ML23082A118
| ML23082A118 | |
| Person / Time | |
|---|---|
| Site: | University of Utah |
| Issue date: | 03/27/2023 |
| From: | Travis Tate NRC/NRR/DANU/UNPO |
| To: | Sjoden G Univ of Utah |
| References | |
| 50-407/23-01 50-407/OL-23 | |
| Download: ML23082A118 (2) | |
Text
March 27, 2023 Dr. Glenn E. Sjoden, Director Utah Nuclear Engineering Program Professor, Energy Solutions Presidential Endowed Chair Dept. of Civil and Environmental Engineering University of Utah 110 Central Campus Drive, Rm 2000 Salt Lake City, Utah 84112
SUBJECT:
EXAMINATION REPORT NO. 50-407/OL-23-01, UNIVERSITY OF UTAH
Dear Dr. Sjoden:
During the week of February 27, 2023, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your University of Utah 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.
G. Sjoden 2 Should you have any questions concerning this examination, please contact Mr. John T.
Nguyen at (301) 415-4007 or via email John.Nguyen@nrc.gov.
Sincerely, Signed by Tate, Travis on 03/27/23 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. 50-407
Enclosures:
- 1. Examination Report No. 50-407/OL-23-01
- 2. Written examination cc: w/o enclosures: See next page
University of Utah Docket No. 50-407 cc:
Mayor of Salt Lake City 451 South State Room 306 Salt Lake City, UT 84111 Dr. Andrew S. Weyrich Vice President for Research University of Utah 201 S Presidents Circle, Room 210 Salt Lake City, UT 84112-9011 Frederick A. Monette Interim Director and RSO Radiological Health 75 S 2000 E, Room 322 University of Utah Salt Lake City, UT 84112 Test, Research and Training Reactor Newsletter Attention: Ms. Amber Johnson Dept of Materials Science and Engineering University of Maryland 4418 Stadium Drive College Park, MD 20742-2115 Director, Division of Radiation Control Dept. of Environmental Quality 195 North 1950 West P.O. Box 14485 Salt Lake City, UT 84114-4850 Andrew Allison, Reactor Supervisor The University of Utah University of Utah Nuclear Engineering Program 50 South Central Drive, Room 1206 Salt Lake City, UT 84112
ML23082A118 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME JNguyen NJones TTate DATE 3/27/2023 3/27/2023 3/27/2023 U.S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-407/OL-23-01 FACILITY DOCKET NO.: 50-407 FACILITY LICENSE NO.: R-126 FACILITY: University of Utah EXAMINATION DATES: February 27 - March 2, 2023 SUBMITTED BY: John Nguyen 03/08/2023 John T. Nguyen, Chief Examiner Date
SUMMARY
During the week of February 27, 2023, the NRC administered operator licensing examinations to three Reactor Operator (RO) and one Senior Reactor Operator Upgrade (SROU) candidates.
The candidates passed all applicable portions of the examinations.
REPORT DETAILS
- 1. Examiner: John T. Nguyen, Chief Examiner, NRC
- 2. Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 3/0 N/A 3/0 Operating Tests 3/0 1/0 4/0 Overall 3/0 1/0 4/0
- 3. Exit Meeting:
John T. Nguyen, Chief Examiner, NRC Andrew Allison, Reactor Supervisor, UUTR Facility comments were accepted prior to the administration of the written examination.
At the conclusion of the meeting, the NRC examiner thanked the facility for their support in the administration of the examinations. The examiner discussed the candidates weaknesses observed during the operating tests to include modifications to procedures and equipment, radiation sources and hazards, and radiation monitoring equipment.
Enclosure 1
University of Utah Operator Licensing Examination Week of February 27, 2023
U.S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: University of Utah REACTOR TYPE: TRIGA DATE ADMINISTERED: 2/28/2023 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 COGE NTROLS 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 Enclosure 2
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 ___
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 ___
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 ______ (0.25 each)
B10 a b c d ___
B11 a b c d ___
B12 a b c d ___
B13 a b c d ___
B14 a b c d ___
B15 a b c d ___
B16 a b c d ___
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 ___
C05 a b c d ___
C06 a ______ b ______ c ______ d ______ (0.25 each)
C07 a b c d ___
C08 a ______ b ______ c ______ d ______ (0.5 each)
C09 a b c d ___
C10 a ______ b ______ c ______ d ______ (0.25 each)
C11 a b c d ___
C12 a b c d ___
C13 a b c d ___
C14 a ______ b ______ c ______ d ______ (0.25 each)
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 ___
(***** END OF CATEGORY C *****)
(********** END OF EXAMINATION **********)
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have neither received nor given assistance in completing the examination. This must be done after you complete the examination.
- 3. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 4. Use black ink or dark pencil only to facilitate legible reproductions.
- 5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each Answer sheet.
- 6. Mark your Answers on the Answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.
- 7. The point value for each question is indicated in [brackets] after the question.
- 8. If the intent of a question is unclear, ask questions of the examiner only.
- 9. When turning in your examination, assemble the completed examination with examination questions, examination aids and Answer sheets. In addition, turn in all scrap paper.
- 10. Ensure all information you wish to have evaluated as part of your Answer is on your Answer sheet. Scrap paper will be disposed of immediately following the examination.
- 11. To pass the examination you must achieve a grade of 70 percent or greater in each category.
- 12. There is a time limit of three (3) hours for completion of the examination.
EQUATION SHEET
2 Q m c P T m H UAT Pmax eff 0.1sec 1 2
- 110 4 sec 1 K eff CR1 1 CR2 2 eff SUR 26 .06 CR1 1 K eff1 CR2 1 K eff 2 1 M 1 CR 2
P P0 1 K eff CR1 P P0 10 SUR (t )
1 K eff1 1 K eff
- M SDM 1 K eff 2 K eff
= + [ ]
T1 0.693 K eff 2 K eff1 2
K eff1 K eff 2 K eff 1 DR DR0 e t 2 2 K eff DR1 d1 DR2 d 2 6 Ci E n 2 2 1 2 DR R2 Peak2 Peak1 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
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.01 [1.0 point]
The primary purpose of _____________ material is thermalizing neutrons.
- a. Moderator
- b. Reflector
- c. Fertile
- d. Fissile QUESTION A.02 [1.0 point]
Energy yielded for fission of Uranium-235 is in the range of (or is approximately):
- a. < 1 eV b 10 keV
- c. 200 MeV
- d. >1000 MeV QUESTION A.03 [1.0 point]
Which ONE of the following factors in the "six factor formula" is the MOST affected by the MODERATOR?
- a. Fast fission factor.
- b. Reproduction factor.
- c. Thermal utilization factor.
- d. Fast non leakage probability.
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.04 [1.0 point]
A reactor is changing from the criticality to super criticality. Which ONE of the following best describes the values of Keff and during the change?
- a. Keff < 1 and = 1
- b. Keff = 1 and = -eff
- c. Keff > 1 and 0 < < -eff
- d. Keff > 1 and -eff < < 1 QUESTION A.05 [1.0 point]
The reactor is critical at 10 watts. A control rod is withdrawn to insert a positive reactivity of 0.240% k/k. Which ONE of the following will be the stable reactor period as a result of this reactivity insertion? Given beta effective = 0.0075
- a. 21 seconds
- b. 32 seconds
- c. 43 seconds
- d. 80 seconds QUESTION A.06 [1.0 point]
The probability of neutron nucleus interaction per centimeter of neutron travel is defined as:
- a. Macroscopic Cross Section
- b. Mean free path
- c. Neutron flux
- d. Barn
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.07 [1.0 point]
All atoms of a given element have the same _______.
- a. Atomic Mass
- b. Mass Number
- c. Atomic Number
- d. Number of Neutrons QUESTION A.08 [1.0 point]
Reactor power is rising on a 15 second period. Approximately how long will it take for the power to be doubled?
- a. 10 seconds
- b. 16 seconds
- c. 24 seconds
- d. 80 seconds QUESTION A.09 [1.0 point]
Which ONE of the following is the major source of heat generation after an operating reactor has been shut down and cooled down for several days?
- a. Resonance capture.
- b. Fission fragment decay.
- c. Delayed neutron reactions.
- d. Corrosion product activation.
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.10 [1.0 point]
A reactor is decreasing with a - 80 second period shortly after shutdown. What is the time for power to decrease by a factor of 10? Note: pay attention to the unit used.
- a. 1 minute
- b. 3 minutes
- c. 6 minutes
- d. 180 minutes QUESTION A.11 [1.0 point]
Which ONE of the following directly produces 95% of all Xenon in a nuclear reactor?
- a. Fission of U-235
- b. Fission of U-238
- c. Decay of Cs-135
- d. Decay of I-135 QUESTION A.12 [1.0 point]
Shown below is a trace of reactor period as a function of time. From point A to point E (included) reactor power is:
- a. constant.
- b. continually increasing.
- c. increasing, then constant.
- d. increasing, decreasing, then constant.
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.13 [1.0 point]
What is the meaning of any point on a differential rod worth curve?
- a. The amount of reactivity that one unit (e.g. one inch, one percent) of rod motion would insert at that position in the core.
- b. The zero reactivity when the rod is on the bottom and the positive reactivity being added as the rod is withdrawn.
- c. The cumulative area under the differential curve starting from the bottom of the core.
- d. The negative reactivity added as the rod is inserted.
QUESTION A.14 [1.0 point]
Which type of neutron interaction (light nuclei) is most important in moderating fast neutrons to thermal neutrons?
- a. Fission
- b. Elastic scattering
- c. Inelastic scattering
- d. Neutron capture QUESTION A.15 [1.0 point]
The Keff for the reactor is 0.950. The reactivity (k/k) needed to bring the reactor to the criticality is:
- a. +0.0256
- b. -0.0256
- c. -0.0526
- d. +0.0526
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.16 [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.
QUESTION A.17 [1.0 point]
Which ONE of the following is the stable reactor period which will result in a power rise from 5%
to 50% power in 3 seconds?
- a. 1.3 seconds
- b. 4.3 seconds
- c. 7.8 seconds
- d. 80 seconds QUESTION A.18 [1.0 point]
Reactor is critical at 10 watts. The reactor operator inserts an experiment worth of 0.08 k/k into the core. This insertion will cause:
Given:
T: reactor period, *: Prompt neutron lifetime; : reactivity insertion; : beta fraction;
-eff: delayed neutron precursor constant
- a. A sudden drop in delayed neutrons
- b. A number of prompt neutrons is twice as much as a number of delayed neutrons
- c. The immediate resultant period as a function of the prompt neutron lifetime (T=*/)
- d. The resultant period as a function of the delayed neutron precursors = [ ]
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.19 [1.0 point]
Which ONE of the following has a long-term effect on Keff but no significant change of Keff for the short term and power transient operation?
- a. Fuel burnup.
- b. Increase in fuel temperature.
- c. Increase in moderator temperature.
- d. Xenon and Samarium fission products.
QUESTION A.20 [1.0 point]
A multiplication factor during a fuel loading is 0.8, which produces the stable neutron count rate of 5000 neutrons per second (N/sec). What is a source strength?
- a. 100 N/sec
- b. 400 N/sec
- c. 1000 N/sec
- d. 4000 N/sec
(***** END OF CATEGORY A *****)
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.01 [1.0 point]
Per UUTR Technical Specifications, a channel test of the reactor area confinement ventilation systems ability to be secured shall be performed _______.
- a. daily
- b. monthly
- c. semiannually
- d. annually QUESTION B.02 [1.0 point]
A two-curie source, emitting 100 Kev gamma with a yield of 80%, is to be stored in the reactor building. What is a dose rate at 2 ft?
- a. 24 mR/hr
- b. 96 mR/hr
- c. 240 mR/hr
- d. 960 mR/hr QUESTION B.03 [1.0 point]
Which ONE of the following modifications would require to submit to the NRC for change?
- a. Revise the Reactor Startup Procedure.
- b. Change the meeting frequency of the Radiation Safety Committee from at least annually to at least quarterly in the Technical Specifications.
- c. Perform a reactor power calibration with a new temperature detector probe.
- d. Replace the differential pressure gauge used to provide the pressure difference between the Reactor Bay and the outside ambient with a new, identical gauge.
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.04 [1.0 point]
Per UUTR Technical Specifications, which of the following statements best states the MINIMUM staffing requirements when the reactor is not secured?
Note: A Certified Person: a person who is familiar with UUTR Emergency Procedures and capable of carrying out facility written procedures.
- a. 2 ROs in the control room.
- b. 1 RS + 1 Certified Person in the control room.
- c. 1 RO in the control room + 1 RS who can arrive at the facility in 15 minutes.
- d. 1 RO + 1 Certified Person in the facility + 1 RS readily available and able to be at the facility within 30 minutes.
QUESTION B.05 [1.0 point]
Select ONE of the following materials may be allowed to irradiate in the reactor core.
- a. Single movable experiment worth of $1.0.
- b. Experiment with boiling point exceeds 200 °F and 25% of the vapors escaped.
- c. The sum of the absolute value reactivity worths of all experiments exceeds $1.10.
- d. Explosive materials in quantities of 35 milligrams TNT equivalent.
QUESTION B.06 [1.0 point]
Which ONE of the following is NOT considered a Special Reports in accordance with TS 6.7.2?
- a. During the steady state operation, the reactor operator found the continuous air monitors (CAM) have been inoperable.
- b. During a steady state operation, the reactor operator found the Shim and Safety rods could be withdrawn at a same time.
- c. During a fuel movement, the operator performed an inadequately developed procedure that exceeds an LCO.
- d. During the steady state operation, a trainee let the power drift up to the 110 % of Percent Power Level Channel, whereupon a reactor scram occurred.
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.07 [1.0 point]
Changes to the UUTR Technical Specifications shall be approved by the _________ before being effectively implemented.
- a. US Nuclear Regulatory Commission
- b. UUTR Radiation Safety Committee
- c. Level 1 management (Vice President for Research)
- d. Level 2 management (UNEF Director)
QUESTION B.08 [1.0 point]
A small radioactive source is to be stored in the reactor bay with no shielding. The source reads 0.5 Rem/hr at 1 foot. A Radiation Area barrier would have to be established approximately
______ from the source.
- a. 25 feet
- b. 15 feet
- c. 10 feet
- d. 5 feet QUESTION B.09 [1.0 point, 0.25 each]
Identify the PRIMARY source (irradiation of air, irradiation of water, irradiate of reactor structure, or fission product) of EACH of the following radioisotopes.
- a. Al-28
- b. Ar-41
- c. Tritium
- d. I-131
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.10 [1.0 point]
Per UUTR Emergency Classification, the emergency classification in which an abnormal continual loss of reactor pool water that exceeds 100 gal/hour is defined as:
- a. Alert
- b. Unusual Event
- c. Abnormal Condition but Not Related to Reactor Safety.
- d. Non-Reactor, Safety-Related Event QUESTION B.11 [1.0 point]
Which ONE of the following would violate the Safety Limit (SL) of the UUTR Technical Specifications?
- a. The shutdown margin is less than one dollar.
- b. The fuel temperature in a stainless-steel clad exceeds 950 °C.
- c. The fuel temperature in an aluminum clad exceeds 550 °C.
- d. The reactor power exceeds 130 kW when experiment failure.
QUESTION B.12 [1.0 point]
A 40-mm thick sheet of lead placed at a certain location in a beam port reduced the gamma radiation level from 600 mR/hr to 150 mR/hr. How many additional lead would be needed to reduce the gamma radiation level to 75 mR/hr?
- a. 20 mm
- b. 40 mm
- c. 60 mm
- d. 80 mm
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.13 [1.0 point]
Which ONE of the following surveillances is a channel test?
- b. During a steady state power, you compare the readings of the Linear channel and the Percent Power channel.
- c. During a steady state power, you compare fuel element temperatures.
- d. You adjust Linear channel in accordance with recent data collected from a power channel calibration.
QUESTION B.14 [1.0 point]
Which ONE of the following types of radiation detectors does NOT have an output intensity proportional to the incident radiation energy (e.g. as incident energy increases, does the output intensity increase)?
- a. Geiger Mueller (GM) Counter
- b. Scintillation
- c. Ion chamber
- d. Proportional counter QUESTION B.15 [1.0 point]
Which ONE of the following is NOT a review function of the Reactor Safety Committee (RSC)?
- a. Review proposed changes to the Technical Specifications or license.
- b. Review operating abnormalities having safety significance.
- c. Review non-substantive changes to existing procedures.
- d. Review audit reports.
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.16 [1.0 point]
The Annual Limit on Intake (ALI) is defined as:
- a. The concentration of a given radionuclide in air which, if breathed by an adult worker for a year, would result in a committed effective dose equivalent of 5 rems.
- b. The dose equivalent to organs or tissues that will be received from an intake of radioactive material by an individual during the 50-year period following the intake.
- c. The concentration of a given radionuclide in air which, if breathed by an adult worker for a year, would result in a committed effective dose equivalent of 15 rems.
- d. The derived limit for the amount of radioactive material taken into the body of an adult worker by inhalation or ingestion in a year that would result in a committed effective dose equivalent of 5 rem whole body or 50 rems to any individual organ or tissue.
QUESTION B.17 [1.0 point]
During a fuel inspection, which ONE of the following is considered a normal (acceptable) condition?
- a. Its length exceeds its original length by 0.130 inches.
- b. Visual inspection identifies a crack in the middle of fuel element.
- c. The transverse bend exceeds 0.025 inches over the length of the cladding.
- d. Fuel burnup of Uranium-235 in the UZrH fuel matrix exceeds 55% of the initial content.
QUESTION B.18 [1.0 point]
The UUTR requalification program must be conducted for a continuous period not to exceed two years, in accordance to _______.
- a. 10 CFR 19
- b. 10 CFR 20
- c. 10 CFR 50
- d. 10 CFR 55
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.19 [1.0 point]
While working on an experiment, you receive the following radiation doses: 100 mrad (),
25 mrad (), and 5 mrad (neutrons of unknow energies). Which ONE of the following is your total dose?
- a. 175 mrem
- b. 155 mrem
- c. 145 mrem
- d. 130 mrem QUESTION B.20 [1.0 point]
Which ONE of the following is the radiation dose rate limit for the public in an unrestricted area?
- a. No limit.
- b. 100 rem in a year.
- c. 2 rem in any one hour.
- d. 2 mrem in any one hour.
(***** END OF CATEGORY B *****)
Category C: Facility and Radiation Monitoring Systems QUESTION C.01 [1.0 point]
Which ONE of the following best describes how the Uncompensated Ion Chamber (UIC) and Compensated Ion Chamber (CIC) operate?
- a. The CIC has Two chambers, one is coated with U-235 for fission reaction and the other is coated with Boron-10 for (n,) reaction; whereas the UIC has only one chamber coated with U-235 for fission reaction.
- b. The CIC has only one chamber coated with U-235 for fission reaction, whereas the UIC has two chambers, both can sense gamma rays but only one is coated with Boron-10 for (n,) reaction.
- c. The CIC has two chamber, both can sense gamma rays but only one is coated with Boron-10 for (n,) reaction; whereas the UIC has only one chamber coated with Boron-10 for (n, ) reaction.
- d. The CIC has only one chamber coated with Boron-10 for (n, ) reaction; whereas the UIC has two chambers, one is coated with U-235 for fission reaction and the other is coated with Boron-10 for (n,) reaction.
QUESTION C.02 [1.0 point]
A control rod is partially withdrawn from the core. At this point, the source level, for some unknown reason, drops to 1 count per second. As a result:
- a. The control rod cannot be withdrawn any further.
- b. The control rod cannot be inserted any further.
- c. The control rod stuck and cannot be moved in any direction.
- d. The control rod can only be inserted by placing the key switch in the OFF position.
QUESTION C.03 [1.0 point]
Which ONE of the following conditions will cause the reactor scram?
- a. Pool water temperature exceeds 33 °C.
- b. Linear Power level exceeds 100 kW.
- c. Percent Power Level exceed 105 % of full power.
- d. Source count is 1 cps on the Startup Power channel.
Category C: Facility and Radiation Monitoring Systems QUESTION C.04 [1.0 point]
Which ONE of the following is the neutron startup source?
- a. Plutonium-Beryllium
- b. Americium-Lithium
- c. Antimony-Beryllium
- d. Americium-Beryllium QUESTION C.05 [1.0 point]
Which ONE of the following is a volume of water reactor tank lost during a maintenance if the water level from the top of tank decreases by 4 cm?
- a. 6 gallons
- b. 12 gallons
- c. 23 gallons
- d. 46 gallons QUESTION C.06 [1.0 point, 0.25 each]
Match the MAIN purification system functions in column A with the correct purification component listed in column B. (Note: items from column B may be used more than once, or not at all.)
Column A Column B
- a. Prevent clogging in the demineralizer. 1. Resin in demineralizer
- b. Remove dissolved impurities 2. Filter
- c. Remove suspended solids
- d. Maintain pH
Category C: Facility and Radiation Monitoring Systems QUESTION C.07 [1.0 point]
Per UUTR -003, which ONE of the following correctly describe the procedure to perform the Shim rod calibration?
- a. Raise the Shim rod to full out (100%). Hold a power level of 1 kW for 5 minutes. Drop the Shim rod by depressing the Shim rod magnetic power button. Record data.
- b. Raise the Shim rod to 1 kW. Hold a power level of 1 kW for 5 minutes. Drop the Regulating rod by depressing the Regulating rod magnetic power button. Record data.
- c. Raise the Shim rod to 1 kW. Hold a power level of 1 kW for 5 minutes. Drop all rods by depressing manual scram button. Record data.
- d. Raise the Shim rod to full out (100%). Hold a power level of 1 kW for 5 minutes. Drop the Regulating rod and Safety rod by depressing their rod magnetic power buttons. Record data.
QUESTION C.08 [2.0 points, 0.5 each]
Match the surveillance requirement listed in column A with their appropriate frequency requirement listed in column B. (Items in column B may be used more than once or not at all.)
Column A Column B
- a. A channel test of the CAM system 1. Each days operation
- b. A channel test of the ARM system 2. Monthly
- c. A channel calibration of the 3. Semi-annually radiation monitoring system
- d. A channel test of the ventilation 4. Annually system
Category C: Facility and Radiation Monitoring Systems QUESTION C.09 [1.0 point]
Which ONE of the following is the appropriate action if the differential pressure between the reactor room and outside of the MEB is 0.05 inches-of-water?
- a. Reactor can operate not to exceed 20 minutes during the investigation of the loss of the differential pressure.
- b. Reactor can operate but need to inform the Reactor Supervisor for abnormal condition.
- c. Immediately shutdown the reactor.
- d. Reactor can fully operate.
QUESTION C.10 [1.0 point, 0.25 each]
The Shim rod is continuously rising from 10% to 50% of full length. Select (Open/Closed) for the Limit Switches and (ON/OFF) for the lights. Note: OPEN means the limit switch does NOT activate.
- a. Rod DOWN limit switch (Open/Close)
- b. Motor UP limit switch (Open/Close)
- c. DOWN light (ON/OFF)
- d. CONTACT light (ON/OFF)
QUESTION C.11 [1.0 point]
The low-source-interlock signal comes from:
- a. Count rate Channel
- b. Log Power Channel
- c. Linear Power Channel
- d. Percent Power Channel
Category C: Facility and Radiation Monitoring Systems QUESTION C.12 [1.0 point]
The CIC detector provides signal to _______.
- a. Log Power Channel
- b. Count rate Channel
- c. Linear Power Channel
- d. Percent Power Channel QUESTION C.13 [1.0 point]
Water returning to the pool from the primary system is ejected into the pool water as a horizontal water jet, which causes a swirling motion in the pool. Which ONE of the following is the PRIMARY purpose for this design?
- a. To decrease the heat transfer rate due to increased convective flow.
- b. To increase the transport time for N16 to reach the surface of the pool.
- c. To break up O16 bubbles in the pool thereby decreasing the production of N16.
- d. To decrease the activation rate of O16 to N16 due to a decrease in time within the core.
QUESTION C.14 [1.0 point, 0.25 each]
When reactor is at full power, identify the transfer mechanism (Forced Convection, Natural Convection or Conduction) for each of the following:
- a. Cooling the core.
- b. Cooling the pool with the cooling system.
- c. Remove ions by demineralizer.
- c. Transfer of pool water heat across the heat exchanger.
Category C: Facility and Radiation Monitoring Systems QUESTION C.15 [1.0 point]
Which ONE of the following statements correctly describes the purpose of the potentiometer in the control rod drive assembly?
- a. Provides rod position indication when the electromagnet engages the connecting rod armature.
- b. Provides a variable voltage to the rod drive motor for regulating control rod speed.
- c. Provides potential voltage as required for resetting the electromagnet current.
- d. Provides the potential voltage to relatch the connecting rod to the electromagnet.
QUESTION C.16 [1.0 point]
Which ONE of the following is the appropriate action if you calculate the reactor excess reactivity of 1.1% K/K during the new core configuration? Note: beta-effective= 0.0076
- a. Reactor can operate not to exceed 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> during the recalculation of excess reactivity.
- b. Reactor can operate but need to inform the Reactor Supervisor for an abnormal condition.
- c. Immediately shutdown the reactor due to exceeding the TS limit.
- d. Reactor can fully operate.
QUESTION C.17 [1.0 point]
The UUTR fuel element contains:
- a. a mixture of U-Zr-H alloy with a maximum of 20 weight percent uranium which has a maximum enrichment of 8.5 % U-235.
- b. a mixture of U-Zn-H alloy with a maximum of 8.5 weight percent uranium which has a maximum enrichment of 20 % U-235.
- c. a mixture of U-Zr-H alloy with a maximum of 8.5 weight percent uranium which has a maximum enrichment of 20 % U-235.
- d. a mixture of U-Zn-H alloy with a maximum of 20 weight percent uranium which has a maximum enrichment of 8.5 % U-235.
Category C: Facility and Radiation Monitoring Systems QUESTION C.18 [1.0 point]
The Reactor Supervisor is required to be present for the following conditions, EXCEPT (select the best answer):
- a. Increasing power from 1 mW to 5 W for the first startup.
- b. Moving the regulating rod out the reactor core for inspection.
- c. Removing an in-core experiment with a reactivity worth of $1.10.
- d. Losing the building electrical power, cause the reactor scram.
QUESTION C.19 [1.0 point]
A gamma source used to test the ARM monitors during the reactor startup is _______.
- a. Co-60
- b. I-131
- c. CS-137
- d. EU-152
(***** END OF CATEGORY C *****)
((***** END OF EXAM *****))
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.01 Answer: a
Reference:
DOE Fundamentals Handbook, Volume 1, Module 2, page 23 A.02 Answer: c
Reference:
Burns, R., Introduction to Nuclear Reactor Operations, Section 3.2.1 A.03 Answer: c
Reference:
DOE Fundamentals Handbook, NPRT, Vol. 2, Module 3, EO 2.3, page 25 A.04 Answer: c
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 4.2 A.05 Answer: a
Reference:
Reactivity added = 0.240 % k/k = 0.00240 k/k
= (-)/eff = 0.0075 - 0.00240 = 21 seconds (0.1) (0.00240)
A.06 Answer: a
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1988, Sec 2.6 A.07 Answer: c
Reference:
DOE Handbook, Vol. 1, Mode 1, page 4 A.08 Answer: a
Reference:
P = P0 et/T --> ln(2) = time ÷ 15 seconds -> time = ln (2) x 15 sec. 0.693 x 15 10.39 sec.
A.09 Answer: b
Reference:
DOE Fundamentals Handbook, NPRT, Vol. 2 NP-03, page 34 A.10 Answer: b
Reference:
P/P0 = e-t/ ln(0.1) = - (t)/(-80sec) Time (t) = ln (0.1) x -80 sec = 184 seconds 3 minutes
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.11 Answer: d
Reference:
DOE Fundamentals Handbook, Volume 2, Module 3, Page 35 A.12 Answer: c
Reference:
NRC Standard Question A.13 Answer: a
Reference:
Burns, R., Introduction to Nuclear Reactor Operations, Example 7.2(b), page 7-4 A.14 Answer: b
Reference:
Lamarsh 3rd ed., Section 3.6, page 68-71 Basic Nuclear Engineering 4th ed., Slowing Down of Neutrons, page 226-227 A.15 Answer: d
Reference:
= (Keff1 - Keff2) / (Keff1
- Keff2)
= (1.0000-0.950) / (0.950
- 1.0000)
= 0.050 / 0.950 = 0.0526 k/k A.16 Answer: b
Reference:
DOE Fundamentals Handbook, Volume 1, Module 2, 3rd paragraph, page 10 A.17 Answer: a
Reference:
P = P0 e t/T --> T= t/Ln(P/ P0 )
T= 3/Ln(50/5 ); T = 1.30 sec.
A.18 Answer: c
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1988, Sec 4.3 A.19 Answer: a
Reference:
Burns, R., Introduction to Nuclear Reactor Operations, Section 3.3.2, page 3-18 A.20 Answer: c
Reference:
CR = S/(1-0.8) S = 5000*(1 - 0.8) S = 1000
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.01 Answer: b
Reference:
Reference:
6CEN = R/hr @ 1 ft. -> 6 x 2 x 0.8 x 0.1 = 0.96 R/hr at 1ft.
960 mR/hr At 2 ft = 960 mR/hr/ 4 = 240 mR/hr B.03 Answer: b
Reference:
10 CFR 50.59 10 CFR 50.90 UUTR TS 6.2.2 B.04 Answer: d
Reference:
Reference:
Reference:
Reference:
10 CFR 50.90 B.08 Answer: c
Reference:
500 mRem/hr * (1)2 ft = 5 mRem/hr * (d)2 d = 10 ft B.09 Answer: a. = Structure; b. = Air; c. = Water, d. = Fission (0.25 each)
Reference:
Standard NRC Question B.10 Answer: b
Reference:
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.11 Answer: c
Reference:
Reference:
DR = DR*e -X Find 150 = 600* e -*40 ; = 0.0346 If insertion of an HVL (thickness of lead), the original intensity will be reduced by half.
Find X: 75 mR/hr = 150 mR/hr* e -0.0346*X ; X= 20 mm Find HVL by shortcut:
600mR- 300 mR is the 1st HVL 300 mR - 150 mR is the 2nd HVL 150- mR - 75 mR is the 3rd HVL B.13 Answer: a
Reference:
UUTR TS 1.3 Definitions B.14 Answer: a
Reference:
Standard NRC HP question B.15 Answer: c
Reference:
Reference:
10 CFR 20 B.17 Answer: c
Reference:
Reference:
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.19 Answer: a
Reference:
100 mrad () = 100 mrem 25 mrad () = 25 mrem 5 mrad of neutrons of unknow energies x10 = 50 mrem Total = 175 mrem B.20 Answer: d
Reference:
Category C: Facility and Radiation Monitoring Systems C.01 Answer: c
Reference:
NRC Standard Question C.02 Answer: a
Reference:
Reference:
Reference:
Reference:
4 cm
Reference:
Standard NRC purification system question.
C.07 Answer: a
Reference:
UUTR -003 C.08 Answer: a(2) b(1) c(4) d(2) (0.5 each)
Reference:
UUTR TS 4.5 & TS 4.7 C.09 Answer: d
Reference:
UUTR TS 3.5 C.10 Answer: a (Open) b(Open) c(OFF) d(ON) (0.25 each)
Reference:
Reference:
SAR 7.2.3.1
Category C: Facility and Radiation Monitoring Systems C.12 Answer: c
Reference:
Reference:
UUTR SAR 5.1 C.14 Answer: a = NC; b = FC; c = FC d = Con (0.25 each)
Reference:
Standard NRC questions C.15 Answer: a
Reference:
UUTRSAR 4.4.8.2 C.16 Answer: c
Reference:
1.1% K/K ($1.50) exceeds the TS limit of $1.20 UUTR TS 3.1.3 B.17 Answer: c
Reference:
Reference:
Reference:
UUTR SOP-01