ML22354A008
| ML22354A008 | |
| Person / Time | |
|---|---|
| Site: | Purdue University |
| Issue date: | 12/20/2022 |
| From: | Travis Tate NRC/NRR/DANU/UNPO |
| To: | Soon Kim Purdue University Research Reactor |
| References | |
| 50-182/23-01 50-182OL-/23-01 | |
| Download: ML22354A008 (1) | |
Text
December 20, 2022 Dr. Seungjin Kim, Reactor Director Purdue University The School of Nuclear Engineering 516 Northwestern Avenue West Lafayette, IN 47906
SUBJECT:
EXAMINATION REPORT NO. 50-182/OL-23-01, PURDUE UNIVERSITY
Dear Dr. Seungjin Kim:
During the week of October 24, 2022, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your Purdue University 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 (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site 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 Michele C. DeSouza at 301-415-0747 or via internet e-mail Michele.DeSouza@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. 50-182
Enclosures:
- 1. Examination Report No. 50-182/
OL-23-01
- 2. Written examination cc: w/o enclosures: See next page Caroline L.
Carusone Digitally signed by Caroline L.
Carusone Date: 2022.12.21 10:13:05 -05'00'
ML22354A008 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME MDeSouza ZTaru TTate (CCarusone for)
DATE 10/28/2022 12/19/2022 12/20/2022
Purdue University Docket No. 50-182 cc:
Dr. Mark Lundstrom Interim Dean of Engineering Armstrong Hall of Engineering, Suite 3000 701 West Stadium Avenue West Lafayette, IN 47907-2045 Mayor City of West Lafayette 1200 N. Salisbury Street West Lafayette, IN 47906 John H. Ruyack, Manager Epidemiology Res Center/Indoor & Radiological Health Indiana Department of Health 2525 N. Shadeland Avenue, Suite E3 Indianapolis, IN 46219 Howard W. Cundiff, P.E., Director Consumer Protection Indiana State Department of Health 2 North Meridian Street, 5D Indianapolis, IN 46204 Test, Research and Training Reactor Newsletter Attention: Amber Johnson Dept of Materials Science and Engineering University of Maryland 4418 Stadium Drive College Park, MD 20742-2115
U.S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-182/OL-23-01 FACILITY DOCKET NO.:
50-182 FACILITY LICENSE NO.:
R-87 FACILITY:
Purdue University EXAMINATION DATES:
October 24-26, 2022 SUBMITTED BY:
10/28/2022 Michele C. DeSouza, Chief Examiner Date
SUMMARY
During the week of October 24, 2022, the NRC administered operator licensing examinations to three Reactor Operators (RO) and one Senior Reactor Operator Upgrade (SROU) candidates.
Two RO and one SROU passed all applicable portions of the examinations, and one RO failed the operating test.
REPORT DETAILS
- 1.
Examiner:
Michele C. DeSouza, Chief Examiner, NRC
- 2.
Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 3/0 N/A 3/0 Operating Tests 2/1 1/0 3/1 Overall 2/1 1/0 3/1
- 3.
Exit Meeting:
Stylianos Chatzidakis, Associate Director, Purdue University True Miller, Reactor Supervisor, Purdue University Michele C. DeSouza, Chief Examiner, NRC Prior to administration of the written examination, based on facility comments, adjustments were accepted. Comments provided corrections and additional clarity to questions/answers and identified where changes were appropriate based on current facility conditions.
Upon completion of all operator licensing examinations, the NRC examiner met with facility staff representatives to discuss the results. At the conclusion of the meeting, the NRC examiner thanked the facility for their support in the administration of the examination.
Purdue University Operator Licensing Examination Week of October 24, 2022
ENCLOSURE 3 U.S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
Purdue University REACTOR TYPE:
Lockheed DATE ADMINISTERED:
10/26/2022 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% 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 18.00 20.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 20.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.3 C. FACILITY AND RADIATION MONITORING SYSTEMS 58.00 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 ___
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 ___
B03 a b c d ___
B04 a b c d ___
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 ______ (0.25 each)
B14 a b c d ___
B15 a b c d ___
B16 a b c d ___
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 d ___
C04 a b c d ___
C05 a b c d ___
C06 a b c d ___
C07 a b c d ___
C08 a b c d ___
C09 a b c d ___
C10 a b c d ___
C11 a b c d ___
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 ___
C19 a b c d ___
C20 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 and a 70 percent or greater overall.
- 12.
There is a time limit of three (3) hours for completion of the examination.
EQUATION SHEET
=
+
() ()
DR = DR0 e-x 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
x
=
+
=
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
=
=
=
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.01
[1.0 point]
Which ONE of the following factors is MOST affected by an increase in fission product poisoning?
- a. Fast Fission Factor
- b. Thermal Fission Factor
- c. Thermal Utilization Factor
- d. Resonance Escape Probability Factor QUESTION A.02
[1.0 point]
Which ONE of the following energy sources generated the highest energy (heat) after reactor shutdown?
- a. Gamma rays (capture)
- b. Delayed neutrons
- c. Fission product decay
- d. Fission neutrons (kinetic energy)
QUESTION A.03
[1.0 point]
Which ONE of the following types of neutrons are produced from the radioactive decay of certain fission products and their daughters?
- a. Fast
- b. Slow
- c. Prompt
- d. Delayed QUESTION A.04
[1.0 point]
What happens to keff when a neutron source is added to a critical reactor?
- a. Subcritical
- b. Critical
- c. Prompt Critical
- d. Supercritical
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.05
[1.0 point]
Reactor power is increasing by a factor of 2 every minute. What is the reactor period?
- a. 18 seconds
- b. 26 seconds
- c. 68 seconds
- d. 86 seconds QUESTION A.06
[1.0 point]
Which ONE of following isotopes of Uranium-235 fission product poisons has the LARGEST neutron absorption cross sections?
- a. Boron-10
- b. Cadmium-113
- c. Xenon-135
- d. Samarium-149 QUESTION A.07
[1.0 point]
The pool temperature increased in the reactor. Which ONE of the following will INCREASE?
- a. Rod worth
- b. Fast non-leakage probability
- c. Resonance escape probability
- d. Thermal non-leakage probability QUESTION A.08
[1.0 point]
Which ONE of the following statements is true about prompt neutrons?
- a. They are the total fraction of all neutrons born.
- b. They are released directly from fission within 10-13 seconds of the fission event.
- c. They are emitted immediately following the first beta decay of a fission fragment.
- d. They are responsible for the ability to control the rate at which power can rise in a reactor.
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.09
[1.0 point]
Which ONE of the following is: the amount of time required for the radioactivity to decrease to one-half of its original value?
- a. radioactive half-life
- b. secular equilibrium
- c. radioactive equilibrium
- d. transient radioactive equilibrium QUESTION A.10
[1.0 point]
QUESTION DELETED - NO CORRECT ANSWER What is the value of 1/M inverse multiplication when a reactor is critical?
- a. 0.1
- b. 0.5
- c. 1.0
- d.
QUESTION A.11 [1.0 point]
A reactor is subcritical with a keff = 0.7. What will be the new value of keff if the subcritical count rate is doubled?
- a. 0.80
- b. 0.85
- c. 0.90
- d. 0.95 QUESTION A.12
[1.0 point]
The largest amount of energy released per fission event appears in the form of _____________.
- a. Gamma radiation
- b. Alpha and Beta radiation
- c. Kinetic energy of fission fragments
- d. Kinetic energy of prompt and delayed neutrons
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.13
[1.0 point]
What is the magnitude (P1/P0 X100) of the prompt drop in the reactor power when a rod worth of 0.05 k/k is rapidly inserted into a critical reactor? Given eff = 0.007
- a. 4.50%
- b. 5.27%
- c. 11.20%
- d. 12.89%
QUESTION A.14
[1.0 point]
What is the amount of reactivity (%k/k) that is added to a subcritical reactor when Keff is increased from 0.710 to 0.995?
- a. 28.50
- b. 35.43
- c. 40.34
- d. 31.21 QUESTION A.15
[1.0 point]
QUESTION DELETED PER CHIEF EXAMINER Which ONE of the following factors will increase the core excess of a reactor?
- a. fuel depletion
- b. burnout of a burnable poison
- c. insertion of a negative reactivity worth experiment
- d. higher moderator temperature (assume negative temperature coefficient)
QUESTION A.16
[1.0 point]
What is the value of Keff if the reactor is shut down by 0.0100 k/k?
- a. 0.9901
- b. 1.2130
- c. 0.9467
- d. 0.9258
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.17 [1.0 point]
Which ONE of the following statements is true when operating a U-235 core with thermal neutrons instead of fast neutrons? Select the MOST accurate answer.
- a. Decrease the -effective when the power increases, so it is easy to control the reactor.
- b. Moderator temperature coefficient becomes positive as neutron energy increases.
- c. Neutron absorption in non-fuel material increases exponentially as neutron energy increases.
- d. The fission cross section of the fuel is much higher for thermal energy neutrons than fast neutrons.
QUESTION A.18
[1.0 point]
The neutron microscopic cross-section for U-238 absorption, a, generally ________.
- a. decreases as neutron energy increases
- b. decreases as the mass of the target nucleus increases
- c. increases as neutron energy increases
- d. increases as the mass of the target nucleus increases QUESTION A.19
[1.0 point]
What is the total reactivity (k/k) change if the temperature decreases by 75oF and the moderator temperature coefficient for the reactor is -0.00082 k/k/oF.
- a. 0.0018
- b. 0.0028
- c. 0.0825
- d. 0.0615
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.20
[1.0 point]
FAST FISSION FACTOR is defined as a ratio of which ONE of the following?
- a. The number of neutrons that reach thermal energy over the number of fast neutrons that start to slow down.
- b. The number of fast neutrons produced from fission in a generation over the number of fast neutrons produced from fission in the previous generation.
- c. The number of fast neutrons produced from U-238 over the number of thermal neutrons produced from U-235.
- d. The number of fast neutrons produced from all fission over the number of fast neutrons produced from thermal fission.
(***** END OF CATEGORY A *****)
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.01
[1.0 point]
The radiation level from an unshielded source is 1 rem/hr. Using a 50 mm thick shield (made from various materials) reduces the radiation level to 625 mrem/hr.
What is the approximate half-value layer (HVL) of the shielding for this source?
(HVL: thickness of shielding required to reduce the original source intensity by half)
- a. 64mm
- b. 70mm
- c. 74mm
- d. 80mm QUESTION B.02
[1.0 point]
Which ONE of the following is: the measured value of the power level scram shall be no higher than 12.0 kW?
- a. Safety Limit
- b. Limiting Safety System Setting
- c. Limiting Condition for Operation
- d. Safety Operational Limit QUESTION B.03
[1.0 point]
What emergency classification is identified if an individual is contaminated and injured?
- a. General emergency
- b. Site emergency
- c. Unusual event
- d. Non-reactor safety event QUESTION B.04
[1.0 point]
Which ONE of the following materials shall NOT be irradiated in the reactor core?
- a. Any buoyant material
- b. Any explosive material
- c. Any movable experiment
- d. Any fissionable material
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.05
[1.0 point]
Based on the Purdue Requalification Plan, each operator must perform the functions of a licensed operator to maintain an ACTIVE operators license a MINIMUM of how many hours?
- a. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per quarter
- b. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per quarter
- c. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per month
- d. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per year QUESTION B.06
[1.0 point]
In accordance with Purdue emergency plan, a fire that may affect any reactor safety systems is an example of what type of classification?
- a. General emergency
- b. Site emergency
- c. Alert
- d. Unusual Event QUESTION B.07 [1.0 point]
Per Purdue Technical Specifications, what is the MINIMUM shutdown margin with the most reactive shim rod and regulating rod fully withdrawn?
- a. 0.01 k/k
- b. 0.03 k/k
- c. 0.003 k/k
- d. 0.006 k/k QUESTION B.08
[1.0 point]
Which ONE of the following conditions is a violation of Purdue Technical Specifications, reactor primary coolant?
- a. Pool temperature is 28 oC
- b. Pool level is 13.25 feet measured above the top of the core
- c. Pool water sample results indicate 5x10-4microcuries of Cobalt-60 per milliliter
- d. Primary coolant conductivity is 1.1 microSiemens per centimeter
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.09
[1.0 point]
What is the approximate HALF LIFE of the isotope contained in a sample which produces the following count rates?
Time (Minutes)
Counts per Minute (cpm)
Initial count 840 30 740 60 615 90 512 180 270
- a. 110 minutes
- b. 170 minutes
- c. 210 minutes
- d. 323 minutes QUESTION B.10 [1.0 point]
Which ONE of the following PUR-1 references states: each reactor operator and senior operator will annually review the contents of the operating manual, technical specifications, and emergency procedures?
- a. Technical Specifications
- b. Administrative Procedures
- c. Final Safety Analysis Report
- d. Operator Requalification Program QUESTION B.11
[1.0 point]
Which ONE of the following does NOT require NRC approval prior to being implemented?
- a. Changes to an operating procedure that will change the intent of the procedure
- b. Changes to Section 6, Administrative Controls of the Technical Specifications
- c. Changing the number of required scram channels
- d. Changing the passing grade of the written examination for the requalification program from 70% to 60%
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.12
[1.0 point]
Which ONE of the following is the minimum number of hours you must complete before resumption of functions authorized by your license if, during the previous calendar quarter, you were unable to perform the functions of an operator for the minimum number of hours?
- a. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
- b. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
- c. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
- d. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> QUESTION B.13
[1.0 point, 0.25 each]
Identify each of the following surveillances as a channel check (CHECK), a channel test (TEST) or a channel calibration (CAL). Write the correct answer on your answer sheet next to the space given for each example listed below.
- a. Performing a calorimetric (heat balance) on the primary system, then adjusting Nuclear Instrumentation to agree with the results.
- b. Verifying overlap between Nuclear Instrumentation channels.
- c. Replacing a Resistance Temperature Detector (RTD) with a precision resistance decade box to verify proper channel output for a given resistance.
- d. Placing radioactive source next to a radiation detector and verifying meter movement.
QUESTION B.14
[1.0 point]
Which ONE of the following emergencies will likely require an evacuation of personnel from the confinement building?
- a. Civil disturbance
- b. Setback by instrumentation and recovery
- c. Airborne contamination and emergency shutdown
- d. Scram by instrumentation and shutdown
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.15
[1.0 point]
In accordance with 10 CFR 20, any failure of an experiment shall not have a consequence that could exceed dose limits, as analyzed and approved by the Reactor Supervisor and the Committee on Reactor Operations. Which ONE of the following is this statement from in the PUR-1 Technical Specifications?
- a. Design Feature
- b. Surveillance Requirements
- c. Limiting Condition for Operation (LCO)
- d. Limiting Safety System Setting (LSSS)
QUESTION B.16
[1.0 point]
Which ONE of the following is the 50 rem (0.5Sv) Annual Dose Limit for occupationally exposed adults?
- a. Planned special exposures
- b. Lens dose equivalent to the lens of the eye
- c. Total effective dose equivalent to the whole body
- d. Shallow dose equivalent to the skin of the whole body or extremities QUESTION B.17
[1.0 point]
Which ONE of the following is the requalification operating test requirement for maintaining an active operator license?
- a. 1 year
- b. 2 years
- c. 4 years
- d. 6 years QUESTION B. 18 [1.0 point]
Which ONE of the following instruments is the best to check your hands and clothing for Beta-Gamma contamination upon leaving a contamination area?
- a. Alpha Scintillation Detector
- b. Gas-Flow Proportional Counter
- c. HPGe Gamma Spectroscopy System
- d. Portable Pancake Probe GM Survey Meter
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.19
[1.0 point]
A radiation field is 330 mR/hr at 3 feet. What is the dose rate at 1.5 feet away from the source?
- a. 660 mR/hr
- b. 1320 mR/hr
- c. 1980 mR/hr
- d. 724 mR/hr QUESTION B.20
[1.0 point]
How long will it take a 50 Curie source, with a half-life of 5.26 years, to decay to 2 Curies?
- a. 20.75 years
- b. 24.48 years
- c. 26.75 years
- d. 28.5 years
(***** END OF CATEGORY B *****)
Category C: Facility and Radiation Monitoring Systems QUESTION C.01
[1.0 point]
In accordance with Purdue Radiation Safety Manual, what is the MAXIMUM half-life of a solid radioactive waste in order to hold it for decay?
- a. 20 days
- b. 30 days
- c. 45 days
- d. 60 days QUESTION C.02
[1.0 point]
The water level in the pool must be maintained at least 13 feet above the reactor core during operation. On average, how much water is added per week to compensate for evaporation and maintain the pool water level?
- a. 25 gallons
- b. 40 gallons
- c. 60 gallons
- d. 75 gallons QUESTION C.03
[1.0 point]
A PUR-1 fueled experiment shall not produce more than how much radioiodine?
- a. 0.3 mCi
- b. 0.4 mCi
- c. 0.5 Ci
- d. 0.7 Ci QUESTION C.04
[1.0 point]
Which ONE of the following is the best description on how the Compensated Ion Chamber (CIC) gets its signal to the Linear channel?
Material used in CIC Interact with Results
- a.
Pu-239 +
neutron B-10 + alpha --> N-14 + gamma
- b.
Am-239 +
neutron Be-9 + gamma --> Li-8 + beta
- c.
U-235 +
neutron Fission fragments + gamma
- d.
B-10 +
neutron B-11 --> Li-7 + alpha
Category C: Facility and Radiation Monitoring Systems QUESTION C.05
[1.0 point]
Which ONE of the following Purdue Technical Specification surveillances is required to be performed on a biennial basis?
- a. calculation of shutdown margin
- b. primary coolant conductivity
- c. shutdown radiation levels
- d. representative fuel plate inspection QUESTION C.06
[1.0 point]
New experiments are required to be reviewed by the ________ and implementation approved by _________.
- a. Senior Reactor Operator and Facility Director
- b. Facility Director and Reactor Operator
- c. CORO and CORO
- d. CORO and Facility Director QUESTION C.07
[1.0 point]
The concentration of Argon-41 shall not exceed what level at the top of the confinement exhaust stack?
- a. 1.07 x 10-7 µCi/cm2
- b. 1.98 x 10-7 µCi/cm2
- c. 2.08 x 10-8 µCi/cm3
- d. 3.01 x 10-7 µCi/cm3 QUESTION C.08
[1.0 point]
Which ONE of the following will result in a rod withdrawal interlock?
- a. Reactor period 7 seconds
- b. High flux 105%
- c. Log count rate 2 cps
- d. Source range signal/noise ratio of 2
Category C: Facility and Radiation Monitoring Systems QUESTION C.09
[1.0 point]
What is the MAXIMUM power when relocating a power detector?
- a. 5% of full power
- b. 10% of full power
- c. 500 watts
- d. 10 kWatts QUESTION C.10
[1.0 point]
Which ONE of the following materials is the regulating rod fabricated from?
- a. 6061 Aluminum
- b. 304 Stainless Steel
- c. Borated Stainless Steel
[1.0 point]
Which ONE of the following is the Purdue neutron startup source?
- a. Plutonium-Beryllium
- b. Americium-Lithium
- c. Antimony-Beryllium
- d. Americium-Beryllium QUESTION C.12
[1.0 point]
What instrumentation region is associated with: the voltage is such that every primary ion produces an avalanche of secondary ions and cannot differentiate between types of radiation?
- a. Region I, Recombination
- b. Region II, Ionization
- c. Region III, Proportional
- d. Region V, Geiger-Mueller
Category C: Facility and Radiation Monitoring Systems QUESTION C.13
[1.0 point]
When using the positive period method for determining the regulating rod worth which ONE of the following parameters is used?
- a. Pool level versus coolant level
- b. Reactivity versus rod height
- c. Temperature versus period
- d. Count rate versus k-effective QUESTION C.14
[1.0 point]
Which ONE of the following Purdue channels/monitors is an Uncompensated Ion Chamber?
- a. Channel #2
- b. Channel #3
- c. Continuous Air Monitor
- d. Radiation Area Monitor QUESTION C.15
[1.0 point]
Which ONE of the following are the detectors used in the Continuous Air Monitor (CAM)?
- a. Geiger-Mueller & Scintillation
- b. Ionization & Proportional
- c. Proportional & Geiger-Mueller
- d. Scintillation & Proportional QUESTION C.16
[1.0 point]
Which ONE of the following records is NOT required to be kept for the lifetime of the facility?
- a. Gaseous and liquid radioactive effluents release to the environment
- b. Drawings of the reactor facility
- c. Radiation exposures for all personnel monitored
- d. Principal maintenance activities
Category C: Facility and Radiation Monitoring Systems QUESTION C.17
[1.0 point]
Which ONE of the following produces significant quantities of Nitrogen-16 in the reactor pool?
- a. Argon - 41
- b. Cobalt - 60
- c. Oxygen - 16
- d. Iodine - 131 QUESTION C.18 [1.0 point]
What is the MINIMUM meeting frequency for the Committee on Reactor Operations (CORO)?
- a. Monthly
- b. Quarterly
- d. Bi-annually
- d. Annually QUESTION C.19
[1.0 point]
Purdue Technical Specification requires the total worth of all movable experiments not to exceed ________ and secured experiments not to exceed ________.
- a. 0.002 k/k and 0.004 k/k
- b. 0.003 k/k and 0.005 k/k
- c. 0.004 k/k and 0.006 k/k
- d. 0.005 k/k and 0.003 k/k QUESTION C.20
[1.0 point]
A sample of pool water is collected monthly and analyzed for gross alpha and beta activity to:
- a. Check the integrity of the fuel cladding
- b. Check the efficiency of the chiller
- c. Check the buildup of long-lived radionuclides
- d. Check the integrity of the primary heat exchanger
(***** END OF CATEGORY C *****)
((***** END OF EXAM *****))
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.01 Answer:
c
Reference:
DOE Handbook Nuclear Physics & Reactor Theory, Volume 2, Section Fission Product Poisons, page 34 A.02 Answer:
c
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, Section 3.2.1, page 3-5 A.03 Answer:
d
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, Section 3.4, page 3-32 A.04 Answer:
b or d TWO CORRECT ANSWERS ACCEPTED
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, Section 3.4, page 5-27 A.05 Answer:
d
Reference:
P=P x e/, P/Po= e/ = 2, T = 60 sec/ln(2) = 86 seconds A.06 Answer:
c
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, Section 8.1, Table 8-1 A.07 Answer:
a
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, Section 3.3.2, page 3-18 A.08 Answer:
b
Reference:
DOE Handbook Nuclear Physics & Reactor Theory, Volume 1, module 2, pg. 29, 32 A.09 Answer:
a
Reference:
DOE Handbook Nuclear Physics & Reactor Theory, Volume 1, Section Nuclear Fission, page 32 A.10 Answer:
c QUESTION DELETED - NO CORRECT ANSWER
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, Table 5, page 5-15 A.11 Answer:
b
Reference:
CR1(1 - Keff1) = CR2(1 - Keff2), count rate is doubled CR2, = 2*CR1 CR1/CR2 = CR1/2CR1 = 0.5 = (1 - Keff2)/(1 - Keff1); (1 - Keff2) = 1 - 0.5*(1 - Keff1);
Keff2 = 1 - 0.5*(1 - 0.7) = 0.85 A.12 Answer:
c
Reference:
Glasstone, Nuclear Reactor Engineering, Section 1.47
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.13 Answer:
d
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, page 4-21. P1/Po = (eff x (1-p)/(eff - p) = ((0.007(1+.05))/(0.007+.05)=0.1289, 12.89%
A.14 Answer:
c
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, Section 3.3.4, page 3-23.
=
(Keff1-Keff2)/(Keff1*Keff2) = ((0.995-0.710)/(0.995*0.710))*100= 40.34%k/k A.15 Answer:
b QUESTION DELETED
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, Section 6.1, page 6-1 A.16 Answer:
a
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, Section 3.3.4, page 3-21.
= (Keff-1)/Keff; = -0.010; -0.010 Keff = Keff -1; 1 = Keff -(-0.010 Keff) = Keff (1+0.010); Keff =1/1.010; Keff =0.9901 A.17 Answer:
d
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, Figure 2.6, page 2-39 A.18 Answer:
c
Reference:
DOE Handbook Nuclear Physics & Reactor Theory, Volume 1, Module 2, page 7 A.19 Answer:
d
Reference:
DOE Handbook Nuclear Physics & Reactor Theory, Volume 2, Section Reactivity Coefficients and Reactivity Defect, page 21, = T*T = (-0.00082 pcm/oF) * (-75oF) = 0.0615 k/k A.20 Answer:
d
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, Section 3.3.1, page 3-16
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.01 Answer:
c
Reference:
DR = DR0 e-x (625) = (1000) e-(50mm); -ln (0.625) = (50mm); = 0.0094 mm-1 (500) = (1000) e-(0.0094)x; -ln (0.5) = (0.0094 mm-1)x; x= 73.739 mm or ~74 mm B.02 Answer:
b
Reference:
Purdue Technical Specification 2.2 B.03 Answer:
d
Reference:
Purdue Emergency Plan 4, Table 1 B.04 Answer:
b
Reference:
Purdue Technical Specification 3.5 B.05 Answer:
a
Reference:
10 CFR 55.59 B.06 Answer:
d
Reference:
Purdue Emergency Plan 4, Table 1 B.07 Answer:
a
Reference:
Purdue Technical Specification 3.1 B.08 Answer:
c
Reference:
Purdue Technical Specification 3.3 B.09 Answer:
a
Reference:
A = A0e-t ; 270 = 840e-180, 180 = -ln (0.321), = 0.00631 min-1 t1/2 = 0.693 /, = 0.693 / 0.00631 min-1 = 109.8 minutes B.10 Answer:
d
Reference:
PUR-1 Requalification Program Section D, pg. 5 B.11 Answer:
a
Reference:
NRC Standard Question B.12 Answer:
c
Reference:
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.13 Answer:
- a. CAL; b. CHECK; c. TEST; d. TEST (0.25 each)
Reference:
Purdue Technical Specification 1.0 Definitions B.14 Answer:
c
Reference:
Purdue SEP-1, Emergency Procedures, page 8 B.15 Answer:
c
Reference:
Purdue Technical Specification 3.5 page 16 B.16 Answer:
d
Reference:
10 CFR 20.1201 B.17 Answer:
a
Reference:
B.18 Answer:
d
Reference:
Glasstone, Nuclear Reactor Engineering, Section 9.88, page 537 B.19 Answer:
b
Reference:
I1D12=I2D22 330 mR/hr@(3ft)2=I2@(1.5ft)2 1320 mR/hr B.20 Answer:
b
Reference:
T A = A*e -t 2Ci = 50Ci* e -(t)
Ln(2/50) = -ln2/5.27 yr*(t) --> -3.2189/-0.1315 solve for t: 24.48 years
Category C: Facility and Radiation Monitoring Systems C.01 Answer:
b
Reference:
Purdue Radiation Safety Manual, Chapter 7 C.02 Answer:
b
Reference:
PUR-1 SAR, Section 5.5 C.03 Answer:
c
Reference:
Purdue Technical Specification 3.5.f C.04 Answer:
d
Reference:
NRC Standard Question C.05 Answer:
a
Reference:
Purdue Technical Specification 4.1.a C.06 Answer:
d
Reference:
Purdue Technical Specification 6.5.a C.07 Answer:
c
Reference:
Purdue Technical Specification 3.4 C.08 Answer:
c
Reference:
Purdue Technical Specification Table I C.09 Answer:
d
Reference:
Purdue SOP 5, Section 7, Bullet 2 C.10 Answer:
b
Reference:
PUR-1 Operating Principles and Core Characteristics Manual, Rev. 3, Chapter 1.1, page 6 C.11 Answer:
a
Reference:
PUR-1 Operating Principles and Core Characteristics Manual, Rev. 3, Chapter 1.5.4, page 19 C.12 Answer:
d
Reference:
NRC Standard Instrumentation question
Category C: Facility and Radiation Monitoring Systems C.13 Answer:
b
Reference:
PUR-1 Procedure 95-7RR C.14 Answer:
b
Reference:
PUR-1 SAR, Chapter 7.4.a.iii, page 103 C.15 Answer:
c
Reference:
Technical Specification 5.4 C.16 Answer:
d
Reference:
Purdue Technical Specification 6.8 C.17 Answer:
c
Reference:
NRC standard question C.18 Answer:
d
Reference:
Purdue Technical Specification 6.2 C.19 Answer:
b
Reference:
Purdue Technical Specification 3.1.e & f C.20 Answer:
a
Reference:
Purdue Technical Specification 4.3