ML20044C513
| ML20044C513 | |
| Person / Time | |
|---|---|
| Site: | General Atomics |
| Issue date: | 03/09/1993 |
| From: | Isaac P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20044C511 | List: |
| References | |
| 50-089-OL-93-01, 50-163-OL-93-01, 50-163-OL-93-1, 50-89-OL-93-1, NUDOCS 9303230230 | |
| Download: ML20044C513 (32) | |
Text
ENCLOSURE 1 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-163/50-89/0L-93-01 FACILITY DOCKET NO.:
50-163/50-89 FACILITY LICENSE NO.:
R-67/R-38 FACILITY:
General Atomics EXAMINATION DATES:
February 16-18, 1993 EXAMINER:
Patr J. Isa e, Chief Examiner
[ A, '
F8 "
J,2f-93 SUBMITTED BY:
. ickIsja i
Examiner Date P
3[4 /
APPROVED BY:
/M
'l. Caldwell, Chief
' Da'te N -Power Reactor Section 0 erator Licensing Branch Division of Reactor Controls and Human Factors i
Office of Nuclear Reactor Regulation
SUMMARY
NRC administered written and operating requalification examinations to five Senior Reactor Operators (SRO). All five SR0s passed the examinations.
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6 9303230230 930312 PDR ADOCK 05000089 V
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REPORT DETAILS 1.
Examiners:
Patrick Isaac, Chief Examiner l
2.
Results:
R0 SRO TOTAL (Pass / Fail)
(Pass / Fail)
(Pass / Fail)
NRC Grading N/A 5/0_
5/0 Facility Grading N/A 5/0 5/0 3.
Written Examination:
The written examination was administered on February 16, 1993 to five Senior Reactor Operators. During the administration of the written examination, the NRC proctor determined that question 19 of section C was incomplete; this question was deleted. All five SR0s passed the written examination.
No official comments were submitted by the facility.
4.
Operating Tests:
Operating examinations were administered on February 17 and 18,1993. All l
five SR0s passed the operating examination.
5.
Exit Meeting:
l An exit meeting was held, on February 18, 1993, between Dr. Junaid Razvi, Director, TRIGA Reactor Facility and Mr. Patrick Isaac. There were no generic
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concerns raised by the examiner and Mr. Isaac thanked Dr. Razvi for his help in the preparation and administration of the examination.
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i NRC Official Use Only i
t Nuclear Regulatory Commission Operator Licensing l
Examination i
i This document is removed from Official Use Only ~ category on t
date of examination.
NRC Official Use Only
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3 9
U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION 4
FACILITY:
General Atomics REACTOR TYPE:
TRIGA DATE ADMINISTERED: 93/02/16 REGION:
5 CANDIDATE:
INSTRUCTIONS TO CANDIDATE Answers are to be written on the answer sheet provided. Attach any answer sheets to the examination. A 70% is required to pass the examination.
t Examinations will be picked up three (3) hours after the examination starts.
i
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL-SCORE VALUE CATEGORY 20.00 33.9 A. -REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 20.00 33.9 B.
NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 19.00 32.2 C.
PLANT 1440 RADIATION MONITORING SYSTEMS 59.00 TOTALS FINAL GRADE All work done on this examination is my own.
I have neither given nor received aid.
Candidate's Signature f
A.
RX THEORY. THERM 0 & FAC OP CHARS ANSWER SHEET Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
MULTIPLE CH0 ICE 001 a
b c
d 002 a
b c
d 003 a
b c
d 004 a
b c
d 005 a
b c
d 006 a
b c
d 007 a
b c
d 008 a
b c
d 009 a
b c
d 010 a
b c
d 011 a
b c
d 012 a
b c
d 013 a
b c
d 014 a
b c
d 015 a
b c
d 1
016 a
b c
d j
017 a
b c
d 018 a
b c
d 019 a
b c
d 020 a
b c
d
(***** END OF CATEGORY A *****)
B.
NORMAL /EMERG PROCEDURES & RAD CON ANSWER SHEET Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
MULTIPLE CH0 ICE f
001 a
b c
d 002 a
b c
d 003 a
b c
d i
004 a
b c
d 005 a
b c
d 006 a
b c
d j
007 a
b c
d l
008 a
b c
d 009 a
b c
d 010 a
b c
d 011 a
b c
d 012 a
b c
d 013 a
b c
d 014 a
b c
d 015 a
b c
d 016 a
b c
d 017 a
b c
d 018 a
b c
d 019 a
b c
d f
020 a
b c
d
(***** END OF CATEGORY B *****)
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l C.
PLANT AND RAD MONITORING SYSTEMS ANSWER SHEET Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
MULTIPLE CHOICE 001 a
b c
d Ol9(a) a b
c d
DELETED 002 a
b c
d Ol9(b) a b
c d
DELETED 003 a
b c
d Ol9(c) a b'
c_
d DELETED 004 a
b c
d 019(d) a b
c d
DELETED 005 a
b c
d 020 a
b c
d 006 a
b c
d 007 a
b c
d 008 a
b c
d 009 a
b c
d 010 a
b c
d 011 a
b c
d 012 a
b c
d 013 a
b c
d 014 a
b c
d 015 a
b c
d 016 a
b c
d 017 a
b c
d 018 a
b c
d
(***** END OF CATEGORY C *****)
(********** END OF EXAMINATION **********)
t 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.
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- 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.
1
- 3. Restroom trips are to be limited and only one candidate at a time may
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leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 4. Use black ink or dark pencil only to facilitate legible reproductions.
- 5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.
- 6. Fill in the date on the cover sheet of the examination (if necessary).
- 7. The point value for each question is indicated in parentheses after the t
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. To pass the examination, you must achieve at least 70%.
- 11. There is a time limit of (3) hours for completion of the examination.
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- 12. When you are done and have turned in your examination, leave the examin-i ation 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.
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A.
RX THEORY. THERM 0 & FAC OP CHARS QUESTION: 001 (1.00)
The prompt negative temperature coefficient of reactivity (a) in TRIGA FLIP l
fuel is strongly affected by the use of a burnable poison. The effects on (a) due to a presence of this burnable poison in FLIP fuel are:
y a)
(a) increases as a function of fuel temperature.
b)
There is no effect, and (a) is independent of fuel temperature.
c)
While the value of (a) is dependent on fuel temperature at beginning of life, it becomes independent of fuel temperature after 3000 Mw-days.of reactor operation.
d)
(a) decreases with increasing fuel temperature due to the presence of a burnable poison.
Question: 002 (1.00) i Which one of the following statements describes the effect of an increase in i
fuel temperature in a TRIGA fuel element.
f i
a)
The probability that i. thermal neutron will lose energy in a collision with an excited state hydrogen atom in UZrHx increases.
1 b)
The probability that a neutron will escape from the element before being captured in the fuel meat increases.
l c)
A shift in the thermal neutron spectrum, towards lower energies, occurs in the fuel element.
.i d)
The mean free path for fast neutrons in the fuel element in decreased.
QUESTION: 003 (1.00)
A kinetics model is used to understand the pulsing characteristics of TRIGA i
type reactors.
This model shows that:
l a) peak pulse power varies as the square of Ak, b) energy released varies as the square root of Ak, c) average fuel temperature varies as the square root of Ak, l
[
d) peak pulse power varies linearly with Ak,.
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A.
RX THEORY. THERM 0 & FAC OP CHARS QUESTION: 004 (1.00)
The purpose of the beryllium in the Am-Be neutron startup source is the following:
a) to dilute the intense source b) to moderate the neutrons produced by Am c) to convert to neutrons the alphas emitted spontaneously by Am d) to enhance the number of delayed neutrons QUESTION: 005 (1.00)
Reactor power on the Mark I decreases on a stable negative period following a reactor scram, following an initial prompt drop. The reason for this is the following.
l a)
All prompt neutrons decay during the prompt drop, and the subsequent rate of power change is dependent only on the half-life of the longest lived prompt gamma emitter.
b)
This rate of power change is dependent on the mean lifetime of the shortest lived delayed neutron precursors.
c)
This rate of power change is dependent on the mean lifetime of the longest lived delayed neutron precursor.
d)
This rate of power change is dependent on the constant decay rate of prompt neutrons following a scram.
QUESTION: 006 (1.00) i In an operating TRIGA reactor, the effect of the xenon poison is different from that due to samarium because:
a)
The xenon poison will begin to decay twelve to 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> after reactor shutdown, whereas the effects of samarium poison will remain indefinitely after shutdown; b)- The magnitude of the xenon poison effect is usually much smaller than thr.t for samarium; c)
While both poisons decay with their respective half lives after shutdown, the samarium poison decays with a shorter half life; d)
While both poisons decay after shutdown, the samarium decays with a much longer half life.
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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A.
RX THEORY. THERM 0 & FAC OP CHARS QUESTION: 007 (1.00)
A reactivity insertion of 2.2 percent is added to a just critical Mark I reactor. What is the equivalent insertion in dollars?
a) 50.21 b) 51.40 c)
$2.00
{
d)
$3.00 QUESTION: 008 (1.00)
Which one of the following most closely approximates " Reactor Period"?
a)
The time in seconds for the neutron population to increase by a factor of 1.333.
b)
The time in seconds for the neutron population to increase by a factor of 1.718.
c)
The time in seconds for the neutron population to increase by a factor of 2.333.
d)
The time in seconds for the neutron population to increase by a factor of 2.718.
1 QUESTION: 009 (1.00)
Immediately after a pulse [approximately 1 milli ~second] where is the HOTTEST part of a fuel element?
a) in the fuel cladding itself b) at the edge of the fuel elements adjacent to the cladding c) 1/3 of the way in to the center of the fuel elements from the edge d) the center of the fuel elements
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
1
l A.
RX THEORY. THERM 0 & FAC OP CHARS i
l QUESTION: 010 (1.00)
The TRIGA Mark I reactor is at a power of I watt, and 25 cents of reactivity is inserted. Calculate the resulting stable reactor period.
a) 48 seconds b) 37 seconds c) 18 seconds d) 10 seconds QUESTION: Oli (1.00)
The TRIGA Mark I reactor is not permitted to be pulsed from power levels above Ikw. The reason for this requirement is:
a)
The additional fast neutron flux from the pulse could dangerously embrittle fuel cladding.
b)
The additional heat from the pulse could cause pool temperature limits to exceed operating specifications.
c)
The additional thermal neutron flux from the pulse could dangerously embrittle fuel cladding.
d)
The additional heat from the pulse could cause fuel temperature limits to be exceeded.
QUESTION: 012 (1.00)
The fundamental design parameter which permits a TRIGA reactor system to operate safely during either steady-state or pulsing conditions is the large prompt negative temperature coefficient of reactivity.
The largest contributor to this design parameter is:
a) doppler effects b) core leakage c) core neutron spectrum-hardening d) formation of core voids
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A.
RX THEORY. THERM 0 & FAC OP CHARS QUESTION: 013 (1.00)
The cladding on the various fuel elements in use.in the Mark I reactor is:
a) aluminum only i
I b) stainless steel only c) aluminum, stainless steel, and incoloy d) aluminum and stainless steel j
QUESTION: 014 (1.00) j i
More plutonium will be produced in the 30-20 fuel than the FLIP fuel in' Mark F.
Why?
l a)
There is much more U-238 in the 30-20 fuel.
b)
There is significantly more U-235 in the 30-20 fuel'.
l c)
Flux peaking is greater in 30-20 fuel.
d)
The 30-20 fuel has much less burnup compared to the older FLIP fuel.
i QUESTION: 015 (1.00) f For the GA Mark F reactor, the following reactivity insertion (s) above "just critical" on delayed neutrons will make the reactor "just prompt critical".
a) 10 cents l
f b) one dollar c) 1%
d) 0.1%
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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l A.
RX THEORY. THERM 0 & FAC OP CHARS QUESTION: 016 (1.00)
In a 20-minute Mark I reactor run with the cooling system 0FF, the pool temperature rise was 3.85*C.
What was the approximate reactor power?
a) 50 kW b) 75 kW c) 100 kW d) 200 kW l
QUESTION: 017 (1.00)
Which statement correctly describes the location where the water treatment system takes suction from the reactor pool, and the reason this location is used?
a)
The upper region to limit siphoning of pool water in case of leakage in system.
b)
The upper region to allow N-16 to decay prior to entering the water monitor box.
c)
Near the top of the core so that N-16 will enter the system rather than become a radiation hazard at the pool surface.
d)
Near the top of the core so impurities are removed before being activated.
QUESTION: 018 (1.00)
The Mark I is being operated at a power of 1 kilowatt in servo mode for the purpose of a D1 Od tube run. At this power level, the servo system adjusts the power demanded by which power indicating channel?
a)
Keithley Channel Kl.
b)
NM1000 c)
NP1000 d) the higher of NM1000 and K1 channels
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
9 A.
RX THEORY. THERM 0 & FAC OP CHARS l
QUESTION: 019 (1.00)
When you switch from steady state mode to pulse mode on the Mark I console's mode control panel, the following changes occur to the reactor safety system.
a)
All % power and HV scrams are bypassed.
l b)
DAC watchdog scram is bypassed.
c)
NMIOOO & NP1000 % power and HV scrams are bypassed.
d)
Two of the three fuel temperature scrams are bypassed.
f QUESTION: 020 (1.00)
The Mark I and Mark F both have Wide Range Channels which provide reactor period information.
Identify the correct answer on how this period information is used for reactor operation.
a)
Both reactors have a period scram for periods shorter than 3 seconds, b)
The Mark I has a period scram as above, but the Mark F does not.
c)
The Mark I has a rod withdrawal permit (RWP) interlock for periods less than a specified minimum, d)
Both the Mark I and Mark F reactor wide range channels provide RWP i
interlocks for periods greater than 1 DPM.
l 1
)
(***** END OF CATEGORY A *****)
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a B.
NORMAL /EMERG PROCEDURES & RAD CON QUESTION: 001 (1.00)
The Technical Specifications for Mark I do not place restrictions on operation with in-core water-filled regions whereas the Mark F Technical Specifications for erbium loaded fuel do place requirements. Why is this?
a)
Because the Mark I fuel is mainly aluminum clad.
b)
Because the negative temperature coefficient of reactivity is larger at I
low temperatures for Mark I.
l c)
Because the fuel with erbium poison is so under-moderated that any extra water will cause power peaking in the adjacent fuel.
d)
Because the H/Zr ratio is larger for the fuel in Mark F.
QUESTION: 002 (1.00)
Which ONE of the following responses is correct if the HV power supply on the K1 power indicating channel fails while operating the Mark F reactor at l
14S0 kilowatts?
a)
The reactor will scram.
1 b)
The reactor will not scram because K1 is only a power indicating channel, with no scram function.
j c)
The reactor will continue operating after giving a trip indication on HVI.
d)
The reactor will continue operating, with the only indication to the i
operator of the possible loss of high voltage being the zero. power I
reading on Kl.
QUESTION: 003 (1.00)
During continuous operation of the Mark F reactor at full power, unmonitored bypass of thermionic capsule scrams is required for extended system repair / maintenance.
This requires the following procedural action:
a)
The on-duty R0 or SR0 need not be notified prior to placing a capsule in scram bypass, as audio and visual console indicators are available to inform him/her of this condition.
b)
Reactor power shall be lowered to 1200 kw before any scrams may be bypassed.
c)
Reactor power shall be reduced to 700 kw or less before any scrams may be bypassed.
d)
Scrams may never be bypassed unless reactor power is reduced below I kw.
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
B.
NORMAL /EMERG-PROCEDURES & RAD CON CUESTION: 004 (1.00)
During a TRIGA King Furnace run at 100 kW, one of the following conditions will automatically scram the Mark I reactor:
a)
NP1000 and NPP1000 channel readings increase to 250 kW.
b)
A decrease in NPP1000 detector HV to 95% of set value.
c)
The pool water radioactivity suddenly increases to 55 mR/h.
d)
A leak in the furnace contair. ment, causing the internal furnace pressure to fall below 11 psig.
l QUESTION: 005 (1.00)
You are operating the Mark I in SS Manual mode at about 10 watts and are setting up to pulse the reactor. However, you are unable to switch the I&C system from manual to pulse mode. The most likely reason for this is:
a) you may switch to pulse mode only at a power of 5 watts or less.
b) air is already applied to the transient rod c) the transient rod cylinder is not in its full up position d) you must be in servo mode prior to switching to pulse mode.
QUESTION: 006 (1.00)
The definition of Reactor Shutdown is one of the following:
a)
When the power to the control rod magnets and solenoids has been turned off and the key removed from the console.
b)
When the reactor is subcritical by at least one dollar of reactivity.
c)
When the operable control rods are such as to make the reactor subcritical by at least 50 cents at all times even with the most j
reactive rod stuck out.
l d)
When no experiments are being inserted into the reactor core or no maintenance on the control rods is in progress.
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
I B.
NORMAL /EMERG PROCEDURES & RAD CON
?.(1.00) l QUESTION:
o i
The Mark I and Mark f Tech Specs permit " Modified Routine Experiments" to be carried out at the facility. Such experiments a) may be carried out after approval of the on-duty SRO.
b) may be performed after obtaining approval on the Irradiation Request of the Associate PIC.
i c) must be approved by the CSC, but further evaluation of hazards is not necessary.
d) may be approved by the PIC, but he/she first needs to obtain a favorable evaluation of the consequences of the required irradiation on reactor safety.
l QUESTION: 008 (1.00)
Both reactors are shutdown, and maintenance work which requires the removal of a control rod drive on the Mark I needs to be accomplished on your shift, which consists of one SR0 and one R0. Which cf the following-(one or more) requirements or conditions are mandatory for maintenance work?
a) cannot be performed because two SR0s are required to perform the work.
b) can be performed, but approval from the APIC or above must be obtained i
because only one SR0 is present, j
c) it has been ascertained that the worth of the shutdown rods in the core is at least twice the available excess reactivity.
d) a spare power indicating channel must be installed and visible from the reactor room and must use the K1 channel detector signal cable.
1 QUESTION: 009 (1.00)
The Mark f Tech Specs require the following automatic scrams for operation with direct conversion devices in core-i a) low diode voltage & diode current i
b) high primary containment temperature (21000 C) c)
high control room radiation levels (2 2.5 mR/hr) d)
high cell top radiation monitor levels (2 60 mR/hr) i
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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B.
NORMAL /EMERG PROCEDURES & RAD CON s
QUESTION: 010 (1.00)
An iodine filter system for the Mark F reactor facility involves a circulating system entirely within the reactor room. The purpose of this system is:
a).To dilute the air within the reactor room in order to prevent the release of any undiluted iodine vapor from the stack after a TRIGA fuel element fails, b)
To shorten the time by one-half, when personnel can safely enter the reactor hall after a significant release of fission products from a failed TRIGA fuel element has occurred.
c)
To reduce the radiation level at the Mark I console in the event of a release of fission products in the Mark F reactor room, d)
To reduce the dose to persons at a distance of 100 meters (GA site boundary) in the event of a release of fission products from a thermionic device.
QUESTION: 011 (1.00)
The Mark F has been operating at full power for one month when an unscheduled scram occurs.
Eight hours later, the reactor is again 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 b
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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B.
NORMAL /EMERG PROCEDURES & RAD CON QUESTION: 012 (1.00) i The following interlock is required in both the Mark I and Mark F Tech Specs:
a)
Withdrawal of a control rod when source level is below the minimum count level.
b)
Withdrawal of any standard rod in pulse mode.
c)
Application of air to transient rod (s) if reactor power exceeds 1 l
kilowatt.
d)
Application of air to transient rod (s) in Pulse mode when the movable cylinder is fully down.
QUESTION: 013 (1.00)
What is the maximum length of travel for the Mark I control rods?
a) 15-1/4 inches for all rods, except the transient rod which can move 30 inches.
b) 15-1/4 inches for all rods, including transient rod.
c) 18 inches for all rods, except the transient rod which can only move 30 inches.
I d) 18 inches for all rods, including transient rod.
QUESTION: 014 (1.00)
What is the principal advantage of using plastic sample containers when irradiating specimens?
a) the amount of radioactivity associated with the container upon removal i
from reactor is small.
r b) plastic is highly resistive to gamma flux degradation.
c) embrittlement of plastic is minimal due to the low thermal neutron cross section of plastic.
d) plastic is highly resistive to fast neutron degradation.
j
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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P.
NORMAL /EMERG PROCEDURES & RAD CON f
QUESTION: 015 (1.00)
Radioactive impurities in the reactor cooling water from normal reactor operations can be:
a)
Na-24, Cl-38, Fe, Fe '
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b)
^
c)
Xe-133, Ba-139, Rb-88 QUESTION: 016 (1.00)
In the event of a release of fission products from a Mark F fuel element clad failure during full power operation, the increase-in airborne activity detected at -the CAM will arise in part from the following radioisotopes:
a) increase in concentrations of N-16 and Ar-41.
b)
Cd-109, Cd-115 and Ta-182 c)
Kr-88, and its daughter Rb-88.
t d)
QUESTION: 017 (1.00)
An emergency has occurred which required the temporary evacuation of the Mark I and Mark F Controlled Access Area. Only one of the following individuals can authorize reentry to resume normal operations:
a)
Security officer on duty b)
GA Emergency Coordinator c)
Facility ERRD d)
The facility ERT member on duty l
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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B.
NORMAL /EMERG PROCEDURES & RAD CON t
QUESTION: 018 (1.00)
During continuous Mark F operations, sustained alarms on hpqt.h the secondary containment pressure of a thermionic capsule as well as the cell top radiation monitor requires the following action:
a)
Restricted reactor room entry until the cause of the alarms has been determined and alarms cleared.
b)
Reactor scram and activation of any appropriate emergency procedures.
c)
Reactor scram, evacuation of facility and declaration of site emergency.
d) lowering of reactor power to see if the alarms would clear prior to activation of any emergency procedures.
QUESTION: 019 (1.00)
During a King furnace run on the Mark I, a release of radioactive gases from the gas trap causes the reading on the HEPA air filter monitor to increase to 25mR/hr. The following automatic actions will occur when this happens:
a)
Reactor scram and closure of ventilation system dampers.
b)
Isolation of ventilation system and closure of room louvers.
c)
Audible and visual annunciation of high radiation level at console.
d)
No automatic action since alarm level is 50 mR/hr.
QUESTION: 020 (1.00)
The appropriate convention for documenting in the operations logbook, removal of control rods from the Mark I core for maintenance purposes is the following:
a) an entry in red ink, cross referencing the entry on the appropriate fuel card.
b) a black ink entry underlined in red, with any maintenance / repair work documented in the maintenance log book.
c) a green ink entry d) a black ink entry.
(***** END OF CATEGORY B *****)
s
C.
PLANT AND RAD MONITORING SYSTEMS QUESTION: 001 (1.00)
[
The " Quality Factor" to relate REM to RAD for thermal neutrons is:
a) 0.5 b) 1.0 I
c) 5.0 d) 10.0 QUESTION: 002 (1.00)
Given a 5 Curie source of 1.5 MeV gamma rays, how far from the source is the unshielded radiation level at 100 mrem /hr?
j a) 7.5 ft.
b) 15.6 ft.
c) 21.2 ft.
d) 31.8 ft.
i QUESTION: 003 (1.00)
During an extended Mark F operation, the ventilation fan belt breaks. The CAM reading generally rises slowly over a few hours. This is because of:
l a)
Argon-41 (Tg-1.83 hr) accumulating slowly 'in the reactor room, I
b)
Chlorine-38 (Tg - 37.3 min) escaping from the top of the reactor pool.
c)
The fission product gases which are normally swept up the stack accumulate in the reactor room and are now detected by the CAM.
d)
The increase in concentration of activation products boiling off from core components into the reactor room.
I
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4
C.
PLANT AND RAD MONITORING SYSTEMS QUESTION: 004 (1.00)
The PIC schedules a tour of the Mark I reactor for a group of eighteen freshmen from a local university, accompanied by one professor.
Two of the students are under 18 years of age; the rest of the group is above 18.
Which one of the following describes the dosimetry requirements for this group?
a)
Film badge or TLD for the two students under 18 as well as the professor for monitoring the group dose.
b)
A total of four pocket type dosimeters for the entire group.
c)
TLDs or film badges for the two students under 18, plus four pocket dosimeters for the rest of the grc d)
TLDs or film badges for the two students under 18, plus two pocket dosimeters for the rest of the group.
l QUESTION: 005 (1.00) i N-16 is one of the radioactive gases that is produced during operation of both TRIGA reactors. The N-16 is produced by which one of the following reactions?
a) 0'6(n,p)N
b)
N'5(n, y )H
f c)
F"(n, a )N
d)
N'5(d, p) N
QUESTION: 006 (1.00)
Which one of the following conditions automatically activates the facility Klaxon evacuation alarm?
a)
Both the Mark I and Mark F RAMS alarming at the low alarm set point, b)
The Mark F RAM only alarming at the high alarm set point.
c)
The Mark I RAM alarming at the low set point, and the Mark F RAM at the high set point.
d)
The Mark F CAM alarming at 50,000 CPM.
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A a
C.
PLANT AND RAD MONITORING SYSTEMS 4
QUESTION: 007 (1.00)
How would an accessible area where the radiation level is 5 mR/hr continuously for a full work week be posted?
a)
CAUTION - RADIATION AREA b)
CAUTION - HIGH RADIATION AREA c)
CAUTION - RADI0 ACTIVE MATERIALS AREA d)
CAUTION - RESTRICTED AREA QUESTION: 008 (1.00)
When performing neutron radiography (NR) using the vertical NR beam port, all areas must be roped off where the dose or dose rate exceeds, as determined from prior radiation measurements, to be:
a) 5 mR/hr.
I b) 20 mR cumulative dose over the duration of the run.
c) 100 mR cumulative dose over the duration of the run.
d) 100 mR/hr.
QUESTION: 009 (1.00)
The purpose of the diffuser system in the Mark F reactor is to:
a) aid in the mixing of the water, which results in the pool attaining a uniform temperature b) reduce pool surface temperature, since the return water is cooler c) increase the transport time of radioactive gases from the core to the pool surface d) reduce pool surface temperature, which reduces surface dose rate.
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I
C.
PLANT AND RAD MONITORING SYSTEMS
[
QUESTION: 010 (1.00) j Hot does the Mark I pneumatic rabbit sample transfer system function to minimize contamination while inserting and removing samples from the l
terminus in the core?
l a)
The blower exhausts through a filter into the reactor room exhaust duct f
and pressurizes the system to move the sample into and out of the l
terminus.
i b)
The blower exhausts through a filter into the reactor room exhaust duct and draws a vacuum on the system to move the sample into and out of the terminus.
c)
The blower draws air through a filter from the reactor room exhaust duct and pressurizes the system to move the sample into and out of the l
terminus.
d)
The blower draws air through a filter from the reactor room exhaust duct and draws a vacuum on the system to move the sample into and out of the terminus.
QUESTION: 011 (1.00)
{
Argon-41 releases from the Mark F stack are measured as follows:
s a)
An ionization chamber placed directly in the air path downstream of the HEPA filter.
b)
A shielded Geiger-Muller detector placed directly in the air path downstream of the HEPA filter.
l t
c)
A shielded Geiger-Muller detector, with the air to the detector drawn from sampling pipes connected to the main ventilation duct.
l d)
An unshielded Geiger-Muller detector placed adjacent to the HEPA filter.
QUESTION: 012 (1.00)
Dispersion of radioactive materials outside the TRIGA Reactors Facility controlled areas are measured by:
i a)
Four shielded GM detectors located around the facility which provide a continuous readout of activity to the HP laboratory, Bldg. 02/548.
b)
Six air samplers with filters to collect particulate matter, to monitor 4
airborne releases either during a potential emergency or for routine l
monitoring.
c)
A single GM detector located on the roof above the Mark F reactor control room to monitor releases from the stack.
d)
Performing radiation surveys using the micro-R meter once a quarter.
[
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1 l
C.
PLANT AND RAD MONITORING SYSTEMS
. QUESTION: 013 (1.00)
If either the identity or concentration of any radionuclide in a mixture is not known, the limiting values for activity for airborne materials for a restricted and unrestricted areas are,
, and a) 6 x 103 p Ci/ml and 3 x 10'8 p Ci/ml b) 2 x 10 p Ci/ml and 6 x 10'7 p Ci/ml c) 6 x 10~7 pCi/ml and 3 x 10-s p Ci/ml d) 6 x 103 pCi/ml and 2 x 10 pCi/ml QUESTION: 014 (1.00) 2 The flux of thermal neutrons (n/cm -sec) which will give a-dose of 100 mR in 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> is:
a) 30 b) 670 c) 500 d) 280 QUESTION: 015 (1.00)
Using an "R02" instrument, you observe the following readings when measuring the dose rate at I foot from an activated sample:
200 mR/hr with shield open, and 150 mR/hr with the shield closed. The difference between the "open" and " closed" reading is due to the following type of radiation.
a) beta and alpha b) beta c) gamma d) alpha 1
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C.
PLANT AND RAD MONITORING SYSTEMS QUESTION: 016 (1.00)
The TLD personnel radiation badges used at the TRIGA Reactors Facility measure accumulated dose due to:
a) thermal and fast neutrons as well as non-penetrating (p) and penetrating (y) radiations, b)
(y) radiation only.
c)
(p) and (y) radiation only.
d) fast neutrons only.
QUESTION: 017 (1.00) l Assume a 10 curie point source of a 2 HeV gamma emitting radionuclide. The-unshielded dose rate (R/hr) at 10 feet from the source is:
a) 120
{
b) 2 c) 1.2 l
d)
0.2 QUESTION
018 (1.00)
Assume a 10 Curie point source of a 2 MeV gamaa emitting radionuclide. How many half thickness of lead shielding are required to bring the dose down to i
2.5 mR/hr at 10 feet?
a) 1.
I b) 29 c) 9 d) 5
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j i
~.
.{
1 y
l C.
PLANT AND RAD MONITORING SYSTEMS-I l.
g 3
j
.i QUESTION:-019 (1.00) DELETED 1
A survey of radiation and contamination levels has been made by the Health Physics surveyor. 'The' map (Figure -1) on the following page has the results' of this survey.
Based only on this survey and the requirements of 10 CFR 20 answer the following:
j i
19-a What posting is-required in the LABORATORY?
'l a) CAUTION AIRBORNE RADI0 ACTIVITY AREA l
b) CAUTION HIGH RADIATION AREA 1
c) CAUTION RADIATION AREA d) NO RADIATION POSTING REQUIRED 19-b What posting is required in the Mark F Reactor Room?
a) CAUTION AIRBORNE RADI0 ACTIVITY AREA
'b) CAUTION HIGH RADIATION AREA c) CAUTION RADIATION AREA d) NO RADIATION POSTING REQUIRED l
19-c What posting is required in the SHOP 7
-j a) CAUTION AIRBORNE RADI0 ACTIVITY AREA b) CAUTION HIGH RADIATION AREA' c) CAUTION ' RADIATION' AREA j
d) NO RADIATION POSTING REQUIRED.
19-d What posting is. required in'the STORAGE BUILDING 7-i a) CAUTION AIRBORNE RADI0 ACTIVITY AREA b) CAUTION HIGH' RADIATION AREA l
c) CAUTION' RADIATION AREA 1
d) NO RADIATION POSTING REQUIRED j
QUESTION: 020 (1.00)
Pit Water Chemistry is routinely performed on both the Mark I and Mark F-reactors to determine the level and trend of activation, fission and corrosion products in the water. This analysis is required to be performed:
j i
a) weekly l
i b) monthly i
c) quarterly
-'I d) semi annually 1
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-l
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i l
l n..,.
L L..
7 A.
RX THEORY. THERM 0 & FAC OP CHARS Answer Key Ouestion No.
Answer Beference I
a Training Manual, Section 6.6.4 2
b Training Manual, Section 6.3.3 3
a Training Manual, Section 6.5.1 4
c Training Manual, Section 1.4.4 5
c Training Manual, Section 6.2.2 6
a Training Manual, Section 6.3.7 7
d Training Manual, Section 6.2.4 8
d Training Manual, Section 6.2.5 9
b Training Manual, Section 6.5.2 10 b
Training Manual, Section 6.2.5 11 d
Training Manual, Section 6.5 12 c
Training Manual, Section 6.3.3 13 d
Training Manual, Section 1.4.1 14 a
Training Manual, Section 1.4.1 15 b
Training Manual, Section 6.2.4 16 d
Mark I 50P No. 8, Section 8.3 17 a
Training Manual, Section 1.6.1 18 b
Training Manual, Section 2.1.5 19 c
Training Manual, Section 2.1.7 20 c
Training Manual, Section 2.1.3 & 2.3.6 9
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1 t
B.
NORMAL /EMERG PROCEDURES & RAD CQH Answer Key Question No.
Answer Reference 1
c Training Manual, Section 6.6.1 2
c Mark F S0P No. 2 Training Manual Section 2.2.3 3
c Mark F S0P No. 15, Section 15.2 4
d Mark I S0P No. 15, Section 15.2 Training Manual Section 2.1.6 Tech Specs Section 8.2 & Table I 5
b Mark I S0P No. 5, Section 5.6 6
b Mark I Tech Specs Section 1.0 7
d Mark I Tech Specs Section 8.1 8
c Mark I S0P No. 1, Section 1.10 9
b Mark F Tech Specs, Section 10.2 10 d
Mark F Tech Specs, Section 10.2 Mark F S0P No. 1, Section 1.5 11 a
Training Manual, Section 6.3.7 12 a
Mark I Tech Specs Table II Mark F Tech Specs Table 11 13 b
Training Manual, Section 1.5 14 a
Training Manual, Section 5.4.3 15 c
Training Manual, Section 5.4.4 16 c
Training Manual, Section 5.4.2 17 c
Mark I and Mark F Emergency Procedures Mark I and Mark F SDP No. 3, rection 3.4.3 18 b
Mark F SDP No. 15, Section 15.2.6 19 c
Mark I SOP No. 3, Section 3.5 Training Manual, Section 2.1.8 20 b
Mark I S0P No. 1, Section 1.8
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i
t C.
PLANT AND RAD MONITORING SYSTEMS Answer Key Question No.
Answer Reference I
c 10CFR20 and Training Manual Appendix C 2
c 6 CE Rule of Thumb 3
a Training Manual, Section 5.4.7 4
e Administrative Procedures Section 3.1 5
a Training Manual, Section 5.4.7 6
c Mark 1 & Mark F S0P No. 3.3 7
a 10CFR20.202, Training Manual Appendix C 8
d Mark I S0P No. 15.1 9
c Training Manual, Section 5.4.7 10 b
Training Manual, Section 1.12.1 11 c
Mark F S0P No. 3.6 12 b
Administrative Procedures Section 5.1.6 13 d
10CFR20 Appendix B 14 b
10CFR20.5 Training Manual Appendix C 15 b
Training Manual, Section 5.5.1 16 a
Training Manual, Section 5.5.3 17 c
GCE Rule of Thumb 18 c
Training Program 19a b
10CFR20 19b a
10CFR20 19c c
10CFR20 19d c
10CFR20 20 c
Mark F SOPS, Section 4.8 I
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