Text

Examination Report Letter No. 50-186/OL-25-01, University of Missouri - Columbia
	ML24330A037
Person / Time
Site:	University of Missouri-Columbia
Issue date:	01/30/2025
From:	Michael Brown; NRC/NRR/DANU/UNPO
To:	Sanford M; Univ of Missouri - Columbia
References
	50-186/OL-25-01 OL-25-01
	Download: ML24330A037 (1)
	v • d • e

Matthew Sanford, Executive Director University of Missouri-Columbia Research Reactor Center 1513 Research Park Drive Columbia, MO 65211

SUBJECT:

EXAMINATION REPORT NO. 50-168/OL-25-01, UNIVERSITY OF MISSOURI-COLUMBIA

Dear Matthew Sanford:

During the week of December 2, 2024, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your University of Missouri - Columbia 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. 50-168

Enclosures:

1. Examination Report No. 50-168/OL-25-01

2. Written examination cc: w/enclosures to GovDelivery Subscribers January 30, 2025 Signed by Brown, Tony on 01/30/25

ML24330A037 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME MDeSouza NJones TBrown DATE 1/30/2025 1/30/2025 1/30/2025 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:

50-186/OL-25-01 FACILITY DOCKET NO.:

50-186 FACILITY LICENSE NO.:

R-103 FACILITY:

University of Missouri-Columbia EXAMINATION DATES:

Week of December 2, 2024 SUBMITTED BY:

SUMMARY

During the week of December 2, 2024, the NRC administered operator licensing examinations to two Reactor Operator (RO) and two Senior Reactor Operator-Upgrade (SROU) candidates.

Three candidates passed all applicable portions of the examination. One SROU candidate failed the operating test.

REPORT DETAILS 1.

Examiner:

Michele C. DeSouza, Chief Examiner, NRC 2.

Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 2/0 N/A 2/0 Operating Tests 2/0 2/0*

4/0*

Overall 2/0 2/0 4/0

One candidate requested an administrative regrade of the operating exam, dated 1/10/2024, which resulted in an NRC determination that the candidate passed the operating test.

3.

Exit Meeting:

Deborah Farnsworth, MURR Senior Director-Reactor Operations Russ Gibson, MURR Interim Reactor Manager Dan Doenges, MURR Health Physics & Safety Manager Robert Hudson, MURR Assistant Reactor Manager-Training Shannon McCall, MURR Assistant Reactor Manager-Compliance Jake Nichols, MURR Radiation Safety Officer Amber Gaddy, MURR Senior Director-Regulatory Assurance Thomas Forland, MURR Assistant Director-Regulatory Affairs 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.

Michele DeSouza 1/27/2025 Michele C. DeSouza, Chief Examiner Date Upon completion of all operator licensing examinations, the NRC examiner met with facility staff representatives to discuss the results. At the conclusion of the meeting, the NRC examiner thanked the facility for their support in the administration of the examination.

University of Missouri-Columbia Operator Licensing Examination Week of December 4, 2024

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

University of Missouri -

Columbia REACTOR TYPE:

Tank DATE ADMINISTERED:

12/06/2024 CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the Answer sheet provided. Attach all Answer sheets to the examination. Point values are indicated in parentheses for each question. A 70% in each category is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 20.00 33.3 B.

NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.3 C.

FACILITY AND RADIATION MONITORING SYSTEMS 60.00 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

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

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

A01 a b c d ___

A02 a b c d ___

A03 a b c d ___

A04 a b c d ___

A05 a b c d ___

A06 a ________ b ________ c ________ d ________ (0.25 each)

A07 a b c d ___

A08 a b c d ___

A09 a b c d ___

A10 a b c d ___

A11 a b c d ___

A12 a b c d ___

A13 a b c d ___

A14 a b c d ___

A15 a b c d ___

A16 a b c d ___

A17 a b c d ___

A18 a b c d ___

A19 a b c d ___

A20 a b c d ___

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

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

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

B01 a b c d ___

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 ________ (0.25 each)

B07 a b c d ___

B08 a b c d ___

B09 a ________ b ________ c ________ d ________ (0.25 each)

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 or X your choice)

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

C01 a b c d ___

C02 a b c d ___

C03 a b c d ___

C04 a b c d ___

C05 a b c d ___

C06 a b c d ___

C07 a b c d ___

C08 a b c d ___

C09 a b c d ___

C10 a b c d ___

C11 a b c d ___

C12 a b c d ___

C13 a b c d ___

C14 a b c d ___

C15 a b c d ___

C16 a b c d ___

C17 a b c d ___

C18 a b c d ___

C19 a b c d ___

C20 a b c d ___

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

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

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

1.

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

2.

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

3.

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

4.

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

5.

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

6.

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

7.

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

8.

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

9.

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

10.

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

11.

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

12.

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

te P

P 0

eff K

S S

SCR

1

sec 10 1

4

eff SUR 06 26

2 1

1 1

2 1

eff eff K

CR K

CR

2 2

1 1

CR CR 2

1 1

1 eff eff K

K M

1 2

1 1

CR CR K

M eff

)

(

0 10 t

SUR P

P

0 1

P P

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

t e

DR DR

0

2 6

R n

E Ci DR 2

2 2

2 1

1 d

DR d

DR

1 2

2 2

Peak Peak

T UA H

m T

c m

Q P

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

[1.0 point]

If (1 - eff )*Keff = 1, the reactor is:

a.

Subcritical b.

Critical c.

Supercritical d.

Prompt Critical QUESTION A.02

[1.0 point]

Which ONE of the following is the stable reactor period which will result in a power rise from 50% to 100% power in 45 seconds?

a.

14 seconds b.

25 seconds c.

43 seconds d.

65 seconds QUESTION A.03

[1.0 point]

Which ONE of the following statements correctly describes the concentration of Xenon in the core following a scram from extended operation of 5 Megawatts? Xenon concentration

a. eventually decreases to zero in approximately 10 to 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months .

b. increases to maximum in approximately 7 to 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months due to I-135 decay.

c. increases to maximum in approximately 7 to 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months due to Cs-135 decay.

d. initially decreases due to the loss of Iodine production, then increases to maximum concentration.

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

[1.0 point]

Which ONE of the following statements best defines reactor excess reactivity?

a.

A measure of the additional fuel loaded to overcome fission product poisoning.

b.

A measure of remaining control blade worth when the reactor is exactly critical.

c.

The combined control blade negative reactivity worth required to keep the reactor shutdown.

d.

The maximum reactivity by which the reactor can be shutdown with one control blade fully withdrawn.

QUESTION A.05

[1.0 point]

How high will the reactor power get given the following: the lowest of the reactor high power scram set points is 120%, the scram delay time is 0.7 seconds, the reactor is operating at 100%

power prior to the scram, and the reactor period is positive 30 seconds?

a.

111%

b.

116%

c.

123%

d.

137%

QUESTION A.06

[1.0 point, 0.25 each]

Match the items in Column A with the isotopes in Column B.

The most important fission product poison is 135Xe. The process that shows how this isotope is formed and its decay is: (Answers used only once)

Column A Column B 1.

135 I 2.

135 Ba 3.

135 Te a

fission 11 0

1 +

b fission 6.7 0

1+ 135 fission 9.2 0

1+ c 2.36 d()

4.

135 Cs

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

[1.0 point]

Which ONE of the following conditions will require the control blade withdrawal to maintain constant power level following the change? Note: consider as applicable to MURR a.

Burnout of Xenon in the core b.

Pool water temperature increase c.

Insertion of an experiment containing cadmium d.

Adding of a fuel experiment such as Uranium-235 into the core QUESTION A.08

[1.0 point]

The following diagram is a trace of reactor period as a function of time. Between points C and D reactor power is:

a. constant

b. continually decreasing

c. continually increasing

d. increasing, then constant QUESTION A.09

[1.0 point]

Which ONE of the following is the multiplication factor if the source strength is 10,000 neutrons per second (N/sec) and it produces the stable neutron count rate of 50,000 N/sec?

a. 0.75

b. 0.80

c. 0.85

d. 0.90

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

[1.0 point]

Which ONE of the following conditions will increase the Negative Temperature Coefficient in a reactor?

a. Doppler broadening effect

b. Increases density of pool water

c. Sudden burn-up of Xenon in the fuel element

d. Increases density of Uranium-235 in the fuel element QUESTION A.11

[1.0 point]

Given the thermal neutron flux (Ø) is 1.0 x 1013 neutrons/cm2/second, and the macroscopic cross-section (f) for fission is 0.1 cm-1. Which ONE of the following is the fission rate?

a. 1.0 x 1012 fissions/cm3/second

b. 1.0 x 1014 fissions /cm3 /second

c. 1.0 x 1014 fissions /cm2 /second

d. 1.0 x 1012fissions /cm/second QUESTION A.12

[1.0 point]

A subcritical reactor, keff is increased from 0.921 to 0.975. Which ONE of the following is the amount of reactivity that was added to the core?

a. 3.64%k/k

b. 4.35%k/k

c. 5.53%k/k

d. 6.01%k/k

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

[1.0 point]

Which ONE of the following BEST describes a supercritical reactor?

a. Keff > 1 based on prompt neutrons alone

b. Keff < 1 based on delayed and prompt neutrons

c. Keff = 1 based on delayed neutrons alone

d. Keff > 1 based on prompt and delayed neutrons QUESTION A.14

[1.0 point]

What is the meaning of any point on a differential rod worth curve?

a. The negative reactivity added as the rod is inserted

b. The cumulative area under the differential curve starting from the bottom of the core

c. The zero reactivity when the rod is on the bottom and the positive reactivity being added as the rod is withdrawn

d. The among of reactivity that one unit (i.e. one inch, one percent) of rod motion would insert at that position in the core QUESTION A.15

[1.0 point]

The neutron microscopic cross-section for absorption a generally:

a. increases as neutron energy increases

b. decreases as neutron energy increases

c. increases as neutron velocity increases

d. decreases as target nucleus mass increases

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

[1.0 point]

Reactor power is rising on a 20 second period. Approximately how long will it take for power to double?

a. 14 seconds

b. 29 seconds

c. 40 seconds

d. 54 seconds QUESTION A.17

[1.0 point]

A reactor is critical at 18.1 inches on a controlling blade. The controlling blade is withdrawn to 18.5 inches. The reactivity inserted is 0.1 % k/k. What is the differential rod worth?

a. 0.10 % k/k/inch at 18.1 inches

b. 0.20 % k/k/inch at 18.2 inches

c. 0.25 % k/k/inch at 18.3 inches

d. 0.30 % k/k/inch at 18.4 inches QUESTION A.18

[1.0 point]

The reactor is critical and increasing in power. Power has increased from 10 watts to 800 watts in 90 seconds. How long, at this rate, will it take power to increase from 4 kW to 10 kW? Note:

Neglect any negative temperature coefficient.

a.

1.9 seconds b.

12 seconds c.

16 seconds d.

19 seconds

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.19

[1.0 point]

The largest amount of energy released per fission event appears in the form of kinetic energy of

a. Gammas

b. Alphas and Betas

c. Fission fragments

d. Prompt and delayed neutrons QUESTION A.20

[1.0 point]

Which type of neutron interaction (light nuclei) is most important in MODERATING fast neutron to thermal neutrons?

a. Fission

b. Elastic Scattering

c. Inelastic Scattering

d. Neutron Capture

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

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

[1.0 point]

Which ONE of the following instruments is the best to check your hands and clothing for Beta-Gamma contamination upon leaving a contamination area?

a.

Alpha scintillation detector b.

Gas-flow proportional counter c.

HPGe gamma spectroscopy system d.

Potable pancake Geiger-Mueller survey meter QUESTION B.02

[1.0 point]

In accordance with 10 CFR 55.59 and MURR operator requalification plan, which ONE of the following is the operating test frequency requirement for maintaining an active operator license?

a.

Annually b.

Every 2 years c.

4 years d.

6 years QUESTION B.03

[1.0 point]

According to the MURR Emergency Plan, which ONE of the following is the action term associated with the emergency director shall use the information and Table I to determine that the emergency is appropriately classified?

a. Subsequent Actions

b. Corrective Actions

c. Assessment Actions

d. Specific Protective Actions

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.04

[1.0 point]

Reactor Operator works in a high radiation area for eight (8) hours a day. The dose rate in the area is 100 mrem/hour. Which ONE of the following is the MAXIMUM number of days in which Reactor Operator may perform his duties WITHOUT exceeding 10 CFR 20 limits?

a. 5 days

b. 6 days

c. 7 days

d. 12 days QUESTION B.05

[1.0 point]

In accordance with the MURR Operator Requalification Program, what is the MINIMUM number of hours you must perform the functions of an RO to return to active status after a license lapse?

a.

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

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

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months d.

7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months QUESTION B.06

[1.0 point, 0.25 each]

Identify each of the following surveillances requirements as QUARTERLY (Q), SEMI-ANNUAL (SA), and/or ANNUAL (A).

a. Shim Blades reactivity insertion rate

b. Shim Blades drop time

c. Shim Blades (minimum 1 of 4) inspections

d. Shim Blades reactivity worths

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.07

[1.0 point]

In an emergency, 10 CFR 50.54(x) allows reasonable action that departs from a license condition or a technical specification when this action is immediately needed to protect the public health and safety. In this case, what is the minimum level of authorization or approved needed to depart from a license condition or technical specification?

a. Reactor Operator

b. Senior Reactor Operator

c. Reactor Facility Manager

d. Facility Director QUESTION B.08

[1.0 point]

During a building evacuation, which ONE of the following buildings is NOT part of the Emergency Planning Zone?

a. Dalton

b. Greenhouse

c. USDA Biological Research Lab

d. Molecular Imagining and Theranostics Center QUESTION B.09

[1.0 point, 0.25 each]

Match the following events in accordance with MURR Emergency Plan Classification

[Notification of Unusual Event (NUE), Alert (A), Site Area Emergency (SAE)].

a. Loss of physical control of the reactor facility.

b. Experiment failure that results in significant release of radioactive material.

c. Significant fuel damage indicated by high coolant fission product activity.

d. Civil disturbance directed toward the reactor.

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.10

[1.0 point]

Which ONE of the following changes would require submittal to the Nuclear Regulatory Commission for approval prior to implementation?

a.

Add a new limit to the pre-startup checklist procedure b.

Replace a primary coolant pump with an identical one c.

Delete section 6.3, Radiation Safety listed in the MURR Technical Specifications d.

Add more responsibilities to the Radiation Protection Officer listed in the health physics procedure QUESTION B.11

[1.0 point]

In accordance with 10 CFR 20, individual members of the public are limited to a dose in any unrestricted area from external sources, the dose in any one hour shall not exceed:

a.

2 mrem.

b.

10 mrem.

c.

50 mrem.

d.

500 mrem.

QUESTION B.12

[1.0 point]

Which ONE of the following is NOT a requirement to prevent damage to the reactor and to minimize excessive release of radioactive materials in the event of an experiment failure?

a.

Corrosive materials shall be doubly encapsulated.

b.

Cryogenic liquids shall not be used in any experiment in the reactor pool.

c.

Explosive materials shall not be limited if the detonation pressure is less than half the design pressure of the container.

d.

The absolute value of the reactivity worth of each unsecured experiments which are in the reactor shall be limited to 0.006 k/k.

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

[1.0 point]

Which ONE of the following is the fueled experiment limit that the total inventory of Iodine-131 through Iodine-135 shall not exceed?

a.

100 curies b.

150 curies c.

200 millicuries d.

225 millicuries QUESTION B.14

[1.0 point]

You are currently a licensed operator at MURR. Which ONE of the following would be a violation of 10 CFR Part 55.53 Conditions of licenses?

a.

Your last medical examination was 18 months ago.

b.

Your last requalification operating test was 11 months ago.

c.

Last quarter you were the licensed operator for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

d.

The new requalification program cycle started 18 months ago.

QUESTION B.15

[1.0 point]

During a reactor operation, a small fire occurs on the control room console. Which ONE of the following classes of fire extinguisher would most likely be used for 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.

c. Class C: Fires in live electrical equipment.

d. Class D: Fires involving combustible metals such as magnesium.

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.16

[1.0 point]

A radiation survey of an area reveals a general radiation reading of 1 mRem/hr. However, an irradiated experiment sample (point source) is brought into the area that reads 10 mRem/hr at 1 meter. Which ONE of the following is the required posting for the area, in accordance with 10 CFR Part 20?

a. CAUTION - RADIATION AREA

b. CAUTION - HIGH RADIATION AREA

c. GRAVE DANGER - VERY HIGH RADIATION AREA

d. CAUTION - AIRBORNE RADIOACTIVITY AREA QUESTION B.17

[1.0 point]

In accordance with MURR Technical Specifications, the reactor shall NOT be operated unless the following radiation monitoring channels are operating EXCEPT which ONE of the following?

a.

Reactor Bridge Radiation Monitor b.

Off-Gas (Stack) Radiation Monitor c.

Iodine-131 Processing Hot Cell Radiation Monitor d.

Reactor Containment Building Exhaust Plenum Radiation Monitor QUESTION B.18

[1.0 point]

Per MURR Technical Specifications, what is the MINIMUM shutdown margin with the most reactive shim blade and regulating rod fully withdrawn?

a. 0.01 k/k

b. 0.02 k/k

c. 0.1% k/k

d. 0.2% k/k

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

[1.0 point]

An experiment reading 40 rem/hr was removed from the reactor. Five hours later, it reads 8 rem/h. What is the half-life of the experiment?

a.

1.23 b.

2.15 c.

3.43 d.

5.98 QUESTION B.20

[1.0 point]

Which ONE of the following defines the term Radiation Area?

a.

Any area to which access is limited for any reason.

b.

Any area to which access is limited for the purpose of protecting individuals against undue risks from exposure to radiation and radioactive materials.

c.

Area where radiation exposure rates would result in a dose equivalent in excess of 5 mrem (0.05 mSv) in one hour at 30 centimeters from the radiation source.

d.

Area where radiation exposure rates would result in a dose equivalent in excess of 0.1 rem (1 mSv) in one hour at 30 centimeters from the radiation source.

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

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

[1.0 point]

Which ONE of the following helps to minimize the mechanical strain when shifting the cooling tower fans from fast to slow speed?

a.

A coolant spray is directed on the fans and aids in slowing down the fans.

b.

A large torsion spring is designed to absorb the shock of energizing the slow speed windings.

c.

Special fan belts are designed to absorb the pulse transfer of energizing the slow speed fans and directing it from the fast fans.

d.

A delay timer allows the fan to coast down to a slow speed before the slow speed relays energizes in about 25 seconds.

QUESTION C.02

[1.0 point]

Which ONE of the following Area Radiation Monitor Systems (ARMS) channels does NOT cause a building isolation?

a. Room 114

b. Reactor Bridge

c. Air Plenum 2

d. Bridge ALARA QUESTION C.03

[1.0 point]

Which ONE of the following is the location of the In-Pool Heat Exchanger (HX505)?

a. Northwest portion of room 114

b. Southwest pool below refuel level

c. West end of pool below refuel level

d. North end of reactor pool below refuel level

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

[1.0 point]

Which ONE of the following Neutron Flux Monitors has an Auto Control Interlock that prevents reactor auto control from being initiated when reactor period is less than 35 seconds?

a. Wide Range Monitor

b. Source Range - Channel 1

c. Power Range - Channel 4,5, & 6

d. Intermediate Range - Channels 2 & 3 QUESTION C.05

[1.0 point]

The figure below depicts which ONE of the following nuclear instrumentation detectors?

a.

Fission Chamber b.

Geiger-Mueller Detector c.

Compensated Ion Chamber d.

Uncompensated Ion Chamber QUESTION C.06

[1.0 point]

Which ONE of the following is the fuel element cladding plate material?

a. Boron

b. Graphite

c. Cadmium

d. Aluminum

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

[1.0 point]

Which ONE of the following MURR Radiation Monitoring Channels contains a charcoal cartridge?

a.

Gas Channel

b. Iodine Channel

c. Particulate Channel

d. Air Plenum Channel #1 QUESTION C.08

[1.0 point]

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

a. Stack Gas Monitor

b. Stack Particulate Monitor

c. Bridge Area Monitor

d. None, Nitrogen-16 half-life is too short to require environmental monitoring QUESTION C.09

[1.0 point]

While the reactor is in automatic operation mode, which ONE of the following conditions will NOT cause control to shift back to manual?

a. Regulating rod control switch (1S5) is actuated

b. Regulating rod inserted to the 10% withdrawn position

c. Regulating blade position is greater than 60% withdrawn

d. Wide Range Monitor indication is less than 90%

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

[1.0 point]

Which ONE of the following monitors receives its signal from the Compensated Ion Chamber (CIC)?

a. Wide Range Monitor (WRM)

b. Power Range Monitor (PRM 4)

c. Source Range Monitor (SRM 1)

d. Intermediate Range Monitor (IRM 2)

QUESTION C.11

[1.0 point]

To prevent the spread of radioactive contamination such as airborne radioactive materials, the ventilation system maintains the reactor containment and laboratory buildings at which ONE of the following?

a. Slightly positive pressure to clear the air from reactor related areas

b. Slightly negative pressure to push or contain the air within the reactor related areas

c. Complete balance of pressure so all areas maintain their own air pressure in each area

d. Pressure is not of concern; all areas release through ventilation hoods with monitoring QUESTION C.12

[1.0 point]

In accordance with MURR Technical Specifications, which ONE of the following is required when the Primary Coolant System Conductivity Meter - Demineralizer Outlet reads less than 2 mho/cm?

a. Resin bed has been depleted and it needs to be changed

b. Control room receives a Reactor or Pool Loop Hi Conductivity alarm

c. Demineralizer is operable and there is no need to change the resin bed

d. It is an indication of corrosion and degradation of aluminum piping and components

Category C: Facility and Radiation Monitoring Systems QUESTION C.13

[1.0 point]

If pressurizer liquid level decreases below the normal operating level, which ONE of the following actions does NOT occur?

a. At approximately 7 inches (17.78 cm) below centerline, LC 936 signals water addition valve V527B to open and start coolant charging pump 533, adding water to the pressurizer.

b. At approximately 11 inches (27.94 cm) below center line LC 937 initiates a pressurizer water low level annunciator alarm and signals valve V527A to close.

c. At approximately 13 inches (33.0 cm) below center line, the surge line isolation valve V527C closes to prevent an introduction of nitrogen gas into the primary coolant system.

d. At approximately 13 inches (33.0 cm) below center line, LC 935 initiates a reactor scram by opening a contact (K28-2) in the process input string to E3B of the Reactor Safety System NCLUs.

QUESTION C.14

[1.0 point]

Which ONE of the following is true about the operation of the Plenum Natural Convection Valve (V547) in the Pool Coolant System?

a. Spring to close, air to open

b. Air to close, spring to open

c. Motor to close, air to open

d. Motor to close, spring to open QUESTION C.15

[1.0 point]

In accordance with MURR Technical Specifications, which ONE of the following Reactor Safety MAXIMUM requirements, is 6 inches above valves?

a. Low Pool Level Rod Run In

b. High Pool Level Rod Run In

c. Vent Tank Low Level Rod Run In

d. Anti-Siphon Line Hi Level Rod Run In

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

[1.0 point]

Which ONE of the following Limiting Safety System Settings (LSSS) listed below is NOT a requirement in Mode I?

a. Reactor Power - 125% full power, maximum 10MW.

b. Primary Coolant Flow - minimum 1,625 gpm each loop.

c. Reactor Outlet Water Temperature - maximum 155C.

d. Primary Coolant Pressurizer Pressure - minimum 75 psia.

QUESTION C.17

[1.0 point]

Which ONE of the following is NOT required to assure proper operation of the reactor control system and the reactor safety system instrument channels?

a. Shim blades shall be inserted and scrammed to verify operability of the manual scram.

b. All control blades, including the regulating blade, shall be verified operable within a shift.

c. The drop time of each of the four shim blades shall be measured at quarterly intervals.

d. Above 100 kW, the distance between the highest and lowest shim blade shall be verified within a shift.

QUESTION C.18

[1.0 point]

In the event of a low primary coolant pressure condition, which ONE of the following actions occurs?

a. Nitrogen gas is vented to the Room 114 exhaust line

b. Water is drained from the pressurizer to the drain collection tank

c. Coolant flow is redirected to bypass the pool coolant heat exchanger

d. Flow path is provided from the anti-siphon tank to the primary coolant system QUESTION C.19

[1.0 point]

Which ONE of the following locations is where domestic water enters the facility?

a.

Laboratory basement b.

Area outside mechanical equipment room 114 c.

Southwest corner of the cooling tower basement d.

Missouri University Research Reactor industrial building

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

[1.0 point]

The Vent Tank System is connected to the primary coolant loop, at the highest points of the inverted loop and the in-pool heat exchanger through __________.

a. Half inch lines

b. Plastic lines

c. Set of filters

d. Gate valves

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

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

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

d

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 4.2 A.02 Answer:

d

Reference:

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

T= 45/Ln(100/50 ); T = 64.9 seconds A.03 Answer:

b

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 8.2 A.04 Answer:

b

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 6.2 A.05 Answer:

c

Reference:

P/Po = 120%, T = 30 seconds, t = 0.7, P/Po = 120 e^0.7/30 = 123%

A.06 Answer:

a. 3; b. 1; c. 4; d. 2

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 5.5 A.07 Answer:

c

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 3.3.1 A.08 Answer:

c

Reference:

Reactor is continually increasing, since a reactor period is still positive.

A.09 Answer:

b

Reference:

CR = S/(1-K) 50,000 = 10,000/(1 - X) 1 - X = 10,000/50,000; K = 0.8 A.10 Answer:

a

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 6.4 A.11 Answer:

a

Reference:

Fission rate = thermal flux (Ø) x macroscopic cross-section. (f) = 1.0 x 10 13 neutrons/cm 2/second x 0.1 cm

-1 = 1.0 x 10 12 neutrons/cm 3/second Burn, Introduction to Nuclear Reactor Operations, Section 2.6.2 A.12 Answer:

d

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 3.3.4, page 3-20&21

=(keff2-keff1)/(keff1*keff2) = (0.975-0.921)/(0.975*0.921) = 0.0601k/k=6.01%k/k

Category A: Reactor Theory, Thermodynamics, & Facility Operating Characteristics A.13 Answer:

d

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 1, Module 2, page 30 A.14 Answer:

d

Reference:

Burn, Introduction to Nuclear Reactor Operations, Example 7.2(b), page 7-4 A.15 Answer:

b

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 2.5 A.16 Answer:

a

Reference:

P = P0 et/T --> ln(2) = time ÷ 20 seconds -> time = ln (2) x 20 sec. 0.693 x 20 13.8 sec. or 14 seconds A.17 Answer:

c

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 7.3 Differential position is mid-point of 18.1 and 18.5 = 18.3 Differential blade worth (k/k/in) = (k/k) / (change in blade position)

= 0.1 (% k/k) /0.4 in = 0.25 % k/k/in A.18 Answer:

d

Reference:

P = P et/T 800 = 10*e (90 sec/T)

T = 20.54sec 10 kW = 4 kW*e (t/20.54) t = 19 sec A.19 Answer:

c

Reference:

Glasstone, Nuclear Reactor Engineering, Section 1.47 A.20 Answer:

b

Reference:

LaMarsh, 3rd ed., Section 3.6, page 345

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

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

d

Reference:

Glasstone, Nuclear Reactor Engineering, Section 9.88, page 5.37 Standard NRC question B.02 Answer:

a

Reference:

10 CFR 55.59(a)(2) and MURR Operator Requalification Plan 2.0 & 2.4 B.03 Answer:

c

Reference:

MURR Emergency Plan 5.1.2 B.04 Answer:

b

Reference:

10CFR20.1201(a)(1) [5000 mr x 1 hr x day] = 6.25 days = 6 days; 100 mr

8 hr B.05 Answer:

c

Reference:

10 CFR 55.59 and MURR Operator Requalification Program Log B.06 Answer:

a. Annual (A); b. Quarterly (Q); c. Semi-Annual (SA); d. Annual (A)

Reference:

MURR Technical Specifications 4.2 B.07 Answer:

b

Reference:

10 CFR 50.54(y)

B.08 Answer:

a

Reference:

MURR EP-RO-014, 1.1 B.09 Answer:

a. Alert (A); b. Alert (A); c. Site Area Emergency (SAE); d. Notification of Unusual Event (NUE)

Reference:

MURR Emergency Plan 3.2, 3.2, and 3.4 B.10 Answer:

c

Reference:

MURR Technical Specifications changes requires an amendment B.11 Answer:

a

Reference:

10 CFR 20.1301 B.12 Answer:

c

Reference:

MURR Technical Specifications 3.8 B.13 Answer:

b

Reference:

MURR Technical Specifications 3.8.f

Category B: Normal/Emergency Operating Procedures and Radiological Controls B.14 Answer:

c

Reference:

10 CFR 55.59 B.15 Answer:

c

Reference:

Standard NRC question B.16 Answer:

b

Reference:

10 CFR 20.1003, 10 CFR 20.1902 (DR1)(D1)2=(DR2)(D2)2 (10 mrem/hr)(100 cm)2/(30 cm)2 = 111.1 mrem/hr B.17 Answer:

c

Reference:

MURR Technical Specifications Section 3.7.a B.18 Answer:

b

Reference:

MURR Technical Specifications 3.1.b B.19 Answer:

b

Reference:

DR = DR0, T1 2 =

0.693

DR = DR0 e-.693/T1/2 8 = 40 e-(.693)(5)/T1/2

0. = e-(.693)(5)/T1/2 ln(0.2) = ln(e-(.693)(5)/T1/2)

-1.609 = -3.465 / T1/2 T1/2 = -3.465 / -1.609 T1/2 = 2.15 hr B.20 Answer:

c

Reference:

10 CFR 20.1003

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

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

d

Reference:

MURR OP-RO-480, Section 5.2.2, NOTE C.02 Answer:

a

Reference:

MURR Operations Training Manual, Reactor Isolation & Facility Evacuation, Page 3.4-1 C.03 Answer:

c

Reference:

MURR Operations Training Manual, In-Pool Heat Exchanger,Section III (HX-505), Page 4.2-3 C.04 Answer:

d

Reference:

MURR SAR, 7.4.2.2.c, Page 7-22 C.05 Answer:

c

Reference:

Standard NRC question C.06 Answer:

d

Reference:

MURR Operations Training Manual, Fuel Elements, Page 7.4-2 C.07 Answer:

b

Reference:

MURR Operations Training Manual, Stack Monitor - Eberline, Page 9.3 - 2 C.08 Answer:

d

Reference:

Standard NRC question C.09 Answer:

c

Reference:

MURR SAR, 7.5.4.3, Page 7-30 C.10 Answer:

a

Reference:

MURR Technical Specifications 3.10, page A-38 C.11 Answer:

b

Reference:

MURR SAR, 11.1.5.2, Page 11-50 C.12 Answer:

c

Reference:

MURR Technical Specifications 3.3.g & SAR 5.5.7

Category C: Facility and Radiation Monitoring Systems C.13 Answer:

b

Reference:

MURR SAR 7.6.5, page 307 C.14 Answer:

b

Reference:

MURR Operations Training Manual, Primary & Pool Sample Station,Section III.A, Page 5.1-2 C.15 Answer:

d

Reference:

MURR Technical Specifications 3.2.f.6, Page A-14 C.16 Answer:

c

Reference:

MURR SAR 4.6.4.1, Table 4-17, Page 4-58 C.17 Answer:

a

Reference:

MURR Technical Specifications 4.2, Page A-42 C.18 Answer:

d

Reference:

MURR Operations Training Manual, page 2-4C C.19 Answer:

c

Reference:

MURR Operations Training Manual, page 1-1A C.20 Answer:

a

Reference:

MURR Operations Training Manual, Primary Coolant System,Section II, Page 4.1-2

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

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

ML24330A037

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