jerry E. Newhouse, Director, Reed College Toria Ellis, Reactor Operations Manager, Reed College Michele C. DeSouza, Chief Examiner, NRC John T. Nguyen, Chief Examiner, NRC Per discussion with the facility, prior to administration of the written examination, adjustments were accepted. At the conclusion of the meeting, the NRC examiner thanked the facility for their support in the administration of the examinations. The examiner also discussed the candidates weaknesses observed during the operating test to include radiation sources and hazards, operational limits and requirements, nuclear instrumentation systems, radiation detection systems, and reactor ventilation system.
U.S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
Reed College REACTOR TYPE:
TRIGA DATE ADMINISTERED:
03/16/2023 CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
Answers are to be written on the Answer sheet provided. Attach all Answer sheets to the examination. Point values are indicated in parentheses for each question. A 70 percent in each category 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 20.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 20.00 33.3 B.
NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL COREED COLLEGEOLS 20.00 33.3 C.
FACILITY AND RADIATION MONITORING SYSTEMS 60.00 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature
Category A - Reactor Theory, Thermodynamics, & Facility Operating Characteristics A N S W E R S H E E T Multiple Choice (Circle or X your choice)
If you change your Answer, write your selection in the blank.
A01 a b c d ___
A02 a ___ b ___ c ___ d ___ (0.25 each)
A03 a b c d ___
A04 a b c d ___
A05 a b c d ___
A06 a b c d ___
A07 a b c d ___
A08 a b c d ___
A09 a b c d ___
A10 a b c d ___
A11 a b c d ___
A12 a b c d ___
A13 a b c d ___
A14 a b c d ___
A15 a b c d ___
A16 a b c d ___
A17 a b c d ___
A18 a b c d ___
A19 a b c d ___
A20 a b c d ___
(***** END OF CATEGORY A *****)
Category B - Normal/Emergency Operating Procedures and Radiological Controls A N S W E R S H E E T Multiple Choice (Circle or X your choice)
If you change your Answer, write your selection in the blank.
B01 a b c d ___
B02 a ___ b ___ c ___ d ___ (0.25 each)
B03 a b c d ___
B04 a ___ b ___ c ___ d ___ (0.25 each)
B05 a b c d ___
B06 a b c d ___
B07 a b c d ___
B08 a b c d ___
B09 a b c d ___
B10 a b c d ___
B11 a b c d ___
B12 a b c d ___
B13 a b c d ___
B14 a b c d ___
B15 a b c d ___
B16 a ___ b ___ c ___ d ___ (0.25 each)
B17 a b c d ___
B18 a b c d ___
B19 a b c d ___
B20 a b c d ___
(***** END OF CATEGORY B *****)
Category C - Facility and Radiation Monitoring Systems A N S W E R S H E E T Multiple Choice (Circle or X your choice)
If you change your Answer, write your selection in the blank.
C01 a b c d ___
C02 a b c d ___
C03 a ___ b ___ c ___
(0.33 each)
C04 a b c d ___
C05 a b c d ___
C06 a b c d ___
C07 a ___ b ___ c ___ d ___ (0.50 each)
C08 a b c d ___
C09 a b c d ___
C10 a b c d ___
C11 a ___ b ___ c ___ d ___ (0.50 each)
C12 a b c d ___
C13 a b c d ___
C14 a b c d ___
C15 a b c d ___
C16 a b c d ___
C17 a b c d ___
C18 a b c d ___
(***** END OF CATEGORY C *****)
(********** END OF EXAMINATION **********)
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
1.
Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
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 neither received nor given assistance in completing the examination. This must be 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.
4.
Use black ink or dark pencil only to facilitate legible reproductions.
5.
Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each Answer sheet.
6.
Mark your Answers on the Answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.
7.
The point value for each question is indicated in [brackets] after the question.
8.
If the intent of a question is unclear, ask questions of the examiner only.
9.
When turning in your examination, assemble the completed examination with examination questions, examination aids and Answer sheets. In addition turn in all scrap paper.
10.
Ensure all information you wish to have evaluated as part of your Answer is on your Answer sheet. Scrap paper will be disposed of immediately following the examination.
11.
To pass the examination you must achieve a grade of 70 percent or greater in each category.
12.
There is a time limit of three (3) hours for completion of the examination.
EQUATION SHEET
=
+ [
]
DR - Rem, Ci - curies, E - Mev, R - feet 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lb 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 1 BTU = 778 ft-lb
°F = 9/5 °C + 32 1 gal (H2O) 8 lb
°C = 5/9 (°F - 32) cP = 1.0 BTU/hr/lb/°F cp = 1 cal/sec/gm/°C
2 2
max
P 1
sec 1.0
eff
te P
P 0
eff K
S S
1
sec 10 1
4
eff SUR 06 26
2 1
1 1
2 1
eff eff K
CR K
CR
2 2
1 1
CR CR 2
1 1
1 eff eff K
K M
1 2
1 1
CR CR K
M eff
)
(
0 10 t
SUR P
P
0 1
P P
eff eff K
K SDM
1
2 1
1 2
eff eff eff eff K
K K
K
693
.0 2
1 T
eff eff K
K 1
t e
DR DR
0
2 6
R n
E Ci DR 2
2 2
2 1
1 d
DR d
DR
1 2
1 2
2 2
Peak Peak
T UA H
m T
c m
Q P
Reed College Operator Licensing Examination Week of March 13, 2023
Category A - Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.01
[1.0 point]
Delayed neutrons contribute more to reactor stability than prompt neutrons because they are born at a
__ kinetic energy and ______ the average neutron generation time.
a.
higher/ increase b.
lower/ increase c.
higher/ decrease d.
lower/ decrease QUESTION A.02
[1.0 point, 0.25 each]
Select INCREASE/DECREASE of the following values due to the effects of moderator temperature increase.
a.
Control rod worth b.
Fast non-leakage probability c.
Resonance escape probability d.
Thermal non-leakage probability QUESTION A.03
[1.0 point]
Which ONE of the following is the correct reason why a reactor gets a negative 80-second period following a reactor scram?
a.
The interaction between U235 and source neutrons during reactor scram.
b.
The fuel temperature coefficient adds positive reactivity as a result of the decrease in fuel temperature following a scram.
c.
The amount of negative reactivity added during a scram is greater than the shutdown margin.
d.
The decay constant of the longest-lived precursor.
Category A - Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.04
[1.0 point]
Reactor power is increasing by a factor of 10 every 2 minutes. The reactor period is:
a.
52 seconds b.
30 seconds c.
21 seconds d.
11 seconds QUESTION A.05
[1.0 point]
During a reactor power increases, the delayed neutron fraction, -effective:
a.
remains unchanged.
b.
increases because prompt neutrons are being produced at a slower rate.
- c.
increases because delayed neutron precursors are being produced at a higher rate.
d.
decreases because delayed neutrons are being produced from precursors that are formed at the previous power level while prompt neutrons are produced immediately at the higher power levels.
QUESTION A.06
[1.0 point]
The moderator negative temperature coefficient for a reactor is -0.00082 k/k/oF. What is a worth of reactivity change if a moderator pool temperature decreases of 5oF?
a.
-0.0082 k/k b.
0.0082 k/k c.
-0.0041 k/k d.
0.0041 k/k
Category A - Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.07
[1.0 point]
A reactor is subcritical with a Keff of 0.955. A positive reactivity of 0.045 k/k is inserted into the core, which ONE of the following best describes the reactor kinetics?
a.
The reactor is sub-critical.
b.
The reactor is critical.
c.
The reactor is super-critical.
d.
The reactor is prompt critical.
QUESTION A.08
[1.0 point]
Reactor #1 increases power from 10% to 20% with a period of 25 seconds. Reactor # 2 increases power from 80% to 100% with a period of also 25 seconds. Compared to Reactor #1, the time required for the power increase of Reactor #2 is:
a.
longer than #1 b.
the same as #1 c.
twice that of #1 d.
shorter than #1 QUESTION A.09
[1.0 point]
The primary purpose of _____________ material is thermalizing neutrons.
a.
Fissile b.
Reflector c.
Fertile d.
Moderator
Category A - Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.10
[1.0 point]
What is the meaning of any point on a differential rod worth curve?
a.
The amount of reactivity that one unit (e.g. one inch, one percent) of rod motion would insert at that position in the core.
b.
The zero reactivity when the rod is on the bottom and the positive reactivity being added as the rod is withdrawn.
c.
The cumulative area under the differential curve starting from the bottom of the core.
d.
The negative reactivity added as the rod is inserted.
QUESTION A.11
[1.0 point]
If the multiplication factor, k, is increased from 0.70 to 0.90, the amount of reactivity added is:
a.
0.12 k/k b.
0.200 k/k c.
0.23 k/k d.
0.32 k/k QUESTION A.12
[1.0 point]
Which ONE of the following is the stable reactor period which will result in a power rise from 15% to 50% power in 6 seconds?
a.
2 seconds b.
5 seconds c.
7 seconds d.
13 seconds
Category A - Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.13
[1.0 point]
All atoms of a given element have the same _______.
a.
Atomic Mass b.
Mass Number c.
Atomic Number d.
Number of Neutrons QUESTION A.14
[1.0 point]
A multiplication factor during a fuel loading is 0.8, which produces the stable neutron count rate of 5000 neutrons per second (N/sec). What is a source strength?
a.
100 N/sec b.
400 N/sec c.
1000 N/sec d.
4000 N/sec QUESTION A.15
[1.0 point]
The neutron count rate is 1000 cps. An experimenter inserts an experiment into the core, and the count rate decreases to 600 cps. Given the initial Keff of the reactor was 0.92, what is the worth of the experiment?
a.
= + 0.02 b.
= - 0.02 c.
= - 0.07 d.
= + 0.07
Category A - Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.16
[1.0 point]
Which ONE of the following is the MINIMUM amount of reactivity that makes the Reed College (finite) critical reactor to be a prompt critical reactor? This MINIMUM amount is equal to:
a.
1.0 k/k b.
A shutdown margin of $1.0 c.
eff d.
1 Keff QUESTION A.17
[1.0 point]
The following data was obtained during a reactor fuel load.
Step No. of Elements Detector A (count/sec) 1 0
100 2
4 120 3
8 140 4
12 200 5
15 400 The TOTAL number of elements required to achieve criticality is between:
a.
16 to 18 b.
19 to 21 c.
22 to 24 d.
25 to 27 QUESTION A.18
[1.0 point]
For the fast energy range, 100 KeV - 10 MeV, the absorption cross section steadily decreases as the energy of the neutron increases. What is this region?
- a.
Slow neutron region.
- b.
Fast neutron region.
- c.
Increases the mass of the target region.
- d.
Destruction the mass of the target region.
Category A - Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.19
[1.0 point]
Which ONE of the following directly produces 95% of all Xenon in a nuclear reactor?
- a.
Decay of Sm-149
- b.
Fission of U-235
- c.
Decay of Cs-135
- d.
Decay of I-135 QUESTION A.20
[1.0 point]
Which ONE of the following is the major source of heat generated after an operating reactor has been shut down and cooled down for several days?
- a.
Resonance capture.
- b.
Fission fragment decay.
- c.
Delayed neutron reactions.
- d.
Corrosion product activation.
(***** END OF CATEGORY A *****)
Category B - Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.01
[1.0 point]
A three-curie source, emitting 100 Kev gamma with a yield of 70%, is to be stored in the reactor building. What is a dose rate at 3 ft?
a.
14 mR/hr b.
23 mR/hr c.
140 mR/hr d.
420 mR/hr QUESTION B.02
[1.0 point, 0.25 each]
Match type of radiation listed in column A with their quality factor listed in column B. Items in column B can be used once, more than once or not at all.
Column A Column B a.
X-ray 1.
1 b.
Gamma 2.
5 c.
Alpha particles 3.
10 d.
High-energy neutron 4.
20 QUESTION B.03
[1.0 point]
Which ONE of the following radionuclides causes a severe damage to thyroid gland from an intake?
a.
I131 b.
N16 c.
Ar41 d.
Co60
Category B - Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.04
[1.0 point, 0.25 each]
Common radioisotopes associated with research reactors are H-3, Na-24, N-16,, and Ar-41.
Fill in the blank with their appropriate half-life (seconds (sec), minutes (min) hours (hr) or years (yr)).
- a.
H-3 is 12.0 _____.
- b.
N-16 is 7.0 _____.
- c.
Na-24 is 15.0 _____.
- d.
Ar-41 is 1.8 _____.
QUESTION B.05
[1.0 point]
A radioactive source currently has an activity of 2 Curies. The activity of the source 25 years ago was 120 Curies. What is the half-life of the radioactive source?
a.
4.2 years b.
5.4 years c.
7.5 years d.
8.2 years QUESTION B.06
[1.0 point]
Per 10 CFR 55, which ONE of the following is the MINIMUM requirement that must be met to retain an active reactor operator license? Reactor operator must perform license duties:
a.
A minimum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per month.
b.
At least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per calendar year.
c.
A minimum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per calendar quarter.
d.
A minimum of 5 significant control manipulations.
Category B - Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.07
[1.0 point]
Per Reed College Technical Specifications, which ONE of the following would most likely be considered a Special Report (the Director shall report by telephone to the NRC no later than the following working day)?
a.
A fire in the reactor bay, lasting 10 minutes.
b.
Rapidly raise the control rods to power that causes reactor scram.
c.
Observe an abnormal loss of core coolant at a rate that exceeds the makeup capacity.
d.
Conduct a reactor operation without properly performing the startup checklist, which causes the bulk pool water temperature exceeding 40 °C.
QUESTION B.08
[1.0 point]
Per Reed College Technical Specifications, the following statement, The steady-state reactor power level shall not exceed 250 kW. is an example of a (an):
a.
Safety Limit (SL) b.
Limiting Safety System Setting (LSS) c.
Limiting Condition for Operations (LCO) d.
Administrative Power Limit (APL)
QUESTION B.09
[1.0 point]
Which ONE of the following surveillances is a channel test?
- a.
During a startup, you depress a scram bar to verify a manual scram.
- b.
During a steady state power, you compare the readings of the Linear channel and the Percent Power channel.
- c.
During a steady state power, you compare bulk water pool temperatures.
- d.
You adjust Linear channel in accordance with recent data collected from a power channel calibration.
Category B - Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.10
[1.0 point]
Which ONE of the following types of radiation detectors does NOT have an output intensity proportional to the incident radiation energy (e.g. as incident energy increases, does the output intensity increase)?
- a.
Ion chamber b.
Scintillation c.
Proportional counter d.
Geiger Mueller (GM) Counter QUESTION B.11
[1.0 point]
Per Reed College Technical Specifications, which ONE of the following is the Limiting Safety System Setting (LSSS)?
- a.
The maximum fuel temperature shall not exceed 1000 °C
- b.
The limiting safety system setting shall be equal to or less than 300 kW as measured by a power measuring channel.
- c.
The steady state reactor power level shall not exceed 275 kW.
- d.
The maximum available excess reactivity based on the reference core condition shall not exceed $3.00.
QUESTION B.12
[1.0 point]
Per Reed College Emergency Classification, the emergency classification in which pool level alarm in conjunction with RAMs alarms is defined as:
a.
Alert b.
Notification of Unusual Event c.
Abnormal Condition but Not Related to Reactor Safety.
d.
Non-Reactor Safety-Related Event
Category B - Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.13
[1.0 point]
Per Reed College Technical Specifications, substantive changes to previously approved experiments shall be made only after review by the ________ and approval in writing by
____________ or designated alternate.
a.
NRC/Director b.
Dean of Faculty/Director c.
ROC/Director d.
Director/Supervisor QUESTION B.14
[1.0 point]
A Radiation Work Permit (RWP), used to maintain the radiological dose received by personnel as low as reasonably achievable (ALARA), will expire ______ after approval.
- a.
1 day b.
10 days c.
30 days d.
as soon as completing the work QUESTION B.15
[1.0 point]
Per Reed College Technical Specifications, the maximum rate of reactivity insertion associated with movement of the control rod shall be not greater than_____ per second.
- a.
$0.10
- b.
$0.16
- c.
$0.25
- d.
$0.50
Category B - Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.16
[1.0 point, 0.25 each]
Fill out the blanks with the value of the Limiting Conditions of Operation (LCO).
Safety Channel LCO
- a.
Core Excess
- b.
Reactor Power level
- c.
Scram time
- d.
Pool Water Temperature QUESTION B.17
[1.0 point]
To ensure the health and safety of the public, 10 CFR 50 allows the operator to deviate from SOPs. What is the minimum level of authorization needed to deviate from SOPs?
a.
ROC b.
Reactor Director c.
Licensed Senior Reactor Operator d.
Licensed Reactor Operator QUESTION B. 18 [1.0 point]
Per Reed College Technical Specifications, when the Radiation Area Monitor (RAM) is inoperable, the reactor Operations may continue only if:
a.
The power level is less than 10 watts.
b.
Continuous Air Monitor is still operable.
c.
Only if portable instruments are substituted for the normally installed monitor within one hour of discovery for periods not to exceed three months.
d.
Only if portable instruments are substituted for the normally installed monitor within one hour of discovery for periods not to exceed one month.
Category B - Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.19
[1.0 point]
Which ONE of the following correctly describes the limitations of experiment? The experiment with _____ shall NOT be irradiated in the reactor.
a.
The absolute reactivity of any single unsecured experiment exceeding $0.80 b.
The sum of the absolute value of reactivity of all experiments in the reactor and facilities exceeding $1.20 c.
30 mg of gunpowder d.
corrosive materials QUESTION B.20
[1.0 point]
A room contains a source which, when exposed, results in a general area dose rate of 150 millirem per hour. This source is scheduled to be exposed continuously for a month. Select an acceptable method for controlling radiation exposure from the source within this room.
a.
Post the area with the words "Controlled Radiation Area".
b.
Lock the room to prevent inadvertent entry into the room.
c.
Equip the room with a device to monitor who entries into the room.
d.
Equip the room with a motion detector that will alarm in the control room.
(***** END OF CATEGORY B *****)
Category C - Facility and Radiation Monitoring Systems QUESTION C.01
[1.0 point]
Given the following color indication of the Shim rod on the console as follows:
CONT: blue light on ON: yellow light on UP: no light DOWN: white light on Provide the correct status of the Shim rod location.
a.
The motor and rod are fully down, and the magnet is energized.
b.
The motor is fully up, Rod is fully down, and the magnet is energized.
c.
The motor and rod are fully down, and the magnet is de-energized.
d.
The motor is partially up, Rod is partially up, and the magnet is energized.
QUESTION C.02
[1.0 point]
The bottom grid plate has ninety holes machined in alignment with the holes in the top grid plate. The main function of these holes is to:
a.
ensure coolant flow through the core.
b.
ensure proper alignment of the top and bottom grid plates.
c.
permit insertion of wires or foils into the core to obtain flux data.
d.
support the lower end fixture of the fuel-moderator elements.
Category C - Facility and Radiation Monitoring Systems QUESTION C.03
[1.0 point, 1/3 each]
Figure below depicts the relative location of three neutron detectors (Linear, log-n, and
%Power). Fill out the label below with the appropriate detector.
a.
A __________
b.
B __________
c.
C __________
Category C - Facility and Radiation Monitoring Systems QUESTION C.04
[1.0 point]
An electrical device consisting of two dissimilar conductors forming electrical junctions at differing temperatures. This device produces a temperature-dependent voltage as a result of the thermoelectric effect. This device is called:
- a.
Resistance Temperature Detector b.
Bimetallic Thermometer c.
Thermocouple b.
Thermistor QUESTION C.05
[1.0 point]
Reactor is critical at 50 kW, which ONE of the following conditions will NOT immediately require a reactor SCRAM?
- a.
Staff has fallen into the reactor pool.
- b.
Continuous Air Monitor (CAM) alarm.
- c.
RAM at the reactor bay exceeds 4 mR/hr.
- d.
You couldnt insert the Shim rod when depressing DOWN button.
QUESTION C.06
[1.0 point]
The primary function of the graphite sections on both sides of the fuel is to:
- a.
reduce Compton scattering.
- b.
absorb delayed neutrons.
- c.
serve as reflectors for the core.
- d.
reduce ratio of delayed neutrons and fast neutrons.
Category C - Facility and Radiation Monitoring Systems QUESTION C.07
[2.0 points, 0.5 each]
Match the devices listed in column A with the operation status listed in column B during an isolation mode of the ventilation system. (Items in column B may be used more than once or not at all.)
Column A Column B a.
Exhaust Fan
- 1. ON b.
Supply Fan
- 2. OFF c.
Damper 11 (Supply inlet)
- 3. OPEN d.
- 4. CLOSED QUESTION C.08
[1.0 point]
Which ONE of the following best describes the reason for the highly sensitive of Geiger-Mueller tube detector?
a.
Coating with special nuclear material.
b.
A larger tube, so target area is bigger for all incident events.
c.
Lower voltage applied to the detector helps to amplify all incident events.
d.
Any incident radiation event causing primary ionization results in ionization of entire detector.
QUESTION C.09
[1 point]
Per Reed College Technical Specifications, the surveillance interval for semiannually shall not exceed:
a.
7.5 weeks.
b.
3 months.
c.
6 months.
d.
7.5 months.
Category C - Facility and Radiation Monitoring Systems QUESTION C.10
[1.0 point]
You conduct a Manual Scram test during the startup. After pressing the Manual scram bar, you notice the following indications:
- The Manual Scram annunciator goes on.
- The three yellow magnet power ON light for the raised rod goes off.
- The blue CONT light for the raised rod goes off less than one second after the scram.
Which additional actions and/or indications will occur on the raised control rod motor drive?
a.
The raised rod motor drives down and the white DOWN light and the blue CONT light go ON when it reaches the bottom.
b.
The raised rod motor drives down and the white DOWN light and the blue CONT light go OFF when it reaches the bottom.
c.
The raised rod motor stops at current position and the white DOWN light and the blue CONT light go ON when it reaches the bottom.
d.
The raised rod motor drives down and the white DOWN light and the blue CONT light continuously blinks after the scram when it reaches the bottom.
QUESTION C.11
[2.0 points, 0.5 each]
Match the input signals listed in column A with their respective responses listed in column B.
(Items in column B may be used more than once or not at all.) Note: use set point/limit during reactor operations.
Column A Column B a.
UP and CONT light on 1.
Indication only b.
30-sec period 2.
Indication and scram only c.
No neutron source 3.
Indication and interlock only d.
Linear channel= 110%
4.
Indication, scram, and interlock QUESTION C.12
[1.0 point]
Which ONE of the following is the best design at Reed College to prevent Ar-41 from the pneumatic transfer system leaking into the reactor control room?
a.
The exhaust stack height.
b.
Good isolation of the reactor room.
c.
Highly efficient particulate air (HEPA) filters.
d.
The rabbit system is negative pressure comparing to the control room.
Category C - Facility and Radiation Monitoring Systems
Category C - Facility and Radiation Monitoring Systems QUESTION C.13
[1.0 point]
How does the control rod position indicator measure rod height?
- a.
A potentiometer is attached to the control rod drive motor.
- b.
A rack and pinion drive are indicated in percentage of total travel.
- c.
Three limit switches determine the relative movement of the control rod.
- d.
A radio-frequency detector measures the height of the control rod extension tube above the piston.
QUESTION C.14
[1.0 point]
The Regulating Rod is located at _____.
a.
C5 b.
C9 c.
D1 d.
E1 QUESTION C.15
[1.0 point]
Order the following equipment in the cooling system, starting from the pool inlet and ending at the pool outlet.
- 1. Heat exchanger
- 2. Primary pump
- 3. Flow meter
- 4. Demin Tank
- 5. Conductivity Prob Output (downstream from demineralizer) a.
1 2 3 4 5.
b.
2 3 1 5 4.
c.
3 4 5 1 2.
d.
2 1 4 5 3.
Category C - Facility and Radiation Monitoring Systems QUESTION C.16
[1.0 point]
Per Reed College Technical Specifications, the pool water inlet and outlet pipes shall be equipped with siphon breaks not less than _______ meters above the upper core plate.
- a.
1
- b.
3
- c.
5
- d.
7 QUESTION C.17
[1.0 point]
The correct reason for running the primary pump at least 15 minutes before reading the reactor water conductivity is to:
- a.
Ensure the water in the reactor tank thoroughly mixed.
- b.
Allow the reactor water temperature to stabilize.
- c.
Clear any standing water out of the system.
- d.
Allow the conductivity meter to warm up.
QUESTION C.18
[1.0 point]
The Regulating rod drive has:
- a.
a single-phase stepper motor and driven at 24 inches/minute.
- b.
a variable-phase stepper motor and driven at 24 inches/minute.
- c.
a synchronous, three-phase motor, and driven at 19 inches/minute.
- d.
a non-synchronous, single-phase motor, and driven at 19 inches/minute.
(***** END OF CATEGORY C *****)
((***** END OF EXAM *****))
Category A - Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.01 Answer:
b
Reference:
Burns, Section 3.2.4, p. 3-12, and Section 3.4.4, p. 3-33 A.02 Answer:
a, INCREASE b, DECREASE c, DECREASE d, DECREASE
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 3.3.1 A.03 Answer:
d
Reference:
Lamarsh, 3rd ed., p. 345 A.04 Answer:
a
Reference:
P=P x e/, P/Po= e/ = 10, T = 120 sec/ln (10) = 52.11 sec.
A.05 Answer:
d
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 4.4, page. 4-8.
A.06 Answer:
d
Reference:
DOE Handbook Nuclear Physics & Reactor Theory, Vol. 2, Section Reactivity Coefficients and Reactivity Defect, page 21, = T*T = (-0.00082 k/k /oF) *
(-5oF) = 0.0041 k/k A.07 Answer:
a
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 3.3.4, page 3-21.
p = (Keff-1)/Keff = (0.955-1)/0.955 = -0.04712 k/k. Reactor needs 0.04712 k/k for reaching to critical, since 0.045 k/k < 0.04712 k/k, the reactor is still in subcritical.
A.08 Answer:
d
Reference:
The power of reactor #1 increases by a factor of 2, while the power of reactor #2 increases by a factor of 1.25. Since the periods are the same (rate of change is the same), power increase #2 takes a shorter time.
A.09 Answer:
d
Reference:
DOE Fundamentals Handbook, Volume 1, Module 2, page 23 A.10 Answer:
a
Reference:
Burns, R., Introduction to Nuclear Reactor Operations, Example 7.2(b), page 7-4
Category A - Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.11 Answer:
d
Reference:
= keff1-keff2/(keff1 x keff2)
(0.90-0.70) /(0.90*0.70) = 0.317 A.12 Answer:
b
Reference:
P = P0 e t/T --> T= t/Ln(P/ P0 )
T= 6/Ln(50/15 ); T = 4.98 sec.
A.13 Answer:
c
Reference:
DOE Handbook, Vol. 1, Mode 1, page 4 A.14 Answer:
c
Reference:
CR = S/(1-0.8) S = 5000*(1 - 0.8) S = 1000 A.15 Answer:
c
Reference:
CR1 / CR2 = (1 - Keff2) / (1 - Keff1) 1000 / 600 = (1 - Keff2) / (1 - 0.92)
Therefore Keff2 = 0.867
= (Keff2 - Keff1) / (Keff2
- Keff1)
= (0.867 - 0.92) / (0.867
- 0.92)
= - 0.0664 A.16 Answer:
c
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1988, § 4.2.
Keff = 1 / (1- ) Keff = 1 when = eff, the reactor is "Prompt Critical".
A.17 Answer:
a
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 5.5 A.18 Answer:
b
Reference:
DOE Fundamentals Handbook, Volume 1, Module 2, 3rd paragraph, page 10 A.19 Answer:
d
Reference:
DOE Fundamentals Handbook, Volume 2, Module 3, Page 35 A.20 Answer:
b
Reference:
DOE Fundamentals Handbook, NPRT, Vol. 2 NP-03, page 34
Category B - Normal/Emergency Operating Procedures and Radiological Controls B.01 Answer:
c
Reference:
6CEN = R/hr @ 1 ft. -> 6 x 3 x 0.7 x 0.1 = 1.26 R/hr at 1ft.
1260 mR/hr At 3 ft = 1260 mR/hr/ 9 = 140 mR/hr B.02 Answer:
a(1) b(1) c(4) d(3)
(0.25 each)
Reference:
10 CFR 20 B.03 Answer:
a
Reference:
Basic Health Physics B.04 Answer:
- a. = yr;
- b. = sec;
- c. = hr;
- d. = hr (0.25 each)
Reference:
NRC Standard Question B.05 Answer:
a
Reference:
A= A0 exp( -*T )
= ln(2) /t 1/2 Ln(2ci/120ci) = (ln(2)/t 1/2) *25 year t 1/2=4.232 years B.06 Answer:
c
Reference:
B.07 Answer:
d
Reference:
TS 6.7.2 B.08 Answer:
c
Reference:
Reed College TS 3.1.1 B.09 Answer:
a
Reference:
Reed College TS 1.0, Definition B.10 Answer:
d
Reference:
Standard NRC HP question
Category B - Normal/Emergency Operating Procedures and Radiological Controls B.11 Answer:
b
Reference:
Reed College TS 2.2 B.12 Answer:
b
Reference:
Reed College TS 1.0, Definition B.13 Answer:
c
Reference:
Reed College TS 6.5 B.14 Answer:
c
Reference:
Reed College SOP 53, Section 53.2 B.15 Answer:
b
Reference:
Reed College TS 3.2.1 B.16 Answer:
a, $3.0 b,250 kw(t) c,1 sec d,40°C (0.25 each)
Reference:
TS 3.1.3, 3.2.1, and 3.3 B.17 Answer:
c
Reference:
B.18 Answer:
d
Reference:
Reed College TS 3.5 B.19 Answer:
c
Reference:
Reed College TS 3.6.2 B.20 Answer:
b
Reference:
Category C - Facility and Radiation Monitoring Systems C.01 Answer:
a
Reference:
Reed College Training Manual 12.3, Control Rods C.02 Answer:
d
Reference:
Reed College Training Manual 12.1, Reactor Core C.03 Answer:
a, Linear b, log-n c, %power (0.33 each)
Reference:
Reed College Training Manual, Figure 12.3 C.04 Answer:
c
Reference:
Reed College Training Manual, Section 12.6, Figure 12.9 C.05 Answer:
c
Reference:
Reed College EIPs C.06 Answer:
c
Reference:
Reed College Training Manual 12.2, Reactor Fuel C.07 Answer a(1) b(2) c(4) d(3)
(0.5 each)
Reference Reed College Training Manual, Figure 12.16 & 12.17 C.08 Answer:
d
Reference:
Reed College Training Manual 5.2 C.09 Answer:
d
Reference:
Reed College TS, Definition C.10 Answer:
a
Reference:
Reed College SOP 20.8.9 C.11 Answer:
a(3) b(1) c(3) d(4)
(0.5 each)
Reference:
Reed College TS 3.2
Category C - Facility and Radiation Monitoring Systems C.12 Answer:
d
Reference:
Reed College Training Manual, Figure 13.12 C.13 Answer:
a
Reference:
Reed College Training Manual 13.3 C.14 Answer:
d
Reference:
Reed College Training Manual Chapter 13, Figure 13.3 C.15 Answer:
d
Reference:
Reed College Training Manual, Figure 13.14 C.16 Answer:
c
Reference:
Reed College TS 5.2 C.17 Answer:
c
Reference:
Reed College SOP 20.17.5 C.18 Answer:
a
Reference:
Reed College Training Manual 13.3