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Examination Report No. 50-407-OL 17-01, University of Utah
	ML17136A012
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Site:	University of Utah
Issue date:	05/17/2017
From:	Anthony Mendiola; Research and Test Reactors Oversight Branch
To:	Schow R; Univ of Utah
	Anthony Mendiola
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May 17, 2017 Mr. Ryan C. Schow, Interim Director University of Utah Nuclear Research Reactor Joseph Merrill Engineering Building 50 South Central Drive, Room 1206 Salt Lake City, UT 84112

SUBJECT:

EXAMINATION REPORT NO. 50-407/OL-17-01, UNIVERSITY OF UTAH

Dear Mr. Schow:

During the week of April 3, 2017, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your University of Utah TRIGA Reactor. The examinations were conducted according to NUREG-1478, Operator Licensing Examiner Standards for Research and Test Reactors, Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report.

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 Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. If you have any questions concerning this examination, please contact Mr. John T. Nguyen at (301) 415-4007, or by e-mail at John.Nguyen@nrc.gov.

Sincerely,

/RA/

Anthony J. Mendiola, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-407

Enclosures:

1. Examination Report No. 50-407/OL-17-01

2. Written Examination

R. Schow 2

SUBJECT:

EXAMINATION REPORT NO. 50-407/OL-17-01, UNIVERSITY OF UTAH DATED MAY 17, 2017.

DISTRIBUTION:

PUBLIC AMendiola AAdams CBassett XYin ADAMS ACCESSION #: ML17036A012 NRR-079 OFFICE NRR/DPR/PROB NRR/DPR/PROB NRR/DPR/PROB NAME Nguyen ABaxter AMendiola DATE 05/09/17 05/16/17 05/17/17 OFFICIAL RECORD COPY

University of Utah Docket No. 50-407 cc:

Mayor of Salt Lake City 451 South State Room 306 Salt Lake City, UT 84111 Dr. Andrew S. Weyrich Vice President for Research 201 S Presidents Circle, Room 210 University of Utah Salt Lake City, UT 84112-9011 Frederick A. Monette Interim Director and RSO Radiological Health 75 S 2000 E, Room 322 University of Utah Salt Lake City, UT 84112 Dr. Cynthia Furse Associate Vice President for Research 201 President Circle, Room 210 University of Utah Salt Lake City, UT 84112 Test, Research and Training Reactor Newsletter P.O. Box 118300 University of Florida Gainesville, FL 32611 Director, Division of Radiation Control Dept. Of Environmental Quality 195 North 1950 West P.O. Box 14485 Salt Lake City, UT 84114-4850

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING EXAMINATION REPORT REPORT NO.: 50-407/OL-17-01 FACILITY DOCKET NO.: 50-407 FACILITY LICENSE NO.: R-126 FACILITY: University of Utah TRIGA Reactor EXAMINATION DATES: April 03 - April 07, 2017 SUBMITTED BY: _________/RA/_________________ 05/09/2017 John T. Nguyen, Chief Examiner Date

SUMMARY

During the week of April 3, 2017, the NRC administered operator licensing examinations to three Senior Reactor Operator-Instant (SROI) and five Reactor Operator (RO) license candidates. One of SROI candidates failed both the examinations (written exam and operating test). Two RO candidates failed the written exam. All of the other candidates passed their applicable portions of the examinations.

REPORT DETAILS

1. Examiners: John T. Nguyen, Chief Examiner, NRC

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 3/2 2/1 5/3 Operating Tests 5/0 2/1 7/1 Overall 3/2 2/1 5/3

3. Exit Meeting:

Ryan C. Schow, Interim Director, University of Utah John T. Nguyen, Chief Examiner, NRC William Schuster, Examiner in Training, NRC Ossy Font, Examiner in Training, NRC At the conclusion of the meeting, the NRC Examiner thanked the facility for their support in the administration of the examinations. The examiner discussed the weaknesses observed from the operating tests including the generic weaknesses in a basic understanding of 10 CFR 50.59 and 10 CFR 20, a lack of knowledge in the operations of nuclear instrumentation channels, and unfamiliar radiation sources and hazards within the facility. The facility licensee promised to take actions to improve program performance in the training programs.

Enclosure 1

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: UNIVERSITY OF UTAH REACTOR TYPE: TRIGA DATE ADMINISTERED: April 04, 2017 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 19.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 19.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 19.00 33.3 C. FACILITY AND RADIATION MONITORING SYSTEMS 57.00 100.00 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature Enclosure 2

A. RX THEORY, THERMO & FAC OP CHARS ANSWER SHEET Multiple Choice (Circle or X your choice)

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

A01 a b c d ___

A02 a b c d ___

A03 a b c d ___

A04 a b c d ___

A05 a ___ b ___ c ___ (0.33 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 ___

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

B. NORMAL/EMERG PROCEDURES & RAD CON ANSWER SHEET Multiple Choice (Circle or X your choice)

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

B01 a b c d ___

B02 a b c d ___

B03 a ___ b ___ c ___ d ___ (0.5 each)

B04 a b c d ___

B05 a ___ b ___ c ___ d ___ (0.25 each)

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 ___

B11 a b c d ___

B12 a b c d ___

B13 a b c d ___

B14 a b c d ___

B15 a b c d ___

B16 a b c d ___

B17 a b c d ___

B18 a b c d ___

B19 a b c d ___

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

C. PLANT AND RAD MONITORING SYSTEMS ANSWER SHEET Multiple Choice (Circle or X your choice)

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

C01 a b c d ___

C02 a b c d ___

C03 a b c d ___

C04 a b c d ___

C05 a b c d ___

C06 a ___ b ___ c ___ d ___ (0.50 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 ___ (0.33 each)

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 ___ (0.33 each)

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

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

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:

1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.

2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have neither received nor given assistance in completing the examination. This must be done after you complete the examination.

3. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

4. Use black ink or dark pencil only to facilitate legible reproductions.

5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each Answer sheet.

6. Mark your Answers on the Answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.

7. The point value for each question is indicated in [brackets] after the question.

8. If the intent of a question is unclear, ask questions of the examiner only.

9. When turning in your examination, assemble the completed examination with examination questions, examination aids and Answer sheets. In addition turn in all scrap paper.

10. Ensure all information you wish to have evaluated as part of your Answer is on your Answer sheet. Scrap paper will be disposed of immediately following the examination.

11. To pass the examination you must achieve a grade of 70 percent or greater in each category.

12. There is a time limit of three (3) hours for completion of the examination.

EQUATION SHEET

( )2 eff = 0.1sec 1 Q&= m&cP T = m&H =UAT Pmax =

(2 )

t P = P0 e S S SCR = * =1x104 sec 1 K eff eff + &

SUR = 26.06

( )

CR1 1 K eff1 CR

= CR1 ((

2 1 1 )K

= CR )

eff 2 2 ( 2 )

(1 ) M=

1

= 2 CR P = P0 10SUR(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 =

eff 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 DR - Rem, Ci - curies, E - Mev, R - feet 1 Curie = 3.7x1010 dps 1 kg = 2.21 lbm 1 hp = 2.54x103 BTU/hr 1 Mw = 3.41x106 BTU/hr 1 BTU = 778 ft-lb f °F = 9/5°C + 32 931 Mev = 1 amu °C = 5/9 (°F - 32)

Section A L Theory, Thermo, and Facility Characteristics QUESTION A.01 [1.0 point]

A mechanism by which a nucleus can gain stability by converting a neutron to a proton or vice versa is called:

a. beta decay.

b. alpha decay.

c. gamma decay.

d. photoelectric effect.

QUESTION A.02 [1.0 point]

The reactor is increasing power from 10 W to 100 kW in a prompt criticality. Which ONE of the following best describes the values of Keff and during the power increment?

a. Keff < 1 and > 1

b. Keff > 1 and > 1

c. Keff > 1 and 0 < < -eff

d. Keff > 1 and -eff < < 1 QUESTION A.03 [1.0 point]

Few minutes following a reactor scram from full power, the reactor period has stabilized and the power level is decreasing at a CONSTANT rate. What is the power level one minute later from 2 kW?

a. 0.2 kW

b. 0.5 kW

c. 0.9 kW

d. 1.2 kW

Section A L Theory, Thermo, and Facility Characteristics QUESTION A.04 [1.0 point]

The MAJOR source of energy released during fission comes from:

a. Fission neutrons.

b. Fission fragments.

c. Prompt gamma rays.

d. Fission product gamma decay.

QUESTION A.05 [1.0 point, 0.33 each]

Match the term listed in Column A with its corresponding units listed in column B. Answer in Column B can be used once, more than once, or not at all.

Column A Column B

a. 1 barn 1. 1/cm

b. Macroscopic Cross Section 2. 10 -24 cm 3

c. Neutron Flux 3. Neutrons / cm 2 /sec

4. Neutrons / cm 3 /sec

5. 10 -24 cm 2 QUESTION A.06 [1.0 point]

The reactor is critical. A control rod is pulled to insert a positive reactivity of 0.156 %k/k.

Which ONE of the following will be the stable reactor period as a result of this reactivity insertion? Given beta-effective = 0.0070 and eff= 0.1

a. 20 seconds

b. 35 seconds

c. 55 seconds

d. 65 seconds

Section A L Theory, Thermo, and Facility Characteristics QUESTION A.07 [1.0 point]

For the alpha decay of a nuclide, the number of protons will ___________ and its atomic mass number will __________.

a. increase by 2 / increase by 2

b. decrease by 2 /decrease by 4

c. decrease by 4 / decrease by 2

d. increase by 4 / increase by 2 QUESTION A.08 [1.0 point]

The reactor is SHUTDOWN by 5 %k/k with the count rate of 100 counts per second (cps).

The control rods are withdrawn until the count rate is doubled. What is the value of Keff when the count rate is doubled?

a. 0.952

b. 0.976

c. 0.998

d. 1.002 QUESTION A.09 [1.0 point]

Given a reactor period of 32 seconds, approximately how long will it take for power to triple?

a. 22 seconds

b. 35 seconds

c. 46 seconds

d. 64 seconds

Section A L Theory, Thermo, and Facility Characteristics QUESTION A.10 [1.0 point]

A reactor is subcritical with a Keff of 0.927. If you add 7.875% k/k into the core, the reactor will be:

a. subcritical

b. critical

c. supercritical

d. prompt critical QUESTION A.11 [1.0 point]

Which ONE of the following is the time period in which the MAXIMUM amount of Xe-135 will be present in the core?

a. 1 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after a power increase from 50% to 100%

b. 7 to 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months after a scram from 100% power

c. 1 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after a start up to 100%power

d. 7 to 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months after a scram from 50% power

Section A L Theory, Thermo, and Facility Characteristics QUESTION A.12 [1.0 point]

A reactor is slightly supercritical with the following values for each of the factors in the six-factor formula:

Fast fission factor 1.03 Fast non-leakage probability 0.84 Resonance escape probability 0.96 Thermal non-leakage probability 0.88 Thermal utilization factor 0.70 Reproduction factor 1.96 A control rod is inserted to bring the reactor back to critical. Assuming all other factors remain unchanged, the new value for the thermal utilization factor is:

a. 0.698

b. 0.702

c. 0.740

d. 0.762 QUESTION A.13 [1.0 point]

Which ONE of the following conditions will DECREASE the shutdown margin of a reactor?

a. Higher moderator temperature (assume negative temperature coefficient)

b. Insertion of a negative reactivity worth experiment

c. Burnout of a burnable poison

d. Fuel depletion

Section A L Theory, Thermo, and Facility Characteristics QUESTION A.14 [1.0 point]

Following a positive reactivity addition to a shutdown reactor, the neutron power will increase even though k-effective is less than 1. The MAIN reason is due to:

a. Production of fast neutrons

b. Negative temperature coefficient in the moderator

c. Subcritical multiplication process

d. Void temperature coefficient in the moderator QUESTION A.15 [1.0 point]

Given a source strength of 100 neutrons per second (N/sec) and a multiplication factor (k) of 0.9, which ONE of the following is the expected stable neutron count rate?

a. 900 N/sec

b. 1000 N/sec

c. 1500 N/sec

d. 2000 N/sec QUESTION A.16 [1.0 point]

Which ONE of the following isotopes will absorb more neutrons when it interacts with neutrons?

a. Hydrogen-1

b. Argon-40

c. Boron-10

d. Uranium-235

Section A L Theory, Thermo, and Facility Characteristics QUESTION A.17 [1.0 point]

Which term is described by the following?

The fractional change of the effective multiplication factor from criticality.

a. 1/M

b. K-effective

c. Reactor period

d. Reactivity QUESTION A.18 [1.0 point]

Inelastic scattering can be described as a process whereby a neutron collides with a nucleus and leaves the nucleus in an excited state. The nucleus later:

a. emit a gamma ray, and a neutron with lower energy

b. emit a gamma ray, and a neutron with higher energy

c. emit a beta particle, and a neutron with lower energy

d. emit an alpha particle ONLY QUESTION A.19 [1.0 point]

Which ONE of the following is the stable reactor period which will result in a power rise from 1%

to 100% power in 120 seconds?

a. 10 seconds

b. 13 seconds

c. 26 seconds

d. 80 seconds

- - - - End of Section A *****************

Section B Normal, Emergency and Radiological Control Procedures QUESTION B.01 [1.0 point]

Per UUTR Technical Specifications, the reactor SHUTDOWN is defined as:

a. all rods are inserted to the reactor core.

b. the reactor is subcritical by at least $1.00 in the reference core condition, but EXCLUDED the reactivity worth of all installed experiments and irradiation facilities.

c. the console key is OFF position and no work is in progress involving core fuel, core structure, installed control rods, or control rod drives.

d. the reactor is subcritical by at least $1.00 in the reference core condition with the reactivity worth of all installed experiments and irradiation facilities INCLUDED.

QUESTION B.02 [1.0 point]

The On-site Emergency Coordinator (OEC) may authorize above normal occupational exposure limits during an emergency. The OEC may authorize the dose limit up to ______ for life saving

a. 100 rem

b. 75 rem

c. 50 rem

d. 15 rem QUESTION B.03 [2.0 points, 0.5 each]

Match the following 10 CFR parts:

Column A Column B

a. Operators Licenses 1. Part 19

b. Standards for Protection against Radiation 2. Part 20

c. Notices, Instructions, and Reports to Workers 3. Part 50

d. Domestic Licensing of Production and Utilization Facilities 4. Part 55

Section B Normal, Emergency and Radiological Control Procedures QUESTION B.04 [1.0 point]

You receive a quarterly report stating that you have received whole body occupational exposures of:

10 mrad of beta 10 mrad of alphas 10 mrad of neutrons of unknown energy What would be the total effective dose equivalent?

a. 30 mrem

b. 120 mrem

c. 220 mrem

d. 310 mrem QUESTION B.05 [1.0 point, 0.25 each]

For a core composed of aluminum clad, match each of the location of instrumented fuel element listed in column A with its corresponding LSSS value listed in column B. (Each limit has only one answer, values in Column B can be used once, more than once or not at all.)

Column A Column B (limit shall not exceed)

a. B-hexagonal ring 1. 580 °C

b. C-hexagonal ring 2. 460 °C

c. D-hexagonal ring 3. 435 °C

d. E-hexagonal ring 4. 415 °C

5. 390 °C

6. 340 °C

Section B Normal, Emergency and Radiological Control Procedures QUESTION B.06 [1.0 point]

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

a. H3

b. N16

c. Ar41

d. Co60 QUESTION B.07 [1.0 point]

A radioactive source reads 5 Rem/hr on contact. Five hours later, the same source reads 1.25 Rem/hr. How long is the time for the source to decay from a reading of 5 Rem/hr to 625 mRem/hr?

a. 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months

b. 7.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months

c. 8.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months

d. 9.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months QUESTION B.08 [1.0 point]

A channel calibration of the CAM system was performed last year. Which ONE of the following is the latest the calibration that must be performed again without violation of the Technical Specifications?

a. 3.5 months after

b. 7.0 months after

c. 14.5 months after

d. 29.5 months after

Section B Normal, Emergency and Radiological Control Procedures QUESTION B.09 [1.0 point]

For two hours, a radioactive material is decayed by 30% of its original. Determine its half-life?

a. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

b. 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months

c. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

d. 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months QUESTION B.10 [1 point]

In the event of a suspected fuel leak, which ONE of the following nuclides would most likely be found in a Continuous Air Monitor?

a. Ar-41

b. I-135

c. N-16

d. Na-24 QUESTION B.11 [1.0 point]

Which ONE of the following materials shall NOT be irradiated at UUTR?

a. Any explosive material

b. Any corrosive material

c. Any fueled experiment such as U-235

d. The sum of the reactivity worth of all experiments is $1.10

Section B Normal, Emergency and Radiological Control Procedures QUESTION B.12 [1.0 point]

The below items are listed as a reportable occurrence EXCEPT:

a. The reactor power level exceeds 110 kW.

b. The reactor tank water temperature exceeds 40 °C.

c. A reactor is in operation when the Continues Air Monitor (CAM) is just broken.

d. The available excess reactivity on the reference core configuration is $1.30.

QUESTION B.13 [1.0 point]

During reactor operations, the Reactor Supervisor (RS) becomes ill and is taken to the hospital.

What is a correct action if only the Reactor Operator (RO) and an experienced student remain in the facility?

a. The reactor can continue if the RO can find the RS served as Supervisor-on call.

b. The reactor shall be shutdown because both an RO and an RS must be present in the control room during reactor operation.

c. The reactor can continue if the SRO can arrive at the facility within 60 minutes.

d. The reactor can continue if the RO can monitor the console, the student can carry out prescribed written instructions, and find a SRO on call.

QUESTION B.14 [1.0 point]

You perform a fuel element inspection. In measuring the transverse bend, you find the bend of one fuel element exceeds the original bend by 1/32 inches. For this measurement, you will:

a. continue the fuel inspection because this bend is within TS limit.

b. continue the fuel inspection because the Technical Specifications require the elongation measurement only.

c. stop the fuel inspection; you immediately report the result to the supervisor because it is considered a damaged fuel element.

d stop the fuel inspection, you immediately report the result to the U.S. NRC since it is a reportable occurrence.

Section B Normal, Emergency and Radiological Control Procedures QUESTION B.15 [1.0 point]

Per UUTR Technical Specifications, a channel test of the ventilation systems ability to operate in the limited intake mode shall be performed:

a. daily

b. monthly

c. quarterly

d. semi-annually QUESTION B.16 [1.0 point]

The reactor area shall contain a minimum free volume of 5.65x108 cm3. This is an example of:

a. Design Features

b. Surveillance Requirements

c. Limiting Conditions for Operation (LCO)

d. Limiting Safety System Setting (LSSS)

QUESTION B.17 [1.0 point]

Which ONE of the following accidents is considered to be the Maximum Hypothetical Accident for the UUTR?

a. During fuel element movement in air, the fuel element is dropped on the reactor bay; resulting in the release of gaseous fission product to the atmosphere.

b. An earthquake occurs and causes a loss of pool water; resulting in the release of high level of radiation.

c. A major earthquake occurs, resulting in the release of the contaminated reactor pool water to the surrounding water table.

d. During fuel movement in reactor pool, an element is dropped underwater and damaged severely enough to breach the cladding and release part of fission product to the atmosphere.

Section B Normal, Emergency and Radiological Control Procedures QUESTION B.18 [1.0 point]

Which ONE of the following modifications would be considered a 50.59 and the UUTR Reactor Facility must file a request to NRC for change? The facility plans to:

a. Replace an identical control rod drive.

b. Change a control rod calibration with new technique.

c. Measure a control rod drop time with new technique.

d. New experiment containing uranium-235 liquid.

QUESTION B.19 [1.0 point]

Which ONE of the following events does NOT require the presence of the Reactor Supervisor in the facility?

a. Fuel relocations within the core region

b. Initial start-up and approach to power of the day

c. Insertion of experiment worth of $0.50

d. Restart following an unplanned shutdown

- - - - End of Section B ********************************

Section C Plant and Radiation Monitoring Systems QUESTION C.01 [1.0 point]

The UUTR Safety Rod is located at:

a. B-ring.

b. C-ring.

c. D-ring

d. F-ring.

QUESTION C.02 [1.0 point]

You perform a procedure for adding water to the reactor tank. After adding, water level from the top of tank increases by 3 cm. A volume of water added to the reactor tank is approximately:

a. 6 gallons

b. 12 gallons

c. 23 gallons

d. 35 gallons QUESTION C.03 [1.0 point]

Figure 7.2-1 depicts the instrumented fuel element with graphite inserted in the top and bottom of the element. Which ONE of the following best describes the function of these inserts?

a. Protect thermocouples when fuel exceeds the safety limit

b. Seal fuel cladding when it ruptures

c. Absorb fission product gases

d. Reduce neutron leakage

Section C Plant and Radiation Monitoring Systems Section C Plant and Radiation Monitoring Systems QUESTION C.04 [1.0 point]

Which ONE of the following substances is MAINLY used as the neutron absorber in the UUTR control rods?

a. Cadmium

b. Zirconium-hydride

c. Borated graphite

d. Heavy water and graphite QUESTION C.05 [1.0 point]

The low-source-interlock signal comes from:

a. Count rate Channel

b. Log Power Channel

c. Linear Power Channel

d. Percent Power Channel QUESTION C.06 [2.0 points, 0.5 each]

The reactor is in operation. Match the input signals listed in column A with their AUTOMATIC responses listed in column B. (Items in column B may be used more than once or not at all.)

Column A Column B

a. Pool water temperature = 35 °F 1. Normal Operation

b. Insert SHIM and REG simultaneously 2. Alarm ONLY

c. Linear Power Channel = 100 kW 3. Interlock

d. Reactor console loses the electrical 4. Scram (with or power without Alarm)

Section C Plant and Radiation Monitoring Systems QUESTION C.07 [1 point]

Which ONE of the following correctly describes the reactor operation when the ventilation system fails?

a. The reactor is immediately secured and shall not be operated until the ventilation is fully operable.

b. The reactor can be operable for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months without the ventilation system but with the operable ARM.

c. The reactor can be operable for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months without the ventilation system but with the operable ARM.

d. The reactor can be operable for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months without the ventilation system but with the operable ARM and CAM.

QUESTION C.08 [1.0 point]

You perform a fuel element inspection. In measuring the length, you find the length of one fuel element exceeds its original by 0.10 inches. For this measurement, you will:

a. continue the fuel inspection because this length is within TS limit.

b. continue the fuel inspection because the UUT Tech Spec is NOT required any measurement of fuel elements.

c. stop the fuel inspection; immediately report the result to the supervisor because it is considered a damaged fuel element.

d stop the fuel inspection, immediately report the result to the U.S. NRC since it is a reportable occurrence.

Section C Plant and Radiation Monitoring Systems QUESTION C.09 [1.0 point]

Per UNEP-003, the control drop rod calibration, which ONE of the following is the correct parameter used for the calibration of the REG rod? The operator will stabilize the reactor power at ____ with the regulating rod in its _____ position before dropping the regulating rod.

a. 100 W / 100%

b. 100 W / 50%

c. 1 kW / 100%

d. 1 kW / 50%

QUESTION C.10 [1.0 point]

Which ONE of the following best describes the method used in the UUTR reactor in order to reduce Ar-41 dose from the pneumatic tube system?

a. Increase a speed of sending and receiving stations

b. A CO2 purge is maintained on the system

c. A Helium purge is maintained on the system

d. Use of aluminum tube QUESTION C.11 [1.0 point]

Fuel burnup of Uranium-235 in the U-Zr-H fuel matrix shall not exceed 50% of initial content.

Fuel burnup calculation shall be performed:

a. quarterly

b. semi-annually

c. annually

d. biennially

Section C Plant and Radiation Monitoring Systems QUESTION C.12 [1.0 point, 0.33 each]

Figure 5.4-2 depicts the recirculation of water system. Identify the water flow listed in column A with their appropriate locations (to/from) listed in the schematics.

Column A

a. To TRIGA tank 1. Location 1

b. From portable water supply 2. Location 2

c. From Chiller 3. Location 3

Section C Plant and Radiation Monitoring Systems QUESTION C.13 [1.0 point]

Which ONE of the following is the best description how the Uncompensated Ion Chamber (UCIC) operates?

Material used in CIC Interact with Results

a. Pu-239 + neutron B-10 + alpha --> N-14 + gamma

b. B-10 + neutron B-11 --> Li-7 + alpha

c. U-235 + neutron Fission fragments + gamma

d. Am-239 + neutron Be-9 + gamma --> Li-8 + beta QUESTION C.14 [1.0 point]

The picture provided below depicts:

a. Diesel power generator for an emergency electrical power.

b. Transfer switch box for an emergency electrical power.

c. UPS for the reactor console during an emergency.

d. UPS for the radiation monitor and the facility intrusion detectors during an emergency.

Section C Plant and Radiation Monitoring Systems Section C Plant and Radiation Monitoring Systems QUESTION C.15 [1.0 point]

Following a loss of building electrical power, power for the radiation monitors and the facility intrusion detectors is supplied by:

a. an UUTR emergency generator.

b. an uninterruptible power supply (UPS) within the reactor room.

c. an uninterruptible power supply (UPS) from the main building.

d. power will be lost completely and will not return until building power returns.

QUESTION C.16 [1.0 point]

Which ONE of the following methods is actually used to minimize the shock to the control rods during a reactor scram?

a. A small spring on the pull rod.

b. A small spring on the bottom of the control rod.

c. An electro-mechanical brake on the motor energizes as the rod down switch is energized.

d. A piston (part of the connecting rod), drives water out of a dashpot as the rod near the bottom of its travel.

QUESTION C.17 [1.0 point]

On the control panel the indicating lights for the SHIM rod are as follows: the CONT light is ON, the UP light is OFF and the DOWN light is OFF. What is the condition of the Shim Rod?

a. The rod drive is at the top of travel, but the rod is at the bottom.

b. The rod drive and the rod are both at the top of travel.

c. The rod drive and the rod are both at the bottom of travel.

d. The rod drive and the rod are both between the bottom and top of travel.

Section C Plant and Radiation Monitoring Systems QUESTION C.18 [1.0 point]

The UUTR fuel element contains:

a. a mixture of U-Zr-H alloy with a maximum of 20 weight percent uranium which has a maximum enrichment of 8.5 % U-235.

b. a mixture of U-Cr-H alloy with a maximum of 8.5 weight percent uranium which has a maximum enrichment of 20 % U-235.

c. a mixture of U-Zr-O alloy with a maximum of 8.5 weight percent uranium which has a maximum enrichment of 20 % U-235.

d. a mixture of U-Zr-H alloy with a maximum of 8.5 weight percent uranium which has a maximum enrichment of 20 % U-235.

QUESTION C.19 [1.0 point, 0.33 each]

Use the following diagram of the control rod; match the Limit Switch (LS) components listed in Column B to the appropriate labels in Column A?

Column A Column B

a. Magnet Down LS 1

b. Magnet UP LS 2

c. Rod Down LS 3

Section C Plant and Radiation Monitoring Systems

- - - - End of Section C *****************************

- - - - End of the Exam ***************************

Section A: Reactor Theory, Thermo, and Facility Characteristics Answer Key A.01 Answer: a

Reference:

NRC Standard Question A.02 Answer: d

Reference:

P = P0 e-t/T = 1 kW e(60sec/-80sec) = 2 kW

e-0.75 = 0.472 2 kW = 0.94 kW A.04 Answer: b

Reference:

A.05 Answer: a(5) b(1) c(3) (0.33 each)

Reference:

Reactivity added = 0.00156 k/k

= (-)/eff = 0.0070 - 0.00156 = 34.8 seconds (0.1) (0.00156)

A.07 Answer: b

Reference:

Chart of the Nuclides A.08 Answer: b

Reference:

Keff1=1/1- 1 Keff1 =1/(1-(-.05)) -->Keff1= 0.952, Count1*(1-Keff1) = Count2*(1-Keff2)

Count1*(1-0.952) = Count2*(1-Keff2) 100*(1-0.952) = 200(1- Keff2); Keff2 = 0.976 A.09 Answer: b

Reference:

P=Poet/ 3=1* et/32 t = 32 sec*ln(3) = 35.2 sec

Section A: Reactor Theory, Thermo, and Facility Characteristics A.10 Answer: b

Reference:

SDM = (1- keff)/keff = (1-0.927)/0.927 = 0.07875 k/k. So if you add the same amount of SDM, the reactor is critical.

Another method: you can find the new value of Keff when adding 0.07875 k/k to reactor.

p = (k2 -k1)/ k1*k2 0.07875 = (k2- 0.927)/(0.927* k2), solve for k2 K2 = 1, hence the reactor is critical A.11 Answer: b

Reference:

A.12 Answer: a

Reference:

K eff = 1.03*0.84*0.96*0.88*1.96*x X= 1/1.4326 = 0.698 A.13 Answer c

Reference:

Standard NRC question A.14 Answer: c

Reference:

A.15 Answer: b

Reference:

CR = S/(1-K) CR = 100/(1 - .9) = 1000 N/sec A.16 Answer: c

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 2.5.1, Pages 2-38-43 A.17 Answer: d

Reference:

Section A: Reactor Theory, Thermo, and Facility Characteristics A.19 Answer: c

Reference:

P = P0 et/T --> T= t/Ln(P/ P0 )

t= 120/Ln(100 ); t = 26 sec.

Section B Normal, Emergency and Radiological Control Procedures Answer Key B.01 Answer: d

Reference:

TS 1.1 B.02 Answer: b

Reference:

EP 3.5 B.03 Answer: a (4), b (2), c (1), d (3)

Reference:

10 CFR B.04 Answer: d

Reference:

10*1 mrem + 10*20 mrem + 10*10 mrem = 310 mrem B.05 Answer: a(2) b(3) c(5) d(6)

Reference:

TS 2.2 B.06 Answer: b

Reference:

Chart of the Nuclides B.07 Answer: b

Reference:

DR = DR*e -t 1.25 rem/hr =5 rem/hr* e -(5hr)

Ln(1.25/5) = -*5 --> =0.277; solve for t: Ln(.625/5)=-0.277 *t t=7.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months B.08 Answer: c

Reference:

TS 4.7.3 (Annually, not exceed 15 months)

B.09 Answer: c

Reference:

DR = DR*e -t 30% is decayed, so 70% is still there 70% =100%* e -(2hrs)

Ln(70/100) = -*2 -->=0.1783 t1/2=Ln(2)/ -->.693/.1783 t=3.89 hours0.00103 days 0.0247 hours 1.471561e-4 weeks 3.38645e-5 months

Section B Normal, Emergency and Radiological Control Procedures B.10 Answer: b

Reference:

SAR 13.2 B.11 Answer: c

Reference:

TS 3.8 B.12 Answer: c

Reference:

TS 3.1, 3.3, and 3.7 B.13 Answer: d

Reference:

TS 6.1.3 B.14 Answer: a

Reference:

TS 3.1.6 B.15 Answer: b

Reference:

TS 4.5 B.16 Answer: a

Reference:

TS 5.1 B.17 Answer: a

Reference:

SAR 13.1 B.18 Answer: d

Reference:

10 CFR 50.59 B.19 Answer: c

Reference:

TS Section 6.1.3

Section C Plant and Radiation Monitoring Systems Answer Key C.01 Answer: c

Reference:

SAR Figure 4.5-1 C.02 Answer: d

Reference:

3 cm

11.6 gallon/cm = 23 gallons SOP UNEP 008 C.03 Answer: d

Reference:

GA Triga fuel design and SAR 4.2.1 C.04 Answer: c

Reference:

SAR Figure 4.2-4 C.05 Answer: a

Reference:

SAR 7.2.3.1 C.06 Answer: a(2) b(1) c(4) d(4)

Reference:

TS 3.2 C.07 Answer: a

Reference:

TS 3.5 C.08 Answer: a

Reference:

TS 3.1.6 C.09 Answer: c

Reference:

SOP UNEP-003 C.10 Answer: c

Reference:

SAR 10.2 C.11 Answer: d

Reference:

TS 4.1 C.12 Answer: a(2) b(3) c(1)

Reference:

SAR Figure 5.4-2

Section C Plant and Radiation Monitoring Systems C.13 Answer: b

Reference:

NRC Standard Question C14 Answer: c

Reference:

SAR Figure 8.2-1 C.15 Answer: b

Reference:

SAR8.2 C.16 Answer: d

Reference:

NRC Walk through C.17 Answer: d

Reference:

NRC Walk through C.18 Answer: d

Reference:

TS 5.3.3 C.19 Answer: a(1) b(2) c(3)

Reference:

SAR Figure 7.3-2

- - - - END OF THE EXAM ********************************

ML17136A012

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