ML020580720
| ML020580720 | |
| Person / Time | |
|---|---|
| Site: | 05000157 |
| Issue date: | 03/15/2002 |
| From: | Madden P NRC/NRR/DRIP/RORP |
| To: | Ulnu K Cornell Univ |
| Eresian W, NRC/NRR/DRIP/RORP, 415-1833 | |
| References | |
| 50-157/OL-02-01 50-157/OL-02-01 | |
| Download: ML020580720 (40) | |
Text
March 15, 2002 Dr. Kenan Ülnü Ward Center for Nuclear Sciences Cornell University 105 Ward Laboratory Ithaca, NY 14853-7701
SUBJECT:
INITIAL EXAMINATION REPORT NO. 50-157/OL-02-01
Dear Dr. Ülnü:
During the week of February 11, 2002, the NRC administered initial examinations to employees of your facility who had applied for a license to operate your Cornell University reactor. The examination was conducted in accordance with NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1. At the conclusion of the examination, the examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report.
In accordance with 10 CFR 2.790 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 document system (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/NRC/ADAMS/indesx.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 Warren Eresian at 301-415-1833 or Internet e-mail wje@nrc.gov.
Sincerely,
/RA/
Patrick M. Madden, Section Chief Research and Test Reactors Section Operating Reactor Improvements Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-157
Enclosures:
- 1. Initial Examination Report No. 50-157/OL-02-01
- 2. Examination and answer key cc w/encls: Please see next page
Cornell University Docket Nos. 50-97/157 cc:
Dr. John Silcox, Vice Provost for Physical Sciences and Engineering Cornell University 314 Day Hall Ithaca, NY 14853-2801 Dr. Paul J. Merges, Director Bureau of Pesticides and Radiation NYS Department of Environmental Conservation 50 Wolf Road, Room 498 Albany, NY 12233-7255 Paul Craven Ward Center for Nuclear Sciences Cornell University 105 Ward Laboratory Ithaca, NY 14853 Mr. John P. Spath NYS Energy Research and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399
March 15, 2002 Dr. Kenan Ülnü Ward Center for Nuclear Sciences Cornell University 105 Ward Laboratory Ithaca, NY 14853-7701
SUBJECT:
INITIAL EXAMINATION REPORT NO. 50-157/OL-02-01
Dear Dr. Ülnü:
During the week of February 11, 2002, the NRC administered initial examinations to employees of your facility who had applied for a license to operate your Cornell University reactor. The examination was conducted in accordance with NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1. At the conclusion of the examination, the examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report.
In accordance with 10 CFR 2.790 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 document system (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/NRC/ADAMS/indesx.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 Warren Eresian at 301-415-1833 or Internet e-mail wje@nrc.gov.
Sincerely,
/RA/
Patrick M. Madden, Section Chief Research and Test Reactors Section Operating Reactor Improvements Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-157
Enclosures:
- 1. Initial Examination Report No. 50-157/OL-02-01
- 2. Examination and answer key cc w/encls: Please see next page DISTRIBUTION:
Public RORP r/f PMadden Facility File (EBarnhill) O6 D-17 WBeckner ADAMS ACCESSION #: ML020580720 TEMPLATE #: NRR-074
- Please see previous concurrence OFFICE RORP:CE IEHB:LA RORP:SC NAME
- WEresian
- EBarnhill PMadden DATE 02/ 28 /2002 03/ 08 /2002 03/ 14 /2002 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY
U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-157/OL-02-01 FACILITY DOCKET NO.:
50-157 FACILITY LICENSE NO.:
R-80 FACILITY:
Cornell University EXAMINATION DATES:
February 12-13, 2002 SUBMITTED BY:
__________/RA/_________________
02/28/02 Warren Eresian, Chief Examiner Date
SUMMARY
During the week of February 11, 2002, the NRC administered operator licensing examinations to two Reactor Operator (RO) initial candidates. Both candidates passed the examination.
REPORT DETAILS 1.
Examiners:
Warren Eresian, Chief Examiner 2.
Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 2/0 N/A 2/0 Operating Tests 2/0 N/A 2/0 Overall 2/0 N/A 2/0 3.
Exit Meeting:
Warren Eresian, NRC Stephen LaFlamme, Director The NRC thanked the facility staff for their cooperation during the examinations. The facility staff presented their comments on the written examination.
ENCLOSURE 1
U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
Cornell University REACTOR TYPE:
TRIGA DATE ADMINISTERED:
02/12/02 REGION:
1 CANDIDATE:___________________________
INSTRUCTIONS TO CANDIDATE:
Answers are to be written on the exam page itself, or the answer sheet provided. Write answers one side ONLY.
Attach any answer sheets to the examination. Points for each question are indicated in parentheses for each question. A 70% is required to pass the examination.
Examination will be picked up one (1) hour after the examination starts.
% OF CATEGORY
% OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20 100 A. REACTOR THEORY, THERMODYNAMICS, AND FACILITY OPERATING CHARACTERISTICS 20 100 B. NORMAL/EMERGENCY PROCEDURES AND RADIOLOGICAL CONTROLS 20 100 C. FACILITY AND RADIATION MONITORING SYSTEMS CANDIDATES SCORE FINAL GRADE %
All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature ENCLOSURE 2
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
1.
Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
2.
After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have not received or given assistance in completing the examination. This must be done after you complete the examination.
3.
Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
4.
Use black ink or dark pencil only to facilitate legible reproductions.
5.
Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.
6.
Print your name in the upper right-hand corner of the answer sheets.
7.
The point value for each question is indicated in parentheses after the question.
8.
Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK. NOTE: partial credit will NOT be given on multiple choice questions.
9.
If the intent of a question is unclear, ask questions of the examiner only.
10.
When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets. In addition, turn in all scrap paper.
11.
When you are done and have turned in your examination, leave the examination area as defined by the examiner. If you are found in this area while the examination is still in progress, your license may be denied or revoked.
A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS Page 3 QUESTION: 001 (1.00)
A reactor is subcritical with a Keff of 0.955. Seven dollars ($7.00) of positive reactivity is inserted into the core
( = 0.007). At this point, the reactor is:
a.
subcritical.
b.
exactly critical.
c.
supercritical.
d.
prompt critical.
QUESTION: 002 (1.00)
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 of fission products.
d.
For small reactivity insertions, prompt neutrons are the dominating factor in determining the reactor period while delayed neutrons have little effect on the reactor period.
QUESTION: 003 (1.00)
Which ONE of the following elements will slow down fast neutrons least quickly, i.e. produces the smallest energy loss per collision?
a.
Oxygen-16 b.
Uranium-238 c.
Hydrogen-1 d.
Boron-10
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS Page 4 QUESTION: 004 (1.00)
Which ONE of the following is the approximate time period during which the MAXIMUM amount of Xenon-135 will be present in the core? Approximately 5 to 7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />s:
a.
after a startup to 100% power.
b.
after a shutdown from 100% power.
c.
after a power decrease from 100% to 50% power.
d.
after a power increase from 50% to 100% power.
QUESTION: 005 (1.00)
During a reactor startup, the count rate is increasing linearly with time, with no rod motion. This means that:
a.
the reactor is subcritical and the count rate increase is due to the buildup of delayed neutron precursors.
b.
the reactor is critical and the count rate increase is due to source neutrons.
c.
the reactor is subcritical and the count rate increase is due to source neutrons.
d.
the reactor is critical and the count rate increase is due to the buildup of delayed neutron precursors.
QUESTION: 006 (1.00)
For the same constant reactor period, which ONE of the following transients requires the SHORTEST time to occur? A power increase of:
a.
5% of rated power - going from 1% to 6% of rated power.
b.
15% of rated power - going from 10% to 25% of rated power.
c.
30% of rated power - going from 20% to 50% of rated power.
d.
50% of rated power - going from 50% to 100% of rated power.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS Page 5 QUESTION: 007 (1.00)
The effective neutron multiplication factor, Keff, is defined as:
a.
production/(absorption + leakage) b.
(production + leakage)/absorption c.
(absorption + leakage)/production d.
absorption/(production + leakage)
QUESTION: 008 (1.00)
For a beta effective = 0.0074, a reactivity insertion of 20 cents corresponds approximately to:
a.
0.0010 delta k/k.
b.
0.0015 delta k/k.
c.
0.0020 delta k/k.
d.
0.0074 delta k/k.
QUESTION: 009 (1.00)
During the minutes following a reactor scram, reactor power decreases on a negative 80 second period, corresponding to the half-life of the longest lived delayed neutron precursor, which is approximately:
a.
20 seconds.
b.
40 seconds.
c.
55 seconds.
d.
80 seconds.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS Page 6 QUESTION: 010 (1.00)
Which ONE of the following describes the characteristics of a good reflector?
a.
High scattering cross-section and low absorption cross-section.
b.
Low scattering cross-section and high absorption cross-section.
c.
Low scattering cross-section and low absorption cross-section.
d.
High scattering cross-section and high absorption cross-section.
QUESTION: 011 (1.00)
You enter the control room and observe that the neutron instrumentation indicates a steady neutron level with no rods in motion. Which ONE condition below CANNOT be true?
a.
The reactor is critical.
b.
The reactor is subcritical.
c.
The reactor is supercritical.
d.
The neutron source is out of the core.
QUESTION: 012 (1.00)
Which factor in the six-factor formula is represented by the ratio:
number of neutrons that reach thermal energy number of neutrons that begin to slow down a.
Fast non-leakage probability.
b.
Resonance escape probability.
c.
Reproduction factor.
d.
Thermal utilization factor.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS Page 7 QUESTION: 013 (1.00)
The major contributor to the production of Xenon-135 in a reactor operating at full power is:
a.
directly from the fission of Uranium-235.
b.
directly from the fission of Uranium-238.
c.
from the radioactive decay of Promethium.
d.
from the radioactive decay of Iodine.
QUESTION: 014 (1.00)
The reactor is to be pulsed. The projected pulse will add TWICE as much reactivity as the last pulse performed.
In relation to the last pulse, for the projected pulse:
a.
peak power will be four times larger and the energy released will be four times larger.
b.
peak power will be two times larger and the energy released will be four times larger.
c.
peak power will be four times larger and the energy released will be two times larger.
d.
peak power will be two times larger and the energy released will be two times larger.
QUESTION: 015 (1.00)
When the fuel temperature is suddenly increased, the neutron spectrum becomes hardened, which means that:
a.
the clad strength increases to contain the higher hydrogen pressure resulting from the release of hydrogen gas from the ZrH.
b.
thermal neutrons gain energy from the higher-energy hydrogen in the ZrH.
c.
the erbium resonance peaks shift to higher energies.
d.
it becomes harder for thermal neutrons to be absorbed in resonance peaks.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS Page 8 QUESTION: 016 (1.00)
Which ONE of the following describes the term prompt critical?
a.
The instantaneous change in power level due to withdrawing a control rod.
b.
A negative reactivity insertion which is greater than beta-effective.
c.
A reactor which is critical on prompt neutrons only.
d.
A positive reactivity insertion which is less than beta-effective.
QUESTION: 017 (1.00)
The equations which describe the operation of an installed neutron source at the Cornell TRIGA are:
a.
Am-241 -> alpha + Np-237 Be-9 + alpha -> C-12 + neutron b.
Am-241 -> alpha + Np-237 B-10 + alpha -> N-13 + neutron c.
Am-241 -> beta + Cm-241 Be-9 + beta -> Li-8 + neutron d.
Am-241 -> beta + Cm-241 B-10 + beta -> Be-9 + neutron QUESTION: 018 (1.00)
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.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS Page 9 QUESTION: 019 (1.00)
The pool (bath) temperature coefficient of reactivity is -1.25x10-3 delta K/K/deg.C. When a control rod with an average rod worth of 0.1% delta K/K/inch is withdrawn 10 inches, reactor power increases and becomes stable at a higher level. At this point, the pool temperature has:
a.
increased by 8 deg C.
b.
decreased by 8 deg C.
c.
increased by 0.8 deg C.
d.
decreased by 0.8 deg C.
QUESTION: 020 (1.00)
Shown below is a trace of reactor period as a function of time. Between points A and B, reactor power is:
a.
continually increasing.
b.
increasing, then decreasing.
c.
continually decreasing.
d.
constant.
(***** END OF CATEGORY A *****)
B. NORMAL/EMERGENCY PROCEDURES AND RADIOLOGICAL CONTROLS Page 10 QUESTION: 001 (1.00)
Which ONE statement below describes the basis for the Safety Limit applicable to fuel temperature for an stainless-steel-clad, high hydride fuel element?
a.
High fuel temperature combined with lack of adequate cooling could result in fuel melt.
b.
Pulsing the reactor at high fuel temperatures could result in loss of fuel element cladding integrity.
c.
Excessive hydrogen gas pressure may result in loss of fuel element cladding integrity.
d.
Phase transitions may result in fuel element cladding failure.
QUESTION: 002 (1.00)
Which ONE of the following defines an "Channel Test?"
a.
The introduction of a an input signal into the channel to verify that it is operable.
b.
A combination of sensors, electronic circuits and output devices which measure and display the value of a parameter.
c.
The qualitative verification of acceptable performance by observation of channel behavior.
d.
The adjustment of a channel such that its output corresponds with acceptable accuracy to known values of the parameter which the channel measures.
QUESTION: 003 (1.00)
Limits are placed on reactivity insertions during pulse operation in order to:
a.
limit fuel temperature increases.
b.
ensure that shutdown margin requirements can be met.
c.
limit the peak power level to 500 kW.
d.
ensure that excess reactivity limits can be met.
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
B. NORMAL/EMERGENCY PROCEDURES AND RADIOLOGICAL CONTROLS Page 11 QUESTION: 004 (1.00)
Which ONE of the following activities must be performed under the direct supervision or presence of a senior licensed operator?
a.
Measurement of Control Rod Drop Time.
b.
Removal of Transient Rod Drive.
c.
Testing of Containment Isolation Butterfly Valves.
d.
Calibration of Radiation Monitoring Equipment.
QUESTION: 005 (1.00)
To maintain an active operator license, the functions of an operator must be actively performed for at least:
a.
one hour per month.
b.
four hours per calendar quarter.
c.
six hours per calendar quarter.
d.
sixteen hours per year.
QUESTION: 006 (1.00)
In accordance with the Technical Specifications, which ONE condition below is permissible during reactor operation?
a.
Drop time of a standard control rod = 1 second.
b.
Water temperature = 130 deg. F.
c.
Reactivity worth of an individual experiment = $3.00.
d.
Water level 19 feet above the bottom of the core.
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
B. NORMAL/EMERGENCY PROCEDURES AND RADIOLOGICAL CONTROLS Page 12 QUESTION: 007 (1.00)
Two point sources have the same Curie strength. Source As gammas have an energy of 1 Mev, whereas source Bs gammas have an energy of 2 Mev. You obtain a reading from the same GM tube 10 feet from each source. Concerning the two readings, which ONE of the following statements is correct?
a.
The reading from Source B is four times that of Source A.
b.
The reading from Source B is twice that of Source A.
c.
The reading from Source B is half that of Source A.
d.
Both readings are the same.
QUESTION: 008 (1.00)
The maximum licensed power level for the Cornell TRIGA is 500 kW. This means that:
a.
at no time may reactor power exceed 500 kW.
b.
the reactor must automatically scram when power exceeds 500 kW.
c.
the steady state power level may not exceed 500 kW.
d.
the steady state power level may not usually exceed 500 kW, but may be exceeded temporarily for a special experiment with permission from the Center Safety Committee.
QUESTION: 009 (1.00)
In accordance with the TRIGA Power Calibration procedure, after power level is determined:
a.
the indicators on the power meters are adjusted to give the proper indication.
b.
the high voltages to the neutron detectors are adjusted to give the proper indication.
c.
the compensating voltages of the compensated ion chambers are adjusted to give the proper indication.
d.
the positions of the neutron detectors are adjusted to give the proper indication.
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
B. NORMAL/EMERGENCY PROCEDURES AND RADIOLOGICAL CONTROLS Page 13 QUESTION: 010 (1.00)
A radiation survey of an area reveals a general radiation reading of 1 mrem/hr. There is, however, a small section of pipe which reads 10 mrem/hr at one (1) meter. Which ONE of the following defines the posting requirements for the area in accordance with 10CFR20?
a.
"CAUTION RADIATION AREA."
b.
"CAUTION RADIOACTIVE MATERIAL."
c.
"CAUTION HIGH RADIATION AREA."
d.
"GRAVE DANGER, VERY HIGH RADIATION AREA."
QUESTION: 011 (1.00)
Two centimeters of lead placed in a beam of gamma rays reduce the radiation level from 400 mR/hr to 200 mR/hr. Which ONE of the following is the total thickness of lead that would reduce the gamma radiation level from 400 mR/hr to 50 mR/hr?
a.
3 cm.
b.
4 cm.
c.
6 cm.
d.
8 cm.
QUESTION: 012 (1.00)
In accordance with 10 CFR 20, the "Derived Air Concentration (DAC)" refers to:
a.
the amount of radioactive material taken into the body by inhalation or ingestion in one year which would result in a committed effective dose equivalent of 5 rems.
b.
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 5 rems.
c.
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.
d.
limits on the release of Ar-41 from the exhaust plenum to an unrestricted environment.
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
B. NORMAL/EMERGENCY PROCEDURES AND RADIOLOGICAL CONTROLS Page 14 QUESTION: 013 (1.00)
An event which causes or threatens to cause radiation hazards within Ward Laboratory would be classified as a(n):
a.
personnel emergency.
b.
emergency alert.
c.
reactor emergency.
d.
facility emergency.
QUESTION: 014 (1.00)
In the event of an emergency which requires evacuation, the primary assembly area is:
a.
Ward Laboratory lobby.
b.
Upson Hall first floor lounge.
c.
Radiation Safety Office.
d.
Emergency Control Center.
QUESTION: 015 (1.00)
A procedure change to an approved operating procedure may be made by the Responsible Person on Duty with the concurrence approval of the Reactor Supervisor ONLY if it is a change:
a.
required for safe reactor shutdown.
b.
required for safe operation of experiments and experiment facilities.
c.
that does not change the original intent of the procedure.
d.
that specifies corrective actions to be taken for specific foreseen malfunctions.
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
B. NORMAL/EMERGENCY PROCEDURES AND RADIOLOGICAL CONTROLS Page 15 QUESTION: 016 (1.00)
In the event of a reportable occurrence, the reactor shall be shut down and reactor operation shall not be resumed until authorized by:
a.
the NRC.
b.
the Center Safety Committee.
c.
the Reactor Supervisor.
d.
the Center Director.
QUESTION: 017 (1.00)
"Releases of Ar-41 from the reactor bay exhaust plenum to an unrestricted environment shall not exceed 32 Ci/year." This is an example of a(n):
a.
safety limit.
b.
limiting safety system setting.
c.
limiting condition for operation.
d.
surveillance requirement.
QUESTION: 018 (2.00)
Match the 10 CFR 55 requirements listed 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
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
B. NORMAL/EMERGENCY PROCEDURES AND RADIOLOGICAL CONTROLS Page 16 QUESTION: 019 (1.00)
There are a number of conditions which will initiate a scram. Of these, the scram signals required by the Technical Specifications are:
a.
short reactor period, high power level, high fuel temperature.
b.
high power level, manual scram, ion-chamber power supply failure.
c.
high fuel temperature, high power level, manual scram.
d.
high fuel temperature, ion-chamber power supply failure, short reactor period.
(***** END OF CATEGORY B *****)
C. FACILITY AND RADIATION MONITORING SYSTEMS Page 17 QUESTION: 001 (1.00)
Which ONE of the following is a control rod drive interlock?
a.
Two rods cannot be moved at the same time unless power is below 1 kW in the steady state mode.
b.
Control rods cannot be withdrawn unless the count rate is at least 60 counts per minute.
c.
The transient rod cannot be withdrawn above 1 kW in the PULSE mode.
d.
Control rods cannot be withdrawn unless the fission chamber is fully inserted.
QUESTION: 002 (1.00)
Pool water temperature is controlled automatically by a temperature controller which:
a.
adjusts the speed of the pool water pump.
b.
adjusts the position of the pool water pump discharge valve.
c.
adjusts the position of a control valve in the chill water return line.
d.
adjusts the position of the chill water pump discharge valve.
QUESTION: 003 (1.00)
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.
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
C. FACILITY AND RADIATION MONITORING SYSTEMS Page 18 QUESTION: 004 (1.00)
Upon receipt of a scram signal, the regulating rod:
a.
magnet is de-energized, and the rod falls into the core.
b.
remains where it is, and must be manually driven into the core.
c.
automatically drives into the core.
d.
magnet and drive both fall into the core.
QUESTION: 005 (1.00)
When the exhaust stack gas monitoring system alarm sounds, which ONE of the following occurs?
a.
The reactor scrams.
b.
The evacuation alarm sounds.
c.
The ventilation system shuts down.
d.
There are no automatic actions.
QUESTION: 006 (1.00)
Which ONE of the following is the purpose of the bottom grid plate in the reactor core?
a.
Prevents the control rods from dropping out of the core if the mechanical connections fail.
b.
Provides support for the weight of the fuel elements.
c.
Provides a catch plate for small tools and hardware dropped while working on the core.
d.
Provides support for the control rod drives.
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
C. FACILITY AND RADIATION MONITORING SYSTEMS Page 19 QUESTION: 007 (1.00)
Primary system flow rates are measured by a(n):
a.
rotometer.
b.
flow orifice.
c.
annubar flow element.
d.
flow controller.
QUESTION: 008 (1.00)
For a control rod drive mechanism, in order to withdraw the rod, the armature is:
a.
bolted to the draw tube.
b.
threaded to accept the draw tube rack and pinion assembly.
c.
connected to the draw tube with a connecting rod.
d.
held by the draw tube using an electromagnet.
QUESTION: 009 (1.00)
The primary and secondary cooling systems are operating normally when the secondary (chill water) system pressure drops to 60 psi. As a result:
a.
the chill water pump is secured, but the pool water pump continues to operate.
b.
the pool water pump is secured, but the chill water pump continues to operate.
c.
both the pool water and chill water pumps continue to operate.
d.
both the pool water and chill water pumps are secured.
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
C. FACILITY AND RADIATION MONITORING SYSTEMS Page 20 QUESTION: 010 (1.00)
Scramming of the transient rod is accomplished by:
a.
a solenoid valve which redirects compressed air to the top of the rod, driving it into the core.
b.
de-energizing the magnet which holds the rod to the drive.
c.
actuating the worm gear which drives the rod into the core.
d.
de-energizing a solenoid valve, which vents the compressed air holding the rod out of the core.
QUESTION: 011 (1.00)
Reactor period information is derived from:
a.
the startup channel.
b.
the log N channel.
c.
power channel No. 1.
d.
power channel No. 2.
QUESTION: 012 (1.00)
For a control rod, the magnet "UP" light is ON, the magnet "DOWN" light is OFF, and the "CONTACT" light is OFF. This indicates that:
a.
the rod and drive are not in contact, the rod is full out and the drive is full in.
b.
the rod and drive are both full out.
c.
the rod and drive are both full in.
d.
the rod and drive are not in contact, the drive is full out and the rod is full in.
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
C. FACILITY AND RADIATION MONITORING SYSTEMS Page 21 QUESTION: 013 (1.00)
Radiation streaming from the beam ports not in use is prevented by:
a.
lining the ports with cadmium to absorb leaking neutrons.
b.
using a stepped inner concrete plug.
c.
a wood plug and lead shutter.
d.
beam stops and beam catchers.
QUESTION: 014 (1.00)
Which ONE of the following controls the amount of reactivity that is inserted by the transient rod during pulse operations?
a.
The timer setting that vents the pneumatic piston.
b.
The pressure of the air applied to the pneumatic piston.
c.
The position of the cylinder.
d.
The initial power level of the reactor prior to firing the pulse.
QUESTION: 015 (1.00)
Thermocouples in an instrumented TRIGA fuel element measure temperature at the:
a.
interior surface of the cladding.
b.
center of the zirconium rod.
c.
outer surface of the fuel.
d.
interior of the fuel.
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
C. FACILITY AND RADIATION MONITORING SYSTEMS Page 22 QUESTION: 016 (1.00)
The purpose of the NaI crystal near the suction line at the top of the pool is to:
a.
detect the presence of fission products from a leaking fuel element.
b.
detect the presence of Ar-41 in the coolant.
c.
detect the presence of N-16 in the coolant.
d.
detect the inleakage of chilled water.
QUESTION: 017 (1.00)
In the pool water cooling system, pool water conductivity is measured at:
a.
the inlet to the pool water pump.
b.
the inlet to the heat exchanger.
c.
the outlet of the heat exchanger.
d.
the outlet of the pool water pump.
QUESTION: 018 (1.00)
A high-hydride fuel element is:
a.
clad with stainless steel, enriched to 8.5% U-235, and contains about 20 weight-percent uranium.
b.
clad with aluminum, enriched to 20% U-235, and contains about 8.5 weight-percent uranium.
c.
clad with stainless steel, enriched to 20% U-235, and contains about 8.5 weight-percent uranium.
d.
clad with aluminum, enriched to 8.5% U-235, and contains about 20 weight-percent uranium.
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
C. FACILITY AND RADIATION MONITORING SYSTEMS Page 23 QUESTION: 019 (1.00)
While operating the TRIGA reactor at 50 kW the operator pushes and immediately releases the MAGNET pushbutton for the regulating rod. Which ONE of the following is the response of the reactor control system?
a.
All rods scram.
b.
Only the regulating rod scrams.
c.
The regulating rod drives inward.
d.
The "ON" light goes out momentarily but the rod does not move.
QUESTION: 020 (1.00)
The in-core terminus of the pneumatic transfer system is located in:
a.
the inner ring.
b.
the outer ring.
c.
the C-ring.
d.
the D-ring.
(***** END OF CATEGORY C *****)
(***** END OF EXAMINATION *****)
A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS ANSWER: 001 (1.00)
A.
REFERENCE:
Reactor Operator Training Manual, Reactor Physics and Kinetics, Sections 6.2.1, 6.2.4.
Shutdown reactivity = (K-1)/K = -0.047 delta K/K. $7.00 added = 7(0.007) = +0.049 delta K/K.
-0.047 + 0.049 = + 0.002, i.e. supercritical.
ANSWER: 002 (1.00)
C.
REFERENCE:
Reactor Operator Training Manual, Reactor Physics and Kinetics, Sections 6.1.3, 6.2.2.
ANSWER: 003 (1.00)
B.
REFERENCE:
Reactor Operator Training Manual, Reactor Physics and Kinetics, Section 6.1.11.
ANSWER: 004 (1.00)
B.
REFERENCE:
Reactor Operator Training Manual, Reactor Physics and Kinetics, Section 6.3.7.
ANSWER: 005 (1.00)
B.
REFERENCE:
Reactor Operator Training Manual, Reactor Physics and Kinetics, Section 6.2.7.
ANSWER: 006 (1.00)
D.
REFERENCE:
Reactor Operator Training Manual, Reactor Physics and Kinetics, Section 6.2.5.
ANSWER: 007 (1.00)
D.
REFERENCE:
Reactor Operator Training Manual, Reactor Physics and Kinetics, Section 6.1.5.
ANSWER: 008 (1.00)
B.
REFERENCE:
Reactor Operator Training Manual, Reactor Physics and Kinetics, Section 6.2.4.
delta k/k = reactivity($) x beta = 0.20 x 0.0074 = 0.0015 ANSWER: 009 (1.00)
C.
REFERENCE:
Reactor Operator Training Manual, Reactor Physics and Kinetics, Section 6.2.5, ANSWER: 010 (1.00)
A.
REFERENCE:
Reactor Operator Training Manual, Reactor Physics and Kinetics, Section 6.1.12.
ANSWER: 011 (1.00)
C.
REFERENCE:
Reactor Operator Training Manual, Reactor Physics and Kinetics, Section2 6.2.1, 6.2.7.
ANSWER: 012 (1.00)
B.
REFERENCE:
Reactor Operator Training Manual, Reactor Physics and Kinetics, Section 6.1.7.
ANSWER: 013 (1.00)
D.
REFERENCE:
Reactor Operator Training Manual, Reactor Physics and Kinetics, Section 6.3.7.
ANSWER: 014 (1.00)
C.
REFERENCE:
Reactor Operator Training Manual, Reactor Physics and Kinetics, Section 6.5.1.
ANSWER: 015 (1.00)
B.
REFERENCE:
Reactor Operator Training Manual, Reactor Physics and Kinetics, Section 6.6.4.
ANSWER: 016 (1.00)
C.
REFERENCE:
Reactor Operator Training Manual, Reactor Physics and Kinetics, Section 6.2.5.
ANSWER: 017 (1.00)
A.
REFERENCE:
Reactor Operator Training Manual, Reactor Physical Plant, Section 1.4.3.
ANSWER: 018 (1.00)
D.
REFERENCE:
Reactor Operator Training Manual, Reactor Physics and Kinetics, Section 6.1.6.
ANSWER: 019 (1.00)
A.
REFERENCE:
Reactor Operator Training Manual, Reactor Physics and Kinetics, Section 6.3.4.
ANSWER: 020 (1.00)
A.
REFERENCE:
Reactor Operator Training Manual, Reactor Physics and Kinetics, Section 6.2.5.
B. NORMAL/EMERGENCY PROCEDURES AND RADIOLOGICAL CONTROLS ANSWER: 001 C.
REFERENCE Technical Specifications, Section 2.1, pg. 4.
ANSWER: 002 A.
REFERENCE Technical Specifications Definitions, Section 1.0, page 1.
ANSWER: 003 A.
REFERENCE Technical Specifications, Section 3.3, pg. 7.
ANSWER: 004 B.
REFERENCE OP 300.
ANSWER: 005 B.
REFERENCE 10 CFR 55.53 ANSWER: 006 B.
REFERENCE Technical Specifications, Section 3.10, pg. 12.
ANSWER: 007 D.
REFERENCE A GM tube cannot distinguish between energies.
ANSWER: 008 C.
REFERENCE Technical Specifications, Section 3.2, pg. 7.
ANSWER: 009 A.
REFERENCE OP 204 ANSWER: 010 C.
REFERENCE 10 CFR 20.1003, Definitions. Radiation level of 10 mrem/hr at 1 meter (100 cm) results in 111 mrem/hr at 30 cm.
ANSWER: 011 C.
REFERENCE Each 2 cm. of lead reduces the radiation level by a factor of 2. 6 cm reduces it by a factor of 8.
ANSWER: 012 B.
REFERENCE 10 CFR 20.1003, Definitions.
ANSWER: 013 C.
REFERENCE Emergency Plan, Section 4.0, pg. 9.
ANSWER: 014 A.
REFERENCE Emergency Plan, Section 7.4.1, pg. 15.
ANSWER: 015 C.
REFERENCE Technical Specifications, Section 6.3, pg. 22.
ANSWER: 016 B.
REFERENCE Technical Specifications, Section 6.9, pg. 24.
ANSWER: 017 C.
REFERENCE Technical Specifications, Section 3.6, pg. 9.
ANSWER: 018 A,4; B,2; C,2; D,1 REFERENCE 10 CFR 55 ANSWER: 019 C.
REFERENCE Technical Specifications, Section 3.5, pg. 9.
(***** END OF CATEGORY B *****)
C. FACILITY AND RADIATION MONITORING SYSTEMS ANSWER: 001 B.
REFERENCE SER, Table 7.1.
ANSWER: 002 C.
REFERENCE OP 500 ANSWER: 003 D.
REFERENCE SER, Section 4.7.1.
ANSWER: 004 A.
REFERENCE SER, Section 7.3.
ANSWER: 005 C.
REFERENCE OP 302 ANSWER: 006 B.
REFERENCE SER, Section 4.3.
ANSWER: 007 C.
REFERENCE OP 500 ANSWER: 008 D.
REFERENCE SER, Section 4.7.1.
ANSWER: 009 C.
REFERENCE SER, Section 5.2.
ANSWER: 010 D.
REFERENCE SER, Section 4.7.1.
ANSWER: 011 B.
REFERENCE SER, Figure 7.1.
ANSWER: 012 D.
REFERENCE SER, Section 7.3.
ANSWER: 013 B.
REFERENCE SER, Section 10.1.3.
ANSWER: 014 C.
REFERENCE SER, Section 4.7.2.
ANSWER: 015 D.
REFERENCE SER, Section 4.1.1.
ANSWER: 016 C.
REFERENCE SER, Section 5.2.
ANSWER: 017 C.
REFERENCE SER, Figure 5.1.
ANSWER: 018 C.
REFERENCE SER, Section 4.1.1.
ANSWER: 019 B.
REFERENCE SER, Section 4.7.1.
ANSWER: 020 B.
REFERENCE SER, Section 10.1.2.
(***** END OF CATEGORY C *****)
A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS ANSWER SHEET MULTIPLE CHOICE (Circle or X your choice)
If you change your answer, write your selection in the blank.
001 a
b c
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002 a
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B. NORMAL/EMERGENCY PROCEDURES AND RADIOLOGICAL CONTROLS ANSWER SHEET MULTIPLE CHOICE (Circle or X your choice)
If you change your answer, write your selection in the blank.
001 a
b c
d _____
002 a
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003 a
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004 a
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019 a
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C. FACILITY AND RADIATION MONITORING SYSTEMS ANSWER SHEET MULTIPLE CHOICE (Circle or X your choice)
If you change your answer, write your selection in the blank.
001 a
b c
d _____
002 a
b c
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003 a
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004 a
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019 a
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020 a
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EQUATION SHEET Q = m cp T CR1 (1-Keff)1 = CR2 (1-Keff)2 SUR = 26.06/
P = P0 10SUR(t)
P = P0 e(t/)
= (*/) + [(-)/eff]
eff = 0.1 seconds-1 DR1D1 2 = DR2D2 2
DR = DRoe-t DR = 6CiE/D2
= (Keff-1)/Keff 1 eV = 1.6x10-19 watt-sec.
1 Curie = 3.7x1010 dps 1 gallon water = 8.34 pounds 1 Btu = 778 ft-lbf
F = 9/5C + 32 1 Mw = 3.41x106 BTU/hr
C = 5/9 (F - 32)