ML20058C638
| ML20058C638 | |
| Person / Time | |
|---|---|
| Site: | Reed College |
| Issue date: | 03/19/1993 |
| From: | Caldwell J, Isaac P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058C618 | List: |
| References | |
| 50-288-OL-93-01, 50-288-OL-93-1, NUDOCS 9312020517 | |
| Download: ML20058C638 (71) | |
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ENCLOSURE 1 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT l
REPORT NO.:
50-288/0L-93-01 FACILITY DOCKET NO.:
50-288 FACILITY LICENSE NO.:
R-ll2 FACILITY:
REED REACTOR FACILITY EXAMINATION DATES:
January 25-27, 1993 EXAMINER:
PatrickA. Isaac, (Chief Examiner)
[uCI
[ fxami,ner, Date SUBMITTED BY:
o-Chie APPROVED BY:
4R0/3 k/kb
. "Caldwejl, 4tiief Dat'e No -Power Reattor Section 0 erator Licensing Branch D vision of Reactor Controls and Human Factors Office of Nuclear Reactor Regulation
SUMMARY
NRC administered a written examination retake of section C to one Reactor Operator (RO) applicant.
Initial written examination and operating tests were administered to four R0 applicants. Operating tests were also administered to one Senior Reactor Operator (SR00) Applicant. All applicants passed the applicable portions of the examination and have been issued the appropriate licenses.
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9312O20517 930322 PDR ADOCK 05000288 V
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' REPORT DETAILS l
1.
Examiner:
Patrick J. Isaac, Chief Examiner I
l 2.
Examination Results:
R0 SR0 TOTAL (Pass / Fail)
(Pass / Fail)
(Pass / Fail)
E 5/0 1/0 6/0 3.
Written Examination:
i The written examination was administered on January 25, 1993 to four R0 candidates. A retake of section C was administered to another R0 candidate.
i' At the conclusion of the examination, the Chief Examiner immediately secured the master examination answer key and all of the candidate answer sheets.
A copy of the master "as given" examination with answer key was forwarded to the licensee's training staff for their formal review.
i The facilities written examination comments and the NRC's resolution to those comments are found in Enclosure 2.
i All five RO applicants passed the applicable portions of the written examination.
4.
Operatina Tests:
l Operating Tests were administered on January 26 and 27, 1993 to 4 R0 and 1 SROU candidates. All the candidates passed this portion of the examination.
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Exit Meetina:
.i Personnel attending:
i Michael Pollock, Director, Reed Reactor Facility Patrick J. Isaac, HRC
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NRC thanked Mr. Pollock for his assistance in the administration of the examination.
l Mr. Isaac noted what he considered to be a generic deficiency in candidates' knowledge.
Several candidates were unable to describe the inputs to the " Loss of Hi Volts" scram and they displayed an unfamiliarity with the design, functions of controls of the console instrumentation as required by 10CFR55.41 (7) and 10CFR55.45 (4).
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ENCLOSURE 2 NRC RESOLUTIONS - WRITTEN EXAMINATION Question A. 006:
Which ONE of the following statements best defines "$1.00" (one dollar) worth of reactivity at the Reed Reactor Facility?
- a. It is equivalent to Beff = 0.0065 delta-K/K.
- b. It is equivalent to Beff = 1.00 delta-K/K.
- c. It is equivalent to Keff = 1.00 delta-K/K.
- d. It is equivalent to Keff = 0.0065 delta-K/K.
Answer A. 006:
a Reference A. 006:
Reed Training Manual, pages 12-5-13, 12-5-23 and 12-7-5 Facility Comment A. 006:
This is a poorly worded question which has two possible correct answers depending on what the examinee feels is the subject ("It") of the sentence in the answer.
If one reads answer (a) to say "The reactivity is equal to p,,, which is equal to 0.0065 delta-K/K" then (a) is the best answer as given in the key (Note however 235 that p for U is 0.0065, while p,,, for our reactor is assumed to be 0.0075--
reference: Facility Tech Specs, Section E.2).
However, answer (b) is correct if it read as "One Dollar is equivalent to p,,, equais reactivity which equals (1.00) del ta-K/K. "
Resolution:
Accept either (a) or (b).
NRC Resolution A. 006:
Comment accepted.
The answer key has been modified to accept both (a) or (b) as correct.
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Question A. 008:
t How does the Reed Reactor Antimony-Beryllium source produce neutrons?
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- c. Berylliam fissions emitting a gamma which interacts with i
Antimony to produce a neutron
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Answer A. 008:
a Reference A.
008:
Reed Training Manual, pages 12-1-7/-11 i
Facility Comment A. 008:
i The Reed Reactor Facility is licensed to use either an Americium-beryllium neutron source (the only one currently in use) or a plutonium beryllium source (which was only used for a couple of months in 1968).
Reference Facility License. We have never used an antimony-beryllium source, do not possess, and do not stress the operation of such a source in our training (though we do mention y,n sources.in
'l lecture and in the reference material cited in the exam key).
l Resolution: Accept the answer as given in the key (since it is the only one that makes sense);
in the future ask questions which relate to the americium-beryllium source with which our operators need to be iamiliar.
NRC Resolution A. 008:
Comment accepted. The question will be deleted from the question bank.
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i Ouestion A. 019:
If reactor power is increasing by a decade every minute, it has a period of:
- a. 13 sec i
- b. 26 sec
- c. 52 sec i
- d. 65 sec l
Answer A. 019:
b i
Reference A. 019:
I Reed Training Manual, Page 12-3-15.
Facility Comment A. 019:
The documentation referenced by the exam key (which I believe should read 12-1-15) does.not use the term " decade" and this term is not used in our training program.
Resolution: Accept the answer key as given (since anyone not understanding the question could have asked the examiner); in the future, define terms in the questions with which examinees may not be familiar.
NRC Resolution A. 019:
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The term " decade" is commonly used to refer to a group or set of 10. On page 5-14 l
of the Reed Reactor Facility Description, the word " decade" is used to describe the l
power indicating range of the count-rate and linear microammeter channels. Since none of the examinees questioned the usage of the word " decade", it is safe to l
assume that they understood the question.
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Question: B. 003 The reactor is at a steady power of 250 kw. As reactor operator, you are requested to increase reactor power to 275 kw for testing the full power safety circuits. Which ONE of the following is the correct response to the request in accordance with Technical Specifications l
(T.S.)?
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- a. Deny the request as power cannot be increased greater than i
250 kw
- b. Comply with the request providing power is not increased above i
the 110% level.
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- c. Comply with the request providing power is not increased above 287.5 kw.
- d. Deny the request as power cannot be increased greater than 262.5 kw.
Answer B. 003:
c Reference B. 003:
Reed Technical Specifications, Section A.2, page 1 l
Facility Comment B. 003:
s We have commented several times in the past about this question, which should be a good one, but which (as worded) appears to be a trick question and may penalize an examinee for an error which the NRC allowed to exist in many research reactor licenses for more than 20 years.
Specifically, we have been informed by the NRC that, regardless of what the Technical Specifications say, the License takes precedence and no operation above the licensed oower of 250 kW is permitted for any reason. The answer to the question as worded is (c); the correct action is (a).
1 Resolution: Accept either (a) or (c) on this exam and then remove the question from the question bank for future exams.
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NRC Resolution B. 003:
Comment not accepted. As stated in the facility's comment, the correct answer to the question, as worded, is (c). The intent of this question was to test the i
candidates' understanding of the difference between the License allowed power level of 250 kW and the TS allowed power level of 287.5 kW for testing.
NRR NPR Project Directorate has been made aware of the facility's comment and they will contact the facility for further resolutions.
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t Ouestion B. 021:
A reactor operator may be called upon to verify the proper labeling of a sealed container of radioactive materials being prepared for shipping.
The radiation levels to be recorded are the Maximum External Surface and Maximum Total dose rates.
i How far must the operator hold the detector probe from the container i
surface for these radiation measurements?
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- a. 5 centimeters
- b. 2 inches
- c. I foot t
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- d. I meter r
Answer B. 021:
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Reference 001:
Reed, SOP-54, Section 54.7.5.1, page 9 Facility Comment B 021:
The document reference in the answer key (SOP-54) requires that two measurements be
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made--1) The Maximum External Surface dose rate (measured at contact with the container); and 2) the Maximum Total dose at 3 feet (1 meter). The answer options given in the exam only give one distance.
Resolution: Accept the answer as given (since it is the only answer which is correct for either question);
reword for any future use or remove from the question bank.
NRC Resolution B. 021:
Comment accepted.
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Ouestion C. 008:
Which ONE of the following is the reason why pool water level must be maintained high enough to prevent the pool skimmer from sucking air?
- a. The reactor water system pumps will loose suction and fail.
- b. Depletion of demineralizer resin.
- c. Clogging water purification system filters.
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- d. Interfere with proper operation of the rabbit tube.
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Answer C. 008:
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Reference C. 008:
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Reed Mech. Maint. and Operations Manual, Section 5.11.3, page 81 Facility Comment C. 008:
The referenced document does state that allowing air to be sucked into the system will deplete the usefulness of the demineralizer resin. This is an unfortunate use of the word deplete since many chemists will read answer (b) to mean that the resin i
will no longer be able to accept ions due to loading (ie. it is " spent resin")
rather than that " channeling" of water through the resin would reduce its effectiveness (which is what is meant in the reference). As installed in our reactor answer (a) is also a correct answer.
Resolution: Accept either (a) or (b).
NRC Resolution C. 008:
Comment accepted. The answer key has been modified to accept either (a) or (b).
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9 Duestion C. 012:
4 Which ONE of the following indicates only ALL places where the evacuation j
alarm can be seen or heard?
- a. Buzzer in the control room and reactor bay.
- b. Buzzer in the reactor bay and a light in radiochem lab.
- c. Buzzer in the reactor bay, rabbit cage, radiochem lab and a light in the radiochem lab.
- d. Buzzer in the control room, reactor bay, rabbit cage and a light in the radiochem lab.
Answer C. 012:
d Reference C. 012_;
Reed 50P-61 and 1990 Requal Exam, question II.6 Facility Comment C. 012:
This question is poorly worded and is confusing since it includes the phrase "only All places where the evacuation alarm can be seen or heard?"
In reality, the alarm can be heard everywhere in the facility including more locations than are given in (d), but-there is no buzzer in the control room (there is a control room switch to temporarily silence all buzzers).
Resolution: Accept answer given in key, but reword or remove from the exam question bank.
NRC Resolution C. 012:
l Due to the extensive remodeling of the old chemistry building, the Reed Reactor i
facility no longer has a rabbit cage or a radiochem lab.
This question, therefore, is no longer relevant to the facility and will be deleted from this exam and will not be added to the question bank.
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l Ouestion C. 015:
1 Which ONE of the following requires the supervisor to be notified of an out of tolerance pressure for the instrument air system while perf orming SOP-70, Completing the Weekly Checklist?
- a. 15 psi line pressure.
- b. 20 psi line pressure.
- c. 55 psi compressor pressure
- d. 75 psi compressor pressure.
I Answer C. 015:
a Reference 001:
Reed 50P-70, Section 70.7.8, page 5 Facility Comment C. 015:
The answer given in the key is correct as given in the 50P.
However, on a recent test of the system, it was determined that the line pressure needs to exceed 23 psi for proper operation of one of the dampers and the system was red-tagged to the effect at the time of the exam.
Following completion of maintenance and testing on the system, which was scheduled for early January but postponed until after the NRC exams due to time constraints, the S0P will be adjusted to correspond with the actual required pressure.
RESOLUTION: Accept either (a) or (b).
NRC Resolution C. 015:
I Comment accepted. The answer key has been modified to accept either (a) or (b).
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5 Ouestion C. 016:
Which ONE of the following is the normal reading and alarm setpoint for the Particulate Stack Monitor?
Normal Alarm a.
0.1 mr/hr 5 mr/hr b.
100 cpm 115 cpm c.
150 cpm 1500 cpm d.
400 cpm 2000 cpm Answer C. 016:
c Reference 001:
Reed Emergency Implementation Procedures, appendix D, page 15 Facility Comment C. 016:
1 We have commented on this question before and, while we realize that examiners are supposed to ask about normal readings and alarm setpoints, it is a very difficult question to write. We are required by a separate branch of NRC to have " typical" values for these parameters in our Emergency Procedures (which is the referenced document) for use if the actual values are not available during an emergency.
However the alarm values may change whenever a detector fails and is replaced or the system is calibrated (we post the alarms levels on the instrument for use during daily testing--reference 50P-01 and 32). The " normal" reading changes daily as radon levels change. Thus examinees are confronted with a dilemma of needing to know both the actual values with which they deal every day and the " typical" values which appear in the Emergency Procedures.
Both (c) and (d) represent values which would be reasonable for these parameters and the true values at the time of the exam were, in fact, higher than those given in (d)
Resolution: Accept either (c) or (d).
In the future may we suggest that the examiner leave the answer options to such a question blank and complete them at the facility on the day of the exam, t
NRC Resolution C. 016:
Comment accepted. The answer key has been modified to accept either (c) or (d).
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ENCLOSURE 3 i
I U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
Reed Inst.
REACTOR TYPE:
TRIGA DATE ADMINISTERED: 93/01/25 REGION:
5 CANDIDATE:
I LICENSE APPLIED FOR:
INSTRUCTIONS TO CANDIDATE Answers are to be written on the answer sheet provided. Attach any answer sheets to the examination. A 70% in each section is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 33.30 A.
REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 1
21.00 35.00 B.
NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL
(
CONTROLS 19.00 31.70 C.
PLANT AND RADIATION MONITORING SYSTEMS 60.00 TOTALS
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FINAL GRADE All work done on this examination is my own.
I have neither given nor received aid.
Candidate's Signature
4 A.
RX THEORY, THERM 0 & FAC OP CHARS Page 2 1
ANSWER SHEET Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
MULTIPLE CHOICE 001 a
b c
d 002 a
b c
d 003 a
b c
d 004 a
b c
d 4
005 a
b c
d 006 a
b c
d 007 a
b c
d 008 a
b c
d 009 a
b c
d 010 a
b c
d 011 a
b c
d 012 a
b c
d 013 a
b c
d 014 a
b c
d 015 a
b c
d 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 *****)
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NORMAL /EMERG PROCEDURES & RAD CON Page 3 D
i ANSWER SHEET Multiple Choice (Circle or X your choice) 1 If you change your answer, write your selection in the blank.
MULTIPLE CHOICE 001 a
b c
d t
002 a
b c
d 003 a
b c
d i
004 a
b c
d 005 a
b c
d 006 a
b c
d 007 a
b c
d l
008 a
b c
d 1
009 a
b c
d 010 a
b c
d 011 a
b c
d 012 a
b c
d f
013 a
b c
d 014 a
b c
d 015 a
b c
d i
016 a
b c
d l
I 017 a
b c
d i
018 a
b c
d r
019 a
b c
d 020 a
b c
d 021 a
b c
d i
(***** END OF CATEGORY B *****)
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s C.
PLANT AND RAD MONITORING SYSTEMS Page 4 ANSWER SHEET Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
MULTIPLE CH0 ICE 001 a
b c
d 002 a
b c
d 003 a
b c
d i
004 a
b c
d 005 a
b c
d 006 a
b c
d 007 a
b c
d 008 a
b c
d 009 a
b c
d 010 a
b c
d 011 a
b c
d 012 a
b c
d 013 a
b c
d 014 a
b c
d 015 a
b c
d 016 a
b c
d 017 a
b c
d 018 a
b c
d 019 a
b c
d i
020 a
b c
d
(***** END OF CATEGORY C *****)
(********** END OF EXAMINATION **********)
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
- l. 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 not received or 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 corner of the examination cover sheet.
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- 6. Fill in the date on the cover sheet of the examination (if necessary).
- 7. The point value for each question is indicated in parentheses after the question. The amount of blank space on an examination question page is NOT an indication of the depth of answer required.
- 8. If the intent of a question is unclear, ask questions of the examiner only.
- 9. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets.
In addition, turn in all scrap paper.
- 10. To pass the examination, you must achieve at least 70% in each category.
- 11. There is a time limit of (3) hours for completion of the examination.
- 12. When you are done and have turned in your examination, leave the examin-ation area as defined by the examiner.
If you are found in this area i
while the examination is still in progress, your license may be' denied or revoked.
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A.
RX THEORY, THERM 0 & FAC OP CHARS Paga 7 QUESTION: 001 (1.00)
'Which ONE of the following is a correct statement concerning the factors i
affecting control rod worth?
- a. Fuel burn up causes the rod worth for periphery rods to decrease.
- b. Fuel burn up causes the rod worth to increase in the center of the core.
- c. The withdrawal of a rod causes the rod worth of the remaining inserted rods to increase.
- d. As Rx power increases rod worth increases by a factor of e.
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i QUESTION: 002 (1.00)
Using the following reactivity worths, calculate the Shutdown Reactivity with the Shim rod stuck all the way out.
Safety and Shim Rods:
$4.25 each Regulating Rod:
$1.75 Core excess reactivity:
$2.5
- a. $0.75
- b. $3.50 i
- c. $6.00
- d. $7.75 i
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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RX THEORY, THERM 0 & FAC OP CHARS Page 8 QUESTION: 003 (1.00)
Which of the following are the two most important properties of a good moderator?
- a. Low elastic scattering and low neutron capture cross sections
- b. High elastic scattering and high neutron capture cross sections
- c. High elastic scattering and low neutron capture cross sections
- d. Low elastic scattering and high neutron capture cross sections QUESTION: 004 (1.00)
Which ONE of the following are the three materials that are 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
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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RX THEORY, THERM 0 & FAC OP CHARS Page 9 i
QUESTION: 005 (1.00) l l
The reactor is shutdown after an extended, two week, high power run at 200 kilowatts.
1 Which ONE of the following is the time it takes for the MAXIMUM Xenon i
concentration to be achieved?
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- a. O to I hours
- b. 2 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
- c. 8 to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
- d. 18 to 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> i
QUESTION: 006 (1.00)
Which ONE of the following statements best defines "$1.00" (one dollar)
{
worth of reactivity at the Reed Reactor Facility?
- a. It is equivalent to Beff = 0.0065 delta-K/K.
- b. It is equivalent to Beff - 1.00 delta-K/K.
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- c. It is equivalent to Keff - 1.00 delta-K/K.
- d. It is equivalent to Keff = 0.0065 delta-K/K.
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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RX THEORV, THERM 0 & FAC OP CHARS Page 10 i
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QUESTION: 007 (1.00)
Which ONE of the following describes " CORE EXCESS"?
- a. Extra reactivity into the core due to the presence of the source neutrons.
- b. A measure of the resultant reactivity if all of the control rods and 1
other poisons were removed.
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- c. The combined reactivity worth of control rods and chemical poison needed to keep the reactor shutdown.
- d. The maximum reactivity insertion with the reactor shutdown with control rods fully inserted under peak Xenon conditions.
i QUESTION: 008 {1.00)
How does the Reed Reactor Antimony-Beryllium source produce neutrons?
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- a. Antimony decays emitting a gamma ray which interacts with l
Beryllium to produce a neutron.
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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RX THEORY, THERM 0 & FAC OP CHARS Page 11 l
r QUESTION: 009 (1.00)
On a rapid power level increase, the Prompt Negative Temp. Coefficient l
(PNTC) causes:
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- a. The hydrogen atoms in the ZrH2 to add energy to the neutrons, increasing their leakage.
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- b. 2380 to absorb neutrons over a narrower range, thus increasing the i
number of neutrons available for fission with 235U.
- c. Doppler resonance effects to decrease.
- d. The water density to decrease, causing the neutron resonance l
escape probability (p) to decrease.
l QUESTION: 010 (1.00)
Which ONE of the following is the type of heat transfer taking place from the fuel cladding surface to the reactor upper pool when the l
reactor is operating at steady state 200 kW?
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- a. Conduction
- b. Film boiling l
- c. Convection I
- d. Nucleate boiling i
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A.
RX THE0RV, THERM 0 & FAC OP CHARS Page 12 i
l QUESTION: 011 (1.00) j Which ONE of the following is correct for a " THERMAL NEUTRON 7" l
- a. A neutron at fast energy levels that causes fission to occur in Pu-240 or U-238.
- b. A neutron at resonant epithermal energy levels that causes fission to occur in Pu-240 or U-238.
- c. The primary source of thermal energy increase in the reactor i
core during reactor operation.
- d. A neutron that experiences no net change in energy after several i
collisions with atoms of the moderator, t
QUESTION: 012 (1.00) i Which ONE of the following is the reason for the 80 second period following l
Rx scram?
- a. U-235 affinity for source neutrons.
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- b. Fuel temp. coefficient adding positive reactivity.
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- c. Amount of negative reactivity added on a scram exceeds the shutdown-f margin.
- d. Longest lived delayed neutrons precursors decay constant.
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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RX THEORY, THERM 0 & FAC OP CHARS Page 13 i
1 QUESTION: 013 (1.00)
Which ONE of the following describes an undermoderated reactor?
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- a. Reducing the amount of moderation will cause a positive i
reactivity response.
- b. As temperature increases, slow neutrons will slow down in a collision with zirconium hydride.
- d. Decreasing core water density will produce a negative reactivity I
response.
j QUESTION: 014 (1.00)
A reactor is subcritical with a shutdown margin of.0526 delta k.
The
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addition of a reactor experiment increases the indicated count rate from 10 cps to 20 cps.
t Which ONE of the following is the new Keff of the reactor?
a.
53 b.
90
[
t c.
975 i
- d. 1.02 e
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
. RX THEORY, THERM 0 & FAC OP CHARS Page 14 A
i QUESTION: 015 (1.00)
The reactor is operating at 200 kw with the reactor power level trip incorrectly set for 125% full power. A reactivity excursion creates a i
stable reactor period of 500 milliseconds.
The reactor scrams with a control element (scram delay) time of 0.25 seconds.
Which one of the following is the maximum peak power reached from the transient?
(Assume no temperature or void effects and the rower peaks and turns instantaneously after a complete rod drop.)
- a. 315 kw
- b. 328 kw i
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- c. 410 kw
- d. 515 kw j
QUESTION: 016 (1.00)
Which ONE of the following statements describes why the fuel element moderator contributes to a " prompt" negative fuel Temperature Coefficient?
- a. Samarium build up causes the insertion of negative reactivity at higher fuel temperatures.
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- b. As fuel temperatures increases, the thermal neutron energy distribution shifts to a higher level.
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- c. As fuel temperatures increases, tne thermal neutron energy distribution shifts to a lower level.
- d. As fuel temperature increases, Zirconium Hydride causes the escape probability to decrease.
(***** CATEGORY A CONTINUED ON HEXT FACE **'+*)
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RX THEORY, THERM 0 &'FAC OP CHARS Page 15 l
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I QUESTION: 017 (1.00) l i
Which ONE of the following describes how doubling the time a target i
nuclide is irradiated affects the activity level.
i
- a. Less than doubles the activity.
- b. More than doubles the activity.
t
- c. Exactly doubles the activity.
- d. Increases the activity by a factor of e.
1 e
QUESTION: 018 (1.00)
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 l
the longer generation time?
l i
- a. Delayed neutrons have shorter half-lives.
l 1
- b. Delayed neutrons thermalize slower.
- c. The escape probability for delayed neutrons is higher.
i
- d. Delayed neutrons are not a product of primary fission.
[
QUESTION: 019 (1.00) l If reactor power is increasing by a decade every minute, it has a period of:
- a. 13 sec l
- b. 26 see i
- c. 52 set i
- d. 65 sec
\\
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' A.
RX THEORY, THERM 0 & 7AC OP CHARS Page 16 i
I QUESTION: 020 (1.00) l Why were burnable poisons added to the reactor core during initial core loading?
- a. Shapes the fast neutron flux for maximum specimen irradiation capability.
- b. Reduces the secondary isotopic radiation effects from irradiated control rods.
s
- c. Shapes the thermal neutron flux for maximum specimen irradiation capability.
- d. Increases the availability of usable nuclear fuel with the
.t existing control rod design.
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(***** END OF CATEGORY A *****)
P s..,
-n-y.
e.
~
B.
NORMAL /EMERG PROCEDURES & RAD CON Page 17'
[
QUESTION: 001 (1.00)
{
Which ONE of the following does NOT require NRC approval for changes?
i f
- a. License
- b. Emergency Implementation Procedures
- c. Requalification Plan
{
- d. Emergency Plan i
I QUESTION: 002 (1.00)
As defined by Technical Specifications, which ONE of the following statements is NOT a definition for a shutdown reactor.
=
- a. The minimum shutdown margin, with the most reactive of the operable control elements withdrawn shall be 0.6 delta K/K.
- b. The console key is in the "0FF position and the key is removed
[
from the console and under the control of a licensed operator.
}
i
- c. Sufficient control rods are inserted so as to assure the reactor is subcritical by a margin greater than 0.7 delta K/K cold
.i j
without Xenon.
i
- d. No work is in progress involving fuel handling or refueling i
operations or maintenance of its control mechanisms.
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
j
B.
NORMAL /EMERG PROCEDURES & RAD CON Page 18 i
i QUESTION: 003 (1.00)
)
The reactor is at a steady power of 250 kw.
As reactor operator, you are requested to increase reactor power to 275 kw for testing the full power safety circuits. Which ONE of the following is the correct response to the request in accordance with Technical Specifications (T.S.)?
I
- a. Deny the request as power cannot be increased greater than l
250 kw
- b. Comply with the request providing power is not increased above the 110% level.
- c. Comply with the request providing power is not increased above 287.5 kw.
i
- d. Deny the request as power cannot be increased greater than i
262.5 kw.
t P
QUESTION: 004 (1.00) i Which ONE of the following scrams is NOT required by Technical Specifications?
- a. Linear channel
- b. Percent Power channel
- c. Manual
- d. Period I
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
i e
I
-i B.
NORMAL /EMERG PROCEDURES & RAD CON Page 19
[
I
. QUESTION: 005 (1.00)
Which ONE of the following is the dosimetry described in the following sentence?
j
" Direct reading with the detection system consisting of a small quartz-fiber electroscope."
l
- a. TLD
- b. Pocket Dosimeter i
- c. Cutie Pie i
- d. Film Badge i
QUESTION: 006 (1.00) 10CFR20, part 20.105, specifies two dose limits that an individual may l
not exceed if continuously present in an " unrestricted area."
Which ONE of the following completes the paragraph following in i
accordance with the limits stated in 10CFR20.1057
{
?
Radiation levels which, if an individual were continuously present in
[
the area would not receive a dose in excess of mrems in any l
hour (s) or mrem (s) in any consecutive days.
i i
- a. 2, 1, 100, 7 i
- b. 1, 2, 100, 5
- c. 5, 1, 75, 7
- d. 2, 1, 100, 5 j
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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B.
NORMAL /EMERG PRCCEDURES & RAD CON Page_20 i
i QUESTION: 007 (1.00)
Which of the following instruments, used at Reed, is portable and used to detect extremely high ranges of beta-gamma radiation in an emergency situation?
- a. Eberline Model R0-2 l
- b. Victoreen CDV-715 Model IB t
- c. Ludlum Model 3
- d. Eberline Model E-140 i
i QUESTION: 008 (1.00)
You are assisting with an experiment in the reactor room working on the RAM 5 feet from a point source. The radiation field created by the i
d point source at the RAM is 100 mrem /hr.
If t'e point source is moved 2 feet further away, which ONE of the following is the new dose rate at the RAM?
- a. 31
- b. 51 l
i
- c. 71 l
=
o 140
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
I
B.
NORMAL /EMERG PROCEDURES & RAD CON Page 21 i
QUESTION: 009 (1.00)
How long can you remain in an area with a gamma dose rate of 3.5 R/hr i
without exceeding the 10CFR20 quarterly whole body limit?
- a. 21 minutes
- b. 28 minutes
- c. 36 minutes i
- d. 85 minutes l
QUESTION: 010 (1.00) j In accordance with Emergency Implementation Procedures, Appendix C, l
Evacuation of the facility, the first staff person using the exit corridor shall take the grab bag.
i Which ONE of the following has the ultimate responsibility to insure the i
bag has been taken?
- a. Emergency Coordinator.
- b. The Operator.
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- c. Senior Member of ENCL.
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- d. The first RRF management to arrive on site.
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
I
B.
NORMAL /EMERG PROCEDURES & RAD CON Page 22
?
QUESTION: 011 (1.00)
I You are standing on the north side of the reactor room when the evacuation alarm sounds.
Which ONE of the following is the evacuation path you should take in accordance with Emergency Implementation Procedures, Appendix C, i
Evacuation of the Facility.
b
- a. Exit corridor to Upper corridor of Chemistry building.
6
- b. Stairway to Upper corridor of the Chemistry building.
i
- c. Exit corridor.
i
- d. Emergency door, Northeast corner of reactor bay.
l QUESTION: 012 (1.00) f i
In the event of a pool level alarm and visual indication of abnormal loss of pool water, which ONE of the following actions is the reactor operator NOT allowed to perform if he is the Emergency Coordinator.
i t
- a. Shutdown the reactor i
- b. Isolate the Pool i
- c. Notify a member of the ENCL
- d. Terminate the emergency
(
I a
I
)
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Il
E B.
NORMAL /EMERG PROCEDURES & RAD CON Page 23
?
i QUESTION: 013 (1.00)
Prior to performing SOP-01, The Startup Checklist, how far back is the i
reactor operator required to review the Main Log?
j
- 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 /> or to the last log entry for that operator whichever i
occurs first,
- 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 operator whichever occurs first.
l
- d. To the last log entry for that operator.
i QUESTION: 014 (1.00)
If the width of the wipe taken is 1.0 inche, which one of the following is the wipe length that meets the minimum requirements of 50P-02, Health l
Physics Wipe Tests?
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- a. 20 inches.
- b. 15 inches.
i
- c. 10 inches.
i
)
- d. 5 inches.
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1
B.
NORMAL /EMERG PROCEDURES & RAD CON Page 24 i
i QUESTION: 015 (1.00)
In accordance with SOP-03, Startup and Core Excess Check, the reactor is brought to equilibrium at approximately 5 watts.
Which one of the following is the definition of equilibrium?
Steady Power within:
l
- a. +/- 0.1 watt with constant rod positions for 2 minutes.
- b. +/- 0.2 watt with constant rod positions for 1 minute.
I
- c. + 0.1, - 0.2 watts with constant rod portions for 2 minutes.
I
- d. + 0.2, - 0.1 watts with constant rod positions for 1 minute.
i 0
QUESTION: 016 (1.00)
The reactor is at constant power. The reactor operator is TEMPORARILY replaced for a short period of time.
Which ONE of the following is correct for the relief in accordance with SOP-04, Reactor Operations?
- a. A line entry in the main log.
- b. A full status stamp must be completed.
- c. A line entry in the main log for replacements up to I hour, a full status stamp for replacements greater than I hour.
- d. A partial status stamp for replacements up to I hour, a full status stamp for replacements greater than I hour.
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
i
i B.
NORMAL /EMERG PROCEDURES & RAD CON Page 25 1
I QUESTION: 017 (1.00) 1 Which ONE of the choices completes the following statement?
When making main log entries, fuel movements entries that are part of an experiment shall be logged in
, a source movement shall be logged in
, and green log entries are used for
- a. black underlined in red, red, all inadvertent scrams.
I
- b. black underlined in red, red, all scrams.
i
- c. red, black underlined with red, all scrams.
- d. red, black underlined with red, all inadvertent scrams.
?
QUESTION: 018 (1.00)
Which ONE of the following is considered MAJOR contamination?
- a. A wipe 1000 times above background.
- b. Contamination causing loss of one working week to the facility.
- c. Contamination causing greater than 1000 dollars damage.
- d. Any accident involving unsealed beta-gamma particulate.
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
i yr
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B.
NORMAL /EMERG PROCEDURES & RAD CON Page 26, QUESTION: 019 (1.00)
Which ONE of the rod configurations should be established initially to CALIBRATE the reg rod?
- a. Safety and reg rods completely withdrawn with shim rods withdrawn as necessary for 3 watts.
- b. Safety and shim rods withdrawn for 3 watts with the reg rod completely in.
- c. Shim and reg rods completely withdrawn with the safety rods withdrawn as necessary for 3 watts.
- d. Safety and shim rods completely withdrawn with the reg rod withdrawn as necessary for 3 watts.
1 QUESTION: 020 (1.00)
Which ONE of the following statements describes why radiation levels in the Reactor Bay may be elevated during performance of 50P-43, Power Calibration?
- a. Reactor will be operated at higher than normal power.
- b. The primary water system is not in operation.
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- c. The pool level is lower than normal.
J
- d. All rods are withdrawn from the core.
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B.
NORMAL /EMERG' PROCEDURES & RAD CON Page 27 l
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QUESTION: 021 (1.00) l A reactor operator may be called upon to verify the proper labeling of-a sealed container of radioactive materials being prepared for shipping.
The radiation levels to be recorded are the Maximum External Surface and Maximum Total dose rates.
How far must the operator hold the detector probe from the container surface for these radiation measurements?
- a. 5 centimeters
'i 4
- b. 2 inches
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- c. I foot
- d. I meter l
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(***** END OF CATEGORY B *****)
r
C.
PLANT AND RAD MONITORING SYSTEMS Page 28 i
i QUESTION: 001- (1.00) l What is the principal advantage of using plastic sample containers when irradiating specimens?
a.
plastic is highly resistive to gamma flux degradation.
l b.
the amount of radioactivity associated with the container upon i
removal from reactor is small.
s c.
embrittlement of plastic is minimal due to the low thermal neutron j
cross section of plastic.
5 d.
plastic is highly resistive to fast neutron degradation.
i QUESTION: 002 (1.00)
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 I
air through filters purging the room at 150 cfm.
l
- 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.
l
[
- d. The exhaust system will automatically stop, dampers will direct air through filters purging the room at 150 cfm.
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(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
3 l
C.'
~ PLANT AND RAD MONITORING SYSTEMS Page 29 l
QUESTION: 003 (1.00)
Which ONE of the following completes the following statement?
The f~el in the Reed reactor is a mixture of l
uranium-hydride alloy containing
% by weight of uranium enriched to i
- a. heterogeneous, graphite, 20, 8.5
- b. heterogeneous, zirconium, 8.5, 20
- c. homogeneous, graphite, 20, 8.5
{
- d. homogeneous, zirconium, 8.5, 20 i
4 QUESTION: 004 (1.00)
Limit switches mounted on each drive assembly provide switching for 4
console lights.
i Which ONE of the following statements is FALSE 7
- a. The DOWN light. indicates 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 I
their upper limits.
- c. The CONT side light of CONT /0N switch goes off less than one second after a scram occurs.
- d. When the CONT /0N pushbuttons are depressed, the ON lights are extinguished.
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I i
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C.
PLANT AND RAD MONITORING SYSTEMS Page 30 i
QUESTION: 005 (1.00)
Which ONE of the following statements is correct for the Linear Power Range Channel?
- a. Provides input to the automatic reactor control circuit.
- b. Uses an uncompensated ion chamber.
- c. Covers the entire power spectrum without switching.
- d. Produces a voltage signal proportional to the logarithm of neutron flux.
QUESTION: 006 (1.00)
Which ONE of the following interlocks will stop withdrawal of control rods?
- a. Automatic control selected following two watts on the log-n
- channel,
- b. Less than two counts per second on the startup channel.
- c. A period less than 2 seconds.
i
- d. Loss of one out of three signals to automatic reactor control.
P
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3 P
C.
PLANT AND RAD MONITORING SYSTEMS Page 31 4
QUESTION: 007 (1.00)
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 turns 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 signal is 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 E0B (End of Bombardment).
QUESTION: 008 (1.00)
Which ONE of the following is the reason why pool water level must be maintained high enough to prevent the pool skimmer from sucking air?
- a. The-reactorwatesystem-pumps-wi1Hoosemetion76d~fitt
{
- b. Depleticrc of d ine C 6 hnel.-S o o c. < r 4Hru. /
- c. Clogging water purification system filters.
- d. Interfere with proper operation of the rabbit tube.
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
C.
PLANT AND RAD MONITORING SYSTEMS Page 32 QUESTION: 009 (1.00)
Which ONE of the following is the MAXIMUM reactor pool level decrease that could occur from a large failure of the primary water system piping?
- a. 5 inches
- b. 12 inches
- c. 36 inches
- d. 48 inches QUESTION: 010 (1.00)
What part of the control rod drive assembly generates remote rod position indication?
i
- a. Draw tube
- b. Potentiometer l
- c. Armature i
- d. Electromagnet i
QUESTION: 011 (1.00) l What assembly component provides a "stop" command signal to the rod j
drive mechanisms at both the top and bottom of rod travel?
- b. Electromagnet
- c. Pinion
- d. Limit switches i
i
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
h C.
PLANT AND RAD MONITORING SYSTEMS Page 33 QUESTION: 012 (1.00)
[)[Illi7'E'/)
Which ONE of the following indicates only ALL places where the evacuation alarm can be seen or heard?
- a. Buzzer in the control room and reactor bay.
- b. Buzzer in the reactor bay and a light in radiochem lab.
- c. Buzzer in the reactor bay, rabbit cage, radiochem lab and a light in the radiochem lab.
- d. Buzzer in the control room, reactor bay, rabbit tage and a light in the radiochem lab.
QUESTION: 013 (1.00)
Which ONE of the following is the reason why the secondary low pressure alarm sounds at 40 psi ?
- a. To ensure that secondary system pressure is not less than primary system pressure.
- b. To alert the operator of possible damage to the secondary pump.
I
- c. To warn the operator of a loss of heat sink due to fouling of the heat exchanger.
- d. To alert the operator of a possible loss of the secondary system due to icing.
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^
C.
PLANT AND RAD MONITORING SYSTEMS Page 34 l
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QUESTION: 014 (1.00) l Which ONE of the following occurs when the CAM reaches the " failsafe" alarm setpoint?
- a. Amber light off.
- b. Amber light on.
l
- c. Amber light on and bell sounds.
- d. Amber light off and bell sounds.
1 QUESTION: 015 (1.00)
Which ONE of the following requires the supervisor to be notified of an out of tolerance pressure for the instrument air system while performing i
SOP-70, Completing the Weekly Checklist?
l
- a. 15 psi line pressure.
i
- b. 20 psi line pressure.
t
- c. 55 psi compressor pressure
- d. 75 psi compressor pressure, f;
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(***** CATEGORY C CONTINUED ON NEXT ? AGE *****)
- i C.
PLANT AND RAD MONITORING SYSTEMS Page 35 QUESTION: 016 (1.00)
Which ONE of the following is the normal reading and alarm setpoint for I
the Particulate Stack Monitor?
i Normal Alarm I
a.
0.1 mr/hr 5 mr/hr l
b.
100 cpm 115 cpm c.
150 cpm 1500 cpm d.
400 cpm 2000 cpm QUESTION: 017 (1.00)
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 full in.
Which ONE of the following is the cause of this?
- a. A loss of voltage scram occurred which does not reset the reg rod.
- b. A manual scram was initiated which does not reset the reg rod.
I
- c. Reactor control was left in manual.
- d. Reactor control was left in automatic.
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m
i C.
PLANT AND RAD MONITORING SYSTEMS Page 36 QUESTION: 018 (1.00)
In what region of the Pulse Size vs. Applied Voltage characteristic
- urve does the fission chamber operate?
- a. Geiger Muller l
- b. Limited Proportionality
- c. Proportional
- d. lonization i
QUESTION: 019 (1.00)
How is water or condensation removed from the rotary specimen rack?
- a. The pool is periodically drained to allow the condensation to evaporate.
- b. Water absorbing material is placed in a perforated specimen tube, which is inserted in the rack.
- c. An electric heater is placed in an insulated specimen tube, i
which is inserted in the rack.
- d. An inert gas is inserted in the rack to blow out the condensation.
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PLANT AND RAD MONITORING-SYSTEMS Page 37 1
QUESTION: 020 (1.00)
Which ONE of the following could cause damage to the CAM detection device?
- a. Water level too high in the reactor pool.
- b. Leaving the CAM toggle switch in " test" too long.
i
- c. Detector high voltage set too low.
- d. Loss of low voltage power supply with high voltage still applied to the detector.
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(***** END OF CATEGORY C *****)
(********** END OF EXAMINATION **********)
a
i A.
RX THEORY, THERM 0 & FAC OP CHARS Page 38 j
l 1
ANSWER:
001 (1.00)
C
REFERENCE:
Reed Training Manual, pgs 12-6-22-23 l
ANSWER:
002 (1.00) i b
REFERENCE:
t 4.25 + 4.25 + 1.75 - 10.25 10.25 - (2.5 + 4.25) - 3.5 Reed Requal Exam 88-89, question 7.
i ANSWER:
003 (1.00) i j
c r
REFERENCE:
e Reed Training Manual, page 12-6-17.
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
s
A.
RX THE0RV, THERMO & FAC OP CHARS' Page 39 i
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ANSWER:
004 (1.00) b j
REFERENCE:
Reed Training Manual, Module 12-6 ANSWER:
005 (1.00) c.
i
REFERENCE:
i Reed Training Manual, page 12-7-24/25 ANSWER:
006 (1.00) a/b
REFERENCE:
i i
Reed Training Manual, pages 12-5-13, 12-5-23 and 12-7-5
(* * * ** CATEGORY A CONTINUED ON NEXT PAGE *****)
v
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c
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A
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A.
RX THEORY, THERMO & FAC OP CHARS Page 40 ANSWER:
007 (1.00) b.
REFERENCE:
Reed Training Manual, pages 12-6-4 and 12-6-5 t
ANSWER:
008 (1.00) a.
I
REFERENCE:
t Reed Training Manual, pages 12-1-7/-11
[
I ANSWER:
009 (1.00)
~
r a.
REFERENCE:
1991 NRC administered examination.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A.
RX THEORY, THERM 0 & FAC OP CHARS Page 41 ANSWER:
010 (1.00) i C.
1
REFERENCE:
i s
Thermo-Dynamics, Enrico Fermi
[1987 Reed examination]
ANSWER:
011 (1.00)
.i d.
REFERENCE:
{
Reed Training Manual, Module 12-6 i
ANSWER:
012 (1.00) d.
REFERENCE:
l Reed Training Manual, Module 12-5
[
t i
6
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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A.
RX THEORY, THERM 0 & FAC OP CHARS Page 42 ANSWER:
013 (1.00) d.
REFERENCE:
Reed Training Manual, 12-7-15/-19 ANSWER:
014 (1.00)
C
REFERENCE:
SDM Keff/Keff Keff - 1/SDM + 1 Keff - 1/.0526 + 1 Keff =.95 CRl/CR2 = (1 - Keff 2) / (1 - Keff 1) 10 / 20 ' (1 - Keff 2) / (1 - 0.95)
(0.5) x (0.05) = (1 - Keff 2)
Keff 2 (0.5)(0.05) = 0.975 Reactor Physics, Modules 4 and 5 Equation sheet
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
.' A.
RX THEORY, THERMO & FAC OP CHARS Page 43
~
i ANSWER:
015 (1.00) i d.
REFERENCE:
Power initial - full power X 125%
Power initial - 250 kw r 125% - 312.5 kw T - 500 x 10(-3) sec = 0.5 sec P(final) - P(initial) x e(t/T)
P(final) - 312.5 kw x e(.25/.5)
P(final) - 312.5 kw x e (.5) 312.5 kw x 1.64 P(final) - 515 kw fQUATION SHEET Reed TECHNICAL SPECIFICATION ANSWER:
016 (1.00) i b.
REFERENCE:
Reed Training Manual, pages 12-1-17, 12-6-19 f
f ANSWER:
017 (1.00) a.
REFERENCE:
This is due to the fact that there is a buildup factor
-(1-e[-lambda t]) involving the decay constant for the nuclide.
Reed Training Manual, Page 1-11
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
I i
I
A.
RX THEORY, THERM 0 & FAC OP CHARS Page 44 j
t ANSWER:
018 (1.00)
I d.
[
REFERENCE:
[
Reed Training Manual, Page 5-10 through 5-17 i
l ANSWER:
019 (1.00) i b.
j
REFERENCE:
Reed Training Manual, Page 12-3-15.
ANSWER:
020 (1.00)
{
d.
I
REFERENCE:
RRF Training Manual, pages 12-6-23 and 12-6-24 4
l
(***** END OF CATEGORY A *****)
l I
'B.
NORMAL /EMERG PROCEDURES & RAD CON Page 45 i
t i
ANSWER:
001 (1.00) b.
REFERENCE:
Reed 1990 R0 Requal Exam.
-t ANSWER:
002 (1.00) r a.
REFERENCE:
Reed Technical Specifications, Section A.1, page 1 ANSWER:
003 (1.00) c.
REFERENCE:
Reed Technical Specifications, Section A.2, page 1 ANSWFR:
004 (1.00) l d
REFERENCE:
Tech Specs, Table I, page 9.
1
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B.
NORMAL /EMERG PROCEDURES & RAD CON Page 46 i
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ANSWER:
005 (1.00) l b
I
REFERENCE:
Reed Training Manual, page 2-41/42.
L ANSWER:
006 (1.00) j a.
i
REFERENCE:
l 10CFR20.105 I
ANSWER:
007 (1.00) i i
b.
I
REFERENCE:
t Reed portable survey instrument instruction manuals.
J i
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
i i
'B.
' NORMAL /EMERG PROCEDURES & RAD CON Page 47 i
ANSWER:
008 (1.00) f l
b.
REFERENCE:
R2 - R1 (D1/D2)^2 R2 - 100 mrem /hr x (5/7)^2 R2 - 51 mrem /hr at 7 ft.
Reed Training Manual, Chapter 2, pages 20-28; ANSWER:
009 (1.00) i a.
i
REFERENCE:
.{
QUARTERLY LIMIT = 1.25 R Time = [(1.25 R) / (3.5 R/hr)] [60 min /hr)
Time - 21.4 min.
t 10 CFR 20 and Reed Administrative Procedures, page 7 i
Reed Training Manual, Chapter 2, pages 18 - 20 P
ANSWER:
010 (1.00) j b.
REFERENCE:
EIPs, Appendix C, page 13 k
l
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
D f
B.
NORMAL /EMERG PROCEDURES & RAD CON Page 48 I
' ~
h j
ANSWUi:
011 (1.00)
[
d.
f f
REFERENCE:
Reed EIP, page 13.
j o
?
ANSWER:
012 (1.00) d
REFERENCE:
Reed E-Plan, page RRF-EP-14 ANSWER:
013 (1.00) d.
REFERENCE:
Reed 50P-01, page 1.
r i
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
1
4 B.
NORMAL./EMERG PROCEDURES & RAD CON Page 49
{
I ANSWER:
014 (1.00) b
REFERENCE:
Reed 50P-02, Section 2.7.4 i
i ANSWER:
015 (1.00) l a.
l t
i
REFERENCE:
i Reed 50P-03, Section 3.7.1.10 I
ANSWER:
016 (1.00) b.
REFERENCE:
Reed SOP-04, Section 4.7.3.4 t
r
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
i:
R.
,10RMAL/EMERG PROCEDURES & RAD CON Page 50 AN3WER:
017 (1.00) d.
REFERENCE:
Reed SOP-10, Section 10.8.6 and.7 ANSWER:
018 (1.00) a.
REFERENCE:
Reed 50P-19, Section 19.9, page 5.
ANSWER:
019 (1.00) b.
REFERENCE:
Reed 50P-42, Section 42.7
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
i
~
B.
NORMAL /EMERG PROCEDURES & RAD CON Page 51 ANSWER:
020 (1.00) b r
REFERENCE:
Reed 50P-43, Section 43.5.3 ANSWER:
021 (1.00) d i
REFERENCE:
t Reed, S0P-54, Section 54.7.5.1, page 9 r
e-1 l
b i
(***** END OF CATEGORY B *****)
4
C.
PLANT AND RAD MONITORING SYSTEMS Page 52 j
ANSWER:
001 (1.n0) b.
REFERENCE:
Reed Mech Maint and Operating Manual, Chapter 4, page 56 i
r ANSWER:
002 (1.00) r L
a.
REFERENCE:
Reed SAR, page 4-5 l
r P
ANSWER:
003 (1.00) d.
REFERENCE:
Reed SAR, page 5-3 ANSWER:
004 (1.00) f i
b.
l t
REFERENCE:
(
GA TRIGA Electrical Maintenance Manual t
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
i
=.
b C.
PLANT AND RAD MONITORING SYSTEMS Page 53 r
.i F
i i
ANSWER:
005 (1.00) a.
i
REFERENCE:
Reed Instrument Maint. Manual, page 1-15 I
i ANSWER:
006 (1.00) b.
REFERENCE:
j Reed Technical Specification, Table II, page 9 l
l ANSWER:
007 (1.00) b.
REFERENCE:
50P-51 I
i
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
?
i
'~
C.
PLANT AfD RtD MONITORING SYSTEMS Page 54 i
ANSWER:
008 (1.00) j a/b
REFERENCE:
Reed Mech. Maint. and Operations Manual, Section.5.11.3, page 81 ANSWER:
009 (1.00)
C.
REFERENCE:
Reed Mech. Maint. and Operating Manual, Section 5.11.10, page 85 ANSWER:
010 (1.00) b.
REFERENCE:
+
Reed Mech. Maint. and Operating Manual, Section 3.8, page 20 ANSWER:
011 (1.00) d.
REFERENCE:
Reed Mech. Maint. and Operating Manual, Section 3.8, pages 20-22
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
.C.
PLANT AND RAD MONITORING SYSTEMS Page 55 1
l ANSWER:
012 (1.00)
DELETED d.
t
REFERENCE:
Reed 50P-61 and 1990 Requal exam, question 11.6 ANSWER:
013 (1.00) a.
k
REFERENCE:
Reed 50P-62 f
L ANSWER:
014 (1.00) a.
REFERENCE:
Reed SOP-70, Section 70.7.4, page 3 i
f ANSWER:
015 (1.00) a/b
REFERENCE:
Reed 50P-70, Section 70.7.8, page 5 I
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
i C.
PLANT AND RAD MONITORING SYSTEMS P ge 56 ANSL'ER:
016 (1.00) c/d
REFERENCE:
Reed Emergency Implementation Proc 2dures, Appendix D, page 15 t
ANSWER:
017 (1.00) d.
REFERENCE:
Reed 1991 R0 Requal exam, question B.1 ANSWER:
018 (1.00) c
REFERENCE:
RRF Introduction to Radioactivity Chapter 2, page 2-31 and Module 12-1, page 12-1-25
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
. ~..
' C.
PLANT AND RAD MONITORING SYSTEMS Page 57 ANSWER:
019 (1.00) b t
REFERENCE:
GA Triga Maintenance and Operating Manual ANSWER:
020 (1.00) a.
REFERENCE:
Reed SOP-63, Section 63.1 f
i E
l t
t a
i
(***** END OF CATEGORY C *****)
(********** END OF EXAMINATION **********)
I A.
RX THEORY, THERM 0 & FAC OP CHARS-Page 1 ANSWER KEY I
MULTIPLE CHOICE 001 c
002 b
003 c
004 b
l 005 c
006 a/b 007 b
008 a
009 a
?
010 e
i 011 d
.i 012 d
013 d
1 014 c
015 d
i 016 b
j 017 a
l 018 d
019 b
i 020 d
l
(***** END OF CATEGORY A *****)
l
i
'~
r' B.
NORML/EMERG PROCEDURES & RAD CON Page 2 i
-ANSWER KEY t'
MULTIPLE CHOICE 001 b
002 a
003 c
004 d
I 005 b
006 a
007 b
008 b
[
009 a
010 b
011 d
012 d
f 013 d
014 b
015 a
4 016 b
017 d
018 a
019 b
020 b
021 d
(***** END OF CATEGORY B *****)
.i C.
PLANT AND RAD MONITORING SYSTEMS Page 3 t
ANSWER KEY t
b i
HULTIPLE CH0 ICE 001 b
002 a
003 d
004 b
005 a
006 b
007 b
008 a/b 009 c
010 b
011 d
012 d
DELETED 013 a
j 014 a
015 a/b 016 c/d 017 d
i 018 c
019 b
5 020 a
I
(***** END OF CATEGORY C *****)
(********** END OF EyfulINATION **********)