ML23115A061
| ML23115A061 | |
| Person / Time | |
|---|---|
| Site: | 05000128 |
| Issue date: | 05/04/2023 |
| From: | Travis Tate NRC/NRR/DANU/UNPO |
| To: | Joel Jenkins Texas A&M Univ |
| References | |
| 50-128/23-02 50-128/OL-23 | |
| Download: ML23115A061 (35) | |
Text
May 4, 2023 Jere Jenkins, Director Nuclear Engineering and Science Center Texas Engineering Experiment Station 1095 Nuclear Science Road, MS 3575 College Station, TX 77843-3575
SUBJECT:
EXAMINATION REPORT NO. 50-128/OL-23-02, TEXAS A&M UNIVERSITY
Dear Jere Jenkins:
During the week of April 3, 2023, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Texas A&M 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 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 Michele DeSouza at (301) 415-0747 or via email at 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. 50-128
Enclosures:
- 1. Examination Report No. 50-128/OL-23-02
- 2. Written examination cc: w/o enclosures to GovDelivery Subscribers Signed by Tate, Travis on 05/04/23
ML23115A061 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME MDeSouza NJones TTate DATE 5/3/2023 5/4/2023 5/4/2023 U.S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-128/OL-23-02 FACILITY DOCKET NO.:
50-128 FACILITY LICENSE NO.:
R-83 FACILITY:
Texas A&M University EXAMINATION DATES:
April 3-7, 2023 SUBMITTED BY:
04/10/2023 Michele C. DeSouza, Chief Examiner Date
SUMMARY
During the week of April 03, 2023, the NRC administered operator licensing examinations to five Reactor Operator (RO), two RO written examination retakes and two Senior Reactor Operators
- Upgrade (SROU) candidates. One RO failed category A of the written examination, one RO failed the operation test, and the remaining candidates passed all applicable portions of the examinations and tests.
REPORT DETAILS 1.
Chief Examiner: Michele C. DeSouza, Chief Examiner, NRC 2.
Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 6/1 N/A 6/1 Operating Tests 4/1 2/0 6/1 Overall 5/2 2/0 7/2 3.
Exit Meeting:
Jere Jenkins, TEES Director Richard Waer, TEES Associate Director Abby Kurwitz, Senior Health Physicist 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.
Texas Engineering Experiment Station Operator Licensing Examination Week of April 3, 2023
U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
University of Texas A&M REACTOR TYPE:
TRIGA DATE ADMINISTERED:
04/07/2023 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% 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 CONTROLS 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
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.
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 ________ (0.25 each)
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 ________ (0.25 each)
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 ________ (0.25 each)
B13 a b c d ___
B14 a b c d ___
B15 a ________ b ________ c ________ d ________ (0.25 each)
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 ________ (0.25 each)
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 **********)
EQUATION SHEET
=
+
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
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.01
[1.0 point]
When large negative reactivity is inserted in the core, reactor power decreases by radioactive decay of the longest-lived source of delayed neutrons, Br-87, with a 55 second half-life. What is the shutdown period (T)?
- a. +49 seconds
- b. -50 seconds
- c. -79 seconds
- d. +86 seconds QUESTION A.02
[1.0 point]
Which ONE of the following directly produces 95% of all Xenon in a nuclear reactor?
- a. Decay of Samarium-149
- b. Fission of Uranium-235
- c. Decay of Cesium-135
- d. Decay of Iodine-135 QUESTION A.03
[1.0 point]
An example of a FISSIONABLE NUCLEI, but not fissile, is:
- a. Pu-239
- b. U-238
- c. U-233
- d. U-235 QUESTION A.04
[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.05
[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 k-effective 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 QUESTION A.06
[1.0 point]
The process in which a neutron strikes a nucleus leaving the nucleus in an excited state is referred to as:
- a. Elastic scattering
- b. Inelastic scattering
- c. Photo electric effect
- d. Neutron annihilation QUESTION A.07
[1.0 point]
What is the fraction of thermal neutrons absorbed in U-235 by fission? Given Isotope 92U²³,
= 577 barns, c = 106 barns. Note: = fission cross section, c = capture cross section
- a. 0.16
- b. 0.18
- c. 0.54
- d. 0.84 QUESTION A.08
[1.0 point]
The primary purpose of ____________ material is thermalizing neutrons.
- a. Moderator
- b. Reflector
- c. Fissile
- d. Fertile
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.09
[1.0 point]
Which ONE of the following would cause an increase in fission product poisoning?
- a. Thermal utilization
- b. Resonance escape probability
- c. Fission yield
- d. Reproduction QUESTION A.10
[1.0 point, 0.25 each]
Match the following statements in Column A with the result in Column B to complete the following statements. Answers in Column B may be used once, more than once, or not at all.
As moderator temperature increases, [Column A] [Column B].
Column A Column B
- a. Control Rod Worth
- 1. Increases
- b. Thermal non-leakage probability
- 2. Decreases
- c. Fast non-leakage probability
- d. Resonance escape probability QUESTION A.11
[1.0 point]
The moderator temperature coefficient for a reactor is -0.00082 k/k/oF. What is the total reactivity change caused by a temperature decrease of 75oF?
- a. 0.0018
- b. 0.0028
- c. 0.0205
- d. 0.0615
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.12
[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.13
[1.0 point]
The reactor is on a constant period. Which ONE of the following changes in reactor power would take the SHORTEST time?
- a. 5% from 1% to 6%
- b. 15% from 20% to 35%
- c. 20% from 40% to 60%
- d. 25% from 75% to 100%
QUESTION A.14
[1.0 point]
A reactor is critical at 18.2 inches on a controlling blade. The controlling blade is inserted to a position of 17.9 inches. The reactivity removal during the insertion is 0.1%k/k. What is the differential rod worth?
- a. 0.1%k/k /inch at 18.20 inches
- b. 0.33%k/k /inch at 18.05 inches
- c. 0.33%k/k /inch at 17.9 inches
- d. 0.1%k/k /inch at 18.05 inches
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.15
[1.0 point]
The THERMAL UTILIZATION FACTOR is defined as a ratio of:
- a. the number of fast neutrons produced by fission in a generation to the number of total neutrons produced by fission in the previous generation.
- b. the number of thermal neutrons absorbed in fuel to the number of thermal neutrons absorbed in fuel and core materials.
- c. the number of fast neutrons produced by U-238 to the number of thermal neutrons absorbed in fuel.
- d. the number of fast neutrons that start to slow down to the number of fast neutrons from all fissions.
QUESTION A.16
[1.0 point]
A reactor contains a neutron source of 1200 neutrons/second. If the stable total neutron production rate is 4800 neutrons/second, what is the value of keff?
- a. 0.60
- b. 0.75
- c. 0.80
- d. 0.95 QUESTION A.17
[1.0 point]
Which ONE of the following parameters is MOST significant in determining the differential rod worth of a control rod?
- a. Flux shape
- b. Rod speed
- c. Reactor power
- d. Fuel temperature
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.18
[1.0 point]
Which ONE of the following isotopes has the largest microscopic absorption cross-section for thermal neutrons?
- a. Xenon-135
- b. Boron-10
- c. Samarium-149
- d. Uranium-235 QUESTION A.19
[1.0 point]
If 0.156% k/k of positive reactivity is suddenly inserted into a critical reactor core, what will be the steady state reactor period? (Assume: B = 0.0074)
- a. 37 seconds
- b. 52 seconds
- c. 31 seconds
- d. 80 seconds QUESTION A.20
[1.0 point]
What is the typical value of prompt neutron generation time?
- a. 15 seconds
- b. 1 second
- c. 0.1 second
- d. 1 E-4 seconds
(***** END OF CATEGORY A *****)
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.01
[1.0 point, 0.25 each]
Match the Federal Annual Dose Limit in Column B to the type of exposure in Column B.
Answers can be used once, more than once or not at all.
Column A Column B
- a. TEDE to a member of the public
- 1. 0.1 Rem
- b. Lens of the Eye
- 2. 5.0 Rem
- c. Occupational Total Effective Dose Equivalent
- d. Extremities
- 4. 50.0 Rem QUESTION B.02
[1.0 point]
A five-curie source emits a 5MeV gamma 65% of the time. The source will be placed in the reactor storage room. How far from the source should a high radiation area sign be posted?
- a. 5.0 feet
- b. 10.25 feet
- c. 12.75 feet
- d. 15.50 feet QUESTION B.03
[1.0 point]
Per NESC Emergency Classification Guide, the pool leakage that indicates abnormal loss at a rate exceeding makeup capacity is defined as:
- a. Operational Event
- b. Notification of Unusual Event
- c. Alert
- d. Site Area Emergency QUESTION B.04
[1.0 point]
Which ONE of the following is the radiation dose limit for the public in an unrestricted area?
- a. No limit
- b. 2 rem in a year
- c. 2 rem in any one hour
- d. 2 mrem in any one hour
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.05
[1.0 point]
In order to ensure the health and safety of the public, 10CFR50 allows the operator to deviate from Technical Specifications. What is the MINIMUM level of authorization needed to deviate from Technical Specifications?
- a. Reactor Director
- b. Reactor Supervisor
- c. Licensed SRO
- d. Licensed RO QUESTION B.06
[1.0 point]
Which ONE of the following statements correctly describes the relationship between the Safety Limit (SL) and the Limiting Safety System Setting (LSSS)?
- a. The SL is a maximum operational limiting value that prevents exceeding the LSSS during normal operations.
- b. The SL is a parameter that assures the integrity of the fuel cladding. The LSSS initiates protective actins to preclude reaching the SL.
- c. The SL is a maximum setpoint for instrumentation response. The LSSS is the minimum number of channels required to be operable.
- d. The LSSS is a parameter that assures the integrity of the fuel cladding. The SL initiates the protective action to preclude reaching the LSSS.
QUESTION B.07
[1.0 point]
Per NESC Emergency Classification, which ONE of the following is a failure of an in-core experiment with a minor release of radioactive material?
- a. Alert
- b. Unusual Event - reactor related
- c. Operational Event - non-reactor related
- d. Normal Operation
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.08
[1.0 point]
Per NSCR Technical Specifications, which ONE of the following is NOT considered an UNSCHEDULED SHUTDOWN?
- a. The operator inadvertently leaned on the scram bar with their elbow and caused all the safety rods to scram
- b. The operator was not watching reactor period when it reached 4 seconds and caused all the safety rods to scram
- c. During the annual surveillance check, a reactor operator inputs a channel test signal of 1250 kW, causing all the safety rods to scram
- d. Loss of power to the building removed the high voltage supply to the reactor console and cases all the safety rods to scram QUESTION B.9
[1.0 point]
How long will it take a 300 Curie source, with a half-life of 5.26 years, to decay to 2 Curie?
- a. 18.5 years
- b. 26.2 years
- c. 31.3 years
- d. 38.1 years QUESTION B.10
[1.0 point]
A system or component is defined as OPERABLE by NSCR Technical Specifications when:
- a. it is capable of performing its intended function.
- b. operating whenever it is not unsecured or shutdown.
- c. a system is operational when reactor is in the shutdown condition.
- d. a system is operational when reactor is in the unsecured condition.
QUESTION B.11
[1.0 point]
What is the MINIMUM number of hours a Research and Test Reactor licensed operator is required to perform the functions of a licensed operator to maintain an active operators license?
- a. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per month
- b. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> per month
- c. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per quarter
- d. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> per quarter
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.12
[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. During performance of the daily checklist, you compare the readings of radiation area monitor one and radiation monitor two
- b. During performance of the daily checklist, you press the scram button to verify a scram on the safety system channel
- c. Adjustment of the wide range monitor channel in accordance with recent data collected during a reactor power calibration
- d. You expose a 2 mCi check source to the continuous air monitor detector to verify that its output is operable QUESTION B.13
[1.0 point]
Per NESC Emergency Plan, the area for which off-site emergency planning is performed to assure that prompt and effective actions can be taken to protect the public in the event of an accident is __________.
- a. Controlled Access Area
- b. Operations Boundary
- c. Unescorted Area
- d. Emergency Planning Zone QUESTION B.14
[1.0 point]
A radiation field is 421 mR/hr at 6 feet. What is the dose rate at 2 feet away from the source?
- a. 6499 mR/hr
- b. 3789 mR/hr
- c. 2660 mR/hr
- d. 1320 mR/hr
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.15
[1.0 point, 0.25 each]
Match the appropriate 10CFR part in Column A with the requirements in Column B.
Column A Column B
- a. 19
- 1. Medical examination by a physician every two years
- b. 20 2. Individual radiation exposure data
- c. 50
- 3. Postings of notices to workers
- d. 55
- 4. Technical information including the proposed maximum power level QUESTION B.16
[1.0 point]
In accordance with NESC SOP-II-C, which ONE of the following is TRUE regarding experiment movement in the reactor?
- a. The reactivity worth of any experiment being moved manually shall be less than $0.50.
- b. It is acceptable to determine the estimated reactivity of a new experiment in conjunction with reactor operation.
- c. Any experiment with a reactivity worth higher than $0.30 will be moved with reactor shutdown.
- d. An RO will direct the manual insertion of new experiments with an estimated worth of $1.00 or higher.
QUESTION B.17
[1.0 point]
A reactor operator (RO) works in a dose rate area of 100 mrem/hour (high radiation area) for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> a day. Which ONE of the following is the MAXIMUM number of days the RO can perform their duties WITHOUT exceeding their 10CFR20 limits?
- a. 4 days
- b. 5 days
- c. 6 days
- d. 7 days
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.18
[1.0 point]
The central exhaust system shall be considered operating when it creates a minimum of
__________ of negative water pressure at the sample point in the central exhaust system duct work.
- a. 0.1 inch
- b. 1.0 inch
- c. 0.5 inch
- d. 5.0 inches QUESTION B. 19
[1.0 point]
In accordance with NESC SOP-II-B, when is all or some of a pre-startup checklist required to be completed?
- a. Once a week
- b. Before every reactor startup
- c. Whenever there is a trainee on the console
- d. Prior to any restart following maintenance on a Technical Specification required component during a shutdown QUESTION B.20
[1.0 point]
Which ONE of the following changes must be submitted to NRC for approval prior to implementation?
- a. Remove a definition of Channel Test listed in the NSCR Technical Specifications.
- b. Replace a primary coolant pump with an identical pump.
- c. Add new limitation to the Pre-Startup Checklist Procedure.
- d. Add more responsibilities to the Radiation Protection Officer listed in the health physics procedure.
(***** End of Category B *****)
Category C: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION C.01
[1.0 point]
In accordance with NSCR Technical Specifications, confinement is required for all operations EXCEPT which ONE of the following?
- a. Fuel Shuffle
- b. Normal Reactor Operations
- c. Movement of new fuel into the Fuel Storage Racks
- d. Control Rod Maintenance that could cause a change in reactivity > $1.00 QUESTION C.02
[1.0 point]
Which ONE of the following channels prevents pulsing when power level is above 1 kW?
- a. Pulse
- b. Log Power
- c. Safety Power
- d. Wide Range Linear QUESTION C.03
[1.0 point]
Which ONE of the following is NOT a method of controlling radiation levels at the NSCR reactor?
- a. Controlling Nitrogen-16 release thru utilization of the diffuser system
- b. Collection of the facility liquid effluents in the holdup tanks
- c. Purging the pneumatic transfer system with CO2 when not in use
- d. Maintaining the NSCR reactor building at a negative differential pressure such that effluent release is through the ventilation stack.
QUESTION C.04
[1.0 point]
What is the MAXIMUM acceptable time between initiation of a scram signal and the time the SHIM rod is fully inserted in the core?
- a. 1.0 second
- b. 1.5 seconds
- c. 2.0 seconds
- d. 2.5 seconds
Category C: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION C.05
[1.0 point]
Which ONE of the following initiates the fuel temperature scram located on the console in the Control Room)?
- a. Pool Thermocouple
- b. Cell Thermocouple
- c. Digital Temperature Meter
- d. Digital Fuel Temperature Meter QUESTION C.06
[1.0 point]
Which ONE of the following produces significant quantities of Nitrogen-16 in the reactor pool?
- a. Argon-41
- b. Iodine-131
- c. Xenon-135
- d. Oxygen-16 QUESTION C.07
[1.0 point]
A neutron flux will activate isotopes in air. What is the primary isotope we worry about if prolonged opening introduces air into the pneumatic transfer system?
- a. H2 (H1 (n, ) H2)
- c. Ar41 (Ar40 (n, ) Ar41)
- d. Kr80 (Kr79 (n, ) Kr80)
QUESTION C.08
[1.0 point]
Which ONE of the following control rods provide scram functions?
- a. Shim safety and regulating
- c. Regulating and transient
Category C: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION C.09
[1.0 point, 0.25 each]
Fill out the blank with the time interval specified in the Technical Specifications.
- a. Monthly - Interval not to exceed ________ weeks (4/6/7).
- b. Quarterly - Interval not to exceed ________ months (4/4.5/5).
- c. Semiannually - Interval not to exceed ________ months (7/7.5/8).
- d. Annually - Interval not to exceed ________ months (14/15/16).
QUESTION C.10
[1.0 point]
What is the primary function of the graphite sections on both sides of the fuel element?
- a. Reduces neutron leakage
- b. Absorbs thermal neutrons
- c. Increases fast neutron flux
- d. Absorbs fission product gases QUESTION C.11
[1.0 point]
Per NSCR Technical Specifications, the central exhaust system shall be operable during the certain reactor operations. Which ONE of the following is NOT required for its operations?
Note: Assume that the central exhaust system is NOT in the maintenance mode.
- a. Reactor is at 5 watts.
- b. Movement of irradiated fuel elements or fuel bundles.
- c. Change in reactivity of $0.80 during a maintenance of control rod work.
- d. Handling of radioactive materials with the potential for airborne release.
QUESTION C.12
[1.0 point]
After firing a pulse, the Pulse Channel provides which of the following indications?
- a. Energy and Percent Power
- b. Energy and Fuel Temperature
- c. Peak Power and Reactor Period
- d. Peak Power and Fuel Temperature
Category C: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION C.13
[1.0 point]
Which ONE of the following is the main purpose of the neutron source in the reactor core?
- a. Prevent the reactor changing from manual to automatic if the period exceeds 5 seconds.
- b. Enable the reactor to go from subcritical to critical without moving Shim/Safety control rods.
- c. Provide sufficient neutron population to ensure proper 1/M calculation during fuel loading.
- d. Provide sufficient neutron population to ensure proper nuclear instrumentation response initial startup.
QUESTION C.14
[1.0 point]
Which ONE of the following indicates the cleanest pool water?
- a. Lowest pH
- b. Highest pH
- c. Highest conductivity
- d. Highest resistivity QUESTION C.15
[1.0 point]
While raising rods during a reactor startup, power as indicated by Log Power suddenly drops to to 2 x 10-3 W. What will happen as a result?
- b. The reactor will automatically scram, and all rods will drive into the core.
- c. The rod jammed light will energize for all shim safety rods will not move in any direction.
- d. The shim safety rods cannot be withdrawn further.
QUESTION C.16
[1.0 point]
What happens if a control rod follower becomes detached from it mounting?
- a. A safety plate stops the follower two inches below its normal down position
- b. The rod falls out of the core
- c. The control rod must be inserted into the core so the follower can be recoupled
- d. A safety plate stops the follower two inches above its normal down position
Category C: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION C.17
[1.0 point]
Who is the only individual (TEES NSC NRC Approved Reviewing Official) allowed to make changes to the Controlled Access List (CAL) or the Facility Access List (FAL)?
- a. Reactor Operator
- b. TEES Dean of Admissions
- c. Senior Reactor Operator
- d. TEES Director QUESTION C.18
[1.0 point]
What is IMMEDIATELY required for a Facility Air Monitor (FAM) Channel 2 unexpected alarm?
- a. Notify Senior Reactor Operator
- b. Notify Radiation Safety Officer
- c. Scram the reactor and evacuate
- d. No notification or action is required QUESTION C.19
[1.0 point]
The annual average concentration of Argon-41 discharged into the unrestricted area shall not exceed __________ at the site boundary?
- a. 1 x 10 -8 µCi/ml
- b. 2.5 x 10 -7 µCi/ml
- c. 1 x 10 -6 µCi/ml
- d. 1 x 10 -9 µCi/ml
Category C: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION C.20 [1.0 point]
In the following diagram, identify which region is the poison region of the control rod.
- a. I
- b. II
- c. III
- d. IV
(***** END OF CATEGORY C *****)
((***** END OF EXAM *****))
Category C: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.01 Answer:
c
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 1.3.3, page 1-6. P(t) =
P(o) e/ = P(o) X exp(-0.693t/T2); t/T = -0.693t/T2; T = -T2/0.693 = -55/0.693 =
-79.37 sec A.02 Answer:
d
Reference:
DOE, Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 2, Module 3, page 35 A.03 Answer:
b
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 3.2, page 3-2 A.04 Answer:
b
Reference:
DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 1, Module 2, page 10 A.05 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.06 Answer:
b
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 2.4.5, page 2-7-1 A.07 Answer:
d
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 3.2, page 3-2.
U-235 Fission Capture = /( + c) = 577/(577+106) = 0.84 A.08 Answer:
a
Reference:
DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 1, Module 2, page 23 A.09 Answer:
a
Reference:
Burn, Introduction to Nuclear Reactor Operations, Sections 3.2.2 and 8.4 A.10 Answer:
- a. (1) Increase; b. (2) Decrease; c. (2) Decrease; d. (2) Decrease
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 3.3.2, page 3-18.
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.11 Answer:
d
Reference:
DOE Handbook Nuclear Physics & Reactor Theory, Volume 2, Section Reactivity, Subsection Reactivity Coefficients and Reactivity Defect, page 21,
= T*T = (-0.00082 k/k /oF) * (-75oF) = 0.0615k/k A.12 Answer:
b
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 3.2.4 & 3.4.4, pages 3-12 & 3-33 A.13 Answer:
d
Reference:
P = P0 et/ Ln(P/P0) = t/ Since you are looking for which would take the SHORTEST time, the ratio P/P0 must be the smallest value.
A.14 Answer:
b
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 7.3 Differential position is at the midpoint (18.05)
= 0.1%k/k x = 18.2 - 17.9 = 0.3 inches Differential rod worth (/in) = ()/(x)
= 0.1%k/k /0.3 = 0.33%k/k at midpoint (18.05 inches)
A.15 Answer:
b
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 3.3.1 A.16 Answer:
b
Reference:
Source CR = (S) / (1 - keff); (1200) / (1 - keff) = 4800; keff = 0.75 DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 2, Module 4, page 4 A.17 Answer:
a
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 7.2 A.18 Answer:
a
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 8.1 A.19 Answer:
a
Reference:
= 0.00156; T = (0.0074 - 0.00156) / (0.1
- 0.00156) T = 37.4 seconds A.20 Answer:
d
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 5.4
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.1 Answer:
- a. 1; b. 3; c. 2; d. 4
Reference:
10 CFR 20 B.2 Answer:
c
Reference:
I=6CEn=R/hr@ft.5Ci x 5Mev x 65% = 16.25 R/hr@ (1ft)2 =
16.25 R/hr = 0.1 R/hr@ D2 = 162.5 R/hr = 12.75 ft.
B.3 Answer:
c
Reference:
NCSR Emergency Plan, Section 4, Emergency Classification Table I B.4 Answer:
d
Reference:
B.5 Answer:
c
Reference:
B.6 Answer:
b
Reference:
NRC Standard Question B.7 Answer:
b
Reference:
NSCR Emergency Plan 4.2 B.8 Answer:
c
Reference:
NSCR Technical Specifications 1.30 B.9 Answer:
c
Reference:
T A = A*e -t 2Ci = 300Ci* e -(t)
Note: = -ln2/t1/2 = -0.1315 Ln(2/100) = -ln2/5.27 yr*(t) --> -5.011/-0.1315 solve for t: 38.1 years B.10 Answer:
a
Reference:
NSCR Technical Specifications Definitions B.11 Answer:
c
Reference:
B.12 Answer:
- a. check; b. test; c. cal; d. test
Reference:
NSCR Technical Specifications Definitions
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.13 Answer:
d
Reference:
NSCR Emergency Plan 2.0 B.14 Answer:
b
Reference:
I1D12=I2D22 421mR/hr@(6ft)2=I2@(2ft)2 3789mR/hr B.15 Answer:
- a. 3; b. 2; c. 4; d. 1
Reference:
10 CFR 19.11, 10 CFR 20.1501(2)(i), 10 CFR 50.34(1)(ii)(A), 10 CFR 55.21 B.16 Answer:
c
Reference:
NSCR SOP-II-C B.17 Answer:
c
Reference:
10 CFR 20.1201(a)(1); [5000mR
- 1hr
- day / 100mR
- 8hours] = 6.25 days B.18 Answer:
a
Reference:
NSCR Technical Specifications 3.3.2 B.19 Answer:
d
Reference:
NSCR SOP-II-B B.20 Answer:
a
Reference:
C.01 Answer:
c
Reference:
NSCR Technical Specifications 3.3.1 C.02 Answer:
b
Reference:
b
Reference:
NSCR Technical Specifications 3.7 and SAR 11 C.04 Answer:
a
Reference:
NSCR Technical Specifications 3.2.3 C.05 Answer:
d
Reference:
NSCR SAR 7.2.3.7, Figure 7-4 C.06 Answer:
d
Reference:
Chart of the Nuclides C.07 Answer:
c
Reference:
NSCR SOP Section IV, Procedure C.2.a C.08 Answer:
b
Reference:
- a. 6; b. 4; c. 7.5; d. 15
Reference:
NSCR Technical Specifications, Definition, Surveillance Intervals C.10 Answer:
a
Reference:
NSCR Technical Specifications 5.4 C.11 Answer:
c
Reference:
NSCR Technical Specifications 3.3.2 C.12 Answer:
a
Reference:
Category B: Normal/Emergency Operating Procedures and Radiological Controls C.13 Answer:
d
Reference:
NSCR Technical Specifications 3.2.2 and SAR 4.2.4 C.14 Answer:
d
Reference:
NRC Standard Question C.15 Answer:
d
Reference:
NSCR Technical Specifications 3.2.1 C.16 Answer:
a
Reference:
d
Reference:
NSCR NSC Security Procedures C.18 Answer:
c
Reference:
NSCR SOP Section II, Procedure M, Facility Air Monitoring Alarm Response C.19 Answer:
d
Reference:
NSCR Technical Specifications 3.5.2 C.20 Answer:
c