ML20253A316
| ML20253A316 | |
| Person / Time | |
|---|---|
| Site: | University of Wisconsin |
| Issue date: | 09/22/2020 |
| From: | Travis Tate NRC/NRR/DANU/UNPO |
| To: | Agasie R Univ of Wisconsin - Madison |
| DeSouza M., 415-0747 | |
| Shared Package | |
| ML20070R921 | List: |
| References | |
| 50-156/OL-20-01 | |
| Download: ML20253A316 (35) | |
Text
September 22, 2020 Robert Agasie, Reactor Director Nuclear Reactor Laboratory University of Wisconsin - Madison 1513 University Avenue, Room 1215 Madison, WI 53706-1687
SUBJECT:
EXAMINATION REPORT NO. 50-156 OL-20-01, UNIVERSITY OF WISCONSIN-MADISON
Dear Mr. Agasie:
During the week of August 03, 2020, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your University of Wisconsin-Madison nuclear reactor. The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.
In accordance with Title 10 of the Code of Federal Regulations, Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Ms. Michele DeSouza at (301) 415-0747 or via internet e-mail Michele.DeSouza@nrc.gov.
Sincerely, Digitally signed by Travis Travis L. Tate L. Tate Date: 2020.09.22 15:38:26
-04'00' 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. 50-156
Enclosures:
- 1. Examination Report No. 50-156/OL-20-01
- 2. Written Examination cc: w/o enclosures: See next page
ML20253A316 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME MDeSouza ZTaru TTate DATE 08/07/2020 09/09/2020 09/22/2020 University of Wisconsin-Madison Docket No. 50-156 cc:
Mayor of Madison City Hall 210 Martin Luther King Jr. Boulevard Room 403 Madison, WI 53703 Chairman, Public Service Commission of Wisconsin 610 North Whitney Way Madison, WI 53707-7854 Paul Schmidt, Manager Radiation Protection Section Division of Public Health Wisconsin Dept of Health Services P.O. Box 2659 Madison, WI 53701-2659 Test, Research and Training Reactor Newsletter Attention: Amber Johnson Dept of Materials Science and Engineering University of Maryland 4418 Stadium Drive College Park, MD 20742-2115 Jason Timm, Assistant Director
& Radiation Safety Officer University of Madison - Wisconsin Department Environmental Health & Safety Environmental Protection and Safety Bldg.
30 E. Campus Mall Madison, WI 53715
U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-156/OL-20-01 FACILITY DOCKET NO.: 50-156 FACILITY LICENSE NO.: R-74 FACILITY: University of Wisconsin-Madison EXAMINATION DATES: August 3-5, 2020 SUBMITTED BY: _______Michele DeSouza____ _August 7, 2020___
Michele DeSouza, Chief Examiner Date
SUMMARY
During the week of August 3, 2020, the NRC administered an operator licensing examination to four Reactor Operator candidates. The candidates passed all applicable portions of the written examination and operating tests.
REPORT DETAILS
- 1. Examiner: Michele DeSouza, Chief Examiner, NRC
- 2. Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 4/0 0/0 4/0 Operating Tests 4/0 0/0 4/0 Overall 4/0 0/0 4/0
- 3. Exit Meeting:
Michele C. DeSouza, Chief Examiner, NRC Robert Agasie, Reactor Director, UWI-Madison Corey Edwards, Training Coordinator, UWI-Madison Upon completion of the examination, the NRC Examiner met with facility staff representative 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.
ENCLOSURE 1
University of Wisconsin-Madison Operator Licensing Examination Week of August 3, 2020 ENCLOSURE 2
U.S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: UWI-Madison REACTOR TYPE: TRIGA DATE ADMINISTERED: 8/05/2020 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
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 ___
B02 a b c d ___
B03 a b c d ___
B04 a ___ b ___ c ___ d ___ (0.25 each)
B05 a b c d ___
B06 a b c d ___
B07 a b c d ___
B08 a b c d ___
B09 a _______ b ________ c _______ d _______ (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 ___ (0.33 each)
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 ___
C07 a b c d ___
C08 a b c d ___
C09 a b c d ___
C10 a b c d ___
C11 a b c d ___
C12 a b c d ___
C13 a b c d ___
C14 a b c d ___
C15 a b c d ___
C16 a b c d ___
C17 a b c d ___
C18 a b c d ___
C19 a b c d ___
C20 a b c d ___
(***** END OF CATEGORY C *****)
(********** END OF EXAMINATION **********)
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have neither received nor given assistance in completing the examination. This must be done after you complete the examination.
- 3. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 4. Use black ink or dark pencil only to facilitate legible reproductions.
- 5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each Answer sheet.
- 6. Mark your Answers on the Answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.
- 7. The point value for each question is indicated in [brackets] after the question.
- 8. If the intent of a question is unclear, ask questions of the examiner only.
- 9. When turning in your examination, assemble the completed examination with examination questions, examination aids and Answer sheets. In addition turn in all scrap paper.
- 10. Ensure all information you wish to have evaluated as part of your Answer is on your Answer sheet. Scrap paper will be disposed of immediately following the examination.
- 11. To pass the examination you must achieve a grade of 70 percent or greater in each category.
- 12. There is a time limit of three (3) hours for completion of the examination.
EQUATION SHEET
Pmax =
( )2 Q = m c P T = m H = UAT eff = 0.1sec 1 (2 )
t P = P0 e S S SCR = * =1x10 4 sec 1 K eff eff + CR1 ( 1 ) = CR2 ( 2 )
SUR = 26.06
( ) (
CR1 1 K eff1 = CR2 1 K eff 2 )
(1 ) 1 CR P= P0 M= = 2 P = P0 10 SUR (t )
1 K eff CR1 1 K eff1 1 K eff
- M= SDM = =
1 K eff 2 K eff 0.693 T1 = 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]
What is ?
- a. The fractional change in neutron population per generation
- b. The fraction of all fission neutrons that are born as delayed neutrons
- c. The time required for the reactor to change by power by a factor of e
- d. The fraction of all delayed neutrons that reach thermal energy QUESTION A.02 [1.0 point]
The reactor is SHUTDOWN by 5 %k/k with the count rate of 300 counts per second (cps).
The control rods are withdrawn until the count rate is tripled. What is the value of Keff when the count rate is tripled?
- a. 0.952
- b. 0.976
- c. 0.984
- d. 0.998 QUESTION A.03 [1.0 point]
The following shows part of a decay chain for the radioactive element Pb-190:
82Pb 83Bi190 190 This decay chain is an example of _______ decay.
- a. Alpha
- b. Beta
- c. Gamma
- d. Neutron QUESTION A.04 [1.0 point]
The reactor is on a CONSTANT positive period. Which ONE of the following power changes will take the SHORTEST time to complete?
- a. From 1 mW to 5 mW
- b. From 10 W to 30 W
- c. From 100 W to 200 W
- d. From 100 kW to 150 kW
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.05 [1.0 point]
Which ONE of the following is the stable reactor period which will result in a power rise from 50% to 100% power in 10 seconds?
- a. 7.3 seconds
- b. 14 seconds
- c. 43 seconds
- d. 69 seconds QUESTION A.06 [1.0 point]
Which ONE of the following isotopes will absorb more neutrons when it interacts with neutrons?
- a. Hydrogen-1
- b. Argon-40
- c. Boron-10
- d. Uranium-235 QUESTION A.07 [1.0 point]
Given a reactor period of 20 seconds, approximately how long will it take for power to quadruple?
- a. 27 seconds
- b. 35 seconds
- c. 45 seconds
- d. 60 seconds QUESTION A.08 [1.0 point]
Which ONE of the following conditions will DECREASE the core excess reactivity of a reactor?
- a. Fuel depletion
- b. Burnout of a burnable poison
- c. Insertion of a positive reactivity worth experiment
- d. Lowering moderator temperature (assume a negative temperature coefficient)
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.09 [1.0 point]
Following a positive reactivity addition to a shutdown reactor, the neutron power will increase even though k-effective is less than 1. The MAIN reason is due to:
- a. Production of fast neutrons
- b. Negative temperature coefficient in the moderator
- c. Subcritical multiplication process
- d. Void temperature coefficient in the moderator QUESTION A.10 [1.0 point, 0.25 each]
Replace X with the type of decay necessary (Alpha, Positron, Gamma or Neutron emission) to produce the following reactions. Choices may be used once, more than once, or not at all.
- a. 92U 238 90Th 234
+X
- b. 83Bi 203 82Pb 203
+ X
- c. 2He 4
+ 4Be9 6C +
12 X
- d. 84Po 210 82Pb 206
+X QUESTION A.11 [1.0 point]
Which of the following isotopes will cause a neutron to lose the most energy during an elastic scattering reaction?
- a. Oxygen-16
- b. Carbon-12
- c. Uranium-235
- d. Hydrogen-1 QUESTION A.12 [1.0 point]
Which ONE of the following conditions will require the control rod withdrawal to maintain constant power level after the following change?
- a. Adding of a fuel experiment such as U-235 into the core.
- b. Insertion of an experiment containing borated graphite.
- c. Decrease of pool water temperature.
- d. Burnout of Xenon in the core.
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.13 [1.0 point]
Which ONE of the following is the definition for Differential Control Rod Worth? The reactivity:
- a. Due to control rod position (K/K).
- b. Change per unit of rod motion (K/K/in).
- c. Due to the difference in rod speed (K/K/in/min).
- d. Still available for shutdown after control rod withdrawal.
QUESTION A.14 [1.0 point]
Shown below is a trace of reactor period as a function of time. Between points D and E reactor power is:
- a. constant.
- b. continually decreasing.
- c. continually increasing.
- d. increasing, then constant.
QUESTION A.15 [1.0 point]
If the multiplication factor, k, is increased from 0.800 to 0.950, the amount of reactivity added is:
- a. 0.150 k/k
- b. 0.197 k/k
- c. 0.250 k/k
- d. 0.297 k/k
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.16 [1.0 point]
Two critical reactors at low power are identical except that Reactor 1 has a beta fraction of 0.0072 and Reactor 2 has a beta fraction of 0.0060. An equal amount of positive reactivity is inserted into both reactors. Which ONE of the following will be the response of Reactor 1 compared to Reactor 2?
- a. The final power level will be lower.
- b. The final power level will be higher.
- c. The resulting period will be longer.
- d. The resulting period will be shorter.
QUESTION A.17 [1.0 point]
Which ONE of the following is the MAIN reason for operating the reactor with thermal neutrons instead of fast neutrons?
- a. The atomic weight of thermal neutrons is larger than fast neutrons, so thermal neutrons are easier to slow down and be captured by the fuel
- b. The neutron lifetime of thermal neutrons is longer than fast neutrons, so the fuel has enough time to capture thermal neutrons
- c. The fission cross section of the fuel is much higher for thermal energy neutrons than fast neutrons
- d. Fast neutrons give off higher radiation than thermal neutrons and the reactor needs to reduce the radiation limit by using thermal neutrons QUESTION A.18 [1.0 point]
Which ONE of the following describes the MAJOR contributions to the production and depletion of xenon in the reactor?
- a. Produced directly from fission and depletes by neutron absorption only.
- b. Produced from radioactive decay of iodine and depletes by neutron absorption only.
- c. Produced directly from fission and depletes by radioactive decay and neutron absorption.
- d. Produced from radioactive decay of iodine and depletes by radioactive decay and neutron absorption
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.19 [1.0 point]
After a thermal neutron is absorbed by Uranium-235, what is the probability that fission will occur? Assume: Uranium-235 fission cross-section = 585 barns Uranium-235 capture cross-section = 98 barns
- a. 0.487
- b. 0.832
- c. 0.857
- d. 1.201 QUESTION A.20 [1.0 point]
A reactor is slightly supercritical with the thermal utilization factor = 0.800. A control rod is inserted to bring the reactor back to critical. Assuming all other factors remain unchanged, the new value for the thermal utilization factor is:
- a. 0.798
- b. 0.800
- c. 0.802
- d. 0.804
(***** END OF CATEGORY A *****)
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.01 [1.0 point]
Which ONE of the following reactor primary coolant conditions is a violation of UWNR Technical Specifications?
- a. Primary coolant conductivity is 4 µS/cm averaged over a week
- b. Primary pool pH is 6.5
- c. Primary coolant outlet temperature is 140oF
- d. Primary coolant pool level decreases six inches below normal level QUESTION B.02 [1.0 point]
Which ONE of the following accidents is considered to be the Maximum Hypothetical Accident for the UWNR?
- a. Damage to a fuel element results in radiation doses in excess of 10CFR20 limits
- b. Damage to the reactor results in a loss of half the pool water
- c. Damage to a fuel element results in a fuel cladding failure
- d. During fuel movement, an element is dropped and a Radiation Worker is contaminated QUESTION B.03 [1.0 point]
A radiation survey of an area reveals a general radiation reading of 1 mrem/hr. There is, however, a small pipe which reads 20 mrem/hr at one (1) meter. Which ONE of the following defines the posting requirements for the area in accordance with 10CFR20?
- a. Control Access Area.
- b. Caution, Radiation Area.
- c. Caution, High Radiation Area.
- d. Grave Danger, Very High Radiation Area.
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.04 [1.0 point, 0.25 each]
Match the gamma radiation readings from column A with its corresponding radiation area classification (per 10 CFR 20; assume all distances @ 30cm) listed in column B.
Answers may be used once, more than once, or not at all.
Column A Column B
- a. 1 mR/hr 1. Unrestricted Area
- b. 200 mR/hr 2. Radiation Area
- c. 100 R/hr 3. High Radiation Area
- d. 550 R/hr 4. Very High Radiation Area QUESTION B.05 [1.0 point]
Which ONE of the following experiments require double encapsulation or a doubled walled container in accordance with the UWNR Technical Specifications?
- a. Non-corrosive liquid experiment
- b. Explosive material experiment
- c. Gaseous material experiment
- d. Material highly reactive to experimental coolant QUESTION B.06 [1.0 point]
Which ONE of the following statements will meet the TS requirement? The resistivity of the pool water, averaged over a month, shall be kept:
- a. greater than 0.2 M-cm
- b. less than 0.2 M-cm
- c. greater than 0.02 M-cm
- d. less than 0.02 M-cm
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.07 [1.0 point]
A radiation survey instrument was used to measure an irradiated experiment. The results were 200 mR/hr with the window open and 140 mR/hr with the window closed.
Not accounting for any beta correction factor or instrument efficiencies, what is the estimated beta dose?
- a. 40 mR/hr
- b. 60 mR/hr
- c. 100 mR/hr
- d. 140 mR/hr QUESTION B.08 [1.0 point]
How many hours (MINIMUM) are Test and Research Reactors licensed operators required to perform the functions of a licensed operator to resume activities if a licensee has not been actively performing the functions of a reactor operator or senior reactor operator?
- a. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
- b. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
- c. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
- d. 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> QUESTION B.09 [1.0 point, 0.25 each]
Identify each of the following surveillances as a channel check (CHECK), a channel test (TEST),
or a channel calibration (CAL). Write the correct answer on your answer sheet next to the space given for each example listed below.
- a. Performing a calorimetric (heat balance) on the primary system, then adjusting Nuclear Instrumentation to agree with results.
- b. Verifying overlap between Nuclear Instrumentation channels.
- c. Replacing a Resistance Temperature Detector (RTD) with a precision resistance decade box to verify proper channel output for a given resistance.
- d. Placing radioactive source next to a radiation detector and verifying meter movement.
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.10 [1.0 point]
UWNR Technical Specification requires the reactivity worth of any single secured experiment shall be < _________.
- a. No limit
- b. 5.6 %k/k
- c. 1.4 %k/k
- d. 0.7 %k/k QUESTION B.11 [1.0 point]
Which ONE of the following emergency situations is classified as an Alert?
- a. Tornado
- b. Security breach of the reactor facility
- c. Laboratory fire extinguished in 5 minutes
- d. Severe fuel clad leak, pool empty, and ventilation inoperable QUESTION B.12 [1.0 point]
Which ONE of the following surveillance checks shall be tested at least quarterly?
- a. Pool water radioactivity
- b. Scram times
- c. HV channel test
- d. Fuel temperature calibration QUESTION B.13 [1.0 point]
An irradiated sample provides a dose rate of 0.5 rem/hr at 2 ft. Approximately how far from the sample reads 5 mrem/hr?
- a. 6 ft.
- b. 9 ft.
- c. 14 ft.
- d. 20 ft.
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.14 [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. Director of Reactor Operations
- b. UWNR Radiation Safety
- c. Licensed Senior Reactor Operator.
- d. Licensed Reactor Operator.
QUESTION B.15 [1.0 point]
Which ONE of the following locations is the normal (no evacuation required) Emergency Support Center per the Emergency Plan?
- a. Reactor Control Room
- b. Reactor Shop
- c. Reactor Directors Office
- d. Lobby of Mechanical Engineering Building QUESTION B.16 [1.0 point]
Which ONE of the following meets the required MINIMUM radiation monitoring channels for reactor operation? Area Radiation Monitor (ARM)
- a. 4 Environmental Dosimeters, 1 ARM, and 1 Gas Stack
- b. 4 Environmental Dosimeters, 3 ARM, 1 Particulate, and 1 Gas Stack
- c. 2 Environmental Dosimeters, 3 ARM, 1 Particulate and 1 Gas Stack
- d. Environmental Dosimeters are not required, 1 ARM, and 1 Gas Stack QUESTION B.17 [1.0 point]
You are currently the licensed operator at UWNR. Which ONE of the following will violate 10 CFR Part 55.53 Conditions of licenses?
- a. Last requalification operating test was 13 months ago.
- b. Last requalification written examination was 13 months ago.
- c. Last quarter you were the licensed operator for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- d. Last licensed renewal was 36 months ago.
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.18 [1.0 point, 0.33 each]
Match the following limitations in Column A with its specification in Column B (Assume natural convection; Answers may be used more than once or not at all)
Column A Column B
- a. Safety Limit 1. 1 kW maximum power to Pulse
- b. Limiting Safety System Setting 2. Maximum 1.25MW
- c. Limiting Condition for Operation 3. Maximum fuel temperature 1150oC QUESTION B.19 [1.0 point]
Which ONE of the following 10 CFR Parts specifies the requirement for applicants to submit NRC Form 396 and 398 to the U.S. NRC prior to sitting for an RO or SRO licensing examination?
- a. 19
- b. 20
- c. 50
- d. 55 QUESTION B. 20 [1.0 point]
According to the UWNR Emergency Plan, transportation of a contaminated and injured person requiring transport to the hospital will be by____________?
- a. Senior Reactor Operator
- b. Reactor Safety Committee
- c. UW Police Department
- d. Madison Fire Department
(***** End of Category B *****)
Category C: Facility and Radiation Monitoring Systems QUESTION C.01 [1.0 point]
Which ONE of the following is the material used as a neutron poison in the Transient Rod?
- a. Erbium
- b. Cadium
- c. Boron
- d. Aluminum QUESTION C.02 [1.0 point]
Which ONE of the following best describes how a Compensated Ion Chamber (CIC) operates?
- a. The CIC has two chambers, one is coated with Uranium-235 for fission reaction and the other is coated with Boron-10 for (n,a) reaction
- b. The CIC has only one chamber coated with Uranium-235 for fission reaction
- c. The CIC has two chambers, both can sense gamma rays but only one is coated with Boron-10 for (n,a) reaction
- d. The CIC has only one chamber coated with Boron-10 for (n,a) reaction QUESTION C.03 [1.0 point]
Which ONE of the following represents the reactor being in a secured condition?
- a. The reactor is subcritical by at least 0.7% k/k
- b. Regulating blade replacement is in progress with the control power key switch in the off position with the key removed and under the control of a licensed operator
- c. The reactor is in the rod drop test mode and a licensed operator is in direct charge of the operation
- d. Insufficient moderator to attain criticality QUESTION C.04 [1.0 point]
If a presence of ________ is found in the intermediate side of the primary heat exchanger, a possible leak occurs from the primary system to the intermediate system.
- a. Sodium-24
- b. Xenon-131
- c. Argon-41
- d. Nitrogen-16
Category C: Facility and Radiation Monitoring Systems QUESTION C.05 [1.0 point]
The Log-N Channel is the neutron flux monitoring channel that provides a signal indicating which ONE of the following?
- a. Linear - a result from the reactor power in a generally straight or nearly straight line
- b. Period - the time required for reactor power to change by a factor of about 2.718
- c. Percent power - ability to readout in a way specified by a certain amount resulting from the reactor power
- d. Count rate - the total number of emissions per amount of time as a result of the reactor power QUESTION C.06 [1.0 point]
Which ONE of the following is the MAIN purpose of the thermal column?
- a. To enhance natural convection flow
- b. Provide a thermal neutron flux for experiments
- c. Provide a fast (high energy) neutron flux for experiments
- d. To shield a radiation dose from reactor core to the experiment area QUESTION C.07 [1.0 point]
Which ONE of the following devices ensures the reactor pool will not be completely drained when a large leak develops in the primary coolant piping?
- a. Siphon Break
- b. Heat Exchanger
- c. Intermediate Coolant System
- d. Primary Coolant Pump QUESTION C.08 [1.0 point]
The pneumatic system uses what gas to move rabbit samples into and out of the reactor?
- a. Air
- b. Nitrogen
- c. Hydrogen
- d. Carbon Dioxide
Category C: Facility and Radiation Monitoring Systems QUESTION C.09 [1.0 point]
Which ONE of the following regions of the pulse size versus applied voltage characteristic curve does UNWRs Log-N channel operate?
- a. Proportional
- b. Ion Chamber
- d. Limited Proportional QUESTION C.10 [1.0 point]
Which ONE of the following produces significant quantities of Nitrogen-16 in the reactor pool water?
- a. Oxygen-16
- b. Argon-41
- c. Cobalt-60
- d. Iodine-131 QUESTION C.11 [1.0 point]
Which power channel provides the period indication?
- a. Startup
- b. Log-N
- c. Pulse
- d. Linear QUESTION C.12 [1.0 point]
Which ONE of the following is correct regarding the Stack Air Monitor (SAM) and Continuous Air Monitor (CAM)?
Category C: Facility and Radiation Monitoring Systems QUESTION C.13 [1.0 point]
What is the primary function of the graphite sections on both sides of the fuel element?
- a. Absorb thermal neutrons
- b. Absorb fission product gases
- c. Reduces neutron leakage
- d. Increases fast neutron flux QUESTION C.14 [1.0 point]
Which ONE of the following is the method used to determine the safety blade position?
- a. The position indication is an odometer style mechanical counter with a contact wiper on each wiper on each unit disc that closes a circuit for each digit of the specific unit.
- b. As the rod moves, it move into or out of a coil, generating a signal proportional to rod position
- c. A logic circuit receives input from two sensors which count 100 pulses per revolution along with detecting direction, converting these signals to rod position
- d. As the rod moves up and down, the magnet opens and closes a series of over 1000 limits switches which generate a signal which is converted to rod position QUESTION C.15 [1.0 point]
When the diffuser pump is set to automatic, it will start when the reactor power reaches what level?
- a. 25 kW
- b. 50 kW
- c. 75 kW
- d. 100 kW QUESTION C.16 [1.0 point]
What is the purpose of the small holes in the control blade shroud and guide tubes?
- a. Prevent excessive withdrawal speeds
- b. Ensures water displacement
- c. Holes allow for proper distribution of the flux
- d. Streams radiation in the proper direction
Category C: Facility and Radiation Monitoring Systems QUESTION C.17 [1.0 point]
Which ONE of the following conditions is the MAIN purpose a nuclear reactor core requires a neutron source for startup?
- a. Prevent the period becoming too short and resulting in an inadvertent power excursion
- b. Provide enough delayed neutrons for all nuclear instrumentations before the reactor can go to a critical position
- c. Ensure the reactor change from subcritical to critical by using neutron source ONLY
- d. Provide a reference point where all instruments undergo a check before the reactor is brought to a critical position QUESTION C.18 [1.0 point]
Which ONE of the following is the fuel element reflector?
- a. Aluminum
- b. Boron
- c. Cadmium
- d. Graphite QUESTION C.19 [1.0 point]
Which ONE of the following is used as the poison in UWNR safety blades?
- a. Boron Carbide
- b. Zirconium Hydride
- c. Aluminum Oxide
- d. Graphite
Category C: Facility and Radiation Monitoring Systems QUESTION C.20 [1.0 point]
Which ONE of the UWNR nuclear instrument channel detectors is depicted in the figure below?
- a. Fission Chamber
- b. Gamma Ion Chamber
- c. Compensated Ion Chamber
- d. Uncompensated Ion Chamber
(***** END OF CATEGORY C *****)
((***** END OF EXAM *****))
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.01 Answer: b
Reference:
DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 2, Module 4 A.02 Answer: c
Reference:
Keff1=1/(1- 1) = 1/(1-(-.05))= 0.952 Count1*(1-Keff1) = Count2*(1-Keff2) 300*(1-0.952) = 900(1- Keff2); Keff2 = 0.984 A.03 Answer: b
Reference:
Chart of the Nuclides A.04 Answer: d
Reference:
P=Poet/Tt=T*ln(P/Po) assume constant period=1; The smallest ratio of P/Po is the shortest time to complete A.05 Answer: b
Reference:
P = P0 e t/T --> T= t/Ln(P/ P0 )
T= 10/Ln(100/50 ); T = 14.4 sec.
A.06 Answer: c
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1982, Section 2.5.1, Pages 2-38 to 2-43 Nuclides and Isotopes, 17th Edition A.07 Answer: a
Reference:
P=Poet/ => 4=1* et/20 t = 20 sec*ln(4) = 27.7 sec A.08 Answer: a
Reference:
Decreasing the reactivity worth in the core will decrease the core excess A.09 Answer: c
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1988, Subcritical Multiplication process A.10 Answer: a. Alpha b. +1 0 c. Neutron d. Alpha (0.25 each)
Reference:
Chart of Nuclides A.11 Answer: d
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1982
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.12 Answer: b
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 3.3.1 A.13 Answer: b
Reference:
DOE Fundamentals of Reactor Theory, Volume 2, NP-03, pg. 52 The reactivity change per unit movement of a rod and is normally expressed as r/inch, k/k per inch, or pcm/inch A.14 Answer: c
Reference:
Burn, Introduction to Nuclear Reactor Operations, Figure 2.6, Page 2-39 A.15 Answer: b
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 3.3.3, page 3-
- 21. = keff1-keff2/(keff1 x keff2) = 0.95-0.8 /(0.8*0.95)=0.197 k/k A.16 Answer: c
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 4.9
= +
eff A.17 Answer: c
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, 1982, Figure 2.6, page 2-39 A.18 Answer: d
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1988 A.19 Answer: c
Reference:
DOE Fundamentals Handbook and Nuclear Data Tables Probability = f/(f+ a) = 585/(585 + 98) = 585/683 = 0.8565 or 0.857 A.20 Answer: a
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 3.3.1
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.1 Answer: c
Reference:
UWNR Technical Specification 3.3 B.2 Answer: c
Reference:
UNWR, SAR 13.1 B.3 Answer: c
Reference:
DR1D12 = DR2D22 ;
20 mrem/hr at one meter (100 cm.)
results in 222.2 mrem/hr at 30 cm.
B.4 Answer: a. 1; b. 3; c. 3; d. 3
Reference:
10 CFR 20.1003, Definitions; 10 CFR 20.1004, Units of radiation dose B.5 Answer: d
Reference:
UNWR TS 3.8.2.5 B.6 Answer: a
Reference:
TS 3.3.3 B.7 Answer: b
Reference:
Instrument reads only dose with window closed. Instrument reads both and dose with window open. Therefore, dose is approximately window open dose less window closed dose.
B.8 Answer: b
Reference:
B.9 Answer: a. CAL; b. CHECK; c. TEST; d. TEST
Reference:
UWNR Technical Specifications 1.0 Definitions B.10 Answer: c
Reference:
UWNR Technical Specifications 3.8 B.11 Answer: d
Reference:
UWNR Emergency Plan, Table 2 B.12 Answer: a
Reference:
UWNR Technical Specifications 4.2 & 4.3
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.13 Answer: d
Reference:
DR1*(D1 ) 2= DR2*(D2) 2 ;
500 mrem (2) 2 = 5 mrem (d) 2 D = 20 ft B.14 Answer: c
Reference:
B.15 Answer: c
Reference:
UWNR Emergency Plan 8.1 B.16 Answer: b
Reference:
UWNR Technical Specifications 3.7.1, Table 3.7.1 B.17 Answer: a
Reference:
- 55.53(i) - the licensee shall have a biennial medical examination.
- 55.53(h), 55.59(c) - annual operating tests
- 55.53(e) - the licensee shall actively perform the functions of a licensed operator for a minimum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per calendar quarter.
- 55.53(h), 55.59(c)(1) - The requalification program must be conducted for a continuous period not to exceed 2 years License renewal : 6 years B.18 Answer: a. 3; b. 2; c. 1
Reference:
UWNR Technical Specifications 2.1, 2.2, and 3.1.3 B.19 Answer: d
Reference:
10 CFR 55 B.20 Answer: d
Reference:
UNWR Emergency Plan 8.3
Category C: Facility and Radiation Monitoring Systems C.01 Answer: c
Reference:
UWNR Technical Specification 5.5.3 C.02 Answer: c
Reference:
NRC Standard Question C.03 Answer: d
Reference:
UWNR Technical Specifications Definitions C.04 Answer: a
Reference:
NRC Standard Question C.05 Answer: b
Reference:
UWNR Training Manual, NE 234, Control and Instrumentation II.3, Page 7 C.06 Answer: b
Reference:
UWNR SAR 9.1.6 C.07 Answer: a
Reference:
UWNR SAR 5.5 and UWNR Training Manual NE 234, Reactor Water Systems C.08 Answer: d
Reference:
UWNR SAR 4.1.3.4 C.09 Answer: b
Reference:
UWNR SAR 7.2.3.2 C.10 Answer: a
Reference:
NRC Standard Question C.11 Answer: b
Reference:
UWNR Training Manual NE 234, Reactor Water Systems IV.I Purpose, Page 2 C.12 Answer: c
Reference:
UWNR SAR 7.7.2 C.13 Answer: c
Reference:
NRC Standard question and UWNR SAR 4.2.4
Category C: Facility and Radiation Monitoring Systems C.14 Answer: a
Reference:
UWNR SAR 4.2.2.5 C.15 Answer: d
Reference:
UWNR SAR 7.2.3 C.16 Answer: b
Reference:
UWNR SAR 4.2.2.1 C.17 Answer: a
Reference:
UWNR SAR 4.2.4 C.18 Answer: d
Reference:
UWNR SAR 4.1.2 and 4.2.3 C.19 Answer: a
Reference:
UWNR SAR 4.2.2.2 C.20 Answer: c
Reference:
NRC Standard Question