Text

Examination Report Letter No. 50-243/OL-25-01, Oregon State University
	ML25132A002
Person / Time
Site:	Oregon State University
Issue date:	07/02/2025
From:	Michael Brown; NRC/NRR/DANU/UNPO
To:	Reese S; Oregon State University
References
	50-243/OL-25-01 OL-25-01
	Download: ML25132A002 (36)
	v • d • e

Dr. Steven R. Reese, Director Oregon State University 100 Radiation Center Corvallis, OR 97331-5903

SUBJECT:

EXAMINATION REPORT NO. 50-243/OL-25-01, OREGON STATE UNIVERSITY

Dear Dr. Reese:

During the week of June 9, 2025, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Oregon State University research 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 those members of your staff identified in the enclosed report at the conclusion of the examination.

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

Sincerely, Tony Brown, Chief Non-Power Production and Utilization Facility Oversight Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation Docket No. 50-243

Enclosures:

1. Examination Report No. 50-243/OL-25-01

2. Written examination cc: w/enclosures to GovDelivery Subscribers July 2, 2025 Signed by Brown, Tony on 07/02/25

ML25132A002 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME MDeSouza NJones TBrown DATE 7/2/2025 7/2/2025 7/2/2025 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:

50-243/25-01 FACILITY DOCKET NO.:

50-243 FACILITY LICENSE NO.:

R-106 FACILITY:

Oregon State University EXAMINATION DATES:

Week of June 9, 2025 SUBMITTED BY:

SUMMARY

During the week of June 9, 2025, the NRC administered operator licensing examinations to seven Reactor Operator (RO) candidates. All candidates passed all applicable portions of the written examination and operating test.

REPORT DETAILS 1.

Examiner:

Michele C. DeSouza, Chief Examiner, NRC 2.

Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 7/0 0/0 7/0 Operating Tests 7/0 0/0 7/0 Overall 7/0 0/0 7/0 3.

Exit Meeting:

Dr. Steven Reese, Radiation Center Director, Oregon State University Zane Tucker, Assistant Director/Reactor Administrator, Oregon State University Celia Oney, Reactor Supervisor, Oregon State University Anthony Coke, Senior Reactor Operator, Oregon State University Michele C. DeSouza, Chief Examiner, NRC Prior to administration of the written examination, based on facility comments, adjustments were accepted. Comments provided corrections and additional clarity to questions/answers and identified where changes were appropriate based on current facility conditions.

Upon completion of all operator licensing examinations, the NRC examiner met with facility staff representatives to discuss the results. The candidates were well prepared for the examination and tests. At the conclusion of the meeting, the NRC examiner thanked the facility for their support in the administration of the examination.

Michele C. DeSouza 6/27/2025 Michele C. DeSouza, Chief Examiner Date Oregon State University Operator Licensing Examination Week of June 9, 2025 U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:

Oregon State University REACTOR TYPE:

TRIGA DATE ADMINISTERED:

June 11, 2025 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% or greater in each category and a 70% or greater overall are required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

CATEGORY VALUE

% OF TOTAL CANDIDATE'S SCORE

% OF CATEGORY VALUE CATEGORY 20.00 33.0 A. REACTOR THEORY, THERMODYNAMICS, AND FACILITY OPERATING CHARACTERISTICS 20.00 33.0 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.0 C. FACILITY AND RADIATION MONITORING SYSTEMS 60.00 TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

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

1.

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

2.

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

3.

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

4.

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

5.

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

6.

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

7.

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

8.

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

9.

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

10.

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

11.

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

12.

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

Category A: Reactor Theory, Thermodynamics, & Facility Operating Characteristics A N S W E R S H E E T Multiple Choice (Circle 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 *****)

Category B: Normal/Emergency Operating Procedures and Radiological Controls A N S W E R S H E E T Multiple Choice (Circle 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 CATEGORY B *****)

Category C: Facility and Radiation Monitoring Systems A N S W E R S H E E T Multiple Choice (Circle your choice)

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

C01 a b c d ___

C02 a b c d ___

C03 a b c d ___

C04 a b c d ___

C05 a b c d ___

C06 a b c d ___

C07 a b c d ___

C08 a b c d ___

C09 a b c d ___

C10 a b c d ___

C11 a b c d ___

C12 a b c d ___

C13 a b c d ___

C14 a b c d ___

C15 a b c d ___

C16 a b c d ___

C17 a b c d ___

C18 a b c d ___

C19 a b c d ___

C20 a b c d ___

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

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

EQUATION SHEET

=

+

DR - Rem, Ci - curies, E - Mev, R - feet 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lb 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 1 BTU = 778 ft-lb

°F = 9/5 °C + 32 1 gal (H2O) 8 lb

°C = 5/9 (°F - 32) cP = 1.0 BTU/hr/lb/°F cp = 1 cal/sec/gm/°C

2 2

max

P 1

sec 1.0

eff

T UA H

m T

c m

Q P

sec 10 1

4

2 1

1 1

2 1

eff eff K

CR K

CR

eff SUR 06 26

te P

P 0

eff K

S S

SCR

1

2 2

1 1

CR CR

0 1

P P

1 2

1 1

CR CR K

M eff

)

(

0 10 t

SUR P

P 2

1 1

1 eff eff K

K M

eff eff K

K SDM

1 2

1 1

2 eff eff eff eff K

K K

K

693

.0 2

1 T

eff eff K

K 1

2 2

1 1

d DR d

DR

t e

DR DR

0

1 2

2 2

Peak Peak

2 6

R n

E Ci DR

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

[1.00 point]

Following a scram during full power operation, what is the effect of delayed neutrons on the neutron flux decay?

a. Decreases the mean neutron lifetime

b. Adds negative reactivity creating a greater shutdown margin c.

Limits the final rate at which power decreases to a -80 second period.

d. Adds positive reactivity due to the fuel temperature decrease from the scram QUESTION A.02

[1.00 point]

Which ONE of the following is the largest amount of energy released per fission event?

a. Gamma radiation

b. Alpha and Beta radiation c.

Kinetic energy of fission fragments

d. Kinetic energy of prompt and delayed neutrons QUESTION A.03

[1.00 point]

Which ONE of the following is the primary mechanism for transferring heat through the cladding of a fuel rod?

a. Radiation b.

Convection c.

Conduction d.

Mass Transfer

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.04

[1.00 point]

Which ONE of the following is defined as the balance between production of neutrons and their absorption in the core for which core leakage can be neglected?

a.

Utilization Factor b.

Reproduction Factor c.

Infinite Multiplication Factor d.

Effective Multiplication Factor QUESTION A.05

[1.00 point]

Which ONE of the following elements has the LARGEST Mean Free Path?

a.

Boron ( = 105.2 cm-1) b.

Tungsten ( = 1.21 cm-1) c.

Plutonium ( = 31.1 cm-1) d.

Titanium ( = 0.323 cm-1)

QUESTION A.06

[1.00 point]

Which ONE of the following will result, if the reactor is operating at 10W and the reactor operator inserts an experiment of $0.25 reactivity worth into the core?

Given:

T: reactor period, *: Prompt neutron lifetime; : reactivity insertion; : beta fraction;

-eff: delayed neutron precursor constant a.

Sudden drop in delayed neutrons b.

Resultant period is a function of the prompt neutron lifetime ( = */)

c.

Number of prompt neutrons is twice as much as a number of delayed neutrons d.

Resultant period is a function of the delayed neutron precursors =

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.07

[1.00 point]

Which ONE of the following is the Keff ? Given the probability of fast non-leakage is 0.69, the probability of thermal non-leakage is 0.86, and Kinf is 1.77.

a.

1.05 b.

1.13 c.

1.19 d.

1.23 QUESTION A.08

[1.00 point]

Which ONE of the following BEST defines reactivity?

a.

The fractional change in neutron population per generation.

b.

The rate of change of the reactor power in neutrons per second.

c.

The number of neutrons by which neutron population changes per generation.

d.

The change in the number of neutrons per second that causes a fission event.

QUESTION A.09

[1.00 point]

After an operating reactor has been shut down and cooled down for several days, which ONE of the following is the major source of heat generation?

a.

Resonance capture b.

Fission fragment decay c.

Delayed neutron reactions d.

Corrosion product activation

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.10

[1.00 point]

Which ONE of the following statements BEST describes the behavior of the microscopic cross-section of fission (f) for U-235?

a.

It remains constant for all neutron energies.

b.

It increases linearly with increasing neutron energy.

c.

The values are highest for the thermal neutron energy range.

d.

It has resonance peaks which expand as fuel temperature increases.

QUESTION A.11

[1.00 point]

Which ONE of the following is MOST correct regarding the properties of neutron moderators?

a.

Moderators must have high scattering cross-sections and low absorption cross-sections.

b.

Moderators must have low scattering cross-sections and high absorption cross-sections.

c.

Moderators must have low scattering cross-sections and low absorption cross-sections.

d.

Moderators must have high scattering cross-sections and high absorption cross-sections.

QUESTION A.12

[1.00 point]

What is the reactor period if = 0.007 and = 0.005?

a.

4.02 seconds b.

6.04 seconds c.

11.5 seconds d.

22.7 seconds

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.13

[1.00 point]

Which ONE of the following statements is MOST accurate regarding subcritical multiplication?

a.

As the multiplication factor gets closer to one, the time required for neutron population to stabilize increases.

b.

As the reactor approaches criticality, the startup source must be removed to prevent an inadvertent prompt jump.

c.

The neutron source strength has no determination on the ultimate neutron population for its associated multiplication factor.

d.

Once the startup source has provided the initial neutron population for the first generation it is no longer needed to produce neutrons.

QUESTION A.14

[1.00 point]

________ neutrons contribute more to reactor stability than ________ neutrons because they increase the average neutron generation time and are born at a lower kinetic energy.

a.

Prompt, fast b.

Fast, prompt c.

Delayed, prompt d.

Fast, delayed QUESTION A.15

[1.00 point]

Which ONE of the following changes does NOT require movement of control rods in order to maintain constant reactor power?

a.

Xenon-135 buildup b.

Nitrogen-16 formation c.

Uranium-235 burnup d.

Decrease pool water temperature

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.16

[1.00 point]

Which ONE of the following shows the reactor is subcritical?

a.

= 1.0 b.

K= 1.0, =

c.

Keff < 1.0 or < 0.0

d. Keff > 1.0 or > 0.0 QUESTION A.17

[1.00 point]

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

a.

Fuel depletion b.

Burnout of Xenon during reactor startup c.

Insertion of a negative reactivity worth experiment d.

Higher moderator temperature, assuming a negative temperature coefficient QUESTION A.18

[1.00 point]

Which ONE of the following coefficients of reactivity is credited with immediately adding negative reactivity in response to a large prompt insertion of reactivity?

a.

Void Coefficient b.

Pressure Coefficient c.

Fuel Temperature Coefficient d.

Moderator Temperature Coefficient QUESTION A.19

[1.00 point]

Which ONE of the following statements BEST describes the purpose of a burnable poison?

a.

The purpose of a burnable poison is to ensure sufficient negative reactivity for future potential decommissioning.

b.

The purpose of a burnable poison is to ensure there is sufficient negative reactivity to provide an adequate shutdown margin throughout the life of the reactor.

c.

Burnable poisons are only generated through the operation of the reactor and thus serve no real purpose but requires excess reactivity to account for their formation.

d.

The purpose of a burnable poison is to account for the initial excess reactivity of a fresh core and generally burns up at the same rate as the fuel to maintain a constant excess reactivity.

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.20

[1.00 point]

If reactor power is at 50 W and $0.25 worth of reactivity is added resulting in a 20 second period, what will reactor power be after 3 minutes?

a.

216 kW b.

391 kW c.

405 kW d.

512 kW

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

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

[1.00 point]

In accordance with OSTROP 17, Reactor Room Ventilation System Procedure, which ONE of the following does NOT indicate that the ventilation system is operating normally?

a.

Rabbit system permissive light flashing RED b.

Ventilation Dampers Closed annunciator is CLEAR c.

Ventilation System Fans Off annunciator is CLEAR d.

Differential pressure gauge reading indicates -0.1 in H2O QUESTION B.02

[1.00 point]

In accordance with OSTR, Tab M, Classification, which ONE of the following statements is NOT classified as a Class I, Notification of Unusual Event?

a.

An explosion in the Radiation Center Complex.

b.

A tornado in the Corvallis area.

c.

A hostile crowd assembling outside the reactor building.

d.

100 mrem thyroid dose.

QUESTION B.03

[1.00 point]

In accordance with the OSTR, Emergency Response Plan, which ONE of the following is NOT designated as an Emergency Support Center location?

a.

Control Room b.

Room A100 c.

Reactor Supervisors office d.

Room D302 QUESTION B.04

[1.00 point]

In accordance with 10 CFR 20, which ONE of the following is the Annual Dose Limit to an Occupational Workers eyes?

a.

10 Rem b.

15 Rem c.

100 mRem d.

500 mRem

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.05

[1.00 point]

Which ONE of the following federal regulations is used to determine whether a change in the reactor water tank water level probe is within compliance?

a.

10 CFR 20.1301 b.

10 CFR 50.59 c.

10 CFR 55.55 d.

10 CFR 74.12 QUESTION B.06

[1.00 point]

What is the exposure rate at a distance of 2 meters if the initial exposure rate is 100 mR/hr at 4 meters?

a.

100 mR/hr b.

200 mR/hr c.

400 mR/hr d.

500 mR/hr QUESTION B.07

[1.00 point]

In accordance with the Oregon State University Technical Specifications, which ONE of the following is NOT a required measuring channel in Steady State Mode?

a.

Safety Power Level b.

Percent Power Level c.

Linear Power Level d.

Nvt-Circuit QUESTION B.08

[1.00 point]

Which ONE of the following scenarios would result in an occupational worker violating their 10 CFR 20 annual dose limits?

a.

Handling a sample releasing a beta radiation dose of 2 rem/hr for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

b.

Accidentally ingesting contaminated water, that results in a dose to the liver of 55 rem.

c.

Accidentally inhaling some radioactive powder that results in a lung uptake of 15 rem.

d.

Handling a fueled experiment that emits a beta contact radiation dose of 50 rem/hr for 3 minutes.

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.09

[1.00 point]

Which ONE of the following experimental facilities bombards the sample with epithermal neutrons?

a.

In-Core Irradiation Tube (ICIT) b.

Cadmium-Lined In-Core Irradiation Tube (CLICIT) c.

Thermal Column d.

Neutron Radiography Facility QUESTION B.10

[1.00 point]

In accordance with Oregon State University, Emergency Response Plan, which ONE of the following individuals is NOT in the line of succession for Emergency Coordinator?

a.

Reactor Administrator b.

Reactor Supervisor c.

Senior Health Physicist d.

Senior Reactor Operator QUESTION B.11

[1.00 point]

Which ONE of the following is the strongest source of radiation?

a.

Pool water b.

Irradiated fuel elements in air c.

Pneumatic transfer system d.

Nitrogen-16 diffusor QUESTION B.12

[1.00 point]

In accordance with OSTROP 05, Procedures for Maintaining Reactor Operational Records,Section V, Requalification, which ONE of the following will NOT count as a reactivity manipulation?

a.

A manual scram due to an emergency condition.

b.

Taking the reactor from shutdown to critical.

c.

Pulsing the reactor.

d.

A high-power scram on the percent power channel.

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.13

[1.00 point]

What is the approximate half-life of the isotope contained in a sample with an initial count rate of 840 counts per minute and after 180 minutes 270 counts per minute?

a.

60 minutes b.

110 minutes c.

210 minutes d.

310 minutes QUESTION B.14

[1.00 point]

If a sample was removed from the rotary specimen rack emitting a dose rate of 360 mrem/hr at 10cm, how long would it need to decay before storing it would NO LONGER require posting it as a radiation area? Assuming the half-life of the specimen is 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

a.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months b.

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

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

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months QUESTION B.15

[1.00 point]

In accordance with Oregon State University Technical Specifications, which ONE of the following is NOT an annual requirement?

a.

Power measuring channel calibration b.

Measuring core excess reactivity c.

Transient rod drive cylinder inspection, cleaning, and lubrication d.

Control rod worth calibration QUESTION B.16

[1.00 point]

In accordance with Oregon State University Technical Specifications, which ONE of the following CANNOT be deferred during reactor shutdown?

a.

Scram time b.

Channel check of reactor tank water temperature system c.

Channel check of the reactor tank water level monitor d.

Control rods and drives visual inspection for damage or deterioration

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B. 17

[1.00 point]

If an experiment was removed from the core emitting a dose rate of 100 rem/hr on contact from beta radiation, how long would someone have to hold it in order to violate their 10 CFR 20 limits?

a.

3 minutes b.

15 minutes c.

30 minutes d.

60 minutes QUESTION B.18

[1.00 point]

Which ONE of the following is the daily method for calculating Shutdown Margin?

a.

Raising the transient, safety, and shim rods to 55%, establish regulating rod height to achieve a power of 100W, and subtracting the core excess from the shutdown margin calculation value.

b.

Raising the transient, safety, and shim rods to 55%, establish regulating rod height to achieve a power of 100W, and adding the core excess to the shutdown margin calculation value.

c.

Raising the transient, safety, and shim rods to 45%, establish regulating rod height to achieve a power of 100W, and subtracting the core excess from the shutdown margin calculation value.

d.

Raising the transient, safety, and shim rods to 45%, establish regulating rod height to achieve a power of 100W, and adding the core excess to the shutdown margin calculation value.

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

[1.00 point]

In accordance with OSTROP 08, Reactor Power Calibration Procedures, no one should be on the reactor top because of which ONE of the following?

a.

Argon-41 may build up due to securing the ventilation for the procedure.

b.

More Nitrogen-16 will reach the surface because the diffuser is off during the procedure.

c.

The nuclear instrumentation should not be moved or disturbed as it will create an adverse negative result.

d.

Accumulation of Xenon-135 that becomes present from the temperature increases above 40oC.

QUESTION B.20

[1.00 point]

Which ONE of the following experiments is NOT permitted?

a.

Double encapsulated corrosive materials b.

Sum of all experiments total reactivity worth $1.50 c.

Single unsecured experiment with a reactivity worth of $0.55 d.

Explosive materials totaling 3 mg encapsulated in a container designed such that the detonation pressure is less than half the design pressure of the container

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

Category C: Facility and Radiation Monitoring Systems QUESTION C.01

[1.00 point]

Which ONE of the following is the primary isotope of concern in the pneumatic transfer system?

a.

H2 (H1 (n, ) H2) b.

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

Kr80 (Kr79 (n, ) Kr80) d.

Ar41 (Ar40 (n, ) Ar41)

QUESTION C.02

[1.00 point]

In accordance with OSTROP 01, Annunciator Response Procedures, which ONE of the following does NOT require an immediate SCRAM, if the intended function does not occur?

a.

Safety Power b.

High Voltage c.

Transient Rod Low Air Pressure d.

Stack Monitor High Activity QUESTION C.03

[1.00 point]

In accordance with OSTROP 06, Administrative and Personnel Procedures, which one of the following are the three documents required to be in the Reactor Control Room and need to be guaranteed to be accurate and up to date versions?

a.

OSTROP 1, 4, and Requalification Plan b.

OSTR Emergency Response Plan, SAR, and OSTROP 1 c.

Emergency Response Plan, Emergency Implementing Procedures, and Security Plan d.

OSTR Operating License, Technical Specifications, and Emergency Response Plan

Category C: Facility and Radiation Monitoring Systems QUESTION C.04

[1.00 point]

Which ONE of the following reactor facilities has the highest potential radiation level when the reactor is operating at 1MW?

a.

Reactor Water Pipes b.

Demineralizer System Filter c.

Beam Port with Shielding installed d.

Radiography Facility with Shutter Open QUESTION C.05

[1.00 point]

Which ONE of the following conditions would result in a Safety Power Scram?

a.

$1.25 Pulse b.

100% Safety Power Channel indication c.

10 second period indication d.

Prompt reactivity insertion of $0.50 while at 100 watts QUESTION C.06

[1.00 point]

Which ONE of the following conditions is the function of the fuel element cladding material?

a.

Aluminum cladding given it easily forms around the fuel materials.

b.

Aluminum cladding because it chemically bonds with the Uranium fuel materials.

c.

Stainless steel cladding given its strength as a function of temperature.

d.

Stainless steel cladding because it easily corrodes if it comes in contact directly with water.

Category C: Facility and Radiation Monitoring Systems QUESTION C.07

[1.00 point]

Which ONE of the following BEST describes how an Uncompensated Ion Chamber (UIC) operates?

a.

The UIC has only one chamber coated with U-235 for fission reaction.

b.

The UIC has only one chamber coated with Boron-10 for a (n,a) reaction.

c.

The UIC has two chambers, both detect gammas but only one is coated with Boron-10 for a (n,a) reaction.

d.

The UIC has two chambers, one coated with U-235 for a fission reaction and the other coated with Boron-10 for (n,a) reaction.

QUESTION C.08

[1.00 point]

The pulse reactivity insertion is limited to ensure the fuel temperature will not exceed a.

830oC b.

900oC c.

1000oC d.

1500oC QUESTION C.09

[1.00 point]

Which ONE of the following was NOT part of the three major areas used to define the reactor design bases?

a.

Reactor power b.

Fuel temperature c.

Prompt temperature coefficient d.

Reactor core shielding material

Category C: Facility and Radiation Monitoring Systems QUESTION C.10

[1.00 point]

Which ONE of the following detectors is used to detect the release of Nitrogen-16 to the environment?

a.

Area Radiation Monitor b.

Stack Gas Continuous Air Monitor c.

Reactor Top Continuous Air Monitor d.

None of the above, Nitrogen-16 has too short a half-life to require environmental monitoring QUESTION C.11

[1.00 point]

Which ONE of the following experimental facilities can be used for the synchronous irradiation of multiple samples and production of radionuclides?

a.

Rotating Rack b.

Central Thimble c.

Thermalizing Column d.

Pneumatic Transfer System QUESTION C.12

[1.00 point]

Which ONE of the following is the maximum time allowed for the slowest scrammable rod to reach the fully inserted position?

a.

0.6 seconds b.

0.8 seconds c.

1.2 seconds d.

2.0 seconds QUESTION C.13

[1.00 point]

Which ONE of the following is NOT a predominant radionuclide in the OSTR primary coolant?

a.

Tritium b.

Nitrogen-16 c.

Sodium-24 d.

Xenon-133

Category C: Facility and Radiation Monitoring Systems QUESTION C.14

[1.00 point]

Which ONE of the following reactor power channels provides indication over the entire range of operating and shutdown levels?

a.

Percent Power Channel b.

Safety Channel c.

Wide Range Log d.

Nvt Circuit QUESTION C.15

[1.00 point]

How long can the ventilation system be non-operational while conducting repairs, maintenance, or testing?

a.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months b.

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

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

Operation not permitted at all without ventilation operating QUESTION C.16

[1.0 point]

In accordance with Oregon State University Technical Specifications, during periods of reactor operation, how frequently must a sample of reactor coolant be measured for conductivity?

a.

Daily b.

Weekly c.

Monthly d.

Quarterly QUESTION C.17

[1.00 point]

In accordance with the Oregon State University SAR, which ONE of the following statements BEST describes the purpose of the dashpots on the control rods?

a.

Provides the constant rod position indications.

b.

Limits the applied force on the control rods to slow the withdrawal within limits c.

Prevents the simultaneous withdrawal of more than two rods at the same time.

d.

Slows the rate of insertion near the bottom to limit deceleration forces.

Category C: Facility and Radiation Monitoring Systems QUESTION C.18

[1.00 point]

In accordance with OSTROP 22, Emergency Power System, which ONE of the following is NOT a step in the event of a Commercial Power Failure?

a.

Observe that the UPS is supplying power to System A.

b.

Check to be sure the stack monitor is secured to prevent the release of any radioactive materials.

c.

Ensure generator starts after about 10 seconds.

d.

Manually scram the reactor.

QUESTION C.19

[1.00 point]

In accordance with Oregon State University Technical Specifications, which ONE of the following is the fuel storage limit on k-effective?

a.

0.6 b.

0.7 c.

0.8 d.

0.9 QUESTION C.20

[1.00 point]

In accordance with the Oregon State University Technical Specifications, water conductivity must be continuously maintained at __________ to ensure acceptably __________.

a.

5 µmhos/cm, high reactivity b.

5 µmhos/cm, low reactivity c.

5 µmhos/cm, low corrosion d.

5 µmhos/cm, high corrosion

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

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

a

Reference:

=

+

= 1 104 0.005 + 0.007 0.005 0.1 0.005 T = 4.02 A.13 Answer:

a

Reference:

Burns, Introduction to Nuclear Reactor Operators, Volume 3 p. 5-7 A.14 Answer:

c

Reference:

Burns, Introduction to Nuclear Reactor Operators, Section 3.2.4, p.3-12 and Section 3.4.4,

OSTROP 11, Fuel Element Handling Procedures,Section I.A.

B.12 Answer:

d

Reference:

OSTROP 05, Procedures for Maintaining Reactor Operational Records,Section V, Requalification

Category B: Normal/Emergency Operating Procedures and Radiological Controls B.13 Answer:

b

Reference:

A = A0e-t 270 = 840e-180, 180 = -ln (0.321), = 0.00631 min-1 t1/2 = 0.693 /, = 0.693 / 0.00631 min-1 = 109.8 minutes = 110 minutes B.14 Answer:

d

Reference:

12 1 = 22 2

360*100 = 2 900 2 = 40

= 0 0 40

5

=

ln (2)

= 2 5 = 40 ln(2) 2

ln 5

40 = ln(2) 2

ln(2) = ln 5

40 2

=

2 ln ( 5 40 )

ln (2)

= 6.0 B.15 Answer:

c

Reference:

Oregon State University Technical Specifications 4.1 and 4.2 B.16 Answer:

c

Reference:

Oregon State University Technical Specifications 4.0, 4.1, and 4.2 B.17 Answer:

c

Reference:

10 CFR 20 limits on extremity dose = 50 rem per year

=

50 100

= 0.5

= 30 B.18 Answer:

a

Reference:

OSTROP 04, Reactor Operation Procedures,Section II and OSTROP 5, Procedures for Maintaining Reactor Operational Records, Figure 1 B.19 Answer:

b

Reference:

OSTROP 08, Reactor Power Calibration Procedures,Section IV

Category B: Normal/Emergency Operating Procedures and Radiological Controls B.20 Answer:

c

Reference:

Oregon State University Technical Specifications 3.8

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

Reference:

Oregon State University Technical Specifications 3.3 and OSTROP 07, Operating Procedures for Reactor Water Systems, Section C

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

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

ML25132A002

Text

SUBJECT:

Dear Dr. Reese:

Enclosures:

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