ML090830267
| ML090830267 | |
| Person / Time | |
|---|---|
| Site: | U.S. Geological Survey |
| Issue date: | 03/26/2009 |
| From: | Johnny Eads Research and Test Reactors Branch B |
| To: | Timothy Debey US Dept of Interior, Geological Survey (USGS) |
| Doyle P, NRR/DPR, 415-1058 | |
| Shared Package | |
| ML083390549 | List: |
| References | |
| 50-274/OL-09-01 | |
| Download: ML090830267 (30) | |
Text
March 26, 2009 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-09-01, U.S. GEOLOGICAL SURVEY TRIGA REACTOR
Dear Mr. DeBey:
During the week of March 9, 2009, 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 at 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
ML090830267 NRR-074 OFFICE PRTB:CE IOLB:LA E PRTB:SC NAME PDoyle:mxc CRevelle JEads DATE 03/24/2008 03/24/2008 03/26/2008 C = 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-09-01 FACILITY DOCKET NO.: 50-274 FACILITY LICENSE NO.: R-113 FACILITY: U.S. Geological Survey TRIGA Reactor EXAMINATION DATES: March 10 - 11, 2009 SUBMITTED BY: _________/RA/_________________ March 24, 2009 Paul V. Doyle Jr., Chief Examiner Date
SUMMARY
On March 10 and 11, 2009 the NRC administered operator licensing examinations to one Reactor Operator and two Senior Reactor Operator (upgrade) license candidates.
All three candidates passed all portions of the administered examinations.
REPORT DETAILS
- 1. Examiners: Paul V. Doyle Jr., Chief Examiner, NRC
- 2. Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 1/0 0/0 1/0 Operating Tests 1/0 2/0 3/0 Overall 1/0 2/0 3/0
- 3. Exit Meeting:
Paul V. Doyle Jr., NRC, Examiner Timothy DeBey, USGS, Reactor Supervisor Darrel Liles, USGS, Radiation Safety Officer 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 March 09, 2009 ENCLOSURE 2
Section A L Theory, Thermo & Facility Operating Characteristics Page 2 QUESTION A.01 [1.0 point]
Following a scram, the value of the stable reactor period is:
- a. infinity, since neutron production has been terminated
- b. about 50 seconds, because the rate of negative reactivity insertion rapidly approaches zero.
- c. about -10 seconds, as determined by the rate of decay of the shortest lived delayed neutron precursors.
- d. about -80 seconds, as determined by the rate of decay of the longest lived delayed neutron precursors.
QUESTION A.02 [1.0 point]
What are the three materials that are designed as moderators/reflectors, for your reactor?
- a. Zirconium Hydride [ZrH2], Concrete, and Graphite
- b. Water, Graphite, and ZrH2
- c. Graphite, Water, and Aluminum
- d. Aluminum, Concrete, and Water QUESTION A.03 [1.0 point]
The reactor is subcritical with a Keff of 0.96 and 30 counts per second indicated. After a fuel element is removed the count rate drops to 10 counts per second. No other changes have occurred. What is the Keff of the core with the fuel element removed?
- a. 0.9733
- b. 0.8800
- c. 0.8400
- d. 0.8000
Section A L Theory, Thermo & Facility Operating Characteristics Page 3 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
-1 made into an exactly critical reactor core? (Assume a beta of .0070 and a lambda of .1 sec )
- a. 50 seconds
- b. 38 seconds
- c. 30 seconds
- d. 18 seconds QUESTION A.05 [1.0 point]
The neutron microscopic cross-section for absorption (a) of an isotope generally Y
- a. increases as neutron energy increases
- b. decreases as neutron energy increases
- c. increases as target nucleus mass increases
- d. decreases as target nucleus mass increases QUESTION A.06 [1.0 point]
You are about to perform a $1.35 pulse of the reactor. Earlier in the day you performed a $1.95 pulse which resulted in a Peak Power reading of 1800 Megawatts. Which ONE of the following is the expected Peak Power of the $1.35 pulse?
- a. 570 Megawatts.
- b. 625 Megawatts.
- c. 1140 Megawatts.
- d. 1250 Megawatts.
Section A L Theory, Thermo & Facility Operating Characteristics Page 4 QUESTION A.07 [2.0 points, 2'5 each]
A FISSILE material is one which will fission upon the absorption of a THERMAL neutron. A FERTILE material is one which will produce a fissile material after absorption of a neutron and subsequent decay.
Identify each of the isotopes listed as either FISSILE or FERTILE.
232
- a. 90Th 233
- b. 92U 235
- c. 92U 238
- d. 92U 239
- e. 94Pu QUESTION A.08 [1.0 point]
With the reactor on a constant period, which of the following changes in reactor power would take the LONGEST time?
- a. 5% from 1% to 6%
- b. 15% from 20% to 35%
- c. 20% from 40% to 60%
- d. 25% from 75% to 100%
QUESTION A.09 [1.0 point]
During a fuel loading, as the reactor approaches criticality, the value of 1/M is plotted. Which ONE of the following describes the slope of the 1/M curve?
- a. decreases toward zero
- b. decreases toward one
- c. increases toward infinity
- d. increases toward one
Section A L Theory, Thermo & Facility Operating Characteristics Page 5 QUESTION A.10 [2.0 points, 1/2 each]
Match each term in column A with the correct definition in column B.
Column A Column B
- a. Prompt Neutron 1. A neutron in equilibrium with its surroundings.
- b. Fast Neutron 2. A neutron born directly from fission.
- c. Thermal Neutron 3. A neutron born due to decay of a fission product.
- d. Delayed Neutron 4. A neutron at an energy level greater than its surroundings.
QUESTION A.11 [1.0 point]
The Reactor Operator started up the reactor, and has been at 100% power for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. The Reactor Operator notes that several small control rod withdrawals are required to maintain power at 100%. Which of the following is the reason for these rod withdrawals?
- a. Fuel temperatures are decreasing.
- b. Xenon is building in to equilibrium concentration.
- c. Pool water temperatures are decreasing.
- d. Samarium is burning out from peak to equilibrium concentration.
QUESTION A.12 [1.0 point]
Which ONE of the following is the PRINCIPAL source of heat in the reactor an hour after shutdown?
- a. Stored energy from the reactor and core materials
- b. Spontaneous fission within the core
- c. Decay of fission products
- d. Cosmic radiation causing fission QUESTION A.13 [1.0 point]
The purpose of the installed neutron source is to:
- a. Compensate for neutrons absorbed in non-fuel materials in the core.
- b. Generate a sufficient neutron population to start the fission chain reaction for each startup.
- c. Provide a means to allow reactivity changes to occur in a subcritical reactor.
- d. Generate a detectable neutron source level for monitoring reactivity changes in a shutdown reactor.
Section A L Theory, Thermo & Facility Operating Characteristics Page 6 QUESTION A.14 [1.0 point]
Given a control rod worth of 0.1% K/K/inch and an T of 0.05% K/K/°F. If temperature INCREASES by 9°F, how much and in what direction will the control rod move?
- a. 41/2 inches inward
- b. 41/2 inches outward
- c. 9 inches inward
- d. 9 inches outward QUESTION A.15 [1.0 point]
Which ONE of the following is the reason that reactor indicated power (count rate) stabilizes several hours after a reactor trip? Assume all instrumentation is operable, and no reactivity changes.
- a. Subcritical multiplication of source neutrons.
- b. Continuing decay of the longest lived delayed neutron precursor.
- c. Neutron level dropping below detection threshold, the detector reading is due to a test signal input from Nuclear Instrumentation.
- d. Gamma radiation due to decay of fission products below detection threshold, the detector reading is due to a test signal input from Nuclear Instrumentation.
QUESTION A.16 [1.0 point]
A THERMAL neutron has the LEAST probability of being absorbed by which ONE of the following elements?
2
- a. 1H 4
- b. 2He 10
- c. 5B 135
- d. 54Xe
Section A L Theory, Thermo & Facility Operating Characteristics Page 7 QUESTION A.17 [1.0 point]
135 135 Which statement best describes Xe behavior immediately following a Reactor Scram? Xenon concentration 135
- a. decreases because I production directly from fission stops.
135 135
- b. decreases because its production from the decay of I being less than Xe decay rate.
135 135
- c. increases because its production from Te exceeds the Xe decay rate.
135 135
- d. increases because its production from the decay of I exceeds the Xe decay rate.
QUESTION A.18 [1.0 point]
The term "PROMPT JUMP" refers to:
- a. the instantaneous change in power due to raising a control rod.
- b. a reactor which has attained criticality on prompt neutrons alone.
- c. a reactor which is critical using both prompt and delayed neutrons.
- d. a negative reactivity insertion which is less than eff.
Section B Normal, Emergency and Radiological Control Procedures Page 8 QUESTION B.01 [1.0 point].
Which ONE of the following situations would illustrate a time when the reactor meets the Technical Specification definition of shutdown?
- a. One of the shim rod drives is removed for inspection; the rod is decoupled and is fully inserted into the core, all other shim rods are fully inserted and the console key is in the off position and removed.
- b. All shim rods are fully inserted; the console key is in the off position and removed, while fuel is being rearranged in the fuel storage racks.
- c. The shim rods are withdrawn to a subcritical position, the core is subcritical by $1.20.
- d. An experiment having a reactivity of 50¢ is being installed in the central thimble with all shim rods fully inserted and the key removed.
QUESTION B.02 [1.0 point]
According to Technical Specification I.4.a non-secured experiments shall have reactivity worths less than
- a. $1.00
- b. $2.00
- c. $3.00
- d. $5.00 QUESTION B.03 [1.0 point]
An accessible area within the facility has a general radiation level of 325 mrem/hour. What would be the EXPECTED posting for this area?
- a. "Caution, Airborne Radioactivity Area"
- b. "Caution, Radiation Area"
- c. "Danger, High Radiation Area"
- d. "Grave Danger, Very High Radiation Area" QUESTION B.04 [1.0 point]
A small radioactive source is to be stored in the reactor building. The source reads 2 R/hr at 1 foot. Assuming no shielding is to be used, a Radiation Area barrier would have to be erected from the source at least a distance of approximately:
- a. 400 feet
- b. 40 feet
- c. 20 feet
- d. 10 feet
Section B Normal, Emergency and Radiological Control Procedures Page 9 QUESTION B.05 [1.0 point]
According to 10 CFR 20.1003, the term Derived Air Concentration (DAC) is defined as:
- 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) rem.
QUESTION B.06 [1.0 point] Question vague (2 correct answers); it will be rewritten prior to next administration.
A group of visitors is going to enter the reactor bay. Dosimeters must be provided to:
- a. each member of the group.
- b. every third member of the group.
- c. only one member of the group.
- d. a few members of the group.
QUESTION B.07 [1.0 point]
10CFR50.54(x) states: A licensee may take reasonable action that departs from a license condition or a technical specification (contained in a license issued under this part) in an emergency when this action is immediately needed to protect the public health and safety and no action consistent with license conditions and technical specifications that can provide adequate or equivalent protection is immediately apparent. Per 10CFR50.54(y), as a minimum, this action must be approved by
- a. a Reactor Operator licensed at the facility.
- b. a Senior Reactor Operator licensed at the facility.
- c. the Facility Manager (or equivalent at facility).
- d. the U.S. Nuclear Regulatory Commission Project Manager QUESTION B.08 [1.0 point]
What is the MAXIMUM contamination level that may be tolerated without further decontamination efforts for a spill in the reactor bay?
2 2
- a. 15 pCi/100 in beta and 100 pCi/100 in alpha activity 2 2
- b. 100 pCi/100 in alpha and 30 pCi/100 in beta activity 2 2
- c. 30 pCi/100 in alpha and 30 pCi/100 in beta activity 2 2
- d. 30 pCi/100 in beta and 15 pCi/100 in alpha activity
Section B Normal, Emergency and Radiological Control Procedures Page 10 QUESTION B.09 [1.0 point]
While performing the surveillance to check fuel rods, a standard fuel element was found which exceeded the limits for longitudinal elongation and traverse bend. According to Technical Specification D.6
- a. the reactor shall not be operated.
- b. the reactor shall only be operated at a power less than 100 kW.
- c. the reactor shall not be operated in the pulse mode.
- d. the reactor shall only be operated in the steady-state mode.
QUESTION B.10 [1.0 point]
A radioactive source generates a reading of 100 mr/hr at a distance of 10 feet. With two inches of lead shielding the reading drops to 50 mr/hr at a distance of 10 feet. If you were to add another four inches of the same type of shielding, the reading at 10 feet would drop to
- a. 25 mr/hr
- b. 121/2 mr/hr
- c. 61/4 mr/hr
- d. 3 mr/hr QUESTION B.11 [1.0 point]
The CURIE content of a radioactive source is a measure of
- a. the number of radioactive atoms in the source.
- b. the number of nuclear disintegrations per unit time.
- c. the amount of damage to soft body tissue per unit time.
- d. the amount of energy emitted per unit time by the source.
QUESTION B.12 [1.0 point]
Technical Specifications require a stack gas analysis be performed quarterly. The primary purpose of this analysis is to determine the release concentration of:
16
- a. N 41
- b. Ar 60
- c. Co 131-135
- d. I
Section B Normal, Emergency and Radiological Control Procedures Page 11 QUESTION B.13 [1.0 point, 1/4 each]
Identify the PRIMARY source (irradiation of AIR, irradiation of WATER, or Fission Product) of EACH of the radioisotopes listed.
3
- a. 1H 41
- b. 18Ar 16
- c. 7N 135
- d. 54Xe QUESTION B.14 [1.0 point]
The reactor has been shutdown for the past eight months to perform maintenance on the Control Console. Which ONE of the following statements describes the requirements for the first pulse mode operation at the conclusion of the outage?
- a. A pulse must be initiated only when the reactor is at a power less than 1 kw and the pulsed reactivity insertion shall not exceed 1.2% )K/K.
- b. Pulse mode operation will not be resumed until approved by the Reactor Operations Committee. The pulse reactivity insertion shall be equal to or less than 2.9% )K/K.
- c. Pulsing operations can be resumed only after the reactor has operated at full power and the fuel temperatures near the core mid-plane has been recorded using a standard thermocouple fuel element.
- d. The reactor shall be pulsed with a reactivity insertion of greater than 1.5% )K/K to compare the reactor/fuel performance with previous data.
QUESTION B.15 [1.0 point]
Which one of the following is NOT a condition for double encapsulation of a sample? If the sample contains
- a. material corrosive to the reactor components.
- b. material worth greater than $1.00 reactivity.
- c. material which reacts violently with water.
- d. Liquid fissionable material.
Section B Normal, Emergency and Radiological Control Procedures Page 12 QUESTION B.16 [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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
- c. 11/2 hours
- d. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> QUESTION B.17 [2.0 points, 1/2 each]
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 QUESTION B.18 [2.0 points, 0.5 each]
Match the annual dose limit values to the type of exposure.
Type of Exposure Annual Dose Limit Value
- a. Extremities 1. 0.1 rem.
- b. Lens of the Eye 2. 5.0 rem.
Section C Plant and Rad Monitoring Systems and Radiological Control Procedures Page 13 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. Higher than normal Column A Column B
- a. radiation Level at demineralizer. 1. Channeling in demineralizer.
- b. radiation Level downstream of demineralizer. 2. Fuel element failure.
- c. flow rate through demineralizer. 3. High temperature in demineralizer system
- d. pressure upstream of demineralizer. 4. Clogged demineralizer QUESTION C.02 [2.0 points, 0.4 each]
For the console alarms listed below indicate whether they will cause an alarm only an alarm and scram or an alarm and ventilation realignment.
- a. Continuous Air Monitor
- b. High Bulk Water Temperature
- c. Low Pool Water Level
- d. Loss of High Voltage to Power Channels
- e. High Fuel Temperature QUESTION C.03 [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.
Section C Plant and Rad Monitoring Systems and Radiological Control Procedures Page 14 QUESTION C.04 [1.0 point]
Which ONE of the following is the main function performed by the DISCRIMINATOR circuit in the Startup Channel?
- a. To generate a current signal equal and of opposite polarity as the signal due to gammas generated within the Startup Channel Detector.
- b. To filter out small pulses due to gamma interactions, passing only pulses due to neutron events within the Startup Channel Detector.
- c. To convert the linear output of the Startup Channel Detector to a logarithmic signal for metering purposes.
- d. To convert the logarithmic output of the metering circuit to a t (delta time) output for period metering purposes.
QUESTION C.05 [1.0 point]
Which ONE of the following describes the response of the four control rods to a reactor scram signal during NORMAL operation?
- a. All four control rods will scram.
QUESTION C.06 [1.0 point]
Which one of the following describes the ventilation system after switching to Emergency Mode?
Normal Exhaust Supply System Emergency Exhaust Dampers Fan Dampers Fan Dampers Fan
- a. Open On Closed Off Open On
- b. Closed Off Closed Off Open On
- c. Closed Off Open On Open On
- d. Open On Open On Open On QUESTION C.07 [1.0 point]
Which ONE of the following statements correctly describes the purpose of the PULL ROD in the control rod drive assembly?
- a. Provides rod full out position indication.
- b. Provides a means for manually adjusting rod position by pulling rod out.
- c. Provides rod bottom indication.
- d. Automatically engages the control rod on a pull signal.
Section C Plant and Rad Monitoring Systems and Radiological Control Procedures Page 15 QUESTION C.08 [1.0 point]
16 WHICH ONE of the following detectors is used primarily to measure N release to the environment?
16
- a. NONE, N has too short a half-life to require environmental monitoring.
- b. Continuous Air Monitor
- c. Exhaust Gas Monitor
- d. Bridge Area Monitor QUESTION C.09 [1.0 point]
Which ONE of the following statements correctly describes the purpose of the potentiometer in the control rod drive assembly?
- a. Provides rod position indication when the electromagnet engages the connecting rod armature.
- b. Provides a variable voltage to the rod drive motor for regulating control rod speed.
- c. Provides potential voltage as required for resetting the electromagnet current.
- d. Provides the potential voltage to re-latch the connecting rod.
QUESTION C.10 [1.0 point]
Complete the following sentence. Placing the CSC mode switch in the PULSE MODE:
- a. fires the transient rod.
- b. removes air from the transient rod in preparation for firing
- c. changes the gain of the NPP-1000 to full scale.
- d. disables the DAC watchdog timer.
C.10 c REF: Exam 1 GA Control Console Operator's Manual pg. 1-6 QUESTION C.11 [1.0 point]
The standard control rods have vents in the lower end of the barrel. The purpose of these vents is to:
- a. provide viscous damping during reactor scrams.
- b. provide a cooling water path through the barrel.
- c. provide points where a lifting tool can be attached.
- d. smooth out the thermal neutron flux distribution at the bottom of the barrel.
Section C Plant and Rad Monitoring Systems and Radiological Control Procedures Page 16 QUESTION C.12 [1.0 point]
What is one of the purposes for the neutron count interlock?
- a. To preclude the reactor from going super critical before the instrumentation starts to detect the neutron level in the core.
- b. To provide a reference point where all instruments undergo a check before the reactor is brought to a critical position.
- c. To allow for all experiments to be installed before the reactor is critical.
- d. To ensure a sufficient neutron count to start the chain reaction.
QUESTION C.13 [2.0 points, 1/2 each]
Match the nuclear instrumentation channel in column A with its corresponding type of detector listed in column B.
(Note, items in column B may be used more than once or not at all.)
Column A Column B
- a. NM1000 1. BF3 Proportional Counter
- b. NP1000 2. Compensated Ion Chamber
- c. NPP 1000 3. Fission Chamber
- d. Period Channel 4. Uncompensated Ion Chamber QUESTION C.14 [1.0 point]
Which ONE of the following parameters is NOT measured in the Primary Cooling or Purification System Loops?
- a. Temperature
- b. Flow Rate
- c. Conductivity
- d. pH QUESTION C.15 [1.0 point]
The purpose of the graphite slugs located at the top and bottom of each fuel rod is
- a. absorb neutrons, thereby reducing neutron embrittlement of the upper and lower guide plates.
- b. absorb neutrons, thereby reducing neutron leakage from the core.
- c. reflect neutrons, thereby reducing neutron leakage from the core.
- d. couple neutrons from the core to the nuclear instrumentation, decreasing shadowing effects.
Section C Plant and Rad Monitoring Systems and Radiological Control Procedures Page 17 QUESTION C.16 [1.0 point]
Which ONE of the following is NOT a control rod limit switch?
- a. Motor in the up position
- b. Motor in the down position
- c. Rod in the up position
- d. Rod in the down position QUESTION C.17 [1.0 point]
All of the following equipment is supplied by the natural gas generator except the
- a. DAC cabinet
- b. Emergency Ventilation System
- c. Normal Ventilation System
- d. RAM #1
Section A L Theory, Thermo & Facility Operating Characteristics Page 18 A.01 d REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.02 b REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.03 b. CR1/CR2 = [1 - Keff2]/[1 - Keff1] 30/10 = [1 - Keff]/[1 - 0.96] 1 - Keff = 3 x 0.04 = 0.12 Keff = 0.88 REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.04 c REF: ( - D)/8effD = ($1 - $0.25)/0.1 x 0.25 = 0.75/0.025 = 30sec A.05 b REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2 2 2 2 A.6 c P1/1 = P2/2 P2 = 1800 Mwatt x (1.55) ]/(1.95) = 1137 Mwatt Ref: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.07 a, FER, b, FISS; c, FISS; d, FER; e, FISS REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.08 a t/
REF: P = P0 e ln(P/P0) = t/ Since you are looking for which would take the longest time it is obvious to the most casual of observers that the ratio P/P0 must be the largest.
A.09 a REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.10 a, 2; b, 4; c, 1; d, 3 REF: Burn, R., Introduction to Nuclear Reactor Operations, 8 1988, 3.2.2, p. 3 7 A.11 a 1
REF: Standard NRC Question A.12 c REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.13 d REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 9° F x 0.0005 K K °F A.14 b REF: 0.001 K K inch = 4.5 inches REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.15 a REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.16 b REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.17 d REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.18 a REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume
Section B Normal, Emergency and Radiological Control Procedures Page 19 B.01 b REF: Technical Specifications § A Definitions A.1 B.02 a REF: Technical Specification § I.4.a B.03 c REF: Standard NRC question B.04 c DR1 DR2 DR1 2 2000 2 REF: 2
= 2 X 22 = X1 X 22 = x1 = 400 ft 2 X = 20 ft X2 X1 DR2 5 B.05 d REF: 10 CFR 20.1003 nd B.06 d or b 2 correct answer added per examiner review of question.
REF: Exam 2 Administrative Procedures, Section 4.3.5.
B.07 b REF: 10CFR50.54(y)
B.08 d REF: Emergency Procedures Pg. 7-12 Exam 1 B.09 c rd REF: Exam 3 Technical Specifications, Section D.6 3 ¶.
B.10 b REF: 2 = one-half thichness (T1/2). Using 3 half-thickness will drop the dose by a factor of (1/2)3 = . 100/8 = 12.5 B.11 b REF: Exam 4 Standard Health Physics Definition.
B.12 b REF: Exam 3 Procedure for Stack Gas Analysis.
B.13 a. = Water; b. = Air; c. = Water; d. = Fission REF: Exam 4 Standard NRC Question.
B.14 d REF: GSTR T.S. page 5, paragraph 5 Exam 1 B.15 b REF: Tech Spec I.5.
B.16 c REF: 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.17 a, = 4; b, = 2; c, = 1 d, = 3 REF: Exam 4 Standard NRC Question B.18 a, 4; b, 3; c, 2; d, 1 REF: 10 CFR 20 §§ 1201.a(2)(ii), 1201.a(1), 1201.a(2)(i), 1301
Section C Plant and Rad Monitoring Systems and Radiological Control Procedures Page 20 C.01 a, 2; b, 3; c, 1; d, 4 Ref: Standard NRC cleanup loop question.
C.02 a, VENT; b, ALARM; c, ALARM; d, SCRAM; e, Alarm REF: Old NRC exam questions combined and rewritten.
C.03 b REF: Standard NRC question C.04 b REF: Standard NRC Question C.05 a REF: Old SAR, section 6.3.1 Control Rods C.06 b REF: SOP 5, p. 13.
C.07 c REF: Exam 1 GSTR SAR C.08 a REF: Standard NRC Question C.09 a REF: Exam 1 GSTR SAR C.10 c REF: Standard NRC question. SOP-4, § B.c.b p. 4.
C.11 a REF: Exam 2 Hazards Summary Report, Section 5.4.1 C.12 a REF: SAR, Section 6.3.3 C.13 a, 3; b, 4; c, 4; d, 3 REF: SAR § 6.2.3.1 C.14 d REF: SAR §§ 4.2 and 4.4 C.15 c th REF: Safety Analysis Report § 3.1 6 ¶ C.16 c nd REF: Safety Analysis Report § 3.6.1, 2 ¶ nd C.17 a or d; 2 correct answer added per facility comment. SAR is incorrect; all RAMs are supplied by UPS.
REF: Safety Analysis Report § 7.1
U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: U.S. Geological Survey REACTOR TYPE: TRIGA Mark I DATE ADMINISTERED: 03/ /2009 CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
Answers are to be written on the answer sheet provided. Attach the answer sheets to the examination.
Points for each question are indicated in brackets for each question. A 70% in each section is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.
% of Category % of Candidates Category Value Total Score Value Category 20.00 33.3 A. Reactor Theory, Thermodynamics and Facility Operating Characteristics 20.00 33.3 B. Normal and Emergency Operating Procedures and Radiological Controls 20.00 33.3 C. Facility and Radiation Monitoring Systems 46.00 % 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.
EQUATION SHEET
( - )2 Q& = m& c p T = m& H = UA T P max = * -4 l = 1 x 10 seconds 2 (k)l S S CR1 (1 - K eff 1 ) = CR 2 (1 - K eff 2 )
eff = 0.1 seconds-1 SCR =
- 1 - K eff CR1 (- 1 ) = CR 2 (- 2 )
eff 1 - K eff 0 1 CR1 SUR = 26.06 M= M= =
- 1 - K eff 1 1 - K eff CR 2 P = P0 10 SUR(t) t (1 - )
P = P0 e P= P0 (1 - K eff ) =
l l SDM = - = +
K eff eff K eff 2 - K eff 1 0.693 ( K eff - 1)
k eff 1 x K eff 2 T=
K eff 6CiE(n) 2 DR1 d 1 = DR 2 d 2 2
DR = DR0 e- t DR = 2 R
DR B Rem, Ci B curies, E B Mev, R B feet 2 2
( 2 - ) ( 1 - )
=
Peak 2 Peak 1 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lbm 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 1 BTU = 778 ft-lbf EF = 9/5 EC + 32 1 gal (H2O) . 8 lbm EC = 5/9 (EF - 32) cP = 1.0 BTU/hr/lbm/EF cp = 1 cal/sec/gm/EC
Section A L Theory, Thermo, and Facility Characteristics Page 1 A.01 a b c d ___ A.09 a b c d ___
A.02 a b c d ___ A.10a 1 2 3 4 ___
A.03 a b c d ___ A.10b 1 2 3 4 ___
A.04 a b c d ___ A.10c 1 2 3 4 ___
A.05 a b c d ___ A.10d 1 2 3 4 ___
A.05 a b c d ___ A.11 a b c d ___
A.06 a b c d ___ A.12 a b c d ___
A.07a Fissile Fertile ___ A.13 a b c d ___
A.07b Fissile Fertile ___ A.14 a b c d ___
A.07c Fissile Fertile ___ A.15 a b c d ___
A.07d Fissile Fertile ___ A.16 a b c d ___
A.07e Fissile Fertile ___ A.17 a b c d ___
A.08 a b c d ___ A.18 a b c d ___
Section B Normal, Emergency & Radiological Controls Procedures Page 2 B.01 a b c d ___ B.13c air water fission ___
B.02 a b c d ___ B.13d air water fission ___
B.03 a b c d ___ B.14 a b c d ___
B.04 a b c d ___ B.15 a b c d ___
B.05 a b c d ___ B.16 a b c d ___
B.06 a b c d ___ B.17a 1 2 3 4 ___
B.07 a b c d ___ B.17b 1 2 3 4 ___
B.08 a b c d ___ B.17c 1 2 3 4 ___
B.09 a b c d ___ B.17d 1 2 3 4 ___
B.10 a b c d ___ B.18a 1 2 3 4 ___
B.11 a b c d ___ B.18b 1 2 3 4 ___
B.12 a b c d ___ B.18c 1 2 3 4 ___
B.13a air water fission ___ B.18d 1 2 3 4 ___
B.13b air water fission ___
Section C Plant and Rad Monitoring Systems and Radiological Control Procedures Page 3 C.01a 1 2 3 4 ___ C.08 a b c d ___
C.01b 1 2 3 4 ___ C.09 a b c d ___
C.01c 1 2 3 4 ___ C.10 a b c d ___
C.01d 1 2 3 4 ___ C.11 a b c d ___
C.02a alarm scram vent ___ C.12 a b c d ___
C.02b alarm scram vent ___ C.13a a b c d ___
C.02c alarm scram vent ___ C.13b a b c d ___
C.02d alarm scram vent ___ C.13c a b c d ___
C.02e alarm scram vent ___ C.13d a b c d ___
C.03 a b c d ___ C.14 a b c d ___
C.04 a b c d ___ C.15 a b c d ___
C.05 a b c d ___ C.16 a b c d ___
C.07 a b c d ___ C.17 a b c d __