ML072710014

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Initial Examination Report No. 50-170/OL-07-01, Armed Forces Radiobiology Research Institute
ML072710014
Person / Time
Site: Armed Forces Radiobiology Research Institute
Issue date: 10/04/2007
From: Johnny Eads
NRC/NRR/ADRA/DPR/PRTB
To: Miller S
US Dept of the Navy, National Naval Medical Ctr
Isaac P, NRC/NRR/DPR/PRTB, 301-415-1019
Shared Package
ML072060308 List:
References
50-170/07-001
Download: ML072710014 (62)
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Text

October 4, 2007 Mr. Stephen I. Miller, Reactor Facility Director Armed Forces Radiobiology Research Institute Naval Medical Center 8901 Wisconsin Ave.

Bethesda, MD 20889-5603

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-170/OL-07-01, ARMED FORCES RADIOBIOLOGY RESEARCH INSTITUTE

Dear Mr. Miller:

During the week of September 10, 2007, the U.S. Nuclear Regulatory Commission (NRC) administered an initial operator licensing examination at your Armed Forces Radiobiology Research Institute reactor. 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 pxi@nrc.gov.

Sincerely,

/RA/

Johnny Eads, Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-170

Enclosures:

1. Examination Report No. 50-170/OL-07-01
2. Written Examination cc w/encls:

Please see next page

October 4, 2007 Mr. Stephen I. Miller, Reactor Facility Director Armed Forces Radiobiology Research Institute Naval Medical Center 8901 Wisconsin Ave.

Bethesda, MD 20889-5603

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-170/OL-07-01, ARMED FORCES RADIOBIOLOGY RESEARCH INSTITUTE

Dear Mr. Miller:

During the week of September 10, 2007, the U.S. Nuclear Regulatory Commission (NRC) administered an initial operator licensing examination at your Armed Forces Radiobiology Research Institute reactor. 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 pxi@nrc.gov.

Sincerely,

/RA/

Johnny Eads, Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-170

Enclosures:

1. Examination Report No. 50-170/OL-07-01
2. Examination and answer key cc w/encls:

Please see next page DISTRIBUTION w/ encls.:

PUBLIC PRTB r/f RidsNrrDprPrtb RidsNrrDprPrta Facility File CHart (O12-D19)

ADAMS ACCESSION #: ML072710014 OFFICE PRTB:CE IOLB:LA PRTB:BC NAME PIsaac pi CHart cah JEads jhe DATE 10/4/2007 10/4/2007 10/4/2007 OFFICIAL RECORD COPY

ARMED FORCES RADIOBIOLOGY RESEARCH INSTITUTE Docket No. 50-170 cc:

Director, Maryland Office of Planning 301 West Preston Street Baltimore, MD 21201 Montgomery County Executive 101 Monroe Street, 2nd Floor Rockville, MD 20850 Environmental Program Manager III Radiological Health Program Air & Radiation Management Adm.

Maryland Dept of the Environment 1800 Washington Blvd.,Suite 750 Baltimore, MD 21230-1724 Rich McLean, Manager Nuclear Programs Maryland Department of Natural Resources Tawes B-3 Annapolis, MD 21401 Director Air & Radiation Management Adm.

Maryland Dept of the Environment 1800 Washington Blvd., Suite 710 Baltimore, MD 21230 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

ENCLOSURE 1 EXAMINATION REPORT NO:

50-170/OL-07-01 FACILITY:

ARMED FORCES RADIOBIOLOGY RESEARCH INSTITUTE FACILITY DOCKET NO.:

50-170 FACILITY LICENSE NO.:

R-84 SUBMITTED BY:

_______________/RA/________________ 9/27/07____

Patrick J. Isaac, Chief Examiner Date

SUMMARY

During the week of September 10, 2007, the NRC administered examinations to four Senior Reactor Operator Instant (SRO-I) candidates. One candidate failed Section B, Normal and Emergency Operating Procedures and Radiological Controls, of the written examinations. All the other candidates passed all portions of the examinations.

REPORT DETAILS

1.

Examiner: Patrick J. Isaac, Chief Examiner

2.

Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written N/A 3/1 3/1 Operating Tests N/A 4/0 4/0 Overall N/A 3/1 3/1

3.

Exit Meeting:

Stephen Miller, Facility Director AFRRI Harry Spence, Reactor Supervisor AFRRI Patrick Isaac, NRC, Examiner There were no generic concerns raised by the Examiner. Mr. Miller stated that the written examination was well written and needed no formal corrections. The NRC Examiner thanked the facility for their support in the administration of the operating tests.

ENCLOSURE 2 U. S. NUCLEAR REGULATORY COMMISSION RESEARCH AND TEST REACTOR OPERATOR LICENSING EXAMINATION FACILITY:

Armed Forces Radiobiology Research Institute REACTOR TYPE:

TRIGA DATE ADMINISTERED: 09/11/07 CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheets provided. Points for each question are indicated in brackets for each question. You must score 70% in each section to pass. Examinations will be picked up three (3) hours after the examination starts.

% of Category

% of Candidates Category Value Total Score Value Category 20.00 33.3 A. Reactor Theory, Thermodynamics and Facility Operating Characteristics 20.00 33.3 B. Normal and Emergency Operating Procedures and Radiological Controls 20.00 33.3 C. Plant and Radiation Monitoring Systems FINAL GRADE

% TOTALS All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

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.

The point value for each question is indicated in [brackets] after the question.

7.

If the intent of a question is unclear, ask questions of the examiner only.

8.

To pass the examination you must achieve a grade of 70 percent or greater in each category.

9.

There is a time limit of three (3) hours for completion of the examination.

10.

When you have completed and turned in you examination, leave the examination area

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Section A L Theory, Thermo, and Facility Characteristics Page 8 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 __

Section B Normal/Emerg. Procedures & Rad Con Page 9 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 ___ e __ __

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 __

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Section C Facility and Radiation Monitoring Systems Page 10 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 __

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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 EXAMINATION *****

Section A L Theory, Thermo, and Facility Characteristics Page 11 Question A.1 [1.0 point]

What is approximately 85% of the fissions energy release coming from?

a. Delayed neutrons.
b. The heat liberated from neutrons slowing down in media.
c. The kinetic energy of the fission fragments.
d. The gamma radiation.

Question A.2 [1.0 point]

Control Rod withdrawal predominantly changes Keff by changing the Y

a. fast fission factor ().
b. thermal utilization factor (f).
c. neutron reproduction factor ().
d. resonance escape probability (p).

Question A.3 [1.0 point]

If the mean generation time for neutrons in a reactor is 0.1 sec and k = 1.001, the time for the power to double is:

a. 10 seconds
b. 69 seconds
c. 2 min
d. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

Section A L Theory, Thermo, and Facility Characteristics Page 12 Question A.4 [1.0 point]

Which ONE of the following is an example of alpha decay?

a.

35Br87 6 33As83

b.

35Br87 6 35Br87

c.

35Br87 6 34Se86

d.

35Br87 6 36Kr87 Question A.5 [1.0 point]

When compared to, eff is Y

a. smaller, because delayed neutrons are born at lower energies than prompt neutrons.
b. larger, because delayed neutrons are born at lower energies than prompt neutrons.
c. smaller, because delayed neutrons are born at higher energies than prompt neutrons.
d. larger, because delayed neutrons are born at higher energies than prompt neutrons.

Question A.6 [1.0 point]

Given a source strength of 100 neutrons per second (N/sec) and a multiplication factor of 0.8, the expected stable neutron count rate would be?

a. 125 N/sec
b. 250 N/sec
c. 400 N/sec
d. 500 N/sec

Section A L Theory, Thermo, and Facility Characteristics Page 13 Question A.7 [1.0 point]

The reactor is on a CONSTANT positive period. Which ONE of the following power changes will take the longest time to complete?

a. 5%, from 95% to 100%
b. 10%, from 80% to 90%
c. 15%, from 15% to 30%
d. 20%, from 60% to 80%

Question A.8 [1.0 point]

The reactor supervisor tells you the reactor is shutdown with a shutdown margin of 12%. An experimenter inserts an experiment in the core and nuclear instrumentation increases from 100 counts per minute to 200 counts per minute. What is the new Keff of the reactor?

a. 0.920
b. 0.946
c. 0.973
d. 1.000 Question A.9 [1.0 point]

The term PROMPT JUMP refers toY

a. the instantaneous change in power due to raising a control rod
b. a reactor which has attained criticality on prompt neutrons alone.
c. a reactor which is critical due to both prompt and delayed neutrons.
d. a negative reactivity insertion which is greater than eff

Section A L Theory, Thermo, and Facility Characteristics Page 14 Question A.10 [1.0 point]

INELASTIC SCATTERING is the process by which a neutron collides with a nucleus and Y

a. recoils with the same kinetic energy it had prior to the collision.
b. recoils with a lower kinetic energy than it had prior to the collision with the nucleus emitting a gamma ray.
c. is absorbed, with the nucleus emitting a gamma ray.
d. recoils with a higher kinetic energy than it had prior to the collision with the nucleus emitting a gamma ray.

Question A.11 [2.0 points, 0.5 each]

Match each of the terms in column A with the correct definition from column B.

Column A Column B

a. Fast neutrons
1. Neutrons released directly from fission.
b. Prompt neutrons
2. High energy neutrons.
c. Slow neutrons
3. Neutrons released from decay of fission products.
d. Delayed neutrons
4. Low energy neutrons.

Question A.12 [1.0 point]

WHICH ONE of the following nuclei will cause a neutron to lose the MOST energy per collision while slowing down (assume elastic scattering)?

a. H1
b. H2
c. C12
d. U238

Section A L Theory, Thermo, and Facility Characteristics Page 15 Question A.13 [1.0 point]

A $1.50 insertion has been made into the cold-critical core. What is the k-effective?

a. 1.0070
b. 1.0098
c. 1.0105
d. 1.1500 Question A.14 [1.0 point]

WHICH ONE of the following describes the MAJOR contributions to the production and depletion of xenon in the reactor?

a. Produced from radioactive decay of iodine and depletes by neutron absorption only.
b. Produced from radioactive decay of iodine and depletes by radioactive decay and neutron absorption.
c. Produced directly from fission and depletes by neutron absorption only.
d. Produced directly from fission and depletes by radioactive decay and neutron absorption.

Question A.15 [1.0 point]

An experimenter makes an error loading a rabbit sample. Injection of the sample results in a 100 millisecond period. If the scram setpoint is 1.25 MW and the scram delay time is 0.1 seconds, WHICH ONE of the following is the peak power of the reactor at shutdown? (Assume Rabbit system is operational for this question.)

a. 1.25 MW
b. 2.5 MW
c. 3.4 MW
d. 12.5 MW

Section A L Theory, Thermo, and Facility Characteristics Page 16 Question A.16 [1.0 point]

The PRIMARY reason that a neutron source is installed in the reactor is to Y

a. allow for testing and irradiation of experiments when the core is shutdown.
b. supply the neutrons required to start the chain reaction for reactor startups.
c. provide a neutron level high enough to be monitored for a controlled reactor startup.
d. increase the excess reactivity of the reactor which reduces the frequency for refueling.

Question A.17 [1.0 point]

Which ONE of the following is the time period in which the maximum amount of Xe135 will be present in the core?

a. 8 to 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> after a startup to 100% power.
b. 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a power increase from 50% to 100%.
c. 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a power decrease from 100% to 50%.
d. 8 to 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> after a scram from 100%.

Question A.18 [1.0 point]

If a $1.5 pulse results in a peak power of 250 MW, (FWHM) of 100 milliseconds and fuel temperature rise of 145EC, a $2.00 pulse would result in Y Peak Power FWHM Temp. Rise

a.

780 MW 80 210EC

b.

1000 MW 50 290EC

c.

1200 MW 50 350EC

d.

900 MW 80 210EC

Section A L Theory, Thermo, and Facility Characteristics Page 17 Question A.19 [1.0 point]

Which of the following physical characteristics of the TRIGA fuel accounts for the majority of the negative temperature feedback?

a. Thermal expansion of the fuel matrix
b. Geometric buckling
c. Doppler broadening
d. Hardening of the neutron spectrum caused by heating the U-ZrH fuel

Section B Normal, Emergency and Radiological Control Procedures Page 18 Question B.1 [1.0 point]

An accessible area within the facility has general radiation levels of 325 mrem/hour. What would be the EXPECTED posting for this area?

a. "Caution, Very High Radiation Area"
b. "Danger, Airborne Radioactivity Area"
c. "Danger, High Radiation Area"
d. "Caution, Radiation Area" Question B.2 [2.0 points, 0.5 each]

Match the 10CFR55 requirements for maintaining an active operator license in column A with the corresponding time period from column B.

Column A Column B

a. Renew License 1 year
b. Medical Exam 2 years
c. Pass Requalification Written Examination 4 years
d. Pass Requalification Operating Test 6 years Question B.3 [1.0 point]

A verification of acceptable performance by observation of channel behavior is:

a. Channel Check
b. Channel Verification
c. Channel Calibration
d. Channel Test

Section B Normal, Emergency and Radiological Control Procedures Page 19 Question B.4 [1.0 point]

While working on an experiment, you receive the following radiation doses: 100 mrem (),

25 mrem (), and 5 mrem (thermal neutrons). Which ONE of the following is your total dose?

a. 175 mrem
b. 155 mrem
c. 145 mrem
d. 130 mrem Question B.5 [2.0 point, 0.5 each]

Match type of radiation (1 thru 4) with the proper penetrating power (a thru d)

a. Gamma
1. Stopped by thin sheet of paper
b. Beta
2. Stopped by thin sheet of metal
c. Alpha
3. Best shielded by light material
d. Neutron
4. Best shielded by dense material Question B.6 [1.0 point]

10CFR50.54(x) states: AA licensee may take reasonable action that departs from a license condition or a technical specification (contained in a license issued under this part) in an emergency when this action is immediately needed to protect the public health and safety and no action consistent with license conditions and technical specifications that can provide adequate or equivalent protection is immediately apparent.@ Per 10CFR50.54(y), which one of the following is the minimum level of authorization for this action?

a. Reactor Operator licensed at the facility.
b. Senior Reactor Operator licensed at the facility.
c. Facility Manager (or equivalent at facility).
d. The U.S. Nuclear Regulatory Commission Project Manager

Section B Normal, Emergency and Radiological Control Procedures Page 20 Question B.7 [1.0 point]

In order to maintain an active reactor or senior reactor operator license, the license-holder must perform the functions of his/her position for at least:

a. four hours per calendar quarter.
b. six hours per calendar quarter.
c. one hour per month.
d. sixteen hours per year Question B.8 [1.0 point]

A non-monitored opening of the exposure room may be performed when which of the following conditions are met?

1. ER cam reading should be less than 200 cpm above background
2. Survey meter readings at the door indicate safe entry conditions
3. The reactor has not been to power in that ER since the last survey
4. At least two days have passed since the last power run
a. 1
b. 1 & 2
c. 1, 2, & 3
d. 1, 2, 3, & 4 Question B.9 [2.0 points, 0.4 each]

Match each of the electronics channels in column A with the reactor modes for which it must be operable in column B.

Column A Column B

a. Fuel Temperature
1. Steady State ONLY
b. Linear Power Channel
2. Pulse ONLY
c. Log Power Channel
3. All Modes
d. High-Flux Safety Channel
e. Pulse Energy Integrating Channel

Section B Normal, Emergency and Radiological Control Procedures Page 21 Question B.10

[1.0 point]

As permitted by 10 CFR 50.59, the AFRRI reactor facility may:

a. Modify systems and change the Technical Specifications (TS) if the NRC is notified afterwards.
b. Perform new and little understood experiments when they are for research.
c. Determine the affects of modifications and their impact on TS.
d. Redefine the boundaries of accidents previously analyzed in the Safety Analysis Report (SAR).

Question B.11

[1.0 point]

When the warning horn is disconnected in either exposure room, how many operators must inspect the room before closing the exposure room door?

a. 1
b. 2
c. 3
d. 4 Question B.12

[1.0 point]

After 5 pulses, a gamma survey of ER1 (in working area) shows a radiation level of 1 R/hr.

What is the longest time you can remain in ER1 without exceeding your daily AFRRI whole body limit?

a. 1 min
b. 3 min
c. 10 min
d. 15 min

Section B Normal, Emergency and Radiological Control Procedures Page 22 Question B.13

[2.0 points, 0.5 each]

Identify each of the following as either a Safety Limit (SL) a Limiting Safety System Setting (LSSS) or a Limiting Condition for Operation (LCO).

a. The maximum step insertion in the pulse mode shall be 2.8%k/k ($4.00) in the pulse mode.
b. The reactor shall not be operated with the maximum available excess reactivity above cold critical with or without all experiments in place greater than $5.00 (3.5% k/k).
c. The temperature of a fuel element shall not exceed 1000EC.
d. During steady-state operation a minimum of two Reactor Power Level Channels shall be operable.

Question B.14

[1.0 point]

Emergency Response Kits are located in all the following listed locations except Y

a. Emergency Response Center (ERC)
b. Hallway 3106 near Emergency Response Team (ERT) Primary Location
c. Stairwell 3317 3rd floor.
d. Emergency Command Post (ECP)

Question B.15

[1.0 point]

Which of the following is NOT a reportable occurrence per the Technical Specifications (TS)?

a. Operation with any safety system setting less conservative than specified in Section 2.2 of the TS.
b. Operation in violation of any Limiting Condition of Operation, Section 3 of the TS.
c. Failure of an experiment in the Core Experiment Tube (CET) that does not result in a release of radioactive material beyond the confines of the reactor room.
d. Any unanticipated or uncontrolled positive change in reactivity greater than $1.00.

Section B Normal, Emergency and Radiological Control Procedures Page 23 Question B.16

[1.0 point]

What is the most severe class of emergency possible at AFRRI?

a. Class 0, Events less severe than the lowest category
b. Class 1, Notification of unusual events
c. Class 2, Alert
d. Class 3, Site area emergency

Section C Plant and Radiation Monitoring Systems Page 24 Question C.1 [2.0 points, 0.5 each]

MATCH the reactor power instrumentation listed in column A with its corresponding detector type from column B. (Choices from column b may be used more than once or not at all.)

Column A Column B

a. Multi-range Linear Channel
1. Boron Lined Uncompensated Ion Chamber
b. Wide-Range Log Channel
2. Boron Lined Compensated Ion Chamber
c. High Flux Safety Channel 1
3. Unlined Ion Chamber
d. High Flux Safety Channel 2 (Pulse Mode)
4. Fission Chamber
5. Cerenkov Detector Question C.2 [1.0 point]

WHICH ONE of the following best depicts the series of boundaries preventing fission product release to the environment?

a. Core shroud, pool water, positive sealing dampers
b. Pool water, reactor tank wall, high efficiency particulate filters
c. Stainless steel fuel element cladding, pool water, positive sealing dampers, HEPA filters
d. Zirconium hydride lattice structure, pool water, high efficiency particulate filters Question C.3 [1.0 point]

The evaporation of 67 gallons of water causes the pool level to decrease by approximately:

a. 1 inch
b. 5 inches
c. 10 inches
d. 1 foot

Section C Plant and Radiation Monitoring Systems Page 25 Question C.4 [1.0 point]

Which ONE of the following radiation monitors alarming will cause the Reactor Room ventilation system to isolate?

a. Stack Gas Monitor (SGM)
b. Continuous Air Monitor (CAM)
c. Remoter Area Monitor (Bridge)
d. Water Box Gamma Monitor Question C.5 [1.0 point]

WHICH ONE of the following is the purpose of the diffuser pump?

a. Increase heat transfer rate due to increased mixing within the core.
b. Decrease the activation rate of O16 to N16 due to reduced time in core.
c. Increase transport time for N16 to reach surface of pool.
d. Break up of O16 bubbles in pool, thereby decreasing production of N16.

Question C.6 [1.0 point]

The samarium wafer in the fuel rods is used to:

a. Mechanically isolate the graphite from the fuel to prevent carbon from changing the physical properties of the fuel lattice.
b. Increase the rigidity of the fuel elements.
c. Minimize reactivity changes resulting from fission-product buildup and fuel burnup.
d. Monitor fuel temperature.

Section C Plant and Radiation Monitoring Systems Page 26 Question C.7 [1.0 point]

A pipe flange fails just downstream of the primary pump. What design feature of the primary system prevents draining of the pool?

a. Signal from a float switch shuts a valve in the pump suction line.
b. Signal from a float switch shuts off the primary pump.
c. Level in the pool drops below the Net Positive Suction Head pressure minimum required to operate the pump.
d. Level in the pool drops below siphon break holes in the primary suction pipe.

Question C.8 [1.0 point]

Which ONE of the following is the design feature which limits Ar41 production in the exposure rooms?

a. Ventilation within the exposure rooms keeps the room at a low pressure thereby decreasing the amount of Argon in the air.
b. The inside of the exposure rooms is slightly pressurized with a CO2 purge, decreasing the amount of Argon in the air.
c. The inside of the exposure rooms is slightly pressurized with an N2 purge, decreasing the amount of Argon in the air.
d. The walls of the exposure rooms have a gadolinium-oxide paint decreasing the amount of thermal neutrons in the room, thereby decreasing the activation of Argon in the air.

Question C.9 [1.0 point]

The Warm liquid radioactive waste subsystem consists of five _______.

a. 500 gallon tanks
b. 1000 gallon tanks
c. 2500 gallon tanks
d. 5000 gallon tanks

Section C Plant and Radiation Monitoring Systems Page 27 Question C.10

[1.0 point]

Due to an interlock failure, the core is driven into region 2 with the lead shield doors closed.

Which ONE of the following will prevent damage to the core or the doors?

a. The clutch on the lead shield door motor.
b. The reverse contact switch on the core shroud.
c. The clutch on the core drive motor.
d. The core shroud itself.

Question C.11

[1.0 point]

An illuminated yellow light alarm on a RAM indicates:

a. it needs to be calibrated.
b. battery power has switched on.
c. the RAM may be failing or malfunctioning.
d. high radiation level in its immediate area.

Question C.12

[1.0 point]

Which ONE of the following contaminants is most efficiently removed by the demineralizer?

a. Ar41
b. I135
c. mosquito larvae
d. Oil

Section C Plant and Radiation Monitoring Systems Page 28 Question C.13

[2.0 point, 0.5 each]

For a power failure, describe the status of each of the following items in column A with the correct choice from column B Column A Column B

a. Shim, Safety and Regulating Blades
1.

Open

b. Control Room Dampers, D-27 & D-28
2.

Closed

c. Main Isolation Dampers
3.

Inserted

d. Transient Rod
4.

No change Question C.14

[1.0 point]

Which ONE of the listed will NOT cause an alarm at the Security Desk in hallway 3101?

a. Tank Pool Level
b. Remote Area Monitor E-3
c. Continuous Air Monitor (CAM) (Reactor Room, Primary)
d. Remote Area Monitor R-1 Question C.15

[1.0 point]

Which of the following in-core locations all contains fuel elements?

a. A-1, B-1 and C-1
b. A-1, D-7, and D-13
c. C-1, C-7, and C-12
d. E-1, E-7, and G-15

Section C Plant and Radiation Monitoring Systems Page 29 Question C.16

[1.0 point]

Which ONE of the following statements concerning the operation of the fully open and fully closed limit switches on the top of the lead shield door reduction gears is true.

a. The limit switches provide indication only.
b. The control rod magnets may only be energized if the doors are fully open.
c. The core may only be moved into region 2 if the lead shield doors are fully open.
d. Refuel may only be accomplished if the doors are fully closed.

Question C.17

[1.0 point]

Which ONE of the following is the reason that 9 psi air is supplied to the shield door bearings?

a. Prevents grease from escaping from the bearings and binding the door if the seals fail.
b. Prevents air leakage from the reactor tank to the outside atmosphere through the bearings.
c. Provides a lifting Acushion@ to minimize bearing wear during door operation.
d. Provides a seal to minimize ingress of water into the door bearing housing if the seals fail.

Question C.18

[1.0 point]

Which two of the following RAMs are required by 10 CFR 70 to have a battery back-up system?

a. R-1 and R-2
b. R-1 and R-5
c. R-2 and E-3
d. R-5 and E-6

Section A L Theory, Thermo, and Facility Characteristics Page 30 Answer Key A.1 c

REF: Nuclear Reactor Engineering Army Manual, pg. 15 A.2 b

REF: Fundamentals of Nuclear Reactor Engineering (FONRE), ' 66.a, p. 54 A.3 b

REF: T = L/k-1 T =.1/(1.001-1) = 100 N = Noet/T 2 = et/100.693 = t/100 t = 69.3 seconds A.4 a

REF: AFRRI Triga Reactor Health Physics, Terms and Definitions, p. 3.

A.5 b

REF: FONRE, ' 29.d, p. 29 A.6 d

REF: CR = S/(1-K) CR = 100/(1 -.8) = 500 A.7 c

REF: Time is related to ratio of final power to initial power. 2:1 is the largest ratio. Also, FONRE, p. 78, Equation 3-14.

A.8 b

REF: Standard NRC Question A.9 a

REF: FONRE, ' 79.h(3), p. 68 A.10 b

REF: FONRE, ' 18.e.3.a(1), p. 10 A.11 a, 2; b, 1; c, 4; d, 3 REF: FONRE, 24 & 25, pp. 27 & 28 A.12 a

REF: FONRE, ' 45, p. 40.

A.13 c

REF: Nuclear Reactor Engineering Army Manual, eqn. 3-17 A.14 b

Section A L Theory, Thermo, and Facility Characteristics Page 31 REF: FONRE, 92.b & c, pp. 85 &86 A.15 c

REF: P = P0 et/, P = 1.25 Mwatt H e0.1/0.1 = 1.25 H e = 3.3979, Also, FONRE, p. 78, Equation 3-14.

A.16 c

REF: FONRE, ' 149.f, p. 137 A.17 d

REF: U. S. Army Engineers Academic Training Phase, Nuclear Power Plant Operations Course, p. 88 A.18 b

REF: Peak Power is proportional to $prompt 2, FWHM is proportional to 1/$prompt, and Temperature increase is proportional to $prompt NOTE: $prompt = -.

A.19 d

REF: SAR, Ch 4.16

Section B Normal, Emergency and Radiological Control Procedures Page 32 Answer Key B.1 c

REF: 10CFR20 B.2 a, 6; b, 2; c, 2; d, 1 REF: 10CFR55.

B.3 a

REF: T.S. Section 1.3 B.4 d

REF: Reactor Training Manual - Ionizing Radiation B.5 a, 4 b, 2 c, 1 d, 3 REF: Reactor Training Manual - Health Physics B.6 b

REF: 10CFR50.54(y).

B.7 a

REF: Requalification Program.

B.8 c

REF: Operational Procedure 1, TAB A B.9 a, 3; b, 3; c, 1; d, 3; e, 2 REF: Technical Specifications Table 1.

B.10 c

REF: 10 CFR 50.59 B.11 b

REF: T.S. Section 4.2.4c B.12 b

REF: Operational Procedure 1, Tab A B.13 a, LCO; b, LCO; c, SL; d, LCO REF: Technical Specifications 2.1, 2.1 and 2.3.

B.14 d

REF: Emergency Plan ' 6.6 B.15 c

REF: Technical Specifications, Section 1.21

Section B Normal, Emergency and Radiological Control Procedures Page 33 B.16 c

REF: Emergency Plan

Section C Plant and Radiation Monitoring Systems Page 34 Answer Key C.1 a, 4; b, 4; c, 1; d, 5 REF: SAR, 4.11.1 through 4.11.3 C.2 c

REF: SAR, ' 6.3.2 - 6.3.4 C.3 a

REF: SAR, ' 3.4.1 1st &.

C.4 b

REF: SAR ' 3.6.2, Table 3-2 C.5 c

REF: SAR, ' 3.3.5 C.6 c

REF: SAR ' 4.9 C.7 d

REF: SAR, ' 3.3.1 1st &.

C.8 d

REF: SAR, ' 5.2.1, 3rd &.

C.9 d

REF: SAR, ' 3.4.2 C.10 c

REF: Previously administered NRC examination C.11 c

REF: Reactor Training C.12 b

REF: SAR ' 3.3.3 C.13 a, 3; b, 2; c, 4; d, 3 REF: AFRRI Operations Manual, Chapter 4 § D Distribution System for Electrical Power; AFRRI SAR, § Standard Control Rod Drives, § Transient Control Rod Drive C.14 b

REF: SAR ' 3.6, Tables 3-1 and 3-2, and ' 3.3.6. 2nd &

C.15 c

REF: SAR, Fig. 4-3

Section C Plant and Radiation Monitoring Systems Page 35 C.16 c

REF: SAR 4.6 and 43.13.

C.17 d

REF: SAR ' 3.7.4, p. 3-48.

C.18 b

REF: AFRRI supplied question

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