ML20128K110
| ML20128K110 | |
| Person / Time | |
|---|---|
| Site: | MIT Nuclear Research Reactor |
| Issue date: | 10/03/1996 |
| From: | Isaac P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20128K084 | List: |
| References | |
| 50-020-OL-96-01, 50-20-OL-96-1, NUDOCS 9610100285 | |
| Download: ML20128K110 (43) | |
Text
... _
e U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-020/0L-96-01 l
FACILITY DOCKET N0.:
50-020 FACILITY LICENSE NO.:
R-37 FACILITY:
Massachusetts Institute of Technology EXAMINATION DATES:
September 3-5, 1996 EXAMINER:
Patrick a e, Chief Examiner SUBMITTED BY:
/46 eou
/0
(
[hiefExaminer D'at6 Pat J. Is
SUMMARY
During the week of September 2,1996, the NRC administered Operator Licensing Examinations to four Reactor Operator (RO) and one Senior Reactor Operator Upgrade (SROU) candidates. All candidates passed the examinations.
ENCLOSURE 1 9610100285 961007 ADOCKOSOOgO PDR
- q h f' REPORT DETAILS 1.
Examiners:
Patrick J. Isaac, Chief Examiner 1
2.
Results:
3 R0 PASS / FAIL SR0 PASS / FAIL TOTAL PASS / FAIL Written 4/0 N/A 4/0 Operating Tests 4/0 1/0 1/0 Overall 4/0 1/0 5/0 j
3.
Exit Meeting:
Thomas Newton, MIT, Asst. Superintendent for ingineering Frank Warmsley, MIT, Operations Coordinator Patrick Isaac, NRC, Chief Examiner The facility examination comments were discussed as noted in Enclosure 2.
There were no generic concerns raised by the Chief Examiner.
.~
NRC RESOLUTIONS - WRITTEN EXAMINATION QUESTION (A.1)
With all rods in, cold, Xe free, the count rate is 1000 cpm and the reactivity is -$5.36. What final count rate would you expect to see if the operator withdraws $2.205 of reactivity?
a.
344 cpm b.
1726 cpm c.
2488 cpm d.
3662 cpm Answer: b Facility Comment:
The calculation given in the answer key in incorrect (negative reactivities should have been used). However, the actual answer (1676 cpm) is most closely represented by answer b.
NRC Resolution:
Comment Accepted. No modification to the answer key is required.
QUESTION (A.6)
During a fuel loading, if the fuel elements are loaded to the core one by one starting near the source and proceeding toward the detector, which ONE of the following statements describes the effect of this loading sequence on the 1/M plot?
a.
The sequence has no effect on the 1/M plot.
b.
The 1/M plot will have a less angular slope, predicting criticality for a larger number of elements.
c.
The 1/M plot will have a steeper slope, initially predicting criticality for a fewer number of elements.
d.
The 1/M plot will approach infinity. Predicting criticality would be difficult.
Answer: b Facility Comment:
The wording of the question is unclear as to the actual core configuration and could thus have more than one correct answer. We suggest this question be removed.
Et1Q.LOSURE 2
J NRC Resolution:
Comment accepted. This question will be deleted from the examination.
T QUESTION (A.07)
Which ONE of the following describes how the effective delayed neutron fraction varies over core
]
life?
- a. Decreases due to the burnup of U2" b.
Increases due to the bumup of U2
- i ra
- c. Decreases due to the buildup of Pu
- d. Increases due to the buildup of Pu "
2 Answer: c 1
Facility Comment:
i The MIT reactor, having 93% enriched uranium fuel, has very little "Pu buildup. Operators are 2
always trained to answer that delayed neutron fraction is constant. We suggest this question be removed.
NRC Resolution:
1 i
Comment accepted. This question will be deleted from the examination.
QUESTION (A.15)
How much (by what factor) would power increase in one second in a prompt critical reactor?
a.
1.00 x 102 5
b.
1.00 x 10 c.
7.55 x 1024 d.
6.33 x 108 Answer: d Facility Comment:
The prompt neutron lifetime used in the solution is different than the one stated in the equation sheet, which yields a significantly different answer. Therefore, both answers @ and (d) should be counted as correct.
NRC Resolution:
Comment accepted. The answer key has been corrected to accept both "c" and "d" as correct.
-.-.. = -
- _ _ ~
QUESTION (A.16)
Which one of the following describes the reactivity effect and associated reason if heavy water
)
was mixed with the light water reflector?
a.
negative reactivity due to higher moderating power of heavy water.
1 b.
positive reactivity due to the higher absorption cross-section of light water.
c.
negative reactivity due to the higher moderating power of light water.
d.
positive reactivity due to the higher absorption cross-section of heavy water.
Answer: b Facility Comment.
The small light water region surrounding the core is not normally referred to as the reflector (the term " reflector" refers to the larger heavy water region surrounding the core tank). Thus, there was again considerable confusion as to the meaning of the question. We suggest that this j
question be removed or that future exams should avoid the use of term " light-water reflector".
(Note: We have raised this issue previously.)
NRC Resolution:
Comtunt accepted. This question will be deleted from the examination.
Question (B.3)
Match the general area radiation levels listed in column A with the corresponding type of radiation area listed in column B. (Note: Only one answer for each item in column A. Items from column B may be used more than once or not at all.)
Column A Column B a.
15 mrem /hr 1.
Unrestricted Area b.
65 mrem /hr 2.
Radiation Area c.
203 mrem /hr 3.
520 mrem /hr 4.
Very High Radiation Area Answer:
- a. 2
- b. 2
- c. 3
- d. 4 Facility Comment:
3(d): The correct answer should be (3).
NRC Resolution:
Comment accepted. The answer key for B.3d will be modified to accept (3) as correct.
Question (B.4)
Match the four surveillances listed in column A with the correct Technical Specification definition listed in column B. (Note: Only one answer for each item in column A. Items in column B may be used more than once or not at all.)
Column A Column B a.
During shutdown you verify operation of period channel by
- 1. ChannelCheck verifying power decreases by a factor of 10 in three minutes b.
Following maintenance on Nuclear Instrument channel 1 you
- 2. ChannelTest compare its readings to Nuclear Instrument channel 2 readings.
c.
You verify a temperature channel's operation by replacing the RTD
- 3. Channel Calibration with a precision variable resistance and checking proper output.
d.
Based on differences between a calorimetric of the primary system and the readings on Nuclear Instrumentation you make adjustments.
Answer: a,1 b,1 c, 2 d, 3 Facility Comment:
Channels #1 and #2 are not normally compared with each other, which caused some confusion as to the meaning of the example. (Note: We don't emphasize the difference between a ' check' and a ' test' to RO candidates.)
NRC Resolution:
Comment accepted. Per telephone conversation with Mr. Thomas Newton, MIT, Assit.
Superintendent for Engineering, the staff understands that the terms ' channel check' and
' channel test' are not emphasized to RO candidates and are not mentioned in any of the procedures at the MIT reactor. Therefore, the staff agrees that question B.4 is not valid for RO candidates at MIT and will be deleted from the examination.
Question (B.7)
You volunteered to help cleanup an accident at a local Power Reactor facility. During the 4
cleanup you received 4.0 REM. What are your limits with respect to receipt of radiation at MIT, j
based on this?
a.
No effect on any radiation limits at MIT. The radiation received during cleanup is tracked only by the power facility and does not count against any radiation dose which may be received at MIT.
b.
No effect on any radiation limits at MIT. The radiation dose received during the cleanup is tracked as a Planned Special Exposure, at the facility, and is not applicable to MIT doses.
c.
Decrease in annual and life-time Planned Special Exposure (PSE) limits at MIT. The radiation dose received during the cleanup is tracked as part of your Planned Special Exposure (PSE) limit.
d.
Decrease of annual whole body limit by 4 Rem.
Answer: c Facility Comment:
The question does not state whether the cleanup work is part of a Planned Special Exposure at the power reactor or as part of a normal occupational exposure. Therefore answers @ and (d) are both acceptable l
NRC Resolution:
Comment accepted. Both answers "c" and "d" will be accepted as correct.
Question (C.11 During startup, after channel 3 starts reading you must shift channels 1 and 2 from their fission chamber inputs to their ion chamber inputs. How do you do this? For the channel you the overall gain and for the fission chamber you the discriminator setting.
a.
Increase, increase b.
Increase, Decrease c.
Decrease, increase d.
Decrease, Decrease Answer: c
.... =_ - _- _._ _ - -
Facility Comment i
Standard practice, according to the MIT Standard Operating Plans, is to decrease the gain but not to adjust the discriminator setting (PM 2.3.1). Therefore, answers C and (d) are both acceptable.
NRC Resolution:
Comment accepted. The answer key has been modified to accept both "c" and "d" as correct.
Question (C.4)
The surveillance system is activated. An alarm on the center scam panel will cause an audible at l
all of the below listed areas except...
i a.
the Reactor floor.
b.
the Utility room.
c.
the Reception desk.
d.
the Operations Office.
Answer: d Facility Comment:
The surveillance system alarm from the reception desk is very easily heard in the operations office. Standard practice also calls for activation of the Control Room surveillance TV monitor which transmits the surveillance alarm audibly to the Operations Office.
NRC Resolution:
Taking the facility's comment in consideration, question C.04 has no correct answer and, therefore, will be deleted from the examination.
Question (C.10)
Which one of the following is incorrect concerning interlocks associated with the Liquid Waste System?
a.
On a high sump level signal a second parallel sump pump will automatically start.
b.
On a high Waste Tank level in one tank, the inlet city water solenoid valve will close.
c.
On a high sump level signal, the inlet city water solenoid valve will close.
d.
On a high Waste Tank level in one tank, both sump pumps will be shut off.
Answer: d l
Facility Comment The second parallel sump pump has been permanently removed. Therefore, answers (a) and (d) are both acceptable.
NRC Resolution:
i Because of new information provided by the facility's comment, this question is no longer valid and will be deleted from the examination.
Question (C.14)
Which one of the following actions (along with reason) would you take on a loss of the Multichannel Radiation Monitoring System while people were on the Main Reactor Floor? (Note:
Allindividual monitors are operating normally.)
a.
Immediately evacuate all personnel due to a loss of all area radiation monitors on the reactor floor, b.
None, required. One of the three area radiation monitors is individually powered so that the requirement for one monitor available is met.
None required. Two of the three area radiation monitors are individually powered so that c.
the requirement for one monitor available is met.
d.
None required. All three area radiation monitors are individually powered so that the requirement for one monitoris met.
Answer: c Facility ComnigDt Part of the multichannel Radiation Monitoring System (including one of the reactor floor monitors) has been replaced with independent units. Therefore, both answers (b) and C are acceptable. (Note: Our training material was out of date.)
NRC Resolution:
Comment accepted. The answer key will tv modified to accept both "b" and "c" as correct.
1 U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION l.
FACILITY:
Massachusetts inst. of Tech.
REACTOR TYPE:
MITR-ll DATE ADMINISTERED: 96/09/03 REGION:
1 CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
4 i
Answers are to be written on the answer sheet provided. Attach the answer sheets to the examination.
P ints 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 cxamination starts.
l
% OF CATEGORY % OF CANDIDATE'S VALUE TOTAL SCORE CATEGORY l
r 17.00 A
A.
REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 17.00 A
B.
NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 17.00 A
C.
PLANT AND RADIATION MONITORING SYSTEMS 51.00 TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature ENCLOSURE 3 i
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During th3 cdministr: tion of this examination th3 following rul:s epply:
1 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 Mamination.
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 Ruly 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.
4 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 tumed 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 l
= &c, bT = 6 bH = UA bT p'"**, (p -Q)*
2a(k)f l
l' = 5 x 10 seconds g gg, _S_,
S
-p 1-K,,
A,, = 0.1 seconds -1 CR,(1 -K,,,) = CR,(1 -K,,,)
CR,(-p,) = CR,(-pa)
A,pl 1 -K.a, 1
SUR = 26.06 M=
,Q-p, 1 -K,,,
i 1
CR P=P 10 sun (n s
0 M=
=
j 1-K,,
CR, 2
SDM = (1 -K,y) t i
p,pe ne T=
P OII-P) P, I
p-Q 0-p
~ "* W, y,[.
b-p gp, "k,,,x K,,,
- Wa p
A,p 0.693 (K,,-1)
Tx-p=
1 K,,
DR =DR e
DR,d,' = DR d,"
o a
DR = 6CE(n)
M - Rem, G - des, g:
E - Mev, R - feet (p,-D)*
(pi D)*
- Peak, Peak, 1 Curie = 3.7 x 10 dis /sec 1 kg = 2.21 lbm 1 Horsepower = 2.54 x 10' BTU /hr 1 Mw = 3.41 x 10' BTU /hr 1 BTU = 778 ft-lbf
- F = 9/5 *C + 32 1 gal (H O) = 8 lbm
- C = 5/9 ("F - 32) 2 cp = 1.0 BTUlbrilbml"F c, = 1 callsec/gml*C
1
, Section A: Reactor Theorv. Thermo. & Fac. Ooeratina Characteristics Pzg31 QUESTION (A.01)
[1.0]
With all rods in, cold, Xe free, the count rate is 1000 cpm and the reactivity is -$5.36. What final count rate i
would you expect to see if the operator withdraws $2.205 of reactivity?
a.
344 cpm b.
1726 cpm c.
2488 cpm I
d.
3662 cpm i
i QUESTION (A.02)
[1.0)
With the reactcr on a constant period, which transient requires the LONGEST time to occur?
A reactor power change of:
- e. 5% of rated power-going from 1% to 6% power of rated power l
- b. 10% of rated power - going from 10% to 20% power of rated power c.
15% of rated power - going from 20% to 35% power of rated power
- d. 20% of rated power - going from 40% to 80% power of rated power QUESTION (A.03)
[1.0]
The time required to increase power from 100 watts to 250 Kwatts on a 5 second period is about:
a.
40 seconds b.
90 seconds c.
200 seconds d.
360 seconds QUESTION (A.04)
[1.0]
Which ONE of the following statements is a characteristic of suberitical multiplication?
a.
The number of neutrons gained per generation doubles for each succeeding generation.
b.
A constant neutron population is achieved when the total number of neutrons produced in one generation is equal to the number of source neutrons in the next generation.
c.
For equal reactivity additions, it takes less time for the equilibrium suberitical neutron population level to be reached as Keff approaches one.
d.
Doubling the indicated count rate will reduce the margin to criticality by approximately one half.
Section A: Reactor Theory. Thermo. & Fac. Ooeratino Characteristics P:ge 2 l
QUESTION (A.05)
[1.0)
Shortly after a reactor trip, reactor power indicates 0.5% where a stable negative SUR is attained. Reactor power will be reduced to 0.05% in approximately seconds.
- c. 90 l
- b. 180
- c. 270
- d. 360 QUESTION (A.06)
[1.0)
DELETED During a fuel loading, if the fuel elements are loaded to the core one by one starting near the source and proceeding toward the detector, which ONE of the following statements describes the effect of this loading s;quence on the 1/M plot?
a.
The sequence has no effect on the 1/M plot.
b.
The 1/M plot will have a less angular slope, predicting criticality for a larger number of elements.
The 1/M plot will have a steeper slope, initially predicting criticality for a fewer number of elements.
c.
J d.
The 1/M plot will approach infinity. Predicting criticality would be difficult.
QUESTION (A.07)
[1.0)
DELETED Which ONE of the fo; lowing describes how the effective delayed neutron fraction varies over core life?
- a. Decreases due to the bumup of U2x
- b. Increases due to the burnup of U2n 2n
- c. Decreases due to the buildup of Pu 2m d.
Increases due to the buildup of Pu QUESTION (A.08)
[1.0)
An initial count rate of 100 is doubled five times during startup. Assuming an initial K,=0.950, what is the new K,7
- c. 0.957
- b. 0.979
- c. 0.988
- d. 0.998
Section A: Reactor Theorv. Thermo. & Fac. Ooeratina Characteristics Piga 3 QUESTION (A.09)
[1.0]
l Given a source strength of 100 neutrons per second (N/sec) and a multiplication factor of 0.8, the expected neutron count rate would be:
i l
c.
125 N/sec i
b.
250 N/sec g
c.
400 N/sec d.
500 N/sec QUESTION (A.10)
[1.0]
Which one of the following is the main source of heat in the reactor after shutdown?
a.
Decay of fission products b.
Fission due to delayed neutrons c
Spontaneous fission with:n the core d.
Decay of radioactive structural material QUESTION (A.11)
[1.0}
Why does the fuel temperature (Doppler) coefficient becomes less negative at higher fuel temperatures?
a.
As reactor power increases, the rate of increase in the fuel temperature diminishes, b.
Neutrons penetrate deeper into the fuel, resulting in an increase in the fast fission factor.
c.
The amount of self-shielding increases, resulting in less neutron absorption by the inner fuel.
d.
The broadening of the resonance peaks diminishes per degree change in fuel temperature.
QUESTION (A.12)
[1.0)
Which one of the following statements describes the effect of an increase in fuel temperature on the neutron lifa cycle?
a.
The probability that a thermal neutron will lose energy in a collision with an excited state hydrogen atom in UZrH, increases.
b.
The probability that a fast neutron will escape resonuce capture decreases.
c.
A shift in the thermal neutron spectrum, towards lower energies, occurs in the fuel element.
d.
The mean free path for fast neutrons in the fuel element decreased.
)
' Section A: Reactor Theory. Thermo. & Fac. Ooeratina Characteristics Pag 2 4 QUESTION (A.13)
[1.0)
Which one of the following could result from an attempt to start up the reactor with the source range channels not on-scale?
c.
The reactor could not be started up because there would not be enough source of neutrons to start the chain reaction.
b.
It is possible that reactor power would not be indicated on the nuclear instrumentation until an incident fission reaction resulted in a very short period.
Subcritical multiplication would result in a stable count rate on the nuclear instrumentation even though c.
power was increasing.
d.
The reactor would go critical at a lower shim bank height.
QUESTION (A.14)
[1.0)
Which one of the following interactions plays the most important role in the production of source neutrons for daily reactor startups at MIT7 c.
uPo2io_>,poros + o '
n d
b.
Porto _ _>,p oros + 2He u
c.
H2 + y ->,H' + c '
n 3
d.
.Be' + y --> 2 He + o '
d n
2 QUESTION (A.15)
[1.0)
How much (by what factor) would power increase in one second in a prompt critical reactor?
a.
1.00 x 102 b.
1.00 x 105 c.
7.55 x 1024 d.
6.33 x 105 QUESTION (A.16)
[1.0)
DELETED Which one of the following describes the reactivity effect and assy.iated reason if heavy water was mixed with the light water reflector?
s.
negative reactivity due to higher moderating power of heavy water, b.
positive reactivity due to the higher absorption cross-section of light water.
negative reactivity due to the higher moderating power of light water.
c.
d.
positive reactivity due to the higher absorption cross-section of heavy water.
~ _ - -.. _ - -,
i l
. Section A* Reactor Theory. Thermo. & Fac. Ooeratina Characteristics Ptga 5 QUESTION (A.17)
[1.0)
What thickness of concrete is needed to reduce the intensity of a narrow 500 kev photon beam to one-fourth its value (in units of cm), given that the mass attenuation coefficient for concrete @ 500 kev is 0.089 cm'/g and the density of concrete is 2.35 g/cm*?
a.
8.135 cm b
6.628 cm i
c.
4.864 cm t
d.
2.357 cm QUESTION (A.18)
[1.0]
is there a physical limit on the rate at which power can be raised?
a.
No.
b.
Yes, the control blade speed.
c.
Yes, the average delayed neutron lifetime.
d.
Yes, the prompt neutron lifetime.
l QUESTION (A.19)
[1.0]
Which one of the following BESTexplains the ef'en ;f a rising coolant temperature on reactivity?
a.
The average energy of the neutrons increases.
Less neutrons are absorbed by U-235.
Neutron leakage increases.
b.
The average energy of the neutrons increases.
More neutrons are absorbed by U-235.
Neutron leakage increases, c.
The average energy of the neutrons decreases.
Less neutrons are absorbed by U-235.
Neutron leakage decreases.
d.
The average energy of the neutrons decreases.
More neutrons are absorbed b/ U-235.
Neutron leakage increases.
j
' Section A: Reactor Theory. Thermo. & Fac. Ooeratina Characteristics Paga 6 QUESTION (A.20)
[1.0)
The reactor can be run with an inoperable shim blade provided that:
a.
The blade is fully withdrawn.
b.
Operations is not allowed.
c.
The blade is fully inserted.
d.
The blade is above the shim bank.
4 l
c
~.
Section B: Normal /Emeraency Procedures & Rad Con Pzga 7 QUESTION (B.01)
[1.0)
The air purge above the reactor is secured. Which one of the following is the action required by Technical V
Specifications if a sample of the air space indicates an H concentration of 1.0 /o?
2 s.
Major Scram.
b.
Minor Scram, c.
Reduce power to less than 200 Kw.
d.
Reduce power to less than 100 Kw.
QUESTION (B,02)
[1.0)
Which of the following is the Technical Specification concerning transfer of irradiated fuel into the transfer cask?
a.
Reactor has been shutdown for a minimum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
Reactor has not been operated above 1 MW for a week.
c.
Reactor has not been operated above 100 KW for four days.
d.
Reactor has been shutdown for a minimum of six days.
QUESTION (B.03)
[2.0)
Match the general area radiation levels listed in column A with the corresponding type of radiation area listed in column B. (Note: Only one answer for each item in column A. Items from column B may be used more than once or not at all.)
Column A Column B a.
15 mrem /hr 1.
Unrestricted Area b.
65 mrem /hr 2.
Radiation Area c.
203 mrem /hr 3.
520 mrem /hr 4.
Very High Radiation Area
.-~.-
. Section 8: Normal /Emeroenev Procedures & Rad Con PIge 8 i
1 1
i!,
QUESTION (B.04)
[2.0)
DELETED Match the four surveillances listed in column A with the correct Technical Specification definition listed in a
column B. (Note: Only one answer for each item in column A. Items in column B may be used more than j
once or not at all.)
j l
Column A Column B i
a.
During shutdown you verify operation of period channel by
- 1. ChannelCheck l
verifying power decreases by a factor of 10 in three minutes i
i b.
Following maintenance on Nuclear Instrument channel 1 you
- 2. ChannelTest compare its readings to Nuclear Instrument channel 2 readings.
c.
You verify a temperature channel's operation by replacing the RTD
- 3. Channel Calibration with a precision variable resistance and checking proper output.
d.
Based on differences between a calorimetric of the primary system and the readings on Nuclear Instrumentation you make adjustments.
l QUESTION (B.05)
[1.0)
Which one of the following materials being irradiated requires monitoring of container during irradiation?
a.
Metastable b.
Explosive c.
Corrosive d.
Radiolytically Decomposible QUESTION (B.06)
[2.0]
Match the experiment type listed in column A with the corresponding Technical Specification limit listed in column B. (Notes: Only one answer for each item in column A. Items in column B, may be used more than once, or not at all.)
Column A Column B a.
Single movable
- 1. 0.2% AK/K b.
Total movable
- 2. 0.5% AK/K c.
Single Non-secured 3.1.0% AK/K d.
Total Non-secured 4.1.5% AK/K o.
Single secured 5.1.8% AK/K f.
Total secured i
Section B: Normal /Emeraency Procedures & Rad Con Pigs 9 I
QUESTION (B.07)
[1.0)
You volunteered to help cleanup an accident at a local Power Reactor facility. During the cleanup you rcceived 4.0 REM. What are your limits with respect to receipt of radiation at MIT, based on this?
a.
No effect on any radiation limits at MIT. The radiation received during cleanup is tracked only by the power facility and does not count against sily radiation dose which may be received at MIT.
b.
No effect on any radiation limits at MIT. The radiation dose received during the cleanup is tracked as a Planned Special Exposure, at the facility, and is not applicable to MIT doses.
c.
Decrease in annual and life-time Planned Special Exposure (PSE) limits at MIT. The radiation dose received during the cleanup is tracked as part of your Planned Special Exposure (PSE) limit.
d.
Decrease of annua' whole body limit by 4 Rem.
OUESTION (B.08)
[1.0)
Which one of the following is a reportable occurrence in accordance with Technical Specifications?
a.
Nuclear Instrument Channel 1 period setpoint at 4 seconds.
b.
An unanticipated change in reactivity of %% AK/K.
c.
D O flow setpoint is at 70 gpm.
2 d.
Single primary pump operation flow trip setpoint is 1000 gpm.
)
l QUESTION (B.09)
(1.0)
Pump MM-1 is LOCKED OUTto support corrective maintenance on the pump (replace packing). Who maintains custody of the key locking the MM-1 breaker open during performance of the work?
a.
Person performing work.
b.
Operator-in-Charge c.
Senior Reactor Operator d.
Reactor Supervisor or his designee.
Section B: Normal /Emeroency Procedures & Rad Con Pags 10 QUESTION (B.10)
[1.0]
So far this year you've received 3.3 Rem whole body dose. You are required to work on a control drive m::chanism in the reactor where there is an average dose rate of 250 mR/hr. Which one of the following times is closest to your stay time without going over? (Assume you are older than 18 years of age.)
a.
3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> b.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> c.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> d.
18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> QUESTION (B.11)
[1.0)
Who by title (s) may authorized reentry after an evacuation of the containment due to high radiation?
a.
The Emergency Director on his own.
b.
The MITR Radiation Protection Officer on his own.
i c.
The Emergency Director after consultation with the Radiation Protection Office.
d.
The MITR Radiation Protection Officer after consultation with the Operations Office.
QUESTION (B.12)
[1.0)
The NRC uses four different categories to classify emergencies. Which one of the following classes of cmergencies is NOT credible at MIT7 l
a.
General Emergency b.
Site Area Emergency J
c.
Alert d.
Notification of Unusual Event QUESTION (B.13)
[1.0]
You wish to perform a startup, but a Safety function NQI required by Technica! Specifications and NQI covered by a procedure must be bypassed. Which one of the following conditions is required before bypassing the safety function?
l a.
Permission from Reactor Superintendent, Duty Shift Supervisor AND Electronics Supervisor.
b.
Permission from Reactor Superintendent DE Duty Shift Supervisor c.
Physical installation must be check by one responsible person after installation.
d.
Shim Blade control handle must be tagged informing operator of bypass (es) installed.
Section Et Normal /Emeroency Procedures & Rad Con Paga 11 QUESTION (B.14)
[1.0]
During a reactor startup you reach 0.5 inches above the Estimate Critical Position for the Shim Bank and the racetor is still subcritical. Which one of the following action is incorrect?
a.
Immediately drive bank in to 1.0" or more below ECP.
b.
Drive each blade out and check neutron level to ensure blade coupled.
c.
Recheck sample reactivities.
d.
If no discrepancy found notify the Superintendent.
QUESTION (B.15)
[1.0)
Following a change in fuel configuration, measurements must be made to determine the conditions of Technical Specification 3.1 are met prior to exceeding...
a.
1 kilowatt b.
10 kilowatts c.
100 kilowatts d.
1 Megawatt QUESTION (B.16)
[1.0]
During a frisk you discover one of your hands is contaminated. Which one of the following would be your initial attempt to remove the contamination?
a.
Use of a mildly acidic solvent, rinsed with hot water.
b.
Wash hand with soap and lukewarm water.
c.
Wash hand with grit, and cold water, d.
Wipe hand with dry paper towels.
I 1
... ~ _. _.. -
Section C. Plant and Radiation Monitorina Svstems Paga 12 QUESTION (C.01)
[2.0)
During startup, after channel 3 starts reading you must shift channels 1 and 2 from their fission chamber inputs to their ion chamber inputs. How do you do this? For the channel you the overall gain and for j
tha fission chamber you the discriminator setting.
c.
Increase, increase b.
Increase, Decrease c.
Decrease, increase d.
Decrease, Decrease QUESTION (C.02)
[1.0)
Which one of the following loads on Electrical Panel #1 will shift to emergency power on a loss of normal power?
a.
Startup Channels l
l b.
Recombiner Heaters c.
Medical Therapy Control Panel d.
Recorders, Clock and Front Panel Outlets QUESTION (C.03) [1.0)
A gas purge is maintained on the vertical sample thimbles while the reactor is operating. Which one of the following gases is used for this purge and why?
a.
He, to reduce the production of Ar and N.
b.
N, to reduce the production of Ar ' and N.
d 2
c.
CO, to reduce the production of Af' and Nitrous Oxide.
2 d
d d.
Ar ", to aid in the production of Ar ' for gamma production.
QUESTION (C.04)
[1.0)
DELETED The surveillance system is activated. An alarm on the center scam panel will cause an audible at all of the below listed areas except...
a.
the Reactor floor.
b.
the Utility room.
c.
the Reception desk.
d.
the Operations Office.
t l
l 1
,e
Section C. Plant and Radiation Monitorina Systems Pcg313 s
QUESTION (C.05)
[1.0)
Which one of the following is the correct type of detector used for Nuclear Instrumentation Channel 9 (used as input to the regulating rod automatic control circuit)?
i a.
Fission Chamber 4
b.
Boron Lined Compensated lon Chamber c.
Boron Lined Uncompensated lon Chamber d.
Unlined lon Chamber QUESTION (C.06) [1.0]
i Which one of the following is the correct value for the alarm setpoint for the high temperature D O reflector 3
2 cl:anup system?
4 a.
40*C b.
50' I
c.
60'C d.
70*C QUESTION (C.07)
[1.0)
Which one of the following is correct with respect to maintaining the D2O reflector dump valve closed when air compressor CM-2 is tagged out for maintenance?
c.
As long as solenoid valves CV-90 and CV-91 remain as is, the dump valve will remain shut.
b.
A dedicated air receiverjust upstream of CV-90 and CV-91, contains sufficient air volume to maintain the dump valve shut for eight hours.
c.
On a low pressure signal a solenoid valve will automatically shift the dump valve air supply to a bank of air cylinders.
d.
When air in the header decreases below 95 psig, a check valve will open supplying air from the backup air receiver.
section C. Plant and Maciation Monttonna systems Pegu T4 l
QUESTION (C.08)
[1.0)
A trainee accidentally depresses the ALL-ABSORBERS-IN pushbutton. Which one of the following actions will stop the inward mction of the control blades?
a.
Going to the out position on the regulating rod.
b.
Depressing the Alarm Acknowledge pushbutton.
c.
Depressing the Alarm Acknowledge pushbutton followed by the Alarm Reset pushbutton.
d.
Depressing the Reactor Start pushbutton 1
QUESTION (C.09)
[1.0)
The secondary system is sampled every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while the reactor is operating. Which one of the following isotopes is used to detect a very small leak from either the D O reflector system or the H O primary system?
2 2
a.
HS b.
N'S c.
F'8 as d.
Kr QUESTION (C.10)
[1.0)
DELETED Which one of the following is incorrect concerning interlocks associated with the Liquid Waste System?
a.
On a high sump level signal a second parallel sump pump will automatically start.
i b.
On a high Waste Tank level in one tank, the inlet city water solenoid valve will close.
c.
On a high sump level signal, the inlet city water solenoid valve will close.
d.
On a high Waste Tank level in one tank, both sump pumps will be shut off.
Section C.~ Plant and Radiation Monitorina Systems P g915 QUESTION (C.11) [2.0)
Using the provided drawing, which one of the following is the correct lineup of solenoid valves to send a rabbit into the reactor utilizing the pneumatic tube system?
a g
w RE,A,QO R a.
A and B shut, C and D open b.
A and B open, C and D shut i
c.
A and D open, B and C shut d.
A and D shut, B and C open QUESTION (C.12) [1.0]
Which one of the following portions of the Medical Therapy Facility is designed to pass neutrons while attenuating undesirable gamma rays?
a.
D O Blister Tank 2
b.
H O Shutter Tank 2
c.
Boral Shutter d.
Bismuth Plug
Section C. Plant and Radiation Monitorina Systems P:ge 16 QUESTION (C.13) [1.0)
Which one of the following is the correct reason that only one vertical thimble may contain a level and period l
channel detector?
c.
Neutron flux is not usable for power detection in all but one thimble.
b.
Only one cable tray supplies the top of the reactor.
i l
c.
Interference with the pneumatic tube system.
d.
The thimble are not large enough to contain the double detectors of channels 1 and 2.
l QUESTION (C.14) [1.0)
Which one of the following actions (along with reason) would you take on a loss of the Multichannel Radiation Monitoring System while people were on the Main Reactor Floor? (Note: Allindividual monitors are operating normally.)
a.
Immediately evacuate all personnel due to a loss of all area radiation monitors on the reactor floor, b.
None, required. One of the three area radiation monitors is individually powered so that the requirement for one monitor available is met.
c.
None required. Two of the three area radiation monitors are individually powered so that the requirement for one monitor available is met.
d.
None required. All three area radiation monitors are individually powered so that the requirement for one monitor is met.
QUESTION (C.15)
[1.0]
The Exhaust Air Effluent Monitor picks up radiation levels in excess of operating limits. Which one of the following actions will NOT occur immediately as a result?
a.
Intake Backup Damper will close b.
Exhaust Fans will stop.
c.
Intake Butterfly Damper will close, d.
Intake Fans will stop.
e.g
Section C. Plant and Radiation Monitorina Svstems PCgg17 QUESTION (C.16)
[1.0]
A radiation survey performed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after the reactor has been shutdown has a contact reading of 2,000 mr/hr on the main heat exchangers. Is this reading normal or abnormal and what is the most likely cause?
a.
Normal, N.
l b.
Normal, F.
i c.
Abnormal, H8 d.
Abnormal, Fission Products 1
QUESTION (C.17) [1.0) j Which one of the following flow detectors does NQI use a flow orifice?
a.
Primary Flow, MF-1.
b.
Reflector Flow, DF-1.
c.
Shield Flow, PF-1.
l d.
Secondary Flow, HF-1 A.
l i
1 Section A: Reactor Theory. Thermo. & Fac. Ooeratino Characteristics Pag 318 ANSWER (A.01) i b
I REFERENCE (A.01)
The.eactor is shutdown by -$5.36 + $2.205 = -$3.155 CR, (1 - keff), = CR, (1 - keff)2 CR = CR, (1 - keff), / (1 - keff)2 2
Keff= 1/1-p where p=$ x p l
Keff,= 1/1-(-5.36 x 0.007) = 0.9638 Keff = 1/1-(-3.155 x 0.007)= 0.9784 2
CR = CR,1 - 0.9638 2
1 - 0.9784
= 1676 cpm ANSWER (A.02) a REFERENCE (A.02)
P=Pe"
- t - In(P/P )
o In 6 > In 2 > In (35/20) > In (3/2) i ANSWER (A.03) e REFERENCE (A.03)
P, = P e"
- t = T (in P/P )
- t = 5 sec (in 250000 w/100 w) = 40 sec ANSWER (A.04) d REFERENCE (A.04)
ANSWER (A.05) b REFERENCE (A.05)
Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida,1991, S 5.47, p. 246.
Lamarsh, J.R., Introduction to NuclearEngineering, Addison-Wesley Publishing, Reading, Massachusetts, 1983. S 7.1, p. 289.
P,=P 10sm - t= log (P/P )/SUR where SUR= -1/3 dpm ANSWER (A.06)
DELETED b
REFERENCE (A.06)
Glasstone, S. and Sesonske, A, Nuclear ReactorEngineering, Kreiger Publishing, Malabar, Florida,1991, $$
3.161 - 3,163, pp.190 & 191.
Lamarsh, J.R., Introduction to Nuclear Engineering, Addison-Wesley Publishing, Reading, Massachusetts, 1983.$
. Section A: Reactor Theory. Thermo. & Fac. Ooeratina Charadenstics Pag 319 ANSWER (A.07)
DELETED C
REFERENCE (A.07)
Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida,1991, i
2.183, p.107.
Lamarsh, J.R., Introduction to Nuclear Engineering, Addison-Wesley Publishing, Reading, Massachusetts, l
1983. @ 7.5, p. 330.
i ANSWER (A.08) d 2
REFERENCE (A.08)
Glasstone, S. and Sesonske, A, Nuclear ReactorEngineering, Kreiger Publishing, Malabar, Florida,1991, Q 3.161 - 3.163, pp.190 - 191.
CR,/CR = (1 - K,n)/(1 - K.,,)
2 1/32 (1 - 0.95) = 1 - K,n 1 - 0.05/32 = K,n l
K,n = 0.9984 4
i ANSWER (A.09) d 1
REFERENCE (A.09)
Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida,1991, @
3.161 - 3.163, pp.190 - 191.
C.R. = S/(1 - K,n) - C.R. = 100/(1 - 0.8) = 100/0.2 = 500 ANSWER (A.10) a REFERENCE (A.10)
Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida,1991, 6.28, p. 337.
ANSWER (A.11) d REFERENCE (A.11)
Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida,1991, @
5.98, p. 94.
ANSWER (A.12) b REFERENCE (A.12)
MITR-il Reactor Physics Notes; Reactivity Feedback para. 5(b).
ANSWER (A.13) b REFERENCE (A.13)
Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida,1991, @@
2.70 - 2.74, pp. 65 - 66.
Section A Reactor Theorv. Thermo. & Fac. Ooeratina Characteristics Pzg2 20 ANSWER (A.14)
~
c REFERENCE (A.14)
MITR-il Reactor Physics Notes; Reactor Startup x
Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida,1991, $$
2.70 - 2.74, pp. 65 - 66.
3 1
ANSWER (A.15) c, d REFERENCE (A.15)
]
Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida,1991, @
5.51, p. 248.
l Lamarsh, J.R., Introduction to Nuclear Engineering, Addison-Wesley Publishing, Reading, Massachusetts, 1983.
7.1, pp. 286 - 287.
l T = (*/p
(* = 5 x 10-5 seconds p =.007 4
T = 5 x 10~5/0.007 = 0.00714 sec P/Po = e'" ~ P/Po = e*"7" = 6.33 x 10' I
4 ANSWER (A.16)
DELETED b
' REFERENCE (A.16)
RSM-10.10 1
ANSWER (A.17) b 1
REFERENCE (A.17) l=l e" o
1/l, = 0.25 = e# en:3six 0.25 = e42 mix In(0.25) = In(e+2 mix)
-1.386 = -0.2091X X = 6.628 cm
~
ANSWER (A.18) d REFERENCE (A.18)
Reactor Physics Notes " Reactor Kinetics" pgs. 5 + 6 ANSWER (A.19) a REFERENCE (A.19)
Rtactor Physics Notes: " Reactor Kinetics"; " Coolant Temperature" ANSWER (A.20) d REFERENCE (A.20) d Technical Specifications 3.9.2
Section B: Normal /Emeroency Procedures & Rad Con Pega 21 ANSWER (B.01) c REFERENCE (B.01)
MITR-Il Tech. Spec. $ 3.4, p.14 ANSWER (B.02) c REFERENCE (B.02)
MITR-Il Tech. Spec. 9 3.10 pp. 3 39.
ANSWER (B.03) a,2; b,2; c,3; d 3; REFERENCE (B.03) 10 CFR 20.1 Definitions ANSVER (B.04)
DELETED a,1; b,1; c,2; d,3 REFERENCE (B.04)
MITR-il Tech Spec. QS 1.12,1.13 & 1.14
]
ANSWER (B.05)
C i
REFERENCE (B.05)
MITR-Il Tech. Spec. S 6.1, Table 6.1-1.
ANSWER (B.06) a,1; b,2; c,2; d,3; e,5; f,5 REFERENCE (B.06)
MITR-Il Tech. Spec. S 6.1, Table within specification 1, p. 6-1.
ANSWER (B.07) c, d REFERENCE (B.07) 10 CFR 20.1206, and 20.1201(b).
ANSWER (B.08) c REFERENCE (B.08)
MITR-Il Tech. Spec. 6 3.7, Table I ANSWER (B.09) a REFERENCE (B.09)
MITR-Il PROCEDURE MANUAL Chapter 1 Administrative Procedures S 1.14.3 Equipment Tagout and Lockout Procedure.
Section B: Normal /Emeroency Procedures & Rad Con Pcge 22 ANSWER (B.10) b 5.0 - 3.3 = 1.7 Rem allowable 1.7 Rem /.25 Rem /hr 6.8 = 6 REFERENCE (B.10) 10 CFR 20.1201 l
ANSWER (B.11) i c
REFERENCE (B.11)
]
MlTR-il PM 4.3.3.3 Authorization for Reentry.
ANSWER (B.12) a REFERENCE (B.12) j MITR-Il PM $ 4.4, p 1 of 8 and PM $ 4.7.2 p.1 of 15.
l ANSWER (B.13) e REFERENCE (B.13)
MITR PM @ 1.9 p.1 of 2 1
ANSWER (B.14) b l
5 REFERENCE (B.14)
MITR PM 2.3 Step (11) on page 2 of 7.
ANSWER (B.15) e REFERENCE (B.15)
MITR-II, PM 1.15 3, pg.1 of 5 ANSWER (B.16) b REFERENCE (B.16)
MITR-il Training Program Sample Question C.5, Also PM 4.4.4 and RPO notes (Note: RPO notes not provided to NRC examiner.)
4 4
4
I Section C. Plant and Radiation Monitorina Systems Pcge 23 ANSWER (C.01) c, d REFERENCE (C.01)
MITR-Il Reactor Systems Manual, S 5.3.1, p 5.5 ANSWER (C.02) d REFERENCE (C.02)
MITR-Il Reactor Systems Manual Table 8-88, p. 8.34 ANSWER (C.03) c REFERENCE (C.03)
MITR-il Reactor Systems Manual 9 2.4, p. 2.7 ANSWER (C.04)
DELETED i
d REFERENCE (C.04)
MITR-Il Reactor Systems Manual,9 9.5, p.17 1
ANSWER (C.05) d REFERENCE (C.05)
MITR-Il Reactor Systems Manual 9 5.6.3, p. 5.9.
ANSWER (C.06) b REFERENCE (C.06)
MITR-il, Reactor Systems Manual, @ 9.2.1, p,9.4
)
ANSWER (C.07) d REFERENCE (C.07)
MITR-il, Reactor Systems Manual, S 8.6.2, p. 8-27.
ANSWER (C.08) d REFERENCE (C.08)
MITR-II, Reactor System Manual, Chapter 4, p. 4.5, first paragraph.
ANSWER (C.09)
O REFERENCE (C.09)
MITR-il, Reactor System Manual g 7.4.1, p,7-6.
ANSWER (C.10)
DELETED d
REFERENCE (C.10)
MITR-il Reactor Systems Manual, S 8.5 p. 8.24.
i
l St.ction C. Plant and Radiation Monitorina Systems P:ga 24 I
t 1
, Section C. Plant and Radiation Monitorina Systems PCge 25 ANSWER (C.11)
)
d REFERENCE (C.11)
MITR-il, Reactor Systems Manual Figure 2.8, p. 2.22.
l ANSWER (C.12) 1 d
REFERENCE (C.12)
MITR il Reactor Systems Manual, 2.6, pp.2.9 & 2.10.
ANSWER (C.13) b REFERENCE (C.13)
MITR-Il Reactor Systems Manual 5 5.1, p. 5.1 ANSWER (C.14) b, c REFERENCE (C.14)
MITR-Il Reactor Systems Manual, S 7.2 and 7.2.1, pp. 7-1 through 7-3.
ANSWER (C.15) a REFERENCE (C.15)
MITR-II, Training Program Sample Questions $ C question 2, also Reactor Systems Manual 6 7.4.2.
l ANSWER (C.16) d REFERENCE (C.16)
MITR-Il Training Program Sample Question C.25, also AOP, PM 5.0 ANSWER (C.17) a REFERENCE (C.17)
MITR-il Training Program Sample Question C.24, also Reactor Systems Manual 99 6.4.1 & 6.4.2.
_~
Section A Reactor Theorv. Thermo. & Fac. Ooeratina Characteristics P gs 26
, s 1
I
~
A.01 b
A.02 a A.03 a A.04 d A.05 b i
A.06 b DELETED A.07 c DELETED t
A.08 d A.09 d A.10 a l
A.11 d
l l
l A.12 b i
A.13 b l
A.14 e A.15 c, d l
A.16 b DELETED A.17 b l
i A.18 d A.19 a i
A.20 d l
l 3
1
, Section B: Normal /Emeroency Procedures & Rad Con Piga 27 I
I i
B.01 c
B.02 c B.03a 2 b2 l
c3 l
d3 B.04a 1 DELETED b1 c2 d3 B.05 c B.06a 1 b2 e2 d3 e5 f 5 B.07 c, d B.08 c B.09 a B.10 b B.11 c
B.12 a B.13 a B.14 b B.15 a B.16 b l
.. _ - =. _. -. -.
l Section C Plant and Radiation Monitorina Systems P!ga 28 C.01 c, d C.02 d C.03 c C.04 d DELETED C.05 d C.06 b l
l' C.07 d l
C.08 d l
C.09 a C.10 d DELETED C.11 d C.12 d l
l C.13 b C.14 b, c C.15 a l
C.16 d l
C.17 a l
l l
l l.,
A. RX THEORY. THERMO & FAC OP CHARS p:ga1 j
ANSWER SHEET Multiple Choice (Circle or X your choice) j If you change your answer, write your selection in the blank.
001 a bcd 4
002 a b c d j
003 a bcd__
004 a bcd 1
005 a b c d I
006 a b c d 4
007 a bcd 008 a bcd 009 a bcd 010 a bcd 1
011 a bcd 012 a bcd 013 a bcd 014 a bcd 015 a bcd i
016 a b c d 017 a b c d 4
1 018 a bcd l
019 a b c d 020 a b c d
("*" END OF CATEGORY A *"**)
I
B. NORMAUEMERG PROCEDURES & RAD CON P ga 2 ANSWER SHEET 001 abcd 002 a b c d 003 a 1234 b
1234 c
1234 d
1234 l
004 a 123 l
l b
123 l
c 123 l
d 123 l
005 a b c d 006 a 12345 l
b 12345 c
12345 d
12345 e
12345 f
12345 007 a b c d 008 a bcd 009 a b c d 010 a b c d 011 abcd 012 a b c d 013 a bcd 014 a b c d 015 a b c d 016 a bcd I
("*" END OF CATEGORY B *"")
l l
o C. PLANT AND RAD MONITORING SYSTEMS P:ga 3 ANSWER SHEET 001 abcd 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 bcd 008 a b c d 009 a b c d 010 a bcd 011 abcd 012 a bcd 013 a bcd i
014 a b c d 015 a bcd 016 a b c d 017 a bcd
(**" END OF CATEGORY C "***)
(********** END OF EXAMINATION "*****"*)