ML20012A337
| ML20012A337 | |
| Person / Time | |
|---|---|
| Site: | Neely Research Reactor |
| Issue date: | 02/26/1990 |
| From: | Baldwin R, Casto C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20012A334 | List: |
| References | |
| 50-160-OL-90-01, 50-160-OL-90-1, NUDOCS 9003090270 | |
| Download: ML20012A337 (56) | |
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i ENCLOSURE 1 L?
EXAMINATION REPORT 160/0L-90-01 l'
Facility Licensee:
Georgia Institute of Technology Neely Nuclear Research Center 900 Atlantic Drive, N. W.
Atlanta. Georgia 30332-0425' Facility Name:
Georcia Institute of Technology Research Reactor (GTRR)
Facility Docket No.:
50-160 Written examinations and operating tests were administered at the Neely Nuclear Research Center, Georcia Institute of Technoloay Research Reactor (GTRR),
located within Georgia Institute of Technoloay Atlanta, Georgia.
Chief Examiner:
/
- A U^#"
"b Richard 5. Baldwin Date Stoned Operator Licensing Section 2 Divisio of Reactor Safety
' Approved By:
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<w[u-4D 1/M/90 Cha'rles A. Casto Chief Datt Signed Operator Licensing Section~2 Division of Reactor Safety
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1.
Sumary:
Examinations were held on January 23-24, 1990.
Written: examinations and operating tests were administered to one Reactor Operator (RO) and one Senior Reactor Operator (SRO), 0 of 1 R0 passed. 1 of 1 SRO passed.
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REPORT DETAILS j
1.
Examiners:
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- R. Baldwin, NRC B. Holbrook. NRC
- Chief Examiner j
2.
Facility Personnel at Exit Meetino:
- R. A. Karam. Director:- Neely Nuclear Research Center
- B. K. Revsin. Associate Director - Neely Nuclear Research Center l
- Attended Exit Meeting l
3.
Exit Meetino:
f At the conclusion of the written examination, the examiners provided R. A. Karam with a copy of the written examination and an>wer key for
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review.
At the conclusion 'of the site visit, the Chie' Examiner met with representatives of GTRR/hNRC staff to discuss the results of the examination.
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The written examination under went a pre-review.
Several changes were made to the examination as a result of this review.
It is important that these pre-reviews be conducted in a very detailed manner in order to provide the technical expertise necessary ~ so as not to have to delete questions after a post-review has taken place.
I It was pointed out to Dr. Karam that it is imperative to have the license
-applications two weeks prior to the examination date in order to facilitate the request for waivers if necessary.
The NRC would like to have DRAFT applications 30 days prior to the examination in order to-prevent a candidate from not being able to sit for an examination due to an application discrepancy.
The following ceneric weaknesses were noted during the oral examinations and presented to GTRR/NRRC manaaement:
a.
'There was a reluctance on behalf of the candidates to use plant operating procedures during the walkthough discussion.
It was also noted when the procedures were used; it did not appear that the candidates were familiar with those procedures. On several occasions it was noted that the candidates could not find certain procedures when asked, t
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b.
All Piping and Instrument diagrams pertinent to reactor operation were not available to the operators outside of the control room.
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The following industrial safety concerns were noted by the examination team and presented to GTRR/NRRC manaoement:
a.
Fire extinouishers throughout the facility were not secure and could easily be knocked over potentially causing a missile hazard.
One fire extinguisher outside of the control room was not calibrated since August 1989.
b.
The High Radiation sign above the Biomedical Facility was held up by tape and was noted on the floor during the examination.
It was pointed out that there was a potential for an unauthorized person i
to attach the city water connection to the ECCS fill connection without I
anyone knowing.
It is recommended that this concern be addressed. There is no positive control for the connecting piping for this last resort fill of the ECCS tank.
The cooperation oiven to the examination team was noted and creatly appreciated.
The licensee did not identify as proprietary.any of the material provided to or reviewed by the reviewer.
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NRC C ff10101: UC3 Only ENCLOSURE 2
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l Nuclear Regulatory Commission Operator Licensing Examination f
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This document is removed from Official Use Only category on date of examination.
NRC Official Use only
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& REAC20R OPERA'ICR LICENSE pTICE SENIOR REGION 2
FACILITY:
Georgia Inst. Tech.
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REACTOR TYPE:
TEST DATE ADMINSTERED:
90/01/23 CAN.i1DATE:
. INSTRUCTIONS TO CANDIDATE:
L-Points'for each question are indicated in parentheses after the question. 'To para this examination, you must achieve an overall grade of at leastt 70%.',
Ex mination papers will be picked tthree hours (3) after the examination starts.:
CATECORY
% OF NUMBER VALUE-TOTAL CORRECT CATEGORY
~
on'/tsiss 18.50 29r&+
3*3' A.
PRINCIPLES OF REACTOR OPERATION
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ba ' r+hs 22.50
-36r29 34.F F B.
FEATURES OF FACILITY DESIGN 40 y'trhs GD '/*'Iss
' H rOO 3 re'7 29 06 31.t r C.
GENERAL OPERATING CHARACTERISTICS g5/vi M os OVERALL CORRECT OVERALL All work done on this examination is my own.
I have neither given nor received aid, i
Candidate's Signature 1'
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NAME
-J PAGE 1 i
es i
i GEORGIA INSTITUTE OF TECHNOLOGY EXAMINATION ANSWER SHEET A.l A
B C
D
'.A.2 A
B C
D
' A43 A
B C
D
A.4' A
B C
D i" A.5 A
B C-D
-A.6 A
B C
D f
A.7 A
B C
D
{
A.8 A.9:
A B
C D
A.10 A
B'C D
'A.11 A
B C -D A.12 A
B C
D l
A.13 a.
A B
C
-D b.
A B
C D
A.14 A
B C
D A.15 a.
12 3.
4 b..
1 2
3 4
c.
1 2
3 4
I~A.16 A
B C
D
-A.17'1'.
A B
C D
E F
2.
A B
C D
E F
3.
A' B
C D
E F
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4.
A B
C D
E F
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GEORGIA INSTITUTE OF TECHNO1DGY EXAMINJA ON l
ANSWER SHEET
. Bel 1.
i-2.
!'B.2 A
B C
D B.3 A
B C
D 6.
i
' B. 4 A
B C
D B,5 A
B C
D l' 'B.6 A
B C
D B7 a.
b.
i c.
B.8 A
B C
D B.9 A
B C
D B.10 A
B C
D
! B.11 A
B C
D i
B.12 A
B C
D l
B.13 A
B C
D B.14 A
B C
D B.15 A
B C
D B.16 A
B.C D
B.17 a.
b.
c.
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'e GEORGIA INSTITUTE OF TECHNOLOGY EXAMINATION 4
ANSWER SHEET J
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- B.18 A
B C-D B.19
.A B
C D
B.20 1.
A B
C D
E F'
2.
A-B C
D E
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B' C
D l
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B C
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-ANSWER SHEET
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'C.2 U A=B: C D
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C D
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A B.
C D-
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b.
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A. B C.
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-C.8 A
B C-D
'C.9 A
B C.D C.10 A.B
.C D
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A B-C D
.C.12.
AB C
D C.13-
- C.14 '-
'A B
C D
'C.15 A
B C
D C.16' A
B C'
D C.17 A'
B C-D iC.18 A'
B C
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-C.19 A'
B C
D-C.20 AB C
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g duNingj th9-cdminictration. o thic oxzmin tion tho follonng rulso apply Ll.Lbbeating on-the examination'means an automatic _ denial.of your application 1Cnd could result in more severe penalties.
,- 24 Af' - the examination has been completed, you must sign the statement on
- th e ver sheet indicating,that the work is your own and you have not
'rs 'el ved or given assistance in completing the examination.
This must be done after-you complete the examination.
3..R:stroom 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 avo, even the (2ppearance or possibility-of cheating.
- 4. Uhe 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.
I6(. Fill in the date on the cover sheet of the examination (if necessary).
- 7. You may write your answers on the examination question page or on a Osparate sheet of-paper.
USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON
~THE BACK SIDE OF THE PAGE.
- 8. IfLyou write your answers on the examination question page and you need more space to answer >a specific question, use a separate sheet of the
.pnper provided and' insert it directly after the specific question.- DO'NOT WRITE ON THE'BACK SIDE OF THE EXAMINATION QUESTION PAGE.
- 9. Print your nameLin the upper right-hand corner of the first page of answer
- cheets.whether_you use the examination question pages or separate sheets of' paper.. Initial.each of the following answer pages.
- 10. B3 fore you turn in your examination, consecutively number each answer cheet, including any additional pages inserted when writing your answers on-the. examination question page.
111..If you are'using separate sheets, number each answer.and skip at least 3 L
lines between' answers to allow space for grading.
'12. Write "Last.Page" on the last answer sheet.
113.-'Use abbreviations only if they are commonly used in facility literature.
-Avoid-using symbols such as < or > signs to avoid a simple transposition crror resulting in an incorrect answer.
Write it out.
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NOTcnindicStienofthh0pthofon:wsrrcquired.f}
115.,Show.all calculations, methods, or assumptions used to obtain an answer.
16.. 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.
l17. Proportional grading will be applied.
Any additional wrong information
.that is provided may count against you.
For example,. if-a question is worth one point and asks for four responses, each of which is worth 0.25 points, and you give five responses, each of your responses will be worth 0.20 points.
If one of your five responses is incorrect, 0.20 will be dsducted and your total credit for that question will be 0.80 instead of 1.00 even though you got the four correct-answers.
18.~If the intent of a question is unclear, ask questions of the examiner only.
- 19. When turning in your examination, assemble the completed examination with-cxamination questions, examination aids and answer sheets.
In addition, turn in all scrap paper.
i-20. To pass the examination, you must achieve an overall grade of 80% or greater.
121. There.is a time limit of~(4 1/2) hours for completion of the examination.
L (or some other time if less than the full examination is taken.)
, 22. When you are done and have turned in your examination, leave the examin-etion aren 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 l
'ravoked.
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' QUESTION:-001 (1.00)_
l JWhichLone..of the following Critical Heat Flux ratios will produce j
tho Maximum heat' transfer?
1 a.: ~ greater than 1.0 b.
.less than 1.0' c.
1.0 d.
0.0 s
' QUESTION:.002 (l'. 00 )
Which one of the following'is most affected by reactor size?
4 a..
thermal utilization factor b.
fast fission factor
.c.
resonance escape probability ld; non-leakage. probability I
I QUESTION: 003 (1. 00)
Which'one.ofithe following.is the correct reason that delayed neutrons cnhnnee:contr'ol of.the reactor?
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a.
More delayed neutrons are produced than prompt neutrons
'b.
Delayed neutrons increase the average neutron generation time l
c.
Delayed neutrons take longer to thermalize than prompt neutrons d.
Delayed neutrons are born at higher energies than prompt neutrons i
(*****
CATEGORY A CONTINUED ON NEXT PAGE *****)
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. QUESTION: 004 (1. 00 )-
Which of of the following is the reason for the -80 second period cftOr a reactor trip?
a.
This is equal to-the decay constant of the longest-lived group of delayed neutrons b.
The ability of U-235 to fission with source neutrons c.
The amount of negative reactivity added on a trip is greater-than the shutdown margin d..
The Doppler effect adding positive reactivity as fuel temperature decreases after a reactor trip tQUESTION: 005 (1.00)
J Enough reactivity is added to a shutdown reactor to double the count rate.
If this same amount of reactivity is again added to-the reactor, then the recctor will be a.
subcritical j
b.
critical l
c.-
super critical d.
prompt critical I
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CATEGORY A CONTINUED ON NEXT PAGE *****)
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(QUESTION:: 006.-(1.00);
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~ Which1one of the following factors of the six factor formula is most 1
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(cccily. varied by the reactor operator?
a.
thermal utilization factor b..
reproduction factor c.
. fast fission factor id.-
fast non-leakage factor QUESTION:'007 (1.00)
- During a power escalation on the log N channel it takes 35 seconds for I
reactor, power to double.
Which one of the following is the stable
'rcactor period.that would cause this rate of change?
1'
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a.
17 seco'nds l-b.
35 seconds l
c.
! 50 seconds-
'd.
70 seconds L QUESTION: 008 (1.00) l
-Fill in the' blanks Xanon-135-is removed from the core by
.and 5,
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CATEGORY A CONTINUED ON NEXT PAGE *****)
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-QUESTION:-009- (1.00)
Which.one of the following statements concerning the reactivity values
'cf.cquilibrium (at power) Xenon and peak (after shutdown) Xenon is j
s c rrect?
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a.
Equilibrium' xenon is INDEPENDENT of power level; peak xenon J
is INDEPENDENT'of power level i
b.
Equilibrium. xenon is INDEPENDENT of power level; peak xenon is DEPENDENT.on power level
. c.
Equilibrium xenon is DEPENDENT on power level; peak xenon is INDEPENDENT of power level d.
Equilibrium xenon is DEPENDENT on power level; peak xenon is 1
DEPENDENT on power level L
QUESTION: 010 (1.00)
Which.one of the following conditions is most appropriate for~
~cnnouncing that the reactor is critical?
i No control rod motion, stable zero Start Up Rate, stable source count l
a.
L rate b.
No control rod motion, stable positive Start Up Rate, increasing source range count rate l-c.
.No control rod motion, stable zer6 Start Up Rate, increasing source range count rate
(
d.
. Control rod motion, stable positive Start Up Rate, increasing source.
range count rate r
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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g QUESTION:-011 (1. 0 0).
j Which one of the following describes the beta decay of a nuclide?
1 1
a.
. Atomic Mass # decreases by 1, number of protons remains constant b.
-Atomic Mass;# remains the same, number of protons' increase by 1 c.
Atomic Mass # remains the same, number of protons remains constant d.
Atomic Mass # decreases by 1, number of protons decreases by 1
- QUESTION: 012
~(1.00)
Which'one of the following is the Maximum fuel center line temperature undsr-normal operating conditions?
a.
205 Deg. F
-b, 207 Deg. F c.
209 Deg. F d.
211 Deg. F 1
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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' QUESTION: 013 (1.00) 1 L
.Th3 attached graph Figure 1,frepresentsLthe Neutron Instrumentation response-iduring a start up.
t M2tch the points represented =on the graph listed under COLUMN A with the
. correct type of coefficient that could cause power to behave as indicated:
a Column A
Column B a.
A a.
Moderator Temperature-Cofficient b.
B b.
Void Coefficient c.
Pressure Coefficient d.
Doppler Coefff.cient
-QUESTION: 014- (1.00)
Which one of the following is NOT true concerning rod worth?
a.
Over core life rod worth will decrease where flux increases..
I
.b.
Rod-worth will increase as moderator. temperature increases.
c.
High concentrations of xenon will cause a noticeable change in integral rod worth, d.
Differential rod worth will decrease when~ inserting adjacent rods to the same height.
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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u QUESTION::015 (1. 50).
-LTh7 attached-graph, Figure'2, represents _the effect?upon cladding ~
t:mperature^be different types--of boiling.
F M;tch the areas-represented on the graph listed under COLUMN A e
s with the correct types of boiling listed in COLUMN B.
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COLUMN A-COLUMN B a.
~ Area A-B 1.
Radiant boiling b.
Area B-C 2.
Transition boiling c.
Area C-D 3.
Nucleate boiling l
4.
Film boiling
- QUESTION: '016 (1.00)'
Which oneiof the following statements concerning Samarium reactivity offects is correct?
a.
'The EQUILIBRIUM (at power) value of Samarium is DEPENDENT upon power level.
The peak value of Samarium following a shutdown is DEPENDENT upon power level prior to_ shutdown.
b.
The EQUILIBRIUM (at power) value ofESamarium is DEPENDENT upon power level.
The' peak value of Samarium following a shutdown is INDEPENDENT of power level prior to shutdown.
~
"c.
The EQUILIBRIUM (at power) value of Samarium is INDEPENDENT of power level.
The peak value of Samarium following a a
shutdown is DEPENDENT upon power level prior to shutdown.
.d.
The EQUILIBRIUM (at power) value of Samarium is INDEPENDENT of power level.
The peak value of Samarium following~a shutdown ~is INDEPENDENT.of power _ level prior to shutdown, i
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CATEGORY A CONTINUED ON NEXT PAGE *****)
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a QUESTION:: 017 =(2.00).
-1
~ Match'each' term listed below with.its corresponding definition.
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TERMS:
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Fast' Fission Factor s
2.
Resonance Escape Probability.
3.
Reproduction Factor s
4.
Thermal Utilization Factor DEFINITIONS:
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The number of neutrons born from fission by thermal neutrons The number of thermal neutrons absorbed in fuel b..
The number of thermal neutrons absorbed in fuel-The number.of. thermal neutrons absorbed in all! materials c,
- The~ number of neutrons that do not leak out while thermal The number of neutrons that escape resonance capture while slowing down I:
-d.
.The' number'of neutrons that escape resonance capture while slowina down a
1The number of neutrons that do not leak out while fast i
- 10. - The number of neutrons'that do not leak ou't'while fast
' Net number of neutrons born from fission by neutron of all energies 1The net number of neutrons' born from fission by neutrons of all energies lf.
The' number,of neutrons born from. fission by thermal neutrons d
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END OF CATEGORY A *****)
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- QUESTION:: 001 (1. 00)
Lict TWO primary-(Direct) indications the operator would have to verify that
..tha shim-safety blades have scrammed.
Note:
DO NOT LIST SECONDARY EFFECTS
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QUESTION: 002 (1.00)-
Liquid Waste is being discharged from a holdup tank.
Which one of the following is correct in regards to stopping the discharge for analysis?
a.
Stop the' discharge when the tank is between 1/4 to 1/2 discharged.
b.
.Stop the discharge after the tank is greater than 3/4 discharged.
c.
Stop.the discharge before the tank is 1/4 diccharged.
d.
Stop the discharge when the tank is between 1/2 and 3/4 discharged.
QUESTION: 003 (1.00)
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Which one of the-following conditions would require containment integrity to bs. maintained?
-a.
The reactor was operated at 2 MW for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and has been shut down
~for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
Irradiated fuel is being moved in a fuel transfer cask from the containment building.
o c.
Maintenance is being. conducted on the inner containment Air lock door.
d.
.The reflector drain shutdown capability was determined to be less
-than 2.75% delta k/k.
(*****
CATEGORY B CONTINUED ON NEXT PAGE *****)
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QUESTION: _004 (1.00)
An cccident has occurred and-radioactive material is loosed from.its
.c:ntainer.
According to.9303, " Guidelines for Handling Radioactive Spills", section
"-5.2.1,
" Managing Small spills".
Which one of the following is the correct Cp3rator actions?
a.
Isolate the spill, notify the Director of NNRC, begin contamination immediately.
b.
Place barriers around the spill, survey area, evacuate the area and I
call NNRC.
c.
Direct personnel traffic away from the spill, call the office of Radiation Safety (ORS) and unless otherwise instructed by ORS do nothing until personnel from ORS arrive, d.
Evacuate the areas, notify the Nuclear Regulatory Commission and await further instructions.
. QUESTION: 005 (1.00) r l
During an emergency shutdown the SCRAM and SHUTDOWN buttons were depressed and FLUX'is NOT decreasing.-
In accordance with Procedure 5000, " Objectives and
. Coda for Emerger.cy Procedures", which one of the following is the correct
?
Opsrator Action?
l a.
Press the manual ECCS initiation button and verify reactor isolation valve closed and LID-T stabilized.
b.
Insert the regulating rod
-c.
Press the OPEN-button for the drain valves and the OPEN button for the clutch magnet circuits.
d.
Dispatch field operator to process room to verify KANNE. chamber reading.
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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- QUESTION: 006-(l'. 00) '
TWh0n changing: power in' the Automatic mode, which one of the following is the (c rrect~ maximum deviation on the servo deviation meter?
a.
3%.
1b.
5%
c.-
7%.
d.
9%
-QUESTION: 007-(1.50)
For the;following, LIST the maximum 10 CFR 20 limits of radiation dose lpprmissible per Calendar Quarter.
.a.
Active blood forming organs.
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b.
Hands c.
Skin'of the whole body
- [ QUESTION: 008 (1.00)
/
" Response to Heavy Water Leakage in
/( LIn(accordance,withiProcedure 6020, Containment Building", which one of the following is correct in regards to 7
l water addition?!
l a.
If; water addition;is' required,
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. pool.
the primary source will be from the p
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[.
.b.-
WaterLaddition should be initiated when the reactor tank level drops below the 56 inch level.
c.-
. Water addition should be initiated.from the City Water supply when Reactor tank level-drops below the 66 cinch level.
I E d..
Water addition should be-initiated only as directed by the Emergency.
Director or NNRC staff.
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CATEGORY B-CONTINUED ON NEXT PAGE *****)
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r QUESTION:'009 (1.00)
'1 C ncerning Personnel Survey Frequency and. Personal Frisking, which'one of the following. statements is correct?
]
a.-
When performing a personal frisk, initially set - or ensure that the frisker unit is set - on its highest scale and fastest response setting.
b.
If an increase in " click rate" is heard, return the probe to the area.of increased click rate and hold the probe over the suspected area for approximately 4 to 5 seconds for confirmation.
s c.
If increased " click rate" is confirmed and/or increased over previous background levels - greater than 1000 cpm over normal background - immediately leave the reactor control zone, proceed to a clean area and promptly notify HP.
d.
When exiting a potentially contaminated area, personnel shall frisk-to a level which is specified on an applicable RWP.
If not specified on the RWP, at a minimum, frisk head, hands, feet, arms,_
legs, back and torso, f
p..
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CATEGORY B CONTINUED ON NEXT PAGE *****)
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, QUESTION: 010 (1.00)
'During the removal of an irradiated fuel element, the element, d:e to a SOchanical failure of the transfer coffin, falls out of.the coffin onto the containment building floor.
lIn cccordance with GTRR/NNRC rules guidelines, the operator (s) conducting the fusi handling operations, should do which one of the following.
a.
Immediately run away from the exposed fuel element.
Immediately evacuate'the containment area and request others to do the same.
Promptly notify NNRC management.
b.
Immediately proceed to an area within containment which affords the greatest amount of shielding.
Immediately request others in the area to do the same.
Promptly notify NNRC management.
c.-
Immediately lie down if atop the reactor (this will afford the greatest amount of shielding).
Attempt to retrieve the element (Minimize exposure time).
Move the element to an area which would provide sufficient shielding.
Promptly notify NNRC management.
d.-
Immediately cover at least the active fuel portion of the assembly with blanketing, blocks, etc...
Immediately evacuate the' containment area and request others to do the same.
Promptly notify senior NNRC management personnel.
. QUESTION:'011 (1.00)
Thn-reactor operator observes a condition or event which is NOT thoroughly
. understood cnr explained.
Which one of the following is the correct reactor oparator action?
a.
contact a Senior Reactor Operator.
b.
notify reactor supervision and Health Physics.
c.
shutdown the reactor.
d.
notify a member of NNRC management.
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
i r,
g.
sj-i t
J O?
O JQUESTION: L012
( 1. 0 0 ) --
w
,i Which on'e of thelfollowing' indicates the allowed time the observing operator L
may-leave.the-Containment building;and NOT be relieved by a licensed operator?
a.
30Lminutes b.-
'26 minutos
'c.
22 minutes
~'d.- l minutes i
IQUESTION: J013 (1.00)
During Normal' Full Power = Operation, Annunciator " LOW H2O FLOW - DELAY SCRAM" alarms.: The,Immediate Action for operators states to check the water flow:on r corder FRA-H11for an indication of a TRUE-low flow: condition.- Which one.of L
- ths following constitutes low flow conditions?
i
- a. --
50 %'of normal or-less
- b..
- 60.%'of normal or less s
c.-
~70 % of normal or-less c
L d.-
80 %.of' normal or less py a
L
\\?
r' l
L.
l'
-t 1
- p :-
t
+
(*****
CATEGORY B CONTINUED ON NEXT PAGE *****)
l g
g 1
QUESTION: 014-(1.00)
Which one of the following is correct in regards to making facility. changes th:t-have been: approved on the Experiment Approval and Report Form?
a.
May select an alternate facility other than what is specified on the Experiment Approval and Report Form, but may not change the facility from a Vertical port to a horizontal port, b.
May select an alternate facility NOT specified on the Experiment.
Approval and Report Form, provided a correct Experiment Approval and report form is completed at the conclusion'of the experiment.
i c.'
May not-select'an alternate facility other than what is specified on the Experiment Approval and Report form.
d.-
May select on alternate facility not specified provided reactor power level and maximum duration of the experiment is not exceeded.
-QUESTION: 015 (1.00)
Which one of~the following Experiment Categories requires the opproval of the Nuclear. Safeguards committee?
a.
1 b.
2 l
L c.
4 1
i d.
5 1
l-I
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
4 1
J "QUESTIONr 016 (1.00)
While removing a sample from a Vertical Experiment port the operator obtains a l
365-rem /hr reading at 3 feet above the hole, the sample was below the lead cov0r plate.
Which one of the following is the correct operator action?
Proceed with caution and observe the dose rate meter for significant a.
increases.
b.
Lower the-sample back into the hole for further decay, c.
Carefully remove the sample and promptly place it is a shielded container, d.
Ensure'HP monitoring of the area and proceed with' caution.
[
- j. QUESTION: 017 (1.00) 1 Complete the following for the procedural limits for each of the following-
.during.a normal startup:
a.
Degrees between the highest and lowest shim control blade, b.
second minimum reactor period by procedure.
c.
regulating rod position between inches and inches.
l I
QUESTION: 018 (1.00)
LWhich-one of the following alarm conditions is an interlock that prevents a L
rsactor: startup?
a.
Emergency-Cooling tank low.
1 b.
D20 leak.
l.
l c.
Regulating Rod low limit.
d.
Outside Automatic Controller servo range.
i l
l l
L
(*****
CATEGORY B CONTINUED ON NEXT PAGE *****)
Y b^'
u er s1 O
o-1
. '.1
{ QUESTION: ~ 019 (1.00):
,1 lAcc:rding/to procedure 6100, " Emergency Notification",:which one.of.the J
"following~isithe correct definition of Immediately?
j a.
within 5 minutes after declaring.an emergency b.
~ within 10' minutes after' declaring an emergency q
c..-
within 15 minutes'after declaring an emergency d..
within 20 minutes after declaring an. emergency-QUESTION:' 020- - (1. 00) -
L Mutch each parameter listed below with its Technical Specification limit.-
1 Parameters Technical Specification Limits
.t 1.
. Shutdown margin a.
0.01 delta k/k-b.
0.10 delta k/k I?
2.
Excess Reactivity / Core c.
1.90 delta k/k limit d.
9.11 delta k/k-V 11.90[ delta-k/k i
e.
V.
' QUESTION: 021;'(1.00)
- -Which one of the following is the Maximum allowable Moderator Temperature?-
y.
- a..
135--degrees F l
b.
137' degrees F
'c;
- 139 degrees F
,.d. :
-141' degrees F
-(*****
CATEGORY B CONTINUED ON NEXT PAGE *****)
-i y.'
1 tl g.
u-s-
a i
((QbESTION:
l 022'-
(1; 00) 4, 35-
~
i s4;Th3;NNRC building,has been Evacuated due to a. Criticality alarm.. Which-one of.
1 th0!following is the correct assembly: area location for personnel evacuating.
)
4 7
lth31NNRC building?
a.-
Georgia Tech police ~ headquarters.
4!
b.-.
fGeorgia Tech-Administration Building ac.
' Southwest of. cooling tower d..
Northwest corner.of the parking lot i
4 r-i L
/
l' l -~ 's l'
j..
'i L
1, L
L 4
O
(***** END OF CATEGORY B *****)
k.
m Q
Q I
QUESTION: 001 (1.00)
Which one of the following~ methods is used to Help maintain a constant water 1cv01 in;the Reactor vessel during normal operations?
a '.
Throttle the Main Circulating Pump discharge valve.
b.
Constant make up from the 300 gal. D20 tank T-D2, via gravity drain.
c.
Throttle the reactor dump line valve discharge to the D20 storage tank.
d.
Main circulating pump provided with additional water supply from the reactor return and purification pump discharge.
QUESTION: 002 (1.00)
Which one of the following is the correct method used to obtain actual reactor Magawatt Thermal power level when operating at greater than 1 megawatt?
a.
Observe the megawatt power indicator.,
b.
Calculate the heat removal rate of the primary and auxiliary coolant system.
c.
Calculate and average the fuel element temperatures.
Ed.
Average the currents from the linear power level channels.
- QUESTION: 003 (1.00)
It has been determined the containment building Truck door is leaking.
Which ons of the following'is the most probable cause?
a.
Damaged Teflon seal b.-
Damaged Neoprene gasket c.
Damaged Inflatable gasket d.
Damaged Liquid seal ih l
(*****
CATEGORY C CONTINUED ON NEXT PAGE *****)
l
b Y h Q.
O
,, QUESTION: 004 ' (1. 00).
Which:one of the following'is the correct flow path for'a Hot Cell Ventilation cyctem?-
.a..
Roughing' filters, common plenum, absolute filters, blower b.
Blower, roughing filters, absolute filters, common plenum-c.
' Absolute filters, common plenum, blower, roughing filters L
t d.
Common plenum, blower, roughing filters, absolute filters
. QUESTION:-005.(1.00)
Which one of the following is correct in regards to the Overpressure relief I
cyctem?
L a.
At upproximately 1 psig a graphite diaphragm will rupture relieving pressure to the expansion chamber.
L' b.
When the 1500 cubic foot expansion chamber pressure reaches 1 psig a.
L graphite diaphragm will rupture relieving pressure.
I c.
Pressure is relieved by a 6 inch pipe connection to the upper part of the reactor tank which relieves to the reactor ventilation system
- d. :
At approximately 1 psig in the expansion chamber a graphite diaphrag.
- p. '
- will. rupture relieving pressure to the Reactor Ventilation system.
1 1
l QUESTION: 006 (1.00)
A," Cutie pie"-instrument is used to survey a beta-gamma radiation-field.
The
~
following readings are recorded:
" Cutie. pie" (closed window) 2.5 roentgens /hr
=
" Cutie pie" (open window )
3.1 roentgens /hr-
=
9.a. '
The " beta" dose rate in the area is R/hr.
b..:
The " beta-gamma dose rate in the area is R/hr.
(*****
CATEGORY C CONTINUED ON NEXT PAGE *****)
o 8
g
'~
gc -
-0;
- O-1 O
. N-
- QUESTION: 007 ~ = ( 1". 0 0 ) -
=
1
'Whichlone oflthe"following.is used'to maintain'a water vapor free' atmosphere; I
/tbove the moderator?
i la.-
Argon blanket b'. -
Hydrogen' blanket
' c. :.-
_ Nitrogen blanket
[,
Ld.
Helium blanket H
-QUESTION: 008-. (1. 00) sWhich1one of the following Nuclear instrument channels'is the special i
cinctrument channel that will permit the cross checking required in the low p
iflux3 environment of a subcritical-reactor?
i
- a.
. Count rate meter channels L
'b.-
' Micro-micro Ammeter channel
- c '.
B10' proportional detection channels d..
'Tsog-N and. period amplifier channels l
L i
v
- l. QUESTION:'009/ (l.00)
I l
During Automatic Reactor power. control, theiregulating--rod automaticallly.
zwitched to' Manual control.
Which one of.the following caused the switch to=
Manual?
a.
-The reactivity' addition was greater-than 0.01% per second.
p b.
There.vas greater than 10% between the power setpoint and actual m
reactor power.
Ec.
.The regulating. rod speed was greater than 0.2 inches per second.
l.
d..
Reactor power is equal to 5 MW.
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
1-o o
.j r.
-e
' QUESTION: 010 (1.00)
Which'one of the following is correct in regards to the STANDBY D20 3
Circulating-pump?
a.
Must be run in parallel with the main D2O pump to-increase power to SMW.
b.
Is an: emergency system powered from an independent power supply to allow forced 1 flow during a loss of normal power.
c.
Is to be used only below 50 KW to minimize pump heat addition to the moderator.
d.-
Is to be used in the event of the main D20 pump fails and then only for reduced power operations.
QUESTION: 011 (1.00)
Which one of the_following Nuclear Instrument Channels uses an Uncompensated IonLChamber with a range of 1 KW to SMW7 a.
Log-N and period amp.
b.
Power level. trip amp.
c.
Micro-Micro ammeter.
d.
Count rate meter channel.
QUESTION: 012 (1.00)
Which one of the following conditions would initiate emergency cooling flow
.from the 300 gallon D20 tank?
.a.
Secondary water. system high temperature.
b.
Primary D20 system high temperature, c.
High H2O coolant activity.
d.
Loss of electrical power.
(*****
CATEGORY C CONTINUED ON NEXT PAGE *****)
m;*
e.
H k
.O O
u h-1 1
. 1013; (1.00).
(1 QUESTION N
Fill'in the blanks.
'In the event of-'a tube leak in the primary to secondary heat exchanger with-
'both' systems ~ operating, the. higher press in the-system will-1COktinto the system.
i
}\\^.
QUESTION:'014- (1. 0 0) -
cr'
- Tho top 28 inches ~of the moderator serves as a reflector for the core tof (choose one) c LT a.
Provide additional shielding.
b.
Absorb neutrons that would otherwise leak from the core.
,3 c.
-Add excess reactivity.
d.
Reduce the thermal flux at the core boundary.
( g {h h}h j
' QUEST ON: 015
.g Accarding>to Technical Specifications whi e operation in Mode 2, which one'of thi followingi arameters is abnormal for steady state, forced convection mode of operation?
Reactor co'olant inlet ten.perature 124 degrees F.
L a.-
b.
~ Moderator lev thin 10-inches.of overflow.
c.
Reactor coolant outlet mperature 138 degrees F.
d.'
Reactor coolant flow-1650 gpm.
t i
n.
y i
s-j t..
,h'
(*****' CATEGORY C CONTINUED ON NEXT PAGE *****)
i
' ', f.
1 o
o
?i.
'1 1
-QUESTION: 016 (1.00)
Annunciator " Drain Valves Open" actuates.
Which one of the following is the zorrrect operator response?
)
-a' Initiate procedure 5000 ABLE.
-b.
Initiate a controlled reactor shutdown.
c.
Attempt to reclose the Drain Valves from the control room, d.
Dispatch the field operator to close the drain: valves locally.
' QUESTION: LO17 (1.00)
Which one of the following is correct for upon loss of power?-
a.
2 shim-safety blades and the' regulating element will immediately be inserted.
b.
2 shim-safety blades will immediately be inserted L
c.
4 shim-safety blades and the regulating element will immediately be inserted.
i d.
4 shim-safety blades will immediately be inserted.
QUESTION:'018 (1.00) 4
_ hich one of the following is-the minimum City Water pressure that would W
g l
dictate'when the spent-fuel basin water should be used for light-water' supply;
- mnks up during a loss of_ coolant accident?
a.
21 psig.
b.-
31 psig c.
41 psig ud.
51 psig 2
(*****
CATEGORY C CONTINUED ON NEXT PAGE *****)
'I'.
~
l 7
o o
L(QUESTION:;019 (1.00)
LTh3 presence of Tritium _in the secondary Coolant water indicates a moderator lOOk in a Heat Exchanger and procedure ABLE has been initiated.
Which one of tha following is correct in regards to the D20 circulation system?
a.
shutdown D20 circulation system immediately, b.
shutdown D20 circulation system after HX-D1 and HX-D2 are completely drained.
c.
shutdown D20 Circulation system directly after securing the H2O
}
~
Circulation system.
d.
do NOT shutdown D20 circulation system.
QUESTION: 020 (1. 00 )'
Which one of the following reactor safety circuits will trip both logic units and generate a " Fast" scram of all shim-safety-blades?
a.
D20. temperature 139 degrees F.
b.
Containment doors open c.
Reflector drain d.
. Reactor power 5.5 MW QUESTION: 021 (1.00)
A Channel check evaluates the difference between actual power and desired
- powar is 4%.
Which one of the following is correct for this condition?-
a.
. Power adjustment changes will normally be made after discussion with the SRO.
b.
Power adjustment changes are NOT necessary for this condition.
c.
Shutdown the Unit and notify Reactor Management, d.
Adjust power to less than 2% or shutdown the reactor.
i
(*****
END OF CATEGORY C *****)
(********** END OF EXAMINATION **********)
o (n) i
?-,,.
%J 001 (1.00)
,!, ANSWER:
c.
f
REFERENCE:
INP Ch. 11 l
l r
r P
- i..
MiANSWER:
002 (1.00) ne, o
d.
j
REFERENCE:
INP Ch. 10 t
i i
f ANSWERt 003 (1.00) b.
k
REFERENCE:
i INP 1971 i
i
' ANSWER:
004 (1.00).
a.-
i g
REFERENCE:
INP 1971 p.10-55 l
l l
l' fANSWER:
005 (1.00) 4 C.
i
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
li
~
l -.
e' tis t
-,, ~
O O
REEERENCE:
INP 1971 P. 10-19 I
l' t
i ANSWER:
006 (1.00) i a.
i k
- l.
REFERENCE:
j INP 1971 p.10-8
}
i 6.
ANSWP.Rt 007 (1.00) c.
REFERENCE INP 1971 P.36 f
I ANSWER:
008 (1. 00) l
- a. decay
~b.
neutron capture (burn up)
REFERENCE
- INP 1971 p.10-74 1
ANSWERt 009 (1.00) d.
~
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
F e
v
~,
O O
REEERENCEt INP 1971 p.10-76 ANSWER:
010 (1.00) b.
i REFERENCE INP-1971 p.12-27 ANSWER:
011 (1.00) b REFERENCEt INP 1971 P4-2,4-b ANSWERt 012- (1.00) d REFERENCE SAR p. 8 ANSWER:
013 (1.00)
A. a (Moderator temperature)
.H B. d (Doppler)
(*****
CATEGORY A CONTINUED ON NEXT PAGE *****)
1 o.
4 O
O REF,ERENCE.
J r
.INP p.12-29 Figure 12-15
- i. ANSWER:
014 (1.00)
I
REFERENCE:
INP 1971 Ch.10,12 t
ANSWER:
015 (1.50) t a..
3-b.
2-1 c.
4-
REFERENCE:
[
'INP 1971 p. 11-12 I
f LANSWER:
016 (1.00)_
l C
l
REFERENCE:
INP p.10-80 i
9 l
l.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
s
m l
1 o
9 ANSWER:
017 (2.00) 1.
f 2.
d l
- 3. a t
- 4. b i
o 1
.REFERENCEt i
4 l
-INP 1971 Ch.10, P.5
{
i L
-l l
i 1
1
]
l' t
Y e
t
(***** END OF CATEGORY A *****)
s
,e
- 9,E O
O 1
j ANSWERt 001 (1.00) j
.any of the following two at 0.5 each 1.
Shim-blade down light indication 3
2..
Dial indicator for shin-safety blades 3.
Indication of de-energized clutch
REFERENCE:
)
i l
- p. 50-52
{
I i
AN WER:
002 (1.00) d 1
REFERENCE:
T/S page 20a ANSWER:
003 (1.00) o
REFERENCE:
T/S p. 14 u.
' ANSWER:
004 (1.00) e
.REFERENCEt 9303 sect. 5.2.1
- p. 2
(*****
CATEGORY B CONTINUED ON NEXT PAGE *****)
.~
j i
' ANSWER:
005 (1.00) i C
REFERENCEt oGTRR Procedure 5000
- p. 1 II.A.1.
2 1
1
)
ANSWER:
006 (1.00) 3 REFERENCE CTRR' Procedure 2000 Reactor Operations,
- p. 3 Rev A Section B.1.c ANSWER:
007 (1.50)
O.5 each a.
1.25 rems /qtr b.
- 18.75 rems /qtr c.
7.5 rems / qtr i
REFERENCEl-10CFR20 'p.
262 1989 i
R:diation Safety Manual, July 1987, p. 13
?
ANSWER:
008 (1.00) i e
i
REFERENCE:
Procedure 6020
- p. 3 1
(*****
CATEGORY B CONTINUED ON NEXT PAGE *****)
i
-~.-
O O
. ANSWERS.
009 (1.00) b
REFERENCE:
NNRC/GTRR HP procedure 9280 l
ANSWER:
010 (1.00) a
.(
REFERENCE:
?
4
.GTRR NNRC/ Procedure 6030 I
^
ANSWER:
011 (1.00)
C
REFERENCE:
.CTRR Procedure -5000 p.2 f
I ANSWER:-
012 (1.00)
L d
REFERENCE:
1 l
CTRR' Procedure 20001
- p. 4 l
I E
1 ANSWER:
013 (1.00) o i
d t
i l'
(*****
CATEGORY B CONTINUED ON NEXT PAGE *****)
I a
o O
O.
F REF.ERENCE:
l GTRR Procedure 5023
- p. 1 Item B ANSWER:
014 (1.00) t i
c
REFERENCE:
NNRC. Procedure 3100, p. 4 of 10 i
l ANSWER:
015 (1.00) d
REFERENCE:
NNRC Procedure 3101, Rev 1
- p. 6 i
i
' ANSWER:
016 (1. 0 0) '
b.
'REFERENCEt'
.NNRC Procedure 3113 RO powe 3
l 1
l l
ANSWER:-
017* (1.00) 1:
.4'Et 0.25 each 0.
5
-b.
20 l.
c.
5, 7
i P
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
a
' [ i
,s.
O O
REFERENCE:
' Procedure 2000 p. 1 ANSWER:
018 (1.00) a.
REFERENCE s
SAR P.
72-73 i
~ ANSWER:
019' (1.00) e REFERENCE
- Procedure 6100 p.2 ANSWER:
020 (1.00)
- 1. e-(0.01' delta k/k)
- 2. O-(11.90 delta k/k)
REFERENCE:
E _T/S
- p. 9
(:
' ANSWER:
021 (1.00)
C-
REFERENCE:
l
~T/S ' p. 7
- T
(***** CATEGORY B CONTINUED ON HEXT PAGE *****)
m E
O O
i j
i i.
ANSWER:
022 (1.00)
I d
REFERENCE:
1
.NNRC procedure 6090
- p. 2 l
t' i
j' I
?
r
-i i
l.
i i
i l
l l
.(***** END OF CATEGORY B *****)
L.
l 1.
m.
6 4
'O.
4.~
O O
)
i ANSWER:
001-.(1.00)
- h. s d'(1.00) s GEFERENCE:
l SAR p. 78 l
l-i
'AN2WER:-
002- (1.00) i l-b n.
t
REFERENCE:
i GTRR procedure 2015 p.1 i
l ANSWER:
003 (1.00) l c
REFERENCE:
SAR. p. 38,39 t
' ANSWER:
004 (1.00) a-
REFERENCE:
r SAR p. 28 1
i l
ANSWER:
005 (1.00) a-t-
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
1 l.
l-t i
+r
s---
---.---a---
i O
O
REFERENCE:
SAR p. 86 section 4.4.9.6 i
ANSWER:
006 (1.00) i
'.b.
0.6 R/hr l
a.
3.1 R/hr-
REFERENCE:
i INP p. 14-36 i
ANSWER:
007 (1.00)
C,d#
l REFERENCEt SAR
.p.
42-44 ANSWER:.
008 (1.00)
\\
a..
ME i/29/?b
REFERENCE:
SAR-.P 66
+
l ANSWER:
009 (1. 00) b i
L L.
1
(*****
CATEGORY C CONTINUED ON NEXT PAGE *****)
9 e
,v e
e h.
d i
L-
REFERENCE:
l SAR
- p. 69 Item 4.4.7.3 i
t' i
)
i: ANZWER:
010 (1.00) l r
i d
l
)'
REFERENCE:
i SAR
- p. 75 i
ANSWER:
011 (1.00) i L
b.
REFERENCE:
SAR' p.66 GTRR procedure 5001 p.2 ANSWER:
012 (1.00) d
REFERENCE:
>?
'SAR p. 81 su l.!
,. ANSWER:
013
.(1. 0 0 )
el+
.a).
primary or D20
- c., > b)..scccondary or H2O l
. r.
i
, 4 :' -
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
'\\
(
REF.ERENCE:
)
SAR.p. 78 l
l
. ANSWER:-
-014.(1.00)
C j :-
REFERENCE:
i I
SAR page 83 I
i
(
0f
\\,
1 Y
REFEREN
/2'?[f 0 j
/.Ms-T/S p.6, 7, l
i ANSWER:
016 (1.00) a l
REFERENCE:
i GTRR-Procedure 5012 page :
ANSWER:
017 (1.00) l d.
l 1
REFERENCE:
SAR'p. 137 section 8.2.1 i
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
r..
O O
9.AN8WER:
018.(1.00)
. Ao JWA
REFERENCE:
GTRR procedure.2160.
- p. 2 l
. ANSWER:
019 (1.00) l r'
b.
t
REFERENCE:
Procedure 5120 p.1 l
i i
ANSWER.
020 (1.00) d
REFERENCE:
f SAR p.67 i
i i
ANSWER:
021-(1.00)
REFERENCE:
t
' GTRR' 2015 ROCctor Power Calibration
- p. 1 Rev. A Item II t
t
(***** END OF CATEGORY C *****)
(********** END OF EXAMINATION **********)
m 1
NAME:
ki/
PAGE 1 GEORGIA INSTITUTE OF TECHNOIDGY EXAMINATION ANSWER SHEET j
hD A.1 A
B h
' 1 A.2 A
B C
A.3 A hC D
?A.4 (k) B C
D
!A.5 A B OD
@) B A.6 C
D hD
'A.7
.A B
.A.8 l)CdY
{
cy uw ( % s-r)
% )<oo c
C.h A.9 A
B A.10
.A hC D
A411 A (RI C D
'A.12 A
B-C @
A.13 a.
(kM B C
D b..
A B
C (D)
A.14
-@B C
D E
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