ML20199G621
| ML20199G621 | |
| Person / Time | |
|---|---|
| Site: | Reed College |
| Issue date: | 10/30/1997 |
| From: | Isaac P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20199G610 | List: |
| References | |
| 50-288-OL-97-02, 50-288-OL-97-2, NUDOCS 9711250223 | |
| Download: ML20199G621 (38) | |
Text
1 Reed College Docket No. 50 288 cc:
Director, Oregon Department of Energy 528 Cottage Street, N.E.
Salem, Oregon 97310 Mayor of City of Portland 1220 Southwest 5th Avenue Portland, Oregon 97204 Administrator Siting and Regulation Oregon Department of Energy I. abor and Industries Building Room 111 Salem, Oregon 97310 9711250223 971110 PDR ADOCK 05000298 V
PDR iuman s'mMammmm Amass
U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT
~
REPORT NO.:
50 288/OL 97-02 FACILITY DOCKET NO.:
50-288 FACILITY LICENSE NO.:
R 112 FACILITY:
Reed College EXAMINATION DATES:
October 16-17, 1997 EXAMINER:
Patrick Isaac, Chief Examiner SUBMITTED BY:
/6
/0[Soh7
" tripi J. Is of Examiner tatef
SUMMARY
During the week of October 13,1997, NRC administered Operator Licensing Examinations to one Reactor Operator (RO) and three Senior Reactor Operator Upgrade (SROU) candidates. All candidates passed their respective examinations.
ENCLOSURE 1
. _.....-- ~
l REPORT DETAILS 1.
Examiners:
Petrick Isaac, Chief Examiner 2.
Results:
SRO PASS / FAIL TOTAL PASS / Fall Written 1/0 0/0 1l0 Operating Test 1/0 3/0 4/0 -
Overall 1/0 3/0 4/0 3.
t!xit Meeting:
Personnel attending:
Mr. Stephen G. Frantz, Directr.:. Reed College Reactor Mr. Christopher S. Melhus, Assistant Director Patrick J. Isaac, Chief Examiner The facility examination comments were discussed as noted in Enclosure 2.
O n
NRC RESOLUTIONS WRITTEN EXAMINATION OUESTION (8.2)
A radioactive source generates a dose of 100 mR/hr at a distance of 10 feet. With two inches of lead shleiding the reading drops to 50 mR/hr at a distance of 10 feet. If you were to add ANOTHER four inches of the same type of shielding, the reading at 10 feet would drop to...
a.
25 mR/hr b.
12% mR/hr c.
6% mR/hr d.
3% mR/hr ANSWER: b
REFERENCE:
two inches = one half thickness (Tw). Using 3 half-thickness will drop the dose by a factor of (%)* = %.
100/8 = 12.5 Facility Comment:
The question is flawed in two ways. First, the values given in the question are unrealistic.
The question states that 2 inches of lead reduce the dose rate from 100 mR/hr to 50 mR/hr.
According to the Radiological Health Handbook (1970) page 164, the half value layer (HVL) for lead is 0.12 mm for 100 kev photons and is 9 mm for 1 MeV photons. The largest HVL for l6ad regardless of photon energy is 15 mm. Since 2 inches of lead is equal to 50.8 mm, there are no photons for which the problem is even approximately correct. For 100 kev photons 2 inches of lead would reduce the dose to undetectable levels. For 1 MeV photons i
2 inches of lead would reduce the dose from 100 mR/hr to 0.02 mR/hr. For i MeV photons 6 inches of lead (the final thickness) would reduce the dose to 0,0008 mR/hr.
l l
The second difficulty is that the problem ignores buildup factors. According to the
(
Radiological Health Handbook (1970) page 146, the build up factor for 0.7 inches of lead is 5.86 for 1 MeV photons. For two inches and six inches, the buildup f actors would be much larger. The measured dose does nnt decrease the same for each HVL added due to the buildup factor. The decrease is much less than anticipated.
We recommend that Ouestion B.2 be deleted, in the future we recammend that the question use 9 mm of lead instead of 2 inches, and that the question specifically state that buildup f actors should be ignored.
NRC Resolution:
Comment Accepted. Question B.2 will be deleted from the examination.
ENCLO'SURE 2
U. S NUCLEAR REOUl.ATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION i
FACILITY:
REED College REACTOR TYPE:
TRIGA DATE ADMINISTERED:
1997/10/16 REGION:
IV CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
Answers are to be written on the answer sheet provided. Attach all answer sheets to the examination. Point values are indicated in parentheses for each question. A 70%
in each category is req.63d to pass the examination. Examinations will be picked up three (3) hours after the examination starts.
% OF CATEGORY % Ot CANDIDATE'S CATEGORY VALUE
.IQIll SCOR5 VALUE CATEGORY 20.00
.311 A.
REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING h
CHARACTERISTICS 19.00_
.22 2 B.
NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00
}11.
C.
FACILITY AND RADIATION MONITORING SYSTEMS 59.00 TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature ENCLOSURE 3
A RX THEORY. THERMO & FAC OP CHARS
(
ANSWER SHEET Multiple Choice (Circle or X your choice)
If you change your aaswer write your selection in the blank.
MULTIPLE CHOICE 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 018 a b c d 019 a b c d 020 a b c d 5
(*"" END OF CATEGORY A ""*)
B. NORMAUEMERG PROCEDURES & RAD QQN ANSWER SHEET Multiple Choice (Circle or X your choice)
N you change your answer, write your selection in the blank.
MULTIPLE CHOICE 001 a b c - d 002 a b c d 003 1 2
3 4
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 s
l
(""* END OF CATEGORY B *"")
l l
C PLANT AND RAD MONITORING SYSTEMS l
l.
ANSWER SHEET Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
MULTIPLE CHOICE 001 abcd 002 a b c d 003 a b c d 004 abcd 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 abcd 015 a b c d 016 a b c d 017 a b c d 018 a b
c d
019 s b c d
(***" END OF CATEGORY C "***)
(......"" 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 only to facilitate legible reproductions.
5.
Print your name in the blank provided in the upper right-hand comer 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, i
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 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.
92.
There is a time limit of three (3) hours for completion of the examination.
13.
When you have completed and tumea 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 = de A T = n AN = UA A T (p-S):
p** *, 2a(k)t l' = 5 x 10 seconds SCR =
S S
=
ett h,,, = 0.1 seconds *1 CR ( -p3 ) = CR ( -p )
3 g
D = 0.0075 1-K,,,'
A*,,p M=
S UR = 2 6. 0 6 1-K,,,,
1 CR P = P, 10 "" '"
3 g,
1 - K,,,
CR,
( 1 -K,,,)
i SDM =
P=P,e ett
(*
D (1 -0)
T=
P=
P, p_3 E-p e t t, " ett, 3,{,
-p o
A.,fo k,,,,= K,,,,
0.693
( X-1 )
T,,
=
p, ett DR =DR, e *kt DR,d,' = DR,d,'
IP ' I (P ' }
2 1
6CIE(n)
DR =
p, p,,g pg, g, g
I = I,e *
1 Curie = 3.7 x 10" dis /sec 1 kg = 2.21 lbm 1 BTU = 778 ft-lbf
'F = 9/5 *C + 32 1 gal (110) = 8 lbm
'C = 5/9 (*F - 32) 3 c, = 1.0 BTUllbml'F c, = 1 callsec/gml*C i
Section A B Theory. Thermo & Fac. Ooeratina Cha acterist!cs Page1 QUESTION (A.1)
[1.0)
- A mixed beta $amma point source measums 200 mrem /hr at one foot and 0.1 mrem /hr at 20 feet. What is the fraction of botas in the source?
a.
10%
b.
20%
4 c.
80 %
d.
90 %
QUESTION (A.2)
[1.0)
An element decays at a rate of 20% per day. Determine its half-life.
a.
3 hr.
b.
75hr.
c.
108 hr.
d.
158 hr.
QUESTION (A.3)
[1.0)
The reactor has scrammed following an extended period of operation at full power. Which one of the following accounts for generation of a majority of the heat one (1) hour after the scram?
a.
Spontaneous fissions b.
Delayed neutron fissions c.
Alpha fission product decay d.
Beta fission product decay
Section A' R Theory. Thermo A Fac. Doeratino Characte istics Page 2 i
QUESTION (A.4)
[1.0) if Keff equals 1.0, how much reactivity must be added to make the reactor prompt critical?
]
i s.
The beta fraction.
b.
The amount to make Keff equal to 1.1.
c.
The amount to make the reactor period infinite, d.
The amount needed to increase the mean neutron lifetime to 0.080 seconds.
QUESTION (A.5)
[1.0)
Which of the following six factor formula terms are affected most by temperature?
a.
Thermal utilization and resonance escape probability D.
Fast fission factor and resonance escape probability c.
Fast fission factor and reproduction factor d.
Reproduction factor and thermal utilization QUESTION (A.6)
[1.0)
If reactor power is increasing by a decade every minute, it has a period of, a.
13 see b.
26 sec c.
52 sec d.
65 sec
4 Section A R Theorv. Thermo & niac. Ooeratina Characteristics Page 3 QUESTION (A.7)
[1.0)
Which one of the following is the primary reason a neutron se i.'e is installed in the core?
a.
To allow for testing and irradiation experiments when the reactor is shutdown, b.
To supply the neutrons required to start the chain reaction for each reactor startup.
c.
To provide a neutron level high enough to be monitored for a controlled reactor startup.
d.
To incresso the excess reactivity of the reactor which reduces the frequency for refueling.
QUESTION (A.8)
[1.0)
The reactor is suberitical with a Keff of 0.95 and a source range count rate of 15 counts per s
second. Control rods are withdrawn until the source range count rate equals 45 counts per second.
Which of the following is the Keff of the core after the control rod withdrawal?
a.
0.953 b.
0.970 e
c.
0.063 d.
0.995 QUESTION (A.9)
[1.0)
The reactor is operating at 100 KW. The reactor operator withdraws the Regulating Rod allowing power to increase. The operator then inserts the same rod to its original position, decreasing power.
In comparison to the rod withdrawal, the rod insertion will result in; a.
the same period due to equal amounts of reactivity being added.
b.
a shorter period due long lived delayed neutron precursors, c.
the same period due to equal reactivity rates from the rod.
d.
a longer period due to long lived delayed neutron precursors.
___,__m
Section A: R Theory. Thermo & Fac. Operatino Characteristics Page 4 QUESTION (A.10)
[1.0)
Following a scram, the value of the stable reactor period is:
a.
approximately 50 seconds, because the rate of negative reactivity insertion rapidly approaches zero b.
approximately -10 seconds, as determined by the rate of decay of the shortest lived delayed reatron precursors.
approximately -80 seconds, as determined by the rate of decay of the longest lived c.
delayed neutron precursors.
d.
Infinity, since neutron production has been terminated.
QUESTION (A.11)
[1.0)
During a reactor startup, as the reactor approaches criticality, the value of 1/M:
a.
decreases toward zero b.
decreases toward one c.
increases toward infinity d.
increases toward one QUESTION (A.12)
[1.0]
With a core excess calculated at $2.87, which one of the following is the MINIMUM amount of negative reactivity needed to assure that the reactor is shutdown per T.S. 7 a.
$0.13 b
$0.93 c.
$3.40 d.
$3.80
Section A R Theory. Thermo & Fac Ooeratino Characteristics Page5 QUESTION (A.13)
[1.0)
With all rods in, cold, Xe free, the count rate is 1000 cpm and the reactivity is -85.36. What final count rate would you expect to see if the safety rod was completely withdrawn? (Assume Safety Rod worth of $3.85) a.
5360 cpm b.
3643 cpm c.
1510 cpm d.
344 cpm QUESTION (A.14)
[1.0)
Withdrawal of a control rod predominantly affects K, by changing the:
a.
fast fission factor.
b.
thermal utilization factor, c.
neutron reproduction factor, d.
resonance escape probability.
QUESTION (A.15)
[1.0)
The regulating blade was withdrawn two (2) inches. The steady reactor period following blade withdrawalis observed to be sixty (60) seconds.
Which one of the following is the differential blade worth?
a.
9.1 x 10d delta k/k per inch b.
5.0 x 10-8 delta k/k per inch c.
1.2 x 10" delta k/k per inch d.
5.4 x 10" detta k/k per inch
Section A' R Theorv. Thermo & Fac. Ooeratina Characteristics Page 6 QUESTION (A.16)
[1.0)
Delayed neutrons have a large effect on control of reactor power due to their longer generation time. Which one of the below is the reason for the longer generation time?
a.
Delayed neutrons have shorter half-lives, b.
Delayed neutrons thermalize slower.
c.
The escape probability for delayed neutrons is higher.
d.
Delayed neutrons are not a product of primary fission.
QUESTION (A.17)
[1.0)
Which one of the following statements describes how fuel temperature affects the core operating characteristics?
a.
Fuel temperature increase will decrease the resonance escape probability, 2
b.
Fuel temperature decrease results in Doppler Broadening of U* and Pu " resonance peaks and the decrease of resonance escape probability.
c.
Decrease in fuel temperature will increase neutron absorption by U" and Pu'".
d.
Fuel temperature increase results in Doppler Broadening of US and PU2" resonance peaks and the decrease of neutron absorption during moderation.
QUESTION (A.18)
[1.0)
Which one of the following are the materials designed as moderators for the reactor?
a.
Zirconium Hydride, Concrete, and Graphite b.
Water, Graphite, and Zirconium Hydride c.
Graphite, Water, and Aluminum d.
Aluminum, Concrete, and Water
Section A: A Theorv. Thermo & Fac Ooeratina Characteristics Page 7 QUESTION (A.19)
[1.0)
Which ONE of the following describes how doubling the time a target nuclide is irradiated affects the activity level.
s.
Less than doubles the activity, b.
More than doubles the activity.
c.
Exactly doubles the activity.
d.
Increases the activity by a factor of e.
QUESTION (A.20)
[1.0)
A control rod is withdrawn from the core. Which of the following explains the reactivity additiori 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.
Reactivity addition per inch will be greatest in the bottom fourth of the core.
d.
Reactivity addition per inch will be greatest in the top fourtt ;'t the core.
l Eg.giion B: Normal /Emero Procedures & Rad con Page 8 QUESTION (B.1)
[1.0)
Since he started omployment at the RRF a radiation worker has accumulated a dose of 3.27 R.
So far this year, the worker has received a dose of 1.25 R. How long can he remain in an area with a gamma dose rate of 75 mR/hr without exceeding the 10CFR20 TEDE limit? (Assume zero committed dose.)
a.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> b.
23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> c.
50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> d.
66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> QUESTION (B.2)
[1.0)
DELETED A radioactive source generates a dese of 100 mR/hr at a distance of 10 feet. With two inches of lead shielding the reading drops to 50 mR/hr at a distance of 10 feet. If you were to add ANOTHER four inches of the same type of shielding, the reading at 10 feet would drop to...
a.
25 mR/hr b.
12% mR/hr c.
6% mR/hr d.
3% mR/hr QUESTION (B.2)
[1.0)
Match the requirements for maintaining an active operator license in column A with the correct time period from column B.
Colt.mn A Column B 1.
Renewal of license a.
1 year 2.
Medical Examination b.
2 years 3.
Regaalification Written examination c.
4 years 4.
Requalification Operating Test d.
6 years
Section B: Normal /Emera Procedures & Rad Con Page g QUESTION (B.4)
[1.0]
The governor requests radiation workers to clean up an accident at Trojan While helping out you receive a dose of 6 Rom.10 CFR 20 requires that this dose be tracked as a Planned special exposure. Who is responsiole for maintaining a permanent record of this dose?
a.
Federal Emergency Management Agency (FEMA).
b.
REFO Reactor Facility c.
Nuclear Regulatory Commission.
d.
State of Oregon, (an agreement state).
QUESTION (B 5)
[1.0]
Consider two point sources, each having the same curie strength. Source A's gammas have an energy of 1 MEV whereas Source B's gamma have an energy of 2 MEV. You obtain a reading from the same Geiger counter 10 feet from each source. Concerning the two readings, which one of the following statements is correct?
- a. The reading from Source B is four times that of Source A.
- b. The reading from Source B is twice that of Source A.
- c. Both readings are the same,
- d. The reading from Source B is half that of Source A.
QUESTION (B.6)
[1.0]
Argon-41 is produced by neutron absorption of argon-40. Argon-41 decays by:
a:
a 1.3 MeV gamma with a half life of 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
b.
a 6.1 MeV gamma with a half-life of 7 seconds.
c.
neutron emission with a half life of 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, d.
a 1.3 MeV beta with a half-life of 7 seconds.
+
Section B: Normal /Emero Procedures & Rad con Page 10 QUESTION (B.7)
[1.0)
Following an irradiation of a specimen, the resulting radioisotope is expected to equal 200 curies. The radioisotope will decay by the emission of two gamma rays per disintegration with energies of 1.10 MeV and 1.29 MeV.
Which one of the following is the radiation exposure rate (R/hr) at one (1) foot from the specimen with no shielding?
a.
1708 R/hr b.
2868 R/hr c.
3405 R/hr d.
5736 R/hr QUESTION (B.8)
[1.0)
Which one of the following statements is TRUE conceming experiments?
a.
All explosive materials shall be irradiated with double encapsulation.
b.
The reactivity worth of any moveable experiment shall not exceed $1.00.
c.
No corrosive materials shall be irradiated in the reactor.
d.
The total reactivity worth of allin-core experiments shall not $1.35.
QUESTION (B.9)
[1.0)
Which one of the following statements is FALSE?
a.
Permission from the Director must be obtained each time the overhead crane is to be operated.
b.
During maintenance on a control rod, the magnet power to the remaining two control rods must be disconnected, c.
Before maintenance work can be started involving manual movement of control rods, the core excess reactivity must be reduced to be equal to the worth of the remaining two control rods.
d.
All pneumatic tube irradiations of naturally occurring fissionable material shall be treated as special experiments each time they are performed.
i l
Ser*ian & Normal /Emern. Prar*aures & Rari con Pege 11 i
QUESTION (B.10)
[1.0)
Prior to pstforming SOP-01, The Startup Checklist, how for back is the reactor operator required to review the Main Log?
a.
One full shift.
b.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or until the last log entry for that oiserstor whichever occurs first.
d.
To the last log entr/ or that operator.
f QUESTION (B.11)
[1.0)
A change to the
- Lectures and Meetings
- section of the Requalification P;an is necessary.
Which one of the following is required for the change to be implemented?
I a.
Implement only aftr/ Reacter Operations Committee review and NRC's approval, b.
Implement immediately with Directors concurrence.
c.
Implement after Directors concurrence with Reactor Operations Committee approval within 14 days, d.
Implement only after Reactor Operations Committee and/or the Rafation Safety Committee approval.
QUESTION (B.12)
[1.0)
No special experiment shall be performed until the proposed experimental procedure has been reviewed and approved by which one of the following?
a.
Reactor Operations Committee - Director RRF - Reactor Supervisor b.
Director RRF Reactor Supervisor c.
Director RRF Radiation Safety Committee d.
Reactor Operations Committee. Licensed SRO
,. - - ~... - -
- _ ~.
Section B: Normal /Emera Procedures & Rad Con Page 12 QUESTICN (B.13)
[1.0)
When calibrating the Gaseous Stack MonMor, the supervisor can authorize a change to the alarm setpoint values. Which one of the following describes the rules that govern the changing of the setpoint values?
The setpoint values may be changed providing:
the FallsLfe setpoint is less than the Alarm setpoint AND the Alarm setpoint is less than a.
1000 cpm.
b.
the Fallsafe setpoint is less than the Alarm setpoint OR the Alarm setpoint is less than 1000 cpm.
the Failsafe setpoint is greater than the Alarm setpoint AND the Alarm setpoint is less c.
than 1000 cpm.
d.
the Failsafe setpoint is greater than the Alarm setpoint OR the Alarm setpoint is less than 1000 cpm.
QUESTION (B.14)
[1.0)
Which one of the following describes the ' Site Boundary *?
a.
Area, including the Psychology Building, which extends 250 feet in every direction from the center of the reactor, b.
Area which, when the door to the Control Room is closed, consist of the Control Room, the Reactor Pay, and the Mech. Room.
c.
Art,a for which offsite emergency planning is performed to assure that prompt and effective actions can be taken to protect the public in the event of an accident.
d.
The area whose size depends on the distance beyond the Operations Boundary at which Protective Action Guide could be exceeded.
llischon B. Normal /Emerg Procedures & Rad Con Page 13 QUESTION (B.15)
[1.0) i When assuming the duties of the Emergency Coordinator, you, the RO, are NOT responsible for:
a.
assessing severity of the emergency event.
b.
notifying the City of Portland of an/ incidents which may have caused an uncont olled release of radioactive materials.
c.
terrninating or minimizing releases of radioactive materials.
I d.
directhg emergency control measures for any incident posing a radiological threat to the public.
- QUESTION (8.16)
[1.0)
Which one of the following states the radiation exposure limits in Rem deep dose equivalent that may be authorized by the Emergency Coordinator during an emergency?
Corrective Action Life Savino Action a.
15 25 b.
15 75 c.
25 25 d.
25 75 QUESTION (B.17)
[1.0)
The condition of ' Notification of Unusual Event
- encompasses all of the following except:
a.
There is time available to take precautionary corrective steps.
b.
Release of radioactive material requiring off site response is expected.
c.
One or more elements of the emergency organization are likely to be notified, d.
A signi5 cant hazard potential has been created.
l I
1 l
Bar*1an B: Normal /Emera. Procedures & RglCDD Page 14 QUESTION (B.18)
[1.0)
Which one of the following emergency classifications is NOT addressed in the RFED reactor Emergency Pfar'?
a.
Alert b.
Site-Area Emergency c.
Non Reactor Safety Related Events d.
Notification of Unusual Event QUEST!ON (B.19)
[1.0)
In accordance with the RRF uperating procedures, which one of the following represents the minimum number of poriable radiation survey instruments necessary to operate the reactor?
a.
One GM detector b.
One ionization chamber c.
One GM and one ionization chamber d.
One GM, one ionization chamber, and one neutron detector QUECTION (B.20)
[1.0)
Which one of the following statements is FAl.SE?
a.
A Radiation Work Permit (RWP) is required for any operation which ir. likeiy to produce a dose to an individuali.. excess of 5 mR deep dose equivalent.
b.
All persons performing an operation which requires an RWP shall wear at least two pesonalion chambers (PICS).
c.
Prior to the operation, Part I of the RWP must have been read and signed by each worker who is to participate.
d.
A RWP is valid up to two weeks after Part I is completed and may be extended a;.
additional one week by the Director or Associate Director.
- + -
- - ~
a
1 l
l Section C lhnt and Rad Monitorina Svatoms Page 15 QUESTON (C.1)
[1.0)
Which one of the following is the dosimetry described in the following sentuce?
'the detection system consist of a small quartz fiber electroscope."
a.
Thermoluminescent Dosimeter (TLD) b.
Self reading Pocket Dosimeter c.
Radiophotoluminescent Dosimeter (RPL) d.
Film Badge QUESTION (C.2)
[1.0)
Which One of the following completes the following statement?
The fuelin the Reed reactor is a mixture of uranium-hydride alloy containing
% by weight of uranium enriched to a.
heterogeneous, graphite,20, 8.5 b.
heterogeneous, zirconium,8.5, 20 c.
homogeneous, graphite,20, 8.5 d.
homogeneous, zirconlum, 8.5,20 QUESTION (C.3)
[1.0)
What is the principal advantage of using plastic sample containers when irradiating specimens?
a.
plastic is highly resistive to gamma flux degradation, b,
the amount of radioactivity associated with the container upon removal from reactor is
- small, c.
embrittlement of plastic is min! mal due to the low thermal neutron cross section of plastic.
d.
plastic is bl hly resistive to fast neutron degradation.
0
4 P
Sadion C Plant and Rad MondorinR Syntams Page 16 QUESTION (C 4)
[1.0)
Air contamination greater than the setpoint has been detected in the Reactor Room.
Which one of the following is the correct response by the ventilation system?
a.
The supply system will automatically stop, dampers will direct air tis.ough filters purging the room at 150 cfm.
b.
The supply system will shift to high speed, dampers w?! direct the exhaust to the ventilation stack at 150 cim.
L c.
T4 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 (C.5)
[1.0)
The reactor has been at power for a while, A specimen capsule is being inserted into the reactor with the pneumatic transfer system in manual. After the rabbit operator tums on the rabbit motor, which one of the following describes the subsequent event?
a.
The operator must hold the switch in manual or the capsule will automatically be removed.
b.
A ventilation isolation signalls generated due to Ar 41.
c.
A timer automatically removes the capsule after 7 minutes if it is not reset, d.
The rabbit motor will automatically turn off 2 5 seconds after the EOB (End of Bombardment).
QUESTION (C.6)
[1.0)
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 plu? onium beryllium source.
d.-
A 2 mg Ra 226 and a 1 curie americium-beryllium source.
Sar41an C: Plant and Rad Monitorina Svatema Page 17 QUESTION (C.7)
[1.0)
Which one of the following describes the purpose of the connecting rod piston and the vents in j
the rod drive barrel of the control rod drive system?
a.
The piston and the small grated vents along the length of the rod barrel prevent excessive rod withdrawal speeds.
b.
The piston and the small grated vents near the bottom of the rod barrel slow the rod speed before bottoming impact during scrams, c.
The piston weight holds the control rods fully inserted while the large slotted vents along the length of the rod barrel provide for unrestricted cooling water flow to the control rods, d.
The piston and the large slotted vents along the length of the rod barrel prevent excessive rod speeds during accidaqtal roa drops while allowing unrestricted normal rod drive speeds.
QUESTION (C.8)
[1.0)
Which one of the following is the MAXIMUM reactor pool level decrease that could occur from a large failure of the prirnary water system piping?
a.
5 inches b.
15 inches c.
36 inches d.
48 inches QUESTION (C.g)
[1.0)
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 b.
Provides a means for manually adjusting rod position by pulling rod out.
l c.
Provides rod bottom ind; cation.
d.
Automatically engages the control rod on a pull signal.
l
Section C: Plant and Rad Monitorina Svstems Page 18 QUESTION (C.10) (1.0)
Which One of the following describes the action of the rod control system to drive the magnet drew tube down after a dropped rod?
a.
Deenergizing the rod magnet inRiates the rod down motion of the draw tube, b.
Actuation of the MAGNET DOWN limit switch inRiates thw 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 th') scram signal initiates the rod down motion of the draw tube.
QUESTION (C.11) [1.0)
While performing a Startup Checklist after a reactor scram it is noted the reg rod motor carriage is one half way out of the core, but the rod is fullin. Which one of the following is the cause of this?
a.
A loss of voltege scram occurred which does not reset the reg rod.
b.
A manual scram was initiated which does not reset the reg rod, c.
Reactor control was left in manual.
d.
Reactor control was left in automatic.
QUESTION (C.12) [1.0)
Which One of the following sanges of nuclear instrumentation utilizes an uncompensated ion chamber as the neutron detection device?
a.
Count Rate channel b.
Log N channel c.
Linear Power channel d.
% Power channel
,,3,
MN C: Plant and Pad MonMorina Svatema Page1g QUESTION (C.13)
[1.0)
Which one of the following is the MAXIMUM length of time that the emergency lights are able to produce light?
a.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, b.
3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
c.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
d.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
QUESTION (C.14)
[1.0)
In what region of the Pulst Si e vs. Applied Vohage characteristic curve does the Count Rate t
Channel operate?
a.
Geiger Muller b.
Limited Proportionality c.
Proportional d.
lonizatien QUESTION (C.15) -[1.0)
Which one of the following does not provide any protective interlocks or actions?
a.
Linear Power Channel.
b.
Log Power (Log-N Channel).
c.
Percent Power Channel.
d.
Count Rate Channel.
n
.~
.. - - - ~. _
r Section C: Plant and Rad Monitorhg Syntama Page 20 QUESTION (C.16) [1.0)
Which one of the choices below completes the following statement?
'The control servo will increase reactor power at a constant period of
. based on the reactor power detected by the a.
+30 se:onds; log-n channel b.
+30 seconds; linear channel c.
+10 seconds; log n channel d.
+10 seconds; linear channel QUESTION (C.17) [1.0)
Which one of the following will result in a reactor scram signal?
a.
Count rate channel produces a 3 second period signal.
b.
Linear micromicroammeter channel exceeds 100% on its lowest range.
c.
Log n channel exceeds 110% of full power.
d.
Bulk reactor water temperature monitor axceeds 120 degrees F.
QUESTION (C.18) [2.0)
Match the fadlity 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
Section C: Plant and Rad Monitorina S atoms Page 21 f
QUESTION (C.19)
[1.0)
A release has occurred in the facility. A check of the Geseous Stack Monitor reveals a red jeweled light on the front of the monMor readout is illuminated. Which of the following is the nignificance of this red light?
a.
The air confinement system is activated.
b.
The detector has failed.
c.
The failsafe is activated, d.
The air confinement system is shutdown.
l l
gestion k a Theory. Thermo & Fac. aaaratina Charactenstics Page 1 ANSWEA (A.1)
[1.0) c REFERENCE At 20 feet, all measured radiation is from gammas.
D, r,8 = Do,'
D, (1)' = 0.1 mr (20)'
D, = 40 mrom/hr gamma r
Ratio of beta to total = 1 -(40/200) = 80%
ANSWER (A.2)
[1.0) b HEFERENCE A = A, e*
A =.693/T2 in(A/A.) =.693tfT2 T2 =.693thn 0.8 = 75 hr ANSWER (A.3)
[1.0) d REFERENCE Bum, R., Introduction to Nuclear Reactor Operations, @ 1988 pg. 3 4 ANSWER (A.4)
[1.0) a REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, C 1982, 9 4.2, p. 4 1.
ANSWER (A.5)
[1.0) a REFERENCE Bum, R., Introduction to Nuclear Reactor Operations, C 1988, 9 3.3, pp. 3 319 ANSWER (A.6)
[1.0) b REFERENCE P = P,e$i 10 = 1e*'
In 10 = 60/T 2.3 = 60/T T = 60/2.3 T = 26 seconds ANSWER (A.7)
[1.0) c
' REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, C 1982, 9 5.2 (b), p. 5-4.
ANSWER (A.8)
[1.0) c REFERENCE CR /CR,= (1 Ken,)/(1 Ke#,)
i 15/45= (1 ken,/(10.95) = (0.05)(0.3333)= 1 Ken, ken,* 1 0.016665= 0.983
-=__-.- -
Rae' inn A* a Theory. Thermo & Fac. nanratina Charmeenristica Page 2 ANSWER (A.9)
[1.0) d REFERENCE Bum, R., /ntroduction to Nucker Reactor Operations, C 1986, f9 4.5.
ANSWER (A.10)
[1.0) e REFERENCE Bum, R., Introduction to Nuclear Reactor Operations, O 1982, t 4.6, p. 416.
ANSWER (A.11)
[1.0) a REFERENCE Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Mr'-her.
Florida, 1991, $$ 3.161 - 3.163, pp.191 - 192.
ANSWER (A.12)
[1.0) d REFERENCE RRF Training Manual pg.10-6 ANSWER (A.13)
[1.0) b REFERENCE The reactor is shutdown by $5.36 - $3.85 = 51.51 after safety rod withdrawal.
CR,= CR, (1 - keff), / (1 - keff),
K,= 1/1 p where p=$ x p K,= 1/1-(5.36 x 0.0075)
K = 1/1-(1.51 x 0.0075)
CR, = CR,l1 1 11/1-f 5 36 x 0.0075)1 }
= 3643 cpm 1 -[1/1-(1.51 x 0.0075)) i ANSWER (A.14)
[1.0) b REFERENCE Lamarsh, J.R., /ntroduction to Nuclear Engineering, Add; son Wesley Publishing, Reading, Massachusetts,1983. $
Burn, R., Introduction to Nuclear Reactor Operations, C 1982, 9 3.3, pp. 3 3-18.
ANSWER (A.15)
[1.0) d REFERENCE Burn, R., introduction to Nuclear Reactor Operations, C 1988, 9 7.2 & 7.3, pp. 7 7 9.
A" T A "~# - p Id U "
p = 0.0075/((0.1
- 60) + 1) = 0.0075/7 p = 1.07 x 10'8 detta k/k p/ inch = 1.07 t 10-8 delta k/k/2 in = 5.4 x 104 detta k/k per inch.
l TaRGiion A: R Theory Thermo & Fac. ooeratina Characteristics Page 3 ANSWER (A.16)
[1.0) o REFERENCE Lamarsh, J.R., Introduction to Nuclear Engineering, Addison Wesley Publishing, Reading, Massachusetts, 1983. $ 7.1, pp. 280 - 284.
ANSWER (A.17)
[1.0) a REFERENCE RRF Training Manual Section 10.5 ANSWER (A.18)
[1.0) b REFERENCE RRF Training Manual Sect.10.2 ANSWER (A.19)
[10) a REFERENCE This is due to the fact that there is a buildup factor (1 - e") involving the dscay constant for the nuclide.
Reed Training Manual, Page 6-18 ANSWER (A.20)
[1.0) b REFERENCE Lamarsh, J.R., Introduction to Nuclear Engineering, Addison Wesley Publishing, Reading, Massachusetts, 1983. $ 7.2, p. 303.
RRF SOP-43 S
Sect}on B Normal /Emera. Procedures & Rad Con Page 4 ANSWER (B.1)
[1.0) c REFERENCE 10CFR20 Whole Body Limit = 5 R T6me = [(5 R - 1.25 R) / 0.075 R/hr) = 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> ANSWER (B.2)
[1.0)
DELETED b
REFERENCE two inches = one hatf thickness (Tw). Using 3 hatf-thickness will drop the dose by a factor of
(%)'= %.
100/8 = 12.5 ANSWER (B.3)
[1.0) 1.d.
2.h.
3.h.
4.a.
REFERENCE 10CFR55 ANSWER (B.4)
[1.0) b REFERENCE 10CFR20 ANSWER (B.5)
(1.0)
C REFERENCE GM is not sensit!ve to energy.
ANSWER (B.6)
[1.0) a REFERENCE Health Phistes Handbook pg. 5 20 ANSWER (B.7)
[1.0) b
- REFERENCE R=6CEn R = 6 (200 ci) (1.10 + 1,29 MeV) (1 disintegration) = 2868 R/hr ANSWER (B.8)
[1.0) b REFERENCE RRF T.S. J.4
Sectiori B. Normal /Emerg. Procedures & Rad Con Page 5 ANSWER (B.9)
[1.0) c REFERENCE RRF-AP 11 ANSWER (B.10)
[1.0) d REFERENCE SOP 01, Stari-up Checklist ANSWER (B.11)
[1.0) a REFERENCE 10 CFR 50.54 (g); 10 CFR 50.59; 10 CFR 55.59 RRF 1990 RO Pequalification Exam ANSWER (B.12)
[1.0) a REFERENCE RRF AP 10; 3.1.2 ANSWER (B.13)
[1.0) a REFERENCE SOP 33, page 4.
ANSWER (B.14)
[1.0) a REFERENCE RRF EPlan 7; Definitions ANSWER (B.15)
[1.0) b REFERENCE RRF EPlan - Organization and Responsibilities ANSWER (B.16)
[1.0)
C REFERENCE RRF EPlan Section 3.5, pg 14, and Section 7.2, pg 21 ANSWER (B.17)
[1.0) b REFERENCE RRF EPlan Section 4.2, pg.15
Rection B: Normal /Emera. Procedures & Rad Con Page 6 ANSWER (B.18)
[1.0) b REFERENCE RRF EPlan, pgs 1516 ANSWER (B.19)
[1.0) c REFERENCE RRF ElP-10 / SOP 01 Sect.1.7.1.7 ANSWER (B.20)
[1.0) d REFERENCE SOP 28 Radiation Work PermMs W
,,w-~
a-n r,
,- s
,- - ~., - -.
.-r-
= - - - - _. - _ -. -
[
i Baqtion C: Plant and Rad Monlioring Systems Page 7 ANSWER (C.1)
[1.0) j b
REFERENCE Glasstone, S. and Sesonske, A NuclearReactor Engineering, Kreiger Publishing, Malabar, Fkrida, 1991, $$ 9.137 - 9.153, pp. 605 - 608.
i ANSWER (C.2)
[1.0) d
REFERENCE:
Reed SAR, page 5-3 ANSWER (C.3)
[1.0) b REFERENCE Reed Mech Maint and Operating Manual, page 37 ANSWER (C.4)
[1.0) a
REFERENCE:
Reed SAR, page 4 5 ANSWER (C.5)
[1.0) b REFERENCE SOP 90.7.2
+
ANSWER (C.8)
[1.0) e REFERENCE Reed Facility License, Section 2.
ANSWER (C.7)
[1.0) b REFERENCE SAR, Section 5.2.8, pg 511 ANSWER (C.8)
[1.0) c REFERENCE Reed Mech. Maint. and Operating Manual, Section 5.11.10, page 85
- ANSWER (C.9)
[1.0) e REFERENCE RRF SAR (pg 5-8 thru 5-12)
?
~
~ - - -, _., _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _
_ ~ _. _. _ _. _ _
Badion C: Nant and Rad Monkoring Syaiems Page 8 ANSWER (C.10)
[1.0) c REFERENCE GA TRIGA Moch Maint, & Operating Manual ANSWER (C.11)
[1,3) d REFERENCE Reed 1991 RO Requal exam, ANSWER (C.12)
[1.0) d REFERENCE GA TRIGA Inst. Maint. Manual ANSWER (C.13)
[1.0) c REFERENCE Reed, ElP 10, Attachment B.
ANSWER (C.14)
[1.0)
C i
REFERENCE-RRF Training Manual pg. 5 8 ANSWER (C.15)
[1.0) b REFERENCE Reed,3AR, page 5-14 l
ANSWER (C.16)
[1.0) b REFERENCE SAR Section 5.3.2. pg 514 ANSWER (C.17)
[1.0) b REFERENCE SAR Section 5.3.2 and 5.3.4, pg 5-14 and 5-16 ANSWER (C.18)
[2.0) e,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 (C.1g)
[1.0) s.
REFERENCE NRC Exam administered on 1/94
- ~
_ -