ML12353A287
| ML12353A287 | |
| Person / Time | |
|---|---|
| Site: | Reed College (R-112) |
| Issue date: | 12/19/2012 |
| From: | Gregory Bowman Division of Policy and Rulemaking |
| To: | Krahenbuhl M Reed College |
| Isaac P | |
| Shared Package | |
| ML12292A084 | List: |
| References | |
| 50-288/OL-13-01 | |
| Download: ML12353A287 (27) | |
Text
December 19, 2012 Dr. Melinda Krahenbuhl, Director Reed Reactor Facility Reed College 3203 SE Woodstock Blvd.
Portland, OR 97202
SUBJECT:
EXAMINATION REPORT NO. 50-288/OL-13-01, REED COLLEGE
Dear Dr. Krahenbuhl:
During the week of November 26, 2012, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your Reed Reactor Facility. The examination was conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2, published in June 2007. Examination questions and preliminary findings were discussed at the conclusion of the examination with those members of your staff identified in the enclosed report.
In accordance with Title 10, Section 2.390 of the Code of Federal Regulations, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. If you have any questions concerning this examination, please contact Patrick Isaac at 301-415-1019 or via email at patrick.isaac@nrc.gov.
Sincerely,
/RA/
Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-288
Enclosures:
- 1. Examination Report No. 50-288/OL-13-01
- 2. Written Examination cc without enclosures: See next page
December 19, 2012 Mrs. Melinda Krahenbuhl, Director Reed Reactor Facility Reed College 3203 SE Woodstock Blvd.
Portland, OR 97202
SUBJECT:
EXAMINATION REPORT NO. 50-288/OL-13-01, REED COLLEGE
Dear Dr. Krahenbuhl:
During the week of November 26, 2012, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examination at your Reed Reactor Facility. The examination was conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2, published in June 2007. Examination questions and preliminary findings were discussed at the conclusion of the examination with those members of your staff identified in the enclosed report.
In accordance with Title 10, Section 2.390 of the Code of Federal Regulations, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. If you have any questions concerning this examination, please contact Patrick Isaac at 301-415-1019 or via email at patrick.isaac@nrc.gov.
Sincerely,
/RA/
Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-288
Enclosures:
- 1. Examination Report No. 50-288/OL-13-01
- 2. Written Examination cc without enclosures: See next page DISTRIBUTION w/ encls.:
PUBLIC PROB r/f Facility File CRevelle (O12-D19)
ADAMS ACCESSION #: ML12353A287 OFFICE PROB:CE IOLB:LA PROB:BC NAME PIsaac CRevelle GBowman DATE 12/18/2012 12/18/2012 12/19/2012 OFFICIAL RECORD COPY
Reed College Docket No. 50-288 cc:
Mayor of the City of Portland 1220 Southwest 5th Avenue Portland, OR 97204 Reed College ATTN: Dr. Ellen Stauder, Dean of Faculty 3203 SE Woodstock Boulevard Portland, OR 97202-8199 Reed College ATTN: Dr. Colin Diver, President 3203 SE Woodstock Boulevard Portland, OR 97202-8199 Ken Niles, Assistant Director Oregon Department of Energy 625 Marion Street NE Salem, OR 97301-3737 Terry D. Lindsey, Program Director Radiation Control Program Oregon Health Services Department of Human Services 800 NE Oregon Street, Suite 640 Portland, OR 97232-2162 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611
ENCLOSURE 1 EXAMINATION REPORT NO:
50-288/OL-13-01 FACILITY:
Reed Reactor FACILITY DOCKET NO.:
50-288 FACILITY LICENSE NO.:
R-112 SUBMITTED BY:
_______/RA/______________
__12/18/2012____
Patrick J. Isaac, Chief Examiner Date
SUMMARY
During the week of November 26, 2012, the NRC administered operator licensing retake examinations to three Reactor Operator candidates. The candidates passed the examinations.
REPORT DETAILS
- 1.
Examiner: Patrick J. Isaac, Chief Examiner
- 2.
Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 3/0 N/A 3/0 Operating Tests 1/0 N/A 1/0 Overall 3/0 N/A 3/0
- 3.
Exit Meeting:
Dr. Melinda Krahenbuhl, Director, Reed Reactor Reuven Lazarus, Reactor Supervisor, Reed Reactor Patrick Isaac, NRC, Examiner The NRC Examiner thanked the facility for their support in the administration of the examinations.
ENCLOSURE 1 U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY:
Reed College REACTOR TYPE:
TRIGA DATE ADMINISTERED:
11/27/2012 CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
Answers are to be written on the answer sheet provided. Attach the answer sheets to the examination. Points for each question are indicated in parentheses for each question. A 70% is required to pass the examination. Examinations will be picked up one (1) hour after the examination starts.
CATEGORY CANDIDATE'S VALUE SCORE CATEGORY_________________
20.00 % B. Normal and Emergency Operating Procedures and Radiological Control FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature
A. Reactor Theory, Thermo & Facility Operating Characteristics A N S W E R S H E E T Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
001 a b c d ___
002 a b c d ___
003 a b c d ___
004 a b c d ___
005 a b c d ___
006 a b c d ___
007 a b c d ___
008 a b c d ___
009 a b c d ___
010 a b c d ___
011 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 *****)
B. Normal and Emergency Operating Procedures and Radiological Control A N S W E R S H E E T Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
001 a b c d ___
002 a b c d ___
003 a b c d ___
004 a b c d ___
005 a ___ b ___ c ___ d ___
006 a b c d ___
007 a b c d ___
008 a b c d ___
009 a b c d ___
010 a b c d ___
011 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 ___
(***** END OF CATEGORY B *****)
(********** END OF EXAMINATION **********)
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
- 1.
Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2.
After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have neither received nor given assistance in completing the examination. This must be done after you complete the examination.
- 3.
Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 4.
Use black ink or dark pencil only to facilitate legible reproductions.
- 5.
Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each answer sheet.
- 6.
Mark your answers on the answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.
- 7.
The point value for each question is indicated in [brackets] after the question.
- 8.
If the intent of a question is unclear, ask questions of the examiner only.
- 9.
When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets. In addition turn in all scrap paper.
- 10.
Ensure all information you wish to have evaluated as part of your answer is on your answer sheet. Scrap paper will be disposed of immediately following the examination.
- 11.
To pass the examination you must achieve a grade of 70 percent or greater in each category.
- 12.
There is a time limit of two (2) hours for completion of the examination.
EQUATION SHEET DR - Rem/hr, Ci - curies, E - Mev, R - feet 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lbm 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 1 BTU = 778 ft-lbf
°F = 9/5 °C + 32 1 gal (H2O) 8 lbm
°C = 5/9 (°F - 32) cP = 1.0 BTU/hr/lbm/°F cp = 1 cal/sec/gm/°C 1
sec 1.0
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A. Reactor Theory, Thermo & Facility Operating Characteristics Page 10 QUESTION A.1 [1.0 point]
Complete the following sentence.
A dollar ($) is a unit of reactivity, where one dollar ($1) is equal to the ___________.
- a.
Delayed neutron precursor decay constant ().
- b.
Effective delayed neutron precursor decay constant (eff).
- c.
Delayed neutron fraction ().
- d.
Effective delayed neutron fraction (eff).
QUESTION A.2 [1.0 point]
Given the following diagram, which of the following most correctly describe the condition of the reactor?
- a.
The prompt jump occurs because the production rate of delayed neutrons abruptly changes as reactivity is added.
- b.
At T=15s, the reactor is considered prompt critical.
- c.
After the prompt jump, the rate of change of power cannot increase any more rapidly than the built-in time delay the neutron precursor half-lives allow.
- d.
Shortly after T=0s, the reactor power is immediately turned due to the rise in moderator temperature.
A. Reactor Theory, Thermo & Facility Operating Characteristics Page 11 QUESTION A.3 [1.0 point]
Complete the following sentence. In a nuclear reactor, 95% of all Xenon production is directly produced through the _________.
- a.
Decay of I-135
- b.
Fission of U-235
- c.
Beta decay of Cs-135
- d.
Fission of U-238 QUESTION A.4 [1.0 point]
The reactor is at 5 W. Given the following data, calculate the Shutdown Margin, as defined by Technical Specifications.
Control Total Remaining Rod Worth Rod Worth Safety
$3.32
$0.95 Shim
$3.41
$0.96 Regulating
$1.85
$0.51
- a.
$2.42
- b.
$2.75
- c.
$5.15
- d.
$6.16
A. Reactor Theory, Thermo & Facility Operating Characteristics Page 12 QUESTION A.5 [1.0 point]
Which ONE of the following is the correct amount of reactivity added if the multiplication factor, k, is increased from 0.800 to 0.950?
- a.
0.150
- b.
0.158
- c.
0.188
- d.
0.197 QUESTION A.6 [1.0 point]
About two minutes following a reactor scram, the reactor period has stabilized and the power level is decreasing at a CONSTANT rate. Given that reactor power at time t0 (i.e., shortly after the scram) was 100 kW power, what will reactor power be three minutes later?
- a.
2 kW
- b.
10 kW
- c.
30 kW
- d.
50 kW QUESTION A.7 [1.0 point]
With the reactor on a constant period, which transient requires the LONGEST time to occur?
- a.
5% of rated power - going from 1% to 6% power of rated power
- b.
10% of rated power - going from 10% to 20% power of rated power
- c.
15% of rated power - going from 20% to 35% power of rated power
- d.
20% of rated power - going from 40% to 60% power of rated power
A. Reactor Theory, Thermo & Facility Operating Characteristics Page 13 QUESTION A.8 [1.0 point]
The time period in which the MAXIMUM concentration of Xe-135 will be present in the core is approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after:
- a.
a startup to 100%power.
- b.
a scram from 100% power.
- c.
a power increase from 0% to 50%.
- d.
a power decrease from 100% to 50%.
QUESTION A.9 [1.0 point]
Which ONE of the following conditions will INCREASE the core excess of a reactor?
- a.
Higher moderator temperature (assume negative temperature coefficient)
- b.
Insertion of a negative reactivity worth experiment
- c.
Burnout of a burnable poison
- d.
Fuel depletion QUESTION A.10 [1.0 point]
A reactor with Keff = 0.8 contributes 1000 neutrons in the first generation. When progressing from the FIRST generation to the SECOND generation, how many total neutrons are there after the SECOND generation?
- a.
1250
- b.
1600
- c.
1800
- d.
2000
A. Reactor Theory, Thermo & Facility Operating Characteristics Page 14 QUESTION A.11 [1.0 point]
Which of the following radiation types has its penetrating ability through biological material impeded the greatest by its high specific ionization?
- a. Alpha
- b. Beta
- c. Gamma
- d. Neutron QUESTION A.12 [1.0 point]
Given the associated graph, which answer best describes neutron behavior within Region I.
- a. For neutrons with energy levels (E <1 ev) the cross section is inversely proportional to the neutron velocity.
- b. For neutrons with energy levels (E >1 ev), the neutron cross section decreases steadily with increasing neutron energy (1/E).
- c. For neutrons with energy levels (E < 1 ev), the high energy neutrons cross section decreases which is proportional to the decrease in their mean free path.
- d. Neutrons of specific energy levels (E > 1 ev) are more likely to be readily absorbed than neutrons at other energy levels because of the affinity of the nucleus for neutrons whose energies closely match its discrete, quantum energy levels.
A. Reactor Theory, Thermo & Facility Operating Characteristics Page 15 QUESTION A.13 [1.0 point]
A reactor pool contains 106, 000 gallons of water at 90 degrees F, and it heats up to 93 degrees F in two hours. Assuming no ambient losses, the calculated reactor power level is ______.
- a.
93 kW.
- b.
259 kW.
- c.
389 kW
- d.
777 kW.
QUESTION A.14 [1.0 point]
The effective neutron multiplication factor, Keff, for a critical reactor is:
- a. Equal to.
- b. Equal to 1.
- b. Equal to the effective delayed neutron fraction.
- d. Any value < 1.
QUESTION A.15 [1.0 point]
Light water is an ideal moderator for thermalizing neutrons. Which of the following most correctly describes the nuclear properties of an ideal moderator?
- a.
Large absorption cross section.
- b.
Small energy loss per collision.
- c.
Large scattering cross section.
- d.
Small Doppler Broadening effect.
A. Reactor Theory, Thermo & Facility Operating Characteristics Page 16 QUESTION A.16 [1.0 point]
Which one of the following is the correct reason that delayed neutrons enhance control of the reactor?
- a.
There are more delayed neutrons than prompt neutrons.
- b.
Delayed neutrons increase the average neutron generation time.
- c.
Delayed neutrons are born at higher energies than prompt neutrons and therefore have a greater effect.
- d.
Delayed neutrons take longer to reach thermal equilibrium QUESTION A.17 [1.0 point]
Which of the following statements best characterizes Natural Circulation?
- a. The driving force is a difference in density.
- b. Heat transfer is more efficient as the heat source decays.
- c. Heat transfer is more efficient if the difference in temperature between the source and sink is small.
- d. The elevation of the heat source must be above that of the heat sink.
QUESTION A.18 [1.0 point]
You are poolside of the reactor conducting a tour when someone from the group asks what the blue glow around the reactor is. Which of the following would be the most correct response?
- a. It is the energy released from the interaction between a neutrino and antineutrino which is known as pair annihilation.
- b. It is binding energy released directly through chain reactions of the fission process
- c. It is the energy released by thermal neutrons when the Keff= 1.000
- d. It is an effect when high energy, charged particles (e.g., electrons) pass through the pool at a speed which is greater than the speed of light
A. Reactor Theory, Thermo & Facility Operating Characteristics Page 17 QUESTION A.19 [1.0 point]
During a reactor startup, criticality occurred at a lower rod height than the last startup. Which ONE of the following reasons could be the cause?
- a. Xe135 peaked.
- b. Moderator temperature increased.
- c. A pre-loaded experiment had positive reactivity.
- d. Maintenance on the control rods resulted in a slightly faster rod speed.
QUESTION A.20 [1.0 point]
In an operating TRIGA reactor, the effect of the Xenon poison is different from that due to samarium because:
- a. Xenon will begin to decay 12 to 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> after reactor shutdown, whereas the effects of Samarium will remain indefinitely after shutdown because it is stable.
- c. While both poisons decay with their respective half lives after shutdown, Samarium decays with a shorter half life and its affects are negligible.
- d. While both poisons decay after shutdown, samarium decays with a much longer half-life, its affects are negligible.
B. Normal and Emergency Operating Procedures and Radiological Control Page 18 Question: B.1 [1.0 point]
A small radioactive source is to be stored in the reactor building. The source is estimated to contain 2 curies and emit a 1.33 Mev gamma. Assuming no shielding was to be used, a Radiation Area barrier would have to be erected from the source at a distance of approximately:
- a.
6 inches
- b.
21 inches
- c.
21 feet
- d.
57 feet Question: B.2
[1.0 point]
Based on 10CFR55, which one of the following is the MINIMUM requirement that must be met to retain an "active" license?
- a.
Must perform license duties at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per calendar quarter.
- b.
Must perform license duties a minimum of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per month.
- c.
Must perform license duties a minimum of 5 eight-hour shifts per calendar quarter.
- d.
Must perform license duties at least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per calendar year.
Question: B.3
[1.0 point]
Which ONE of the following is the absolute MAXIMUM STEADY-STATE power level allowed by TECHNICAL SPECIFICATIONS?
- a.
240 Kilowatts
- b.
250 Kilowatts
- c.
287.5 Kilowatts
- d.
300 Kilowatts Question: B.4
[1.0 point]
A system or component is defined as "operable" by Technical Specifications if:
- a.
a channel check has been performed.
- b.
it is capable of performing its intended function.
- c.
it has no outstanding testing requirements.
- d.
a functional test has been performed.
B. Normal and Emergency Operating Procedures and Radiological Control Page 19 Question:
B.5
[1.0 points, 0.25 each]
Match the following experiments in Column A with their applicable requirements in Column B.
COLUMN A COLUMN B
- a. explosive materials.
- 1. Not allowed
- b. Liquid fissionable materials
- 2. Doubly encapsulated
- c. materials corrosive to reactor components.
- 3. No special requirements
- d. compounds highly reactive with water Question: B.6
[1.0 point]
Which one of the following is a definition for AEmergency Planning Zone@ (EPZ)?
- a.
The geographical area that is beyond the site boundary where the Reactor Director has direct authority over all activities.
- b.
The Psychology building located on the REED College Campus.
- c.
The area which includes the Psychology building and extends 250 feet in every direction from the center of the reactor.
- d.
The area beyond the site boundary at which Protective Action Guide (PAG) could be exceeded.
Question: B.7
[1.0 point]
Which one of the following radioactive gases poses the most significant hazard within the reactor room during normal operations?
- a.
- b.
- c.
Xenon-135
- d.
Argon-41
B. Normal and Emergency Operating Procedures and Radiological Control Page 20 Question: B.8
[1.0 point]
While conducting a tour of a radiation area, your pocket dosimeter goes off-scale after being dropped. Which one of the following actions do you take?
- a.
Stay where you are and call for help.
- b.
Reset the dosimeter back to zero. Notify Health Physics after completion of tour.
- c.
Leave the radiation area and notify Health Physics or Reactor Operations.
- d.
Continue the tour making sure to stay out of High-radiation areas. Obtain a new dosimeter from Reactor Health Physics.
Question: B.9
[1.0 point]
Which one of the following has the ultimate responsibility to ensure the emergency grab bag has been taken when evacuating the facility?
- a. Emergency Coordinator.
- b. The Operator.
- c. The Director.
- d. The first staff member using the exit corridor.
Question: B.10
[1.0 point]
The reactor operator calculates that the maximum excess reactivity for Ref core conditions is 2.35% k/k. For this excess reactivity, which ONE of the following is the best action?
- a.
Continue to operate because the excess reactivity is within TS limit.
- b.
Increase power to 100 W and verify the excess reactivity again.
- c.
Shutdown the reactor; immediately report the result to the supervisor due to excess reactivity being above TS limit.
- d.
Continue operation, but immediately report the result to the supervisor since the excess reactivity is exceeding TS limit.
B. Normal and Emergency Operating Procedures and Radiological Control Page 21 Question: B.11
[1.0 point]
During a rabbit irradiation at full power, which ONE of the following precautions must be followed as part of the procedure?
- a.
Do not allow the rabbit motor to be turned on after the reactor has been at power for a while.
- b.
The rabbit operator must not allow anyone except him/herself to have complete control over the insertion and removal of the sample in the core.
- c.
The reactor operator must scram the reactor if there is a power level change greater than 10% when the sample is inserted in the core.
- d.
Discolored rabbit tubes must be used since they are more brittle and will allow a greater percentage of neutrons to irradiate the sample.
Question: B.12
[1.0 point]
Whose approval is necessary before radioactive material can be transferred to personnel of another department?
- a. The Senior Reactor Operator on duty.
- b. The Health Physicist.
- c. The Reactor Operations Committee.
- d. The Director.
Question: B.13
[1.0 point]
During an earthquake, the reactor operator must perform the following tasks, EXCEPT:
- a. Isolate the demin tank.
- b. Isolate the heat exchanger.
- c. Stop the cooling system pumps.
- d. Scram the reactor
B. Normal and Emergency Operating Procedures and Radiological Control Page 22 Question: B.14
[1.0 point]
Which one of the following is the minimum temperature above which the reactor shall be shutdown?
- a. 120 EF
- b. 148 EC
- c. 48.9 EF
- d. 50 EC Question: B.15
[1.0 point]
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.
- a. Shutdown the reactor
- b. Isolate the Pool
- c. Notify a member of the ENCL
- d. Terminate the emergency Question: B.16
[1.0 point]
Which one of the following is the definition for AAnnual Limit on Intake@ (ALI)?
- a. The concentration of a radionuclide in air which, if inhaled by an adult worker for a year, results in a total effective dose equivalent of 100 millirems.
- b. 10 CFR 20 derived limit, based on a Committed Effective Dose Equivalent of 5 rems whole body or 50 rems to any individual organ, for the amount of radioactive material inhaled or ingested in a year by an adult worker.
- c. The effluent concentration of a radionuclide in air which, if inhaled continuously over a year, would result in a total effective dose equivalent of 50 millirems for noble gases.
- d. Projected dose commitment to individuals that warrant protective action following a release of radioactive material.
B. Normal and Emergency Operating Procedures and Radiological Control Page 23 Question:
B.17
[1.0 point]
Per Reed's Emergency Implementation Procedures, where do facility personnel assemble when the Reactor Facility must be evacuated due to a fire?
- a. Chemistry Laboratory
- b. Reactor parking area
- c. Director=s Office, Chem 102
- d. Chemistry building hallway Question: B.18
[1.0 point]
Which ONE of the following scrams is NOT required by Technical Specifications?
- a. Linear channel
- b. % power channel
- c. Manual
- d. Log channel Question: B.19
[1.0 point]
While performing SOP 01, The Start-up Checklist, the operator places the Log Channel switch to one of the calibrate positions and attempts to raise a control rod. The Source light illuminates and you note rod motion. Which one of the following describes what was just observed? The operator checked the:
- a. Source Interlock is inoperable.
- b. Source Interlock is operable.
- c. Rod Raising Interlock is inoperable.
- d. Rod Raising Interlock is operable.
Question: B.20
[1.0 point]
An entry was made in the log in red ink. Which one of the following is the significance of the red ink?
- a. It indicates only unexplained scrams.
- b. It indicates only inadvertent scrams.
- c. It indicates a fuel movement.
- d. It indicates all in-core changes.
(*** End of Section B ***)
Section A: Theory, Thermo & Fac. Operating Characteristics Page 24 A.1 d
Ref:
Reactor Theory (Neutron Characteristics) DOE-HDBK-1019/1-93 PROMPT AND DELAYED NEUTRONS A.2 c
Ref:
DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2 A.3 a
Ref:
DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2 A.4 b
Ref:
SDM = $CR $ HWR CE SDM = 8.58 - 3.41 - 2.42 = $2.75 A.5 d
Ref:
Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 3.3.3, page 3-21.
At Keff =0.8; = Keff -1/ Keff = -0.2/0.8 =-0.25.
At Keff =0.95, =-0.05/0.95 = -0.053.
= 1 - 2= -0.053-(-0.25)=0.197 A.6 b
Ref:
P = P0 e-T/t = 100e(180sec/-80sec) = 100 e-2.25 =( 0.1054) x 100 kW = 10 kW DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2 A.7 a
Ref:
Burn, R., Introduction to Nuclear Reactor Operations, ©1988, § 4.3 T=1 was set arbitrarily for simplicity.
P(t) = P(0)
- e ^ (t / T) 6% = 1%
- e ^ (t / 1) --> t = 1.79176 20% = 10%
- e ^ (t /1) --> t = 0.693147 35% = 20%
- e ^ (t / 1) --> t = 0.559616 60% = 40%
- e ^ (t / 1) --> t = 0.405465 Hence, the transient that takes the LONGEST time to occur is the 5% increase from 1% to 6%
power.
A.8 b
Ref:
Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 8.4, page 8-9 A.9 c
Ref:
DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2 A.10 c
Ref:
Burn, R., Introduction to Nuclear Reactor Operations, © 1982, § 5.3, p. 5.6 2-nd generation=n + K*n=1000+800=1800 neutrons A.11 a
Section A: Theory, Thermo & Fac. Operating Characteristics Page 25 Ref:
PSBR Training Manual Chapter 2.1.1 Alpha Particle Interactions with Matter A.12 a
Ref:
PSBR Training Manual Chapter 2.3.2.2 Cross Sections A.13 c
Ref:
Power = mcT/t, where: m=106,000 gallons x 8.34 lbs/gal = 884,040 lb; c=1 Btu/F-lb; T/t = 1.5 degrees/hour. Power = 1,326,060 Btu/hour; 3413 Btu/hour = 1 kW. Power
= 1,326,060/3413 = 389 kW A.14 b
Ref: DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2 A.15 c
Ref:
DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 1 A.16 b
REF: Reference 1: volume 2, module 4, pg. 10 A.17 a
Ref: General Physics, HT&FF, pp. 355 - 358 A.18 d
Ref: PSBR Training Manual, Chapter 1.8 Bremstrahlung and Cerenkov Effect A.19 c
Ref: DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2 A.20 a
Ref: DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2
Section C Facility and Radiation Monitoring Systems B.1 d
Ref:
DR= 6CEn/(f)(f) = 0.005 R = 6(2)(1.33)/x2, x2 = 3192, x = 56.50 feet B.2 a
Ref:
10CFR55.53(e)
B.3 b
Ref:
Technical Specifications § A.2 Steady State Mode B.4 b
Ref:
REED T.S. Definitions B.5 a 1 b 2 c 2 d 2_
Ref:
SOP 50D B.6 c
Ref:
Emergency Plan B.7 d
Ref:
NRC Requalification Exam - Chart of the Nuclides B.8 c
Ref:
NRC REED Examination Bank B.9 b
Ref:
EIP.7-8 B.10 c
Ref:
TS, Section E, Reactor Core B.11 c
Ref:
Reed Research Reactor SOP-51; Rabbit Irradiations 51.5.3 B.12 d
Ref:
Admin Procedures Sect. 5.1 B.13 a
Ref:
EIP, 5 pg. 6 B.14 a
Ref:
Tech. Specs D.1 B.15 d
Ref:
E plan 3.3 B.16 b
Ref:
10CFR20.1003
Section C Facility and Radiation Monitoring Systems B.17 c
Ref:
Emergency Implementation Procedures, EIP Situation 7 B.18 d
Ref:
Tech Specs Table 1 B.19 a
Ref:
Reed, SOP 01, Step 1.7.6.6.2 B.20 c
Ref:
SOP 10, 10.7.1.2; 10.7.7.1; & 10.7.8.2
(*** End of Section B ***)
(***** End of Examination *****)