ML13316B663

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Examination Report, No. 50-186/OL-14-01, University of Missouri Columbia
ML13316B663
Person / Time
Site: University of Missouri-Columbia
Issue date: 11/19/2013
From: Gregory Bowman
Research and Test Reactors Licensing Branch
To: Rhonda Butler
Univ of Missouri - Columbia
Young P
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November 19, 2013 Mr. Ralph A. Butler, Chief Operating Officer Research Reactor Facility University of Missouri Columbia, MO 65211

SUBJECT:

EXAMINATION REPORT No. 50-186/OL-14-01, UNIVERSITY OF MISSOURI -

COLUMBIA

Dear Mr. Butler:

During the week of November 4, 2013, the NRC administered operator licensing examinations 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 (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Mr. Phillip T. Young at (301) 415-4094 or via internet e-mail phillip.young@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:

Examination Report No. 50-186/OL-14-01 cc: John Fruits, Assistant Reactor Manager of Operations cc w/o enclosures:

See next page

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

John Ernst, Associate Director Regulatory Assurance Group Research Reactor Facility Columbia, MO 65201 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

November 19, 2013 Mr. Ralph A. Butler, Chief Operating Officer Research Reactor Facility University of Missouri Columbia, MO 65211

SUBJECT:

EXAMINATION REPORT No. 50-186/OL-14-01, UNIVERSITY OF MISSOURI -

COLUMBIA

Dear Mr. Butler:

During the week of November 4, 2013, the NRC administered operator licensing examinations 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 (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Mr. Phillip T. Young at (301) 415-4094 or via internet e-mail phillip.young@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:

Examination Report No. 50-186/OL-14-01 cc: John Fruits, Assistant Reactor Manager of Operations cc w/o enclosures:

See next page DISTRIBUTION:

PRTB r/f RidsNrrDprPrta RidsNrrDprPrtb ADAMS ACCESSION NO.: ML13316B663 NRR-074 OFFICE NRR/DPR/PROB NRR/DPR/PROB NRR/DPR/PROB NAME PYoung CRevelle GBowman DATE 11/14/13 11/18/13 11/19/13 OFFICIAL RECORD COPY

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-186/OL-14-01 FACILITY DOCKET NO.: 50-186 FACILITY LICENSE NO.: R-103 FACILITY: University of Missouri - Columbia EXAMINATION DATES: November 4 -& 7, 2013 SUBMITTED BY: __________/RA/____________ _11/14/13___

Phillip T. Young, Chief Examiner Date

SUMMARY

During the week of November 4, 2013 the NRC administered licensing examinations to three RO applicants, one SRO-I applicant and two SRO-U applicants. All applicants passed all portions of these examinations.

REPORT DETAILS

1. Examiners: Phillip T. Young, 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:

Phillip T. Young, Chief Examiner, NRC Carl Herbold, Assistant Reactor Manager - Operations, MURR John L. Fruits, Reactor Manager, MURR Les Foyto, Associate Director Reactor & Facilities Operations, MURR The facility stated that they did not have any comments on the written examination. The examiner thanked the facility for their assistance in completing the examinations.

ENCLOSURE 1

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: UNIVERSITY OF MISSOURI - COLUMBIA REACTOR TYPE: Tank DATE ADMINISTERED: 11/05/2013 CANDIDATE: _____________________________

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheet provided. Attach the answer sheets to the examination. Points for each question are indicated in brackets for each question. A 70% in each section is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

% of Category % of Candidates 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

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.
13. When you have completed and turned in you examination, leave the examination area. If you are observed in this area while the examination is still in progress, your license may be denied or revoked.

EQUATION SHEETs

Q = m c p T = m H = UA T eff = 0.1 seconds -1 S S CR1 (1 - K eff 1 ) = CR 2 (1 - K eff 2 )

eff SCR =

SUR = 26.06 - 1 - K eff CR1 (- 1 ) = CR 2 (- 2 )

1 - K eff 0 1 M= CR1 1 - K eff 1 M= =

t 1 - K eff CR2 P = P0 10 SUR(t)

P = P0 e (1 - )

P= P0 (1 - K eff ) -

SDM = = = +

K eff eff

( K eff - 1)

K eff 2 - K eff 1 0.693 =

K eff k eff 1 x K eff 2 T

DR = DR0 e- t 6CiE(n)

DR = 2 2

DR 1 d 1 = DR 2 d 2 2

R DR - Rem, Ci - curies, E - Mev, R - feet 2

( 2 - )2 ( 1 - )

=

Peak 2 Peak 1 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 EF = 9/5 EC + 32 1 gal (H2O) . 8 lbm EC = 5/9 (EF - 32) cP = 1.0 BTU/hr/lbm/EF cp = 1 cal/sec/gm/EC

Section A Reactor Theory, Thermo, and Facility Characteristic Question A.001 [1.0 point] {1.0}

During a fuel loading of the core, as the reactor approaches criticality, the value of 1/M:

a. Increases toward one
b. Decreases toward one
c. Increases toward infinity
d. Decreases toward zero Answer: A.01 d.

Reference:

Module 4, Theory ( Operations), E.O. 1.4, pg. 7 and DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Volumes 1 and 2, January 1993.

Question A.002 [1.0 point] {2.0}

Which one of the following accurately details a factor contributing to Xenon balance within the reactor?

a. Most Xe135 is formed by fission.
b. Te135 is a fission product which quickly decays to I135.
c. Within approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after startup, Xe135 has reached its equilibrium value.
d. Several minutes following a reactor shutdown, Xe level is increasing because I135 is not being produced.

Answer: A.02 b.

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume X, Module Y, Enabling Objective Z.Z Question A.003 [1.0 point] {3.0}

Given a fuel temperature coefficient of -1.25 x 10-4 K/K/ C. When a control rod with an average worth of 0.1% K/K/inch is withdrawn 10 inches, reactor power increases and becomes stable at a higher level. At this point fuel temperature has (neglect power coefficient)

a. increased by 80 C
b. decreased by 80 C
c. increased by 8 C
d. decreased by 8 C Answer A.03 a.

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

Section A Reactor Theory, Thermo, and Facility Characteristics Question A.004 [1.0 point] {4.0}

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

a. Increase moderator temperature (Assume negative temperature coefficient)
b. Insertion of a negative reactivity worth experiment
c. Burnout of a burnable poison
d. Fuel depletion Answer: A.04 c.

Reference:

Standard NRC question Question A.005 [1.0 point] {5.0}

Reactor power is rising on a 30 second period. Approximately how long will it take for power to double?

a. 15 seconds
b. 21 seconds
c. 30 seconds
d. 60 seconds Answer A.05 b.

Reference DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, t/T P = P0 e -> ln (2) = time ÷ 30 sec -> time = ln (2) x 30 sec. 0.693 x 30 0.7 x 30 21 sec Question A.006 [1.0 point] {6.0}

Reactor power is increasing on a constant positive reactor period. Which ONE of the following power changes would finish in the shortest time?

a. 5% power - from 1% to 6%
b. 10% power - from 10% to 20%
c. 15% power - from 20% to 35%
d. 20% power - from 40% to 60%

Answer A.06 d.

Reference DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume

Section A Reactor Theory, Thermo, and Facility Characteristic Question A.007 [1.0 point] {7.0}

The Moderating Ratio measures the effectiveness of a moderator by combining the scattering cross section, the absorption cross section, and the average energy loss per collision. The Moderating Ratio is expressed as:

a. (absorption cross section)x(scattering cross section)/(average energy loss per collision).
b. (absorption cross section)x(average energy loss per collision)/(scattering cross section).
c. (scattering cross section)x(absorption cross section)x(average energy loss per collision).
d. (average energy loss per collision)x(scattering cross section)/(absorption cross section).

Answer A.07 d.

Reference DOE Fundamentals Handbook, Module 2, Neutron Moderation, page 28.

Question A.008 [1.0 point] {8.0}

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

a. reappears with a lower kinetic energy, with the nucleus emitting a gamma ray.
b. reappears with the same kinetic energy it had prior to the collision.
c. is absorbed by the nucleus, with the nucleus emitting a gamma ray.
d. reappears with a higher kinetic energy, with the nucleus absorbing a gamma ray.

Answer A.08 a.

Reference DOE Fundamentals Handbook, Module 1, Neutron Interactions, page 45.

Question A.009 [1.0 point] {9.0}

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

Prompt neutrons

a. account for less than 1% of the neutron population, while delayed neutrons account for the rest.
b. are released only during fast-fission events, while delayed neutrons are released during the decay process.
c. are released during the fission process (fast & thermal), 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.

Answer A.09 c.

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

Section A Reactor Theory, Thermo, and Facility Characteristics Question A.010 [1.0 point] {10.0}

To make a just critical reactor PROMPT CRITICAL, by definition you must add reactivity equal to

a. eff
b. eff
c. eff
d. Keff Answer A.10 c.

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory Volume 2, Module 4, Reactor Theory (Reactor Operations), Enabling Objective 2.8 Question A.011 [1.0 point] {11.0}

What is the period that would cause reactor power to double in 40 seconds?

a. 3.7 seconds
b. 27.7 seconds
c. 57.7 seconds
d. 80.0 seconds Answer A.11 c. P = P0 et/T ln(P/P0) = t/T T= t/ln(P/P0) T = 30 sec/(ln(2))

= 30/0.693 = 57.7 sec

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume X, Module Y, Enabling Objective Z.Z

Section A Reactor Theory, Thermo, and Facility Characteristic Question A.012 [1.0 point] {12.0}

A reactor has a moderator temperature coefficient of reactivity is 1.0 x 10-4 K/K/ C. If the average coolant temperature decreases by 10 C, a regulating rod with a differential rod worth of 0.05%K/K/inch must be ______________ to maintain the same power.

a. inserted 2 inches
b. withdrawn 2 inches
c. inserted 0.5 inches
d. withdrawn 0.5 inches Answer A.12 b.

Reference Burn, R., Introduction to Nuclear Reactor Operations, © 1988, § K K

10. x 104 x 10°C = +103 K °C K K K

+103 = 0.0005 x? Inches K K 103 KK

? Inches = = +2 inches (Withdrawn )

5 x104 KK Question A.013 [1.0 point] {13.0}

A reactor is subcritical with a Keff of 0.955. If you add 4.5% k/k of positive reactivity into the core, the reactor will be

a. subcritical
b. exactly critical
c. supercritical
d. prompt critical Answer A.13 a.

Reference DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2, Module 4, Reactor Theory (Reactor Operations), Enabling Objective 1.3 1 k eff 1 0.955 0.045 SDM = = = = 0.04712 If you add 0.045, the resultwillstill be 0.212% shutdown k eff 0.955 0.955

Section A Reactor Theory, Thermo, and Facility Characteristics Question A.014 [1.0 point] {14.0}

The PRIMARY reason that a neutron source is installed in the reactor is to

a. allow for testing and irradiation of experiments when the core is shutdown.
b. supply the neutrons required to start the chain reaction for subsequent reactor startups.
c. provide a neutron level high enough to be monitored for a controlled reactor startup.
d. increase the excess reactivity of the reactor which reduces the frequency for refueling.

Answer A.14 c.

Reference DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 1, Module 1, Reactor Theory (Reactor Operations), Enabling Objective 3.1 Question A.015 [1.0 point] {15.0}

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

a. A reflector increases the fast non-leakage factor and a moderator increases the thermal utilization factor.
b. A reflector increases the neutron production factor and a moderator increases the fast fission factor.
c. A reflector decreases the thermal utilization factor and a moderator increases the fast fission factor.
d. A reflector decreases the neutron production factor and a moderator decreases the fast non-leakage factor.

Answer A.15 a.

Reference DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2, Module 4, Reactor Theory (Reactor Operations), pp. 25-26

Section A Reactor Theory, Thermo, and Facility Characteristic Question A.016 [1.0 point] {16.0}

A few minutes after a reactor scram period has steadied and reactor power is at 5 x 105 counts/minute. Three minutes later you would expect reactor power to be at

a. 5 x 106 counts/minute.
b. 1 x 105 counts/minute.
c. 5 x 104 counts/minute.
d. 1 x 105 counts/minute.

Answer A.16 c.

Reference This is an 80 second period which implies power decreases by ~ decade per minute, in 3 minutes power will decrease by 1 decade. DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2 Question A.017 [1.0 point] {17.0}

A reactor has a count rate of 45 cps with a Keff of 0.965. Which one of the following is the Keff of this reactor when the count rate increases to 90 cps?

a. 0.9800
b. 0.9825
c. 0.9850
d. 0.9875 Answer A.17 b.

Reference DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 45(1-Keff1) = 90(1 -Keff2)

Keff2 = 0.9825 Question A.018 [1.0 point] {18.0}

Which ONE of the following is the correct definition of effective? The number of delayed neutrons compared to the total number of neutrons per generation

a. corrected for resonance escape.
b. corrected for leakage.
c. corrected for time after the fission event.
d. corrected for both leakage and resonance escape.

Answer A.18 d.

Reference DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2, Module 4, Reactor Theory (Reactor Operations), Enabling Objective 2.2

Section A Reactor Theory, Thermo, and Facility Characteristics Question A.019 [1.0 point] {19.0}

Which ONE of the following factors is the most significant in determining the differential worth of a control rod?

a. The rod speed.
b. Reactor power.
c. The flux shape.
d. The amount of fuel in the core.

Answer A.19 c.

Reference DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, (Reactor Operations), Enabling Objective 5.4 Question A.020 [1.0 point] {20.0}

During a reactor startup, the count rate is increasing linearly on a logarithmic scale, with no rod motion. This means that:

a. the reactor is subcritical and the count rate increase is due to the buildup of delayed neutron precursors.
b. the reactor is subcritical and the count rate increase is due to source neutrons.
c. the reactor is critical and the count rate increase is due to source neutrons.
d. the reactor is supercritical.

Answer: A.20 d.

Reference:

DOE Fundamentals Handbook, Module 4, Reactor Kinetics, page 14.

Section B Normal/Emergency Procedures & Radiological Controls Question B.001 [1.0 point] {1.0}

Which ONE of the following Reactor Emergencies would require you to insert a manual rod run-in as an immediate action?

a. Failure of experimental apparatus
b. High radiation levels
c. Nuclear instrumentation failure
d. Control rod drive failure/stuck rod Answer: B.01 a.

Reference:

REP-RO-100 Rx Emergency Procedures: REP 12, REP 4, REP 5 and REP-8 Question B.002 [1.0 point] {2.0}

While working in an area marked "Caution, Radiation Area," you discover your dosimeter is off scale and leave the area. Assuming you had been working in the area for 45 minutes, what is the maximum dose you would have received?

a. 3.8 mr
b. 35.6 mr
c. 75 mr
d. 100 mr Answer: B.02 c.

Reference:

10 CFR 20.1003 Maximum dose in a rad area is 100 mr/hr.

100 mr/hr x 0.75 hr = 75 mr.

Question B.003 [1.0 point] {3.0}

The NRC has four standard emergency classifications. Which ONE of the four listed below is NOT applicable at MURR?

a. Alert
b. General Emergency
c. Site Area Emergency
d. Notification of Unusual Event Answer: B.03 b.

Reference:

Emergency Plan, § 3.0 Classification of Emergency Conditions

Section B Normal/Emergency Procedures & Radiological Controls Question B.004 [1.0 point] {4.0}

Technical Specification 5.8 requires that All fuel elements or fueled devices outside the reactor core shall be stored in a geometry such that the calculated Keff is less than _____ under all conditions of moderation.

a. 0.80
b. 0.85
c. 0.90
d. 0.95 Answer: B.04 c.

Reference:

Technical Specifications, § 3.8(d)

Question B.005 [1.0 point] {5.0}

Which ONE of the following emergencies requires the console operator to scram the reactor by placing Master Control Switch (1S1) in the TEST position?

a. REP-22, Emergency Core Cooling Valves 546A and 546B open during reactor operations.
b. REP-4, High Radiation Levels
c. REP-5, Nuclear Instrument Failure
d. REP-8, Control Rod Drive Mechanism Failure or Stuck Rod Answer: B.05 d.

Reference:

REO-RO-100, REP-4, REP-5, REP-8 and REP-22 Question B.006 [1.0 point] {6.0}

Following an unscheduled shutdown, the operating staff has performed a thorough investigation but has not been able to determine the cause of the shutdown. All system are normal. The minimum level of management who may authorize the operating crew to restart the reactor is

a. the Lead Senior Reactor Operator on shift.
b. the Assistant Reactor Manager-Physics
c. the Reactor Manager
d. the NRC Answer: B.06 c.

Reference:

AP-RO-110 Conduct of Operations, (6.2.2)

Section B Normal/Emergency Procedures & Radiological Controls Question B.007 [1.0 point, 1/4 each] {7.0}

The appropriate federal regulation contains many requirements for Operator Licenses, match each of the requirements listed in column A with its appropriate time period in column B. (Note:

Periods from column B may be used more than once or not at all.)

Column A (Requirements) Column B (Years)

a. License Renewal 1
b. Requalification Written Examination 2
c. Requalification Operating Test 4
d. Medical Examination 6 Answer: B.07 a. = 6; b. = 2; c. = 1; d. = 2

Reference:

10CFR55 Question B.008 [1.0 point] {8.0}

How long (by standard practice) must the reactor be secured prior to venting a beam port containing Ar41?

a. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
b. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
c. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
d. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Answer: B.08 b.

Reference:

AP-RO-110 step 6.9.2.d Question B.009 [1.0 point, 1/4 each] {9.0}

Identify each of the following reactor plant limitations as a Safety Limit (SL), Limiting Safety System Setting (LSSS) or a Limiting Condition for Operation (LCO). (Choices may be used more than once or not at all.)

a. Primary Coolant Pressure (minimum) 75 psia
b. 1" (maximum) distance between highest and lowest shim arms above 100 Kilowatts
c. 1625 gpm (minimum) either loop.
d. A minimum of one decade of overlap shall exist between adjacent ranges of nuclear instrument channels.

Answer: B.09 a. = LS; b. = LC; c. = LS; d. = LC

Reference:

Technical Specifications

Section B Normal/Emergency Procedures & Radiological Controls Question B.010 [1.0 point] {10.0}

Two point sources have the same Curie strength. Source As gammas have an energy of 1 Mev, while Source Bs gammas have an energy of 2 Mev. You obtain a measurement from the same GM tube 10 feet from each source. Concerning the two measurements, which ONE of the following statements is true?

a. The measured dose rate from Source B is four times that of Source A.
b. The measured dose rate from Source B is twice that of Source A.
c. The measured dose rate from Source B. is half that of Source A.
d. Both measurements are the same.

Answer: B.10 d.

Reference:

NRC Generic Section B Bank {GM tubes cannot distinguish between energies.}

Question B.011 [1.0 point] {11.0}

When placing Fire Protection Systems in online, failure to wait for air systems to reach normal operating pressure before proceeding could result in..

a. Sprinklers may activate
b. Sprinkler head damage
c. Inoperability of detection capability
d. Hydrant or Post Indicator Valve (PIV) damage Answer: B.11 a.

Reference:

OP-OR-555 (4.2)

Question B.012 [1.0 point] {12.0}

A survey instrument with a window probe was used to measure an irradiated experiment. The results were 100 millirem/hr window open and 60 millirem/hr window closed. What was the gamma dose?

a. 40 millirem/hr
b. 60 millirem/hr
c. 100 millirem/hr
d. 160 millirem/hr Answer: B.12 b.

Reference:

NRC Generic Section B Bank {Instrument reads only gamma with window closed therefore reading with window closed is gamma dose.}

Section B Normal/Emergency Procedures & Radiological Controls Question B.013 [1.0 point] {13.0}

When placing the Rod Control Mode in Auto, why should the Wide Range Monitor Level indication be greater than 2% above the Power level Set? Ensure that the

a. Period is longer than 35 seconds.
b. Reactor Power Calculator is operating and indicating properly.
c. Area Radiation Monitor reads will not exceed acceptable levels.
d. First automatic movement of the Regulating Blade is in the inward direction.

Answer: B.13 d.

Reference:

OP-RO-210 (step 5.2.30 NOTE #3)

Question B.014 [1.0 point] {14.0}

An experimenter wishes to irradiate three specimens with reactivity worths of 0.0005 k/k, 0.0013 k/k and 0.0027 k/k. Can these specimens be placed in the reactor as UNSECURED experiments and why (why not).

a. Yes, each specimen is less than 0.006 k/k.
b. No, one of the specimens is greater than 0.0025 k/k.
c. Yes, the sum of the three specimens is less than 0.025 k/k.
d. No, the sum of the three specimens is greater than 0.01 k/k.

Answer: B.14 b.

Reference:

Technical Specifications, §§ 3.1(g)-(k).

Question B.015 [1.0 point] {15.0}

According to the Technical Specifications, which ONE of the following conditions is NOT permissible when the reactor is operating?

a. Above 100 kW, the maximum distance between the highest and lowest shim blade = 1 inch.
b. Emergency generator is out of service for one hour for maintenance.
c. A fueled experiment containing 300 millicuries of I135.
d. Core excess reactivity = 0.006 k/k.

Answer: B.15 b.

Reference:

MURR Technical Specifications, Section 3.10.a.

Section B Normal/Emergency Procedures & Radiological Controls Question B.016 [1.0 point] {16.0}

The CURIE content of a radioactive source is a measure of

a. the number of radioactive atoms in the source.
b. the amount of energy emitted per unit time by the source
c. the amount of damage to soft body tissue per unit time.
d. the number of nuclear disintegrations per unit time.

Answer: B.16 d

Reference:

Standard Health Physics Definition.

Question B.017 [1.0 point] {17.0}

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

a. The SL is a maximum operationally limiting value that prevents exceeding the LSSS during normal operations.
b. The SL is a parameter that assures the integrity of the fuel cladding. The LSSS initiates protective actions to preclude reaching the SL.
c. The LSSS is a parameter that assures the integrity of the fuel cladding. The SL initiates protective action to preclude reaching the LSSS.
d. The SL is a maximum setpoint for instrumentation response. The LSSS is the minimum number of channels required to be operable.

Answer: B.17 b.

Reference:

Standard NRC Technical Specification Question Question B.018 [1.0 point] {18.0}

With the exception of routine sample handling, when moving radioactive material around the pool, Health Physics personnel are required to be present when the dose rate exceeds:

a. 50 mR/hr.
b. 75 mR/hr.
c. 100 mR/hr.
d. 200 mR/hr.

Answer: B.18 c.

Reference:

EX-RO-105 Reactor Irradiation Experiments (step 4.2)

Section B Normal/Emergency Procedures & Radiological Controls Question B.019 [1.0 point] {19.0}

In the event of a high stack monitor readings (in excess of alarm points), the reactor operator should immediately:

a. notify the shift supervisor.
b. scram the reactor.
c. shut down the reactor.
d. reduce power slowly until the alarm clears.

Answer: B.19 a.

Reference:

REP-RO-100 - REP-4 Question B.20 [1.0 point] {20.0}

Per the definition in the Emergency Plan, an EMERGENCY is

a. The person or persons appointed by the Emergency Coordinator to ensure that all personnel have evacuated the facility or a specific part of the facility.
b. Projected radiological dose or dose commitment values to individuals that warrant protective action following a release of radioactive material.
c. a condition or conditions which call(s) for immediate action, beyond the scope of normal operating procedures, to avoid an accident or to mitigate the consequences of one.
d. Specific instrument readings, or observations; radiological dose or dose rates; or specific contamination levels of airborne, waterborne, or surface- deposited radioactive materials that may be used as thresholds for establishing emergency classes and initiating appropriate emergency measures.

Answer: B.20 c.

Reference:

EP-RO-001 Emergency Procedure - Definitions

Section C Facility and Radiation Monitoring Systems Question C.001 [1.0 point] {1.0}

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. All systems will remain running with all automatic functions operable.
d. The system is mechanically interlocked and you cannot move 1S1 to the off position with all systems running.

Answer: C.01 c.

Reference:

SAR, Chapter 7 -Instrumentation and Control Systems; 7.5.3 Manual Control.

Question C.002 [1.0 point] {2.0}

The purpose of the thermal column is to

a. enhance natural convection flow.
b. provide thermal neutron flux for experiments.
c. enhance heat transfer characteristics of the core.
d. provide a thermal temperature rise for experiments.

Answer: C.02 b.

Reference:

SAR, Chapter 10 - EXPERIMENTAL FACILITIES AND UTILIZATION Question C.003 [1.0 point] {3.0}

The reactor is in the automatic mode of operation. Which ONE of the following conditions will NOT cause control to shift back to manual?

a. Regulating rod control switch (1S5) actuated.
b. Regulating rod inserted to the 10% withdrawn position.
c. Regulating blade position is greater than 60% withdrawn.
d. Wide Range Monitor selector switch is in the 5 kW black scale position.

Answer: C.03 c.

Reference:

SAR, Chapter 7 -Instrumentation and Control Systems; 7.5.4 Automatic Control

Section C Facility and Radiation Monitoring Systems Question C.004 [1.0 point, 1/4 point each] {4.0}

For each of the Rod Run-In Functions listed below, fill in the minimum number of instrument channels required by Technical Specifications for Reactor Operation in Mode 1.

Rod Run-In Minimum Number of Channels

a. High Reactor Power 1
b. Reactor Period 2
c. Rod not in contact with magnet 3
d. Vent Tank Low Level 4 Answer: C.04 a. = 3; b. = 2; c. = 4; d.= 1

Reference:

Technical Specification 3.4. Reactor Instrumentation Question C.005 [1.0 point] {5.0}

A Facility Evacuation can be manually initiated from the control console and:

a. the reactor bridge.
b. equipment room 278.
c. the front lobby.
d. equipment room 114.

Answer: C.05 c.

Reference:

CP-6 Building Evacuation/Isolation Scram Question C.006 [1.0 point, 1/4 point each] {6.0}

Match each of the beamports in column A with the correct characteristics in Column B Column A Column B Beamport Characteristic

a. A 1. 6" radial (6R)
b. B 2. 6" radial - tangential (6RT)
c. C 3. 4" radial (4R)
d. D 4. 4" radial - tangential (4RT)

Answer: C.06 a. = 3; b. = 1; c. = 2; d. = 4

Reference:

SAR, Chapter 10 - Experimental Facilities and Utilization - Table 10-1

Section C Facility and Radiation Monitoring Systems Question C.007 [1.0 point, 1/4 point each] {7.0}

Match the channel in column A with the correct detector in column B.

Column A Column B

a. Fission Product Monitor 1. Geiger Müeller
b. Secondary Coolant Monitor 2. Scintillation Detector
c. Bridge ARMS 3. GeLi Detector
d. Exhaust Plenum 1 4. BF3 Ion Chamber Detector Answer: C.07 a. = 2; b. = 2; c. = 1; d. = 1;

Reference:

SAR, Chapter 7 -Instrumentation and Control Systems; Figure 7.11 Area Radiation Monitoring System pages 7-63/64 Question C.008 [1.0 point, 1/4 point each] {8.0}

Which ONE of the following DOES NOT describe a function of the Uninterruptible Power Supply?

a. supply power to the Emergency Distribution Center (CTR-1).
b. supply power to the Area Radiation Monitoring System (ARMS) to ensure radiation levels are known.
c. reduce spurious (false) reactor scrams caused by voltage fluctuations or a momentary interruption in electrical power.
d. ensures that the reactor control console and instrument panel indications are maintained during the transition period from the time of a loss of normal electrical power to the time the diesel generator supplies the load.

Answer: C.08 a.

Reference:

SAR Chapter 8.0 - Electrical Power Systems - 8.1.2 Description of System Question C.009 [1.0 point] {9.0}

Containment building isolation is accomplished by closing two butterfly valves, 16A and 16B, in the main exhaust line. Which ONE of the following describes the operation of these valves?

Valve 16A Valve 16B

a. air open, air close air open, spring close.
b. air open, spring close air open, air close.
c. motor-operated (open and close) air open, air close.
d. air open, spring close motor-operated (open and close)

Section C Facility and Radiation Monitoring Systems Answer: C.09 b.

Reference:

SAR Chapter 6 - Engineered Safety Features - 6.2.3.8 Hot Exhaust Line Question C.010 [1.0 point] {10.0}

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

a. Double encapsulation of samples.
b. Speed at which the sample container is transported through the system.
c. Facility exhaust fans operation prevent stagnant air in the vicinity of the rabbit system.
d. A time delay starts the east p-tube blower approximately 15 seconds after the west p-tube blower.

Answer: C.10 a.

Reference:

SAR, Chapter 10 - Experimental Facilities and Utilization - 10.3.4 Pneumatic Tube System Question C.011 [1.0 point] {11.0}

Which ONE of the following describes the response of the regulating blade to a reactor scram signal?

a. It's electromagnetic clutch deenergizes and the rod falls into the core via the force of gravity.
b. The rod will be driven into the core.
c. The rod will withdraw in an attempt to compensate for the shim blades insertion.
d. The rod will remain in its position.

Answer: C.11 d.

Reference:

MURR Lesson Plan, Rod Control - Reg Blade Question C.012 [1.0 point] {12.0}

Which Area Radiation Monitors below can cause a Reactor Isolation?

a. Bridge, Bridge ALARA, Air Plenum 1, Air Plenum 2.
b. Bridge, Bridge ALARA, Fission Product Monitor, Air Plenum 1.
c. Fission Product Monitor, Air Plenum 1, Air Plenum 2, Bridge ALARA.
d. Beamport Floor North Wall, Beamport Floor West Wall, Beamport Floor South Wall, Bridge.

Answer: C.12 a.

Reference:

MURR Lesson Plan, Reactor Isolation & Facility Evacuation

Section C Facility and Radiation Monitoring Systems Question C.013 [1.0 point] {13.0}

For each action in Column A select the appropriate pressurizer system setpoint listed in Column B. Pressures in Column B may be used once, more than once or not at all. Only one answer may occupy each space in column A. (Three answers required at 0.333 each)

Column A (Actions) Column B (Setpoints)

a. High pressure scram 1. 63 psig
2. 67 psig
b. Nitrogen makeup valve opens 3. 69.5 psig
4. 70 psig
c. High pressure relief valve lifts 5. 73.5 psig
6. 78 psig
7. 80.5 psig
8. 100 psig Answer: C.13 a. = 6; b. = 2; c. = 8

Reference:

MURR Lesson Plan, Pressurizer System Question C.014 [1.0 point] {14.0}

Which ONE of the following Nuclear Instrument Channels has an input into the regulating blade auto control circuit?

a. PRM 4
b. PRM 5
c. Wide Range Monitor
d. PRM 6 Answer: C.14 c.

Reference:

MURR Lesson Plan, Rod Control - Reg Blade Question C.015 [1.0 point] {15.0}

Which one of the following correctly describes the operation of a Thermocouple?

a. A bi-metallic strip which winds/unwinds due to different thermal expansion constants for the two metals, one end is fixed and the other moves a lever proportional to the temperature change.
b. a junction of two dissimilar metals, generating a potential (voltage) proportional to temperature changes.
c. a precision wound resistor, placed in a Wheatstone bridge, the resistance of the resistor varies proportionally to temperature changes.
d. a liquid filled container which expands and contracts proportional to temperature changes, one part of which is connected to a lever.

Section C Facility and Radiation Monitoring Systems Answer: C.15 b.

Reference:

Standard NRC question Question C.016 [1.0 point] {16.0}

Which ONE of the following is the main function performed by the DISCRIMINATOR circuit in the Startup Channel?

a. To generate a current signal equal and of opposite polarity as the signal due to gammas generated within the Startup Channel Detector.
b. To filter out small pulses due to gamma interactions, passing only pulses due to neutron events within the Startup Channel Detector.
c. To convert the linear output of the Startup Channel Detector to a logarithmic signal for metering purposes.
d. To convert the logarithmic output of the metering circuit to a t (delta time) output for period metering purposes.

Answer: C.16 b.

Reference:

MURR Lesson Plan, Nuclear Instrumentation Question C.017 [1.0 point] {17.0}

Which ONE of the following is a load supplied by the Emergency Generator?

a. Primary Coolant Isolation Valves 507 A/B
b. Reactor Exhaust System Fan EF-14
c. Ventilation Fan SF-1
d. Primary Pump P501A Answer: C.17 b.

Reference:

MURR Lesson Plan, Emergency Electrical Distribution Question C.018 [1.0 point] {18.0}

In the event of a commercial power failure, the diesel engine starts and the emergency generator supplies power to_______. When normal power is restored, the emergency electrical load is shifted back after a time delay of_______.

a. Substation B; ten minutes.
b. Emergency Distribution Center ; ten minutes.
c. Substation B; seven seconds.
d. Emergency Distribution Center ; seven seconds.

Section C Facility and Radiation Monitoring Systems Answer: C.18 b.

Reference:

HSR pg 7-3 and MURR drawing 522 sheet 1 of 3 Question C.019 [1.0 point, 1/4 point each] {19.0}

Match the purification system conditions listed in column A with their respective causes listed in column B. Each choice is used only once. Higher than normal Column A Column B

a. Radiation Level at demineralizer. 1. Channeling in demineralizer.
b. Radiation Level downstream of demineralizer. 2. Fuel element failure.
c. flow rate through demineralizer. 3. High temperature in demineralizer system
d. pressure upstream of demineralizer. 4. Clogged demineralizer Answer: C.19 a. = 2; b. = 3; c. = 1; d. = 4

Reference:

Standard NRC cleanup loop question.

Question C.020 [1.0 point] {20.0}

Mechanical strain when shifting Cooling Tower Fans from fast to slow speed is minimized by

a. a directed spray of coolant aiding in the slowing down of the fans.
b. a large torsion spring designed to absorb the shock of energizing the slow speed windings.
c. the use of special fan belts designed to absorb the shock of energizing the slow speed windings.
d. a delay timer allowing the fan to coast down (about 20 seconds), before the slow speed windings energize.

Answer: C.20 d.

Reference:

OP-RO-480, Secondary Coolant System, Step 5.2.2 NOTE

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