ML100190858

Initial Examination Report, No. 50-274/OL-10-01, U. S. Geological Survey Triga Reactor

ML100190858
Person / Time
Site:	U.S. Geological Survey
Issue date:	01/22/2010
From:	Johnny Eads Research and Test Reactors Branch B
To:	Timothy Debey US Dept of Interior, Geological Survey (USGS)
Doyle P, NRC/NRR/DPR/PRTB, 415-1058
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ML093030622	List: ML100190858 ML100191417
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50-274/OL-10-01
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Text

January 22, 2010

Mr. Timothy DeBey Reactor Director U.S. Geological Survey Box 25046 - Mail Stop 424 Denver Federal Center Denver, CO 80225

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-274/OL-10-01, U.S. GEOLOGICAL SURVEY TRIGA REACTOR

Dear Mr. DeBey:

During the week of January 11, 2010, the Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your U.S. Geological Survey TRIGA 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. Paul V. Doyle, Jr. at (301) 415-1058 or via internet e-mail paul.doyle@nrc.gov.

Sincerely,

/RA/ Johnny H. Eads, Jr., Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-274

Enclosures:

As stated

cc: see next page

ML100190858 NRR-074 OFFICE PRTB:CE IOLB:L AEPRTB:SC NAME PDoyle: CRevelleJEads DATE 01/19/2010 01

/21/201001/22/2010C = COVER E = COVER & ENCLOSURE N = NO COPY U.S. Geological Survey Docket No. 50-274 cc: Mr. Brian Nielsen Environmental Services Manager 480 S. Allison Pkwy. Lakewood, CO 80226 Mr. Eugene W. Potter State of Colorado Radiation Management Program HMWM-RM-B2 4300 Cherry Creek Drive South Denver, CO 80246 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.: 50-274/OL-10-01

FACILITY DOCKET NO.: 50-274

FACILITY LICENSE NO.: R-113

FACILITY: U.S. Geological Survey TRIGA Reactor

EXAMINATION DATES: January 12, 2010

SUBMITTED BY: __________________________ _________

Paul V. Doyle Jr., Chief Examiner Date

SUMMARY

On January 12, 2010 the NRC administered operator licensing examinations to one Reactor Operator and one Senior Reactor Operator (upgrade) license candidate. Both candidates passed all portions of the administered examinations.

REPORT DETAILS

1. Examiners: Paul V. Doyle Jr., Chief Examiner, NRC

2. Results:

RO PASS/FAILSRO PASS/FAILTOTAL PASS/FAIL Written 1/0 0/01/0 Operating Tests1/0 1

/02/0 Overall 1/0 1

/02/0 3. Exit Meeting:

Paul V. Doyle Jr., NRC, Examiner Timothy DeBey, USGS, Reactor Supervisor

The examiner thanked the facility staff for their support in the administration of the examination.

The Reactor Supervisor, pointed out two typographic errors in the answer key, the examiner agreed. The examination included with this report has been corrected, per facility comment and examiner review.

ENCLOSURE 1 OPERATOR LICENSING INITIAL EXAMINATION With Answer Key

U.S. Geological Survey TRIGA Week of January 11, 2010 ENCLOSURE 2 Section A L Theory, Thermo & Facility Operating Characteristics Page 1 QUESTION A.01 [1.0 point]

A reactor similar to the U.S.G.S reactor was operated at full power for one week when a scram occurred. Twelve hours later, the reactor is brought critical and quickly raised to full power. Considering xenon effects only, to maintain a constant power level for the next few hours, control rods must be:

a. inserted

b. maintained at the present position

c. withdrawn

d. withdrawn, then inserted to the original position

QUESTION A.02 [1.0 point]

Which ONE of the following is the reason for the -80 second period following a reactor scram?

a. The negative reactivity added during a scram is greater than -effective

b. The longest lived delayed neutron precursor half life is 55 seconds

c. The fuel temperature coefficient adds positive reactivity as the fuel cools down, thus retarding the rate at which power drops

d. The amount of negative reactivity added is greater than the Shutdown Margin

QUESTION A.03 [1.0 point] Which ONE of the following is true concerning the differences between prompt and delayed neutrons?

a. Prompt neutrons account for less than one percent of the neutron population while delayed neutrons account for approximately ninety-nine percent of the neutron population

b. Prompt neutrons are released during fast fissions while delayed neutrons are released during thermal fissions

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

d. Prompt neutrons are the dominating factor in determining the reactor period while delayed neutrons have little effect on the reactor period QUESTION A.04 [1.0 point]

Which ONE of the following will be the resulting stable reactor period when a $0.25 reactivity insertion is made into an exactly critical reactor core? (Assume a eff of .0070 and a lambda of 0.1 sec

-1)

a. 50 seconds

b. 38 seconds

c. 30 seconds

d. 18 seconds

Section A L Theory, Thermo & Facility Operating Characteristics Page 2 QUESTION A.05 [1.0 point]

Reactor power doubles in 0.66 minutes (40 seconds). Which ONE of the following is the time required for power to increase from 10 watts to 800 watts? (Assume a positive step change in reactivity.)

a. 10.1 minutes

b. 6.4 minutes

c. 4.2 minutes

d. 2.8 minutes

QUESTION A.06 [1.0 point]

Which ONE of the following statements describes the difference between Differential and Integral (IRW) rod worth curves?

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

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

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

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

QUESTION A.07 [1.0 point]

If a $1.50 pulse has a peak power of 250 MW, a FWHM of 100 ms, and a fuel temperature rise of 145°C, what would you estimate the peak power, FWHM, and fuel temperature rise values would be for a $2.00 pulse?

a. Peak power: 780 MW FWHM: 80 ms Temp. rise: 210°C

b. Peak power: 1000 MW FWHM: 50 ms Temp. rise: 290°C

c. Peak power: 1200 MW FWHM: 50 ms Temp. rise: 350°C

d. Peak power: 900 MW FWHM: 80 ms Temp. rise: 210°C QUESTION A.08 [1.0 point]

Which ONE of the following coefficients will be the first (fastest acting) to start turning reactor power after a step change in power?

a. Fuel-moderator Temperature

b. Coolant-moderator Temperature

c. Void

d. Power

Section A L Theory, Thermo & Facility Operating Characteristics Page 3 QUESTION A.09 [2.0 points a each] For the following terms (a through F) pick a definition (1 through 6) which most clearly describes the term.

a. Subcritical Multiplication 1. Substance used in a reactor to reduce the energy of neutrons to the energy at which there is a high probability of causing fissioning of the fuel.

b. Reactor Period 2. Different forms of the same chemical element which differ only by the number of neutrons in the nucleus.

c. Reactivity 3. The time required for neutron flux (power) to change by a factor of e (2.718).

d. Moderator 4. The multiplication of source neutrons resulting from reactivity addition.

e. Shutdown Margin 5. A measure of the deviation from critical.

f. Isotope 6. A measure of the reactivity which must be added to a shutdown reactor to make it just critical.

QUESTION A.10 [1.0 point] Question rewritten to incorporate facility comment see answer sheet.

Approximately how much reactivity would have to be added to go from 100 kw to 900 kw?

a. $3.20

b. $2.10 $2.40 c. $1.20

d. $0.50

QUESTION A.11 [1.0 point]

Which alteration or change to the core will most strongly affect the thermal utilization factor?

a. Build up of fission products in fuel.

b. Removal of a control rod.

c. Removal of moderator.

d. Addition of U-238

QUESTION A.12 [1.0 point]

Which one of the following describes the MAJOR contributor to the production and depletion of Xenon respectively in a STEADY-STATE OPERATING reactor?

Production Depletion

a. Radioactive decay of Iodine Radioactive Decay

b. Radioactive decay of Iodine Neutron Absorption

c. Directly from fission Radioactive Decay

d. Directly from fission Neutron Absorption

Section A L Theory, Thermo & Facility Operating Characteristics Page 4 QUESTION A.13 [1.0 point]

You perform two initial startups a day apart. Each of the startups has the same starting conditions. (E.g. core burnup, pool, fuel temperature and starting count rate are the same.) The only difference between the two startups is that during the SECOND startup you stop for 10 minutes to answer the phone. For the second startup compare the critical rod height and count rate to the first startup.

Rod Height Count Rate

a. Higher Same

b. Lower Same

c. Same Lower

d. Same Higher

QUESTION A.14 [1.0 point]

Which one of the following factors has the LEAST effect on K eff?

a. Fuel burnup.

b. Increase in fuel temperature.

c. Increase in moderator temperature.

d. Xenon and samarium fission products.

QUESTION A.15 [1.0 point]

Which ONE of the following describes the response of the reactor to EQUAL amounts of reactivity insertion as the reactor approaches critical (K eff =1.0)? The change in neutron population per reactivity insertion is -

a. smaller, and it requires a longer time to reach a new equilibrium count rate.

b. larger, and it requires a longer time to reach a new equilibrium count rate.

c. smaller, and it requires a shorter time to reach a new equilibrium count rate.

d. larger, and it takes an equal amount of time to reach a new equilibrium count rate.

QUESTION A.16 [1.0 point]

About two minutes following a reactor scram, period has stabilized, and is decreasing at a CONSTANT rate. If reactor power is 10

-5 % full power what will the power be in three minutes.

a. 5 x 10-6 % full power

b. 2 x 10-6 % full power

c. 1 x 10-6 % full power

d. 5 x 10-7 % full power

Section A L Theory, Thermo & Facility Operating Characteristics Page 5 QUESTION A.17 [1.0 point]

Which ONE of the following isotopes has the largest microscopic cross-section for absorption for thermal neutrons?

a. Sm 149 b. U 235

c. Xe 135

d. B 10 QUESTION A.18 [1.0 point]

During the neutron cycle from one generation to the next, several processes occur that may increase or decrease the available number of neutrons. Which ONE of the following factors describes an INCREASE in the number of neutrons during the cycle?

a. Thermal utilization factor.

b. Resonance escape probability.

c. Thermal non-leakage probability.

d. Fast fission factor.

QUESTION A.19 [1.0 point]

A reactor is slightly supercritical with the following values for each of the factors in the six-factor formula:

Fast fission factor = 1.03 Fast non-leakage probability = 0.84 Resonance escape probability = 0.96 Thermal non-leakage probability = 0.88 Thermal utilization factor = 0.70 Reproduction factor = 1.96

A control rod is inserted to bring the reactor back to critical. Assuming all other factors remain unchanged, the new value for the thermal utilization factor is:

a. 0.698

b. 0.702

c. 0.704

d. 0.708

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

In accordance with the Technical Specifications, given the control rod worths and excess reactivity below, calculate the minimum shutdown margin.

Shim rod = 1.8% delta k/k Regulating rod = 2.5% delta k/k Safety rod = 2.0% delta k/k Transient rod = 2.1% delta k/k Excess reactivity = 4% delta k/k

a. 1.8% delta k/k.

b. 1.9% delta k/k.

c. 4.4% delta k/k.

d. 8.4% delta k/k.

QUESTION B.02 [1.0 point] Which ONE of the following is NOT a required condition for the reactor to be considered "Shutdown"?

a. No work is in progress involving fuel handling or maintenance of control mechanisms.

b. The console key is in the "OFF" position and the key is removed from the console and under the control of a licensed operator.

c. The minimum shutdown margin, with the most reactive of the operable control elements withdrawn shall be $1.10 d. Sufficient control rods are inserted so as to assure the reactor is subcritical by a margin greater than $0.70, cold without Xenon.

QUESTION B.03 [1.0 point] Which ONE of the following would be a Class I experiment? a. A new experiment.

b. A previously run experiment.

c. A major modification of a previous experiment.

d. An experiment with a reactivity worth greater than necessary to produce a prompt critical condition in the reactor.

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

Match the USGS Requalification Plan requirements in Column A for an actively licensed operator with the correct time period from Column B. Column B answers may be used once, more than once, or not at all.

Column A Column B

a. License Expiration 1. 1 year

b. Medical Examination 2. 2 years

c. Requalification Written Examination 3. 3 years

d. Requalification Operating Test 4. 6 years

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

In accordance with the Emergency Plan, "onsite" means:

a. the area within the site boundary.

b. the area within the operations boundary.

c. the reactor facility.

d. the protected area.

QUESTION B.06 [1.0 point]

In accordance with 10 CFR 20, the "Annual Limit on Intake (ALI)" refers to:

a. the amount of radioactive material taken into the body by inhalation or ingestion in one (1) year which would result in a committed effective dose equivalent of five (5) rems.

b. the dose equivalent to organs that will be received from an intake of radioactive material by an individual during the 50-year period following the intake.

c. limits on the release of effluents to an unrestricted environment.

d. the concentration of a given radionuclide in air which, if breathed for a working year of 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, would result in a committed effective dose equivalent of five (5) rems.

QUESTION B.07 [1.0 point]

A survey instrument with a window probe is used to measure the beta-gamma dose rate from an irradiated experiment. The dose rate with the window open is 100 mrem/hour, and the dose rate with the window closed is 60 mrem/hour. The beta dose rate is:

a. 40 mrem/hour.

b. 60 mrem/hour.

c. 100 mrem/hour.

d. 160 mrem/hour.

QUESTION B.08 [1.0 point] Question modification per facility comment An All of the reactor room area radiation monitors are is out of service while being repaired. As a result:

a. the reactor cannot be operated.

b. the reactor can continue to operate.

c. the reactor can continue to operate only if the alarm setpoints of other area radiation monitors are lowered.

d. the reactor can continue to operate only if the monitor is replaced by a portable gamma-sensitive ion chamber.

Section B Normal, Emergency and Radiological Control Procedures Page 8 QUESTION B.09 [1.0 point]

Which ONE of the following activities requires the direct presence (supervision) of a senior licensed operator?

a. Removal of one (1) fuel element.

b. Removal of control rod for inspection.

c. Reactor power calibration.

d. Control rod drop time measurement.

QUESTION B.10 [1.0 point]

Two point sources have the same curie strength. Source A's gammas have an energy of 1 Mev, whereas Source B's gammas have an energy of 2 Mev. You obtain readings from the same GM tube and Ion Chamber at 10 feet from each source. Concerning the four readings, which ONE of the following statements is correct?

a. The reading from Source B is twice that of Source A for both meters.

b. The reading from Source B is twice that of Source A for the Ion chamber but the same for the GM tube.

c. The reading from Source B is half that of Source A for the GM tube, but the same for the Ion Chamber.

d. The reading from both sources are the same for both meters.

QUESTION B.11 [1.0 point]

How often is a "Stack Gas Analysis" required to be performed?

a. Annually

b. Semiannually

c. Quarterly

d. Monthly

QUESTION B.12 [1.0 point]

In order to maintain your license 'active' in accordance with 10 CFR 55.53.f(2), you must perform the functions of your license position for a minimum of -

a. 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> per calendar month

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

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

d. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> per calendar quarter

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

While removing a pneumatic system terminus from the core the reactor-

a. must be shutdown

b. may be critical, at a power level less than 100 watts

c. may be critical at any power level.

d. may be critical at any power level but only if it has been operated for less then 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

QUESTION B.14 [1.0 point]

An irradiated sample (t 1/2 = 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />) is measure as having a dose rate of 200 mrem/hr at 1 foot. Which ONE of the following is the CLOSEST DISTANCE to the source that a "RADIATION AREA" sign can be posted (assume no shielding)?

a. 1.4 feet

b. 2.4 feet

c. 4.5 feet

d. 14.1 feet

QUESTION B.15 [1.0 point]

According to Technical Specifications, the only mode in which the withdrawal of any control rod other than the pulse rod is prevented is the -

a. Auto mode.

b. Square-Wave mode.

c. Steady-State mode.

d. Pulse mode.

QUESTION B.16 [1.0 point]

Which ONE of the following statements is TRUE with regard to experiments?

a. The reactivity worth of any in-core experiment shall be limited to $3.00.

b. Explosive materials in quantities greater than 25 milligrams shall not be irradiated in the reactor.

c. Experiments containing materials corrosive to reactor components shall not be irradiated in the reactor.

d. Explosive materials in quantities greater than 25 milligrams may be irradiated provided that the resulting pressure upon detonation does not exceed the design pressure of the reactor building.

Section B Normal, Emergency and Radiological Control Procedures Page 10 QUESTION B.17 [2.0 points, 1/2 each]

Match the condition listed in column A with the appropriate emergency class in Column B. (Column B answer may be used once, more than once, or not at all.)

Column A Column B

a. Sustained fire in facility NOT involving reactor controls or materials. 1. Notification of Unusual Event

b. Continuous Air Monitor reading exceeds 10K cpm above background. 2. Alert

c. Fire which damages reactor controls. 3. Site Area Emergency

d. Report of Tornado winds which COULD strike the facility.

QUESTION B.18 [1.0 point]

Preparations are being made to measure the elongation and bending of many fuel elements. Which ONE of the following staffing requirements applies at the start of the fuel movement?

a. A Senior Reactor Operator in charge

b. A Senior Reactor Operator in charge, a Reactor Operator at the console

c. A Senior Reactor Operator in charge, a Reactor Operator at the console, a reactor Health Physicist

d. A Senior Reactor Operator in charge, a Reactor Operator at the console, the Reactor Supervisor

Section C Plant and Rad Monitoring Systems and Radiological Control Procedures Page 11 QUESTION C.01 [1.0 point]

Which ONE is NOT an input to the Regulating Rod Servo?

a. NM1000 channel

b. % demand potentiometer

c. Rod raising interlock

d. Period channel

QUESTION C.02 [1.0 point]

Limit switches mounted on each drive assembly provide switching for console lights. What is the significance of a "MAGENTA" rod color and a "BLACK" magnet box?

a. Rod and drive completely withdrawn, magnet making contact.

b. Reactor scram, control rod drive down.

c. Drive between limits, rod down, no magnet current.

d. Drive completely up, rod is down, no magnet contact.

QUESTION C.03 [1.0 point]

Which ONE of the following describes the action of the rod control system to drive the magnet draw tube down after a dropped rod?

a. Resetting the scram signal initiates the rod down motion of the draw tube.

b. Deenergizing the rod magnet initiates the rod down motion of the draw tube.

c. Actuation of the MAGNET DOWN limit switch initiates the rod down motion of the draw tube.

d. Actuation of the ROD DOWN limit switch initiates the rod down motion if the rod drive is withdrawn.

QUESTION C.04 [1.0 point] Word added per examiner answer to candidate question.

The Air Particulate Monitor "Low Alert" alarm is activated at:

a. 1000 cps

b. 3000 cps

c. 3000 cpm

d. 10K cpm

Section C Plant and Rad Monitoring Systems and Radiological Control Procedures Page 12 QUESTION C.05 [1.0 point] Which one of the following set of devices is tested when the TRIGA control system is in the PRESTART mode?

a. Fuel temperature scram circuits

1. NM1000 scram circuits

1. Interlock preventing control rod withdrawal with low neutron level

b. DAC Watchdog timer

1. NPP High Voltage Scram

1. NM1000 power level calibration

c. Interlock preventing simultaneous withdrawal of two control rods

1. Fuel temperature scram circuits

1. NPP1000 High % power scram

d. NM1000 scram circuits

1. Key Switch in the OFF position

1. DAC Watchdog timer QUESTION C.06 [1.0 point]

Which ONE of the following temperatures is measured by the thermocouples in the instrumented fuel element?

a. Inside surface of the fuel element cladding.

b. Outer surface of the fuel.

c. Interior of the fuel.

d. Center of the zirconium rod.

QUESTION C.07 [1.0 point]

Pool water conductivity in the purification system is measured:

a. at the inlet to the demineralizer.

b. at the outlet of the flow meter.

c. at the discharge of the pump.

d. at the inlet of the filter.

QUESTION C.08 [1.0 point]

The reactor is in the AUTOMATIC mode at a power level of 500 kW. The neutron detector from which the control system receives its input signal fails low (signal suddenly goes to zero). As a result:

a. the control system inserts the regulating rod to reduce power, to try to match the power of the failed detector.

b. the control system drops out of the AUTOMATIC mode into the MANUAL mode.

c. the control system withdraws the regulating rod to try to increase power.

d. the reactor scrams.

Section C Plant and Rad Monitoring Systems and Radiological Control Procedures Page 13 QUESTION C.09 [1.0 point]

Which ONE of the following is the purpose of the bottom grid plate?

a. Provides support for core components.

b. Acts as a safety plate to prevent the possibility of a fuel rod dropping out of the core.

c. Acts as a safety plate to prevent the possibility of a control rod dropping out of the core.

d. Provides a catch plate for small tools and hardware which may have dropped into the core.

QUESTION C.10 [1.0 point]

The neutron source used in the reactor is a:

a. plutonium-beryllium source.

b. polonium-americium source.

c. americium-beryllium source.

d. antimony-beryllium source.

QUESTION C.11 [1.0 point]

A three-way solenoid valve controls the air supplied to the pneumatic cylinder of the transient rod. De-energizing the solenoid causes the valve to shift to:

a. open, admitting air to the cylinder.

b. close, admitting air to the cylinder.

c. open, removing air from the cylinder.

d. close, removing air from the cylinder.

QUESTION C.12 [1.0 point]

Application of air pressure to the pulse rod mechanism unless the cylinder is fully inserted in prevented in the:

a. Steady State mode.

b. Pulse mode.

c. Square Wave mode.

d. Prestart mode.

Section C Plant and Rad Monitoring Systems and Radiological Control Procedures Page 14 QUESTION C.13 [1.0 point]

Which ONE of the following will cause a HIGH conductivity reading at the inlet of the demineralizer?

a. Failure of cooling water heat exchanger

b. Pool water temperature low

c. Reactor water system pressure greater than secondary water pressure

d. High reactor water pump flow

QUESTION C.14 [1.0 point]

The neutron absorber in the TRIGA Mark I reactor control rods is:

a. Aluminum oxide

b. Zirconium hydride

c. Graphite powder

d. Borated graphite

QUESTION C.15 [1.0 point]

The meter of the Continuous Air Monitor is periodically calibrated using:

a. a Cs-137 source

b. an internal check source

c. comparison readings obtained from portable instruments

d. a pulse signal generator QUESTION C.16 [1.0 point]

Water which has been treated by the Purification system is returned:

a. to the outlet of the primary pump.

b. directly to the reactor tank.

c to the inlet of the heat exchanger.

d. to the outlet of the heat exchanger.

Section C Plant and Rad Monitoring Systems and Radiological Control Procedures Page 15 QUESTION C.17 [1.0 point]

The reactor is in the steady state mode with the transient rod shock absorber in the full down position and no air applied. The shock absorber is moved upward, and the operator then attempts to apply air to the transient rod. Which ONE of the following occurs?

a. The air solenoid blocks air to the transient rod.

b. The transient rod moves up until it reaches the shock absorber.

c. The shock absorber returns to its full down position.

d. The reactor scrams.

QUESTION C.18 [1.0 point] Question modified during administration to remove detectors no longer in use.

Which of the following instruments is used to detect High level Gamma radiation during an emergency condition?

a. ALOOKA PID

b. Snoopy

c. Ludlum 14A

d. Victoreen 451

QUESTION C.19 [1.0 point]

Which ONE of the following is the approximate worth of all control rods and transient rod?

a. 2.1% k/k. b. 6.3% k/k.

c. 8.4% k/k.

d. 10.5% k/k. QUESTION C.20 [1.0 point]

Which ONE of the following describes a fuel-moderator element?

a. 20% enriched uranium contained within stainless steel cladding.

b. 12% enriched uranium contained within zircaloy cladding.

c. 20% enriched uranium contained within zircaloy cladding.

d. 12% enriched uranium contained within stainless steel cladding.

Section A L Theory, Thermo & Facility Operating Characteristics Page 16 A.01 a REF: Ref 1, Volume

A.02 b REF: Ref 1, Volume

A.03 c REF: Ref 1, Volume

A.04 c T = (eff - )/( ) T = (.0070 - .00175)/.1 x .00175 T = 30 seconds REF: Ref 1, Volume

A.05 c REF: P f = P 0 e t/ = (ln P f/P 0) x t = 0.66 min/ln2 = 0.952 t = ln(800/10) x 0.952 = 4.17 min A.6 a REF: Ref 1, Volume

A.07 b REF: GSTR Requal Exam 2/4/91

A.08 a REF: Ref 1, Volume A.09 a, 4; b, 3; c, 5; d, 1; e, 6; f, 2 REF: Ref 1, Volume

A.10 a b Answer changed per facility, new data: use $0.3 for increase above 100 Kwatt. (900 - 100) x $0.3 = $2.40 Closest answer 'b' REF: GSTR Nuc Eng. Data pg. 11-15 (500 - 100) x $0.5 = $2.00 (900 - 500) x $0.3 = $1.20/$3.20. Rewritten exam answer 'b'.

A.11 b REF: Ref 1, Volume A.12 b. REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1988, §§ 8.1 -8.4, pp. 8 8-14.

A.13 d Same rod height (core burnup and temperatures are the same. Higher count rate due to increased subcritical multiplication REF: Ref 1, Volume A.14 a.

REF: Ref 1, Volume

A.015 b.

REF: Ref 1, Volume A.016 c.

REF: P = P 0 e-T/ = 10-5 x e(-180sec/80sec) = 10-5 x e-2.25 = 0.1054 x 10

-5 = 1.054 x 10-6 A.17 c.

REF: Ref 1, Volume A. 18 d Exam 2, Exam 3 REF: Ref 1, Volume

A.19 a 1.03 x 0.96 x X x 0.84 x 0.88 x 196 = 1.000 X = 1/(1.03 x 0.96 x 0.84 x 0.88 x 1.96) = 0.698 REF: Exam 3 Ref 1, Volume

REF 1 = DOE Handbook, Nuclear Physics & Reactor Theory, Volumes I and II.

Section B Normal, Emergency and Radiological Control Procedures Page 17 B.01 b. REF: Technical Specifications, Section E.5. Shutdown margin + Excess reactivity = Rod worth (excluding the most reactive rod)

B.02 c.

REF: USGS T.S. App. A

B.03 b. REF: Administrative Procedures, Section 4.5.

B.04 a. = 4; b.= 2; c. = 1; d. = 1 REF: 10 CFR 55; USGS Requalification Program

B.05 a REF: USGS Emergency Plan, Definitions. Also 2004 exam

B.06 a REF: 10 CFR 20.

B.07 a REF: With the window closed, no betas are measured. The beta dose rate is 40 mrem/hour.

B.08 d REF: Technical Specifications, Section F.1.

B.09 a REF: GSTR Procedure No. 4.

B.10 b REF: Radiological Safety at Vallecitos Nuclear Center, Page 11. GM tube cannot distinguish between energies.

B.11 c REF: GSTR Requal Exam (2/89)

B.12 c REF: 10 CFR 55.53.f(2)

B.13 a REF: GSTR Procedure No. 6

B.14 a REF: Standard NRC question. 200 (1) 2 = 100 (x) 2 x 2 = (200/100) (1) 2 x 2 = 2 x = 2 1/2 = 1.4 B.15 d REF: Technical Specifications Table II

B.16 a REF: Technical Specifications § I.4 B.17 a, 1; b, 1; c, 2; d, 1 REF:

B.18 c REF: Procedure for Fuel Loading and Unloading Exam 1, Exam 4 Section C Plant and Rad Monitoring Systems and Radiological Control Procedures Page 18 C.01 c. Ref: GA TRIGA Instrumentation Maintenance Manual C.02 d.

Ref: GA Control Console Operator's Manual pg. 1-5

C.03 d.

Ref: GA TRIGA Mech. Maint. & Operating Manual pg 2-18 C.04 c.

Ref: GSTR Reactor Data

C.05 b.

Ref: GA Control Console Operator's Manual pg. 2-5 C.06 c.

Ref: Hazards Summary Report, Section 5.2.

C.07 a. Ref: GSTR Cooling and Purification Systems diagram.

C.08 c.

Ref: Hazards Summary Report, Section 5.5.2.

C.09 a. Ref: Hazards Summary Report, Section 5.1.

C.10 c REF: Hazards Summary Report, Section 5.6.

C.11 d REF: Hazards Summary Report, Section 5.4.2.

C.12 a.

REF: Technical Specifications, Table II

C.13 a REF: Exam 1, Exam 3 GA TRIGA Maintenance and Operating Manual

C.14 d REF: Exam 1 GA TRIGA Maintenance and Operating Manual pg. 2-15, SAR § 4.2.2 Control Rods 1 st ¶ C.15 d REF: Exam 1, Exam 4 CAM Calibration Procedure

C.16 b REF: Exam 2, Exam 4 USGS Reactor Reference Material, Training Resources

C.17 a REF: Exam 2, Exam 3 Technical Specifications, Table II

C.18 d REF: Exam 1 GSTR Operator Requal Exam (2/89)

C.19 b or c 2 nd correct answer added due to correct answer between these two values. REF: Exam 2, Exam 4 Hazards Summary Report, Section 5.3.2.

C.20 a REF: Exam 2, Exam 4 USGS Reactor Reference Material, Reactor Data.

U. S. NUCLEAR REGULATORY COMMISSION RESEARCH AND TEST REACTOR INITIAL OPERATOR LICENSING EXAMINATION FACILITY: U.S. Geological Survey Reactor

REACTOR TYPE: TRIGA-PULSING DATE ADMINISTERED: 01/ 12 13 /2010 Circle one 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 33.33 A. Reactor Theory, Thermodynamics and Facility Operating Characteristics 20.00 33.33 B. Normal and Emergency Operating Procedures and Radiological Controls 20.00 33.33 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

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.

Calculator.lnkEQUATION SHEET

DR B Rem, Ci B curies, E B Mev, R B 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 (H 2O) 8 lbm C = 5/9 (F - 32) c P = 1.0 BTU/hr/lbm/F c p = 1 cal/sec/gm/C T UA = H m = T c m = Q p (k)2)-( = P 2max seconds 10 x 1 = -4* seconds 0.1 = -1 eff )(-CR = )(-CR)K-(1 CR = )K-(1 CR 2 2 1 1 eff 2 eff 1 2 1 K-1 S -S = SCR eff -26.06 = SUR eff K-1 K-1 = M eff eff 1 0 CR CR = K-1 1 = M 2 1 eff 10 P = P SUR(t)0 e P = P t 0 P -)-(1 = P 0 K)K-(1 = SDM eff eff - =

• eff*- + = K x k K - K = eff eff eff eff 2 1 1 2 K 1)-K ( = eff eff 0.693 = T R 6CiE(n) = DR 2 e DR= DR t-0 d DR = d DR 2 2 2 1 2 1 Peak)-( = Peak)-(1 1 2 2 2 2 Section A L Theory, Thermo, and Facility Characteristics Page 1 A.01 a b c d ___ A.09e 1 2 3 4 5 6 ___

A.02 a b c d ___ A.09f 1 2 3 4 5 6 ___

A.03 a b c d ___ A.10 a b c d ___

A.04 a b c d ___ A.11 a b c d ___

A.05 a b c d ___ A.12 a b c d ___

A.06 a b c d ___ A.13 a b c d ___

A.07 a b c d ___ A.14 a b c d ___

A.08 a b c d ___ A.15 a b c d ___

A.09a 1 2 3 4 5 6 ___ A.16 a b c d ___

A.09b 1 2 3 4 5 6 ___ A.17 a b c d ___

A.09c 1 2 3 4 5 6 ___ A.18 a b c d ___

A.09d 1 2 3 4 5 6 ___ A.19 a b c d ___

Section B Normal/Emerg. Procedures & Rad Con Page 2 B.01 a b c d ___ B.10 a b c d ___

B.02 a b c d ___ B.11 a b c d ___

B.03 a b c d ___ B.12 a b c d ___

B.04a 1 2 3 4 ___ B.13 a b c d ___

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

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

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

B.05 a b c d ___ B.17a 1 2 3 ___

B.06 a b c d ___ B.17b 1 2 3 ___

B.07 a b c d ___ B.17c 1 2 3 ___

B.08 a b c d ___ B.17d 1 2 3 ___

B.09 a b c d ___ B.18 a b c d ___

Section C Plant and Rad Monitoring Systems and Radiological Control Procedures Page 3 C.01 a b c d ___ C.11 a b c d ___

C.02 a b c d ___ C.12 a b c d ___

C.03 a b c d ___ C.13 a b c d ___

C.04 a b c d ___ C.14 a b c d ___

C.05 a b c d ___ C.15 a b c d ___

C.06 a b c d ___ C.16 a b c d ___

C.07 a b c d ___ C.17 a b c d ___

C.08 a b c d ___ C.18 a b c d ___

C.09 a b c d ___ C.19 a b c d ___

C.10 a b c d ___ C.20 a b c d ___