Text

Examination Report Letter No. 50-326/OL-24-02, University of California-Irvine
	ML24113A005
Person / Time
Site:	University of California - Irvine
Issue date:	05/20/2024
From:	Travis Tate; NRC/NRR/DANU/UNPO
To:	Keffer J; University of California - Irvine
References
	50-326/OL-24-02 OL-24-02
	Download: ML24113A005 (1)
	v • d • e

John Keffer, Reactor Supervisor Nuclear Reactor Facility Department of Chemistry University of California - Irvine 1102 Natural Sciences 2 Irvine, CA 92697-2025

SUBJECT:

EXAMINATION REPORT NO. 50-326/OL-24-02, UNIVERSITY OF CALIFORNIA-IRVINE

Dear John Keffer:

During the week of April 29, 2024, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your University of California-Irvine Nuclear Reactor 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, 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-24-02

2. Written examination cc: w/enclosures to GovDelivery Subscribers May 20, 2024 Signed by Tate, Travis on 05/20/24

ML24113A005 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME MDeSouza NJones TTate DATE 5/20/2024 5/20/2024 5/20/2024 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:

50-326/OL-24-02 FACILITY DOCKET NO.:

50-326 FACILITY LICENSE NO.:

R-116 FACILITY:

University of California - Irvine EXAMINATION DATES:

Week of May 2, 2024 SUBMITTED BY:

SUMMARY

During the week of May 2, 2024, the NRC administered operator licensing examinations to one Reactor Operator (RO) retake candidate. The candidate 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 1/0 N/A 1/0 Operating Tests Excused N/A Excused Overall 1/0 N/A 1/0 3.

Exit Meeting:

John Keffer, Reactor Supervisor, University of California-Irvine 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.

5/3/2024 Michele C. DeSouza, Chief Examiner Date

University of California-Irvine Operator Licensing Examination Week of May 2, 2024

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:

University of California-Irvine REACTOR TYPE:

TRIGA DATE ADMINISTERED:

May 2, 2024 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 _____

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 __________ d __________ (0.25 each)

B16 a b c d _____

B17 a b c d _____

B18 a b c d _____

B19 a b c d _____

B20 a b c d _____

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

Category C: Facility and Radiation Monitoring Systems 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 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 **********)

EQUATION SHEET

=

+

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

2 2

max

P 1

sec 1.0

eff

T UA H

m T

c m

Q P

2 1

1 1

2 1

eff eff K

CR K

CR

2 2

1 1

CR CR sec 10 1

4

eff K

S S

SCR

1

eff SUR 06 26

te P

P 0

)

(

0 10 t

SUR P

P 1

2 1

1 CR CR K

M eff

0 1

P P

2 1

1 1

eff eff K

K M

eff eff K

K SDM

1 2

1 1

2 eff eff eff eff K

K K

K

693

.0 2

1 T

eff eff K

K 1

2 2

1 1

d DR d

DR

t e

DR DR

0

1 2

2 2

Peak Peak

2 6

R n

E Ci DR

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

[1.0 point]

You are performing a startup from a very low reactor power level. If you establish a 26 second period, approximately how long will it take to increase reactor power by a factor of 1000?

a. 1 minute

b. 3 minutes

c. 10 minutes

d. 30 minutes QUESTION A.02

[1.0 point]

Which ONE of the following is the material used for the purpose of thermalizing neutrons?

a.

Poison b.

Leakage c.

Absorber d.

Moderator QUESTION A.03

[1.0 point, 0.25 each]

Replace X with the type of primary 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. 92U238 90Th234 + X

b. 83Bi203 82Pb203 + X

c. 2He4 + 4Be9 6C12 + X

d. 84Po210 82Pb206 + X QUESTION A.04

[1.0 point]

After an initial power drop to 25 kW, the power level is decreasing at a constant 80 second period. What is the reactor power seven minutes?

a.

0.131 kW b.

0.291 kW c.

0.322 kW

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

0.573 kW QUESTION A.05

[1.0 point]

Which ONE of the following describes Integral Rod Worth?

a. The reactivity change per unit movement of a rod.

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

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

d. The plot of the slope of the change in reactivity over the change in rod position (/x).

QUESTION A.06

[1.0 point]

Which ONE of the following describes the relationship between reactivity and criticality?

a.

The smaller the absolute value of reactivity in the core, the further the reactor is from criticality.

b.

The larger the absolute value of reactivity in the core, the further the reactor is from criticality.

c.

Reactivity is zero when the reactor is critical, reactivity is negative when the reactor is supercritical.

d.

Reactivity is zero when the reactor is critical, reactivity is positive when the reactor is subcritical.

QUESTION A.07

[1.0 point]

Which ONE of the following is the expected stable neutron count rate, given a source strength of 1000 Neutrons/second and a multiplication factor of 0.8?

a. 700 N/sec

b. 5000 N/sec

c. 10,000 N/sec

d. 20,000 N/sec

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.08

[1.0 point]

Which ONE of the following design characteristics is the reason for the decrease in reactivity following an increase in fuel temperature in a TRIGA reactor?

a. Hexagonal fuel matrix

b. High fuel element reactivity worth

c. Negative temperature coefficient

d. Long delay time for transferring heat to the core cooling water QUESTION A.09

[1.0 point]

Several processes occur that may increase or decrease the available number of neutrons.

SELECT ONE of the following, six-factor formula terms, that describes an INCREASE in the number of neutrons during the cycle.

a. Reproduction Factor

b. Thermal Utilization Factor

c. Resonance Escape Probability

d. Thermal Non-Leakage Probability QUESTION A.10

[1.0 point]

Which ONE of the following best describes the likelihood of fission occurring in U-235 and U-238?

a.

Neutrons at low energy levels (eV) are more likely to cause fission with U-235 than neutrons at higher energy levels (MeV).

b.

Neutrons cross section of U-235 increases with increasing neutron energy, whereas neutron cross section of U-238 decreases with increasing neutron energy.

c.

Neutrons at low energy levels (eV) are more likely to cause fission with U-238 than neutrons at higher energy levels (MeV).

d.

Neutron cross sections of U-235 and U-238 are independent from the neutron energy levels.

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.11

[1.0 point]

Which ONE of the following is the definition of Thermal Utilization Factor?

a.

The ratio of the number of fast neutrons absorbed in fuel to the number of fast neutrons absorbed in the reactor material.

b.

The ratio of the number of fast neutrons produced by thermal fission to the number of thermal neutrons absorbed in the fuel.

c.

The ratio of the number of thermal neutrons absorbed in fuel to the number of thermal neutrons absorbed in the reactor material.

d.

The ratio of the number of fast neutrons produced by thermal fission to the number of thermal neutrons absorbed in the fuel.

QUESTION A.12

[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.13

[1.0 point]

During reg rod calibration, doubling time was recorded to be 68 seconds. What was the reactor period?

a. 47 seconds

b. 98 seconds

c. 113 seconds

d. 136 seconds QUESTION A.14

[1.0 point]

Which ONE of the following isotopes has the LARGEST microscopic absorption cross-section for thermal neutrons?

a. B-10

b. Xe-135

c. U-235

d. Sm-149

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.15

[1.0 point]

Which ONE of the following is the correct reason that delayed neutrons allow us to easily control of the reactor?

a. Delayed neutrons increase the mean neutron lifetime.

b. More delayed neutrons are produced than prompt neutrons.

c. Delayed neutrons take longer to thermalize than prompt neutrons.

d. Delayed neutrons are born at higher energies than prompt neutrons.

QUESTION A.16

[1.0 point]

The count rate for a reactor is 100 cps. An operator inserts an experiment into the core, and the count rate decreases to 55 cps. Given the initial keff of the reactor was 0.95, what is the worth of the experiment?

a. = - 0.02

b. = + 0.02

c. = - 0.05

d. = + 0.05 QUESTION A.17

[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. Reproduction factor

c. Infinite multiplication factor

d. Effective multiplication factor QUESTION A.18

[1.0 point]

FAST FISSION FACTOR is defined as a ratio of which ONE of the following?

a. The number of neutrons that reach thermal energy over the number of fast neutrons that start to slow down.

b. The number of fast neutrons produced from fission in a generation over the number of fast neutrons produced from fission in the previous generation.

c. The number of fast neutrons produced from U-238 over the number of thermal neutrons produced from U-235.

d. The number of fast neutrons produced from all fission over the number of fast neutrons

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics produced from thermal fission.

QUESTION A.19

[1.0 point]

Which ONE of the following factors in the six factor formula is the MOST affected by the MODERATOR?

a.

Fast fission factor b.

Reproduction factor

c. Thermal utilization factor

d. Fast non leakage probability QUESTION A.20

[1.0 point]

Which ONE of the following parameter changes will require control rod INSERTION to maintain constant power level following the change?

a. Insertion of a void into the core

b. Buildup of Samarium in the core

c. Increase in coolant water temperature (assume a negative temperature coefficient)

d. Removal of an experiment containing cadmium

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

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.01

[1.0 point, 0.25 each]

Fill out the blanks with the Limiting Conditions of Operation (LCO) listed in the UC-Irvine Technical Specifications.

Safety System Parameter a.

Core excess reactivity b.

Pool water conductivity c.

Steady state reactor power d.

Reactivity worth of both transient rods LCO a.

_____ ($) (2.5/3.0/3.5) b.

_____ microohms/cm (1/3/5) c.

_____ kW (200/250/275) d.

_____ ($) (3.00/3.50/3.75)

QUESTION B.02

[1.0 point]

Which ONE of the following radioisotopes produces the HIGHEST ionizing energy gamma?

a. Tritium

b. Nitrogen - 16

c. Argon - 41

d. Uranium - 235 QUESTION B.03

[1.0 point]

Which ONE of the following regulations states the UC-Irvine Requalification Program must be conducted for a continuous period not to exceed 24 months?

a.

10 CFR 19 b.

10 CFR 20 c.

10 CFR 50 d.

10 CFR 55 QUESTION B.04

[1.0 point]

Which ONE of the following experiments is NOT allowed to be installed in the reactor or experimental facilities under ANY condition?

a. experiment contains corrosive materials

b. secured experiment worth of $2.00

c. single, movable experiment worth of $1.50

d. experiment contains 15 milligrams of TNT material

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 0 hours 0 weeks 0 months 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]

Which ONE of the following surveillances is classified as a Channel Test?

a. Expose a detector to a check source to verify that it responds.

b. Verification of the log channel performance requirements by observation.

c. Compare the prestart readings of the radiation area monitors to the previous day readings

d. Adjust the wide range linear channel in accordance with recent data collected during a reactor power calibration.

QUESTION B.07

[1.0 point]

The radiation level from an unshielded source is 1 rem/hr. Using a 50 mm thick shield (made from various materials) reduces the radiation level to 625 mrem/hr.

What is the approximate half-value layer (HVL) of the shielding for this source?

(HVL: thickness of shielding required to reduce the original source intensity by half)

a. 64mm

b. 70mm

c. 74mm

d. 80mm

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.08

[1.0 point]

A sample reads 456 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.

20 feet c.

34 feet d.

65 feet QUESTION B.09

[1.0 point]

An experiment reading 82.00 mrem/hr was removed from the reactor. Four hours later, it reads 8.00 mrem/h. What is the half-life of the radioisotope in the experiment sample?

a.

1.01 hr b.

1.19 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 MONTHLY, QUARTERLY, SEMI-ANNUAL, ANNUALLY. Answers may be used once, more than once, or not at all. Note: in accordance with UC-Irvine Technical Specifications.

a.

Total reactivity worth of the control rods b.

Radiation Area Monitor (RAM) channel test c.

Pool water radioactivity

d. Control rod scram time QUESTION B.11

[1.0 point]

In accordance with UC-Irvine Emergency Plan, which ONE of the following is the emergency response limit for life saving?

a.

5.0 rem b.

10 rem c.

15 rem d.

25 rem

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]

In accordance with UC-Irvine Emergency Plan, which ONE of the following actions is NOT a Class 1, Notification of Unusual Event?

a.

Threat or breach of security b.

Personnel injury c.

Fire or minor explosion in the reactor room d.

Noticeable, abnormal loss of pool water QUESTION B.14

[1.0 point]

During a reactor operation, a small fire occurs in the control room console. Which ONE of the following classes of extinguisher would most likely be used with this type of fire?

a.

Class A: fires involving ordinary combustibles, such as wood, paper, plastic, etc.

b.

Class B: fires involving flammable or combustible liquids, flammable gases, greases.

c.

Class C: fires involving live electrical equipment d.

Class D: fires involving combustible metals such as magnesium.

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.15

[1.0 point, 0.25 each]

Match the type of radiation in Column A to the proper shielding material in Column B.

Column A a.

Alpha b.

Beta c.

Gamma

d. Neutron Column B 1.

Water or concrete 2.

Thin sheet of paper 3.

Low Z, plastics 4.

Lead, high Z QUESTION B.16

[1.0 point]

What are the MINIMUM radiation monitors required per the UC-Irvine Technical Specifications?

a.

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

1 Portable Radiation Monitor (PRM) and 1 CAM c.

1 RAM and 1 CAM d.

2 RAM and 1 CAM QUESTION B.17

[1.0 point]

A small section of pipe (point source) reads 10 mRem/hr at 1 meter. Which ONE of the following is the posting requirement for the area, in accordance with 10 CFR part 20?

a.

Radiation Area b.

High Radiation Area c.

Very High Radiation Area d.

Contaminated Materials QUESTION B.18

[1.0 point]

Which ONE of the following is the MINIMUM staffing requirement when the reactor is NOT secured?

a. Senior Reactor Operator (SRO) and Reactor Supervisor

b. Reactor Supervisor and Reactor Operator (RO)

c. Director of Emergency Operations and SRO

d. RO in the control room, a staff member, and SRO on call

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.19

[1.0 point]

Which ONE of the following is NOT an individual in line for reactor incident commander in the event of an emergency?

a. Reactor Supervisor

b. Senior Reactor Operator

c. UC-Irvine Police Chief

d. Reactor staff member 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 0.0111 hours 6.613757e-5 weeks 1.522e-5 months 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 NOT true for the standard TRIGA fuel elements?

a.

Cladding shall be 304 stainless steel b.

Zirconium hydride shall not be included c.

Upper fitting shall be designated to fit a latching tool d.

Total Uranium content shall be normally 8.5% by weight QUESTION C.02

[1.0 point]

Which ONE of the following radiation facilities is NOT within the UC-Irvine reactor core?

a.

Dry Well b.

Lazy Susan c.

Pneumatic Transfer System d.

Central Thimble QUESTION C.03

[1.0 point]

What is the primary function of the graphite sections on both sides of the fuel element?

a.

Absorb thermal neutrons b.

Increases fast neutron flux c.

Reduces neutron leakage d.

Absorb fission product gases QUESTION C.04

[1.0 point]

What is the MINIMUM motion setting of the seismic switch that ensures the reactor scram during an earthquake?

a.

0.01g b.

0.03g c.

0.10g d.

0.30g

Category C: Facility and Radiation Monitoring Systems QUESTION C.05

[1.0 point]

Which ONE of the following produces significant quantities of Nitrogen-16 in the reactor pool?

a. Argon - 41

b. Cobalt - 60

c. Oxygen - 16

d. Iodine - 131 QUESTION C.06

[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. complete a normal start up

b. remove any non-fixed experiments

c. reactor pool temperature below 18.5°C but >17°C

d. thermistor probe for the digital thermometer placement has been removed QUESTION C.07

[1.0 point]

The Continuous Air Monitor (CAM) is continuously sampled from above the reactor pool, it measures alpha, beta, and gamma levels to make conclusions of derived air concentrations (DAC) for a specific radionuclide. Which ONE of the following isotopes is the CAM set for?

a. Argon-41

b. Bromine-81

c. Iodine-131

d. Cesium-137 QUESTION C.08

[1.0 point]

Which ONE of the following, if found in the reactor pool, signifies a possible fuel cladding failure?

a. Nitrogen-16

b. Argon-41

c. Cobalt-60

d. Cesium-137

Category C: Facility and Radiation Monitoring Systems QUESTION C.09

[1.0 point]

Which ONE of the following is represented by the figure below?

a.

Scintillation detector b.

Pocket ionization chamber c.

Thermoluminescent Dosimeter (TLD) d.

Portable Ionization chamber QUESTION C.10

[1.0 point]

Which ONE of the following is the annual average concentration of Argon-41 discharged to the environment/unrestricted area SHALL NOT EXCEED?

a. 1 x 10 -6 µCi/ml

b. 1 x 10 -7 µCi/ml

c. 1 x 10 -8 µCi/ml

d. 1 x 10 -9 µCi/ml QUESTION C.11

[1.0 point]

What is the main purpose of the fuel followers in the control rods?

a.

Decrease the fast neutron flux in the core b.

Increase the effectiveness for reactor pulsing c.

Decrease the thermal neutron flux in the core d.

Increase the core excess reactivity in the reactor core

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]

In accordance with UC-Irvine Technical Specifications, 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]

Which ONE of the following is the primary isotope of concern in air? Note: A neutron flux will activate isotopes in air.

a.

H2 (H1 (n, ) H2) b.

N16 (O16 (n,p) N16) c.

Kr80 (Kr79 (n, ) Kr80) d.

Ar41 (Ar40 (n, ) Ar41)

QUESTION C.15

[1.0 point]

Which ONE of the following is the detector for the Wide Range Log Channel?

a.

Compensated Ion Chamber b.

Uncompensated Ion Chamber c.

Fission Chamber d.

Scintillation Chamber

Category C: Facility and Radiation Monitoring Systems QUESTION C.16

[1.0 point]

During the annual pulsing operation calibration what channel provides the peak power channel (nv) and integrated power-time channel (nvt) information?

a. Power Range Monitor

b. Wide Range Monitor

c. Wide Range Linear Power Monitor

d. Dual-pen Strip Chart Recorder QUESTION C.17

[1.0 point]

Which ONE of the following is used in the pneumatic transfer system to move a rabbit sample between the terminus and receiver?

a. N16

b. Kr80

c. CO2

d. Air QUESTION C.18

[1.0 point]

In accordance with UC-Irvine Technical Specifications, which ONE of the following is the MAXIMUM amount of fueled experiments are limited to of Stronium-90?

a.

1 microcurie b.

5 microcurie c.

1 curie d.

5 millicurie QUESTION C.19

[1.0 point]

During fuel inspection, you find the growth in length over the original measurements exceeds 1/16th inches (0.0625 inches), what action needs to be taken?

a. Nothing, it is still under a limit of 0.125 inches.

b. The fuel is damaged, and the reactor shall not be operated.

c. Nothing, growth in length limit of the fuel is not required to be measured.

d. Considered partially damaged fuel, and the maximum power shall not exceed 1 kW.

Category C: Facility and Radiation Monitoring Systems QUESTION C.20

[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

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

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

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

b.

Reference:

SUR = 26/ 26/26 = 1 SUR = time in[1.0] minutes to increase power by a factor of

10. 1000 = three decades 3 x 1 = 3 minutes or time = ln(1000)*26 = 180 seconds = 3 min A.02 Answer:

d.

Reference:

DOE Fundamentals of Reactor Theory, Volume 1, Module 2, page 23 A.03 Answer:

a. Alpha; b. Positron; c. Neutron; d. Alpha (0.25 each)

Reference:

Burn, R., Introduction to Nuclear Reactor Operations, 1982, Section 1.3.1 A.04 Answer:

a.

Reference:

P = P0 e-t/T P = 25 kW

e(420s/-80s) 25 kW

e-5.25 25 kW

0.0052475; P = 0.131 kW A.05 Answer:

DOE Fundamentals of Reactor Theory, Volume 2, NP-04, page 30-31

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

Category B: Normal/Emergency Operating Procedures and Radiological Controls B.01 Answer:

a. 3; b. 3; c. 250; d. 3.00 (0.25 each)

Reference:

UC-Irvine Technical Specifications 3.1.1, 3.1.3, and 3.3.3 B.02 Answer:

b.

Reference:

Chart of the Nuclides B.03 Answer:

d.

Reference:

10 CFR Part 55.59(a)(1)

Reference:

DR=DR0e(-t)

T1/2=0.693/

DR = DR0 e-.693/T1/2 8 = 82 e-(.693)(4)/T1/2 0.0923 = e-(2.772)/T1/2 ln(0.0976) = ln(e-(2.772)/T1/2)

-2.327 = -2.772 / T1/2 T1/2 = -2.772 / -2.327 T1/2 = 1.19 hr B.10 Answer:

a. Annual; b. Monthly; c. Quarterly; d. Annual

Reference:

UC-Irvine Technical Specifications 4.1, 4.2, 4.3, and 5.4

10 CFR Part 55

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

NRC standard question

NRC Standard Question

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

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

ML24113A005

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SUBJECT:

Dear John Keffer:

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