Text

Examination Report 50-243/OL-16-001,February 23, 2016 Oregon State University
	ML16073A009
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Site:	Oregon State University
Issue date:	03/21/2016
From:	Anthony Mendiola; Research and Test Reactors Branch B
To:	Reese S; Oregon State University
	Anthony Mendiola
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ML16073A008	List: ML16073A009;
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March 21, 2016 Dr. Steven E. Reese, Director Oregon State University Radiation Center, A100 Corvallis, OR 97331-5903

SUBJECT:

EXAMINATION REPORT NO. 50-243/OL-16-01, OREGON STATE UNIVERSITY

Dear Dr. Reese:

During the week of February 22, 2016, the NRC administered an operator licensing examination at your Oregon State University TRIGA reactor. The examination was conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors,"

Revision 2. Examination questions and preliminary findings were discussed with you and 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 enclosure 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 Mrs. Paulette Torres at (301) 415-5656 or via e-mail Paulette.Torres@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. 50-243

Enclosures:

1. Examination Report No. 50-243/OL-16-01

2. Facility Comments with NRC Resolution

3. Written Examination cc w/o enclosures: See next page

ML16073A009 NRR-079 OFFICE NRR/DPR/PROB/CE NRR/DPR/PROB/OLA NRR/DPR/PROB/BC NAME PTorres CRevelle AMendiola DATE 3/01/2016 3/14/2016 3/21/2016 Oregon State University Docket No. 50-243 cc:

Mayor of the City of Corvallis Corvallis, OR 97331 Division Administrator Nuclear Safety Division Oregon Department of Energy 625 Marion Street NE Salem, OR 97301-3737 Dr. Ron Adams Interim Vice President for Research Oregon State University Administrative Services Bldg., Room A-312 100 Radiation Center Corvallis, OR 97331-5904 Mr. Todd Keller Reactor Administrator Oregon State University 100 Radiation Center, A-100 Corvallis, OR 97331-5903 Dr. Andrew Klein, Chairman Reactor Operations Committee Oregon State University 100 Radiation Center, A-100 Corvallis, OR 97331-5904 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.: 50-243/OL-16-01 FACILITY DOCKET NO.: 50-243 FACILITY LICENSE NO.: R-120 FACILITY: Oregon State University TRIGA Reactor EXAMINATION DATE: February 23, 2016 SUBMITTED BY: _____________/RA/ ______ ____03/15/2016____

Paulette Torres, Chief Examiner Date

SUMMARY

During the week of February 22, 2016 the NRC administered a licensing examination to one Reactor Operator (RO) applicant. The applicant passed all portions of the examination.

REPORT DETAILS

1. Examiner: Paulette Torres, Chief Examiner, NRC

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 1/0 0/0 1/0 Operating Tests 1/0 0/0 1/0 Overall 1/0 0/0 1/0

3. Exit Meeting:

Paulette Torres, Chief Examiner, NRC S. Todd Keller, SRO / Reactor Administrator, OSTR Celia Oney, Reactor Supervisor, OSTR The facility licensee agreed to email their comments on the written examination that were incorporated in the examination report (see Enclosure 2).

FACILITY COMMENTS ON THE WRITTEN EXAM WITH NRC RESOLUTION We do not wish to challenge any of the exam (written) questions, but we would like to provide as much feedback as possible to improve future exams. In particular, we wish to point out that at the Oregon State TRIGA Reactor (OSTR) there is no line of succession that would result in a licensed RO taking on the duties of the Reactor Supervisor, an SRO licensed position. A licensed RO should certainly be aware of supervisor duties, and be able to provide advice. However, in accordance with our emergency plan, the RO may be required to take on duties of the Radiological Assessment Team and/or a hallway checker, but the RO will not rise to the level of responsibility of the Supervisor.

Please see below for specific comments on written exam questions. Note that we can only provide feedback on written questions since oral interactions were not specifically documented.

QUESTION A.06 [1.0 point, 0.33 each]

Match the best answer. If a reactor has values of k (multiplication factor) and (reactivity) as follow:

Column A Column B

a. k = 1, = 0 1. The rate of fissioning is increasing.

b. k < 1, < 0 2. The rate of fissioning is decreasing.

c. k > 1, > 0 3. The rate of fissioning is constant.

Answer: a, 3 b,2 c,1 REF: OSU TRIGA Reactor Operator Training I, Neutron Flux and Multiplication Factor OSU TRIGA Reactor Training Manual, Volume 3, pg. 12 Lamarsh, 3rd ed., Section 7.2, pg. 337 When k = 1, = 0 and reactor is critical When k < 1, < 0 and reactor is subcritical When k > 1, > 0 and reactor is supercritical Facility Comments &

Recommendations: It should be clarified that there is no neutron source present.

Some of the answers change if a source is present in the reactor.

NRC Resolution: Thank you for the comment. We will consider writing the question differently in the future.

ENCLOSURE 2

QUESTION A.07 [1.0 point]

Which ONE of the following factors is not affected by the amount of moderator in the reactor?

a. Fast Fission Factor ()

b. Resonance Escape Probability (p)

c. Thermal Utilization Factor (f)

d. Reproduction Factor ()

Answer: d REF: The reproduction factor (also called the fuel utilization factor) is not affected by the moderator since it is purely a function of the nuclear characteristics of 235U and other fissile nucleus.

OSU TRIGA Reactor Training Manual, Volume 3, pg. 11 DOE Fundamentals Handbook, NP-03, pg. 6-8 Facility Comments &

Recommendations: The Reproduction Factor is slightly dependent on neutron spectrum and average neutron energy. This factor depends on the average number of neutrons released from fission, , which is dependent on neutron energy. Average neutron energy is determined by the amount of moderator present. (See Duderstadt and Hamilton, Nuclear Reactor Analysis, p. 61, fig. 2-20.) We feel that this question has no correct answer. Changing the wording from not affected to least affected would make (d) the best answer.

NRC Resolution: Thank you for the comment. We will consider writing the question differently in the future.

QUESTION B.04 [1.0 point]

Which ONE of the following Radiation Monitoring Channels is NOT required to measure gaseous airborne radionuclide concentration?

a. Reactor Top Area Radiation Monitor

b. Continuous Air Particulate Radiation Monitor

c. Exhaust Gas Radiation Monitor

d. Exhaust Particulate Radiation Monitor Answer: b ENCLOSURE 2

REF: OSU TRIGA Reactor Operator Training I & II, Radiological Protection OSU TRIGA Reactor Training Manual, Volume 4, pg. 20 Facility Comments &

Recommendations: This question is a bit confusing and may have no correct answer from the options provided. All four of the possible answers are required by Tech Specs. (TS 3.7.1, Table 4). The reference in the answer key refers to the OSU TRIGA Reactor Training Manual, Vol. 4, pg. 20. This page states: The CAM is also capable of measuring the gaseous airborne radionuclide concentration using a G-M detector; however, this feature is not required by technical specifications. This sentence refers to the Continuous Air Gas Radiation Monitor, which would be the correct answer to the question as written.

NRC Resolution: Thank you for the comment. We will consider writing the question differently in the future.

QUESTION C.03 [1.0 point]

Which ONE of the following Safety Channels operates in all effective modes?

a. High Voltage

b. Fuel Element Temperature

c. Power Level

d. Preset Timer Answer: a REF: TS 3.2.3, Table 2, pg. 14 Facility Comments &

Recommendations: As stated in the answer key, the correct answer is (a) per TS 3.2.3 Table 2, Minimum Reactor Safety Channels. However, some of the items in this table, including the High Voltage scram, do not fit the Technical Specification definition of a Safety Channel (TS 1.27, a measuring channel in the reactor safety system). We are currently undergoing revisions to our Technical Specifications and this will be corrected in the future. For this question, changing Safety Channels to Safety Systems or SCRAMs would make the intent of the question more clear.

NRC Resolution: Thank you for the comment. We will consider writing the question differently in the future.

ENCLOSURE 2

QUESTION C.05 [1.0 point]

Which ONE of the following Interlocks operates only in the steady state and square wave mode?

a. 1 kW Pulse Interlock

b. Shim, Safety, and Regulating Rod Drive Circuit Interlock

c. Wide Range Log Power Level Channel Interlock

d. Transient Rod Cylinder Interlock Answer: b REF: TS 3.2.3 Table 3, pg. 14 Facility Comments &

Recommendations: This question is a bit confusing and may have no correct answer from the options provided. The answer key gives (b) as the correct answer, Shim, Safety, and Regulating Rod Drive Circuit Interlock. TS 3.2.3, Table 3, lists this interlock twice, with one function in steady state and square wave mode and a different function in pulse mode. None of the interlocks in this table operate only in steady state and square wave mode.

NRC Resolution: Thank you for the comment. We will consider writing the question differently in the future.

QUESTION C.16 [1.0 point]

Per Technical Specifications, activities such as changing out of the NORMAL core, moving away from the reference state or adding negative worth experiments will make core excess __________ and shutdown margin __________.

a. Less Negative, More Positive

b. More Positive, Less Negative

c. More Negative, Less Positive

d. Less Positive, More Negative Answer: c REF: TS 3.1.3 Basis, pg. 10 Facility Comments &

ENCLOSURE 2

Recommendations: The stated basis of this Technical Specification is incorrect. Core Excess should never be a negative quantity and Shutdown Margin should never be a positive quantity. We believe that (d) is the most correct option. We are currently undergoing revisions to our Technical Specifications and this will be corrected in the future.

NRC Resolution: Thank you for the comment.

QUESTION C.17 [1.0 point]

Which ONE of the following Reactor Measuring Channels may not be inoperable while the reactor is operating?

a. Fuel Element Temperature

b. Linear Power Level

c. Log Power Level

d. Power Level Answer: a REF: TS 3.2.2 Footnote (1), pg. 12 TS 3.2.3 Footnote (1), pg. 14 Facility Comments &

Recommendations: The answer key gives (a), Fuel Element Temperature as the correct answer on the basis of TS 3.2.2 Footnote (1) and 3.2.3 Footnote (1). However, these footnotes apply if a channel is inoperable while performing a channel check, test, or experiment.

TS 3.2.2 Footnote (2) states that if any of the required measuring channels (including Fuel Element Temperature) becomes inoperable for other reasons (i.e., channel failure), the channel shall be restored within five minutes or the reactor shall be shutdown.

NRC Resolution: Thank you for the comment. We will consider writing the question differently in the future.

ENCLOSURE 2

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: Oregon State University REACTOR TYPE: TRIGA DATE ADMINISTERED: 02/23/2016 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 3

A. Reactor Theory, Thermohydraulics & Facility Operating Characteristics ANSWER SHEET Multiple Choice (Circle or X your choice)

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

A01 a ___ b ___ c ___ d ___

A02 a b c d ___

A03 a b c d ___

A04 a b c d ___

A05 a b c d ___

A06 a ___ b ___ c ___

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 SECTION A *****)

B. Normal/Emergency Procedures and Radiological Controls ANSWER SHEET Multiple Choice (Circle or X your choice)

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

B01 a b c d ___

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 ___

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 SECTION B *****)

C. Facility and Radiation Monitoring Systems ANSWER SHEET Multiple Choice (Circle or X your choice)

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

C01 a b c d ___

C02 a b c d ___

C03 a b c d ___

C04 a b c d ___

C05 a b c d ___

C06 a ___ b ___ c ___ 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 SECTION 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 + & CR1 ( 1 ) = CR2 ( 2 )

SUR = 26 .06

( ) (

CR1 1 K eff1 = CR2 1 K eff 2 )

(1 ) M=

1 CR

= 2 P = P0 10SUR(t )

P= P0 1 K eff CR1 1 K eff1 1 K eff M=

1 K eff 2 SDM = =

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 = 3.7 x 1010 dis/sec 1 kg = 2.21 lbm 3

1 Horsepower = 2.54 x 10 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 1 BTU = 778 ft-lbf °F = 9/5 °C + 32 1 gal (H2O) 8 lbm °C = 5/9 (°F - 32) cP = 1.0 BTU/hr/lbm/°F cp = 1 cal/sec/gm/°C

OREGON STATE UNIVERSITY Operator Licensing Examination Week of February 22, 2016

Section A: Theory, Thermo & Facility Operating Characteristics Page 2 QUESTION A.01 [1.0 point, 0.25 each]

The following are various particles emitted in the radioactive process. Match the emission with its corresponding change in nucleus.

Column A: Emission Column B: Mass #, Atomic #

a. Beta 1. No change , No change

b. Gamma 2. No change , Decreases by 1

c. Positron 3. Decreases by 1, No change

d. Neutron 4. No change, Increases by 1 QUESTION A.02 [1.0 point]

Xenon-135 is formed directly by decay of __________.

a. Antimony-135

b. Cesium -135

c. Iodine-135

d. Tellurium-135 QUESTION A.03 [1.0 point]

The term Core Excess is defined as:

a. The negative reactivity inserted by an increase in moderator temperature within the core when the reactor is brought from zero to full power.

b. Provides a measure of excess reactivity available to overcome fission product buildup, fuel burnup, and power defect.

c. The amount of negative reactivity that would be added to a core if the rods in a critical, cold, clean reactor were fully inserted.

d. The positive reactivity available which is above that necessary to achieve criticality.

Section A: Theory, Thermo & Facility Operating Characteristics Page 3 QUESTION A.04 [1.0 point]

The count rate is 100 cps. An experimenter inserts an experiment into the core, and the count rate decreases to 60 cps. Given the initial Keff of the reactor was 0.92, what is the worth of the experiment?

a. = - 0.07

b. = + 0.07

c. = - 0.02

d. = + 0.02 QUESTION A.05 [1.0 point]

From the figure below, which ONE of the following points corresponds to a condition leading to a Departure from Nucleate Boiling (DNB)?

a. Point A

b. Point B

c. Point C

d. Point D

Section A: Theory, Thermo & Facility Operating Characteristics Page 4 QUESTION A.06 [1.0 point, 0.33 each]

Match the best answer. If a reactor has values of k (multiplication factor) and (reactivity) as follow:

Column A Column B

a. k = 1, = 0 1. The rate of fissioning is increasing.

b. k < 1, < 0 2. The rate of fissioning is decreasing.

c. k > 1, > 0 3. The rate of fissioning is constant.

QUESTION A.07 [1.0 point]

Which ONE of the following factors is not affected by the amount of moderator in the reactor?

a. Fast Fission Factor ()

b. Resonance Escape Probability (p)

c. Thermal Utilization Factor (f)

d. Reproduction Factor ()

QUESTION A.08 [1.0 point]

Which ONE of the following statements correctly describes the term neutron lifetime?

a. The mean time required for fission neutrons to slow down to thermal energies.

b. The average time that thermal neutrons diffuse before being lost in some way.

c. The time between succeeding neutron generations and is the sum of fission time, slowing down time, and diffusion time.

d. The average time elapsing between the release of a neutron in a fission reaction and its loss from the system by absorption or escape.

Section A: Theory, Thermo & Facility Operating Characteristics Page 5 QUESTION A.09 [1.0 point]

Most text books list for a U235 fueled reactor as 0.0065 K/K and eff as being 0.0075 K/K. Why is eff larger than ?

a. Delayed neutrons are born at lower energies than prompt neutrons resulting in less loss due to leakage for these neutrons.

b. Delayed neutrons are born at higher energies than prompt neutrons resulting in a greater worth for these neutrons.

c. The fuel includes U238 which has a relatively large for fast fission.

d. Some U238 in the core becomes Pu239 (by neutron absorption) which has a larger for fission.

QUESTION A.10 [1.0 point]

The term macroscopic cross section is defined as:

a. The average distance travelled by a neutron between interactions in a material.

b. An indication of energy loss per collision.

c. The probability of neutron interaction per centimeter of travel in a material.

d. The effective cross sectional area of a single nucleus presented to an oncoming neutron.

QUESTION A.11 [1.0 point]

During a Subcritical Multiplication "1/M" plot, data is required to be taken. What does the 1/M represent?

a. The inverse of fuel elements presented in the core.

b. The inverse of the moderator coefficient of reactivity.

c. The inverse migration length of neutrons of varying energies.

d. The inverse multiplication of the count rate between generations.

Section A: Theory, Thermo & Facility Operating Characteristics Page 6 QUESTION A.12 [1.0 point]

Which ONE defines an integral rod worth curve?

a. A plot of incremental reactivity (K/K/in) as a function of the axial rod position (in) in the core.

b. Any point on the curve represents the amount of reactivity that one inch of rod motion would insert at that position in the core.

c. Represents the cumulative area under the differential curve starting from the bottom of the core.

d. Reactivity is lowest at the top of the core and bottom of the core.

QUESTION A.13 [1.0 point]

Which ONE of the following is the correct reason for the 80 second negative period following a reactor scram?

a. The fuel temperature coefficient adding positive reactivity due to the fuel temperature decrease following a scram.

b. The ability of U-235 to fission with source neutrons.

c. The decay constant for the longest lived precursor.

d. The amount of negative reactivity added on a cram being greater that the shutdown margin.

QUESTION A.14 [1.0 point]

The reactor is operating at a power of 1 MW. The reactor shutdown adding a reactivity of

$1.10. To what fission power level has the reactor fallen 5 minutes later? (Assume eff =

0.0065)

a. 0.01 MW

b. 0.02 MW

c. 0.11 MW

d. 0.48 MW

Section A: Theory, Thermo & Facility Operating Characteristics Page 7 QUESTION A.15 [1.0 point]

By reducing neutron leakage, the __________ increases keff and reduces the amount of fuel necessary to make the reactor critical.

a. Reflector

b. Control Rods

c. Moderator

d. Source QUESTION A.16 [1.0 point]

The reactor is critical at 5 watts. Which ONE of the following correctly describes the reactor behavior when a reactivity worth of 0.50% K/K is IMMEDIATELY inserted to the reactor core?

a. Subcritical

b. Critical

c. Supercritical

d. Delayed Critical QUESTION A.17 [1.0 point]

Which one of the following has the highest thermal neutron cross section?

a. Cd-113

b. Gd-157

c. Xe-135

d. Sm-149

Section A: Theory, Thermo & Facility Operating Characteristics Page 8 QUESTION A.18 [1.0 point]

Which ONE is true about the four factor formula, k = p f ?

a. Neutron leakages can be reduced by increasing the size of the core.

b. Neutron leakages can be reduced by using a reflector.

c. Neutron leakages can be reduced by increasing moderator temperature.

d. There is no leakage term. The reactor is considered to be infinite in size.

QUESTION A.19 [1.0 point]

Reactor period is defined as __________.

a. The time required to change reactor power by a factor of e.

b. The time required for the reactor power to double.

c. The number of factors of ten that reactor power changes in one minute.

d. The fraction of all neutrons that are born as delayed neutrons.

QUESTION A.20 [1.0 point]

Which one of the following is the MAJOR source of energy released during fission?

a. Kinetic energy of the fission neutrons.

b. Kinetic energy of the fission fragments.

c. Decay of the fission fragments.

d. Prompt gamma rays.

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

Section B: Normal/Emergency Procedures and Radiological Controls Page 9 QUESTION B.01 [1.0 point]

Per 10 CFR 20.1003, a __________ is defined as an area, access to which is limited by the licensee for the purpose of protecting individuals against undue risk from exposure to radiation and radioactive materials.

a. Restricted Area

b. Radiation Area

c. High Radiation Area

d. Airborne Radioactivity Area QUESTION B.02 [1.0 point]

What is the Occupation Dose Limit for Total Effective Dose Equivalent?

a. 0.5 rem

b. 5 rem

c. 15 rem

d. 50 rem QUESTION B.03 [1.0 point]

Which ONE of the following Area Radiation Monitors (ARMs) has an intermediate alarm setting of 10 mR/h?

a. Beam Port # 4

b. Fuel Storage Pits

c. Sample Handling

d. Demineralizer Column

Section B: Normal/Emergency Procedures and Radiological Controls Page 10 QUESTION B.04 [1.0 point]

Which ONE of the following Radiation Monitoring Channels is NOT required to measure gaseous airborne radionuclide concentration?

a. Reactor Top Area Radiation Monitor

b. Continuous Air Particulate Radiation Monitor

c. Exhaust Gas Radiation Monitor

d. Exhaust Particulate Radiation Monitor QUESTION B.05 [1.0 point]

If the Nitrogen-16 control system was not in use, what type of dose would increase?

a. Alpha

b. Beta

c. Gamma

d. Neutron QUESTION B.06 [1.0 point]

Which ONE of the following dosimeters measures ONLY gamma dose and gives real-time dose information, but not dose rate?

a. Thermoluminescent Dosimeter (TLD)

b. Electronic Dosimeter

c. Pocket Ion Chamber (PIC)

d. Finger Rings

Section B: Normal/Emergency Procedures and Radiological Controls Page 11 QUESTION B.07 [1.0 point]

The OSTR shall notify the NRC within 30 days when finding that the licensed operator is convicted for a felony. This requirement can be found in:

a. 10 CFR Part 26

b. 10 CFR Part 50.59

c. 10 CFR Part 55

d. 10 CFR Part 73 QUESTION B.08 [1.0 point]

Which ONE of the following statements correctly describes the relationship between the Safety Limit (SL) and the Limiting Safety System Setting (LSSS)?

a. The LSSS is a limit on important process variables that assures the integrity of the fuel cladding. The SL initiates protective action to preclude reaching the LSSS.

b. The SL is a limit on important process variables that assures the integrity of the fuel cladding. The LSSS initiates protective actions to preclude reaching the SL.

c. The SL is a maximum operationally limiting value that prevents exceeding the LSSS during normal operations.

d. The SL is a maximum setpoint for instrumentation response. The LSSS is the minimum number of channels required to be operable.

QUESTION B.09 [1.0 point]

Which ONE of following types of radiation has the LOWEST Quality Factor specified in 10 CFR 20?

a. Alpha Particles, Heavy Recoil Nuclei

b. Gamma/X-Ray/Beta

c. Fast Neutrons/Protons

d. Thermal Neutrons

Section B: Normal/Emergency Procedures and Radiological Controls Page 12 QUESTION B.10 [1.0 point]

An applicant for a license shall have a medical examination by a physician every

a. Six Months

b. One Year

c. Two Years

d. Four Years QUESTION B.11 [1.0 point]

In accordance with 10 CFR Part 50.47(b)(11), under what conditions a radiation worker can have exposure in excess of 10 CFR 20 limits?

a. During any emergency.

b. For lifesaving situations, a total effective dose equivalent of up to 25 rem is permissible, due to the urgency of the situation.

c. As long as the radiation worker does not exceed 50 Rem whole body for life saving.

d. In an emergency declared by the Emergency Director with concurrence of the OSU Radiation Safety Officer if available.

QUESTION B.12 [1.0 point]

The __________ ensures proper evacuation of the reactor facility when evacuation is required during an emergency.

a. Emergency Director

b. Radiation Center Director

c. Emergency Coordinator

d. Senior Reactor Operator

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

Which ONE of the following is denoted as a Class O Emergency event?

a. Personnel and Operational Events

b. Notification of Unusual Events

c. Alert

d. Site Area Emergency QUESTION B.14 [1.0 point]

If background radiation levels permit, direct surface contamination levels will be monitored using a __________ detector.

a. Geiger-Müeller

b. Plastic Scintillator

c. Ionization Chamber

d. High-Purity Germanium (HPGe)

QUESTION B.15 [1.0 point]

Which ONE of the following correctly defines the term Emergency Action Levels?

a. Projected radiation doses or dose commitments to individuals in the general population that warrant protective action following a release of radioactive material.

b. Radiological dose rates, specific concentrations of airborne, waterborne or surface-deposited radioactive materials, specific observations, or specific instrument readings that may be used as thresholds for initiating specific emergency measures.

c. Actions taken during or after an accident to obtain and process information that is necessary when deciding whether to implement specific emergency measures.

d. Measures taken in anticipation of an uncontrolled release of radioactive material, or after an uncontrolled release of radioactive material has occurred, for the purpose of preventing or minimizing personnel radiation doses or dose commitments that would otherwise be likely to occur if the actions were not taken.

Section B: Normal/Emergency Procedures and Radiological Controls Page 14 QUESTION B.16 [1.0 point]

Beam Port 3 abnormal operations is an example of a __________.

a. High Voltage Scram

b. Safety Scram

c. Experiment Scram

d. External Scram QUESTION B.17 [1.0 point]

All of the following items are audited by the Reactor Operations Committee (ROC) on an annual basis EXCEPT:

a. The Emergency Plan

b. The Physical Security Plan

c. The Technical Specifications

d. The Reactor Operator Requalification Program QUESTION B.18 [1.0 point]

The water temperature shall not be permitted to rise above 49°C. This is a Technical Specification Requirement:

a. To minimize the degradation of the aluminum tank.

b. To maintain the usefulness of the demineralizer resin.

c. For best operation of the skimmer and for proper shielding.

d. For effective cooling of the fuel.

Section B: Normal/Emergency Procedures and Radiological Controls Page 15 QUESTION B.19 [1.0 point]

If the reactor is to be operated at greater than 100 kW, then the __________ purge must be in service.

a. Nitrogen

b. Argon

c. Xenon

d. Radon QUESTION B.20 [1.0 point]

While operating the pneumatic-transfer rabbit system, the remote area monitor indicates greater than 10 mR h-1, but less than 50 mR h-1. Per the radiation monitoring procedure for the rabbit system you are required to:

a. Stand back. Do not handle the sample. Wait for a reactor operations or health physics staff member to monitor the sample.

b. Quickly remove the rabbit capsule using remote handling tongs and place the rabbit at the bottom of the hood within the lead brick shielded area.

c. Grasp the rabbit capsule with remote handling tongs and place it in the round lead holder/shield.

d. Evacuate D102 and proceed to the east end of the controlled hallway. Wait there for instructions from the Reactor Operations staff or health physics personnel.

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

Section C: Facility and Radiation Monitoring Systems Page 16 QUESTION C.01 [1.0 point]

The instrumented fuel element shall be located in the __________.

a. B-ring

b. C-ring

c. E-ring

d. G-ring QUESTION C.02 [1.0 point]

Which ONE of the following correctly describes the characteristic of the unirradiated 30/20 fuel rods used at the OSTR?

a. The uranium content is a nominal 30 wt%, enriched to less than 20% U-235; and the natural erbium content is homogeneously distributed with a nominal 1.1 wt%.

b. The uranium content is a nominal 30 wt%, enriched to less than 20% U-235, and NO erbium content.

c. The hydrogen to zirconium atom ratio (in the ZrHx) shall be between 1.5 and 1.8.

d. The uranium content is 30 wt%, enriched to less than 20% U-235; and the natural erbium content is homogeneously distributed with a nominal 0.90 wt%.

QUESTION C.03 [1.0 point]

Which ONE of the following Safety Channels operates in all effective modes?

a. High Voltage

b. Fuel Element Temperature

c. Power Level

d. Preset Timer

Section C: Facility and Radiation Monitoring Systems Page 17 QUESTION C.04 [1.0 point]

Which ONE of the following systems is located on the first floor, mechanical equipment room of the reactor building?

a. The Reactor Cooling System Components

b. The Pneumatic Transfer System Receiver Sender Stations

c. The Reactor Building Pressure Regulating Systems

d. The Fuel Storage Pits QUESTION C.05 [1.0 point]

Which ONE of the following Interlocks operates only in the steady state and square wave mode?

a. 1 kW Pulse Interlock

b. Shim, Safety, and Regulating Rod Drive Circuit Interlock

c. Wide Range Log Power Level Channel Interlock

d. Transient Rod Cylinder Interlock QUESTION C.06 [1.0 point, 0.25 points each]

Match the possible combination of standard control rod indicating lights UP, DOWN and CONT/ON in Column A with the possible meaning of each combination for Control Rod and Drive Normal Condition in Column B.

Column A: UP, DOWN, CONT/ON Column B: Control Rod and Drive Normal Condition

a. ON, OFF, ON 1. After scram, control rod down.

b. OFF, ON, ON 2. Rod drive completely withdrawn, magnet making contact.

c. OFF, OFF, ON 3. Rod and drive between either limit, magnet making contact.

d. OFF, OFF, OFF 4. Rod and drive at their lower limits, magnet making contact.

Section C: Facility and Radiation Monitoring Systems Page 18 QUESTION C.07 [1.0 point]

The Uncompensated Ion Chamber __________.

a. Is able to discriminate between Neutrons and Beta Radiation.

b. Is able to discriminate between Neutrons and Fission Fragments.

c. Is able to discriminate between Neutrons and Gamma Radiation.

d. Lacks Gamma Compensation.

QUESTION C.08 [1.0 point]

The __________ is grounded in square-wave and pulse modes.

a. Linear Channel

b. Log-N Channel

c. Safety Channel

d. Period Channel QUESTION C.09 [1.0 point]

Which ONE of the following reactor power indicator monitors DOES NOT operates off the Fission Chamber?

a. Linear Power Recorder

b. Log Power Recorder

c. Safety Power Meter

d. Log Power Meter

Section C: Facility and Radiation Monitoring Systems Page 19 QUESTION C.10 [1.0 point]

Fuel element temperature must be limited in the TRIGA fuel element in order to avoid fuel element cladding failure due to which of the following mechanisms:

a. Distortion of the fuel element due to a phase change of the 304 stainless steel.

b. Fission product built up.

c. Excessive pressure from expansion of Argon-41.

d. Excessive pressure caused by air, fission product gases, and zirconium hydride hydrogen dissociation.

QUESTION C.11 [1.0 point]

Which ONE of the following design features prevents the accidental siphoning of reactor pool water?

a. The action of the coolant diffuser nozzle.

b. The capacity of the primary coolant makeup water tank.

c. A positive pressure difference between the shells inside the heat exchanger.

d. Holes located in the in-tank system pipping at 22 inches below normal tank level.

QUESTION C.12 [1.0 point]

Which ONE of the following Standard Control Rod Drive components provides rod position indication?

a. Limit Switches

b. Potentiometer

c. Electromagnet

d. Armature

Section C: Facility and Radiation Monitoring Systems Page 20 QUESTION C.13 [1.0 point]

Which ONE of the following Beam Ports is the piercing Beam Port that penetrates the graphite reflector?

a. B.P. # 1

b. B.P. # 2

c. B.P. # 3

d. B.P. # 4 QUESTION C.14 [1.0 point]

Which ONE of the following will result in a reactor scram?

a. Bulk tank water temperature exceeds 40°C.

b. Instrumented fuel element temperature exceeds 500°C.

c. Simultaneous withdrawal of two control rods.

d. Loss of high voltage to the power measuring channels.

QUESTION C.15 [1.0 point]

The ventilation system shall be shut down upon a high activity alarm from:

a. Reactor Top Area Radiation Monitor

b. Continuous Air Particulate Radiation Monitor

c. Exhaust Gas Radiation Monitor

d. Exhaust Particulate Radiation Monitor

Section C: Facility and Radiation Monitoring Systems Page 21 QUESTION C.16 [1.0 point]

Per Technical Specifications, activities such as changing out of the NORMAL core, moving away from the reference state or adding negative worth experiments will make core excess __________ and shutdown margin __________.

a. Less Negative, More Positive

b. More Positive, Less Negative

c. More Negative, Less Positive

d. Less Positive, More Negative QUESTION C.17 [1.0 point]

Which ONE of the following Reactor Measuring Channels may not be inoperable while the reactor is operating?

a. Fuel Element Temperature

b. Linear Power Level

c. Log Power Level

d. Power Level QUESTION C.18 [1.0 point]

Which ONE of the following OSTR Control Rods is equipped with a pneumatic system?

a. Regulating Rod

b. Shim Rod

c. Safety Rod

d. Transient Rod

Section C: Facility and Radiation Monitoring Systems Page 22 QUESTION C.19 [1.0 point]

The reactor bay is maintained at a negative pressure with respect to outside atmosphere to:

a. Minimize uncontrollable leakage to the unrestricted environment.

b. Prevent the generation of Argon-41.

c. Keep personnel exposures ALARA.

d. Expedite reactor cooling by natural convection.

QUESTION C.20 [1.0 point]

Per Technical Specifications, to guarantee the radiation levels at the top of the reactor are within acceptable levels, the Reactor Primary Tank Water level shall be greater than

__________ of water above the top of the core.

a. 12 feet

b. 14 feet

c. 16 feet

d. 20 feet

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

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

Oregon State University OL 16-01 Section A: Theory, Thermo & Facility Operating Characteristics Page 23 A.01 Answer: a, 4 b,1 c,2 d,3 REF: Shultis and Faw, Fundamentals of Nuclear Science and Engineering, Section 5.4, pg.93-101 Beta decay: A Z P [ A Z +1 D ]+

+ 0 1 e + ve Gamma decay: A Z P * = ZAP +

Positron decay: Z A

P [ A Z 1 D ]+

0

+1 e + ve A1

P+

A 1 Neutron decay: Z P= Z 0 n Where A=Mass#, Z=Atomic#, P=parent atom, D=daughter atom A.02 Answer: c REF: Burns, Figure 8.1, pg. 8-6 OSU TRIGA Reactor Operator Training I, Decay and Build-up of Nuclides OSU TRIGA Reactor Training Manual, Volume 3, pg. 19 A.03 Answer: d REF: OSU TRIGA Reactor Training Manual, Volume 3, pg. 22 OSU TRIGA Reactor Operator Training I, Steady Reactor Physics A.04 Answer: a REF: CR1 / CR2 = (1 - Keff2) / (1 - Keff1) 100 / 60 = (1 - Keff2) / (1 - 0.92)

Therefore Keff2 = 0.867

= (Keff2 - Keff1) / (Keff2

Keff1)

= (0.867 - 0.92) / (0.867

0.92)

= - 0.0664 A.05 Answer: c REF: Lamarsh, 3rd ed., Figure 8.10, pg. 442 and section 8.5, pg. 446 OSU TRIGA Reactor Operator Training I, Steady State Fundamental Thermal Hydraulics, Steady State Analysis

Oregon State University OL 16-01 Section A: Theory, Thermo & Facility Operating Characteristics Page 24 A.06 Answer: a, 3 b,2 c,1 REF: OSU TRIGA Reactor Operator Training I, Neutron Flux and Multiplication Factor OSU TRIGA Reactor Training Manual, Volume 3, pg. 12 Lamarsh, 3rd ed., Section 7.2, pg. 337 When k = 1, = 0 and reactor is critical When k < 1, < 0 and reactor is subcritical When k > 1, > 0 and reactor is supercritical A.07 Answer: d REF: The reproduction factor (also called the fuel utilization factor) is not affected by the moderator since it is purely a function of the nuclear characteristics of 235U and other fissile nucleus.

OSU TRIGA Reactor Training Manual, Volume 3, pg. 11 DOE Fundamentals Handbook, NP-03, pg. 6-8 A.08 Answer: d REF: Burns, section 3.3.5, pg. 3-23 OSU TRIGA Reactor Training Manual, Volume 3, pg. 24 A.09 Answer: a REF: Burns, Section 3.2.4, pg. 3-12 OSU TRIGA Reactor Training Manual, Volume 3, pg. 24 A.10 Answer: c REF: Burns, Section 2.5.2, pg. 2-43 OSU TRIGA Reactor Training Manual, Volume 3, pg. 25 A.11 Answer: d REF: DOE Fundamentals Handbook, NP-04, pg. 6-8 OSU TRIGA Reactor Operator Training I, Neutron Flux and Multiplication Factor OSU TRIGA Reactor Training Manual, Volume 3, pg. 33-35 A.12 Answer: c REF: Burns, Section 7.3, pg. 7-5 to 7-7 OSU TRIGA Reactor Training Manual, Volume 3, Figure 3.6, pg. 17-7

Oregon State University OL 16-01 Section A: Theory, Thermo & Facility Operating Characteristics Page 25 A.13 Answer: c REF: Lamarsh, 3rd ed., pg. 345 OSU TRIGA Reactor Training Manual, Volume 3, pg. 29 A.14 Answer: a

= $ eff

= 1.1 x 0.0065 = 0.00715 (1 )P0 0.0065(1 + 0.00715) x 1 P1 = = = 0.4796 MW 0.0065 + 0.00715 t 5x60 80 P (t ) = P1e T

= 0.4796e P (5 min) = 0.0113MW REF: Lamarsh, 3rd ed., Example 7.6, pg. 345-346 OSU TRIGA Reactor Training Manual, Volume 3, pg. 30 A.15 Answer: a REF: OSU TRIGA Reactor Training Manual, Volume 3, pg. 15 A.16 Answer: c REF: Burn, Section 4.2, Figure 4-1, pg. 4-2 0.5 % K/K = 0.005 K/K = , > 0

= (keff -1) / keff, then keff = 1.005 When k > 1, > 0 and reactor is supercritical A.17 Answer: c REF: Lamarsh, 3rd ed., pg. 377, 387 OSU TRIGA Reactor Training Manual, Volume 3, pg. 19 A.18 Answer: d REF: OSU TRIGA Reactor Training Manual, Volume 3, pg. 9 Lamarsh, 3rd ed., Section 6.5, pg. 287

Oregon State University OL 16-01 Section A: Theory, Thermo & Facility Operating Characteristics Page 26 A.19 Answer: a REF: DOE Handbook part 2, module 4, pg. 21 OSU TRIGA Reactor Training Manual, Volume 2, pg. 22 OSU TRIGA Reactor Training Manual, Volume 3, pg. 26 A.20 Answer: b REF: Burns, Table 3.2, pg. 3-5 Lamarsh, 3rd ed., Table 3.6, pg. 88

Oregon State University OL 16-01 Section B Normal, Emergency and Radiological Control Procedures Page 27 B.01 Answer: a REF: OSU TRIGA Reactor Operator Training I & II, Radiological Protection OSU TRIGA Reactor Training Manual, Volume 4, pg. 14 10 CFR 20.1003 B.02 Answer: b REF: OSU TRIGA Reactor Operator Training I & II, Radiological Protection OSU TRIGA Reactor Training Manual, Volume 4, Table 4.4, pg. 17 10 CFR 20.1201(a)(1)(i)

B.03 Answer: b REF: OSU TRIGA Reactor Operator Training I & II, Radiological Protection OSU TRIGA Reactor Training Manual, Volume 4, Table 4.6, pg. 19 B.04 Answer: b REF: OSU TRIGA Reactor Operator Training I & II, Radiological Protection OSU TRIGA Reactor Training Manual, Volume 4, pg. 20 B.05 Answer: c REF: OSU TRIGA Reactor Training Manual, Volume 4, pg. 12 SAR 5.6, pg. 5 SAR 11.1.1.2.1, pg. 9 Nitrogen-16 is produced by (n,p) reaction of Oxygen-16 (due to neutron interactions with oxygen-16 in the primary coolant and neutron-activated dust particulates). The hazard is due to high energy gamma (6.13 MeV and 7.11 MeV). N-16 is produced within the coolant passing through the core of the reactor. To decrease the N-16 gas that becomes airborne, water above the core may be over stirred using diffuser pumps. This increases the transport time of the short-lived (t1/2 = 7.13 sec) N-16 from the core to the surface of the pool and allows additional decay time.

B.06 Answer: c REF: OSU TRIGA Reactor Training Manual, Volume 4, pg. 17 TLDs and finger rings all provide information on accumulated dose. These have to be processed. They do not tell you the dose rate. Pocket ion chambers provide immediate visual information on your accumulated dose, but not dose rates. Electronic dosimeters give real time reading of the dose received by the wearer but not the gamma dose.

Oregon State University OL 16-01 Section B Normal, Emergency and Radiological Control Procedures Page 28 B.07 Answer: c REF: 10 CFR 55.53 (g)

OSU TRIGA Reactor Operator Training II, Operators Licenses B.08 Answer: b

Reference:

TS 2.1 and 2.2 B.09 Answer: b REF: 10 CFR 20.1004 OSU TRIGA Reactor Operator Training I & II, Radiological Protection OSU TRIGA Reactor Training Manual, Volume 4, pg. 8 B.10 Answer: c REF: 10 CFR 55.21 OSU TRIGA Reactor Operator Training II, Operators Licenses B.11 Answer: b REF: ERP 7.4.1, pg. 7-13 B.12 Answer: c REF: ERP 3.3.2, pg. 3-6 B.13 Answer: a REF: ERP 4.1, pg. 4-1 B.14 Answer: a REF: ERP 7.1.2 6) a), pg. 7-3 OSU TRIGA Reactor Training Manual, Volume 4, pg. 25 B.15 Answer: b REF: ERP 2.0, pg. 2-1 B.16 Answer: d REF: OSTROP 1, II.A.6, pg. 4 SAR 7.4.1, pg. 11

Oregon State University OL 16-01 Section B Normal, Emergency and Radiological Control Procedures Page 29 B.17 Answer: c REF: OSTROP 6, IV.C.1.c., pg. 11 B.18 Answer: a REF: OSTROP 7, I.D., pg. 5 TS 3.3.b and 3.3 Basis, pg. 16 B.19 Answer: a REF: OSTROP 2, V.D., pg. 23 B.20 Answer: b REF: OSTROP 10, II.B.4.a.(1)(b), pg. 12

Oregon State University OL 16-01 Section C Facility and Radiation Monitoring Systems Page 30 C.01 Answer: a REF: OSU TRIGA Reactor Operator Training I TS 2.2, pg. 8 C.02 Answer: a REF: TS 5.3.3, pg. 31 C.03 Answer: a REF: TS 3.2.3, Table 2, pg. 14 C.04 Answer: c REF: SAR 9.1.1, pg. 1 C.05 Answer: b REF: TS 3.2.3 Table 3, pg. 14 C.06 Answer: a,2 b,4 c,3 d,1 REF: OSU TRIGA Reactor Operator Training II, Instrumentation & Control System OSU TRIGA Reactor Training Manual, Volume 2, Table 2.1, pg. 12 C.07 Answer: d REF: OSU TRIGA Reactor Training Manual, Volume 2, pg. 21 C.08 Answer: d REF: OSU TRIGA Reactor Training Manual, Volume 2, pg. 22 C.09 Answer: c REF: ERP 8.2.5 1) a), pg. 8-3 OSU TRIGA Reactor Training Manual, Volume 2, Figure 2.17 & 2.19 SAR 7.2.3.1, pg. 2 C.10 Answer: d REF: TS 2.1 Basis, pg. 6 C.11 Answer: d

Oregon State University OL 16-01 Section C Facility and Radiation Monitoring Systems Page 31 REF: SAR 5.2, pg. 1 C.12 Answer: b REF: SAR 7.3.1, pg. 6 C.13 Answer: d REF: SAR 10.2.1, pg. 1-2 C.14 Answer: d REF: TS 3.2.3 Table 2, pg. 14 SAR 7.4.1, pg. 11 C.15 Answer: d REF: TS 3.5.b, pg. 17 C.16 Answer: c REF: TS 3.1.3 Basis, pg. 10 C.17 Answer: a REF: TS 3.2.2 Footnote (1), pg. 12 TS 3.2.3 Footnote (1), pg. 14 C.18 Answer: d REF: SAR 3.5.1, pg. 4 SAR 4.2.2, pg. 24 OSU TRIGA Reactor Training Manual, Volume 1, pg. 28, 29, 37 C.19 Answer: a REF: TS 4.5, pg. 25 TS 5.1 Basis, pg. 27 C.20 Answer: b REF: TS 3.3.a, pg. 16