ML23276B459

University of California - Irvine, Examination Report Letter No. 50-326/OL-24-01,

ML23276B459
Person / Time
Site:	University of California - Irvine
Issue date:	12/12/2023
From:	Travis Tate NRC/NRR/DANU/UNPO
To:	Shaka A University of California - Irvine
References
50-326/24-01 50-326/OL-24
Download: ML23276B459 (34)

Text

December 12, 2023 Dr. A.J. Shaka, Reactor Director Nuclear Reactor Facility Department of Chemistry University of California, Irvine 231A Rowland Hall Irvine, CA 92697-2025

SUBJECT:

EXAMINATION REPORT NO. 50-326/OL-24-01, UNIVERSITY OF CALIFORNIA-IRVINE

Dear Dr. Shaka:

During the week of October 16, 2023, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your University of California, Irvine Nuclear Research Facility. The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with Title 10 of the Code of Federal Regulations, Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Michele DeSouza at (301) 415-0747 or via email at Michele.DeSouza@nrc.gov.

Sincerely, Signed by Tate, Travis on 12/12/23 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. 50-326

Enclosures:

1. Examination Report No. 50-326/OL-24-01

2. Written examination cc: w/enclosures to GovDelivery Subscribers

ML23276B458 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME MDeSouza NJones TTate DATE 11/13/2023 12/12/2023 12/12/2023 U.S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-326/OL-24-01 FACILITY DOCKET NO.: 50-326 FACILITY LICENSE NO.: R-116 FACILITY: University of California - Irvine EXAMINATION DATES: October 16-20, 2023 SUBMITTED BY: ________ 10/23/2023 Michele C. DeSouza, Chief Examiner Date

SUMMARY

During the week of October 16, 2023, the NRC administered operator licensing examinations to six Reactor Operator (RO) candidates and one Senior Reactor Operator-Instant (SROI) candidate. One RO candidate failed the written examination and the operations test. One RO candidate failed the written examination. Four RO and one SROI candidates passed all applicable portions of the written examinations and operations tests. One applicant was withdrawn by the facility licensee prior to taking any portion of the written examination or operations test, therefore, this applicant is not being issued a license denial and is eligible to reapply without the wait time restriction.

REPORT DETAILS

1. Examiner: Michele C. DeSouza, Chief Examiner, NRC

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 4/2 1/0 5/2 Operating Tests 5/1 1/0 6/1 Overall 4/2 1/0 5/2

3. Exit Meeting:

John Keffer, Reactor Supervisor, UC-Irvine Dr. George Miller, Professor, UC-Irvine 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

University of California - Irvine Operator Licensing Examination Week of October 16, 2023 Enclosure 2

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: University of California-Irvine REACTOR TYPE: TRIGA DATE ADMINISTERED: October 20, 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 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 __________ (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 ANSWER SHEET Multiple Choice (Circle or X your choice)

If you change your answer, write your selection in the blank.

B01 a __________ b __________ c __________ d __________ (0.25 each)

B02 a b c d _____

B03 a b c d _____

B04 a b c d _____

B05 a b c d _____

B06 a b c d _____

B07 a b c d _____

B08 a b c d _____

B09 a b c d _____

B10 a __________ b __________ c _________ d __________ (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 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 __________ (0.33 each)

C07 a b c d _____

C08 a b c d _____

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 _____

C20 a __________ b __________ c __________ d __________ (0.25 each)

(***** END OF CATEGORY C *****)

(********** END OF EXAMINATION **********)

EQUATION SHEET

2 eff 0.1sec 1 Q m c P T m H UAT Pmax 2

t P P0 e S S SCR

• 110 4 sec 1 K eff SUR 26 .06 eff CR1 1 CR2 2 CR1 1 K eff1 CR2 1 K eff 2 1 M 1

2 CR P P0 10 SUR (t )

P P0 1 K eff CR1 1 K eff1 1 K eff

• M SDM 1 K eff 2 K eff

=

+ 0.693 K eff 2 K eff1 T1 2

K eff1 K eff 2 K eff 1 DR DR0 e t 2 DR1 d1 DR2 d 2 2

K eff 6 Ci E n 2 2 1 2 DR 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 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.02 [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 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]

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.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]

Which ONE of the following materials has a primary purpose of thermalizing neutrons?

a. Absorber

b. Reflector

c. Moderator

d. Deflector QUESTION A.07 [1.0 point]

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

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics 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).

c. The control rod worth when inserted at maximum reactor flux.

d. The total reactivity worth of the rod at a particular position of withdrawal.

QUESTION A.09 [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.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]

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

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.12 [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 following the scram?

a. 22.9 kW

b. 14.8 kW

c. 131 watts

d. 13.0 watts 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]

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.

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.15 [1.0 point]

As new fuel is being loaded into the core, the reactor operator is using a 1/M plot to monitor core loading. Which ONE of the following conditions could result in the OVER prediction of the number of fuel rods needed for criticality?

a. The detector and source are too close to each other.

b. Too much time elapses between subsequent core loadings.

c. The core fuel is loaded and then the detector is adjusted to reach criticality.

d. The detector is located so that core load starts away from the detector and subsequent loading proceeds towards the detector.

QUESTION A.16 [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.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

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics 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 QUESTION A.19 [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

b. 0.242 k/k

c. 0.374 k/k

d. 0.543 k/k QUESTION A.20 [1.0 point]

In a collision to which ONE of the following atoms will a fast neutron lose the most energy?

a. U238

b. C12

c. H2

d. H1

(***** 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 UC-Irvine 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. Fuel cladding damage; consistent with bubbling from fuel element in water. Class 0 - Events less severe than the lowest category

b. Fire in reactor control room.

Class 1 - Notification of unusual event

c. Imminent danger to the public anticipated because of the reactor. Class 2 - Alert

d. Earthquake felt in the facility. Class 3 - 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. Strontium-90 fueled experiment 10 millicuries.

b. 15 milligrams of explosive TNT.

c. The reactivity worth of a movable experiment is $3.00.

d. The reactivity worth of an individual experiment is $1.00.

QUESTION B.03 [1.0 point]

The calibration setting on the ___________ monitor should be changed last, as it will trigger a scram immediately when adjusting.

a. power range

b. power range linear

c. wide range

d. wide range linear

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.04 [1.0 point]

Which ONE of the following is NOT accurate in reference to reactor log entries?

a. Transient pulse data shall be recorded in red ink.

b. Core fuel changes shall be made in red ink.

c. Criticality status and pulse information in red ink.

d. Core reactivity worth core changes shall be underlined in red ink.

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 between 17°C and 25°C.

b. A minimum of 0.10 inches of H2O negative pressure difference between the control room and the outside of the building.

c. The sum of the absolute values of reactivity worths of all experiments shall not exceed

$3.00.

d. The pool water conductivity shall not exceed 3 micromhos/cm.

Category B: Normal/Emergency Operating Procedures and Radiological Controls 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.

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, QUARTERLY, or ANNUALLY. Answers may be used once, more than once, or not at all.

a. Channel test of the function of the Continuous Air Monitor (CAM) alarm

b. Calorimetric calibration of the power level monitoring channels

c. Control rod scram times

d. Pool water radioactivity

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.11 [1.0 point]

In accordance with the UC-Irvine Emergency Plan, which ONE of the following is the first person to be contacted in the event of a vague threat?

a. UC-Irvine Police

b. UC-Irvine Facility Director

c. Reactor Operator

d. Senior Reactor Operator 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]

In the event of an emergency, which ONE of the following is responsible for maintaining liaison with off-campus agencies?

a. Reactor operator

b. Senior reactor operator

c. Emergency Management Director

d. Reactor Operations Committee QUESTION B.14 [1.0 point]

Which ONE of the following is classified as a Class 1-Notification of Unusual Event?

a. Explosion in the region of the reactor core.

b. Noticeable abnormal loss of pool water.

c. Reduction in the level of pool water to below five feet above the reactor core.

d. Intrusion, or threat of intrusion of water into the facility.

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 UC-Irvine Technical Specifications.

Column A LCO

a. Core Excess Reactivity _____ $ (2.50/3.00/3.50)

b. Steady State Reactor Power _____ kW (200/250/275)

c. Reactivity Worth of both Transient Rods _____ $ (2.50/2.75/3.00)

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

d. High 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 UC-Irvine Technical Specifications?

a. 1 Radiation Area Monitor (RAM) and 1 Continuous Air Monitor (CAM)

b. 1 RAM and 2 CAM

c. 2 RAM and 1 CAM

d. 2 RAM and 2 CAM

Category B: Normal/Emergency Operating Procedures and Radiological Controls 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 UC-Irvine 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 UC - Irvine 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]

What is the MAIN reason for the control rod fuel followers?

a. Enhance their control characteristics.

b. Decrease the fast neutron flux in the core.

c. Increase the effectiveness for reactor pulsing.

d. Increase the core excess reactivity in the reactor core.

QUESTION C.02 [1.0 point]

Which ONE of the following is NOT part of the criteria to determine if a fuel element is damaged and should be removed from the core?

a. Burnup of the fuel element is greater than 25%.

b. Visual inspection identifies pitting, bulging or corrosion.

c. Growth in length over the original measurements exceeds 0.125 inches.

d. Traverse bend exceeds 0.0625 inches over the length of the element.

QUESTION C.03 [1.0 point]

A loss of fuel element integrity could arise from an excessive buildup of pressure between the fuel and the cladding. Which ONE of the following is the cause of the pressure?

a. Increase of the pool temperature causing dissociation between the hydrogen and oxygen resulting in the pressure on the cladding.

b. Contraction of the Uranium and expansion of the fuel creating an external implosion.

c. The presence of argon and helium intermixing at different molecular levels causing the pressure dissociation.

d. The presence of fission product gases and the dissociation of the hydrogen and zirconium in the fuel moderator.

Category C: Facility and Radiation Monitoring Systems QUESTION C.04 [1.0 point]

Which ONE of the following is NOT true regarding the configuration of the UC-Irvine TRIGA fuel elements?

a. Cladding shall be 304 stainless steel, at a nominal thickness of 0.020 inches.

b. The total Uranium content shall be nominally 8.5% by weight, enriched to less than 20%

Uranium-235.

c. An upper fitting with an engraved unique serial number shall be designed to fit a latching tool for fuel movement.

d. The hydrogen to zirconium atom ratio in the zirconium hydride shall be a nominal 1.00 hydrogen atoms to 1.64 zirconium atoms.

QUESTION C.05 [1.0 point]

Which ONE of the following reactor safety channels in NOT required when in PULSE mode?

a. Preset Timer

b. Reactor Power Level

c. Pool Water Temperature

d. Fuel Element Temperature QUESTION C.06 [1.0 point, 0.33 point each]

Identify the type of drive system in Column A with the rod type in Column B. Options in Column B may be used once, more than once, or not at all.

Column A Column B

a. Fixed Pneumatic Cylinder 1. Standard control rods

b. Rack and Pinion 2. Fast Transient rod

c. Adjustable Pneumatic Cylinder 3. Adjustable Transient rod

Category C: Facility and Radiation Monitoring Systems QUESTION C.07 [1.0 point]

Which ONE of the following uses the compressed air system?

a. Pneumatic transfer system

b. Rotary specimen rack

c. Transient rods

d. Standard control rods QUESTION C.08 [1.0 point]

The Eco Gamma Area Radiation Monitors warning is set to __________ and alarm is set to

a. 5 mR/hr and 10 R/hr

b. 5 mR/hr and 10 mR/hr

c. 2 mR/hr and 10 mR/hr

d. 2 R/hr and 10 R/hr QUESTION C.09 [1.0 point]

The Continuous Air Monitor (CAM) alarm is set to monitor which ONE of the following to protect personnel from exposure?

a. Nitrogen-16

b. Argon-41

c. Iodine-131

d. Radon-222

Category C: Facility and Radiation Monitoring Systems QUESTION C.10 [1.0 point, 0.25 each]

Match the scram in Column A to the initiating factor in Column B. Options in Column B may be used once, more than once, or not at all.

Column A Column B

a. Seismic 1. Wide Range Linear Monitor usually about 107% of full power

b. Period

2. Power range monitor usually

c. Linear Power about 106% of full power

d. Percent Power 3. Signal thru conduit to the reactor console with a set point of 0.03g

4. Not required by Technical Specifications; Wide Range Monitor set to about 3.2 seconds QUESTION C.11 [1.0 point]

In the event of a loss of power emergency, the diesel generator will power the below EXCEPT:

a. Security alarms

b. Emergency lights

c. Area Radiation Monitor alarms

d. Fuel Temperature indications 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

Category C: Facility and Radiation Monitoring Systems 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, 0.25 each]

Match the standard control rod switch when illuminated in Column A to the appropriate action in Column B. Options in Column B may be used once, more than once, or not at all.

Column A Column B

a. UP

1. Indicates the control rod & drive are at

b. DOWN the lower limit.

c. ON of CONT/ON 2. Indicates the control rod drive is at the top limit

d. CONT of CONT/ON

3. Control rod drive not down, assembly armature not down

4. Electromagnetic contact energized 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

c. Geiger-Mueller

d. Limited Proportional

Category C: Facility and Radiation Monitoring Systems QUESTION C.16 [1.0 point]

Which ONE of the following channels will display the peak power (nv) and energy (nvt) data?

a. Power range monitor

b. Wide range monitor

c. Wide range linear monitor

d. Period channel QUESTION C.17 [1.0 point]

The reactor operator is preparing for the Reactor Power Calibration. Which ONE of the following prerequisites is NOT required prior to the calibration?

a. Completing a normal start-up.

b. Removing any non-fixed experiments.

c. The reactor pool temperature below 18.5 °C but >170C.

d. The thermistor probe for the digital thermometer has been removed.

QUESTION C.18 [1.0 point]

Which ONE of the following best describes the reason for a high sensitivity of a Geiger-Mueller detector?

a. Coating with special nuclear material

b. A larger tube, so target area is bigger for all incident events

c. Lower voltage applied to the detector helps to amplify all incident events

d. Any incident radiation detected results in ionization of the entire detector QUESTION C.19 [1.0 point]

What is the primary isotope of concern created during operation of the pneumatic transfer system?

a. Nitrogen-16

b. Argon-41

c. Cobalt-60

d. Krypton-80

Category C: Facility and Radiation Monitoring Systems QUESTION C.20 [1.0 point, 0.25 each]

Match the items in Column A to the material make up in Column B. Options in Column B may be used once, more than once, or not at all.

Column A Column B

a. Fuel element 1. Single length poison section, air or void follower

b. Standard control rod 2. Fuel, graphite ends, no follower

c. Fast transient rod 3. Borated graphite, fuel follower

d. Adjustable transient control rod 4. Double length poison section, air or void follower

(***** END OF CATEGORY C *****)

(******** END OF EXAMINATION ********)

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.01 Answer: b.

Reference:

DOE Fundamentals Handbook, Nuclear Physics & Reactor Theory, Volume 2, Module 3, p. 28 A.02 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 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: b.

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 1.3.1, p. 1-5 A.05 Answer: a. alpha b. Beta (+1 0) c. neutron d. alpha

Reference:

NRC standard question A.06 Answer: c.

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 1, Module 2, p. 23 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: 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.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: 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.13 Answer: b.

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2, Module 3, p. 2 A.14 Answer: c.

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2, Module 03, p. 34 A.15 Answer: a or d.

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 5.5, p. 5-18 & 5-23 A.16 Answer: d.

Reference:

Burn, Introduction to Nuclear Reactor Operation, Section 5.3, p. 5-12 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 1013 neutrons/cm2/second) x 0.1 cm-1 (f) = 1.0 x 1012 neutrons/cm3/second Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 2.6.2

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.19 Answer: c.

Reference:

Burn, Section 3.3.4, p 3-20-21

= (keff2-keff1)/(keff1*keff2)

= (0.987-0.721) / (0.721*0.987); 0.266 / 0.712

= 0.374 k/k A.20 Answer: d.

Reference:

NRC standard question

(***** END OF CATEGORY A *****)

Category B: Normal/Emergency Operating Procedures and Radiological Controls B.01 Answer: a. Class 2-Alert; b. Class 1-Notification of Unusual Event; c. Class 2-Alert or Class 3-Site Area Emergency; d. Class 1-Notification of Unusual Event

Reference:

UC-Irvine Emergency Plan 4.0 B.02 Answer: a or c.

Reference:

UC-Irvine Technical Specifications 3.8 & 3.8.2 B.03 Answer: d.

Reference:

UC-Irvine SOP 3.3, Section 4.3 B.04 Answer: c.

Reference:

UC-Irvine SOP 3.3, Section 4.2 B.05 Answer: b.

Reference:

10 CFR 20.1003 B.06 Answer: b.

Reference:

UC-Irvine Technical Specifications 3.3.1, 3.3.2, 3.3.3, and 3.4 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. Daily; b. Annually; c. Annually; d. Quarterly

Reference:

UC-Irvine Technical Specifications 4.2, 4.3, and 4.5

Category B: Normal/Emergency Operating Procedures and Radiological Controls B.11 Answer: a.

Reference:

UC-Irvine Emergency Plan, Section 7.1 B.12 Answer: d.

Reference:

10 CFR Part 55 B.13 Answer: c.

Reference:

UC-Irvine Emergency Plan, Section 3.6 B.14 Answer: b.

Reference:

UC-Irvine Emergency Plan, Section 4.2 B.15 Answer: a. 3.00; b. 250; c. 3.00

Reference:

UC-Irvine Technical Specifications 3.1.1, 3.1.3, and 3.3.3 B.16 Answer: d.

Reference:

10 CFR 20 B.17 Answer: c.

Reference:

UC-Irvine Technical Specifications 3.7.1.a B.18 Answer: b.

Reference:

NRC standard question B.19 Answer: a.

Reference:

10 CFR 50.59 & 10 CFR 50.90 B.20 Answer: b.

Reference:

10 CFR Part 55

(***** END OF CATEGORY B *****)

Category C: Facility and Radiation Monitoring Systems C.01 Answer: d.

Reference:

UC-Irvine SAR 1.8 & UC-Irvine Instruction Manual Chapter 8.2.1 C.02 Answer: a.

Reference:

UC-Irvine Technical Specifications 3.1.6 C.03 Answer: d.

Reference:

UC-Irvine SAR 13.2.1, 1999 C.04 Answer: d.

Reference:

UC-Irvine Technical Specifications 5.3.3 C.05 Answer: b.

Reference:

UC-Irvine Technical Specifications 3.2.3, Table 2 C.06 Answer: a. (2) FTR; b. (1) Standard control rods; c. (3) ATR;

Reference:

UC-Irvine Instruction Manual Chapter 8.2 C.07 Answer: c.

Reference:

UC-Irvine Instruction Manual Chapter 9.2.6 C.08 Answer: c.

Reference:

UC-Irvine Instruction Manual Chapter 9.4.1 C.09 Answer: c.

Reference:

UC-Irvine Technical Specifications 3.7.1 C.10 Answer: a. 3; b. 4; c. 1; d. 2

Reference:

UC-Irvine Instruction Manual Chapter 9.1-5 C.11 Answer: d.

Reference:

UC-Irvine SAR 13.8 & UC-Irvine Instruction Manual Chapter 7.1.10 C.12 Answer: c.

Reference:

NRC standard question C.13 Answer: a.

Reference:

UC-Irvine Technical Specifications 5.4.a Enclosure 2

Category C: Facility and Radiation Monitoring Systems C.14 Answer: a. (2); b. (1); c. (4); d. (1 or 3);

Reference:

UC-Irvine SAR 7.2.1 & UC-Irvine Instruction Manual Chapter 9.1.1 C.15 Answer: b.

Reference:

UC-Irvine SAR 7.2.4 & UC-Irvine Instruction Manual Chapter 3.2.1-C & 9.1.2-B C.16 Answer: a.

Reference:

UC-Irvine SAR 7.2 & UC-Irvine Instruction Manual Chapter 9.1.2 C.17 Answer: d.

Reference:

UC-Irvine SOP, Section 4.3, Reactor Power Calibration, Item 4.3.1, Prerequisites, p. 4-11.

C.18 Answer: d.

Reference:

NRC standard question C.19 Answer: b.

Reference:

UC-Irvine Instruction Manual Chapter 4.5.5 C.20 Answer: a. 2; b. 3; c. 4; d. 1;

Reference:

UC-Irvine SAR 4-6, 4-7, and 4-8 & UC-Irvine Instruction Manual Chapter 8.2

(***** END OF CATEGORY C *****)

(******** END OF EXAMINATION ********)