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Examination Report No. 50-186/OL-16-02, University of Missouri-Columbia
	ML16225A133
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Site:	University of Missouri-Columbia
Issue date:	08/12/2016
From:	Mendiola A J; Research and Test Reactors Oversight Branch
To:	Butler R A; Univ of Missouri - Columbia
	Anthony Mendiola
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ML16082A088	List: ML16082A037; ML16225A133;
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August 12, 2016 Mr. Ralph A. Butler, Executive Director

University of Missouri-Columbia

Research Reactor Center 1513 Research Park Drive Columbia, MO 65211

SUBJECT:

EXAMINATION REPORT NO. 50-186/OL-16-02, UNIVERSITY OF MISSOURI - COLUMBIA

Dear Mr. Butler:

During the week of July 18, 2016, the U. S. Nuclear Regulatory Commission 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 a nd 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 e-mail at Phillip.Young@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

Enclosure:

1. Examination Report No. 50-186/OL-16-02

cc w/enclosure: John Fruits, Assistant Reactor Manager of Operations cc w/o enclosures: See next page

August 12, 2016 Mr. Ralph A. Butler, Executive Director

University of Missouri-Columbia Research Reactor Center 1513 Research Park Drive Columbia, MO 65211

SUBJECT:

EXAMINATION REPORT NO. 50-186/OL-16-02, UNIVERSITY OF MISSOURI - COLUMBIA

Dear Mr. Butler:

During the week of July 18, 2016, the U. S. Nuclear Regulatory Commission 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 a nd 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 e-mail at Phillip.Young@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-16-02

cc: John Fruits, Assistant Reactor Manager of Operations cc w/o enclosures: See next page DISTRIBUTION w/ encls. PUBLIC AMendiola JEads AAdams GWertz ADAMS ACCESSION #: ML16225A133 TEMPLATE #:NRR-074 OFFICE NRR/DPR/PROB/CENRR/DPR/PROB/OLA NRR/DPR/PROB/BCNAME PYoung CRevelle AMendiolaDATE 07/28/201608/12/201608/12/2016

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

Les Foyto, Associate Director Reactor and Facilities Operations 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-16-02

FACILITY DOCKET NO.: 50-186

FACILITY LICENSE NO.: R-103

FACILITY: University of Missouri - Columbia

EXAMINATION DATES: July 18 & 19, 2016

SUBMITTED BY: ___________

/RA/ __________ _7/

28/2016____ Phillip T. Young, Chief Examiner Date

SUMMARY:

During the week of July 18, 2016 the U. S. Nuclear Regulatory Commission administered licensing examinations to two RO applicants. One applicant passed all portions of these examinations and one applicant failed one section of the written examination.

REPORT DETAILS

1. Examiners: Phillip T. Young, Chief Examiner, NRC

2. Results:

RO PASS/FAILSRO PASS/FAIL TOTAL PASS/FAIL Written 1

/10/01/1 Operating Tests 2

/00/02/0 Overall 1

/10/01/1 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 Rob Hudson, Reactor Operations Training Coordinator, MURR

The examiner thanked the facility for their assistance in completing the examinations. The examiner explained that question C.01 and C.03 would be deleted from the examination because the required diagrams for the questions were not properly prepared. The facility stated that question C.04 has answer 'c.' as the answer verses the correct answer 'b.'

ENCLOSURE 1

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

FACILITY: UNIVERSITY OF MISSOURI - COLUMBIA REACTOR

REACTOR TYPE: TANK

DATE ADMINISTERED: 7/19/2016

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 parentheses for each question. A 70% overall is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

CATEGORY VALUE % OF TOTAL CANDIDATE'S SCORE % OF CATEGORY VALUE CATEGORY 20.00 33.3 _______ _______

A. REACTOR THEORY, THERMODYNAMICS, AND FACILITY OPERATING CHARACTISTICS

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 ___________ FINAL GRADE TOTALS ALL THE WORK DONE ON THIS EXAMINATION IS MY OWN. I HAVE NEITHER GIVEN NOR RECEIVED AID.

__________________________ CANDIDATE'S SIGNATURE

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

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

2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have not received or 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.

6. Fill in the date on the cover sheet of the examination (if necessary).

7. Print your name in the upper right-hand corner of the first page of each section of your answer sheets.

8. The point value for each question is indicated in parentheses after the question.

9. Partial credit will NOT be given.

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

11. When you are done and have turned in your examination, leave the examination area as defined by the examiner.

EQUATION SHEET

DR - Rem/hr, Ci - curies, E - Mev, R - feet

1 Curie = 3.7 x 10 10 dis/sec 1 kg = 2.21 lbm 1 Horsepower = 2.54 x 10 3 BTU/hr 1 Mw = 3.41 x 10 6 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 c p = 1 cal/sec/gm/°C

()()22max=P1sec1.0=eff=tePP0effKSSSCR=1sec1014*x=+=&effSUR06.26()()211121effeffKCRKCR=()()2211=CRCR2111effeffKKM=1211CRCRKMeff==)(010tSURPP=()01PP=effeffKKSDM=1=*++=&eff*2112effeffeffeffKKKK=693.021=TeffeffKK1=teDRDR=0()26RnECiDR=222211dDRdDR=()()121222PeakPeak=TUAHmTcmQP===&&&

Section A: Reactor Theory, Thermodynamics, and Fac. Operating Characteristics Question A.001 [1.0 point] (1.0)

Keff is K times - a. the fast fission factor () b. the total non-leakage probability (f x th) c. the reproduction factor () d. the resonance escape probability (p)

Answer: A.01 b.

Reference:

DOE Fundamentals Handbook Module 3, Theory (Nuclear Parameters), E.O. 1.1 a&b, pg. 9

Question A.002 [1.0 point] (2.0)

Which ONE of the following is an example of alpha decay? a. 35Br87 33As83 b. 35Br87 35Br86 c. 35Br87 34Se86 d. 35Br87 36Kr87 Answer: A.02 a.

Reference:

DOE Fundamentals Handbook, Nuclear Physics & Theory, Volume 1, Module 1, Atomic and Nuclear Physics, Enabling Objective 2.1

Question A.003 [1.0 point] (3.0) An experimenter makes an error loading a rabbit sample. Injection of the sample results in a 100 millisecond period. If the scram setpoint is 12.5 Mwatt and the scram delay time is 0.1 seconds, WHICH ONE of the following is the peak power of the reactor at shutdown. (Assume Rabbit system is operational for this question.)

a. 12.5 Mw b. 25.0 Mw

c. 34.0 Mw d. 125 Mw

Answer: A.03 c.

Reference DOE Fundamentals Handbook, Volume 2, Module 4, pp. 11.

P = P 0 et/ P = 12.5 Mwatts x e(0.1/0.1) = 12.5 x 2.71828 = 33.98

Section A: Reactor Theory, Thermodynamics, and Fac. Operating Characteristics Question A.004 [1.0 point] (4.0) With the reactor on a constant period which transient will take the LONGEST time to complete? A reactor power change of -

a. 5%, going from 1% to 6% of rated power. b. 10%, going from 10% to 20% of rated power. c. 15%, going from 20% to 35% of rated power. d. 20%, going from 40% to 60% of rated power.

Answer: A.04 a.

Reference:

Standard NRC question

Question A.005 [1.0 point] (5.0) An Integral Rod Worth (IRW) curve is ________________, while a Differential Rod Worth (DRW) curve is __________.

a. the total reactivity worth added by the rod at any point of withdrawal; the reactivity change per unit movement of the rod at the point of withdrawal.

b. at its maximum value when the rod is approximately half-way out of the core; at its maximum value when the rod is fully withdrawn from the core.

c. the slope of the DRW curve at any point of withdrawal; the area under the IRW curve at any point of withdrawal.

d. the reactivity change per unit movement of the rod at any point of withdrawal; the total reactivity worth of the rod at any point of withdrawal.

Answer: A.05 a.

Reference:

DOE Fundamentals Handbook, Module 3, Control Rods, page 51.

Question A.006 [1.0 point] (6.0) You enter the control room and note that all nuclear instrumentation channels show a steady neutron level, and no rods are in motion. Which ONE of the following conditions CANNOT be true?

a. The reactor is critical. b. The reactor is subcritical. c. The reactor is supercritical. d. The neutron source has been removed from the core.

Answer: A.06 c.

Reference:

DOE Handbook, Nuclear Physics & Theory, Volume Section A: Reactor Theory, Thermodynamics, and Fac. Operating Characteristics Question A.007 [1.0 point] (7.0) Core excess reactivity changes with - a. fuel element burnup

b. control rod height

c. neutron energy level

d. reactor power level Answer: A.07 a.

Reference:

Technical Specification Requirement.

Question A.008 [1.0 point] (8.0) Which ONE of the following is the principle source of heat in the reactor after a shutdown from extended operation at 10 MW?

a. Decay of fission products. b. Spontaneous fission of U 238. c. Production of delayed neutrons. d. Production of prompt gamma rays.

Answer: A.08 a.

Reference:

Question A.009 [1.0 point] (9.0) The moderator-to-fuel ratio describes the relationship between the number of moderator atoms in a volume of core to the number of fuel atoms. A reactor which is:

a. undermoderated will have a positive moderator temperature coefficient. b. undermoderated will have a negative moderator temperature coefficient. c. overmoderated will have a constant moderator temperature coefficient. d. overmoderated will have a negative moderator temperature coefficient.

Answer: A.09 b.

Reference:

DOE Fundamentals Handbook, Module 3, Reactivity Coefficients, page 25.

Section A: Reactor Theory, Thermodynamics, and Fac. Operating Characteristics Question A.010 [1.0 point] (10.0) Which ONE of the following statements is the definition of REACTIVITY?

a. A measure of the core's fuel depletion. b. A measure of the core's deviation from criticality. c. Equal to 1.00 K/K when the reactor is critical. d. Equal to 1.00 K/K when the reactor is prompt critical.

Answer: A.10 b.

Reference:

DOE Handbook Vol 1 Module 3

Question A.011 [1.0 point] (11.0) Which ONE of the following factors in the "six factor" formula is the MOST affected by the CONTROL BLADES? a. Fast fission factor b. Reproduction factor

c. Thermal utilization factor

d. Resonance escape probability Answer: A.11 c.

Reference:

Question A.012 [1.0 point] (12.0) Which ONE of the following reactor changes requires a control rod INSERTION to return reactor power to its initial level following the change?

a. Formation of N 16 in the coolant. b. Removal of an experiment with positive reactivity from the reactor. c. Buildup of Xe 135 d. A fault in the automatic system resulting in a primary coolant temperature decrease.

Answer: A.12 d.

Reference:

DOE Handbook

Section A: Reactor Theory, Thermodynamics, and Fac. Operating Characteristics Question A.013 [1.0 point] (13.0) Which of the following statements describes the concentration of Xenon in the core after a scram from extended operation at 10 MW? Xenon concentration -

a. initially decreases due to loss of Iodine production then increases to maximum concentration b. decreases to a Xenon free condition in approximately ten (10) hours c. increases to maximum in approximately ten (10) hours due to the reduction in Xenon burnup d. remains at equilibrium value since power level has no effect on Xenon concentration

Answer: A.13 c.

Reference:

DOE Handbook, Volume 2, Module 3, Theory (Nuclear Parameters).

Question: A.014 [1.0 point] {14.0} Which ONE of the following statements concerning reactor poisons is NOT true? a. During reactor operation, Xenon concentration is dependent on reactor power level. b. Following shutdown, Samarium concentration will increase to some value then stabilize.

c. During reactor operation, Samarium concentration is independent of reactor power level. d. Following shutdown, Xenon concentration will initially increase to some value then decrease exponentially.

Answer: A.014 c.

Reference:

DOE Fundamentals Handbook

Question: A.015 [1.0 point] {15.0} One minute following a scram from full power, the indications on the nuclear channels are primarily due to: a. Prompt neutrons b. Delayed and photo-neutrons c. Prompt and delayed neutrons d. Prompt, delayed and photo-neutrons Answer: A.15 b.

Reference:

Section A: Reactor Theory, Thermodynamics, and Fac. Operating Characteristics Question: A.016 [1.0 point] {16.0} Which ONE of the following reactor parameter changes would have the LEAST effect on reactivity of the reactor?

a. Increase moderator temperature by 5°F b. Increase fuel temperature by 50°F c. Drain the water out of the center flux trap. d. Increase the pressure of the moderator by 20 psi.

Answer A.16 d. References DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory

Question: A.017 [1.0 point] {17.0} Which ONE of the following isotopes will cause a neutron to lose the most energy in an ELASTIC scattering reaction?

a. O16 b. C12 c. Be9 d. H1 Answer: A.17 d.

Reference:

DOE Handbook, Nuclear Cross-Sections and Neutron Flux, p. 5.

Question: A.018 [1.0 point] {18.0} A common method for calibrating control elements (rods, blades, etc.), is to measure doubling time then calculate period. If the doubling time is 42 seconds, which ONE of the following is the period?

a. 29 seconds b. 42 seconds c. 61 seconds d. 84 seconds

Answer: A.18 c.

Reference:

DOE Fundamentals Handbook, Module X, Standard NRC Question

1. Also: period = (doubling time) ÷ (ln(2)) = 42/0.693 = 60.6 61

Section A: Reactor Theory, Thermodynamics, and Fac. Operating Characteristics Question: A.019 [1.0 point] {19.0}

The effective target area, in cm 2, presented by a single nucleus to an incident neutron beam is defined as: a. a neutron flux. b. a mean free path. c. a microscopic cross section. d. a macroscopic cross section.

Answer: A.19 c.

Reference:

Question A.020 [1.0 point] {20.0} What is the kinetic energy range of a thermal neutron? a. > 1 MeV b. 100 KeV - 1 MeV

c. 1 eV - 100 KeV d. < 1 eV

Answer: A.20 d.

Reference:

DOE Handbook, Volume 1, Module 2, Neutron Moderation, p. 23.

Section B. - Normal & Emerg Operating Procedures & Radiological Controls

Section B. - Normal & Emerg Operating Procedures & Radiological Controls Question B.001 [1.0 point] {1.0} Which ONE of the following conditions would NOT preclude sending a volunteer into a high radiation area in order to save a life?

a. The radiation levels in the area are unknown. b. All volunteers are women of child bearing age. c. All volunteers are men under the age of 45. d. The only volunteer is a new hire, not trained in the consequences of receiving an emergency dose.

Answer: B.01 c.

Reference:

EP-RO-018 Emergency Radiation Exposure

Question B.002 [1.0 point] {2.0} When pumping the Liquid Waste tanks to the sanitary sewer, the maximum accumulated activity for nuclides other than H 3 is 2 millicuries for the Lead Senior Reactor Operator to authorize the procedure. The maximum accumulated activity for H 3 is less than-

a. 1 millicuries b. 5 millicuries

c. 10 millicuries d. 20 millicuries

Answer: B.02 c.

Reference:

OP-RO-741, Waste Tank System Operation

Question B.003 [1.0 point] {3.0} You are operating the reactor when it scrams (unscheduled). After looking for hours neither you nor the SRO, nor the shift supervisor can find the reason for the scram. Which one of the following conditions must be met to restart the reactor?

a. You may NOT startup the reactor under any conditions until the cause of the scram is found and corrected.

b. You may startup the reactor if authorized by any Senior Reactor Operator.

c. You may startup the reactor if authorized by the designated Shift Supervisor.

d. You may startup the reactor if authorized by the Reactor Manager.

Answer: B.03 d.

Reference:

AP-RO-110 Conduct of Operation (§ 6.6.8)

Section B. - Normal & Emerg Operating Procedures & Radiological Controls Question B.004 [1.0 point] {4.0} During startup of the Primary Coolant System, per procedure you start the pumps with system pressure greater than 63 psig. After starting the second pump, the pumps cycle off then on. Per procedure you should -

a. continue the system startup. b. stop both pumps, and inform the Lead Senior Reactor Operator.

c. continue the system startup, after informing the Lead Senior Reactor Operator. d. stop both pumps, wait for primary pressure to increase greater than 66 psig, then restart the pumps.

Answer: B.04 d.

Reference:

OP-RO-410, Primary Coolant System. 5.4.13

Question B.005 [1.0 point] {5.0} The four parameters used to evaluate the safety limits are: a. reactor power level, core flow rate, reactor inlet water temperature, and water tank level. b. reactivity, reactor power level, reactor inlet water temperature, and pressurizer pressure.

c. reactor power level, core flow rate, reactor inlet water temperature, and pressurizer pressure.

d. reactor power level, core flow rate, reactor outlet water temperature, and pressurizer pressure.

Answer: B.05 c.

Reference:

TS 2.1

Section B. - Normal & Emerg Operating Procedures & Radiological Controls Question B.006 [1.0 point] {6.0} An experiment is removed from the reactor with a radiation level of 10R/hr at 15 feet. 15 minutes later, the radiation level is 7.2 Rem/hr at 15 feet. Approximately how long must you let the experiment decay before the radiation level is less than 100 mR/hr at 1 foot.

a. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months b. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months c. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months d. 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months Answer: B.06 b.

Reference; first solve for eff; A = A0 e-t eff; ln (A/A

0) = time x eff eff = (ln (7.2/10)) ÷ time = (-0.329)/15 minutes = -0.0219 minutes

-1 Next solve for initial dose at 1 foot. A 1 ft = A15 ft x 152 = 10 R/hr x 225 = 2250 R/hr at 1 foot. Finally solve for time to get to 0.1 R/hr at 1 foot.

0.1 = 2250 e t eff ===> time = ln (0.1/2250) ÷ eff = 457.6 minutes = 7.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

Question B.007 [1.0 point] {7.0} The calculated K eff in the fuel storage shall be less than _____ under all conditions of moderation.

a. 0.80 b. 0.85

c. 0.90

d. 0.95 Answer: B.07 c.

Reference:

TS 3.8.d

Question B.008 [1.0 point] {8.0} Radiation level at the distance corresponding to the nearest site boundary equals 20 mRem/hr for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months whole-body is classified as:

a. Unusual Event

b. Alert

c. Site Area Emergency

d. General Emergency

Answer: B.08 b

Reference:

Emergency Plan Table I

Section B. - Normal & Emerg Operating Procedures & Radiological Controls Question B.009 [1.0 point] {9.0} Which ONE of the following control rod manipulations is NOT by procedure? a. Gang operation of the control rods after criticality to reduce power. b. Gang operation of the control rods as part of automatic shimming.

c. Simultaneous withdrawal of one control blade and the regulating blade. d. Gang operation of the controls rods during hot startup.

Answer: B.09 c.

Reference:

AP-RO-110, Conduct of Operations step 6.6.6 Question B.010 [1.0 point] {10.0} Which ONE of the following locations is NOT an Emergency Command Center per the

Emergency Plan?

a. Control Room b. Research Park Development Building c. Dalton Cardiovascular Research Center d. Facility Front Lobby

Answer: B.10 c.

Reference:

Emergency Plan section 6.1

Question B.011 [1.0 point] {11.0} Common radioisotopes associated with research reactors are N 16, Ar4l, H3 and Na24. The half-life for each is (seconds (sec), minutes (min) hours (hr) or years (yr)).

a. N16 is 7.0 _____. b. Ar41 is 1.9 _____. c. H3 is 12.0 _____. d. Na24 is 15.0 _____.

Answer: B.11 a. = sec, b. = hr; c. = yr; d. = hr;

Reference:

NRC bank question

Section B. - Normal & Emerg Operating Procedures & Radiological Controls Question B.012 [1.0 point] {12.0} Match type of radiation (a thru d) with the proper penetrating power (1 thru 4) a. Gamma 1. Stopped by thin sheet of paper

b. Beta 2. Stopped by thin sheet of metal

c. Alpha 3. Best shielded by light material

d. Neutron 4. Best shielded by dense material Answer: B.12 a. = 4; b. = 2; c. = 1; d. = 3

Reference:

Standard NRC Health Physics Question

Question B.013 [1.0 point] {13.0} The SHUTDOWN MARGIN of the MURR shall be at least: a. 2% delta k/k. b. 2% delta k/k with any one shim blade fully withdrawn.

c. 0.02% delta k/k. d. 0.02% delta k/k with any one shim blade fully withdrawn.

Answer: A.013 b.

Reference:

MURR Technical Specifications, Section 3.1.e.

Question B.014 [1.0 point] {14.0} Unless extended in writing, a Radiation Work Permits expires in: a. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

b. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . c. a week. d. a month.

Answer: B.14 b.

Reference:

AP-HP-105, RWP 4.0 Note #1.

Section B. - Normal & Emerg Operating Procedures & Radiological Controls Question B.015 [1.0 point] {15.0} The Primary System Fuel Failure Monitor is secured due to an electrical problem. How often must the primary coolant be sampled to continue reactor operation?

a. every hour b. every two hours

c. every four hours

d. every eight hours Answer: B.15 c.

Reference:

Technical Specifications, § 3.9.b, Coolant System

Question B.016 [1.0 point] {16.0} In the case of an evacuation beyond the EPZ, according to EP-RO-014, all personnel who have evacuated the reactor building will proceed to the:

a. Dalton parking lot. b. Science Instrument Shop.

c. Research Park Development Building. d. USDA Research Laboratory parking lot.

Answer: B.16 a.

Reference:

EP-RO-014, EPZ and Site Area Evacuations Question B.017 [1.0 point] {17.0} If the reactor core contains NEW fuel, an estimated critical position (ECP) adjustment needs to Fbe :

a. subtracted 0.2 inch from an ECP that is based on ONE new fuel element b. subtracted 0.6 inch from an ECP that is based on TWO new fuel element

c. added 0.2 inch from an ECP that is based on ONE new fuel element d. added 0.6 inch from an ECP that is based on TWO new fuel element

Answer: B.17 a.

Reference:

RP-RO-100, Fuel Movement - Section 6.3.3

Section B. - Normal & Emerg Operating Procedures & Radiological Controls Question B.018 [1.0 point] {18.0} "The shim blades shall be capable of insertion to the 20% withdrawn position in less than 0.7 seconds." This is an example of a:

a. safety limit b. limiting safety system setting c. limiting condition for operation d. surveillance requirement

Answer: B.18 c.

Reference:

TS 3.2.c

Question B.019 [1.0 point] {19.0} A Radiation Work Permit (RWP) is required if non-routine work is being performed with anticipated MINIMUM exposure rates of ______ per hour.

a. 20 mR

b. 50 mR

c. 100 mR

d. 150 mR Answer: B.19 c.

Reference:

AP-HP-105, Radiation Work Permit - Step 4.1

Question B.020 [1.0 point] {20.0} The area bounded by a 150 meter radius from the MURR exhaust stack is defined as: a. Emergency Planning Zone (EPZ)

b. Nearest Site Boundary

c. Onsite

d. Operations Boundary

Answer: B.20 a.

Reference:

Emergency Plan, Section 9.8

Section C - Plant and Rad Monitoring Systems and Radiological Control Procedures Question C.001 [1.0 points, 0.25 points each] (1.0) Identify the components labeled a through d on the figure of the cross section of the core area provided. (Note: Only one answer per letter.

a. A 1. Active Fuel Region 2. Mounting Bracket b. B 3. Beryllium Skirt 4. Outer Pressure Vessel

c. C 5. Graphite Reflector

6. Control Blade

d. D 7. Beryllium Reflector Answer: C.01 a. = 1; b. = 4; c. = 6; d. = 7

Reference:

Training Manual for Reactor Operations, cross section of the core area

Question C.002 [1.0 point] (2.0) Which ONE statement below describes the operation of the three-way solenoid valves in the Valve Operating System? When the solenoid valve is -

a. energized, the vent side of the valve closes, directing air pressure to the isolation valve operator.

b. deenergized, the vent side of the valve closes, directing air pressure to the isolation valve operator.

c. energized, the vent side of the valve opens, directing air pressure to the isolation valve operator.

d. deenergized, the vent side of the valve opens, directing air pressure to the isolation valve operator.

Answer: C.02 a.

Reference:

Training Manual for Reactor Operations, Section - Valve Operating System

Section C - Plant and Rad Monitoring Systems and Radiological Control Procedures Question C.003 [1.0 points, 0.125 points each] (3.0) Identify the components labeled a through h on the figure of a Control Blade Drive Mechanism

provided. (Note: Items are used only once. Only one answer per letter.)

a. ___ 1. Reduction Gears b. ___ 2. Drive Motor c. ___ 3. Lead Screw d. ___ 4. Relays

e. ___ 5. Lower Limit Switch

f. ___ 6. Rod Position Encoder

g. ___ 7. Scram Magnet Assembly

h. ___ 8. Upper Limit Switch Answer: C.03 a. = 2; b. = 6; c. = 8; d. = 3; e. = 4; f. = 5;

g. = 1; h. = 7

Reference:

Training Manual for Reactor Operations, Diagram of a Control Blade Mechanism

Question C.004 [1.0 point] (4.0) Which ONE of the following radiation monitor channels contains a charcoal cartridge?

a. The gas channel. b. The iodine channel.

c. The particulate channel. d. The Air Plenum # 1 channel.

Answer: C.04 c.

Reference:

Training Manual for Reactor Operations, Stack Monitor - Eberline Question C.005 [1.0 point] (5.0) Which ONE of the following is the method used to DE-ICE the cooling tower fans. a. Run the cooling tower fan in reverse.

b. Use the facilities steam line located in the area for that purpose. c. Use a heat gun (similar to a hair dryer) designated for de-icing use. d. De-icing is not necessary due to anti-freeze added to cooling tower water.

Answer: C.05 a.

Reference:

OP-RO-480, § 7.0 Note #2 Section C - Plant and Rad Monitoring Systems and Radiological Control Procedures Question C.006 [1.0 point] (6.0)

Which ONE of the following design features minimizes the effects of H3 (Tritium)? a. Vent Exhaust system at the top of the pool.

b. Hold up tanks in the primary coolant system.

c. Primary demineralizer system.

d. Controlled release of the gases held in the beam ports.

Answer: C.06 a.

Reference:

Facility Walk-through

Question C.007 [1.0 point] (7.0) Reactor is at 5 MW power in Auto Mode. You accidently move the Regulating Blade Switch 1S5, your action will cause:

a. a Scram.

b. a Rod Run-In.

c. terminate the Auto Mode.

d. no effect to the Auto Mode.

Answer: C.07 c.

Reference:

OP-RO-211, Reactor Startup - Hot - Note #2 following Section 5.2.22

Question C.008 [1.0 point] (8.0) Which ONE of the following correctly describes the actions of the automatic shim control circuit?

Shim rods will automatically insert when the regulating rod reaches the ____ withdrawn position. The insertion will be enough to drive the regulating rod to ____ withdrawn.

a. 20% 60% b. 20% 70% c. 30% 60% d. 30% 70%

Answer: C.08 a.

Reference:

Training Manual for Reactor Operations, Automatic Shim Control Circuit

Section C - Plant and Rad Monitoring Systems and Radiological Control Procedures Question C.009 [1.0 point] (9.0)

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

a. Air Plenum 2 b. Bridge ALARA c. Room 114 d. Bridge

Answer: C.09 c.

Reference:

Training Manual for Reactor Operations, Area Radiation Monitor System

Question C.010 [1.0 point] (10.0) When the "Pressurizer Lo Press" annunciator alarms, it means that: a. Valve 537 has opened, reducing pressure to 70 psi. b. Valve 526 has opened, reducing pressure to 60 psi.

c. PS 945 has sensed a pressure of 60 psi. d. PS 941 has sensed a pressure of 70 psi.

Answer: C.10 c.

Reference:

Training Manual for Reactor Operations, Pressurizer System Lesson

Question C.011 [1.0 point] (11.0) Which ONE of the following is the approximate MAXIMUM capacity of the MURR liquid waste

disposal?

a. Approximately 5,000 gallons (five tanks with approximately 1,000 gallons capacity each).

b. Approximately 10,000 gallons (two tanks with approximately 5,000 gallons capacity each).

c. Approximately 15,000 gallons (three tanks with approximately 5,000 gallons capacity each).

d. Approximately 25,000 gallons (five tanks with approximately 5,000 gallons capacity each).

Answer: C.11 c.

Reference:

Training Manual for Reactor Operations, Liquid Radioactive Waste Disposal System

Section C - Plant and Rad Monitoring Systems and Radiological Control Procedures Question C.012 [1.0 point] (12.0)

The ventilation system has two backup doors located in the ventilation supply and return plenums which shut on containment isolation. Which ONE of the following is the method used to shut these doors? The doors are:

a. air motor operated, with their own emergency air supply tanks. b. held open by air pistons, which when vented, the doors close via gravity. c. motor operated, with air supplied from the emergency air supply system. d. held open by solenoid, which when deenergized, the door closes via gravity.

Answer: C.12 b.

Reference:

Facility Walk-Through

Question C.013 [1.0 point] (13.0) The Compensated Ion Chamber (CIC) detector provides a signal input for the: a. Source Range Monitor (SMR1). b. Intermediate Range Monitor (IRM 2).

c. Power Range Monitor (PRM 4) d. Wide Range Monitor (WRM).

Answer: C.13 d.

Reference:

Training Manual for Reactor Operations, Nuclear Instrumentation

Question C.014 [1.0 point] (14.0) The reactor has been operating for six days straight at full power when the facility has a complete loss of power. How is damage to the fuel prevented?

a. Two thermally (temperature) actuated valves open, allowing steam to escape from the primary system, which is quenched in the pool water.

b. Two air operated valves fail open due to loss of electrical power, lining up the primary to an in-pool heat exchanger. Water flow is via natural convection.

c. Two thermally (temperature) actuated valves open, lining up the primary to an in-pool heat exchanger. Water flow is via natural convection.

d. Two motor operated valves (powered off the diesel) open, lining up the primary to an in-pool heat exchanger.

Answer: C.14 b.

Reference:

Training Manual for Reacto r Operations, Valve Operating System

Section C - Plant and Rad Monitoring Systems and Radiological Control Procedures Question C.015 [1.0 point] (15.0) You are going to lower pool level lower than the surface block intake level. Prior to starting the evolution you must

a. close the upper suction and open the lower suction using the "T" wrench. b. do nothing, both suctions (upper and lower) are normally open. c. close the upper and open suctions the lower using the hand wheels on the valves. d. close the upper and open suctions the lower the switches in the control room (solenoid controlled air valves).

Answer: C.15 a.

Reference:

OP-RO-465, Pool Level Control - Skimmer System Step 5.3

Question C.016 [1.0 point] (16.0) The purification system contains a fission product monitor. This monitor detects radiation from fission products collected in -:

a. the filter. b. the holdup tank.

c. the cation column. d. the anion column.

Answer: C.16 d.

Reference:

Training Manual for Reactor Operations, Fission Product Monitor.

Question C.017 [1.0 point] (17.0) Temperature detectors 980A/B will provide a reactor scram in the event of high reactor coolant temperature. If they fail to initiate a scram, a backup scram signal is provided by:

a. TE901A. b. TE901B.

c. TE901C. d. TE980C/D.

Answer: C.17 b.

Reference:

Training Manual for Reactor Operations, Primary Coolant System

Section C - Plant and Rad Monitoring Systems and Radiological Control Procedures Question C.018 [1.0 point] (18.0) Which ONE of the following represents the normal flow rate of the ENTIRE primary coolant system at 10 MW power?

a. 1250 gpm. b. 1900 gpm. c. 2600 gpm. d. 3800 gpm.

Answer: C.18 d.

Reference:

Training Manual for Reactor Operations, Primary Coolant System Question C.019 [1.0 point] (19.0) Which ONE of the following is the reason that the pool demineralizer system water returns to the pool about 2 feet below the pool surface? In order to -

a. aid in the mixing of the water, which results in a more even temperature distribution. b. reduce pool surface temperature, since the demineralizer water is cooler than pool water.

c. reduce interference between the pool cooling system and the pool skimmer, which takes its suction at the pool surface.

d. create a blanket of warmer water at the top of the pool to reduce mixing, and therefore reduce the dose rate at the surface of the pool.

Answer: C.19 d.

Reference:

MURR HSR, § 7. 1. 10, Pool Coolant Cleanup System. 7-15.

Question C.020 [1.0 point] (20.0) During normal operation, a period on the Intermediate Range Monitor 2 (IRM2) reaches 10 seconds, the reactor will:

a. cause a rod run-in. b. cause a reactor scram.

c. have no effect on the operation.

d. prevent withdrawal of control rods.

Answer: C.20 a.

Reference:

Training Manual for Reactor Operations, Nuclear Instrumentation

Section C - Plant and Rad Monitoring Systems and Radiological Control Procedures

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