ML23102A168
| ML23102A168 | |
| Person / Time | |
|---|---|
| Site: | University of Maryland |
| Issue date: | 07/27/2023 |
| From: | Travis Tate NRC/NRR/DANU |
| To: | Andrea Johnson Univ of Maryland |
| References | |
| 50-166/OL-23-01 50-166/OL-23 | |
| Download: ML23102A168 (35) | |
Text
July 27, 2023 Amber Johnson, Director Nuclear Reactor and Radiation Services University of Maryland Department of Materials Science and Engineering 4418 Stadium Drive, Room 1004 College Park, MD 20742-2115
SUBJECT:
EXAMINATION REPORT NO. 50-166/OL-23-01, UNIVERSITY OF MARYLAND
Dear Amber Johnson:
During the week of June 5, 2023, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your University of Maryland 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 Michele DeSouza at (301) 415-0747 or via email at Michele.DeSouza@nrc.gov.
Sincerely, Signed by Tate, Travis on 07/27/23 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. 50-166
Enclosures:
- 1. Examination Report No. 50-166/OL-23-01
- 2. Written examination cc: w/o enclosures to GovDelivery Subscribers
ML23102A168 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME MDeSouza NJones TTate DATE 7/27/2023 7/27/2023 7/27/2023 U.S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-166/OL-23-01 FACILITY DOCKET NO.: 50-166 FACILITY LICENSE NO.: R-70 FACILITY: University of Maryland EXAMINATION DATES: June 4-6, 2023 SUBMITTED BY: ________ 06/09/2023 Michele C. DeSouza, Chief Examiner Date
SUMMARY
During the week of June 05, 2023, the NRC administered operator licensing examinations to two Reactor Operator (RO) and one RO written examination retake candidates. All 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 3/0 N/A 3/0 Operating Tests 2/0 N/A 2/0 Overall 3/0 N/A 3/0
- 3. Exit Meeting:
Luke Gilde, UMD Reactor Operations Manager 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.
Maryland University Training Reactor Operator Licensing Examination Week of June 5, 2023
U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: Maryland University Training Reactor REACTOR TYPE: TRIGA DATE ADMINISTERED: 06/07/2023 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 ANSWER SHEET 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 ANSWER SHEET 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 ANSWER SHEET 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 ___ Question deleted: as written all answers are correct 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 ________ e ________ (0.4 each)
(***** END OF CATEGORY C *****)
(********** END OF EXAMINATION **********)
EQUATION SHEET
S eff 0.1sec 1 1 K eff t
P P0 e Pmax 2
- 110 4 sec 2
1 P P0 1 CR P P0 10 SUR (t )
SUR 26 .06 eff M 2 CR1 11 KCReff 2 2 CR1 CR1 1 K eff1 CR2 1 K eff 2 1 K eff1
- M 1 K eff 1 K eff 2 SDM K eff 0.693
=
+ T1 2
K eff 2 K eff1 K eff1 K eff 2 K eff 1 t DR DR0 e K eff 2 2 DR1 d1 DR2 d 2 6 Ci E n 2 2 1 2 DR R2 Peak2 Peak1
= 0 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
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.01 [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.02 [1.0 point]
The neutron count rate is 1000 cps. An experimenter inserts an experiment into the core and the count rate decreases to 725 cps. Given the initial Keff of the reactor was 0.91, what is the worth of the experiment?
- a. = + 0.02
- b. = - 0.04
- c. = - 0.06
- d. = + 0.08 QUESTION A.03 [1.0 point]
All atoms of a given element have the same ______________.
- a. Atomic Mass
- b. Atomic Number
- c. Mass Number
- d. Number of Neutrons QUESTION A.04 [1.0 point]
Which ONE of the following describes Integral Rod Worth?
- a. The remaining reactivity worth of a rod up to the point of withdrawal
- b. The plot of the slope of the change in reactivity over the change in rod position (/x)
- c. The reactivity change per unit movement of a rod.
- d. The total reactivity worth of the rod at a particular degree of withdrawal
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.05 [1.0 point]
Which ONE of the following is an example of a FISSILE material?
- a. Thorium-232
- b. Uranium-233
- c. Uranium-238
- d. Plutonium-240 QUESTION A.06 [1.0 point]
Given a reactor period of 38 seconds, approximately how long will it take power to quadruple?
- a. 33 seconds
- b. 46 seconds
- c. 53 seconds
- d. 99 seconds 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]
During fission of U-235, the majority of energy is released in the form of which ONE of the following?
- a. Fission neutrons
- b. Neutrinos
- c. Capture gamma rays
- d. Fission fragments 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]
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 QUESTION A.12 [1.0 point]
Which ONE of the following isotopes has the largest microscopic absorption cross-section for thermal neutrons?
- a. Boron-10
- b. Xenon-135
- c. Samarium-149
- d. Uranium-235
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics 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]
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 QUESTION A.15 [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.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
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.17 [1.0 point]
Define :
- a. The total fraction of delayed neutrons weighted by the percent of all neutrons contributed by the fuel.
- b. The fraction of neutrons at thermal energies which were born as delayed neutrons.
- c. The total fraction of all neutrons born as delayed neutrons.
- d. The fraction of neutrons at fast energies which were born as delayed neutrons.
QUESTION A.18 [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. lower/increase
- b. higher/increase
- c. higher/decrease
- d. lower/decrease QUESTION A.19 [1.0 point]
If 0.141% k/k of positive reactivity is suddenly inserted into a critical reactor core, what will be the steady state reactor period? (Assume: B = 0.0072)
- a. 37 seconds
- b. 52 seconds
- c. 41 seconds
- d. 80 seconds
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.20 [1.0 point]
The moderator temperature coefficient for a reactor is -0.00071 k/k/oF. What is the total reactivity change caused by a temperature decrease of 75oF?
- a. 0.00218
- b. 0.00376
- c. 0.04211
- d. 0.05325
(***** 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 A.
Answers can be used once, more than once or not at all.
Column A Column B
- a. Extremities 1. 0.1 Rem
- b. Lens of the Eye 2. 5.0 Rem
- d. Occupational Total Effective Dose Equivalent 4. 50.0 Rem QUESTION B.02 [1.0 point]
A radiation field is 67 mR/hr at 6.5 feet. What is the dose rate at 2 feet away from the source?
- a. 321 mR/hr
- b. 708 mR/hr
- c. 1360 mR/hr
- d. 1575 mR/hr QUESTION B.03 [1.0 point]
Per MUTR Emergency Plan, a significant loss of pool water that indicates abnormal loss at a rate exceeding makeup capacity is defined as:
- a. Personnel Emergency
- b. Unusual Event
- c. Alert
- d. Site Area Emergency QUESTION B.04 [1.0 point]
How long will it take a 350 Curie source, with a half-life of 5.26 years, to decay to 5 Curie?
- a. 18.5 years
- b. 27.6 years
- c. 32.3 years
- d. 38.1 years
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.05 [1.0 point]
Per MUTR Emergency Plan, which ONE of the following has the authority to terminate an emergency?
- a. Emergency Coordinator
- b. Emergency Director
- c. Senior Reactor Operator
- d. Reactor Support Coordinator QUESTION B.06 [1.0 point]
Per MUTR 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 300 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.07 [1.0 point]
Per MUTR Emergency Plan, which ONE of the following is NOT a set of actions required when responding to an emergency?
- a. Protective
- b. Assessment
- c. Corrective
- d. Evaluation
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.08 [1.0 point]
Fill in the blanks: The __________ initiates protective actions to preclude reaching the
__________. The __________ is a parameter that assures the integrity of the fuel cladding.
Safety Limit (SL), Limiting Safety System Setting (LSSS), and Limiting Conditions of Operations (LCO). May be used once, more than once, or not at all.
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 QUESTION B.10 [1.0 point]
Per MUTR Technical Specifications, a system or component is defined as OPERABLE 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]
Which ONE of the following must review and approve substantive changes to any operating, maintenance, surveillance, emergency, alarm, or experimental procedures?
- a. Senior Reactor Operator
- b. Emergency Coordinator
- c. Reactor Safety Committee
- d. Reactor Director
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 radiation area monitor detector to verify that its output is operable QUESTION B.13 [1.0 point]
In order to ensure the health and safety of the public, 10 CFR 50.54 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. Licensed SRO
- c. Licensed RO
- d. Reactor Supervisor QUESTION B.14 [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. 11.25 feet
- c. 31.22 feet
- d. 56.50 feet
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.15 [1.0 point, 0.25 each]
Match the appropriate 10 CFR 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. Postings of notices to workers
- c. 50 3. Individual radiation exposure data
- d. 55 4. Technical information including the proposed maximum power level QUESTION B.16 [1.0 point]
In accordance with MUTR Technical Specifications, which ONE of the following is NOT correct regarding the requirement for the establishment of confinement?
- a. Whenever the reactor is not secured.
- b. Whenever the bridge Radiation Area Monitor (RAM) is 10 mR/hr.
- c. When the ventilation system is off and the louvers are closed.
- d. When handling radioactive material with a significant potential for airborne release.
QUESTION B.17 [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 QUESTION B.18 [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. 19 [1.0 point]
Which ONE of the following is NOT correct concerning limitations on experiments?
- a. Total reactivity of experiments cannot be greater than $3.00.
- b. Explosive TNT must be equal to or less than 25mg.
- c. Any single experiment must be less than $1.00.
- d. Total inventory of fueled experiments of Iodine-131 thru Iodine-135 must be greater than 5mCi.
QUESTION B.20 [1.0 point]
Which ONE of the following changes must be submitted to NRC for approval prior to implementation?
- a. Add new limitation to the Pre-Startup Checklist Procedure.
- b. Replace a primary coolant pump with an identical pump.
- c. Remove a definition of Channel Test listed in the MUTR Technical Specifications.
- 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]
All the following initiate a scram, EXCEPT:
- a. instrumented fuel element temperature is 185oC.
- b. Loss of console electrical power.
- c. Neutron count rate is less than 1cps.
- d. Period is 5 seconds.
QUESTION C.02 [1.0 point]
__________ may make temporary deviations from procedures to deal with special or unusual circumstances, but such deviations must be documented and reported to the __________ within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- a. Reactor Operator, Senior Reactor Operator
- b. Senior Reactor Operator, Reactor Director
- c. Reactor Director, Reactor Safety Committee
- d. Reactor Safety Committee, Nuclear Regulatory Commission QUESTION C.03 [1.0 point]
Per MUTR OP-104, Reactor Operations, Precautions and Requirements, the thermal power as indicated on Safety I, Safety II, or the CIC under any conditions, shall not exceed?
- a. 150 kW
- b. 175 kW
- c. 215 kW
- d. 245 kW QUESTION C.04 [1.0 point] Question deleted: as written all answers are correct Which ONE of the following is a MUTR Technical Specification objective for the primary coolant system?
- a. Maximize biological shielding while the reactor is operating
- b. Minimize possibility of fuel cladding corrosion
- c. Minimize dissolved materials neutron activation
- d. Maximize Nitrogen-16 transport time
Category C: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION C.05 [1.0 point]
Which ONE of the following is NOT required to be conducted on an annual frequency basis?
- a. Excess Reactivity
- b. Environmental Monitors
- c. Reactor Safety Committee Audit
- d. Linear Power Channel Calibration QUESTION C.06 [1.0 point]
Which ONE of the following produces significant quantities of Nitrogen-16 in the reactor pool?
- a. Oxygen-16
- b. Argon-41
- c. Iodine-131
- d. Xenon-135 QUESTION C.07 [1.0 point]
A neutron flux will activate isotopes in air. What is the primary isotope of concern if a prolonged opening introduces air into the pneumatic transfer system?
- a. H2 (H1 (n, ) H2)
- b. N16 (O16 (n,p) N16)
- c. Ar41 (Ar40 (n, ) Ar41)
- d. Kr80 (Kr79 (n, ) Kr80)
QUESTION C.08 [1.0 point]
Which ONE of the following is a main reason the filtration and demineralizer system is required on the primary coolant system?
- a. Extend the longevity and integrity of the fuel cladding
- b. Maintain the proper flow rates needed to cool
- c. Maximize the shielding around the core
- d. Minimize transport time of radionuclides
Category C: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION C.09 [1.0 point, 0.25 each]
Match the corresponding control panel buttons/lights in Column A with the corresponding limit switch indication in Column B. Answers may be used once, more than once, or not at all.
Column A Column B
- a. Top button displays blue light 1. Magnet UP limit
- b. Top button displays yellow light 2. Magnet DOWN limit
- c. Middle button displays red light 3. Rod contact CONT
- d. Bottom button displays white light 4. Magnet current ON 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]
When conducting thermal power calibration, what percentage will require an adjustment of the detector(s)?
- a. 2%
- b. 3%
- c. 4%
- d. 5%
QUESTION C.12 [1.0 point]
Which ONE of the following provides the control rod position indicator measure rod height?
- b. Rack and Pinion Drive
- c. Limit Switches
- d. Ball and Gear Indicators
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 Pu-Be 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]
According to the MUTR SAR, which ONE of the following is NOT listed as a neutron moderator and reflector?
- a. Reactor pool water
- b. Aluminum encapsulated graphite blocks
- c. Thermal column experimental facility
- d. Boron carbide powder QUESTION C.16 [1.0 point]
Who is the only individual (MUTR NRC Approved Reviewing Official) allowed to make changes to the Controlled Access List (CAL) or the Facility Access List (FAL)?
- a. Reactor Operator
- b. MUTR Dean of Admissions
- c. Senior Reactor Operator
- d. MUTR Director
Category C: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION C.17 [1.0 point]
Which ONE of the following is a reportable occurrence example related to an unscheduled shutdown?
- a. Operator error causing a scram
- b. Reactor fuel cladding degradation causing RAM scram
- c. Equipment malfunction discovered during reactor startup evaluation
- d. Actuation of a reactor safety system QUESTION C.18 [1.0 point]
What is the ONE MUTR Engineered Safety Feature?
- a. Electrical Power Systems
- c. Reactor Building Ventilation System
- d. Power Regulation System QUESTION C.19 [2.0 points, 0.4 each]
In the following figure of the instrumented fuel element, select the indicated areas in the diagram (A, B, C, D, or E) to match the items in the list below.
- a. Thermocouple
- b. Zirconium Rod
- c. Stainless Steel Cladding
- d. Fuel Moderator
- e. Graphite Reflector
Category C: Reactor Theory, Thermodynamics, and Facility Operating Characteristics Figure 4.3: Instrumented Fuel-Moderator Element
(***** END OF CATEGORY C *****)
((***** END OF EXAM *****))
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.01 Answer: b
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 3.3.1 A.02 Answer: b
Reference:
CR1 / CR2 = (1 - keff2) / (1 - keff1) 1000 / 725 = (1- keff2) / (1 - 0.92)
Therefore: keff2 = 0.876
= (keff2 - keff1) / (keff2
- keff1)
= (0.876 - 0.91) / (0.876
- 0.91)
= - 0.0427 A.03 Answer: b
Reference:
DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 1, Module 1, page 4 A.04 Answer: d
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 3.4, page 3-32 A.05 Answer: b
Reference:
NRC Glossary, Fertile material, Fissionable material, Fissile material A.06 Answer: c
Reference:
P = P0et/T 4 = 1
- et/38 t = 38
- ln(4) t = 52.7 sec 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: d
Reference:
Burn, Introduction to Nuclear Reactor Operations, Sections 3.2.1, page 3-5 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:
Burn, Introduction to Nuclear Reactor Operations, Section 5.4 A.12 Answer: b
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 8.1 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: a
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 7.2 A.15 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.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: c
Reference:
DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 1, Module 1, page 30 A.18 Answer: a
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 3.2.4 & 3.4.4, pages 3-12 & 3-33 A.19 Answer: c
Reference:
= 0.00141; T = (0.0072 - 0.00141) / (0.1
- 0.00141) T = 41.06 seconds
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.20 Answer: d
Reference:
DOE Handbook Nuclear Physics & Reactor Theory, Volume 2, Section Reactivity, Subsection Reactivity Coefficients and Reactivity Defect, page 21,
= T*T = (-0.00071 k/k /oF) * (-75oF) = 0.05325k/k
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.1 Answer: a. 4; b. 3; c. 1; d. 2
Reference:
10 CFR 20 B.2 Answer: b
Reference:
I1D12=I2D22 67mR/hr@(6.5ft)2=I2@(2ft)2 708 mR/hr B.3 Answer: c
Reference:
MUTR Emergency Plan, Section 5, Emergency Classification Table 5.1 B.4 Answer: c
Reference:
T A = A*e -t 5Ci = 350Ci* e -(t) Note: = -ln2/t1/2 = -0.1315 Ln(5/350) = -ln2/5.27 yr*(t) --> -4.248/-0.1315 solve for t: 32.3 years B.5 Answer: b
Reference:
MUTR Emergency Plan 3.1.3 B.6 Answer: c
Reference:
MUTR Technical Specifications Definitions B.7 Answer: d
Reference:
MUTR Emergency Plan 7.2, 7.3, and 7.4 B.8 Answer: b
Reference:
MUTR Technical Specifications 2.1 & 2.2 B.9 Answer: c
Reference:
10 CFR 20.1201(a)(1); [5000mR
- 1hr
- day / 100mR
- 8hours] = 6.25 days B.10 Answer: a
Reference:
MUTR Technical Specifications Definitions B.11 Answer: c
Reference:
MUTR Technical Specifications 6.4 & OP-100 Section 2.2 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: b
Reference:
10 CFR 50.54(x&y)
B.14 Answer: c
Reference:
I=6CEn=R/hr@ft. 6 x 5 Ci x 5 Mev x 65% = 97.5 R/hr@ (1ft)2 =
97.5 R/hr = 0.1 R/hr@ D2 = 975 R/hr = 31.22 ft.
B.15 Answer: a. 2; b. 3; 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: b
Reference:
MUTR Technical Specifications 3.4 B.17 Answer: d
Reference:
B.18 Answer: c
Reference:
B.19 Answer: d
Reference:
MUTR Technical Specifications 3.6 B.20 Answer: c
Reference:
C.01 Answer: c
Reference:
MUTR Technical Specifications Table 3.1 & 3.2 C.02 Answer: b
Reference:
MUTR OP-100, Section 2.4 C.03 Answer: d
Reference:
MUTR OP-104, Section 3.3 C.04 Question deleted: as written all answers are correct Answer: d
Reference:
MUTR Technical Specifications 3.3 C.05 Answer: b
Reference:
MUTR Technical Specifications 3.5, 4.1, 4.2, 4.5.2, and 6.2.1.3 C.06 Answer: a
Reference:
Chart of the Nuclides C.07 Answer: c
Reference:
NSCR SOP Section IV, Procedure C.2.a C.08 Answer: a
Reference:
MUTR Technical Specifications 3.3 C.09 Answer: a. 3; b. 4; c. 1; d. 2
Reference:
MUTR SAR 7.3.1.1 C.10 Answer: a
Reference:
MUTR Technical Specifications 5.3 C.11 Answer: d
Reference:
MUTR SP-202, Section 5.4 C.12 Answer: a
Reference:
MUTR SAR 4.2.2.3 C.13 Answer: d
Reference:
MUTR SAR 4.2.4
Category B: Normal/Emergency Operating Procedures and Radiological Controls C.14 Answer: d
Reference:
NRC Standard Question C.15 Answer: d
Reference:
MUTR SAR 4.2.2.1 C.16 Answer: d
Reference:
MUTR Security Procedures C.17 Answer: b
Reference:
MUTR AP-500, Section 3.5 C.18 Answer: c
Reference:
MUTR SAR 7.5 C.19 Answer: a. C; b. A; c. D; d. B; e. E
Reference:
MUTR SAR Figure 4.3