ML24024A247
| ML24024A247 | |
| Person / Time | |
|---|---|
| Site: | Purdue University |
| Issue date: | 02/10/2024 |
| From: | Travis Tate NRC/NRR/DANU/UNPO |
| To: | Chatzidakis S Purdue University Research Reactor |
| References | |
| 50-182/OL 24-01 OL 24-01 | |
| Download: ML24024A247 (1) | |
Text
Dr. Stylianos Chatzidakis, Associate Reactor Director 1290 Nuclear Engineering Building School of Nuclear Engineering Purdue University West Lafayette, IN 47907
SUBJECT:
EXAMINATION REPORT NO. 50-182/OL 24-01, PURDUE UNIVERSITY REACTOR (PUR-1)
Dear Dr. Chatzidakis:
During the week of December 11, 2023, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Purdue University research reactor (PUR-1). 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 C. DeSouza at (301) 415-0747 or via email at Michele.DeSouza@nrc.gov.
Sincerely, Travis L. Tate, Chief Non-Power Production and Utilization Facility Oversight Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation Docket No. 50-182/OL 24-01
Enclosures:
- 1. Examination Report No. 50-182/OL 24-01
- 2. Written examination cc: w/enclosures to GovDelivery SubscribersFebruary 10, 2024 Signed by Tate, Travis on 02/10/24
ML24024A247 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME MDeSouza AHughes TTate DATE 01/08/2024 1/30/2024 2/10/2024 U.S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT
REPORT NO.: 50-182/OL-24-01
FACILITY DOCKET NO.: 50-182
FACILITY LICENSE NO.: R-87
FACILITY: Purdue University Reactor (PUR-1)
EXAMINATION DATES: December 11-14, 2023
SUBMITTED BY: ________ 01/10/2024 Michele C. DeSouza, Chief Examiner Date
SUMMARY
During the week of December 11, 2023, the NRC administered operator licensing examinations to five Reactor Operator (RO) candidates and one Senior Reactor Operator-Upgrade (SROU) candidate. All candidates passed all applicable portions of the examinations and tests.
REPORT DETAILS
- 1. Examiner: Michele C. DeSouza, Chief Examiner, NRC
- 2. Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL
Written 5/0 0/0 5/0
Operating Tests 5/0 1/0 6/0
Overall 5/0 1/0 6/0
- 3. Exit Meeting:
True Miller, Reactor Supervisor, Purdue University Reactor Dr. Stylianos Chatzidakis, Associate Reactor Director, Purdue University Reactor 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.
Enclosure 1 Purdue University
Operator Licensing Examination
Week of December 11, 2023
Enclosure 2 U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION
FACILITY: Purdue University
REACTOR TYPE: LOCKHEED
DATE ADMINISTERED: December 14, 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 and an overall grade of 70 percent or greater.
- 12. There is a time limit of three (3) hours for completion of the examination.
Category A: Reactor Theory, Thermodynamics, & Facility Operating Characteristics
A N S W E R S H E E T
Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
A01 a b c d _____
A02 a b c d _____
A03 a __________ b __________ c __________ d __________ (0.25 each)
A04 a b c d _____
A05 a __________ b __________ c __________ d __________ (0.25 each)
A06 a b c d _____
A07 a b c d _____
A08 a b c d _____
A09 a b c d _____
A10 a b c d _____
A11 a b c d _____
A12 a b c d _____
A13 a b c d _____
A14 a b c d _____
A15 a b c d _____
A16 a b c d _____
A17 a b c d _____
A18 a b c d _____
A19 a b c d _____
A20 a b c d _____
(***** END OF CATEGORY A *****)
Category B: Normal/Emergency Operating Procedures and Radiological Controls
A N S W E R S H E E T
Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
B01 a __________ b __________ c __________ d __________ (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 __________ (0.25 each)
B11 a b c d _____
B12 a b c d _____
B13 a b c d _____
B14 a b c d _____
B15 a __________ b __________ c __________ (0.33 each)
B16 a b c d _____
B17 a b c d _____
B18 a b c d _____
B19 a b c d _____
B20 a b c d _____
(***** END OF CATEGORY B *****)
Category C: Facility and Radiation Monitoring Systems
A N S W E R S H E E T
Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
C01 a b c d _____
C02 a b c d _____
C03 a b c d _____
C04 a b c d _____
C05 a b c d _____
C06 a __________ b __________ c __________ (0.33 each)
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 __________ (0.25 each)
(***** END OF CATEGORY C *****)
(********** END OF EXAMINATION **********)
EQUATION SHEET
2 0.1sec1 QmcPTmH UAT Pmax 2 eff
t S S
eff CR1 1CR22 CR 1K CR 1K SUR 26.06 1 eff1 2 eff2
1 M 1 CR2 P P 10SUR(t)
P P0 1 K CR 0 eff 1
1 Keff1 1 K
- M 1 K SDM eff
eff2 Keff
= + 0.693 K K eff2 eff1 T1 2 K K eff1eff2
Keff1 DR DR et 2 2 K 0 DR1 d1 DR2d2 eff
6CiE n 2 2 DR 2 1 R2 Peak2 Peak1
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]
Which ONE of the following most accurately describes the reason that fission products such as Xenon-135 and Samarium-149 have the most substantial impact in reactor design and operation?
- a. Xenon-135 and Samarium-149 cause excess positive reactivity in the core.
- b. Xenon-135 and Samarium-149 burn up results in an increase in the thermal flux.
- c. Xenon-135 and Samarium-149 have large absorption cross sections resulting in a large removal of neutrons from the reactor.
- d. Xenon-135 and Samarium-149 produce fast fission neutrons, resulting in the net increase in the fast neutron population of the reactor core.
QUESTION A.02 [1.0 point]
Given a reactor period of 16.00 seconds, how long will it take for reactor power to quadruple?
- a. 17.88
- b. 20.06
- c. 22.18
- d. 31.63
QUESTION A.03 [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.
(Assume fuel temperature unchanged)
As moderator temperature increases, [Column A] [Column B].
Column A Column B
- a. Resonance escape probability 1. Increases
- b. Thermal non-leakage probability 2. Decreases
- c. Fast non-leakage probability
- d. Thermal utilization factor Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics
QUESTION A.04 [1.0 point]
The reactor is scrammed from 250 kW. After an initial power drop to 25 kW, the power level is decreasing at a constant period. What is the reactor power seven minutes later?
- a. 22.9 kW
- b. 14.8 kW
- c. 131 watts
- d. 13.0 watts
QUESTION A.05 [1.0 point, 0.25 each]
Replace X with the type of decay necessary (Alpha, Beta, Gamma or Neutron emission) to produce the following reactions. Choices may be used once, more than once, or not at all.
- a. 92U238 90Th234 + X
- b. 83Bi203 82Pb203 + X
- c. 2He4 + 4Be9 6C12 + X
- d. 84Po210 82Pb206 + X
QUESTION A.06 [1.0 point]
While bringing the reactor critical, which ONE of the following describes how a subcritical reactor responds to equal insertions of positive reactivity?
- a. Each reactivity insertion results in a smaller increase in neutron flux resulting in a shorter time to stabilize.
- b. Each reactivity insertion results in a smaller increase in neutron flux resulting in a longer time to stabilize.
- c. Each reactivity insertion results in a larger increase in neutron flux resulting in a shorter time to stabilize.
- d. Each reactivity insertion results in a larger increase in neutron flux resulting in a longer time to stabilize.
QUESTION A.07 [1.0 point]
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics
A reactor is slightly supercritical (k=1.001) with a thermal utilization factor of 0.900. A control rod is inserted to bring the reactor back to critical. Assuming all other factors remain unchanged, what is the new value for the thermal utilization factor?
- a. 0.899
- b. 0.876
- c. 0.799
- d. 0.711
QUESTION A.08 [1.0 point]
Which ONE of the following describes Integral Rod Worth?
- a. The reactivity change per unit movement of a rod.
- b. The plot of the slope of the change in reactivity over the change in rod position (/x).
©NntrolNro-NwortNw©nNins©rt©-NtNmximumNr©torNluxT
-TNNN©NtotlNt©N-NtNNprtiulrNpositionNoNwit-rwlT
QUESTION A.09 [1.0 point]
In a collision to which ONE of the following atoms will a fast neutron lose the most energy?
- a. U238
- b. C 12
- c. H 2
- d. H 1
QUESTION A.10 [1.0 point]
Delayed neutrons are produced by which ONE of the following?
- a. decay of N-16
- b. directly from fission
- c. pair production process
- d. decay of fission fragments
QUESTION A.11 [1.0 point]
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics
Which ONE of the following factors in the six-factor formula are NOT affected by the enrichment of U-235?
- a. Fast Fission Factor
- b. Thermal Utilization Factor
- c. Reproduction Factor
- d. Resonance Escape Probability
QUESTION A.12 [1.0 point]
Which ONE of the following is the definition of reactivity?
- a. Rate of change of reactor power in neutron per second.
- b. Fractional change in neutron population per generation.
- c. Number of neutrons by which population changes per generation.
- d. Change in the number of neutrons per second that causes a fission event.
QUESTION A.13 [1.0 point]
Which ONE of the following is defined as the balance between production of neutrons and their absorption in the core for which core leakage can be neglected?
- a. Utilization Factor.
- b. Infinite Multiplication Factor.
- c. Effective Multiplication Factor.
- d. Reproduction Factor.
QUESTION A.14 [1.0 point]
A subcritical reactor has a keff of 0.721. How much reactivity is added to change the keff to 0.987?
- a. 0.117 k/k
MT585Nk/k
MT-Y8Nk/k
MT/8-Nk/k QUESTION A.15 [1.0 point]
What is the meaning of any point on a differential rod worth curve?
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics
- a. The negative reactivity added as the rod is inserted.
- b. The cumulative area under the differential curve starting from the bottom of the core.
- c. The zero reactivity when the rod is on the bottom and the positive reactivity being added as the rod is withdrawn.
- d. The amount of reactivity of one unit (e.g. one inch, one percent) of rod motion would insert at that position in the core.
QUESTION A.16 [1.0 point]
Which ONE of the following materials has a primary purpose of thermalizing neutrons?
- a. Absorber
- b. Reflector
- c. Moderator
- d. Deflector
QUESTION A.17 [1.0 point]
A reactor contains a neutron source of 1250 neutrons/second. If the stable total neutron production rate is 5150 neutrons/second, what is the value of keff?
- a. 0.696
- b. 0.757
- c. 0.805
- d. 0.958
QUESTION A.18 [1.0 point]
Given the thermal neutron flux (Ø) is 1.0 x 1013 neutrons/cm2/second, and the macroscopic cross-section ( f) for fission is 0.1 cm-1. The fission rate is:
- a. 1.0 x 1012 fissions/cm/second
- b. 1.0 x 1014 fissions /cm/second
- c. 1.0 x 1012 fissions/cm3/second
- d. 1.0 x 1014 fissions/cm3/second Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics
QUESTION A.19 [1.0 point]
Which ONE of the following best describes the importance of a negative temperature coefficient of reactivity?
- a. An increase in reactor power causes an increase in fuel burnup which results in a positive reactivity addition, causing the power increase to slow or stop.
- b. An increase in reactor power causes an increase in fuel temperature which results in a negative reactivity addition, causing the power increase to slow or stop.
- c. An increase in reactor power causes an increase in fuel temperature which results in a positive reactivity addition, causing the power increase to slow or stop.
- d. An increase in reactor power causes an increase in fuel burnup which results in a negative reactivity addition, causing the power increase to slow or stop.
QUESTION A.20 [1.0 point]
The moderator temperature coefficient for a reactor is 0.00124 k/k/ oC. What is the total reactivity change caused by a temperature decrease of 40oC?
- a. 0.007
- b. 0.030
- c. 0.042
- d. 0.050
(***** END OF CATEGORY A *****)
Category B: Normal/Emergency Operating Procedures and Radiological Controls
QUESTION B.01 [1.0 point, 0.25 each]
Match the conditions or events in Column A to the appropriate Purdue emergency Class in Column B. Options in Column B may be used once, more than once, or not at all.
Column A Column B
- a. Individual contamination. 1. Non-reactor related safety event
- b. Fire on reactor control panel. 2. Notification of unusual event
- c. Tornado impacting the facility. 3. Alert
- d. Personnel injury. 4. Site Area Emergency
QUESTION B.02 [1.0 point]
Which ONE of the following is NOT allowed as an experiment in the reactor under any circumstances?
- a. Fueled experiment that yields 10 millicuries Iodine-131.
- b. 15 milligrams of explosive TNT.
- c. The reactivity worth of a movable experiment is 0.003 k/k.
- d. The reactivity worth of a secured experiment is 0.004 k/k.
+F6*& qTM- OTMNpoint#
Which ONE of the following channels provides the function of 2 cps rod withdrawal interlock?
- a. Channel #1
- b. Channel #2
- c. Channel #3
- d. Channel #4
QUESTION B.04 [1.0 point]
Which ONE of the following channels is a compensated ion chamber and provides change rate and power?
- a. Channel 1
- b. Channel 2
- c. Channel 3
- d. Channel 4 Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.05 [1.0 point]
In accordance with 10 CFR 20, which ONE of the following correctly defines the total effective dose equivalent (TEDE)?
- a. The sum of the products of the weighting factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to these organs or tissues.
- b. The sum of the effective dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures).
- c. The concentration of a given radionuclide in air which, if breathed by the reference man for a working year of 2,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> under conditions of light work, results in an intake of one ALI.
- d. The sum of the products of the dose equivalent to the organ or tissue and the weighting factors applicable to each of the body organs or tissues that are irradiated.
QUESTION B.06 [1.0 point]
All of the following are Technical Specifications requirements EXCEPT which ONE of the below?
- a. Reactor pool temperature shall be less than 30°C.
- b. A minimum of 13 feet of water above reactor core during operations.
- c. The sum of the absolute values of reactivity worths of all secured experiments shall not exceed 0.003 k/k.
- d. The pool water conductivity shall not exceed 3 microSiemens/cm.
QUESTION B.07 [1.0 point]
Which ONE of the following is the greatest immediate concern in the event of a significant loss of reactor pool water due to a rupture of the pool wall?
- a. Cladding rupture resulting in a fission product release.
- b. Groundwater contamination to the surrounding water table.
- c. Increased personnel exposure due to higher amounts of radiation.
- d. Zirconium Hydride interaction with oxygen in air, releasing explosive hydrogen gas due to the TRIGA fuel overheating.
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.08 [1.0 point]
A sample reads 325 mrem/hr at a distance of 3 feet from the source. How far away from the source will the reading be 10 mrem/hr?
- a. 17 feet
- b. 21 feet
- c. 34 feet
- d. 65 feet
QUESTION B.09 [1.0 point]
An experiment reading 65.00 mrem/hr was removed from the reactor. Four hours later, it reads 6.00 mrem/h. What is the half-life of the radioisotope in the experiment sample?
- a. 1.16 hr
- b. 1.28 hr
- c. 1.55 hr
- d. 2.12 hr
QUESTION B.10 [1.0 point, 0.25 each]
For each ONE of the following, identify the required surveillance frequency as DAILY, MONTHLY, BIANNUALLY, or ANNUALLY. Answers may be used once, more than once, or not at all.
- a. Primary coolant conductivity
- b. Scram channel check prior to operations
- c. Dampers
- d. Rod drop times
QUESTION B.11 [1.0 point]
Which ONE of the following in NOT in the line of succession for Emergency Director, in accordance with Purdue Emergency Plan?
- a. Purdue, Dean of College of Engineering
- b. Purdue Facility Director
- c. Purdue Associate Facility Director
- d. Senior Reactor Operator Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.12 [1.0 point]
10 CFR Part ________ requires all applicants for a reactor operator or senior reactor operator license to submit NRC Form 396 and 398 to the US NRC before taking the examination.
- a. 19
- b. 20
- c. 50
- d. 55
QUESTION B.13 [1.0 point]
Purdue emergency plan accident scenarios shall include all the following EXCEPT which ONE of the following.
- a. Medical emergency drills involving a simulated contaminated individual.
- b. Radiological monitoring including contamination control methods, dose rate measurements, nonessential personnel evacuation, and record keeping.
- c. Communication drills designed to ensure reliability of the system(s) and correct transmission and receipt of messages.
- d. Submission and approval thru the Nuclear Regulatory Commission prior to implementation.
QUESTION B.14 [1.0 point]
Which ONE of the following is classified as a Protective Action?
- a. Actions to correct and terminate an emergency.
- b. Actions taken after an emergency to restore the facility to its pre-emergency condition.
- c. Actions taken during or after an emergency to obtain and process information which is necessary to make decisions to implement specific emergency procedures.
- d. Actions taken in anticipation of or after an emergency has occurred to protect public health and safety of individuals and to prevent damage to property.
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.15 [1.0 point, 0.33 each]
Fill in the blanks with the Limiting Conditions for Operation in Column B listed in the Purdue Technical Specifications.
Column A LCO
- a. Maximum Excess keff _____ % (0.6/0.7/0.8)
- b. Licensed Reactor Power _____ kW (10/12/15)
- c. Fuel Temperature Maximum _____ oC (510/520/530)
QUESTION B.16 [1.0 point]
During a routine radiation survey, a dose rate of 150 mrem/hr at a distance of 2 feet from a pneumatic transfer tube is detected. How should this area be posted?
- a. No posting is required
- b. Contaminated Area
- c. Radiation Area
QUESTION B.17 [1.0 point]
Which ONE of the following is the MINIMUM number of required radiation monitoring systems to be classified as operable in accordance with Purdue Technical Specifications?
QUESTION B.18 [1.0 point]
Which ONE of the following statements correctly describes the relationship between the Safety Limit (SL) and the Limiting Safety System Setting (LSSS)?
- a. The SL is a maximum operational limiting value that prevents exceeding the LSSS during normal operations.
- b. The SL is a parameter that assures the integrity of the fuel cladding. The LSSS initiates protective actions to preclude reaching the SL.
- c. The SL is a maximum setpoint for instrumentation response. The LSSS is the minimum number of channels required to be operable.
- d. The LSSS is a parameter that assures the integrity of the fuel cladding. The SL initiates the protective action to preclude reaching the LSSS.
QUESTION B.19 [1.0 point]
Which ONE of the following changes must be submitted to NRC for approval prior to implementation?
- a. Remove a definition of Channel Test listed in the Purdue Technical Specifications.
- b. Replace a primary coolant pump with an identical pump.
- c. Add new limitation to the Pre-Startup Checklist Procedure.
- d. Add more responsibilities to the Radiation Safety Officer listed in the radiation safety procedure.
QUESTION B.20 [1.0 point]
Assume you are currently a licensed operator at Purdue reactor. Which ONE of the following is a requirement of 10 CFR 55, Operators Licenses?
- a. All licensed operators must pass an annual written requalification exam.
- b. All licensed operators must successfully complete a continuous requalification program, not to exceed 24 months.
- c. All licensed operators must actively perform the functions of an operator or senior operator for a minimum of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per quarter to maintain active status.
- d. All licensed operators must have a medical examination by a physician every 3 years.
(***** END OF CATEGORY B *****)
Category C: Facility and Radiation Monitoring Systems
QUESTION C.01 [1.0 point]
Which ONE of the following is the neutron absorbing material in the shim safety rods?
- a. Boron
- b. Cadmium
- c. Aluminum
- d. Stainless Steel
QUESTION C.02 [1.0 point]
Which ONE of the following is NOT part of the initial conditions in accordance with Purdue SOP-07-05, SOP for Core Loading?
- a. Complete the prestart checkout.
- b. A minimum of two people must be present during all operations.
- c. An SRO must be present to move the actual fuel or remove a control rod.
- d. Install an auxiliary Geiger-Mueller detector, inside the reflector, near the neutron source.
QUESTION C.03 [1.0 point]
According to the Purdue Continuous Air Monitor (CAM) SOP, which ONE of the following is the Continuous Air Monitor (CAM) radionuclide of interest?
- a. Nitrogen-16
- b. Argon-41
- c. Cesium-137
- d. Radium-222 Category C: Facility and Radiation Monitoring Systems
QUESTION C.04 [1.0 point))
Which ONE of the following nuclear safety channels does NOT have a function of a rod withdrawal interlock?
- a. Channel #1
- b. Channel #2
- c. Channel #3
- d. None of the above
QUESTION C.05 [1.0 point]
Which ONE of the following correctly lists the FREQUENCY for a pool water sample and what is ANALYZED?
- a. Monthly, gross alpha and beta
- b. Quarterly, neutrons
- c. Bi-Annually, gammas
- d. Whenever there is a change in core configuration, all isotopes
QUESTION C.06 [1.0 point, 0.33 point each]
Select the correct limitation in Column B with the Purdue Technical Specification in Column A.
Column A Column B
- a. Safety Limit Fuel Temperature 500/515/530 oC
- b. Limiting Safety System Setting Max 12/15/18 kW Power Level Scram
- c. Limiting Condition for Operations 25/30/35 oC Primary Coolant Temperature
QUESTION C.07 [1.0 point]
Which ONE of the following is the radio-iodine level that must not be exceeded for fueled experiments?
- a. 0.4 Curies
- b. 0.5 Curies
- c. 0.8 Becquerels
- d. 0.9 Becquerels Category C: Facility and Radiation Monitoring Systems
QUESTION C.08 [1.0 point]
Which ONE of the following is the material for the LEU fuel cladding?
- a. 304 Stainless Steel
- b. Boron Stainless Steel
- c. 6061 Aluminum Alloy
- d. Borated Graphite
QUESTION C.09 [1.0 point]
Which ONE of the following monitors is a proportional detector?
- a. Console
- b. Pool Top
- c. Water Process
- d. Continuous Air Monitor
QUESTION C.10 [1.0 point]
When using Purdue Procedure M-6 to determine the excess reactivity, the Technical Specification max excess reactivity allowed is __________ and shall be determined at a power level not greater than __________.
15 wattsa. 0.005 k/k,
10 wattsb. 0.006 k/k,
- c. 0.001 k/k, 5 watts
12 watts d. 0.004 k/k,
QUESTION C.11 [1.0 point]
When using RMS-3, RAM calibration procedure to calibrate the Radiation Area Monitors (RAM) which ONE of the following radioactive sources is used?
- a. Boron-10
- b. Cobalt-60
- c. Cesium-137
- d. Radon-222 Category C: Facility and Radiation Monitoring Systems
QUESTION C.12 [1.0 point]
Which ONE of the following indicates the cleanest pool water?
- a. Lowest pH
- b. Highest pH
- c. Highest resistivity
- d. Highest conductivity
QUESTION C.13 [1.0 point]
All fuel elements shall be stored in a geometrical array where the keff is less than ________ for all conditions of moderation.
- a. 0.8
- b. 0.9
- c. 1.0
- d. 1.1
QUESTION C.14 [1.0 point]
In accordance with Purdue RMS-3 procedure, when calibrating a Reactor Room RAM which points are used to verify linearity?
- a. 2 mR/hr and 10 mR/hr
- b. 1 mR/hr, 7.5 mR/hr, and 15 mR/hr
- c. 2 mR/hr, 5 mR/hr, and 20 mR/hr
- d. 5 mR/hr and 50 mR/hr
QUESTION C.15 [1.0 point]
In which region of the output signal versus applied voltage curve does a fission chamber operate?
- a. Ion Chamber
- b. Proportional
- d. Limited Proportional Category C: Facility and Radiation Monitoring Systems
QUESTION C.16 [1.0 point]
The irradiation facilities are comprised of which ONE of the following.
- a. 6 cylindrical aluminum tubes normally filled with graphite
- b. 20 graphite moderators
- c. 10 boron filled thru tubes
- d. 8 stainless steel transfer ports always filled with boron
QUESTION C.17 [1.0 point]
Which ONE of the following will occur if the reactor results in a change rate of 8% per second?
- a. Scram
- b. Setback
- c. Rod withdrawal interlock
- d. Reactor functions normally
QUESTION C.18 [1.0 point]
Which ONE of the following is the radioactive source used in the calibration of the Continuous Air Monitor (CAM)?
- a. Chlorine-35
- b. Chlorine-36
- c. Krypton-89
- d. Radon-222
QUESTION C.19 [1.0 point]
According to Purdue SOP Calibration of Pocket Dosimeters, what is the required calibration frequency?
- a. Monthly
- b. Quarterly
- c. Bi-annually
- d. Annually Category C: Facility and Radiation Monitoring Systems
QUESTION C.20 [1.0 point, 0.25 each]
Match the type of detector listed in Column B to the nuclear instrumentation channel in Column A. Options in Column B may be used once, more than once, or not at all.
Column A Column B
- a. Channel #1 1. Compensated Ion Chamber
- b. Channel #2 2. Uncompensated Ion Chamber
- c. Channel #3 3. Fission Chamber
- d. Channel #4
(***** END OF CATEGORY C *****)
(******** END OF EXAMINATION ********)
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics
A.01 Answer: c.
Reference:
DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2, Module 03, p. 34
A.02 Answer: c.
Reference:
P = P0 et/T 4 = 1t/16s ln(4) = ln(t/16s) 1.386 = t/16s t = (1.386)*16s t = 22.18 seconds
A.03 Answer: a. (2) Decreases; b. (2) Decreases; c. (2) Decreases; d. (1) Increases
Reference:
DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2, p. 16
A.04 Answer: c.
Reference:
P = P0 e-t/T P = 250 kW
- e(420s/-80s) 250 kW
- e-5.25 250 kW
- 0.0052475; P = 1.31 kW = 131 watts
A.05 Answer: a. alpha b. Beta (+1 0) c. neutron d. alpha
Reference:
NRC standard question
A.06 Answer: d.
Reference:
Burn, Introduction to Nuclear Reactor Operation, Section 5.3, p. 5-12
A.07 Answer: a.
Reference:
k=1.001; critical, k=1.000; 0.900 x 1.000//1.001 = 0.899
A.08 Answer: d.
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 3.4, p. 3-32 & UC-Irvine Chapter 6.4.1, Figure 6.6
A.09 Answer: d.
Reference:
NRC standard question
A.10 Answer: d.
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 3.2.1 Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics
A.11 Answer: a.
Reference:
DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2, Module 3, p. 16
A.12 Answer: b.
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 1.3.1, p. 1-5
A.13 Answer: b.
Reference:
DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2, Module 3, p. 2
A.14 Answer: c.
Reference:
Burn, Section 3.3.4, p 3-20-21
= (k eff2-keff1)/(keff1*keff2)
= (0.987-0.721) / (0.721*0.987); 0.266 / 0.712
= 0.374 k/k
Answer: d.
Reference:
Burn, Introduction to Nuclear Reactor Operations, Example 7.2b, p. 7-4
A.16 Answer: c.
Reference:
DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 1, Module 2, p. 23
A.17 Answer: b.
Reference:
Source CR = (S) / (1 - keff)
(1250) / (1 - keff) = 5150; 1250 / 5150 = (1 - keff) keff = 0.757 DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2, Module 4, p. 4
A.18 Answer: c.
Reference:
Fission rate = thermal flux (Ø) x macroscopic cross-section.
(f) = (1.0 x 10 13 neutrons/cm 2/second) x 0.1 cm-1 (f) = 1.0 x 10 12 neutrons/cm3/second Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 2.6.2
A.19 Answer: b.
Reference:
DOE Fundamentals Handbook, Nuclear Physics & Reactor Theory, Volume 2, Module 3, p. 28 Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics
A.20 Answer: d.
Reference:
DOE Fundamentals Handbook, Nuclear Physics & Reactor Theory, Volume 2, p.
21, = T*T = (0.00124 k/k / oC) * (40oC) = 0.050k/k
(***** END OF CATEGORY A *****)
Category B: Normal/Emergency Operating Procedures and Radiological Controls
B.01 Answer: a. 1-Non-reactor safety related event; b. 2-Notification of Unusual Event; c. 2-Notification of Unusual Event; d. 1-Non-reactor safety related event
Reference:
Purdue Emergency Plan 4, Table 1
B.02 Answer: b.
Reference:
Purdue Technical Specifications 3.1 & 3.5
B.03 Answer: a.
Reference:
Purdue Technical Specifications 3, Table 1
B.04 Answer: b.
Reference:
Purdue Operating Principles and Core Characteristics Table 0-2
B.05 Answer: b.
Reference:
B.06 Answer: c.
Reference:
Purdue Technical Specifications 3.1 and 3.3
B.07 Answer: c.
Reference:
NRC standard question
B.08 Answer: a.
Reference:
DR1*(D1)2 = DR2*(D2)2 ;
325 mrem*(3)2 = 10 mrem(d)2; 2925/10 = d2 d = 17 feet
B.09 Answer: a.
Reference:
DR=DR0e(-t) T1/2=0.693/
DR = DR0 e-.693/T1/2 6 = 65 e-(.693)(4)/T1/2 0.0923 = e-(2.772)/T1/2 ln(0.0923) = ln(e-(2.772)/T1/2)
-2.383 = -2.772 / T1/2 T1/2 = -2.772 / -2.383 T1/2 = 1.16 hr
B.10 Answer: a. Monthly; b. Daily; c. Biannually; d. Annually
Reference:
Purdue Technical Specifications 4.2 Category B: Normal/Emergency Operating Procedures and Radiological Controls
B.11 Answer: a.
Reference:
Purdue Emergency Plan, Section 3.1.1 and 3.1.4
B.12 Answer: d.
Reference:
B.13 Answer: d.
Reference:
Purdue Emergency Plan, Section 9.2
B.14 Answer: d.
Reference:
Purdue Emergency Plan, Section 2.0, Definitions
B.15 Answer: a. 0.6; b. 12; c. 530
Reference:
Purdue Operating Principles and Core Characteristics 1.1
B.16 Answer: d.
Reference:
B.17 Answer: c.
Reference:
Purdue Technical Specifications 3.2, Table II
B.18 Answer: b.
Reference:
NRC standard question
B.19 Answer: a.
Reference:
B.20 Answer: b.
Reference:
(***** END OF CATEGORY B *****)
C.01 Answer: a.
Reference:
Purdue SAR 1.3
C.02 Answer: d.
Reference:
Purdue SOP 07-05, SOP for Core Loading, 6, Initial Conditions
C.03 Answer: b or c.
Reference:
Purdue Technical Specifications 3.4, and Purdue SOP CAM, Appendix A
C.04 Answer: c.
Reference:
Purdue Technical Specifications 3.2, Table I
C.05 Answer: a.
Reference:
Purdue Technical Specifications 4.3
C.06 Answer: a. 530 oC; b. 12 kW; c. 30oC;
Reference:
Purdue Technical Specifications 2.1, 2.2, and 3.3
C.07 Answer: b.
Reference:
Purdue Technical Specifications 3.5
C.08 Answer: c.
Reference:
Purdue Technical Specifications 2.1
C.09 Answer: d.
Reference:
Purdue SAR 7.1, Table I, p. 79
C.10 Answer: b.
Reference:
Purdue Procedure M-6, Procedure for determining the Excess Reactivity
C.11 Answer: c.
Reference:
Purdue RMS-3, RAM Calibration Procedure
C.12 Answer: c.
Reference:
NRC standard question
C.13 Answer: a.
Reference:
Purdue Technical Specifications 5.4 C.14 Category B: Normal/Emergency Operating Procedures and Radiological Controls
Answer: c.
Reference:
Purdue RMS-3, RAM Calibration Procedure
C.15 Answer: b.
Reference:
NRC standard question
C.16 Answer: a.
Reference:
Purdue SAR 4.2, p. 39
C.17 Answer: b.
Reference:
Purdue Technical Specifications 3.2, Table I
C.18 Answer: b.
Reference:
C.19 Answer: c.
Reference:
Purdue SOP, Calibration of Pocket Dosimeters
C.20 Answer: a. 3; b. 1; c. 2; d. 2;
Reference:
Purdue SAR, Table 7-1, p. 82
(***** END OF CATEGORY C *****)
(******** END OF EXAMINATION ********)