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Examination Report No 50-166/OL-16-01, University of Maryland
	ML16299A013
Person / Time
Site:	University of Maryland
Issue date:	11/03/2016
From:	Anthony Mendiola; Research and Test Reactors Oversight Branch
To:	Koeth T; Univ of Maryland - College Park
	Anthony Mendiola
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ML16208A023	List: ML16222B018; ML16299A013;
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November 3, 2016 Dr. Timothy Koeth, Director The University of Maryland Radiation Facilities and Nuclear Reactor Department of Materials Science and Engineering 2309D Chemical and Nuclear Engineering Building Building 090, Stadium Drive College Park, MD 20742-2115

SUBJECT:

EXAMINATION REPORT NO. 50-166/OL-16-01, UNIVERSITY OF MARYLAND

Dear Dr. Koeth:

During the week of September 26, 2016, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Maryland University Training reactor.

The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with Title 10 of the Code of Federal Regulations, Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Mr. John T. Nguyen at (301) 415-4007 or via e-mail 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. 50-166

Enclosures:

1. Examination Report No. 50-166/OL-16-01

2. Written examination cc: Amber Johnson cc: w/o enclosures: See next page

Dr. Timothy Koeth, Director November 3, 2016 The University of Maryland Radiation Facilities and Nuclear Reactor Department of Materials Science and Engineering 2309D Chemical and Nuclear Engineering Building Building 090, Stadium Drive College Park, MD 20742-2115

SUBJECT:

EXAMINATION REPORT NO. 50-166/OL-16-01, UNIVERSITY OF MARYLAND

Dear Dr. Koeth:

During the week of September 26, 2016, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Maryland University Training reactor.

The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with Title 10 of the Code of Federal Regulations, Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Mr. John T. Nguyen at (301) 415-4007 or via e-mail 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. 50-166

Enclosures:

1. Examination Report No. 50-166/OL-16-01

2. Written examination cc: Amber Johnson cc: w/o enclosures: See next page DISTRIBUTION w/ encls.:

PUBLIC AMendiola AAdams CMontgomery ADAMS ACCESSION #: ML16299A013 TEMPLATE #:NRR-074 OFFICE NRR/DPR/PROB/CE NRR/DPR/PROB/OLA NRR/DPR/PROB/BC NAME JNguyen CRevelle AMendiola DATE 10/12/2016 10/25/2016 11/03/2016 OFFICIAL RECORD COPY

University Of Maryland Docket No. 50-166 cc:

Director, Dept. of Natural Resources Power Plant Siting Program Energy & Coastal Zone Administration Tawes State Office Building Annapolis, MD 21401 Roland G. Fletcher, Program Manager IV Radiological Health Program Maryland Department of Environment 1800 Washington Blvd., Suite 750 Baltimore, MD 21230-1718 Vincent G. Adams Facility Coordinator Chemical and Nuclear Engineering Building 090 University of Maryland College Park, MD 20742 Mary J. Dorman Radiation Safety Officer Department of Environmental Safety 3115 Chesapeake Building 338 University of Maryland College Park, MD 20742 Ray Phaneuf Professor and Acting Chair University of Maryland Department of Materials Science and Engineering, Room 2135 Chem. & Nuclear Engineering Building 090 College Park, MD 20742-2115 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-166/OL-16-01 FACILITY DOCKET NO.: 50-166 FACILITY LICENSE NO.: R-70 FACILITY: TRIGA EXAMINATION DATES: September 26-28, 2016 SUBMUTRTED BY: _____________/RA/ _____ __10/12/16_

John T. Nguyen, Chief Examiner Date

SUMMARY

During the week of September 26, 2016, the NRC administered operator licensing examinations to one Senior Reactor Operator-Instant (SRO-I), one Senior Reactor Operator-Upgrade (SRO-U), and three Reactor Operator (RO) candidates. The candidates passed all 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 3/0 1/0 4/0 Operating Tests 3/0 2/0 5/0 Overall 3/0 2/0 5/0

3. Exit Meeting:

John T. Nguyen, Chief Examiner, NRC Timothy Koeth, Director, MUTR Amber Johnson, Training Supervisor, MUTR At the conclusion of the meeting, the NRC Examiner thanked the facility for their support in the administration of the examinations. The facility licensee had no comments on the written examination. The examiner also discussed the weaknesses observed during the examination. Two reactor operator candidates have shown the weaknesses in a basic understanding of 10 CFR 50.59, a lack of knowledge in the operations of nuclear instrumentation channels, and unfamiliar with a condition when nuclear instrumentation channels are out of calibration. 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: Pool REACTOR TYPE: TRIGA DATE ADMINISTERED: 9/27/2016 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 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 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 *****)

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 ___ (0.25 each)

B03 a ___ b ___ c ___ d ___ (0.25 each)

B04 a b c d ___

B05 a b c d ___

B06 a ___ b ___ c ___ d ___ (0.25 each)

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 ___

B20 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 ___ (0.25 each)

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 ___ (0.3 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 MUTR 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 Q&= m&c p T = m&H = UA T ( - )2 P max = * -4

= 1 x 10 seconds 2 (k)

S CR 1 (1 - K eff 1 ) = CR 2 (1 - K eff 2 )

SCR =

1 - K eff eff = 0.1 sec -1 SUR = 26.06 eff 1 - K eff 0

- 1 CR1 M= M= =

1 - K eff 1 1 - K eff CR 2 P = P0 10 SUR(t) t P = P0 e (1 - )

P= P0 (1 - K eff )

SDM = = = +

K eff eff K eff 2 - K eff 1 0.693 ( K eff - 1)

T=

k eff 1 x K eff 2 K eff 6CiE(n) 2 DR1 d 1 = DR 2 d 2 2

DR = DR0 e- t DR = 2 R

eff = 0.1/sec 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-lbf °F = 9/5°C + 32 931 Mev = 1 amu °C = 5/9 (°F - 32)

Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.01 [1.0 point]

The following graph for U-235 depicts:

a. differential rod worth curve in the core

b. distribution of fission product yield

c. radial flux distribution in the core

d. neutron energy distribution in the moderator QUESTION A.02 [1.0 point]

You're increasing reactor power on a steady +26 second period. How long will it take to increase power by a factor of 10?

a. 1 minute

b. 3 minutes

c. 5 minutes

d. 60 minutes QUESTION A.03 [1.0 point]

Which ONE of the following is a number of neutrons in the tritium nucleus (1T3 or 1 H3 )?

a. 1 b.

b. 2

c. 3

d. 4

Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.04 [1.0 point]

The MUTR Reactor is critical at 100 W. A reactor operator makes a mistake by inserting a sample worth of $1.5 into the reactor core. 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 -eff < < 1

d. Keff > 1 and 0 < < -eff QUESTION A.05 [1.0 point]

If the multiplication factor, k, is increased from 0.800 to 0.950, the amount of reactivity added is between:

a. 0.140 - 0.150

b. 0.160 - 0.170

c. 0.180 - 0.190

d. 0.190 - 0.200 QUESTION A.06 [1.0 point]

Which ONE of the following correctly describes the SIX- FACTOR FORMULA at MUTR?

Note: : infinitive and eff: effective

a. K = Keff

the thermal utilization factor

b. K = Keff

the total non-leakage probability

c. Keff = K

the total non-leakage probability

d. Keff = K * (the resonance escape probability

the reproduction factor)

Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.07 [1.0 point]

Which ONE of the following describes the term PROMPT DROP?

a. A reactor is subcritical at negative 80-second period

b. A reactor has attained criticality on prompt neutrons alone

c. The instantaneous change in power level due to inserting a control rod

d. The instantaneous change in power level due to withdrawing a control rod QUESTION A.08 [1.0 point]

Which ONE of the following is the MAIN reason for operating reactor with thermal neutrons instead of fast neutrons?

a. The atomic weight of thermal neutrons is larger than fast neutrons, so thermal neutrons are easily to slow down and be captured by the fuel

b. The neutron lifetime of thermal neutrons is longer than fast neutrons, so the fuel has enough time to capture thermal neutrons

c. Fast neutrons give off higher radiation than thermal neutrons. Reactor needs to reduce radiation limit by using thermal neutrons

d. The fission cross section of the fuel is much higher for thermal energy neutrons than fast neutrons QUESTION A.09 [1.0 point]

Which ONE of the following is the MINIMUM amount of reactivity that makes the MUTR (finite) critical reactor to be a prompt critical reactor? This MINIMUM amount is equal to:

a. the shutdown margin

b. the -effective value

c. 1.0 % K/K

d. the factor of e

Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.10 [1.0 point]

A few minutes following a reactor scram at full power, the reactor period has stabilized and the power level is decreasing at a CONSTANT rate. What is a reactor power level five minutes later from 4 kW?

a. 1500 W

b. 940 W

c. 94 W

d. 15 W QUESTION A.11 [1.0 point]

Reactor A increases power from 10% to 20% with a period of 25 seconds. Reactor B increases power from 80% to 100% with a period of also 25 seconds. Compared to Reactor A, the time required for the power increase of Reactor B is:

a. longer than A

b. exactly the same as A

c. twice that of A

d. shorter than A QUESTION A.12 [1.0 point]

Two common FISSION PRODUCTS that have especially large neutron capture cross sections and play a significant role in reactor physics. One is Sm-149 and the other is:

a. B-10

b. Ar-41

c. Xe-135

d. Cs-137

Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.13 [1.0 point]

Which ONE statement below describes a NEGATIVE moderator temperature coefficient?

a. When moderator temperature increases, negative reactivity is added

b. When moderator temperature decreases, negative reactivity is added

c. When moderator temperature increases, positive reactivity is added

d. When moderator temperature increases, no change in reactivity QUESTION A.14 [1.0 point]

During the time following a reactor scram, reactor power decreases on an 80 second period, which corresponds to the half-life of the longest-lived delayed neutron precursors of:

a. 80 seconds

b. 55 seconds

c. 40 seconds

d. 20 seconds QUESTION A.15 [1.0 point]

You enter the control room and note that all nuclear instrumentation show a steady neutron level, and no rods are in motion. Which ONE of the following conditions CANNOT be true?

a. The reactor is critical

b. The reactor is subcritical

c. The reactor is supercritical

d. The neutron source has been removed from the core

Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.16 [1.0 point]

Which ONE of the following nuclides will cause a fast neutron to lose its most energy per collision?

a. H-1

b. B-10

c. C-12

d. U-235 QUESTION A.17 [1.0 point]

Which ONE of the following is a correct statement describing prompt and delayed neutrons?

Prompt neutrons:

a. are released during U-238 interacts with fast neutrons, while delayed neutrons are released during U-235 interacts with thermal neutrons

b. account for less than 1% of the neutron population, while delayed neutrons account for the rest

c. are released during the fission process, while delayed neutrons are released during the decayed process

d. are the dominating factor in determining reactor period, while delayed neutrons have no effect on reactor period QUESTION A.18 [1.0 point]

Which ONE of the following conditions will DECREASE the Core Excess of a reactor?

a. Lowering moderator temperature (assume negative temperature coefficient)

b. Insertion of a positive reactivity worth experiment

c. Burnout of a burnable poison

d. Fuel depletion

Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.19 [1.0 point]

The effective target area in cm2 presented by a single nucleus to an incident neutron beam is defined as:

a. a microscopic cross section

b. a macroscopic cross section

c. a mean free path

d. a neutron flux QUESTION A.20 [1.0 point]

Which ONE of the following physical characteristics of the TRIGA fuel is the main contributor for the prompt negative temperature coefficient?

a. As the fuel heats up the resonance absorption peaks broaden and increases the likelihood of neutron absorption in U-238

b. As the fuel heats up a rapid increase in moderator temperature occurs through conduction and convection heat transfer mechanisms which adds negative reactivity

c. As the fuel heats up fission product poisons (e.g., Xe) increase in concentration within the fuel matrix and add negative reactivity via neutron absorption

d. As the fuel heats up the oscillating hydrogen in the ZrH lattice imparts energy to a thermal neutron, thereby increasing its mean free path and probability of escape

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

Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.01 [1.0 point]

Per MUTR Emergency Procedure, the individual who can authorize emergency exposures in excess of normal occupational limits during rescue and recovery activities is the:

a. MUTR Police Chief

b. Public Relations Coordinator

c. MUTR Radiation Protection Officer

d. MUTR Emergency Director QUESTION B.02 [1.0 points, 0.25 each]

Match the radiation reading from Column A with its corresponding radiation area classification (per 10 CFR 20) listed in Column B. Answer in Column B can be used more than once, or not at all. Assume a Quality Factor of 1.

Column A Column B

a. 5 mrem/hr at 30 cm 1. Public Area

b. 50 mrem/hr at 30 cm 2. Radiation Area

c. 20 mrem/hr at 1 m 3. High Radiation Area

d. 550 rem/hr at 1 m 4. Very High Radiation Area QUESTION B.03 [1.0 point, 0.25 each]

Identify each of the following surveillances as a channel check (CHECK), a channel test (TEST), or a channel calibration (CAL).

a. During reactor operation, you compare readings of a reactor power level

b. During the startup, you verify the interlock system by performing simultaneous manual withdrawal of two control rods

c. During the startup, you press the manual scram to verify a reactor scram

d. Adjust the Wide Range Linear Power Channel in accordance with recent data collected on the reactor thermal power calibration

Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.04 [1.0 point]

The radiation from an unshielded source is 500 mrem/hr. You insert a lead sheet with 30 mm thickness; the radiation level reduces to 125 mrem/hr. What is the half-value-layer (HVL) of lead? (HVL: thickness of lead required so that the original intensity will be reduced by half)?

a. 15 mm

b. 20 mm

c. 30 mm

d. 60 mm QUESTION B.05 [1.0 point]

Which ONE of the following conditions requires the NRC APPROVAL for changes?

a. Revise the MUTR startup checklist

b. Add more responsibilities to facility staff requirements on the fuel movement procedure

c. Revise a frequency of requalification written examination from biennial to annual

d. Reduce a minimum number of Reactor Safety Committee members listed in Tech Spec from five to three QUESTION B.06 [1.0 point, 0.25 each]

Match each of the Technical Specification Limits in column A with its corresponding value in column B. (Each limit has only one answer, values in Column B may be used once, more than once or not at all.)

Column A Column B

a. Worth of single experiment 1. $0.30

b. Non-Secured experiment 2. $0.50

c. Excess reactivity 3. $1.00

d. Total worth of experiments 4. $3.00

5. $3.50

Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.07 [1.0 point]

Per MUTR Tec Spec, which ONE of the following will violate the Limiting Safety System Settings?

a. An unanticipated change in reactivity of two dollars

b. Instrumented fuel temperature = 450 °C

c. Steady State power of 120 % full power

d. Coolant Height = 10 feet above top of fuel core QUESTION B.08 [1.0 point]

A biennial test of the reactor shutdown margin was performed. Which ONE of the following is the latest the test that must be performed again?

a. 7.5 months after

b. 15 months after

c. 27 months after

d. 29 months after QUESTION B.09 [1.0 point]

The reactor operator licensing candidate requires submitting an NRC Form 396, Medical Requirements, as part of his or her application. This requirement can be found in:

a. 10 CFR Part 20

b. 10 CFR Part 50.59

c. 10 CFR Part 55

d. 10 CFR Part 19

Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.10 [1.0 point]

During a reactor operation, a short circuit occurs in the reactor console and causing a small fire.

Which ONE of the following classes of extinguisher would most likely be used with this type of fire?

a. Class A: Fires in ordinary combustibles, such as wood, paper, plastic, etc

b. Class B: Fires in flammable or combustible liquids, flammable gases, greases, etc

c. Class C: Fires in live electrical equipment

d. Class D: Fires involving combustible metals such as magnesium QUESTION B.11 [1.0 point]

An example of Byproduct Material would be:

a. Pu-239

b. U-233

c. U-235

d. Au-198 QUESTION B.12 [1.0 point]

A radioactive source reads 2 Rem/hr on contact. Five hours later, the same source reads 1.0 Rem/hr. How long is the time for the source to decay from a reading of 2 Rem/hr to 20 mRem/hr?

a. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

b. 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months

c. 33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months

d. 41 hours4.74537e-4 days 0.0114 hours 6.779101e-5 weeks 1.56005e-5 months

Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.13 [1.0 point]

Which ONE of the following events does NOT require the presence of a licensed Senior Reactor Operator in the facility?

a. Fuel relocations within the core region

b. Removal of Safety control rod for inspection

c. Insertion of experiment worth of $0.40

d. Restart reactor following an unplanned shutdown QUESTION B.14 [1.0 point]

A survey instrument with a window probe is used to measure the beta-gamma dose rate from an irradiated experiment. The dose rate is 240 mrem/hour with the window opened and 60 mrem/hour with the window closed. The gamma dose rate is:

a. 60 mrem/hour

b. 180 mrem/hour

c. 240 mrem/hour.

d. 300 mrem/hour QUESTION B.15 [1.0 point]

What is the HALF LIFE of the isotope contained in a sample which produces the following count rates?

Time (Minutes) Counts per Minute (cpm)

Initial 950 60 702 120 518 180 383 240 283

a. 124 minutes

b. 137 minutes

c. 201 minutes

d. 558 minutes

Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.16 [1.0 point]

Which ONE of the following radioactive gases poses the most significant hazard within the reactor room during normal operations at full power?

a. Tritium

b. Argon-41

c. Xenon-135

d. Nitrogen-16 QUESTION B.17 [1.0 point]

According to MUTR procedures and Technical Specifications, which ONE of the following is NOT considered an UNSCHEDULED SHUTDOWN?

a. Loss of Power to the building removed the high voltage supply to the reactor console and caused all the safety rods to scram

b. During the annual surveillance check, a channel input signal of 320 kW caused all the safety rods to scram

c. The operator was not watching reactor period when it reached 4 seconds and caused all the safety rods to scram

d. The operator inadvertently leaned on the scram bar with their elbow and caused all the safety rods to scram QUESTION B.18 [1.0 point]

The procedures to follow for a reactor building evacuation can be found in the:

a. 100 Series

b. 200 Series

c. 400 Series

d. 500 Series

Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.19 [1.0 point]

The tygon tubing for the pneumatic (rabbit) system is disconnected. An experiment is inserted into the core via the remaining tubing of the rabbit system. With the reactor running at 100%

power, which ONE of the following would most likely be a concern?

a. Radiation level increases due to Ar-41

b. Radiation level increases due to neutron streaming

c. Radiation level increases due to fission products released

d. Radiation level increases due to N-16 QUESTION B.20 [1.0 point]

A reactor operator works continuously in radiation area of 120 mrem/hr. What is the Maximum time he could stay there before exceeding a total dose limit (TEDE)?

a. 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months

b. 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months

c. 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months

d. 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months

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

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

The MUTR control rods are located at C-row and:

a. B-row

b. D-row

c. E-row

d. F-row QUESTION C.02 [1.0 point]

Use the following diagram of an instrumented fuel element. Which ONE of the following is the correct match for the position locator (Column A) to the correct component (Column B)?

Column A Column B I A. Zirconium Hydride-Uranium II B. Stainless steel III C. Samarium Burnable Poison IV D. Graphite Reflector E. Zirconium Rod F. Spacer G. Thermocouples

a. I-C, II-F, III-A, IV-C

b. I-D, II-A, III-E, IV-C

c. I-D, II-E, III-A, IV-G

d. I-C, II-B, III-E, IV-G

Section C Facility and Radiation Monitoring Systems Section C Facility and Radiation Monitoring Systems QUESTION C.03 [1.0 point]

Graphite inserts are placed in the top and bottom of the fuel element. Which ONE of the following best describes the function of these inserts?

a. Reduce gamma radiation

b. Increase fast neutron flux

c. Absorb fission product gases

d. Reduce neutron leakage QUESTION C.04 [1.0 point]

During reactor operation, which ONE of the following is the MAIN reason for not operating the coolant pumps in dry (no prime) for no longer than two minutes?

a. Increasing the amount of Ar-41 released to the reactor bay

b. Increasing the amount of N-16 in the reactor pool

c. Damaging the pump motor

d. Damaging the coolant pipes QUESTION C.05 [1.0 point]

The low-source-interlock signal comes from:

a. Fuel Temperature Channel

b. Wide Range Linear Channel

c. Safety Channel 2

d. Log Power Level Channel

Section C Facility and Radiation Monitoring Systems QUESTION C.06 [2.0 points, 0.5 each]

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

Column A Column B

a. Fuel temperature = 170 °C 1. Normal Operation

b. Source count rate = 1 cps 2. Alarm ONLY

c. Wide Range Linear Channel = 120% power 3. Interlock

d. Bay Radiation Monitor = exceed second setpoint 4. Scram (with or without Alarm)

QUESTION C.07 [1 point]

Which ONE of the following elements is MAINLY used as the neutron absorber on the MUTR control rods?

a. boron

b. zirconium-hydride

c. borated graphite

d. gold-indium-cadmium QUESTION C.08 [1.0 point]

A neutron flux will activate isotopes in air. The primary isotope of concern in the pneumatic transfer system is:

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

b. Kr80 (Kr79 (n, ) kr80)

c. Ar41 (Ar40 (n, ) Ar41)

d. H2 (H1 (n, ) H2)

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

Which ONE of the following is the correct parameter used for the calibration of control rods by the procedure SP 204?

a. count rate vs. 1/M

b. temperature vs. period

c. pool level vs. coolant flow

d. reactivity vs. rod height QUESTION C.10 [1.0 point, 0.25 each]

Use the following diagram of the control rod armature; match the components listed in Column A to the appropriate position locator listed in the diagram.

Column A

a. Barrel

b. Armature

c. Dashpot Port

d. Pull Rod

Section C Facility and Radiation Monitoring Systems QUESTION C.11 [1.0 point]

The Main purpose for setting a conductivity limit of the pool water is to:

a. Minimize the possibility of corrosion of the cladding on the fuel elements

b. Minimize Ar-41 released to the public

c. Extend integrity of resin bed on the demineralizer

d. Maximize the heat transfer rate between fuel elements and pool water

Section C Facility and Radiation Monitoring Systems QUESTION C.12 [1.0 point]

If 120 gpm is the total flowrate for the primary coolant system, what is the flowrate through the coolant purification system?

a. 12 gpm

b. 18 gpm

c. 60 gpm

d. 80 gpm QUESTION C.13 [1.0 point]

Which ONE of the following is the best description on how the Compensated Ion Chamber (CIC) 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. B-10 + gamma B-10 + gamma QUESTION C.14 [1.0 point]

In an event of a loss of normal electrical power, an emergency power will distribute its power to:

a. Radiation monitoring systems

b. Coolant pumps

c. Building security system

d. Reactor console

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

You conducted a control drop test for the Safety control rod. Which ONE of the following is an acceptable value?

a. 1500 msec

b. 1000 msec

c. 800 msec

d. 50 msec QUESTION C.16 [1.0 point]

Which ONE of the following is the main function of the DISCRIMINATOR circuit in the Wide Range Log Power Channel?

a. Convert the signal from a fission counter to LINEAR output over a range of 10 -8 to 150 percent of full power

b. Convert a number of pulses per second to reactor period

c. Filter out small pulses due to gamma interactions, passing only pulses due to neutron events within the Wide Range Log Power Channel

d. Generate a current signal equal and of opposite polarity as the signal due to gamma generated within the Wide Range Log Power Channel QUESTION C.17 [1.0 point]

The MUTR fuel element contains:

a. a mixture of U-Zn-O alloy with a maximum of 9.0 weight percent uranium which has a maximum enrichment of 20 percent

b. a mixture of U-Zn-H alloy with a maximum of 20 weight percent uranium which has a maximum enrichment of 9 percent

c. a mixture of U-Zr-O alloy with a maximum of 20 weight percent uranium which has a maximum enrichment of 9 percent

d. a mixture of U-Zr-H alloy with a maximum of 9.0 weight percent uranium which has a maximum enrichment of 20 percent

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

Which of the following is a correct flowpath through the primary water system? After leaving the primary coolant pump the water passes through:

a. Particle filter, flow orifice, heat exchange, demineralizer column

b. Flow orifice, particle filter, heat exchange, demineralizer column

c. Heat exchange, a particle filter, flow orifice, demineralizer column

d. Particle filter, heat exchange, flow orifice, demineralizer column 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 Facility and Radiation Monitoring Systems Section C Facility and Radiation Monitoring Systems

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

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

Section A L Theory, Thermo & Fac. Operating Characteristics A.01 Answer: b

Reference:

DOE Manual Vol. 1, pg. 57 A.02 Answer: a

Reference:

A.03 Answer: b

Reference:

Nuclides and Isotopes N=A-Z 3-1 = 2 A.04 Answer: c

Reference:

In order to solve the question A.05, the applicant can use one of the following methods:

At k=0.8; = Keff/Keff or = Keff-1/Keff = -0.2/0.8 =-0.25. At k=0.95, =-

0.05/0.95

= -0.053. The difference between is the answer ,i.e. -0.053-(-0.25)=0.197

= 1 - 2 where 1 = Keff1-1/Keff1 and 2 = Keff2-1/Keff2. Substitute 1 and 2 with Keff1 and Keff2 into the equation above, the result is = keff1-keff2/(keff1 x keff2) = 0.95-0.8 /(0.8*0.95)=0.197 A.06 Answer: c

Reference:

A.08 Answer: d

Reference:

Section A L Theory, Thermo & Fac. Operating Characteristics A.10 Answer: c

Reference:

P = P0 e-t/T = 4 kW

e(300sec/-80sec) = 4 kW

exp(-3.75) = 0.0235

4 kW =

0.094 kW = 94 W A.11 Answer: d

Reference:

The power of reactor A increases by a factor of 2, while the power of reactor B increases by a factor of 1.25. Since the periods are the same (rate of change is the same), power increase B takes a shorter time.

A.12 Answer c

Reference:

Introduction to Nuclear Operation, Reed Burn, 1982, Sec 6.4 A.14 Answer: b

Reference:

Group 1 is the longest-lived delayed neutron precursor for thermal fission in U-235, with a half-life of 55.72 sec.

Lamarsh, J. Introduction to Nuclear Engineering p. 88 A.15 Answer: c

Reference:

decreasing the reactivity worth in the core will decrease the core excess.

A.19 Answer: a

Reference:

TRIGA Fuel Design

Section B Normal/Emergency Procedures and Radiological Controls B.01 Answer: d

Reference:

EP 406, Section 3.0 B.02 Answer: a(2); b(2); c(3); d(4)

Reference:

10 CFR 20.1003 Definitions For part c, 20 mrem/hr at 1m will be equal to 222 mrem/hr at 30 cm :=> high radiation area 550 rem/hr / (QF = 1) 550 rad/hr at 1 m very high radiation area Definition High Radiation Area: 100 mrem/hr at 30 cm Radiation Area : 5 mrem/hr at 30 cm Very High Radiation Area: 500 rads/hr at 1 m B.03 Answer: a = CHECK; b = TEST; c = TEST; d = CAL

Reference:

MUTR Technical specification, Definitions B.04 Answer: a

Reference:

DR = DR*e -X Find : 125 = 500* e -*30 ; = 0.0462 If insertion of an HVL (thickness of lead), the original intensity will be reduced by half.

Find X: 1 = 2* e -0.0462*X ; X= 15 mm Find HVL by shortcut:

500mR- 250 mR is the 1st HVL 250 mR - 125 mR is the 2nd HVL So HVL=30mm/2 = 15 mm B.05 Answer: d

Reference:

TS change requires an amendment B.06 Answer: a, 3 b,3 c,5 d,4

Reference:

TS 3.1 and TS 3.5 B.07 Answer: b

Reference:

TS 2.2 B.08 Answer: c

Reference:

TS 4.1 B.09 Answer: c

Reference:

10 CFR 55

Section B Normal/Emergency Procedures and Radiological Controls B.10 Answer: c

Reference:

NRC standard question B.11 Answer: d

Reference:

Byproduct material is any radioactive material (except special nuclear material) made radioactive by the process of producing or using special nuclear material.

10 CFR Part 20.1003 B.12 Answer: c

Reference:

DR = DR*e -t 1 rem/hr =2 rem/hr* e -(5hr)

Ln(1.0/2) = -*5 --> =0.1386; solve for t: Ln(.02/2)=-0.1386 (t) t=33 hours B.13 Answer: c

Reference:

TS Section 6.1.3 B.14 Answer: a

Reference:

Basic radiation instrumentation B.15 Answer: b

Reference:

, , , = 0.00505

, minutes B.16 Answer: b

Reference:

NRC Standard Question B.17 Answer: b

Reference:

TS 1.30 B.18 Answer: c

Reference:

MUTR Procedure Index B.19 Answer: a

Reference:

MUTR SAR B.20 Answer c

Reference:

5000 mrem/120 mr/hr= 41.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months will exceed the TEDE limit

Section C Facility and Radiation Monitoring Systems C.01 Answer: c

Reference:

SAR, Figure 4.9 C.02 Answer: c

Reference:

SAR, Figure 4.2 C.03 Answer: d

Reference:

SAR 4.1 C.04 Answer: c

Reference:

NRC Standard Question C.05 Answer: d

Reference:

SAR Figure 7.7 and 7.3.3 C.06 Answer: a(1) b(3) c(4) d(4)

Reference:

SAR, Chapter 7 and TS, Section 3 C.07 Answer: c

Reference:

SAR 4.2.2.1 C.08 Answer: c

Reference:

NRC Standard Question C.09 Answer: d

Reference:

SP 204 C.10 Answer: a(3) b(4) c(8) d(1)

Reference:

SAR Figure 4.14 C.11 Answer: a

Reference:

TS 4.1.2 C.12 Answer: a

Reference:

SAR 5.4.2 C.13 Answer: b

Reference:

NRC Standard Question

Section C Facility and Radiation Monitoring Systems C.14 Answer: c

Reference:

SAR 8.2 C.15 Answer: c

Reference:

Technical Specifications 3.2 (d is within a TS but it is too short)

C.16 Answer: c

Reference:

SAR 7.4.1.1.1 C.17 Answer: d

Reference:

SAR 4.2.1.1 C.18 Answer: a

Reference:

SAR, Figure 5.1 C.19 Answer: a(1) b(2) c(3)

Reference:

SAR 4.2.2

ML16299A013

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