Text

Initial Examination Report, No. 50-407/OL-07-01, University of Utah Triga Reactor
	ML070100029
Person / Time
Site:	University of Utah
Issue date:	01/11/2007
From:	Doyle P; NRC/NRR/ADRA/DPR/PRTB
To:	Krahenbuhl M; Univ of Utah
	Doyle P, NRC/NRR/DPR/PRT, 415-1058
Shared Package
ML062330242	List: ML062330246; ML070100029; ML070100037;
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	05-407/07-001
	Download: ML070100029 (33)
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January 11, 2007 Dr. Melinda P. Krahenbuhl Reactor Administrator 122 S. Central Campus Drive Room 104 University of Utah Salt Lake City, UT 84112

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-407/OL-07-01, UNIVERSITY OF UTAH

Dear Dr. Krahenbuhl:

During the week of December 04, 2006, the NRC administered an operator licensing examination at your University of Utah Reactor. The examination was conducted according to NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1.

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 10 CFR 2.390 of the Commission's regulations, 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 (the Public Electronic Reading Room) 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. Paul V. Doyle Jr. at (301) 415-1058 or via internet e-mail pvd@nrc.gov.

Sincerely,

/RA/

Johnny Eads, Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-407

Enclosures:

1. Initial Examination Report No. 50-407/OL-07-01

2. Facility comments with NRC resolution

3. Examination and answer key (RO/SRO) cc w/encls:

Please see next page

Dr. Melinda P. Krahenbuhl Reactor Administrator 122 S. Central Campus Drive Room 104 University of Utah Salt Lake City, UT 84112

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-407/OL-07-01, UNIVERSITY OF UTAH

Dear Dr. Krahenbuhl:

During the week of December 04, 2006, the NRC administered an operator licensing examination at your University of Utah Reactor. The examination was conducted according to NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1.

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 10 CFR 2.390 of the Commission's regulations, 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 (the Public Electronic Reading Room) 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. Paul V. Doyle Jr. at (301) 415-1058 or via internet e-mail pvd@nrc.gov.

Sincerely,

/RA/

Johnny Eads, Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-407

Enclosures:

1. Initial Examination Report No. 50-407/OL-07-01

2. Facility comments with NRC resolution

3. Examination and answer key (RO/SRO) cc w/encls:

Please see next page DISTRIBUTION w/ encls.:

PUBLIC PRTB r/f JEads MMendonca Facility File (EBarnhill) O-6 F-2 ADAMS ACCESSION #: ML070100029 TEMPLATE #:NRR-074 OFFICE PRTB:CE IOLB:LA E PRTB:SC NAME Pdoyle:cah EBarnhill JEads DATE 01/10/2007 01/10/2007 01/11/2007 OFFICIAL RECORD COPY

University of Utah Docket No. 50-407 cc:

Mayor of Salt Lake City 451 South State Room 306 Salt Lake City, UT 84111 Dr. Raymond F. Gesteland Vice President for Research 201 S. Presidents Circle, Room 210 University of Utah Salt Lake City, UT 84112-9011 Dr. Dong-Ok Choe Reactor Supervisor 122 S. Central Campus Drive University of Utah Salt Lake City, UT 84112 Ms. Karen Langley Director, University of Utah Radiological Health 100 OSH, University of Utah Salt Lake City, UT 84112 Dr. Ronald J. Pugmire Associate Vice President for Research 210 Park, University of Utah Salt Lake City, UT 84112 Test, Research, and Training Reactor Newsletter Universities of Florida 202 Nuclear Sciences Center Gainesville, FL 32611 Dane Finerfrock, Director Division of Radiation Control Dept. Of Environmental quality 168 North 1959 West P.O. Box 144850 Salt Lake City, UT 84114-4850

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-407/OL-07-01 FACILITY DOCKET NO.: 50-407 FACILITY LICENSE NO.: R-126 FACILITY: University of Utah EXAMINATION DATES: December 04-07, 2006 SUBMITTED BY: __________/RA/_____________________ 01/09/2007

_____________

Paul V. Doyle Jr., Chief Examiner Date

SUMMARY

During the week of December 04, 2006, the NRC administered operator licensing examinations to six Senior Reactor Operator (Instant) [SRO(I)], candidates. Two SRO(I) candidates failed section A only of the written examination. One SRO(I) candidate failed sections A and C of the written examination and the operating test. Three SRO(I) candidates passed all portions of their respective examinations.

REPORT DETAILS

1. Examiners:

Paul V. Doyle Jr., Chief Examiner

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 0/0 3/3 3/3 Operating Tests 0/0 5/1 5/1 Overall 0/0 3/3 3/3

3. Exit Meeting:

Paul V. Doyle Jr., NRC, Examiner Dong-Ok Choe, Univ. Of Utah, Reactor Supervisor Melinda Krahenbuhl, Univ. Of Utah, Reactor Administrator The examiner thanked the facility for their support in the administration of the examinations. The examiner noted that the facility was very late in supplying material in support of the examination. In addition, the facility used applications which were four years out of date. The examiner reminded the facility that applications are available on-line, at the NRC web page. The facility discussed four corrections to the written examination (one no correct answer two typographical errors and one question with two correct answers. The examination attached to this report contains all suggested corrections.

ENCLOSURE 1

OPERATOR LICENSING EXAMINATION With Answer Key UNIVERSITY OF UTAH Week of December 04, 2006 Enclosure 2

Section A: L Theory, Thermodynamics & Facility Operating Characteristics Page 1 Question A.01 [1.0 point]

The number of neutrons passing through a square centimeter per second is the definition of which ONE of the following?

a. Neutron Population (np)

b. Neutron Impact Potential (nip)

c. Neutron Flux (nv)

d. Neutron Density (nd)

Question A.02 [1.0 point]

The Fast Fission Factor () is defined as The ratio of the number of neutrons produced by

a. fast fission to the number produced by thermal fission.

b. thermal fission to the number produced by fast fission.

c. fast and thermal fission to the number produced by thermal fission.

d. fast fission to the number produced by fast and thermal fission.

Question A.03 [1.0 point]

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 Question A.04 [2.0 points, 0.4 each]

Given a mother isotope of (35Br87)*, identify each of the daughter isotopes as a result of , +, -, , or n, decay.

a. 33 As83

b. 34 Se87

c. 35 Br86

d. 35 Br87

e. 36 Kr87

Section A: L Theory, Thermodynamics & Facility Operating Characteristics Page 2 Question A.05 [1.0 point]

Which ONE of the following is the definition of the term Cross-Section?

a. The probability that a neutron will be captured by a nucleus.

b. The most likely energy at which a charge particle will be captured.

c. The length a charged particle travels past the nucleus before being captured.

d. The area of the nucleus including the electron cloud.

Question A.6 [1.0 point]

Given the data in the table to the right, which ONE of the following is the closest to the half-life of the material?

a. 11 minutes TIME ACTIVITY 0 minutes 2400 cps

b. 22 minutes 10 minutes 1757 cps

c. 44 minutes 20 minutes 1286 cps

d. 51 minutes 30 minutes 941 cps 60 minutes 369 cps Question A.07 [1.0 point]

When performing rod calibrations, many facilities pull the rod out a given increment, then measure the time for reactor power to double (doubling time), then calculate the reactor period. If the doubling time is 42 seconds, what is the reactor period?

a. 29 sec

b. 42 sec

c. 61 sec

d. 84 sec Question A.08 [1.0 point]

Using the graphs provided in the handout. Choose the ONE which most closely depicts the reactivity versus time plot for xenon for the following evolution. Bring the reactor to 100% power (clean core) and operate for four days (96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months ). Shutdown the reactor for 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months . Bring the reactor to 50% power for a day (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ).

a. A

b. B

c. C

d. D

Section A: L Theory, Thermodynamics & Facility Operating Characteristics Page 3 Question A.09 [1.0 point]

Which ONE of the following is the reason that D2O is a better reflector than H2O? D2O has a

a. lower log energy decrement

b. higher log energy decrement

c. lower microscopic absorption cross-section a

d. higher microscopic absorption cross-section a Question A.10 [1.0 point]

Keff is K4 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)

Question A.11 [1.0 points]

Which ONE of the following causes indicated power (Startup Channel Count Rate) to stabilize several hours after a reactor trip? Assume reactor was operated for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months at 100 Kwatts, and no core alterations or changes in experiments.

a. Decay of compensating voltage at low power levels.

b. Actual power dropping below noise level for the instrumentation.

c. Decay of the longest lived delayed neutron precursor.

d. Subcritical multiplication of Source neutrons within the reactor.

Question A.12 [1.0 point]

You enter the control room and note that all nuclear instrumentation 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.

Section A: L Theory, Thermodynamics & Facility Operating Characteristics Page 4 Question A.13 [1.0 point]

The term Prompt Jump refers to

a. The instantaneous change in power due to control rod movement.

b. A reactor which has attained criticality on prompt neutrons only.

c. A reactor which is critical using both prompt and delayed neutrons.

d. A reactivity insertion equal to $1.00 Question A.14 [1.0 point]

Which one of the following statements details the effect of fuel temperature on core operating characteristics? As fuel temperature

a. increases, Doppler peaks will become higher.

b. decreases, resonance escape probability will increase.

c. decreases, U238 will absorb more neutrons.

d. increases, the fast non-leakage probability will decrease.

Question A.15 [1.0 point]

The reactor supervisor tells you that the Keff for the reactor is 0.955. How much reactivity must you add to the reactor to reach criticality?

a. +0.0471

b. +0.0450

c. -0.0471

d. -0.0450 Question A.16 [1.0 point]

Given an average rod reactivity worth of 0.1%/inch, and Tprompt of -0.005%k/EC. If fuel temperature were to increase by 150EC, how far and in what direction would you have to move the rod to compensate?

a. 7.5 inches, inward

b. 0.75 inches, inward

c. 7.5 inches, outward

d. 0.75 inches, outward

Section A: L Theory, Thermodynamics & Facility Operating Characteristics Page 5 Question A.17 [2.0 points, 1/2 each]

Using the drawing of the Integral Rod Worth Curve provided, identify each of the following reactivity worths.

a. Total Rod Worth 1. B - A

b. Actual Shutdown Margin 2. C - A

c. Technical Specification Shutdown Margin Limit 3. C - B

d. Excess Reactivity 4. D - C

5. E - C

6. E - D

7. E - A Question A.18 [1.0 point]

Which of the following atoms will cause a neutron to lose the most energy during an elastic scattering reaction?

a. O16

b. C12

c. U235

d. H1

Section B Normal, Emergency and Radiological Control Procedures Page 6 Question B.01 [1.0 point]

You note that 1 cm of a material (used as a shield) reduces the radiation level from a given source by a factor of 2.

If you add another nine cm of the material (for a total of 10 cm), you would expect the radiation level to be reduced by a factor of approximately ____ over no shielding. (Note: Ignore dose decrease due to distance, and decay.)

a. 20

b. 100

c. 200

d. 1,000 Question B.02 [1.0 point, a each]

Identify the source for the listed radioisotopes. Irradiation of air, water, or fission product.

a. N16

b. Ar41

c. Xe188 Question B.03 [2.0 points, 1/2 each]

Match the terms in column A with their respective definitions in column B.

Column A Column B

a. Radioactivity 1. The thickness of a material which will reduce a gamma flux by a factor of two.

b. Contamination 2. An impurity which pollutes or adulterates another substance. In radiological safety, contamination refers to the radioactive materials which are the sources of ionizing radiations.

c. Dose 3. The quantity of radiation absorbed per unit mass by the body or by any portion of the body.

d. Half-thickness 4. That property of a substance which causes it to emit ionizing radiation. This property is the spontaneous transmutation of the atoms of the substance.

Question B.04 [2.0 points, 1/2 each]

Match type of radiation (1 thru 4) with the proper penetrating power (a thru d)

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 (e.g., hydrogenous) material

d. Neutron 4. Best shielded by dense material

Section B Normal, Emergency and Radiological Control Procedures Page 7 Question B.05 [1.0 point]

The Emergency Response Plan defines Emergency Planning Zone (EPZ) as

a. within the walls of the CENTER (Rooms 1205A-G).

b. the area within a 100 meter radius of the reactor core centerline.

c. within the walls of the Merrill Engineering Building.

d. Geographical Area within the U of U campus Question B.06 [1.0 point]

The Quality Factor (QF) is used to convert

a. dose in rads to dose equivalent in rems.

b. dose in rems to dose equivalent in rads.

c. contamination in rads to contamination equivalent in rems.

d. contamination in rems to contamination equivalent in rads.

Question B.07 [1.0 point]

Maintenance on which ONE of the listed instrument channels requires the reactor to be in the shutdown condition with all control rods fully inserted, and power to the control-rod magnets and actuating solenoid switched off and the key removed?

a. Continuous Air Radiation Monitor

b. Reactor Tank Water Level

c. Startup Count Rate

d. Fuel Element Temperature Question B.08 [1.0 point]

A gamma source emits 8 R/hour @ 1 foot. How long could you work four (4) feet from the source without exceeding your yearly Whole body limit from 10CFR20? Assume you have already received 3 R this year.

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

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

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

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

Section B Normal, Emergency and Radiological Control Procedures Page 8 Question B.9 [1.0 point]

The University of Utah Emergency Plan states that the limits of 10 CFR 20 may be exceeded to rescue injured personnel. Which ONE of the following is the maximum dose equivalent limit for life saving, and who may authorize it?

a. 25 rem, Radiation Safety Officer

b. 25 rem, Reactor Supervisor

c. 75 rem, Radiation Safety Officer

d. 75 rem, Reactor Supervisor Question B.10 [1.0 point]

Which ONE of the following experiments is NOT allowed to be irradiated in accordance with Technical Specifications?

a. 9 millicuries of Iodine, singly encapsulated.

b. 24 milligrams of liquid fissionable material, doubly encapsulated.

c. 10 milligrams of explosive material, singly encapsulated.

d. any amount of Sodium, doubly encapsulated.

Question B.11 [1.0 point]

While attempting to fight a fire, the experimenter fighting it tells you that it's more than can be handled with local fire fighting equipment. What actions are you (the operator at the controls) required to take?

a. evacuate the building and contact the reactor supervisor.

b. take charge until the reactor supervisor arrives.

c. scram the reactor, sound the fire alarm, and order an evacuation of the laboratory.

d. scram the reactor, sound the fire alarm, and attempt to handle the fire using the fire hose in the cabinet outside the laboratory.

Question B.12 [1.0 point]

Which ONE of the following conditions would require you, (the console operator) to shutdown the reactor immediately?

a. The reactor period channel fails to a reading of -4

b. The ventilation exhaust fan failed two minutes ago.

c. The startup channel fails downscale (reading # zero).

d. The freon compressor EPR valve fails open.

Section B Normal, Emergency and Radiological Control Procedures Page 9 Question B.13 [1.0 point]

Listed below are the four standard emergency classifications defined by the NRC. Which ONE of the listed classifications is used at the University of Utah Research Reactor?

a. Alert

b. General Emergency

c. Site-Area Emergency

d. Unusual Event Question B.14 [1.0 point]

You initially remove a sample from the pool reading 1 R/hr at 30 cm from the source. You then replace the sample in the pool. An hour later you remove the sample and the reading is now 390 mR/hr at 30 cm. You again replace the sample back in the pool. How much longer should you wait to be able to bring out the sample without generating a high radiation area?

a. 1/2 hour

b. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

c. 11/2 hours

d. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Question B.15 [1.0 point]

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

a. The SL is a maximum operationally limiting value that prevents the LSSS from being reached during normal operations.

b. The SL is a parameter that ensures the integrity of the fuel cladding. The LSSS initiates protective action to preclude reaching the SL.

c. The LSSS is a parameter that ensures 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.

Question B.16 [1.0 point]

Which ONE of the following accidents has been designated as the maximum hypothetical accident at the U of U reactor facility?

a. Total loss of coolant from the reactor tank.

b. Rapid insertion of reactivity into the core.

c. Breaching of the cladding of a single fuel element during fuel handling.

d. Accidental misplacement of a single experiment with the maximum allowable reactivity worth.

Section B Normal, Emergency and Radiological Control Procedures Page 10 Question B.17 [1.0 point]

You perform the Semi-Annual Thermal Power Calibration with Reactor Power indicating 95% power. According to the power calculation indicated power was 8% below actual power. What action is required?

a. None.

b. Adjust the power channel in accordance with NEL-013.

c. Call the Reactor Supervisor and inform him that you have violated T.S. 3.1 Normal Operation.

d. Notify the U.S. Nuclear Regulatory Commission, Region IV, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Question B.18 [1.0 point]

At what power level is the startup source removed from the reactor?

a. 0.1 watt

b. 1.0 watt

c. 10 watts

d. 1 Kilowatt

Section C Facility and Radiation Monitoring Systems Page 11 Question C.01 [2.0 points, 1/2 each]

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

Column A Column B

a. High Radiation Level at Demineralizer. 1. Channeling in Demineralizer.

b. High Radiation Level downstream of Demineralizer. 2. Fuel element failure.

c. High flow rate through Demineralizer. 3. High temperature in Demineralizer system.

d. High pressure upstream of Demineralizer. 4. Clogged Demineralizer.

Question C.02 [1.0 point]

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.

Question C.03 [1.0 point]

WHICH ONE of the following detectors is used primarily to measure Ar41 released to the environment?

a. NONE, Ar41 has too short a half-life to require environmental monitoring.

b. Contiuous Air Monitor (Noble Gas)

c. Contiuous Air Monitor (Particulate)

d. Area Radiation Monitor (Stack)

Question C.04 [2.0 points, 1/2 each]

Identify the type of heat mechanism (listed in column B) primarily responsible for removing heat for each of the facility regions listed in column A.

Column A Column B

a. Centerline to outside edge of fuel 1. Conduction

b. Core to pool water 2. Forced Convection

c. Pool water to heat exchanger 3. Natural Convection

d. Heat exchanger to freon 4. Radiative

Section C Facility and Radiation Monitoring Systems Page 12 Question C.05 [1.0 point]

Which ONE of the following elements is used as the neutron absorber in the Shim-Safety rods?

a. Hafnium

b. Aluminum Clad Boron Carbide

c. Borated Stainless Steel

d. Cadmium Question C.06 [1.0 point]

Which ONE of the following parameters is NOT be measured in the Primary Coolant Circulation System Loop?

a. Temperature

b. Flow

c. Conductivity

d. pH Question C.07 [2.0 points, 1/4 each]

Using the figure provided in the handout, Identify each of the labeled components in the recirculation system.

a. 1. Rough cut demineralizer

b. 2. Fine cut demineralizer

c. 3. Conductivity Probe

d. 4. Filter

e. 5. Pre-Demineralizer Filter

f. 6. Post Demineralizer Filter

g. 7. Pump

h. 8. Flow Meter Question C.08 [1.0 point]

Which ONE of the following methods is used to reduce the mechanical shock to the shim-safety rods on a reactor scram?

a. A small spring is located on the bottom of the absorber rod.

b. A piston moves into a dashpot as the rod nears the bottom of its travel.

c. An electro-mechanical brake is energized as the rod nears the bottom of its travel.

d. A small spring is located at the top of the absorber rod.

Section C Facility and Radiation Monitoring Systems Page 13 Question C.09 [1.0 point]

Which ONE of the following reflector materials is in the cans surrounding the core?

a. Heavy water (D2O)

b. Graphite (C)

c. Beryllium (Be)

d. Polyethylene Question C.10 [1.0 point]

Which ONE of the following methods is used to compensate for gamma radiation in a Compensated Ion Chamber?

a. Pulses smaller than a height (voltage) are stopped by a pulse-height discriminator circuit from entering the instrument channels amplifier.

b. The chamber contains concentric tubes one of which detects both neutrons and gammas the other only gammas, are wired electronically to subtract the gamma signal, leaving only the signal due to neutrons.

c. The signal travels through a Resistance-Capacitance (RC) circuit, converting the signal to a power change per time period effectively deleting the signal due to gammas.

d. A compensating voltage equal to a predetermined source gamma level is fed into the pre-amplifier electronically removing source gammas from the signal. Fission gammas are proportional to reactor power and therefore not compensated for.

Question C.11 [1.0 point]

Which ONE of the following describes the operation of the ventilation system in the event of a release of particulate or gaseous activity?

a. The inlet isolation damper closes and the reactor room filter damper opens forcing air through the filter and maintaining a negative pressure in the reactor room .

b. The inlet and outlet dampers close and the dampers for the reactor room and hood filter open to route the building air through the filtration system.

c. The inlet and outlet dampers close and the air is bypassed through a HEPA filtration system maintaining the reactor room at a negative pressure.

d. The outlet damper closes forcing air through the HEPA filter and maintaining the reactor room at a slight positive pressure in relation to the laboratory.

Question C.12 [1.0 point]

Two alarms provide sight and sound indication of high radiation conditions in the reactor room and at Campus Security Headquarters. Which ONE of the following choices lists these two alarms?

a. Reactor Tank area radiation monitor and Neutron Generator Monitor

b. Reactor Tank area radiation monitor and Reactor pool low water level.

c. Pool Top area radiation monitor and Neutron Generator Monitor

d. Pool top area radiation monitor and Reactor pool low water level.

Section C Facility and Radiation Monitoring Systems Page 14 Question C.13 [1.0 point]

On the control panel the indicating lights for the SHIM rod are as follows: the CONT light is OFF, the UP light is ON and the DOWN light is OFF. What is the condition of the Shim Rod?

a. The rod mechanism is at the top of travel, but the rod is at the bottom.

b. The rod mechanism and the rod are both at the top of travel.

c. The rod mechanism and the rod are both at the bottom of travel.

d. The rod mechanism and the rod are both at the bottom of travel.

Question C.14 [1.0 point]

Immediately upon loss of normal AC power to the facility the security system will receive power from

a. a temporary AC generator located at the EPA ground station

b. temporary batteries which will be installed by University Maintenance personnel.

c. a 12 VDC battery system installed within the facility.

d. emergency generators located at the Hospital Generating Plant.

Question C.15 [1.0 point]

Which ONE of the following correctly describes how the Control Element position indication on the console is generated?

a. As the rod moves out, the impedance of a pick-up coil changes, generating a change in voltage proportional to rod position.

b. A chain driven mechanical position indicator, generates a signal sent to a servo motor in the console.

c. A series of limit switches open and close as the rod passes, generating a change in voltage proportional to rod position.

d. A ten turn potentiometer generates a signal based proportional to rod movement.

Question C.16 [1.0 point]

Which ONE of the following would be the first indication of a pinhole leak in a fuel element in the core?

a. The CAM would indicate an increasing trend in background radiation over a period of days.

b. The monthly gamma spectroscopy of the CAM filters would reveal a measurable Kr85 concentration.

c. The detection of a 151 KeV gamma on the germanium crystal attached to the peristaltic pump.

d. The monthly gamma spectroscopy of tank water would reveal a concentration of long-lived soluble products.

Section C Facility and Radiation Monitoring Systems Page 15 Question C.17 [1.0 point]

Which ONE of the following is the NORMAL method for adding makeup water to the reactor?

a. Directly to the top of the core using a hose.

b. At the suction of the cooling pump.

c. At the inlet to the filter prior to the demineralizer.

d. At the discharge of the filter after the demineralizer.

Section A: L Theory, Thermodynamics & Facility Operating Characteristics Page 16 A.01 c REF: Introduction to Nuclear Reactor Operations, ©1982, Reed Robert Burn § A.02 c REF: Introduction to Nuclear Reactor Operations, ©1982, Reed Robert Burn § A.03 d REF: Introduction to Nuclear Reactor Operations, ©1982, Reed Robert Burn § A.04 a, ; b, +; c, n; d, ; e, -

REF: STD NRC question.

A.07 c REF: ln (2) = -time/ = time/(ln(2)) = 60.59 . 61 seconds A.08 a REF: Introduction to Nuclear Reactor Operations, ©1982, Reed Robert Burn § A.09 c REF: Burn, Reed Robert, Introduction to Nuclear Reactor Operations, © December 1988, § 2.7, Table 2.4 A.10 b REF: Introduction to Nuclear Reactor Operations, ©1982, Reed Robert Burn § A.11 d REF: Burn, Reed Robert, Introduction to Nuclear Reactor Operations, © December, 1988, § 5.2.1 - 5.3 pp. 5 5-13.

Keff2) = (0.9550 - 1.0000) ÷ (0.9550

1.0000)

= -0.0450 ÷ 0.9550 = -0.0471 A.16 c REF: -0.00005k/EC x +150EC = -0.0075 k of reactivity added. To compensate, must add +0.0075 k.

+0.0075k ÷ 0.001 k/inch = 7.5 inches in the positive or outward direction A.17 a, 7; b, 2; c, 6; d, 5 REF:

Section B Normal, Emergency and Radiological Control Procedures Page 17 B.01 d REF: 210 = 1,024 . 1,000 B.02 a, water; b, air; c, fission product REF: Standard NRC question B.03 a, 4; b, 2; c, 3; d, 1 REF: Standard NRC question B.04 a, 4; b, 2; c, 1; d, 3 REF: Standard NRC question B.05 c REF: Emergency Response Plan § 1.0 Definitions: Emergency Planning Zone.

B.06 a REF: 10CFR20.1003 Definitions, also the University of Utah, Radiation Protection Program, Biological Effects of Radiation, page 3.

B.07 d REF: Technical Specifications § 3.3.2, Table Note (b), also § 3.3.3, Table Note (a 8 R B.08 c D1R12 = D2 R22 D 2 = D1 R 12 R 22 hr 4 2

D2 = 8 R 1 2 = hr 16

=

1 R 2 hr Stay time = Total allowed dose (5R) less amount already received (3R) divided by 1/2 R/hr. 2 ÷ 1/2 = 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

REF:

B.09 c REF: U. Utah Emergency Plan, § 7.2 Protective Action Values B.10 c REF: Technical Specification 3.6 Limitations on Experiments B.11 c REF: Emergency Procedures, Fire in the Laboratory or Irradiator B.12 c REF: U of U TS 3.3.3 Reactor Safety System (Loss of Startup Count Rate Interlock)

B.13 d REF: U. Utah Emergency Plan § 4.0, Emergency Classification System B.14 c REF: Burn, Reed Robert, Introduction to Nuclear Reactor Operations, © December, 1988, Appendix 3. Solving for LAMBDA (): It = I0 e-t 390 mR/hr ÷ 1000 mR/hr = e-1hr ln(0.39) = -

1 hr. = 0.9416 hour-1 SOLVING for additional time: If = It e-t 100mR/hr = 390 mR/hr e-0.9416 (time) ln (0.25) = -0.9163

time time = 1.4454 B.15 b REF: Technical Specifications T.S. 1 Definitions B.16 c Ref: SER § 14.1 Fuel Handling Accident B.17 b REF: Description of Operation § III.II.D.1.b B.18 b REF: Form NEL-001 TRIGA START-UP CHECKLIST

Section C Facility and Radiation Monitoring Systems Page 18 C.01 a, 2; b, 3; c, 1; d, 4 REF: Standard NRC Question C.02 b REF: Standard NRC question.

C.03 b REF: Description of Operations, Chapt. V. TRIGA L Console, § I.E, Radiation Monitors.

C.04 a, 1; b, 3; c, 2; d, 2 REF: Standard NRC question C.05 b REF: Modification Authorization M-1, figure 1.

C.06 d REF: SER § 5.0.

C.07 a, 8; b, 2; c, 1; d, 4; e, 3; f, 6; g, 5; h, 7 REF: Form CENTER-006, Rev 3, Figures 1 and 2 (combined).

C.08 d REF: Modification Authorization M-1. Figures 1 and 2.

C.09 a REF: Description of Operations, Chapt. II L Operations, § F.7.

C.10 b REF: Standard NRC question.

C.11 c REF: Description of Operations, § III.IV.D C.12 d REF: Description of Operation, § III.I.B.2 C.13 a REF: Hardware Description (Post 1984) Control Rods, also examination administered 03/1995 C.14 c REF: Description of Operations, § IV.III Auxiliary Power System.

C.15 d REF: Hardware description (Post 1984), Control Rods, also 1995 NRC examination C.16 d REF: Description of Operation, Maintenance and Surveillance of the TRIGA Reactor and Support Systems, § III.B.2 Pin Hole Leak C.17 c REF: Form NEL-008 Procedure for Adding Water to the Reactor Tank.

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: University of Utah REACTOR TYPE: TRIGA DATE ADMINISTERED: 2007/12/04 CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

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

%of Category % of Candidate Category Value Total Score Value Category A. Reactor Theory, Thermodynamics, and Facility Operating 20 33 _____ _____ Characteristics B. Normal and Emergency Operating Procedures and Radiological 21 33 _____ _____ Controls C. Plant and Radiation Monitoring Systems 20 33 _____ _____

61 _____ _____ TOTALS FINAL GRADE All 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 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 answer sheets.

10. Ensure all information you wish to have evaluated as part of your answer is on your answer sheet.

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 SHEET 44444444444444444444444444444444444444444444444444444444444444444444444444444444444444 DR Rem, Ci curies, Fuchs Pulse Model Equations (Estimates)

E Mev, R feet 2( ) ( )2 2( )

Tmax = T0 °C Pmax = MW Etot = MWS 2 ( k ) I k ( )

I = 39 x10-6 sec. = 1.26 x 10-4k/k/EC k = 9.6 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 L Theory, Thermo & Fac. Operating Characteristics Page 22 A.01a + - n ___ A.09 a b c d ___

A.01b + - n ___ A.10 a b c d ___

A.01c + - n ___ A.11 a b c d ___

A.01d + - n ___ A.12 a b c d ___

A.01e + - n ___ A.13 a b c d ___

A.02 a b c d ___ A.14 a b c d ___

A.03 a b c d ___ A.15 a b c d ___

A.04 a b c d ___ A.16 a b c d ___

A.05 a b c d ___ A.17a 1 2 3 4 5 6 7 ___

A.06 a b c d ___ A.17b 1 2 3 4 5 6 7 ___

A.07 a b c d ___ A.17c 1 2 3 4 5 6 7 ___

A.08 a b c d ___ A.17c 1 2 3 4 5 6 7 ___

A.18 a b c d ___

Section B Normal/Emerg. Procedures & Rad Con Page 23 B.01 a b c d ___ B.06 a b c d ___

B.02a air water F.P. ___ B.07 a b c d ___

B.02b air water F.P. ___ B.08 a b c d ___

B.02c air water F.P. ___ B.09 a b c d ___

B.03a 1 2 3 4 ___ B.10 a b c d ___

B.03b 1 2 3 4 ___ B.11 a b c d ___

B.03c 1 2 3 4 ___ B.12 a b c d ___

B.03d 1 2 3 4 ___ B.13 a b c d ___

B.04a 1 2 3 4 ___ B.14 a b c d ___

B.04b 1 2 3 4 ___ B.15 a b c d ___

B.04c 1 2 3 4 ___ B.16 a b c d ___

B.04d 1 2 3 4 ___ B.17 a b c d ___

B.05 a b c d ___ B.18 a b c d ___

Section C Plant and Radiation Monitoring Systems Page 24 C.01a 1 2 3 4 ___ C.07d 1 2 3 4 5 6 7 ___

C.01b 1 2 3 4 ___ C.07e 1 2 3 4 5 6 7 ___

C.01c 1 2 3 4 ___ C.07f 1 2 3 4 5 6 7 ___

C.01d 1 2 3 4 ___ C.07g 1 2 3 4 5 6 7 ___

C.02 a b c d ___ C.07h 1 2 3 4 5 6 7 ___

C.03 a b c d ___ C.08 a b c d ___

C.04a 1 2 3 4 ___ C.09 a b c d ___

C.04b 1 2 3 4 ___ C.10 a b c d ___

C.04c 1 2 3 4 ___ C.11 a b c d ___

C.04d 1 2 3 4 ___ C.12 a b c d ___

C.05 a b c d ___ C.13 a b c d ___

C.06 a b c d ___ C.14 a b c d ___

C.07a 1 2 3 4 5 6 7 ___ C.15 a b c d ___

C.07b 1 2 3 4 5 6 7 ___ C.16 a b c d ___

C.07c 1 2 3 4 5 6 7 ___ C.17 a b c d ___

Figure for Question A.08 a b c d

Figure for Question A.17 Figure for Question C.07

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