ML14114A496

Examination Report No. 50-186/OL-14-02, University of Missouri Research Reactor

ML14114A496
Person / Time
Site:	University of Missouri-Columbia
Issue date:	05/08/2014
From:	Gregory Bowman Research and Test Reactors Branch B
To:	Rhonda Butler Univ of Missouri - Columbia
J Nguyen, 301-415-4007
Shared Package
ML14008A307	List: ML14008A292 ML14114A496
References
50-186/14-02 50-186/OL-14
Download: ML14114A496 (25)

Text

May 8, 2014 Mr. Ralph A. Butler, Chief Operating Officer Research Reactor Facility University of Missouri Columbia, MO 65211

SUBJECT:

EXAMINATION REPORT NO. 50-186/OL-14-02, UNIVERSITY OF MISSOURI - COLUMBIA

Dear Mr. Butler:

During the week of April 14, 2014, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your University of Missouri - Columbia reactor. The examinations were conducted according to NUREG-1478, Operator Licensing Examiner Standards for Research and Test Reactors, Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

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

Sincerely,

/RA/

Gregory T. Bowman, 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-14-02

2. Written examination cc: John Fruits, Reactor Manager of Operations cc w/o enclosures: See next page

Mr. Ralph A. Butler, Chief Operating Officer Research Reactor Facility University of Missouri Columbia, MO 65211

SUBJECT:

EXAMINATION REPORT NO. 50-186/OL-14-02, UNIVERSITY OF MISSOURI - COLUMBIA

Dear Mr. Butler:

During the week of April 14, 2014, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your University of Missouri - Columbia reactor. The examinations were conducted according to NUREG-1478, Operator Licensing Examiner Standards for Research and Test Reactors, Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

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

Sincerely,

/RA/

Gregory T. Bowman, 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-14-02

2. Written examination cc: John Fruits, Reactor Manager of Operations cc w/o enclosures: See next page DISTRIBUTION:

PUBLIC PRTB r/f RidsNrrDprPrta RidsNrrDprPrtb Facility File (CRevelle) O-07 F-08 ADAMS ACCESSION #: ML14114A496 NRR-079 OFFICE PRTB:CE IOLB:OLA PRTB:BC NAME JNguyen CRevelle GBowman DATE 4/29/2014 5/06/2014 5/08/2014 OFFICIAL RECORD COPY

University of Missouri-Columbia Docket No. 50-186 cc:

John Ernst, Associate Director Health and Safety Research Reactor Facility 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 930 Wildwood Drive, 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-14-02 FACILITY DOCKET NO.: 50-186 FACILITY LICENSE NO.: R-103 FACILITY: University of Missouri-Columbia EXAMINATION DATES: April 14 - April 17, 2014 SUBMITTED BY: __________/RA/_________ _04/29/2014 John T. Nguyen, Chief Examiner Date

SUMMARY

During the week of April 14, 2014, the NRC administered operator licensing examinations to three Reactor Operator (RO), two Senior Reactor Operator Upgrade (SROU), and one Senior Reactor Operator Instant (SROI) candidates. The candidates passed all portions of the examinations.

REPORT DETAILS

1. Examiners: John T. Nguyen, Chief Examiner, NRC

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 3/0 1/0 4/0 Operating Tests 3/0 3/0 6/0 Overall 3/0 3/0 6/0

3. Exit Meeting:

Les Foyto, Associate Director - Reactor & Facility Operations John Fruits, Reactor Manager Bruce Meffert, Assistant Reactor Manager - Training Carl Herbold, Assistant Reactor Manager - Operations John T. Nguyen, Chief Examiner, NRC At the conclusion of the site visit, the examiner met with representatives of the facility staff to discuss the results of the examinations. The examiner thanked the facility for their support of the examination.

ENCLOSURE 1

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

Columbia REACTOR TYPE: Tank DATE ADMINISTERED: 4/15/2014 CANDIDATE: _______________________

INSTRUCTIONS TO CANDIDATE:

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

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 20.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.3 C. FACILITY AND RADIATION MONITORING SYSTEMS 60.00  % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

______________________________________

Candidate's Signature ENCLOSURE 2

A. RX THEORY, THERMO & FAC OP CHARS ANSWER SHEET Multiple Choice (Circle or X your choice)

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

A01 a b c d ___

A02 a b c d ___

A03 a b c d ___

A04 a b c d ___

A05 a b c d ___

A06 a b c d ___

A07 a b c d ___

A08 a b c d ___

A09 a b c d ___

A10 a b c d ___

A11 a b c d ___

A12 a b c d ___

A13 a b c d ___

A14 a b c d ___

A15 a b c d ___

A16 a b c d ___

A17 a b c d ___

A18 a b c d ___

A19 a b c d ___

A20 a b c d ___

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

B. NORMAL/EMERG PROCEDURES & RAD CON ANSWER SHEET Multiple Choice (Circle or X your choice)

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

B01 a b c d ___

B02 a ___ b ___ c ___ d ___ (0.25 each)

B03 a b c d ___

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 ___ (0.25 each)

B14 a b c d ___

B15 a b c d ___

B16 a b c d ___

B17 a b c d ___

B18 a b c d ___

B19 a b c d ___

B20 a b c d ___

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

C. PLANT AND RAD MONITORING SYSTEMS ANSWER SHEET Multiple Choice (Circle or X your choice)

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

C01 a b c d ___

C02 a b c d ___

C03 a b c d ___

C04 a b c d ___

C05 a b c d ___

C06 a ___ b ___ c ___ d ___ (0.25 each)

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.

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

EQUATION SHEET Q = m c p T = m H = UA T ( - )2 P max = * -4

= 1 x 10 seconds 2 (k)

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

SCR =

1 - K eff eff = 0.1 sec -1

SUR = 26.06 eff

- 1 - K eff 0 1 M= M= = CR2 1 - K eff 1 1 - K eff CR1 P = P0 10 SUR(t) P = P0 e t

(1 - )

P= P0

-

(1 - K eff ) * -

SDM = = =

+

-

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

T=

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

DR = DR0 e- t DR = 2 R

eff = 0.1/sec 2

( 2 - )2 ( 1 - )

=

Peak 2 Peak 1

1 Curie = 3.7x1010 dps 1 kg = 2.21 lbm 1 hp = 2.54x103 BTU/hr 1 Mw = 3.41x106 BTU/hr 1 BTU = 778 ft-lbf EF = 9/5EC + 32 931 Mev = 1 amu EC = 5/9 (EF - 32)

Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.1 [1.0 point]

Reactor is stabilized at 100 watts. Keff and respectively are:

a. 0 and 0

b. 0 and 1

c. 1 and 0

d. 1 and 1 QUESTION A.2 [1.0 point]

You're increasing reactor power on a steady + 26 second period. How long will it take to increase power by a factor of 1000?

a. 1 minute

b. 3 minutes

c. 5 minutes

d. 180 minutes QUESTION A.3 [1.0 point]

The following shows part of a decay chain for the radioactive element Pa-234.

234 91 Pa 92 U 234 This decay chain is a good example of ___ decay.

a. Alpha

b. Beta

c. Gamma

d. Neutron

Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.4 [1.0 point]

A subcritical nuclear reactor has a count rate of 300 cps with a shutdown reactivity of 2.0%

K/K. Approximately how much positive reactivity must be added to establish a count rate of 600 cps?

a. 0.40% K/K

b. 1.03% K/K

c. 1.40% K/K

d. 1.62% K/K QUESTION A.5 [1.0 point]

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

a. the shutdown margin

b. the value

c. 1.0 % K/K

d. the -effective value QUESTION A.6 [1.0 point]

Reactor A with a Keff of 0.1 and reactor B with a Keff of 0.8, Keff is increased by 0.1 for each reactor. The amount of reactivity added in reactor A is ______ in reactor B for the same increment.

a. less than

b. same

c. eight times

d. thirty-six times

Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.7 [1.0 point]

Which ONE of the following best describes the effects of moderator temperature decrease on neutron multiplication?

a. Fast non-leakage probability ; Thermal non-leakage probability ; Rod worth

b. Fast non-leakage probability ; Thermal non-leakage probability ; Rod worth

c. Fast non-leakage probability ; Thermal non-leakage probability ; Rod worth

d. Fast non-leakage probability ; Thermal non-leakage probability ; Rod worth QUESTION A.8 [1.0 point]

Which ONE of the following best describes the likelihood of fission reactions occurring in U-235 and U-238?

a. Neutron cross sections of U-235 and U-238 are independent in the neutron energy.

b. Neutron cross section of U-235 increases with increasing neutron energy, whereas neutron cross section of U-238 decreases with increasing neutron energy.

c. Neutrons at low energy levels (eV) are more likely to cause fission with U-238 than neutrons at higher energy levels (MeV).

d. Neutrons at low energy levels (eV) are more likely to cause fission with U-235 than neutrons at higher energy levels (MeV).

QUESTION A.9 [1.0 point]

If the mean generation time for neutrons in a reactor is 0.1 sec and k = 1.001, the time for the power to double is:

a. 9 seconds

b. 69 seconds

c. 100 seconds

d. 180 seconds

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

A few minutes following a reactor scram, the reactor period has stabilized and the power level is decreasing at a CONSTANT rate. Given that reactor power at time tconstant is 200 kW power, what will it be five minutes later?

a. 0.5 kW

b. 2.3 kW

c. 4.7 kW

d. 110.0 kW QUESTION A.11 [1.0 point]

Which ONE of the following best describes the MAJOR contributor to the production and depletion of Xenon at 500 kW power?

Xe-135 MAJORLY produced by Xe-135 MAJORLY depleted by

a. Directly from fission Neutron absorption

b. Directly from fission Radioactive Decay

c. Radioactive decay of Iodine Neutron absorption

d. Radioactive decay of Cesium Radioactive Decay QUESTION A.12 [1.0 point]

The following data was obtained during a reactor fuel load.

Step No. of Elements Detector A (count/sec) 1 0 100 2 4 120 3 8 140 4 12 200 5 15 400 The estimated number of additional elements required to achieve criticality is:

a. 2

b. 3

c. 4

d. 6

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

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

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

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

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

d. The fission cross section of the fuel is much higher for thermal energy neutrons than fast neutrons.

QUESTION A.14 [1.0 point]

Which ONE of the following core arrangements (I through IV) would likely provide the most accurate fuel loading for the 1/M plot?

I. II.

III.

IV.

a. I

b. II

c. III

d. IV

Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.15 [1.0 point] Change made during administration of the examination The reactor is operating in the automatic mode at 1 MW with the regulating rod at 8 inches. A malfunction of equipment in the secondary cooling system causes primary temperature to increase by 10 °C. Disregarding any other automated system design features, the new position of the regulating rod is between:

a. 7.00 - 7.20 inches

b. 8.00 - 9.50 9.25 inches

c. 9.50 9.75 - 10.50 inches

d. 10.75 - 11.25 inches Given the temperature coefficient =- 0.04 %K/K per °C See the curve as follows:

Section A L Theory, Thermo & Fac. Operating Characteristics

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

Which ONE of the following best describes the difference between a moderator and reflector?

a. A reflector will increase the fast non-leakage factor whereas a moderator increases the thermal utilization factor.

b. A reflector will increase the fast non-leakage factor whereas a moderator decreases the thermal utilization factor.

c. A reflector will decrease the fast non-leakage factor whereas a moderator increases the thermal utilization factor.

d. A reflector will decrease the fast non-leakage factor whereas a moderator decreases the thermal utilization factor.

QUESTION A.17 [1.0 point]

Which ONE of the following describes the difference between prompt and delayed neutrons?

Prompt neutrons

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

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

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

d. are the dominating factor in determining reactor period, while delayed neutrons have little effect on reactor period.

QUESTION A.18 [1.0 point]

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

a. Lowering moderator temperature (assume negative temperature coefficient)

b. Insertion of a positive reactivity worth experiment

c. Burnout of a burnable poison

d. Fuel depletion

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

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

a. 1 b.

b. 2

c. 3

d. 4 QUESTION A.20 [1.0 point]

Reactor is at 100 % power. The following graph shows the reactor time behavior following a reactor scram. Which ONE of the following best describes the transition of power between point A and B after the initial insertion? .

a. An immediate decrease in the prompt neutron fraction due to leakage, absorption, and a reduction in the fission rate.

b. Fission product gases such as xenon begin to buildup causing the expansion of fuel density

c. The longest lived delayed neutron precursor begins to effect

d. The short lived delayed neutron precursors begin to effect

Section A L Theory, Thermo & Fac. Operating Characteristics

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

Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.1 [1.0 point]

Before depressing Rod Run-In or Scram push button for a normal shutdown, you should:

a. SET Intermediate Range Monitor Level Recorder to FAST speed and START Source Range Monitor Level Recorder and Scaler.

b. SET Intermediate Range Monitor Level Recorder to FAST speed and STOP Source Range Monitor Level Recorder and Scaler.

a. SET Intermediate Range Monitor Level Recorder to SLOW speed and START Source Range Monitor Level Recorder and Scaler.

a. SET Intermediate Range Monitor Level Recorder to SLOW speed and STOP Source Range Monitor Level Recorder and Scaler.

QUESTION B.2 [1.0 point. 0.25 each]

Match the annual dose limit values to the type of exposure.

Type of Exposure Annual Dose Limit Value

a. Extremities 1. 0.1 rem.

b. Lens of the Eye 2. 5.0 rem.

c. Occupational Total Effective Dose Equivalent (TEDE) 3. 15.0 rem.

d. TEDE to a member of the public 4. 50.0 rem.

QUESTION B.3 [1.0 point]

An unshielded source reads 300 mr/hr at 100 cm. You store it in a lead pig and perform a survey. It reads 200 mr/hr on contact, and 10 mr/hr at 100 cm. If a shielded source is stored in a lead pig, how do you post this area with your justification?

a. Very High Radiation Area because an unshielded source reads 3333 mr/hr at 30 cm

b. High Radiation Area because a shielded source reads 200 mr/hr on contact

c. High Radiation Area because a shielded source reads 111 mr/hr at 30 cm from the lead pig

d. Radiation Area because a shielded source reads 10 mr/hr at 100 cm from the lead pig

Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.4 [1.0 point]

An unshielded source has a dose rate of 1 Rem/hr. What is the actual dose rate if shielded by 1/2 inch lead?

Given:

Lead density: 11.35 g/cm3 Lead Mass Attenuation Coefficient: 0.0708 cm2/g 1 in = 2.54 cm

a. 181 mrem/hr

b. 362 mrem/hr

c. 742 mrem/hr

d. 914 mrem/hr QUESTION B.5 [1.0 point]

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

a. 10 CFR Part 20

b. 10 CFR Part 50.59

c. 10 CFR Part 55

d. 10 CFR Part 73 QUESTION B.6 [1.0 point]

You conduct a facility tour for the U.S. President. The reactor is operating at a certain power level and the area radiation monitor near the President reads 5 mrem/hr. How long can the President stay before he exceeds his 10 CFR 20 limit?

a. 50 hrs

b. 20 hrs

c. 10 hrs

d. 2 hrs

Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.7 [1.0 point]

A biennial test of the nuclear instrument was performed. When is the latest the test must be performed again?

a. 8 months after

b. 24 months after

c. 26 months after

d. 28 months after QUESTION B.8 [1.0 point]

Which ONE of the following will be violate the Limiting Safety System Settings in MODE I operation?

a. Primary Coolant Flow of 1800 gpm

b. Inlet Water Temperature of 150 °F

c. Pressurizer Pressure of 70 Psia

d. Reactor Power of 10 MW QUESTION B.9 [1.0 point]

During the normal steady state power, a complete set of Process Data will be taken every:

a. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

b. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

c. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

d. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />

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

During a reactor operation, a small fire occurs in the reactor console. Which ONE of the following classes of extinguisher would most likely be used with this type of fire?

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

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

c. Class C: Fires in live electrical equipment.

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

Each fuel experiment shall be limited such that the maximum strontium-90 inventory is no greater than ______?

a. 150 millicuries

b. 300 millicuries

c. 150 curies

d. 300 curies QUESTION B.12 [1.0 point]

Attached is the gas-filled detector curve (detector effect vs. voltage). Different regions of this curve are useful for different detectors. Which ONE of the following is the Geiger Mueller region?

a. II

b. III

c. IV

d. V

Section B Normal/Emergency Procedures and Radiological Controls

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

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

Column A Column B

a. Absolute value of all experiments in 1. 0.0010 K center test hole

b. Core Excess Reactivity 2. 0.0025 K

c. Reactivity worth of each secured 3. 0.006 K removable experiment

d. Removable parts of any 4. 0.0980 K/k individual experiment QUESTION B.14 [1.0 point]

What is the MINIMUM level of management who may authorize minor changes to the MURR Technical Specifications such as corrections of typographical errors that do NOT changes their original intent?

a. Senior Reactor Operator

b. Lead Senior Reactor Operator

c. Reactor Manager

d. This change requires the NRC approval QUESTION B.15 [1.0 point]

You follow the Standing Order Guidance related to electrical breakers. This Standing Order will remain in effect until:

a. you complete verifying the electrical breakers are functional

b. cancelled by the Lead Senior Reactor Operator

c. cancelled by the Reactor Manager

d. cancelled by the Reactor Director

Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.16 [1.0 point] Change made during administration of the examination A system or component is defined as "OPERATING OPERABLE by Technical Specifications when:

a. a system was calibrated recently

b. a reactor is in the operational Mode I

c. it is capable of performing its intended function

d. a system is operational when reactor is NOT secured QUESTION B.17 [1.0 point]

Per MURR Emergency Plan, the individual authorized to terminate an emergency and initiating recovery action is the:

a. U.S. NRC Emergency Operation Coordinator

b. Radiation Safety Officer

c. Campus Police Chief

d. Emergency Director QUESTION B.18 [1.0 point]

A radioactive source reads 10 Rem/hr on contact. Five hours later, the same source reads 5.0 Rem/hr. How long is the time for the source to decay from a reading of 10 Rem/hr to 50 mRem/hr?

a. 9.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />

b. 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br />

c. 38 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br />

d. 47 hours5.439815e-4 days <br />0.0131 hours <br />7.771164e-5 weeks <br />1.78835e-5 months <br />

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

The siphon break system pressure will be verified, recorded, and readjusted as required every

_______ as part of the facility routine patrol.

a. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

b. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

c. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

d. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> QUESTION B.20 [1.0 point]

In the event of an accident involving personnel injury and potential radiological contamination, which ONE of the following is the correct treatment facility by the MURR E-Plan used?

a. UMC Police Station

b. UMC Radiation Safety Office

c. Columbia Fire Department Station

d. University of Missouri Hospital and Clinics

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

Section C Facility and Radiation Monitoring Systems QUESTION C.1 [1.0 point]

Reactor is in operation. The BRIDGE Radiation Monitor System (ARMS) changes from normal to a failure mode. Its failure mode will cause:

a. The reactor is initiated the rod run-in

b. The Evacuation Relays (R3A & R3B) are tripped

c. The containment building exhaust isolation valves 16A and 16B remain in the open mode

d. Warning light at the entrance to the containment building personnel airlock will illuminate QUESTION C.2 [1.0 point]

Which ONE of the following is the method used to CONTINUOUSLY sample air for the MURR stack gas monitor?

a. Instrumental Reference Method

b. Evacuated Bottle Method

c. Anisokinetic Method

d. Isokinetic Method QUESTION C.3 [1.0 point]

Which ONE of the following correctly describes the function of an INVERTER in the Uninterruptible Power Supply (UPS) system?

a. Switch the electrical power from the normal source to the Emergency Power source during a loss of electrical power.

b. Covert DC from the battery bank to a step-like AC. This AC signal is then sent to the Static Switch for distribution of the UPS loads during a loss of electrical power.

c. Step down 480-V three-phase AC to 120-V single phase AC. This 120-V AC signal is sent to the Static Switch for distribution of the UPS loads during a loss of electrical power.

d. Covert alternating current (AC) from the Emergency Distribution to direct current (DC).

This DC signal is then sent in parallel to the inverter and a float charge of the battery bank.

Section C Facility and Radiation Monitoring Systems QUESTION C.4 [1.0 point]

The emergency pool fill system is required to admit water to the pool at a MINIMUM flow rate of

__________ gpm.

a. 100

b. 500

c. 1000

d. 2000 QUESTION C.5 [1.0 point]

Which ONE statement below describes the operation of the three-way solenoid valve of the Primary Demineralizer Inlet (527 E&F)? During normal operation, the solenoid valve is:

a. energized; the exhaust port is closed, and air is continuously supplied to the actuator

b. de-energized; the supply port is closed, and air from the actual port is vented through the exhaust port

c. energized; the supply port is closed, and no air flows in exhaust port nor the actuator

d. de-energized; the exhaust port is opened and air is continuously supplied to the exhaust port QUESTION C.6 [1.0 point]

The following diagram depicts the Off-Gas Radiation Monitoring System. Match the locations of radiation detectors in column A with its detection in column B. Items in column B can be used once, more than once or not at all.

Column A Column B

a. Particulate (Phosphor Scintillation 1. alpha Detector)

b. Particulate (ZnS Detector) 2. beta

c. Iodine (NaI Detector) 3. gamma

d. Gas (Phosphor Scintillation Detector) 4. neutron

Section C Facility and Radiation Monitoring Systems

Section C Facility and Radiation Monitoring Systems QUESTION C.7 [1.0 point]

The GREEN leg signal of the Safety System is disconnected to the non-coincidence logic unit (NCLU) B. This action will :

a. de-energize only 1K8 relay; and cause rod run-in A/ B

b. de-energize only 2K21 relay; and scram rod C/ rod D

c. de-energize 2K20 and 2K21 relays; and scram rod A / B/ C/ D

d. de-energize 1K8 and1K9 relays; and cause rod run-in A / B /C/ D QUESTION C.8 [1.0 point]

Reactor is in the Mode II operation. Which ONE of the following conditions considers a NORMAL operation?

a. Anti-siphon system pressure is 34 psig

b. Vent Tank Low Level is 1 foot below centerline

c. Primary Coolant System pressure is 120 psig

d. Anti-siphon System Level is 10 inches above valves QUESTION C.9 [1.0 point]

Just prior to withdrawing control rods with all process control systems on line, the Master Control Switch (1S1) is taken from the ON position to the OFF position. Which ONE of the following conditions will result?

a. All systems will shut down

b. All systems will remain running, but without automatic operation

c. The system is mechanically interlocked and you cannot move 1S1 to the off position with all systems running

d. All systems will remain running with all automatic functions operable

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

Reactor is in Mode I operation. You, a Senior Reactor Operator, calculate a secondary heat balance of 11 MW. Which ONE of the following is your proper action?

a. You may continue the reactor operation and start investigating the result

b. You may continue the reactor operation and inform the result to Lead Senior Reactor Operator

c. You reduce the reactor power to Mode II operation and recalculate the heat balance

d. You immediately shut down the reactor and inform the result to Lead Senior Reactor Operator QUESTION C.11 [1.0 point]

Reactor is in Mode I operation. Which ONE of the following describes the status of reactor coolant systems when reactor pressure PT 944A decreases to a critical level?

a. The isolation valves (V507A&B) CLOSE; Anti-Siphon valves (543 A&B) OPEN; primary coolant pumps (501 A&B) OFF.

b. The isolation valves (V507A&B) OPEN; Anti-Siphon valves (543 A&B) OPEN; primary coolant pumps (501 A&B) OFF.

c. The isolation valves (V507A&B) CLOSE; Anti-Siphon valves (543 A&B) CLOSE; primary coolant pumps (501 A&B) OFF.

d. The isolation valves (V507A&B) CLOSE; Anti-Siphon valves (543 A&B) OPEN; primary coolant pumps (501 A&B) ON.

QUESTION C.12 [1.0 point]

Which ONE of the following best describes the purpose of the Nitrogen System?

The purpose of the Nitrogen System is to provide a reliable and regulated source of nitrogen to:

a. the Heat Exchanger System, for use in cooling the overheated Heat Exchanger

b. the Pressurizer System, for use in maintaining Primary Coolant System pressure

c. the Reactor Vessel, for use in cooling the reactor fuel in case of emergency

d. the Pneumatic Transfer System, for use in transporting rabbit tubes

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

Which ONE of the following locations does NOT provide the reactor coolant temperature meter?

a. Between Isolation Valve 507 A and Pump 501 B

b. Between Pump 501A and Heat Exchanger 503A

c. Between Heat Exchanger 503B and Isolation Valve 507B

d. Between Heat Exchanger 503A and Isolation Valve 507B QUESTION C.14 [1.0 point]

Reactor is at 10 MW power. Which ONE of the following indications considers an abnormal operation?

a. Primary Coolant Flow 3800 gpm

b. Inlet Water Temperature 121 °F

c. Pressurizer Pressure 85 Psia

d. Outlet Water Temperature 174 °F QUESTION C.15 [1.0 point]

The compensated Ion Chamber (CIC) detector provides a signal input for the:

a. Power Range Monitor 6 (PRM 6) that provides a scram

b. Intermediate Range Monitor (IRM 2) that provide a scram

c. Source Range Monitor (SMR1) that provides a Rod Run-In

d. Wide Range Monitor (WRM) that provides an input for auto control

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

To prevent the inadvertent trip of the operating facility exhaust fan, a maximum number of quadrant isolation damper permitted to be shut at a time is:

a. 1

b. 2

c. 3

d. 4 QUESTION C.17 [1.0 point]

Which ONE of the following describes on how the automatic control operates?

a. The output of the Source Range Monitor is delivered to the Servo Amplifier, which senses the error between the reactor power and the power demand set point, and actuates relays which cause the movement of the regulating rod.

b. The output of the Power Range Monitor is delivered to the Pre-Amplifier, which senses the error between the reactor power and the power demand set point, and actuates relays which cause the movement of the regulating rod.

c. The output of the Intermediate Range Monitor is delivered to the Pre-Amplifier, which senses the error between the reactor power and the power demand set point, and actuates relays which cause the movement of the regulating rod.

d. The output of the Wide Range Monitor is delivered to the Servo Amplifier, which senses the error between the reactor power and the power demand set point, and actuates relays which cause the movement of the regulating rod.

QUESTION C.18 [1.0 point]

The normal path for adding water to the pool is by way of gravity drain from either demineralized water tank to:

a. a diffuser header located about a foot below the normal fill line

b. a garden hose located at the top of the reactor pool

c. the suction of the pool coolant system pump

d. the suction of the pool skimmer pump

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

Which ONE of the following is NOT a feature of the pneumatic tube system designed to limit the radiation hazard?

a. A time delay starts the east p-tube blower approximately 15 seconds after the west p-tube blower

b. Facility exhaust fan system prevents stagnant air in the vicinity of the rabbit system

c. Speed at which the sample container is transported through the system

d. Double encapsulation of samples QUESTION C.20 [1.0 point]

Reactor is at 5 MW power in Auto Mode. You accidently depress the Rod Control Mode MAN Switch S1-2, your action will cause:

a. Scram

b. Rod Run-In

c. Terminate the Auto Mode

d. Normal operation/ no effect to the Auto Mode

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

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

Section A L Theory, Thermo & Fac. Operating Characteristics A.1 Answer: a

Reference:

Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 4.2 A.2 Answer: b

Reference:

Burn, R., Introduction of Nuclear Reactor Operations, © 1988 ln (P/P0) x period = time, ln(1000) x 26 = 6.908 x 26 = 179.6 180 seconds = 3 min.

A.3 Answer b

Reference:

Chart of the Nuclides A.4 Answer: b

Reference:

First, find Keff1 with = -2.0% K/K (shutdown: negative reactivity)

( K eff - 1)

=

K eff

-0.02 Keff1 = Keff1 -1 so 1.02 Keff1 = 1 Keff1 = 0.980 CR2(1 - Keff2) = CR1 (1 - Keff1) 600/300 = (1 - 0.980)/(1 - Keff2)

Then find: Keff2 = 0.990

= (Keff2-Keff1)/(Keff1*Keff2) = (0.990-0.980)/(0.990*0.98) = 1.03% K/K A.5 Answer: d

Reference:

Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 4.6 b cannot be a correct answer because < -effective (finite)

A.6 Answer: d

Reference:

Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 3.3.3, page 3-21.

reactor A = (Keff1-Keff2)/(Keff1*Keff2). (0.2-0.1)/(0.2*0.1) = 5 k/k reactor B = (Keff1-Keff2)/(Keff1*Keff2). (0.9-0.8)/(0.9*0.8) = 0.139 k/k 5/0.139 = 36 A.7 Answer: c

Reference:

Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 3.3.2 A.8 Answer: d

Reference:

Burn, R., Introduction to Nuclear Reactor Operations, © 1988, Section 3.2

Section A L Theory, Thermo & Fac. Operating Characteristics A.9 Answer: b

Reference:

Period T = l*/

= k-1/k = 0.001 T = 0.1 /0.001 = 100 N = Noet/T 2 = et/100 0.693 = t/100 t = 69.3 seconds A.10 Answer: c

Reference:

P = P0 e-T/ = 200 kW e(300sec/-80sec) = 200 kW e-3.75 = 0.0235 200 kW = 4.7 KW A.11 Answer: c

Reference:

Burn, R., Introduction to Nuclear Reactor Operations, © 1988, Section 8.2 A.12 Answer: b

Reference:

Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 5.5, page 5-18-5-25.

A.13 Answer: d

Reference:

Burn, R., Introduction of Nuclear Reactor Operations, © 1982, Figure 2.6, page 2-39 A.14 Answer: c

Reference:

Burn, R., Introduction to Nuclear Reactor Operations, Section 5.5, 1988 A.15 Answer: b

Reference:

The temperature increase has added -0.40% K/K of reactivity which must be accounted for by the regulating rod to maintain 1 MW. Therefore, the Reg rod must be withdrawn 0.40% K/K worth. Using the integral rod worth curve, with the Reg rod initially at 8 in (1.30 % K/K), the new rod height at 1.70 % K/K is 9.25 in.

A.16 Answer: a

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2, Module 4, Reactor Theory (Reactor Operations), pp. 25-26 A.17 Answer: c

Reference:

Burn, R., Introduction to Nuclear Reactor Operations, © 1988

Section A L Theory, Thermo & Fac. Operating Characteristics A.18 Answer: d

Reference:

decreasing the reactivity worth in the core will increase the shutdown margin.

A.19 Answer: b

Reference:

Nuclides and Isotopes N=A-Z 3-1 = 2 A.20 Answer: d

Reference:

Burn, R., Introduction to Nuclear Reactor Operations, ©4.5, 1988 a cannot be a correct answer, it describes a prompt drop.

Section B Normal/Emergency Procedures and Radiological Controls B.1 Answer: a

Reference:

OP-RO-220, Section 5.1 B.2 Answer: a, 4; b, 3; c, 2; d, 1

Reference:

10 CFR 20 B.3 Answer: c

Reference:

10 CFR 20. 10 mR/hr (100 cm) 2 = X * (30 cm) 2 X = 111 mR/hr at 30 cm B.4 Answer: b

Reference:

and Solving for µ= x = (0.0708 cm2/g ) x (11.35 g/cm3) = 0.8 cm-1 x = 0.5 inches x 2.54 cm/in = 1.27 cm I = 1 Rem/hr

• exp(-1.27*0.8) = 362 mRem/hr B.5 Answer: c

Reference:

10 CFR 55 B.6 Answer: b

References:

100 mrem dose limit to members of the public (10 CFR 20)

B.7 Answer: c

Reference:

TS Section 1.2 B.8 Answer: c

Reference:

TS Section 2.2 B.9 Answer: b

Reference:

AP-RO-110 B.10 Answer: c

Reference:

NRC standard question

Section B Normal/Emergency Procedures and Radiological Controls B.11 Answer: b

Reference:

TS 3.6 B.12 Answer: d

Reference:

NRC standard question B.13 Answer: a, 3 b,4 c,3 d,1

Reference:

Technical Specifications 3.1 B.14 Answer: d

Reference:

Technical Specifications 6.1 (require an amendment)

B.15 Answer: c

Reference:

Standing Order 12-04 B.16 Answer: c

Reference:

Technical Specifications, Section 1 B.17 Answer: d

Reference:

Emergency Plan, 2.1 B.18 Answer: c

Reference:

DR = DR*e -t 5 rem/hr =10 rem/hr* e -(5hr)

Ln(5.0/10) = -*5 --> =0.1386; solve for t: Ln(.05/10)=-0.315 (t) t=38 hours B.19 Answer: c

Reference:

Technical Specifications, 3.9 B.20 Answer: d

Reference:

MURR E-Plan

Section C Facility and Radiation Monitoring Systems C.1 Answer: d

Reference:

MURR Reactor Operations Training Manual, Reactor Isolation and Facility Evacuation C.2 Answer: d

Reference:

MURR Reactor Operations Training Manual, Stack Monitor C.3 Answer: b

Reference:

MURR Reactor Operations Training Manual, UPS System C.4 Answer: c

Reference:

MURR TS 3.10.c C.5 Answer: b

Reference:

MURR Reactor Operations Training Manual, Valve Operating System C.6 Answer: a, 2 b,1 c,3 d,2

Reference:

MURR Reactor Operations Training Manual, Stack Monitor - Eberline C.7 Answer: c

Reference:

MURR Reactor Operations Training Manual, Safety System and Rod Run-In System C.8 Answer: a

Reference:

MURR TS 3.4 C.9 Answer: d

Reference:

SAR, Chapter 7 -Instrumentation and Control Systems C.10 Answer: d

Reference:

SOP AP-RO-110, Section 6.7 C.11 Answer: a

Reference:

MURR Reactor Operations Training Manual, Primary Coolant Loop

Section C Facility and Radiation Monitoring Systems C.12 Answer: b

Reference:

MURR Reactor Operations Training Manual, Nitrogen System C.13 Answer: b

Reference:

MURR Reactor Operations Training Manual, Primary Coolant Loop C.14 Answer: d

Reference:

AP-RO-110 and TS 3.3 (not violate TS LCO, but exceed the procedure limit setting)

C.15 Answer: d

Reference:

MURR Reactor Operations Training Manual, Nuclear Instrumentation C.16 Answer: a

Reference:

OP-RO-730, Section 3.5 C.17 Answer: d

Reference:

MURR Training Manual, Nuclear Instrumentation, Wide Range Monitor C.18 Answer: d

Reference:

OP-RO-465 C.19 Answer: d

Reference:

Hazard Summary Report, Section 8.5 - Pneumatic Tubes SAR, Chapter 10.3.4 - Pneumatic Tube System C.20 Answer: c

Reference:

OP-RO-210