ML17193A001

Examination Report No. 50-186/OL-17-02, University of Missouri - Columbia

ML17193A001
Person / Time
Site:	University of Missouri-Columbia
Issue date:	07/12/2017
From:	Anthony Mendiola Research and Test Reactors Oversight Branch
To:	Rhonda Butler Univ of Missouri - Columbia
Paulette Torres
Shared Package
ML17086A128	List: IR 05000186/2017002 ML17193A001
References
50-186/OL-17
Download: ML17193A001 (42)

Text

July 12, 2017 Mr. Ralph A. Butler, Director University of Missouri - Columbia Research Reactor Center 1513 Research Park Drive Columbia, MO 65211

SUBJECT:

EXAMINATION REPORT NO. 50-186/OL-17-02, UNIVERSITY OF MISSOURI -

COLUMBIA

Dear Mr. Butler:

During the week of June 26, 2017, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your University of Missouri - Columbia 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 NRCs 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. 50-186

Enclosures:

1. Examination Report No. 50-186/OL-17-02

2. Facility Suggestions with NRC Resolution

3. Written Examination cc: Bruce Meffert, Reactor Manager, MURR cc w/o enclosure: See next page

ML NRR-074 OFFICE NRR/DPR/PROB NRR/DIRS/IOLB/OLA NRR/DPR/PROB/BC NAME PTorres ABaxter AMendiola DATE 7/05/2017 7/12/2017 7/12/2017 University Of Missouri - Columbia Docket No: 50-186 cc:

Les Foyto, Associate Director University of Missouri-Columbia Research Reactor Center 1513 Research Park Drive Columbia, MO 65211 Homeland Security Coordinator Missouri Office of Homeland Security P.O. Box 749 Jefferson City, MO 65102 Planner, Dept. of Health and Senior Services Section for Environmental Public Health P.O. Box 570 Jefferson City, MO 65102-0570 Deputy Director for Policy Department of Natural Resources 1101 Riverside Drive Fourth Floor East Jefferson City, MO 65101 A-95 Coordinator Division of Planning Office of Administration P.O. Box 809, State Capitol Building Jefferson City, MO 65101 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.: 50-186/OL-17-02 FACILITY DOCKET NO.: 50-186 FACILITY LICENSE NO.: R-103 FACILITY: University of Missouri - Columbia Reactor EXAMINATION DATE: June 26-27, 2017 SUBMITTED BY: _________/RA/_____________ _______7/5/17___

Paulette Torres, Chief Examiner Date

SUMMARY

During the week of June 26, 2017, the NRC administered a licensing examination to one Senior Reactor Operator Instant (SRO-I) applicant, and one Senior Reactor Operator Upgrade (SRO-U) applicant. The applicants 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 0/0 1/0 1/0 Operating Tests 0/0 2/0 2/0 Overall 0/0 2/0 2/0

3. Exit Meeting:

Paulette Torres, Chief Examiner, NRC Robert Hudson, Training Coordinator, MURR Bruce Meffert, Reactor Manager, MURR Les Foyto, Associate Director, MURR The facility licensee agreed to e-mail their comments/suggestions on the written examination that were incorporated into the examination report (see Enclosure 2).

Enclosure 1

FACILITY SUGGESTIONS ON THE WRITTEN EXAM WITH NRC RESOLUTION QUESTION B.14 [1.0 point]

Which ONE of the following Emergency Action Levels provides notification to the NRC, the American Nuclear Insurers (ANI) and the State Emergency Management Agency (SEMA) during an emergency?

a. Assessment Actions

b. Corrective Actions

c. Specific Protective Actions

d. Subsequent Actions Answer: d REF: Emergency Plan, Section 5.1.5, 5.2.5, 5.3.5, pg. 13-15 Facility Suggestions &

Recommendations: Section 5.0 Emergency Response of the MURR Emergency Plan contains a multiple subsections titled Emergency Action Levels which direct an operator to utilizes Appendix B, if a specified threshold is met. None the these subsections direct the operator to perform any of the answers provided. Each of the answers provided are companion but independent subsections to the Emergency Action Levels subsection. Recommendation:

Change the term Emergency Action Levels to Emergency Responses to encompass all answers provided.

Reference:

MURR Emergency Plan Procedures Manual, pages 12-15.

NRC Resolution: The NRC accepts the facility recommendation and understands that changing the term Emergency Action Levels to Emergency Responses will make the question correct to encompass all answers provided.

Enclosure 2

QUESTION B.15 [1.0 point]

The Emergency Organization consists of two groups: (1) the Facility Emergency Organization and (2) the Emergency Support Organizations. Which ONE of the following is part of the Emergency Support Organizations?

a. Reactor Operations

b. The UMC Radiation Safety Office

c. MURR staff in the Directors Office

d. The City of Columbia Fire Department Answer: b REF: Emergency Plan, Section 2.3, pg. 6 and Figure II, pg. 7 Facility Suggestions &

Recommendations: Answers B and D are both correct as the question is written.

Both the UMC Radiation Safety Office and the City of Columbia Fire Department are members of the Emergency Support Organizations. However, the fire department is the only member not composed of University of Missouri staff. Recommendation:

Change second sentence to Which ONE of the following is part of the Emergency Support Organizations and composed of University of Missouri staff?

Reference:

MURR Emergency Plan Procedures Manual, page 6.

NRC Resolution: The NRC agrees with the facility suggestion and accepts answers B and D as both correct. The NRC also accepts the facility recommendation and understands that changing the sentence to Which ONE of the following is part of the Emergency Support Organizations and composed of University of Missouri staff? will make B the only correct answer.

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

- Columbia REACTOR TYPE: TANK DATE ADMINISTERED: 06/27/2017 CANDIDATE: _______________________

INSTRUCTIONS TO CANDIDATE:

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

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 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 ___

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 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 + &

SUR = 26 .06

( ) (

CR1 1 K eff1 = CR2 1 K eff 2 ) CR1 ( 1 ) = CR2 ( 2 )

(1 ) M=

1

= 2 CR P = P0 10SUR(t )

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

• M= SDM = =

1 K eff 2 K eff

• 0.693 K eff 2 K eff1

+ T1 =

eff + & 2 K eff1 K eff 2 K eff 1

= DR = DR0 e t 2 DR1 d1 = DR2 d 2 2

K eff 6 Ci E (n) ( 2 )2 = (1 )2 DR =

R2 Peak2 Peak1 DR - Rem, Ci - curies, E - Mev, R - feet 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lbm 1 Horsepower = 2.54 x 103 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

UNIVERSITY OF MISSOURI -

COLUMBIA Operator Licensing Examination Week of June 26, 2017

QUESTION A.01 [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.

QUESTION A.02 [1.0 point, 0.33 each]

Match the best answer. If a reactor has values of k (multiplication factor) and (reactivity) as follow (assume there is no neutron source present):

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.03 [1.0 point]

Which ONE of the following factors is least affected by short term reactor transients?

a. Fast Non Leakage Probability (Lf)

b. Resonance Escape Probability (p)

c. Thermal Utilization Factor (f)

d. Reproduction Factor ()

Section A: Reactor Theory, Thermohydraulics & Facility Operating Characteristics Page 2 QUESTION A.04 [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.05 [1.0 point, 0.25 each]

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

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.06 [1.0 point]

The term Excess Reactivity 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.

Section A: Reactor Theory, Thermohydraulics & Facility Operating Characteristics Page 3

d. The amount of positive reactivity that would exist if all the control blades were moved to the fully withdrawn position from the point the reactor is exactly critical.

QUESTION A.07 [1.0 point]

Which of ONE the following does NOT affect the Effective Multiplication Factor (Keff)?

a. The moderator-to-fuel ratio.

b. The physical dimensions of the core.

c. The strength of the installed neutron source.

d. The current time in core life.

QUESTION A.08 [1.0 point]

The reactor has been operating at 100% power for the past 20 days. Which ONE of the following is the PRIMARY SOURCE of heat generation in the core 30 seconds following a reactor scram from 100% power?

a. Fission resulting from spent fuel.

b. Fission resulting from installed neutrons sources.

c. Beta and gamma heating from fission decay products.

d. Beta and gamma heating from fission generated by installed neutron sources.

QUESTION A.09 [1.0 point]

The amount of reactivity necessary to make a reactor prompt critical is _________.

a. =

b. (1-)k < 1

c. <

d. eff = 0.00738

Section A: Reactor Theory, Thermohydraulics & Facility Operating Characteristics Page 4 QUESTION A.10 [1.0 point]

Which ONE of the following describes the difference between reflectors and moderators?

a. Reflectors decrease core leakage while moderators thermalize neutrons.

b. Reflectors thermalize neutrons while moderators decrease core leakage.

c. Reflectors shield against neutrons while moderators decrease core leakage.

d. Reflectors decrease thermal leakage while moderators decrease fast leakage.

QUESTION A.11 [1.0 point]

What is the Keff for a reactor shutdown by 0.0455 K/K?

a. 0.957

b. 0.855

c. 0.786

d. 0.0455 QUESTION A.12 [1.0 point]

Which ONE of the following changes to the core will most strongly affect the Thermal Utilization Factor?

a. Going from High Enrichment fuel to Low Enrichment fuel.

b. Removal of moderator (Thermal expansion).

c. Buildup of fission products in the fuel.

d. Removal of a control rod.

Section A: Reactor Theory, Thermohydraulics & Facility Operating Characteristics Page 5 QUESTION A.13 [1.0 point]

For U-235, the thermal fission cross-section is f = 582 barns, and the capture cross-section is = 99 barns. When a thermal neutron is absorbed by U-235, what is the relative probability that fission will occur?

a. 14.6 %

b. 17.0 %

c. 83.0 %

d. 85.5 %

QUESTION A.14 [1.0 point]

Which ONE of the following statements describes the difference between the Integral Rod Worth (IRW) curves and the Differential Rod Worth (DRW) curves?

a. IRW relates the worth of the rod per increment of movement to rod position. DRW relates the total reactivity added by the rod to the rod position.

b. IRW relates the total reactivity added by the rod to the rod position. DRW relates the worth of the rod per increment of movement to rod position.

c. IRW relates the total reactivity in the core to the time rate of reactivity change. DRW relates the time rate of reactivity change to rod position.

d. IRW is the slope of the DRW at a given rod position.

QUESTION A.15 [1.0 point]

During the minutes following a reactor scram, reactor power decreases on a negative 80 second period, corresponding to the half-life of the longest lived delayed neutron precursor, which is approximately __________.

a. 20 seconds

b. 40 seconds

Section A: Reactor Theory, Thermohydraulics & Facility Operating Characteristics Page 6

c. 55 seconds

d. 80 seconds QUESTION A.16 [1.0 point]

A reactor with an initial population of 1 x 108 neutrons is operating with Keff = 1.001. Considering only the increase in neutron population, how many neutrons (of the increase) will be prompt when the neutron population changes from the current generation to the next? Assume =

0.007.

a. 700

b. 7,000

c. 99,300

d. 100,000 QUESTION A.17 [1.0 point]

Inelastic Scattering can be described as a process whereby a neutron collides with a nucleus and:

a. Recoils with the same kinetic energy it had prior to the collision.

b. Is absorbed by the nucleus, with the nucleus emitting a gamma ray.

c. Recoils with a lower kinetic energy, with the nucleus emitting a gamma ray.

d. Recoils with a higher kinetic energy, with the nucleus absorbing a gamma ray.

QUESTION A.18 [1.0 point]

During a startup you increase reactor power from 50 watts to 1000 watts in 100 seconds.

What is the reactor period?

a. 25

b. 33

c. 41

d. 50

Section A: Reactor Theory, Thermohydraulics & Facility Operating Characteristics Page 7 QUESTION A.19 [1.0 point]

Which ONE of the following is the correct reason that delayed neutrons enhance control of the reactor?

a. There are more delayed neutrons than prompt neutrons.

b. Delayed neutrons take longer to reach thermal equilibrium.

c. Delayed neutrons increase the average neutron generation time.

d. Delayed neutrons are born at higher energies than prompt neutrons and therefore have a greater effect.

QUESTION A.20 [1.0 point]

A fissile material is one which will fission upon absorption of a thermal neutron. A fertile material is one which upon absorption of a neutron becomes a fissile material. Which ONE of the following isotopes is an example of a fertile material?

a. U-233

b. U-235

c. U-238

d. Pu-239

• • • • • • • • • • • • • • • • • End of Section A *****************

Section B: Normal/Emergency Procedures and Radiological Controls Page 8 QUESTION B.01 [1.0 point, 0.25 each]

Based on 10 CFR 55, which ONE of the following is the MINIMUM requirement that must be met to retain an active Reactor Operator license? Must perform license duties:

a. A minimum of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per month.

b. At least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per calendar year.

c. A minimum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per calendar quarter.

d. A minimum of 5 eight-hour shifts per calendar quarter.

QUESTION B.02 [1.0 point]

Per Technical Specifications, the average reactor core temperature coefficient of reactivity shall be more negative than __________.

a. -6.0 x 10-5 k/k/°F

b. -2.0 x 10-3 k/k/°F

c. -5.0 x 10-5 k/k/°F

d. -20.0 x 10-3 k/k/°F QUESTION B.03 [1.0 point]

In accordance with the Technical Specifications, a SAFETY LIMIT is:

a. The actuating level for an automatic protective device related to those variables having significant safety functions.

b. A system which is designed to initiate automatic reactor protection or to provide information for initiation of manual protective action.

c. An administratively established constraint on equipment and operational characteristics which shall be adhered to during operation of the reactor.

d. A limit on an important process variable which is found to be necessary to reasonably protect the integrity of physical barriers which guard against the uncontrolled release of radioactivity.

Section B: Normal/Emergency Procedures and Radiological Controls Page 9 QUESTION B.04 [1.0 point]

Temporary changes may be made to a procedure with the approval of the __________.

a. Reactor Manager Supervisor

b. Lead Senior Reactor Operator (LSRO)

c. LSRO and another licensed operator

d. Reactor Procedure Review Subcommittee (RPRS)

QUESTION B.05 [1.0 point]

How would an accessible area be posted if the radiation level in the area is 65 mR/hr?

a. CAUTION - RADIATION AREA

b. CAUTION - RESTRICTED AREA

c. CAUTION - HIGH RADIATION AREA

d. CAUTION - RADIOACTIVE MATERIALS AREA QUESTION B.06 [1.0 point]

Which ONE of the following records need NOT be retained for the lifetime of the reactor facility?

a. Radiation Exposures for All Monitored Personnel

b. Off-Site Environmental Monitoring Surveys

c. Updated Drawings of the Reactor Facility

d. Reportable Occurrences

Section B: Normal/Emergency Procedures and Radiological Controls Page 10 QUESTION B.07 [1.0 point]

Area for which emergency planning is performed to assure that prompt and effective actions can be taken to protect the public in the event of an accident defines a (an):

a. Site Boundary

b. Operations Boundary

c. Emergency Planning Zone

d. Emergency Control Center QUESTION B.08 [1.0 point]

In accordance with Technical Specifications, a REACTOR SHUTDOWN condition requires all four (4) of the shim blades are fully inserted and:

a. The console key removed.

b. Power is unavailable to the shim rod drive mechanism electromagnets.

c. No operations are in progress which involve control rod maintenance.

d. No operations are in progress which involve moving fuel elements in the reactor vessel.

QUESTION B.09 [1.0 point]

10 CFR 20 requires that dose equivalent to the embryo/fetus during the entire pregnancy, due to the occupational exposure of a declared pregnant woman, does not exceed __________.

a. 0.5 rem

b. 5.0 rem

c. 0.1 rem

d. 1.0 rem

Section B: Normal/Emergency Procedures and Radiological Controls Page 11 QUESTION B.10 [1.0 point]

An individual is accidentally exposed to a mixed gamma and neutron radiation field for 20 minutes. The radiation field from gamma is 30 R/hr, and the radiation field from neutrons of unknown energy is 9 R/hr. What is the individuals total absorbed dose?

Refer to the table below.

a. 10 rem

b. 13 rem

c. 40 rem

d. 39 rem/hr QUESTION B.11 [1.0 point]

The intensity of radiation from a point source is 100 mR/hr at a distance of 12 meters.

What is the intensity at 4 meters?

a. 1,800 mR/hr

b. 900 mR/hr

c. 33 mR/hr

d. 11.1 mR/hr QUESTION B.12 [1.0 point]

Which ONE of the following listed experiments is NOT allowed per Technical Specifications?

a. A double encapsulated experiment containing corrosive materials.

b. A fueled experiment generating 300 curies of Iodine-131 through Iodine-135.

c. An experiment containing 20 milligrams of explosive material.

d. A movable experiment with a maximum absolute reactivity worth of 0.001K/K.

Section B: Normal/Emergency Procedures and Radiological Controls Page 12 QUESTION B.13 [1.0 point]

During an emergency, who has the responsibility for authorizing volunteer emergency workers to incur radiation exposure in excess of normal occupational limits?

a. The Emergency Director.

b. The Health Physics Manager.

c. The Emergency Coordinator.

d. The Emergency Coordinator, with concurrence of Health Physics Manager.

QUESTION B.14 [1.0 point]

Which ONE of the following Emergency Action Levels provides notification to the NRC, the American Nuclear Insurers (ANI) and the State Emergency Management Agency (SEMA) during an emergency event?

a. Assessment Actions

b. Corrective Actions

c. Specific Protective Actions

d. Subsequent Actions QUESTION B.15 [1.0 point]

The Emergency Organization consist of two groups: (1) the Facility Emergency Organization, and (2) the Emergency Support Organizations. Which ONE of the following is part of the Emergency Support Organizations?

a. Reactor Operations

b. The UMC Radiation Safety Office

c. MURR staff in the Directors Office

d. The City of Columbia Fire Department

Section B: Normal/Emergency Procedures and Radiological Controls Page 13 QUESTION B.16 [1.0 point]

Which ONE of the following Action Levels corresponds to an ALERT Emergency Class?

a. Loss of physical control of the facility.

b. Prolonged fire or explosion within the facility.

c. Concentration of airborne radioactivity at the stack monitor exceeding 20,000 Air Effluent Concentration averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

d. Radiation levels at the distance corresponding to the nearest site boundary of 100 mrem/hr for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> whole-body of 500 mem thyroid dose.

QUESTION B.17 [1.0 point]

Which ONE of the following nuclear instruments is required for Startup only?

a. The Source Range Monitor (SRM)

b. The Intermediate Range Monitor (IRM)

c. The Power Range Monitor (PRM)

d. The Wide Range Monitor (WRM)

QUESTION B.18 [1.0 point]

Which ONE of the following experimental facilities/research projects conducts experiments that are classified as Neutron Beam Experiments?

a. The Thermal Column

b. The Pneumatic Tube System

c. The Graphite Reflector Region

d. The Center Test Hole (Flux Trap)

Section B: Normal/Emergency Procedures and Radiological Controls Page 14 QUESTION B.19 [1.0 point]

Which ONE of the following is NOT part of the Reactor Shutdown Checklist?

a. VERIFY core free of debris and abnormalities.

b. VERIFY all key box keys inventoried and key box locked.

c. VERIFY area radiation monitoring system trip levels set as specified on form FM-21.

d. VERIFY all control blades are bottomed and all control rod drive mechanism are fully inserted.

QUESTION B.20 [1.0 point]

FM-57 and FM 58 corresponds to the Long and Short Form Startup Checksheet respectively. In both forms, an asterisk (*) denotes an item that is a corrective action commitment resulting from a:

a. Reactor Utilization Request (RUR)

b. Radiation Work Permit (RWP)

c. Licensee Event Report (LER)

d. Safety Analysis (SA)

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • End of Section B ********************************

Section C: Facility and Radiation Monitoring Systems Page 15 QUESTION C.01 [1.0 point]

The neutron source consists of a homogeneous mixture of _________, double encapsulated in stainless steel.

a. Am-Li

b. Am-Be

c. Sb-Be

d. Pu-Be QUESTION C.02 [1.0 point]

The Anti-Siphon System is connected to the primary coolant loop, at the high point of the inverted loop, by valves:

a. 507A and 507B

b. 527E and 527F

c. 543A and 543B

d. 546A and 546B QUESTION C.03 [1.0 point]

A containment building isolation is initiated when a high radiation level condition is detected by the __________ channel.

a. Room 114

b. South Wall

c. Secondary Coolant monitor

d. Air Plenum #2

Section C: Facility and Radiation Monitoring Systems Page 16 QUESTION C.04 [1.0 point]

The neutron-absorbing material in the MURR shim blades is:

a. Beryllium

b. Boral Plate

c. Aluminum Oxide

d. Zirconium Hydride QUESTION C.05 [1.0 point]

The alarm modules are segregated by their illumination color. Which ONE of the following color corresponds to an abnormal condition or event?

a. Blue

b. White

c. Green

d. Yellow QUESTION C.06 [1.0 point, 0.25 each]

Match the following pH ranges in Colum A with their corresponding function in Column B.

Column A Column B

a. 5 to 6 1. The pH of the water in the primary coolant system shall be maintained between _________ when averaged over a period of one (1) quarter.

b. 5.0 and 7.0 2. Waste Tank Sample release pH must be between

c. 8.0 to 8.4 3. The primary and pool coolant ion-exchange systems maintain the pH in a range around _________.

d. 5.5 and 9.5 4. Secondary Coolant System Chemistry pH level is maintained in the normal range of _________ by the addition of sulfuric acid.

Section C: Facility and Radiation Monitoring Systems Page 17 QUESTION C.07 [1.0 point]

Per the Reactor Startup - Normal Operation Procedure, the _________ low pressure alarm may cause electrical noise at lower reactor powers during reactor start up.

a. Firemain

b. Pressurizer

c. Anti-Siphon Tank

d. Primary Coolant System QUESTION C.08 [1.0 point]

High Voltage Panel # _______ provide power to Distribution Center-1 and Distribution Center-2.

a. HVP #1

b. HVP #2

c. HVP #3

d. HVP #4 QUESTION C.09 [1.0 point]

The _________ houses the sensing and control devices to ensure emergency electrical distribution is powered from either the normal or emergency source.

a. Automatic Transfer Switch (ATS)

b. Emergency Distribution Center (EDC)

c. Emergency Power Generator (EPG)

d. Uninterruptible Power Supply (UPS)

Section C: Facility and Radiation Monitoring Systems Page 18 QUESTION C.10 [1.0 point]

Air produced by the Emergency Air Compressor is stored in the __________.

a. Air Tank

b. Vent Tank

c. Holdup Tank

d. Receiver Tank QUESTION C.11 [1.0 point]

Which ONE of the following actions will NOT occur upon actuation of the Reactor Isolation -Manual Initiation?

a. Reactor scram is initiated by the Reactor Safety System.

b. Evacuation or Isolation Scram alarm annunciation.

c. Containment building ventilation exhaust plenum backup doors close.

d. Reactor Isolation relays R2A and R2B are tripped.

QUESTION C.12 [1.0 point]

The primary coolant system fuel element failure monitor shall be _________ on a semiannual basis.

a. Channel-Checked

b. Channel-Calibrated

c. Channel-Replaced

d. Channel-Tested

Section C: Facility and Radiation Monitoring Systems Page 19 QUESTION C.13 [1.0 point]

The major flow path for the Primary Coolant Loop, beginning at the reactor core, is as follows:

a. First V502, second V507A, Third V507B, Fourth P501A, Fifth HX503A.

b. First 507A, second P501A&B, Third HX503A&B, Fourth V507B, Fifth V502.

c. First HX503A&B, second V502, Third P501A&B, Fourth 507A, Fifth V507B.

d. First 507A, second V507B, Third HX503B, Fourth V502, Fifth P501B.

QUESTION C.14 [1.0 point]

When the pressurizer pressure falls below the lower limit of the normal operating band, V526 will automatically open. Which ONE of the following gases supplies the volume above the water surface to maintain the necessary operating pressure?

a. CO2

b. Hydrogen

c. Nitrogen

d. Oxygen QUESTION C.15 [1.0 point]

Which ONE of the following systems provides a means of heat removal from in-pool components such as control blade gaps, the center test hole and the reflector region?

a. Pool Coolant System

b. Primary Coolant System

c. Reactor Coolant Clean Up System

d. Secondary Coolant System

Section C: Facility and Radiation Monitoring Systems Page 20 QUESTION C.16 [1.0 point]

The pool skimmer system may be arranged to perform any of three operations EXCEPT:

a. Remove debris from the reactor pool surface.

b. Provide a path for make-up water to the reactor pool.

c. Lower reactor pool water level to the elevation of the lower bridge.

d. Purifies pool coolant water, thereby, reducing the radioactive nuclide inventory.

QUESTION C.17 [1.0 point, 0.25 each]

The figure below is a simplified system drawing of the reactor. Match the corresponding regions in Column A with the reactor system in Column B.

Column A Column B

1. Graphite Reflector Wedges

2. Fuel Elements

3. Beryllium Reflector

4. Inner pressure Vessel

5. Outer Pressure Vessel

6. Control Blade

7. Regulating Blade

Section C: Facility and Radiation Monitoring Systems Page 21 QUESTION C.18 [1.0 point]

Which ONE of the following Reactor Core Assembly Support Structure is composed of a single component named the island tube?

a. Outer Pressure Vessel

b. Inner Pressure Vessel

c. Upper Reflector Tank

d. Lower Reflector Plenum QUESTION C.19 [1.0 point]

The regulating blade is driven at a speed of __________ per minute.

a. 2 inches

b. 15 inches

c. 26 inches

d. 40 inches QUESTION C.20 [1.0 point]

Which ONE of the following detector signal is fed directly to the Wide Range Monitor (WRM) drawer in the Control Room Instrument Panel?

a. Fission Chamber #1

b. Fission Chamber #2

c. Compensated Ion Chamber

d. Uncompensated Ion Chamber

• • • • • • • • • • • • • • • • • • • End of Section C ****************************

• • • • • • • • • • • • • • • • • • • End of the Exam ***************************

University Of Missouri - Columbia OL 17-02 Section A: Theory, Thermo & Facility Operating Characteristics Page 22 A.01 Answer: d REF: DOE Handbook, Volume 2, Module 4, Subcritical Multiplication, pg. 1-9 A.02 Answer: a, 3; b,2; c,1 REF: 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.03 Answer: d REF: Burns, Example 3.3.1 (c), pg. 3-18 A.04 Answer: c REF: Burns, Figure 8.1, pg. 8-6 A.05 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 Where A=Mass#, Z=Atomic#, P=parent atom, D=daughter atom A.06 Answer: d REF: Technical Specifications, Definitions 1.9, pg. A-2 A.07 Answer: c REF: Burns, Section 3.3.2, pg. 3-18 A.08 Answer: c REF: Glasstone and Sesonske, 1967, Section 2.178-2.188

University Of Missouri - Columbia OL 17-02 Section A: Theory, Thermo & Facility Operating Characteristics Page 23 A.09 Answer: a REF: Lamarsh 3rd ed., pg. 340-341 A.10 Answer: a REF: Lamarsh, 3rd ed., pg. 71, 297 A.11 Answer: a REF:

K eff 1

=

K eff K eff = K eff 1 1

K eff =

1 1

K eff =

1 (0.455) k eff = 0.9565 A.12 Answer: d REF: Burns, Section 3.3.2, pg. 3-19 A.13 Answer: d REF: Lamarsh, 3rd ed., Example 3.2, pg. 56 The probability of fission is f / ( + f) = 582 / (99 + 582) = 0.855 A.14 Answer: b REF: Burns, Section 7.2 and 7.3, pg. 7-1 to 7-10 A.15 Answer: c REF: Burns, Section 1.3.3, pg. 1-6 and 1-7

University Of Missouri - Columbia OL 17-02 Section A: Theory, Thermo & Facility Operating Characteristics Page 24 A.16 Answer: c REF: Lamarsh, 3rd edition, Section 7.2, pg. 340 1st generation = 1 x 108 2nd generation = (1.001) 1 x 108 = 1.001 x 108 Increase = 2nd generation - 1st generation = 1 x 105 Of the increase, (1-) = 0.993 is the fraction of the neutrons that are prompt =

(0.993) 1 x 105 = 99,300 A.17 Answer: c REF: Burns, Section 2.4.5, pg. 2-28 A.18 Answer: b REF: P = P0 et/

ln(P/P0) = t/

= t/(ln(P/P0)

= 100/ln(20) = 33.381 A.19 Answer: c REF: Burns, Example 3.3.7(e), pg. 3-31 A.20 Answer: c REF: Burns, Example 3.2(a), pg. 3-2

Section B: Normal, Emergency and Radiological Control Procedures Page 25 B.01 Answer: c REF: 10 CFR 55.53(e)

B.02 Answer: a REF: TS 5.3, pg. A-58 B.03 Answer: d REF: TS 1.34, pg. A-5 B.04 Answer: c REF: AP-RO-110, Section 6.3.1, pg. 10 B.05 Answer: a REF: 10 CFR 20.202 B.06 Answer: d REF: TS 6.7, pg. A-74 B.07 Answer: c REF: Emergency Plan, Section 9.8, pg. 22 B.08 Answer: b REF: TS 1.27, pg. A-5 B.09 Answer: a REF: 10 CFR 20.1208 (a)

Section B: Normal, Emergency and Radiological Control Procedures Page 26 B.10 Answer: c REF: 10 CFR 20.1004 Radiation Absorbed Exposure Quality Effective Dose dose (D) time factor (Q) equivalent (exposure time x D x Q)

Gamma 30 R/hr 20 min 1 30 R/hr x 1hr/60 min x 20 min x 1

= 10 rem Neutrons 9 R/hr 20 min 10 9 R/hr x 1hr/60 of min x 20 min x unknown 10 = 30 rem energy Total 10 rem + 30 rem absorbed = 40 rem exposure:

B.11 Answer: b REF: DR1d12 = DR2d22 100 mR/hr x (12 m)2 = DR2 x (4 m)2 DR2 = 900 mR/hr B.12 Answer: b REF: TS 3.8, pg. A-32 B.13 Answer: a REF: Emergency Plan, Section 2.1, pg. 4 B.14 Answer: d REF: Emergency Plan, Section 5.1.5, 5.2.5, 5.3.5, pg. 13-15 B.15 Answer: b and d (Per Facility Suggestion)

REF: Emergency Plan, Section 2.3, pg. 6 and Figure II, pg. 7 B.16 Answer: a REF: Emergency Plan, Table I, pg. 26

Section B: Normal, Emergency and Radiological Control Procedures Page 27 B.17 Answer: a REF: REP-RO-100, Rev. 20, REP-5, pg. 9 B.18 Answer: a REF: AP-RO-135, Introduction, pg. 3 & Attachment 9.2, pg. 1 of 2 B.19 Answer: a REF: FM-11, pg. 1 and 2 B.20 Answer: c REF: FM-57 NOTE, pg. 1 of 6 & FM-58 NOTE, pg. 1 of 1

Section C: Facility and Radiation Monitoring Systems Page 28 C.01 Answer: c REF: MURR Operations Training Manual, pg. 4-5B C.02 Answer: c REF: MURR Operations Training Manual, pg. 2-4A C.03 Answer: d REF: MURR Operations Training Manual, pg. 2-9B, 3-9B C.04 Answer: b REF: MURR Operations Training Manual, pg. 1-8C C.05 Answer: b REF: MURR Operations Training Manual, pg. 1-9E C.06 Answer: a,3 b,1 c,4 d,2 REF: TS 3.3h, pg. A-22 FM-20, pg. 1 of 1 SAR 16.1.4, pg. 16-5 MURR Operations Training Manual, pg. 2-6C C.07 Answer: c REF: OP-RO-210, Section 5.1 NOTE, pg. 5 C.08 Answer: c REF: MURR Operations Training Manual, pg. 2-2A C.09 Answer: a REF: MURR Operations Training Manual, pg. 2-2B C.10 Answer: d REF: MURR Operations Training Manual, pg. 2-3A C.11 Answer: c REF: MURR Operations Training Manual, pg. 2-3B

Section C: Facility and Radiation Monitoring Systems Page 29 C.12 Answer: b REF: TS 4.3 b, pg. A-45 C.13 Answer: b REF MURR Operations Training Manual, pg. 1-4A & 2-4A C.14 Answer: c REF: MURR Operations Training Manual, pg. 1-4E, 2-4E & 1-4F C.15 Answer: a REF: MURR Operations Training Manual, pg. 1-5A C.16 Answer: d REF: MURR Operations Training Manual, pg. 2-5D C.17 Answer: A,2 B,7 C,6 D,3 REF: MURR Operations Training Manual, pg. 1-8A C.18 Answer: b REF: MURR Operations Training Manual, pg. 2-8B C.19 Answer: d REF: MURR Operations Training Manual, pg. 2-8C C.20 Answer: c REF: MURR Operations Training Manual, pg. 1-9A, 2-9A, 3-9A, 10-9A, 12-9A