ML20128Q262
| ML20128Q262 | |
| Person / Time | |
|---|---|
| Site: | Reed College |
| Issue date: | 10/07/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20128Q260 | List: |
| References | |
| 50-288-OL-96-03, 50-288-OL-96-3, NUDOCS 9610210005 | |
| Download: ML20128Q262 (33) | |
Text
._.
U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-288/OL-96-03 FACILITY DOCKET NO.:
50-288 FACILITY LICENSE NO.:
R-112 FACILITY:
Reed College EXAMINATION DATES:
September 24,1996 EXAMINER:
Patrick Isaac, Chief Examiner SUBMITTED BY:
N7 e
Pa kIsa hief Examiner Date
SUMMARY
During the week of September 23, the NRC administered retake examinations to three Reactor Operator candidates. All three candidates passed their respective examinations.
REPORT DETAILS 1.
Examiners:
Patrick Isaac, Chief Examiner 2.
Results:
RO PASS / Fall SRO PASS / FAIL TOTAL PASS / Fall Written 3/0 0/0 3/0 Operating T*st 0/0 O/0 0/0 Overall 3/0 0/0 3/0 ENCLOSURE 1 9610210005 961011 i
PDR ADOCK 05000238 V
)
l
~
f 5
U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
Reed College REACTOR TYPE:
TRIGA DATE ADMINISTERED:
1996/09/23 REGION:
IV CANDIDATE:
INSTRUCTIONS TO CAdQ'DATE:
Answers are to be written on the answer sheet provided. Attach the answer sheets to the examination. Points for each question are indicated in parentheses for each question. A 70% is required to pass the examination. Examinations will be picked up one (1) hour after the axamination starts.
CATEGORY CANDIDATE'S
% OF VALUE SCORE TOTAL CATEGORY 20.00 A.
REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature ENCLOSURE 2
~
A. RX THEORY. THERMO & FAC OP CHARS Paga 2 l
ANSWER SHEET 1
4 Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
001 a b c d 002 a b c 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 1
008 a b c d 009 a b c d 010 a b c d 011 abcd 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 020 a b c d
("* END OF CATEGORY A"*)
(*"" END OF EXAMINATION "*")
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
l 1.
Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
2.
After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have neither received nor given assistance in completing the examination. This must be done after you complete the examination.
3.
Restroom trips are to be limited and only one candidate at a time may leave.
You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
4.
Use black ink or dark pencil Saly to facilitate legible reproductions.
5.
Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each answer sheet.
6.
Mark your answers on the answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.
7.
The point value for each question is indicated in [ brackets) after the question.
8.
If the intent of a question is unclear, ask questions of the examiner only.
9.
When tuming 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 (1) hour for completion of the examination.
13.
When you have completed and turned in you examination, leave the examination area. If you are observed in this area while the examination is still in progress, your license may be denied or revoked.
EQUATION SHEET d = sc, AT = s AH = UA AT p"'**, (p -0)2
~
2a(k)f t' = 5 x 10** seconds S _
S ggg _
-p 1-K,y A,, = 0.1 seconds -$
CR,(1 -K,,,) = CR (1 -K,)
2 er CR,(-p,) = CR,(-p,)
SUR = 26.06 M=
,p-p, 1-K,y, 1
CR, P = P,10suam M=
=
1 -K,y CR, SDM = (1 -K,,)
T p=p e g
o en I1 -P) P, I
T=
P=
p-)
0-P Ap =
T=f+
~P k,y,xK,y, p
h,yp 0.693 (K,y-1) 73=
Ken DR =DR, e ~h' DR,d, = DR d,'
a Y("I DR =
=
g2 Q,,
= 0.007 DR - Rem, Ci - curies, E - Mev, R - feet 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 BTU /hr/lbm/"F c, = Ical/sec/gm/ C
~
Page 6 i
A. RX THEORY, THERMO & FAC OP CHARS 4
QUESTION: 001 (1.00)
As power level increases, the Prompt Negative Temp. Coefficient (PNTC) causes:
a.
238U to absorb neutrons over a wider range, thus decreating the number i
of neutrons available for fission with 235U.
b.
Doppler resonance effects to decrease.
l c.
The hydrogen atoms in the ZrH2 to slow down more neutrons.
i d.
More thermal neutron absorption by the moderator.
2 QUESTION: 002 (1.00)
During a fuel loading, as the reactor approaches criticality, the value of 1/M:
- a. decreases toward zero 4
- b. decreases toward one
- c. increases toward infinity I
- d. increases toward one i
a i
I e
(*"" CATEGORY A CONTINUED ON NEXT PAGE ""*)
Page 7 A. RX THEORY, THERMO & FAC OP CHARS QUESTION: 003 (1.00)
Select one of the following statements which correctly describes the influence of delayed neutrons on the neutron life cycle. Delayed neutrons:
a.
decrease the period of a reactivity addition because they thermalize more quickly than prompt neutrons.
b.
take longer to thermalize because they are born at higher energies than prompt neutrons.
c.
cause the length of the average neutron generation time to increase and reactor period to increase.
d.
increase the value cf Beff because they are born at higher energies than prompt neutrons.
QUESTION: 004 (1.00)
What is the stable Rx period which produces a power rise from 1 watt to 5 KW in 186 secs?
a.
10 secs.
b.
22 secs.
c.
30 secs.
d.
116 secs.
(*"" CATEGORY A CONTINUED ON NEXT PAGE *"")
._.... ~..
I~
Paga 8 c
A. RX THEORY, THERMO & FAC OF CHARS QUESTION: 005 (1.00)
Which one of the following completes the statement?
l The largest amount of recoverable energy from fission of U-235 is due to the kinetic energy of the:
a.
Thermal neutrons i
i b.
Fast neutrons c.
Fission fragments d.
Beta decay particles QUESTION: 006 (1.00)
What three materials help moderata Reed's reactor?
a.
Water, Zirconium Hydride, Boron carbide b; Graphite, water, concrete c.
Graphite, water, Zirconium Hydride d.
Zenon, samarium, promethium QUESTION: 007 (1.00)
Given a source strength of 50 neutrons per second (N/sec) and a multiplication factor of 0.8, the expected neutron count rate would be:
a.
125 N/sec b.
250 N/sec c.
400 N/sec d.
500 N/sec
(*"** CATEGORY A CONTINUED ON NEXT PAGE *"")
~
Pag 3 9 A. RX THEORY, THERMO & FAC OP CHARS QUESTION: 008 (1.00)'
Which ONE of the following is the reason for the -80 second period following a Rx scram?
a.
U235 affinity for source neutrons.
b.
Fuel temp, coefficient adding positive reactivity.
c.
Longest lived delayed neutron precursors decay constant.
d.
Amount of negative reactivity added on a scram exceeds the shutdown margin.
QUESTION: 009 (1.00)
In a subcritical Rx, Keff is increased from 0.861 to 0.946. Which one of the following is the amount of reactivity that was added to the core?
a.
0.085 delta-K/K b.
0.220 delta-K/K c.
0.104 delta-K/K d.
0.125 delta-K/K QUESTION: 010 (1.00)
The purpose of the beryllium in the Am-Be neutron startup source is the following:
a.
to convert the installed Am241 to Am245 b.
to moderate the neutrons produced by Am241 c.
to convert to neutrons the y emitted spontaneously by Am241 d.
to enhance the conversion of Am241 to Np237
("'" CATEGORY A CONTINUED ON NEXT PAGE *"")
_ _. _ ~.
P g310 A. RX THEORY, THERMO & FAC OP CHARS 4
f 1
l QUESTION: 011 (1.00) i Which one of the following describes the difference between a moderator and reflector?
a.
A reflector increases the fast non-leakage factor and a moderator increases the thermal utilization factor.
i b.
A reflector increases the neutron production factor and a moderator increases the fast fission factor.
c.
A reflector decreases the thermal utilization factor and a moderator increases the fast fission factor.
1 4
l d.
A reflector decreases the neutron production factor and a moderator decreases the fast non-leakage factor.
l QUESTION: 012 (1.00)
~
The shim rod is withdrawn from the core.
l Which one of the following explains the reactivity addition from the rod?
a.
Reactivity added will be equal for each inch of withdrawal.
b.
Reactivity addition per inch will be greatest from 40% to 60% withdrawn.
c.
The first 30% of rod travel will have the greatest reactivity addition per inch.
d.
The last 30% of rod travel will have the greatest reactivity addition per inch.
(*"" CATEGORY A CONTINUED ON NEXT PAGE "*")
Pcg311 A. RX THEORY, THERMO & FAC OP CHARS QUESTION: 013 (1.00)
Which one of the following factors plays the MOST important role in determining the worth of a control rod?
a.
The value of the delayed neutron frcction.
b.
Reactor power.
c.
The rod speed.
d.
The flux shape.
QUESTION: 014 (1.00)
Which one of the following describes " Excess Reactivity"?
Excess reactivity is:
a.
a measure of the additional fuel loaded to overcome fission product poisoning, b.
a measure of remaining control rod worth with the reactor exactly critical.
c.
the combined control rod negative reactivity worth required to keep the reactor shutdown.
d.
the maximum reactivity by,which the reactor can be shutdown with one control rod fully withdrawn.
(""* CATEGORY A CONTINUED ON NEXT PAGE ""*)
_. _ _ _. _ _. ~ _....
P:g312 2
A. RXTHEORY, THERMO & FAC OP CHARS 4
i QUESTION: 015 (1.00) a Which one of the following is the MAXIMUM amount of reactivity that can be prompey inserted into the reactor WITHOUT causing the reactor to go " Prompt Criticar?
a.
0.10 dollars b.
0.50 dollars c.
0.90 dollars d.
1.25 dollars QUESTION: 016 (1.00)
Reactor power is 100 kw with equilibrium Xenon (Xe) concentration. The reactor scrams (reactor power is instantly reduced to 0 kw). What will the Xenon concentration graph looklike?
a.
Xenon concentration will decrease initially, then increase to a new equilibrium concentration.
i b.
Xenon concentration will increase to peak in 8-12 hours then decay to zero.
c.
Xenon concentration will increase initially, then decrease to a new equilibrium concentration.
d.
Xenon concentration will decrease to a new equilibrium concentration.
(""* CATEGORY A CONTINUED ON NEXT PAGE **"*)
~
Pigs 13 A. RX THEORY, THERMO & FAC OP CHARS QUESTION: 017 (1.00) i Which one of the following statements describes the effect of an increato in fuel temperature in a TRIGA fuel element.
i a.
The probability that a thermal neutron will lose energy in a collision with an excited state hydrogen atom in UZrHx increases.
4 b.
The probability that a neutron will escape from the element before being captured in the fuel meat increases.
c.
A shift in the thermal neutron spectrum, towards lower energies, occurs in the fuel element.
]
l d.
The mean free path for fast neutrons in the fuel element in decreased.
QUESTION: 018 - (1.00)
Which statement best describes the heat transfer mechanism at the Reed College Reactor?
a.
From the fuel center line, heat is transferred to the surface of the fuel rod by convection and is carried into the coolant by conduction.
b.
Heat is transmitted to the fuel rod surface by thermal radiation and carried to the coolant bt conduction.
i c.
Heat conducted to the surface of a fuel rod is carried into the coolant and out of the system by convection.
1 d.
The temperature distribution from the fuel center line to the coolant is linear.
(""* CATEGORY A CONTINUED ON NEXT PAGE "*")
Page 14 A. RX THEORY, THERMO & FAC OP CHARS i
i l
QUESTION: 019 (1.00) d Assume your reactor is being taken critical by periodically withdrawing equal reactivity control-rod increments. Comparing two consecutive control rod withdrawals, which one of the following statements is correct ?
a.
Time for power to stabilize will be equal for both withdrawals and the power increase will be the same for both withdrawals.
l b.
The power increase will be the same for both withdrawals but the time i
for power to stablize will be less for the second withdrawal.
c.
The power increase will be the same for both withdrawals but time for l
power to stabilize will be longer for the second withdrawal.
2 d.
The power increase will be larger for the second withdrawal and the time l
for power to stabilize will be longer for the second withdrawal.
i e
QUESTION: 020 (1.00)
An initial count rate of 100 is doubled five times during startup. Assuming an initial Keff=0.950, what is the new Keff?
- a. 0.957
- b. 0.979
- c. 0.988
- d. 0.998
(*" END OF CATEGORY A *")
("*" END OF EXAMINATION *"")
_ = _ _
Paga 15 A. RX THEORY,THERMO & FAC OP CHARS ANSWER: 001 (1.00) a
REFERENCE:
Reed Training Manual Sect.10.5.2 l
ANSWER: 002 (1.00) a
REFERENCE:
Reed Training Manual Sect. 8.6 ANSWER: 003 (1.00) c
REFERENCE:
Reed Training Manual Sect 9.6 ANSWER: 004 (1.00) b
REFERENCE:
Reed Training Manual Sect.10.1 Pr:P e" o
("*" CATEGORY A CONTINUED ON NEXT PAGE "*")
w
Page 16 A. RX THEORY, THERMO & FAC OP CHARS
~
\\
ANSWER: 005 (1.00)
C 4
REFERENCE:
Reed Training Manual Sect.10.1 Lamarsh, J.R., Introduction to Nuclear Engineering, Addison-Wesley Publishing, Reading, Massachusetts,1983. Sect. 3.7, Table 3.6, p. 77 ANSWER: 006 (1.00) c
REFERENCE:
Reed Training Manual Sect.10.5.2 J
ANSWER: 007 (1.00) b
REFERENCE:
C.R. = S/(1 - Keff) C.R. = 50/(1 - 0.8) = 50/0.2 = 250 ANSWER: 008 (1.00) c
REFERENCE:
Reed Training Manual Sect. 9.7 Lamarsh, J.R., Introduction to Nuclear Engineering, Addison-Wesley Publishing, Reading, Massachusetts,1983. Sect. 7.1, p. 289.
(*"" CATEGORY A CONTINUED ON NEXT PAGE ""*)
Pags 17 A. RX THEORY, THERMO & FAC OP CHARS ANSWER: 009 (1.00) e
REFERENCE:
Lamarsh, J.R., introduction to Nuclear Engineering, Addison-Wesley Publishing, Reading, Massachusetts,1983. Sect. 4,1, p.102 & Sect. 7.1, p. 282.
i l
ANSWER: 010 (1.00) e
REFERENCE:
Reed Training Manual Sect. 7.5.2 Glassione, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida,1991, Sect. 2.70 2.74, pp. 65 - 66.
ANSWER: 011 (1.00) a
REFERENCE:
Reed Training Manual Sect.10 2 Lamarsh, J.R., Introduction to Nuclear Engineering, Addison-Wesley Publishing, Reading, Massachusetts,1983. Sect. 5.10, p. 213 215.
ANSWER: 012 (1.00) b
REFERENCE:
Rod Curve
(*"** CATEGORY A CONTINUED ON NEXT PAGE "*")
-. =. _ -. - - -. - -.. -
Pcge 18 A. RX THEORY, THERMO & FAC OP CHARS S
ANSWER: 013 (1.00) d
REFERENCE:
Lamarsh, J.R., Introduction to Nuclear Engineering, Addison-Wesley Publishing,
)
Reading, Massachusetts,1983. Sect. 7.2, p. 303.
l ANSWER: 014 (1.00) b.
l
REFERENCE:
Reed Training Manual Sect.10.3 i
Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida,1991, Sect. 5.198, p. 300.
ANSWER: 015 (1.00)
C
REFERENCE:
REED Reactor Training Manual Sect. 9.8 k = 1/ (1-p) k = 1 when p =
ANSWER: 016 (1.00) b.
REFERENCE:
Reed Training Manual Sect.10.4.2 Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida, 1991, 5.56 5.80, pp. 250 260.
(*" CATEGORY A CONTINUED ON NEXT PAGE "")
Pcg319 l'
A. RX THEORY, THERMO & FAC OP CHARS i
ANSWER: 017 (1.00) b
REFERENCE:
t RRF Training Manual, page 10-16, i
ANSWER: 018 (1.00) i
REFERENCE:
Reed Requal Exam 1990 l
ANSWER: 019 (1.00) d
REFERENCE:
Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida, 1991, 3.161 3.163, pp.190 191.
ANSWER: 020 (1.00) d
REFERENCE:
CR1/CR2 = (1 - Keff2)/(1 - Keff1) 1/32 (1 - 0.95) = 1 - Keff2 a
1 - 0.05/32 = Keff2 Ke'i2 = 0.9984
("* END OF CATEGORY A *")
("*" END OF EXAMINATION "*")
Peg 3 20 A. RX THEORY, THERMO & FAC OP CHARS ANSWER KEY MULTIPLE CHOICE 001 a 002 a 003 c 004 b 005 c 006 c 007 b 008 c 009 c 010 c 011 a 012 b 013 d 014 b 015 c 016 b 017 b i
018 c l
019 d 020 d
(*" END OF CATEGORY A "*)
("*" END OF EXAMINATION "*")
l U. S. NUCLEAR REGl;LATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
Reed College REACTOR TYPE:
TRIGA DATE ADMINISTERED:
1996/09/23 REGION:
IV CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
Answers are to be written on the answer sheet provided. Attach the answer sheets to the examination. Points for each que tion are indicated in parentheses for each question. A 70% is required to pass tne examination. Examinations will be picked up one (1) hour after the examination starts.
CATEGORY CANDIDATE'S
% OF VALUE SCORE TOTAL CATEGORY 20.00 B.
NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature ENCLOSURE 2
,~....
B. NORMAL 1EMERG PROCEDURES & RAD CON
+-
ANSWER SHEET Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
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 b c d 008 a b c d 009 a b c d 010 a b c d 011 abcd 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 020 a b c d
(*" END OF CATEGORY B "*)
("*" END OF EXAMINATION "*")
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
1.
Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
2.
After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have neither received nor given assistance in completing the examination. This must be done after you complete the examination.
3.
Restroom trips are to be limited and only one candidate at a time may leave.
You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
4.
Use black ink or dark pencil nely to facilitate legible reproductions.
5.
Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each answer sheet.
6.
Mark your answers on the answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.
7.
The point value for each question is indicated in [ brackets) after the question.
8.
If the intent of a question is unclear, ask questions of the examiner only.
9.
When turning in your examination, assemble the completed examination with examination quest!ons, examination aids and answer sheets. In addition turn in all scrap paper.
10.
Ensure allinformation 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 one (1) hour for completion of the examination.
13.
When you have completed and turned in you examination, leave the examination area. If you are observed in this area while the examination is stillin progress, your license may be denied or revoked.
. ~ = _ - - -. -
1 l
Page 5 B. NORMAIJEMERG PROCEDURES & RAD CON
]
QUESTION: 001 (1.00)
An irradiated sample provides a dose rate of 200 mr/hr at 3 ft. Approximately how far from the sample must a Radiation Area sign be posted?
I 4
i a.
5ft.
b.
8ft.
I c.
20 ft.
l
~d.
50 ft.
s i
\\
l QUESTION: 002 (1.00)
Which one of the following radiation detector types does not have an output intensity (current or pulse height) proportional to the incident radiation energy; i.e., if the incident energy increases, the output intensity does not e
increase?
)
l l
a.
lon Chamber b.
GM c.
Proportional Counter d.
Scintillation QUESTION: 003 (1.00)
Which one of the following is the best absorber of beta radiation?
j
- a. wood I
- b. water j
- c. concrete
- d. lead
]
i
(""* CATEGORY B CONTINUED ON NEXT PAGE **"*)
I
Page 6 B. NORMAUEMERG PROCEDURES & RAD CON QUESTION: 004 (1.00)
Based on the Raqualification Plan for operators at the REED Reactor facility, each licensed operator must complete a minimum of reactivity manipulations during each requalification year, i
a.
4 b.
6 c.
8 d.
10 QUESTION: 005 (1.00)
A reactor sample has a disintegration rate of 5 x 1012 disintegrations per second. Each disintegration emits a.6 Mev gamma. What is the dose rate expected 5 feet from the above sample (assume point source)?
a.
7 R/hr b.
19 R/hr c.
135 R/hr d.
162 R/hr
(*"" CATEGORY B CONTINUED ON NEXT PAGE ***")
Page 7 B. NORMAUEMERG PROCEDURES & RAD CON QUESTION: 006 (1.00)
Which one of the foliowing conditions COMPLETELY satisfies,the technical specification definition of " Reactor Shutdown?"
When the reactor contains insufficient fissile material to attain criticality under a.
optimum available conditions of moderation and reflection, b.
When all scramable rods have been fully inserted, and the reactor is shutdown by greater than 0.7% detta K/K, and the console key has been removed from the console.
When no work is in progress involving core fuel, and the reactor is subcritical by c.
0.7% delta K/K, and the console kay has been removed from the console.
I d.
When sufficient control rode are inserted to assure that the reactor is subcritical by at least 1.00 dollar of reactivity, with the fuel and moderator at ambient temperature.
QUESTION: 007 (1.00)
The Emergency Support Center is located within the:
a.
Site Boundary.
b.
Operations Boundary, c.
Operations Boundary when the control room door is opened.
d.
The Emergency Planning Zone.
QUESTION: 008 (1.00)
A source of radiation release to the environment through the ventilation system during reactor operation is:
a.
Nitrogen-16 from the activation of air b.
Argon-41 from the activation of air c.
Nitrogen-16 from pool water evaporation d.
Argon-41 from activation of pool water
(*"" CATEGORY B CONTINUED ON NEXT PAGE *****)
P, Ige 8 l
B. NORMAUEMERG PROCEDURES & RAD CON i
f QUESTION: 009 (1.00)
A system or component is defined as " operable" by Technical Specifications if:
a.
a channel check has been performed.
]
b.
It is capable of performing its intended function.
c.
it has no outstanding testing requirements.
i d.
It is correctly lined-up and has an adequate source of power.
l l
QUESTION: 010 (1.00)
V&ich one of the following requires a Radiation Work Permit (R&)?
a.
?!henever a sample is being removed from the Lazy Suzan, b.
When entering a potentially contaminated area.
c.
Whenever the expected whole body dose is in excess of 5 mR.
i
- d. Whenever the person performing the operation deems it necessary.
QUESTION: 011 (1.00)
While performing SOP 01, The Start-up Checklist, the operator places the Count Rate Channel switch to one of the calibrate positions and attempts to raise a control rod. The Source light illuminates and rod motion is noted to occur. Which one of the following describes what was just observed?
The operator checked that the:
a.
Rod Raising Interlock is operable.
b.
Source Interlock is operable.
c.
Rod Raising interlock is inoperable.
d.
Source Interlock is inoperable.
("*" CATEGORY B CONTINUED ON NEXT PAGE **"*)
Page 9 i
B. NORMAUEMERG PROCEDURES & RAD CON i
QUESTION: 012 (1.00)
Which one of the following is a prerequisite prior to inspecting any control rod?
a.
Perform a shutdown margin calculation to ensure the reactor remains shutdown during the rod inspection.
b.
Move any two elements of the B ring to the fuel storage racks.
c.
Perform a reactor startup to ew.luate core excess.
d.
Perform the " Calibration and Scram Check" portion of the Start-up Checklist to ensure the scram circuit is operable.
QUESTION: 013 (1.00)
You are the RO during a reactor startup. You verify that the core excess is $3.15.
Which of the following statements correctly lists your subsequent actions?
a.
Lower the Safety and Shim rods until equilibrium is reached. Calculate the shutdown margin.
b.
Shutdown the reactor. Notify the Reactor Supervisor.
c.
Record the critical rod positions after establishing equilibrium conditions.
Complete the remainder of the Purpose Stamp.
d.
Shutdown the reactor. Notify the NRC at (301)816-5100.
(""* CATEGORY B CONTINUED ON NEXT PAGE ***")
. - ~.
Page 10 B. NORMAUEMERG PROCEDURES & RAD CON QUESTION: 014 (1.00)
You are designated as " Checker" for the Start-up checkUst just completed.
Under the console section of the checklist, the following cata is observed:
Calibration Pt.
Scram Setooint Linear Channel 104 %
273 kW Percent Power Channel 103 %
276 kW Period Channel 5 sec 2.8 see Which one of the following describes your expected response to this data?
(According to the Tech. Specs.)
a.
The Period Channel Scram setpoint exceeds the allowable limit.
Operations cannot proceed.
b.
The Percent Power Scram setpoint exceeds the allowable limit.
Operations cannot proceed c.
The Linear Channel Scram setpoint exceeds the allowable limit.
Operations cannot proceed d.
All data is acceptable, operations can proceed.
QUESTION: 015 (1.00)
The REED reactor has been shutdown due to a fuel element leak. Which one of the following radioactive gases poses the most significant hazard during the search for the leaking fuel element? Assume that the fuel element is leaking during the search.
a.
Nitrogen-16 b.
Tritium c.
Xenon-135 d.
Argon 41
("*" CATEGORY B CONTINUED ON NEXT PAGE *"")
.=
_. =,
Page 11 B. NORMAIJEMERG PROCEDURES & RAD CON QUESTION: 016 (1.00) 3 A point source of gamma radiation measures 50 mnhr at 5 ft. What is the exposure rate (mr/hr) from the source at a distance of 10 ft.
a.
25 mr/hr b.
12.5 mr/hr c.
6.25 mr/hr i
)
' d.
17.5 mr/hr l
QUESTION: 017 (1.00)
Which ONE of the following is the correct posting if the radiation level in the area is 75 mr/hr?
a.
CAUTION RADIATION AREA 1
b.
CAUTION RADIOACTIVE MATERIAL (S)
CAUTION AIRBORNE RADIOACTIVITY AREA c.
d.
CAUTION HIGH RADIATION AREA QUESTION: 018 (1.00) 1 in accordance with SOP-03, Reactor Operations, which one of the following statements describes when a STATUS STAMP is to be completed during operations at constant power.
a.
Whenever 30 minutes pass without an intervening shift change.
b.
Whenever a Technical Specification limit is exceeded.
c.
Whenever the reactor operator is temporarily replaced.
d.
When rods are moved to maintain the flux profile.
("*" CATEGORY B CONTINUED ON NEXT PAGE *"")
Page 12 l
B. NORMAUEMERG PROCEDURES & RAD CON I
QUESTION: 019 (1.00)
The preferred hospital for dealing with radiological injuries is:
a.
Providence Hospital b.
Good Samarital Hospital c.
Mount Sinal Hospital d.
Kaiser Permanente QUESTION: 020 (1.00)
Per Reed's Ernergency implementation Procedures, where do facility personnel assemble when the Reactor Facility must be evacuated due to a fire?
Chemistry Laboratory b.
Reactor parking area c.
Director's Office, Chem 102 d.
Chemistry building hallway
(""* END OF CATEGORY B *"")
~
. Page 13 i
i B. NORMAUEMERG PROCEDURES & RAD CON ANSWER: 001 (1.00) e
REFERENCE:
l DR,D,2=DR,D,2 (200mr/hr)(3ft')= (5 mr/hr) X2 X=((200 x 9)/5 = 18.97 - 20 ft ANSWER: 002 (1.00) b
REFERENCE:
J REED Training Manual, Sect. 6.2 ANSWER: 003 (1.00) a
REFERENCE:
REED Training Manual, Sect. 3.4.2 ANSWER: 004 (1.00) d
REFERENCE:
REED Reactor Facility Requalification Plan, Sect. 4.2
(*"" CATEGORY B CONTINUED ON NEXT PAGE "*")
Page 14 B. NORMAUEMERG PROCEDURES & RAD CON ANSWER: 005 (1.00) b
REFERENCE:
1 Curie = 3.7x10 dps==> (5 x 1012 dps)/3.7 x 10'" dps = 135 Cl
+ DR = (6 x 135 x.6)/52 = 19 R/hr ANSWER: 006 (1.00) c
REFERENCE:
Technical Specification Definition A.1 ANSWER: 007 (1.00) a
REFERENCE:
REED Emergency Plan pg 8,26 ANSWER: 008 (1.00) b j
REFERENCE:
Lamarsh, Intro. to Nuclear Eng.,2nd Ed., pg. 520 REED SAR pg. 7-6
("*" CATEGORY B CONTINUED ON NEXT PAGE "*")
~
Page 15 B. NORMAUEMERG PROCEDURES & RAD CON ANSWER: 009 (1.00) b
REFERENCE:
T.S. Definitions A.3 ANSWER- 010 (1.00) c j
REFERENCF_:
SOP-28, Radiation Work Permits,28.2 ANSWER: 011 (1.00) d
REFERENCE:
Reed, SOP 01, Step 1.7.6.7, page 8.
ANSWER: 012 (1.00) b
REFERENCE:
SOP-41, Control Rod inspection, 41.4.2 REED Admin Procedures, pg AP-11 ANSWER: 013 (1.00) b
REFERENCE:
SOP-02 sect. 2.7.2.2
(""* CATEGORY B CONTINUED ON NEXT PAGE ""*)
Page 16 B. NORMAIJEME '; PROCEDURES & RAD CON 4
ANSWER: 014 (1.00) b
REFERENCE:
T.S. Table 1 ANSWER: 015 (1.00) i c
REFERENCE:
Facility Comments on 5/96 Written Examination RRF SOP-91,91.7.1 ANSWER: 016 (1.00) b
REFERENCE:
RRF Training Manual ch. 2 ANSWER: 017 (1.00) a
REFERENCE:
(*"" CATEGORY B CONTINUED ON NEXT PAGE ""*)
i W
Page 17 B. NORMAUEMERG PROCEDURES & RAD CON
)
ANSWER: 018 (1.00) c
REFERENCE:
1 SOP-03, 3.7.3.4
. ANSWER: 019 (1.00) j b
REFERENCE:
Emergency Plan pg. EP-12,3.1.14 ANSWER: 020 (1.00) c
REFERENCE:
Emergency implernentation Procedures, ElP-3 l
l
("* END OF CATEGORY B ***)
1.
("*** END OF EXAMINATION *****)
l
O Page 18 B. NORMAUEMERG PROCEDURES & RAD CON ANSWER KEY MULTIPLE CHOICE 001 e i
002 b 003 a 004 d 005 b 000 c 007 a 008 b 009 b 010 c 1
I 011 d l
012 b 013 b 014 b 015 c j
016 b 017 a 018 c 019 b 020 e
(***** END OF EXAMINATION **"*)
U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
Reed College REACTOR TYPE:
TRIGA DATE ADMINISTERED:
1996/09/23 l
REGION:
IV CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
Answers are to be written on the answer sheet provided. Attach the answer sheets to the examination. Points for each question are indicated in parentheses for each question. A 70% is required to pass the examination. Examinations will be picked up one (1) hour after the examination starts.
CATEGORY CANDIDATE'S
% OF VALUE SCORE TOTAL CATEGORY 20.00 C.
PLANT AND RADIATION MONITORING SYSTEMS All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature ENCLOSURE 2
l*
C. PLANT AND RAD MONITORING SYSTEMS ANSWER SHEET l
Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
001 a b c d 002 a b c 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 abcd 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 i
018 a b c d 019 a b c d
(*" END OF CATEGORY C *")
(""* END OF EXAMINATION *"")
Page 4 j
C. PLANT AND RAD MONITORING SYSTEMS QUESTION: 001 (1.00)
Which one of the following scrams is NOT required by Technical Specifications?
a.
Linear channel b.
% power channei
- c. ' Manual d.
Log channel QUESTION: 002 (1.00)
The pool water level must be maintained at a specified level for proper skimmer operation. Why is this pool level necessary?
a.
Above this pool level, the reactor water system pumps will lose suction and fail, b.
Below this level, air entry could interfere with proper operation of the rabbit tube.
c.
Above this level, the water pressure could damage the purification system filters.
d.
Below this level, air entry could reduce the effectivt ness of the purification system demineralizers.
("*" CATEGORY C CONTINUED ON NEXT PAGE "*")
Page 5 C. PLANT AND RAD MONITORING SYSTEMS QUESTION: 003 (1.00)
Which one of the following would indicate a fuel element failure?
4 a.
A higher than normal pH as indicated by a water sample b.
Slight discoloration of the poolwater c.
Above average fuel element temperature as indicated by a temperature probe d.
Above average conductivity as indicated by a water sample at the exit of the fuel element QUESTION: 004 (1.00)
The neutron absorber in Reed's reactor control rods is:
a.
Aluminum oxide b.
Zirconium hydride c.
Graphite powder d.
Boron carbide QUESTION: 005 (1.00)
What is the purpose of the orifice in the Primary Cooling System?
a.- To restrict coolant flow to 20 gpm through the demineralizers.
b.
To prevent excessive coolant flow back into the core.
c.
To restrict coolant flow to 100 gpm bypassing the demineralizers.
d.
To prevent excessive backpressure on the heat exchanger.
(*** CATEGORY C CONTINUED ON NEXT PAGE *****)
Page 6 C. PLANT AND RAD MONITORING SYSTEMS QUESTION: 006 (1.00)
Limit switches mounted on each drive assembly provide switching for console lights.
Which one of the following statements is FALSE 7 a.
The DOWN light hhs that the control rod and rod drive are at their lower limits.
b.
The UP light indicates that the control rod and rod drive are at their upper limits.
' c.
When the CONT /ON pushbuttons are depressed, the ON lights are extinguished.
d.
The CONT side light of the CONT /ON switch goes off less than one second after a scram occurs.
j QUESTION: 007 (1.00) '
What will be the effect of a high differential pressure across the filter on the reactor water pump and the demineralizer flows?
a.
Increase reactor water pump flow and increase domineralizer flow.
b.
Increase reactor water pump flow and decrease demineralizer flow.
c.
decrease reactor water pump flow and increase demineralizer flow.
d.
decrease reactor water pump flow and decrease demineralizer flow.
("*" CATEGORY C CONTINUED ON NEXT PAGE "*")
" " " ~ -
,w...a-a,,
O Page 7 4
4 8
s l
l 1
8 1
i e
l l
I 4
i i
i i
n 4
Y 1
)
1
m.
Page 8 C. PLANT AND RAD MONITORING SYSTEMS QUESTION: 008 (1.00)
Which one of the following ranges of nuclear instrumentation utilizes an uncompensated ion chamber as the neutron detection device?
a.
Count Rate channel l
b.
Log N channel j
t c.
Linear Power channel d.
% Power channel 4
QUESTION: 009 (1.00) i Which one of the following statements correctly describes the purpose of the PULL ROD in the control rod drive assembly?
a.
Provides rod full out position indication.
i l
b.
Provides a means for manually adjusting rod position by pulling rod out.
}
c.
Provides rod bottom indication.
i d.
Automatically engages the control rod on a pull signal.
i QUESTION: 010 (1.00) j Which one of the following statements correctly describes the purpose of the potentiometer in the control rod drive assembly.
a.
Provides rod position indication when the electromagnet engages the connecting rod armature.
j b.
Provides a variable voltage to the rod drive motor for regulating control rod speed.
c.
Provides potential voltage as required for resetting the electromagnet current.
d.
Provides the potential voltage to relatch the connecting rod.
j
(*"" CATEGORY C CONTINUED ON NEXT PAGE "*")
4
Page 9 t
C. PLANT AND RAD MONITORING SYSTEMS l
QUESTION: 011 (1.00)
Which one of the following statements describes the drive speeds of the l
Shim rod, Regulating rod and Safety rod?
a.
The Shim rod drives at 24 inches per minute, the Regulating and Safety rods drive at 19.nches per minute, j
b.
The Shim and Regulating rods drive at 24 inches per minute, the Safety rod drives at 19 inches per minute.
c.
The Safety rod drives at 24 inches per minute, the Regulating and Shim i
rods drive at 19 inches per minute.
d.
The Regulating rod drives at 24 inches per minute, the Safety and Shim rods drive at 19 inches per minute.
QUESTION: 012 (1.00) in what region of the Pulse Size vs. Applied Voltage characteristic curve does the fission chamber operate?
a.
Geiger Muller b.
Limited Proportionality c.
Proportional d.
lonization QUESTION: 013 (1.00)
Which one of the following occurs when the CAM reaches the " failsafe" setpoint?
a.
Amber light on.
b.
Amber light off.
c.
Amber light on and bell sounds.
d.
Amber light off and bell sounds.
(***** CATEGORY C CONTINUED ON NEXT PAGE "***)
.. =. - -
Page 10 t
C. PLANT AND RAD MONITORING SYSTEMS QUESTION: 014 (2.00)
Match the facility radiation detector in column A with the type of radiological problem it detects in column B.
Column A Column B a.
- 1. Gases and Particulates b.
- 2. Particulates Only c.
- 3. Radiation Level d.
GSM
- 4. Gases Only QUESTION: 015 (1.00)
The Reed Facility License grants permission for possession of 2 specific sources.
Which one of the following describes these sources?
a.
A 2 mg Ra-226 and a 1.64 curie plutonium-beryllium source.
b.
A 1 curie americium-beryllium and a 1.64 curie plutonium-beryllium source.
c.
A 1.64 curie americium-beryllium and a 1 curie plutonium-beryllium source.
d.
A 2 mg Ra-226 and a 1 curie americium-beryllium source.
(*"" CATEGORY C CONTINUED ON NEXT PAGE *****)
Page 11 C. PLANT AND RAD MONITORING SYSTEMS QUESTION: 016 (1.00)
Air contamination greater than the setpoint has been detected in the Reactor Room.
l Which one of the following is the correct response by the ventilation system?
a.
The supply system will automatically stop, dampers will direct air through filters purging the room at 150 cfm.
b.
The supply system will shift to high speed, dampers will direct the exhaust to the ventilation stack at 150 cfm.
c.
The exhaust system will shift to high speed, dampers will direct air through filters purging the room at 150 cfm.
d.
The exhaust system will automatically stop, dampers will direct air through filters purging the room at 150 cfm.
QUESTION: 017 (1.00)
Which one of the following correctly describes how the cleanup system functions to minimize corrosion of reactor components?
The cleanup system a.
maintains pool water pH at a basic value.
b.
maintains pool water pH at an acidic value.
c.
maintains pool water conductivity low.
d.
filters suspended particles from the pool water.
(*"" CATEGORY C CONTINUED ON NEXT PAGE ""*)
Page 12 C. PLANT AND RAD MONITORING SYSTEMS QUESTION:018 (1.00)
With the rod control system in automatic mode, the circuit will change power on a +30 second period based on a rate signal from the channel and a level signal from the channel.
a.
linear, log-n b.
log-n, linear
. c.
startup, linear d.
log-n, percent power QUESTION: 019 (1.00)
Which one of the following describes the action of the rod control system to drive the magnet draw tube down after a dropped rod?
a.
Deenergizing the rod magnet initiates the rod down motion of the draw tube.
b.
Actuation of the MAGNET DOWN limit switch initiates the rod down motion of the draw tube.
c.
Actuation of the ROD DOWN limit switch initiates the rod down motion if the rod drive is withdrawn.
d.
Resetting the scram signalinitiates the rod down motion of the draw tube.
("* END OF CATEGORY C *")
(*"" END OF EXAMINATION ""*)
1 i:
Page 13 C. PLANT AND RAD MONITORING SYSTEMS l
ANSWER: 001 (1.00) d
REFERENCE:
i Tech Specs Table I i
ANSWER: 002 (1.00) d
REFERENCE:
GA Triga Mechanical Maintenance and Operating Manual, pg. 81 1
ANSWER: 003 (1.00) d
'l
REFERENCE:
Facility Comments from exam adm!nistered in 1/95 ANSWER: 004 (1.00) d
REFERENCE:
GA Triga Mechanical Maintenance and Operating Manual, pg.15
("*** CATEGORY C CONTINUED ON NEXT PAGE ***")
Page 14 p
C. PLANT AND RAD MONITORING SYSTEMS l
ANSWER: 005 (1.00) c l
REFERENCE GA Triga Mechanical Maintenance and Operating Manual, pg. 78 ANSWER: 006 (1.00) l b
l
REFERENCE:
l SAR pg. 5-12 GA TRIGA Electrical Maintenance Manual, pg. 22 ANSWER: 007 (1.00) d'
REFERENCE:
GA TRIGA Mechanical Maintenance and Operating Manual. pg. 77 1
ANSWER: 008 (1.00) j l
d
REFERENCE:
I
{
SAR Fig. 5-7, Block diagram of reactor instrumentation 1
i
(**"' CATEGORY C CONTINUED ON NEXT PAGE "*")
Page 15 C. PLANT AND RAD MONITORING SYSTEMS ANSWER: 009 (1.00) c
REFERENCE:
RRF SAR (pg 5-8 thru 5-12) 4 ANSWER: 010 (1.00) a
REFERENCE:
RRF SAR pg 5-12 ANSWER: 011 (1.00) 1 d
[
REFERENCE:
SAR pg. 5-11 ANSWER: 012 (1.00) c
REFERENCE:
RRF Training Manual, pg. 6-8 e
("** CATEGORY C CONTINUED ON NEXT PAGE ""*)
4 g
Page 16 C. PLANT AND RAD MONITORING SYSTEMS ANSWER: 013 (1.00) b
REFERENCE:
Reed SOP-70, Section 70.7.3.2 ANSWER: 014 (2.00) l a, 3; b,1; c,2; d,4 REFERENCE SOP-30, Cal. of RAM; SOP-31, Cal of CAM; SOP-32, Cal of APM; SOP-33, Cal. of GSM ANSWER: 015 (1.00) c
REFERENCE:
4 i
Reed Facility License, Section 2.
ANSWER: 016 (1.00) a
REFERENCE:
l SAR pg. 4-5
("*" CATEGORY C CONTINUED ON NEXT PAGE *"**)
Page 17 De*
C. PLANT AND RAD MONITORING SYSTEMS ANSWER: 017 (1.00) c
REFERENCE:
RRF SAR, Sect. 5.2.6 p. 5-7.
ANSWER: 018 (1.00) i b
REFERENCE:
RRF SAR, Sect. 5.3.2, p. 5-14 ANSWER: 019 (1.00) c
REFERENCE:
GA TRIGA Mech. Maint. & Operating Manual I
("* END OF CATEGORY C *")
(""* END OF EXAMINATION "*")
Page 18 C. PLANT AND RAD MONITORING SYSTEMS ANSWER KEY MULTIPLE CHOICE 1
001 d 002 d 003 d 2
004 d 005 c 006 b 4
007 d 008 d 1
009 c j
010 a 011 d i
012 c i
013 b 014 a. 3; b.1; c.2;
- d. 4 015 c 016 a 017 c 018 b i
019 c 4
(*" END OF CATEGORY C "*)
("*" END OF EXAMINATION *"")