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Examination Report No 50-128/OL 12-02, Texas A&M University
	ML12250A704
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Site:	05000128
Issue date:	09/17/2012
From:	Gregory Bowman; Division of Policy and Rulemaking
To:	Reece W; Texas A&M Univ
	Nguyen J
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September 17, 2012 Dr. Warren D. Reece, Director Texas A&M University System Nuclear Science Center 1095 Nuclear Science Road MS 3575 College Station, Texas 77843-3575

SUBJECT:

EXAMINATION REPORT NO. 50-128/OL-12-02, TEXAS A&M UNIVERSITY

Dear Dr. Reece:

During the week of August 20, 2012, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your Texas A&M University TRIGA Reactor.

The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. 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 Mr. John T. Nguyen at (301) 415-4007 or via internet e-mail John.Nguyen@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. 50-128

Enclosures:

1. Examination Report No. 50-128/OL-12-02

2. Written Examination cc: Jerry E. Newhouse cc: w/o enclosures: See next page

ML12250A704 OFFICE PROB:CE IOLB:LA E PROB:BC NAME JNguyen CRevelle GBowman DATE 08/ 29 /2012 09/ 06 /2012 09/ 17/2012 Texas A&M University Docket No. 50-128 cc:

Mayor, City of College Station P.O. Box Drawer 9960 College Station, TX 77840-3575 Governors Budget and Planning Office P.O. Box 13561 Austin, TX 78711 Texas A&M University System ATTN: Jim Remlinger, Associate Director Nuclear Science Center Texas Engineering Experiment Station 1095 Nuclear Science Road MS 3575 College Station, Texas 77843 Radiation Program Officer Bureau of Radiation Control Dept. Of State Health Services Division for Regulatory Services 1100 West 49th Street, MC 2828 Austin, TX 78756-3189 Susan M. Jablonski Technical Advisor Office of Permitting, Remediation & Registration Texas Commission on Environmental Quality P.O. Box 13087, MS 122 Austin, TX 78711-3087 Test, Research and Training Reactor Newsletter 202 Nuclear Sciences Center University of Florida Gainesville, FL 32611

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-128/OL-12-02 FACILITY DOCKET NO.: 50-128 FACILITY LICENSE NO.: R-83 FACILITY: Texas A&M University TRIGA Reactor EXAMINATION DATES: August 20 - August 23, 2012 SUBMITTED BY: ________/RS/_______________ ___08/29/2012___

John T. Nguyen, Chief Examiner Date

SUMMARY

During the week of August 20, 2012, the NRC administered operator licensing examinations to Three Reactor Operator (RO), one Senior Reactor Operator Instant (SRO-I), and one Senior Reactor Operator Upgrade (SRO-U) license candidates. One SRO-I and one RO candidates failed the Section A, Reactor Theory, Thermo-hydraulics and Facility Operating Characteristics, of the written examination. All other license candidates passed all applicable portions of the examinations.

REPORT DETAILS

1. Examiners: John T. Nguyen, Chief Examiner, NRC

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 2/1 0/1 2/2 Operating Tests 3/0 2/0 5/0 Overall 2/1 1/1 3/2

3. Exit Meeting:

John T. Nguyen, Chief Examiner, NRC Warren D. Reece, Director, Texas A&M University TRIGA Reactor Jerry Newhouse, Reactor Supervisor, Texas A&M University TRIGA Reactor At the conclusion of the meeting, The NRC Examiner thanked the facility for their support in the administration of the examinations. The facility licensee had no comments on the written examination. The examiner also discussed some critical issues noted during the examination including the generic weaknesses in a basic understanding of 10 CFR 50.59 and 10 CFR 20, unfamiliar nuclear instrumentation channels, a lack of knowledge in the thermal power calibration and control rod calibration, and possibly radioactive contamination in front of the MHA door. The facility licensee promised taking actions to improve program performance in the training programs and to conduct a survey in the identified area.

ENCLOSURE 1

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: Texas A&M University REACTOR TYPE: TRIGA DATE ADMINISTERED: 08/20/2012 CANDIDATE: _______________________

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the Answer sheet provided. Attach all Answer sheets to the examination. Point values are indicated in parentheses for each question. A 70% in each category is 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 33.3 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. FACILITY AND RADIATION MONITORING SYSTEMS 60.00 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature ENCLOSURE 1

A. RX THEORY, THERMO & FAC OP CHARS ANSWER SHEET Multiple Choice (Circle or X your choice)

If you change your Answer, write your selection in the blank.

A01 a b c d ___

A02 a b c d ___

A03 a b c d ___

A04 a b c d ___

A05 a b c d ___

A06 a b c d ___

A07 a b c d ___

A08 a ___ b ___ c ___ d ___ (0.25 each)

A09 a b c d ___

A10 a b c d ___

A11 a b c d ___

A12 a b c d ___

A13 a b c d ___

A14 a b c d ___

A15 a b c d ___

A16 a b c d ___

A17 a b c d ___

A18 a b c d ___

A19 a b c d ___

A20 a b c d ___

(***** END OF CATEGORY A *****)

B. NORMAL/EMERG PROCEDURES & RAD CON ANSWER SHEET Multiple Choice (Circle or X your choice)

If you change your Answer, write your selection in the blank.

B01 a b c d ___

B02 a b c d ___

B03 a b c d ___

B04 a b c d ___

B05 a b c d ___

B06 a b c d ___

B07 a b c d ___

B08 a b c d ___

B09 a b c d ___

B10 a b c d ___

B11 a b c d ___

B12 a b c d ___

B13 a ___ b ___ c ___ d ___ (0.25 each)

B14 a b c d ___

B15 a b c d ___

B16 a b c d ___

B17 a b c d ___

B18 a b c d ___

B19 I ___ II ___ III ___ IV ___ (0.25 each)

B20 a b c d ___

(***** END OF CATEGORY B *****)

C. PLANT AND RAD MONITORING SYSTEMS ANSWER SHEET Multiple Choice (Circle or X your choice)

If you change your Answer, write your selection in the blank.

C01 a b c d ___

C02 a b c d ___

C03 a b c d ___

C04 a ___ b ___ c ___ d ___ (0.25 each)

C05 a b c d ___

C06 a b c d ___

C07 a b c d ___

C08 a b c d ___

C09 a b c d ___

C10 a b c d ___

C11 a b c d ___

C12 a ___ b ___ c ___ d ___ (0.5 each)

C13 a b c d ___

C14 a b c d ___

C15 a b c d ___

C16 a b c d ___

C17 a b c d ___

C18 a b c d ___

C19 a b c d ___

(***** END OF CATEGORY C *****)

(********** END OF EXAMINATION **********)

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:

1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.

2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have neither received nor given assistance in completing the examination. This must be done after you complete the examination.

3. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

4. Use black ink or dark pencil only to facilitate legible reproductions.

5. Print your name in the blank provided in the upper right-hand 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 three (3) hours for completion of the examination.

EQUATION SHEET

( )2 eff = 0.1sec 1 Q = m cP T = m H =UAT Pmax =

(2 )

t P = P0 e S S SCR = * =1x104 sec 1 K eff eff +

SUR = 26 .06

( ) (

CR1 1 K eff1 = CR2 1 K eff 2 ) CR1 ( 1 ) = CR2 ( 2 )

(1 ) M=

1

= 2 CR P = P0 10SUR(t )

P= P0 1 K eff CR1 1 K eff1 1 K eff

M= SDM = =

1 K eff 2 K eff

0.693 K eff 2 K eff1

+ T1 =

eff 2 K eff1 K eff 2 K eff 1

= DR = DR0 et 2 DR1 d1 = DR2 d 2 2

K eff 6 Ci E (n ) ( 2 )2 = (1 )2 DR =

R2 Peak2 Peak1 DR - Rem, 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

TEXAS A&M UNIVERSITY TRIGA REACTOR Operator Licensing Examination Week of August 20, 2012 ENCLOSURE 2

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 1 QUESTION A.1 [1.0 points]

Reactor is at full power. The operator immediately scrams all control rods into the core. This insertion will cause:

Given:

T: reactor period, *: Prompt neutron lifetime; : reactivity insertion; : beta fraction

a. The delayed period to be equal to 80 seconds

b. A number of prompt neutrons equals to a number of delayed neutrons

c. The immediate period to be a function of the prompt neutron lifetime (T=*/)

d. A sudden change of power that equals to the initial power multiplied by (1- )/ ( -)

QUESTION A.2 [1.0 point]

Which ONE of the following is a correct statement of why delayed neutrons enhance the ability to control reactor power?

a. Prompt neutrons are born at lower energy levels than delayed neutrons

b. Prompt neutrons can cause fissions in both U-235 and U-238; whereas delayed neutrons can only cause fissions in U-235

c. Delayed neutrons increase the average neutron lifetime that allows a reactor to be controlled

d. The average number of delayed neutrons produced per fission is higher than the average number of prompt neutrons QUESTION A.3 [1.0 point]

A reactor with Keff = 0.8 contributes 1000 neutrons in the first generation. Changing from the first generation to the THIRD generation, how many TOTAL neutrons are there after the third generation?

a. 1800

b. 2440

c. 3240

d. 6400

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 2 QUESTION A.4 [1.0 point]

Which ONE of the following will be the resulting stable reactor period when a $0.25 reactivity insertion is made into an exactly critical reactor core? Neglect any effects from prompt. Given

=0.0070 and =0.1

a. 15 seconds

b. 20 seconds

c. 25 seconds

d. 30 seconds QUESTION A.5 [1.0 point]

A nuclear reactor startup is being performed by adding EQUAL amounts of positive reactivity and waiting for neutron population to stabilize. As the reactor approaches criticality, the Neutron Multiplication, Keff, will __________ after each reactivity addition; and the time required for the neutron population to STABILIZE will ___________ after each reactivity addition.

a. decrease; decrease

b. increase; increase

c. increase; decrease

d. remains the same; increase

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 3 QUESTION A.6 [1.0 point]

Given the following Core Reactivity Data during startup:

Control Rod Total Rod Worth Rod Worth removed

($) at 5 watts critical ($)

SAFE/SHIM 3.00 2.00 Rod 1 REG Rod 1.50 0.50 (scrammable)

SAFE/SHIM 2.50 1.00 Rod 2 TRANS Rod 4.00 3.20 The TECHNICAL SPECIFICATION LIMIT for Shutdown Margin for this core is:

a. $2.7

b. $3.7

c. $4.3

d. $6.7 QUESTION A.7 [1.0 point]

Which ONE of the following best describes the alpha decay of a nuclide?

a. The atomic mass number unchanged and the number of protons decreases by 2

b. The atomic mass number decrease by 2 and the number of protons decreases by 2

c. The atomic mass number increases by 4 and the number of protons increases by 2

d. The atomic mass number decreases by 4 and the number of protons decreases by 2

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 4 QUESTION A.8 [1.0 point, 0.25 each]

Fill out the blank with INCREASE or DECREASE due to effects of moderator temperature increase.

a. Slowing down length _____________.

b. Thermal non leakage _____________.

c. Fast non leakage _____________.

d. Rod worth _____________.

QUESTION A.9 [1.0 point]

You are the reactor operator performing two pulsing operations. The first pulse has a reactivity worth of $1.20 which results in a peak power of 200 MW. If the second pulse has a reactivity worth of $2.00, the corresponding peak power is:

Given:

=0.0070

a. 1000 MW

b. 1750 MW

c. 2500 MW

d. 5000 MW QUESTION A.10 [1.0 point]

Which ONE of the following physical characteristics of the TRIGA fuel is the MAIN contributor for the prompt negative temperature coefficient?

a. As the fuel heats up the resonance absorption peaks broaden and increases the likelihood of absorption in U-238 and/or Pu-240

b. As the fuel heats up a rapid increase in moderator temperature occurs through conduction and convection heat transfer mechanisms which adds negative reactivity

c. As the fuel heats up fission product poisons (e.g., Xe) increase in concentration within the fuel matrix and add negative reactivity via neutron absorption

d. As the fuel heats up the oscillating hydrogen in the ZrH lattice imparts energy to a thermal neutron, thereby increasing its mean free path and probability of escape

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 5 QUESTION A.11 [1.0 point]

Which of the following is the definition for reactivity ()?

a. The measure of a reactors departure from criticality

b. The time required for power to change by a factor of e

c. The fraction of all fission neutrons that are born as delayed neutrons

d. The faction of number of neutrons of current generation and number of neutrons of the previous generation QUESTION A.12 [1.0 point]

Prompt neutrons are produced by:

a. decay of N-16

b. directly from the fission

c. decayed fission fragments

d. Pair Production of high energy photon QUESTION A.13 [1.0 point]

The reactor is critical. The reactor operator accidentally inserts an experiment in the core and Keff changes to 1.010. What is the period of the reactor? Given a prompt neutron lifetime (*) of 1 x 10 -4 seconds.

a. 0.001 sec

b. 0.01 sec

c. 0.10 sec

d. 1.0 sec

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 6 QUESTION A.14 [1.0 point]

In a subcritical reactor with Keff of 0.931, a reactivity worth of 0.017 k is inserted into the reactor core. Which ONE of the following is the NEW Keff ?

a. 0.925

b. 0.933

c. 0.946

d. 1.001 QUESTION A.15 [1.0 point]

Which one of the following describe the difference between a moderator and reflector?

a. A reflector increases the fast non-leakage factor and a moderator increases the thermal utilization factor.

b. A reflector increases the neutron production factor and a moderator increases the fast fission factor.

c. A reflector decreases the thermal utilization factor and a moderator increases the fast fission factor.

d. A reflector decreases the neutron production factor and a moderator decreases the fast non-leakage factor.

QUESTION A.16 [1.0 point]

Which ONE of the following is the most correct reason for having an installed neutron source within the core?

An installed neutron source is very important during startup because without of a neutron source...

a. the chain reaction in the reactor core would NOT start

b. the startup channel would NEVER indicate neutron population

c. the compensating voltage on the source range detector doesnt work

d. the reactor could result in a sudden increase in power if the control rods were pulled out far enough

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 7 QUESTION A.17 [1.0 point]

Reactor power is increasing by a factor of 5 every minute. The reactor period is:

a. 65 seconds

b. 37 seconds

c. 26 seconds

d. 13 seconds QUESTION A.18 [1.0 point]

The reactor is shutdown. Which ONE of the following correctly describes the reactor behavior when a reactivity worth of $1.00 is inserted to the reactor core?

a. Subcritical

b. Critical

c. Supercritical

d. Prompt critical QUESTION A.19 [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%

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 8 QUESTION A.20 [1.0 point]

Which ONE of the following statements correctly describes thermal neutrons?

a. A neutron that experiences a linear decrease in energy as the temperature of the moderator increases.

b. A neutron that experiences no net change in energy after several collisions with atoms of the moderator.

c. A neutron that experiences an increase in energy levels after collisions with larger atoms of the moderator.

d. A neutron at resonant epithermal energy levels that causes fissions to occur in U-238.

- - - - End of Section A ********************************

Section B - Normal/Emergency Procedures and Radiological Controls Page 9 QUESTION B.1 [1.0 point]

Which ONE of the following statements is NOT true regarding to the NSC limitation of experiments?

a. The reactivity worth of any single experiments shall be less than $2.00

b. The total facility Xe-125 inventory of all experiment shall not exceed 3500 Ci

c. Explosive materials in quantities greater than 10 mg shall not be irradiated in the reactor or irradiation facilities

d. The absolute value of the reactivity worth of any single unsecured experiment shall be less than $1.00 QUESTION B.2 [1.0 point]

The NSC TRIGA reactor has been shutdown due to a fuel element leak. Which ONE of the following radioactive GASES poses the most significant hazard during the research for the leaking fuel element? (Assume the fuel element is leaking during the search)?

a. Ar-41

b. I-125

c. Cs-137

d. N-16 QUESTION B.3 [1.0 point]

Per NSC Technical Specification, what is the MINIMUM level of management who may direct any unloading of fuel within the reactor core?

a. Yourself as a Reactor Operator

b. Senior Reactor Operator

c. Reactor Facility Director

d. The Reactor Operations Committee

Section B - Normal/Emergency Procedures and Radiological Controls Page 10 QUESTION B.4 [1.0 point]

Which ONE of the following is the definition of the Site Boundary for the NSC reactor facility?

a. The reactor building

b. The laboratory building

c. The reactor bay and reactor room

d. The chain-link fence which surrounds the reactor building QUESTION B.5 [1.0 point]

Before entering to the experimental facility, you see a sign at the door CAUTION, HIGH RADIATION AREA. You would expect that radiation level in the facility could result in an individual receiving a dose equivalent of:

a. 5 mRem/hr at 30 cm from the source

b. 100 mRem/hr at 1 m from the source

c. 100 mRem/hr at 30 cm from the source

d. 500 Rads/hr at 1 m from the source QUESTION B.6 [1.0 point]

According to NSC Tech Spec, which ONE of the following would most likely be considered a Special Report (the Facility shall report to the NRC no later than the following working day)?

a. You receive a fire alarm during reactor operation

b. You did not pay attention while raising the control rods to power, which causes reactor scram

c. You observe an abnormal loss of core coolant at a rate that exceeds the normal makeup capacity.

d. You load an unknown sample to the core, which causes an unexplained change in a $1.20 worth of reactivity.

Section B - Normal/Emergency Procedures and Radiological Controls Page 11 QUESTION B.07 [1.0 point]

Which ONE of the following would be an initiating condition for an ALERT status?

a. Major fire in the control room

b. Explosion in the reactor building

c. Earthquake with personnel injury

d. Release of Xe-125 equal to 800 Ci QUESTION B.8 [1.0 point]

Per SOP II-C, the MINIMUM staff required in the control room during a reactor startup is:

a. A Reactor Operator

b. A Senior Reactor Operator

c. A Senior Reactor Operator + any staff

d. A Senior Reactor Operator + a Reactor Operator QUESTION B.9 [1.0 point]

The reactor shall not be operated unless the Continuous Air Radiation Monitor is operable.

This is an example of:

a. a Safety Limit (SL)

b. a Surveillance Requirement (SR)

c. a Limiting Safety System Setting (LSSS)

d. a Limiting Conditions for Operation (LCO)

Section B - Normal/Emergency Procedures and Radiological Controls Page 12 QUESTION B.10 [1.0 point]

A radioactive source reads 50 Rem/hr on contact. Five hours later, the same source reads 5.0 Rem/hr. How long is the time for the source to decay from a reading of 50 Rem/hr to 50 mRem/hr?

a. 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months

b. 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months

c. 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months

d. 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months QUESTION B.11 [1.0 point]

Which ONE of the following conditions requires the NRC APPROVAL for changes?

a. Revise the Safety Analysis Report

b. Major changes in the SOP II-E, Pulsing Operation

c. Revise the requalification operator licensing examination

d. Reduce the minimum number of the Reactor Safety Board members from three to two QUESTION B.12 [1.0 point]

The radiation from an unshielded source is 1 rem/hr. You insert 60 mm thickness of lead sheet; the radiation level reduces to 125 mrem/hr. What is the half-value-layer of lead? (HVL:

thickness of lead required so that the original intensity will be reduced by half)?

a. 10 mm

b. 20 mm

c. 30 mm

d. 40 mm

Section B - Normal/Emergency Procedures and Radiological Controls Page 13 QUESTION B.13 [1.0 point, 0.25 each]

Match each Access Level listed in column A with its associated Badge Color in column B.

Column A Column B

a. Visitor 1. Green

b. Ground Access 2. Yellow

c. Limited Access 3. Blue

d. Unescorted Access 4. Orange QUESTION B.14 [1.0 point]

Use the following diagram of an instrumented fuel element. Which ONE of the following is the correct match for the position locator (Column A) to the correct component (Column B)?

Column A Column B I A. Zirconium Hydride-Uranium II B. Stainless steel III C. Samarium Burnable Poison IV D. Graphite Reflector E. Zirconium Rod F. Spacer G. Thermocouples

a. I-C, II-F, III-A, IV-C

b. I-D, II-A, III-E, IV-C

c. I-D, II-E, III-A, IV-G

d. I-C, II-B, III-E, IV-G

Section B - Normal/Emergency Procedures and Radiological Controls Page 14

Section B - Normal/Emergency Procedures and Radiological Controls Page 15 QUESTION B.15 [1.0 point]

Guidance for the physical protection of the Special Nuclear Material can be found in:

a. 10 CFR Part 26

b. 10 CFR Part 50.59

c. 10 CFR Part 55

d. 10 CFR Part 73 QUESTION B.16 [1.0 point]

Which one of the following is the definition of Total Effective Dose Equivalent (TEDE) specified in 10 CFR Part 20?

a. The sum of thyroid dose and external dose.

b. The sum of the external deep dose and the organ dose.

c. The sum of the deep dose equivalent and the committed effective dose equivalent.

d. The dose that your whole body is received from the source, but excluded from the deep dose.

QUESTION B.17 [1.0 point]

A reactor operator sees a tag marked 99-24-3. It means:

a. the tag was issued on March 24 th, 1999

b. the tag was the 24 th tag of the 3 rd tag group, in 1999

c. the tag was the 1999 th tag of the 24 th tag group, in 2003

d. the tag was the 3 rd tag of the 24 th tag group, in 1999

Section B - Normal/Emergency Procedures and Radiological Controls Page 16 QUESTION B.18 [1.0 point]

A survey instrument with a window probe is used to measure the beta-gamma dose rate from an irradiated experiment. The dose rate is 100 mrem/hour with the window opened and 60 mrem/hour with the window closed. The gamma dose rate is:

a. 40 mrem/hour

b. 60 mrem/hour

c. 100 mrem/hour.

d. 160 mrem/hour QUESTION B.19 [1.0 point, 0.25 each]

Use the following diagram of the FUEL FOLLOWED control rod. Match for the position locator listed Column A to the correct materials listed in Column B Column A Column B I A. Fuel II B. Stainless steel plug III C. Void IV D. Borated Graphite E. Zirconium Rod

Section B - Normal/Emergency Procedures and Radiological Controls Page 17

Section B - Normal/Emergency Procedures and Radiological Controls Page 18 QUESTION B.20 [1.0 point]

Which ONE of the following is the 10CFR20 definition for Annual Limit on Intake (ALI)?

a. The concentration of a radionuclide in air which, if inhaled by an adult worker for a year, would result in a total effective dose equivalent of 100 millirem

b. Projected dose commitment values to individuals, that warrant protective action following a release of radioactive material

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 millirem for noble gases

d. 10CFR20 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

- - - - End of Section B ********************************

Section C: Plant and Rad Monitoring Systems Page 19 QUESTION C.1 [1.0 point]

Which ONE of the following correctly describes the method used to detect radioactivity in the cooling tower if a possible leak in the heat exchanger?

a. Collect and analyze the cooling tower sample by monthly

b. Place a Continuous Air monitor near the cooling tower and check by daily

c. Place a radiation area monitor near the cooling tower and check by daily

d. Place a radiation area monitor near the heat exchanger and check by weekly QUESTION C.2 [1.0 point]

Which ONE of the following correctly describes the Pool Level Alarm? When the pool level falls to approximately 90% of normal operating level, it will initiate:

a. a visual and audible alarms in the control room ONLY

b. a visual and audible alarms University Communications Room ONLY

c. a visual and audible alarms in the control room and University Communications Room; and a visual alarm in the Director Office

d. a visual and audible alarms in the control room and University Communications room; and a visual alarm in the Reception Room QUESTION C.3 [1.0 point]

Which ONE of the statements below describes the operation of the three-way solenoid valve of the Transient rod air system?

a. When the solenoid valve is energized, the vent (exhaust) port is closed, the supply port is opened and the actual port (to the cylinder) is opened. Air from the accumulator is continuously supplied to the pneumatic cylinder of the Transient rod.

b. When the solenoid valve energized, the supply port is opened and the actual port is closed.

Air from the accumulator is vented through the vent port.

c. When the solenoid valve is de-energized, the vent (exhaust) port is closed, the supply port is opened and the actual port (to the cylinder) is opened. Air from the accumulator is continuously supplied to the pneumatic cylinder of the Transient rod.

d. When the solenoid valve de-energized; the vent port is closed. Air flows from pneumatic cylinder back to the accumulator.

Section C: Plant and Rad Monitoring Systems Page 20 Question C.4 [1.0 point, 0.25 each]

Match the inputs listed in column A with their responses listed in column B. (Items in column B may be used more than once or not at all). Assume the reactor is in operation.

Column A Column B

a. Log Power =3 mW 1. Indicate only

b. Detector Supply Voltage=100 V 2. Interlocks

c. Pool water conductivity = 1 micomho/cm 3. Scram

d. Withdrawal of Shim and Transient rods simultaneously in Steady State mode QUESTION C.5 [1.0 point]

The reactor operator is conducting the Thermal Power Calibration (Power Calorimetric). Which ONE of the following is an initial setup before recording pool temperature?

a. Primary water system: ON, Secondary water system: ON, Power level: 40 kW

b. Primary water system: ON, Secondary water system: OFF, Power level: 400 KW

c. Primary water system: OFF, Secondary water system: ON, Power level: 40 kW

d. Primary water system: OFF, Secondary water system: OFF, Power level: 400 kW

Section C: Plant and Rad Monitoring Systems Page 21

Section C: Plant and Rad Monitoring Systems Page 22 QUESTION C.6 [1.0 point]

During a reactor operation, you discover the Particulate Air Monitor and the Continuous Air Monitor pump failure. Other monitors are operating. Which ONE of the following is the best action?

a. Continue to operate because the pump failure does NOT affect the operations of these monitors

b. Continue to operate because the Area Radiation and Gas Radiation Monitors are still working

c. Shutdown the reactor; immediately report the result to the supervisor because these monitors are inoperable due to a pump failure; and their failure considers a Tech Spec violation d Shutdown the reactor, immediately report the result to the U.S. NRC because it is a reportable occurrence QUESTION C.7 [1.0 point]

The Log Power Channel consists of:

a. Fission Chamber and Log Power Monitor

b. Fission Chamber and Wide Range Linear Monitor

c. Compensated Ion Chamber and Log Power Monitor

d. Uncompensated Ion Chamber and Safety Drawer QUESTION C.8 [1.0 point]

The attached figure, Figure II-K-2, depicts:

a. the In-hour Curves

b. the Rod Drop Worth Curves

c. the Period-Differential Worth Curves

d. the Control Rod Scram Time Curves

Section C: Plant and Rad Monitoring Systems Page 23 QUESTION C.9 [1.0 point]

Which ONE of the following is the correct source used to calibrate the Area Radiation Monitor?

a. Ar-41

b. Cs-137

c. P-10

d. Xe-125 QUESTION C.10 [1.0 point]

You perform a fuel element inspection. In measuring the transverse bend, you find the bend of one fuel element exceeds the original length by 0.126 inches. For this measurement, you will:

a. continue the fuel inspection because this bend is within TS limit

b. continue the fuel inspection because the NSC Tech Spec requires the elongation measurement only

c. stop the fuel inspection; immediately report the result to the supervisor because it is considered a damaged fuel element d stop the fuel inspection, immediately report the result to the U.S. NRC since it is a reportable occurrence QUESTION C.11 [1.0 point]

Which ONE of the following can cause the control rod interlock when a steady state mode is selected?

a. SHIM rod drive DOWN and SHIM control rod DOWN

b. Pneumatic cylinder DOWN and supply air energized

c. SHIM rod drive UP and SHIM control rod DOWN

d. Pneumatic cylinder UP and supply air is ready

Section C: Plant and Rad Monitoring Systems Page 24 Question C.12 [2.0 points, 0.5 each]

Match each instrument (channel) listed in column A with a specific purpose in column B. Items in column B is to be used only once.

Column A Column B

a. Log Power Channel 1. Provide a high power scram

b. Safety Power Channel 2. Provide Energy (Mw-sec) information.

c. Pulse Channel 3. Provide a low count rate interlock

d. Wide Range Linear Channel 4. Control the regulating rod in automatic mode.

QUESTION C.13 [1.0 point]

Per SOP II-K, the control rod worth calibration for the positive period method, the operators will establish the critical power level at ________ before withdrawal of the calibrated rod.

a. 1 W

b. 5 W

c. 30 W

d. 100 W QUESTION C.14 [1.0 point]

Which ONE of the following best describes on how the compensated Ion Chamber (CIC) and Fission Chamber (FC) operate?

a. The CIC has two chambers, both can sense gamma rays but only one is coated with boron-10 for (n,) reaction; whereas FC is coated with U-235 for fission reaction.

b. The CIC has two chambers, one is coated with U-235 for fission reaction and the other is coated with boron-10 for (n,) reaction; whereas the FC has only one chamber coated with U-235 for fission reaction.

c. The CIC has only one chamber coated with boron-10 for (n,) reaction; whereas the FC is coated with U-235 for fission reaction.

d. The CIC has only one chamber coated with U-235 for fission reaction, whereas the FC has two chambers, both can sense gamma rays but only one is coated with U-235 for fission reaction.

Section C: Plant and Rad Monitoring Systems Page 25 QUESTION C.15 [1.0 point, 0.25 each]

During the calibration of the NSCR Pulse Channel, you depress and hold the Pulse Cal button on the Power Range Monitor Module, the power displayed is approximately:

a. 100 MW

b. 500 MW

c. 1000 MW

d. 2000 MW QUESTION C.16 [1.0 point]

During reactor operation, a leak develops in the SECONDARY to PRIMARY heat exchanger.

Which ONE of the following correctly explains the reactor pool level?

a. Pool level will increase because the Primary pressure is HIGHER than the Secondary pressure

b. Pool Level will decrease because the Primary pressure is LOWER than the Secondary pressure

c. Pool Level will be the same because the Primary pressure is EQUAL to the Secondary pressure

d. Pool Level will decrease because the Primary pressure is HIGHER than Secondary pressure QUESTION C.17 [1.0 point]

The Pulse drawer in the STEADY STATE Mode provides the indications of:

a. Percent Power ONLY

b. Percent Power and 1 KW Interlock

c. Energy (Mw-sec) and Low Count Rate

d. Peak Power and Energy (Mw-sec)

Section C: Plant and Rad Monitoring Systems Page 26 QUESTION C.18 [1.0 point]

After an annual calibration, you bring the reactor to full power and notice that the fuel temperature increases to 530 °C. For this indication, you will:

a. continue operation because the indication is normal at full power

b. scram reactor because of a potential violation of the Tech Spec LCO

c. scram reactor because of a potential violation of the Tech Spec LSSS d scram reactor because of a potential violation of the Tech Spec SL QUESTION C.19 [1.0 point]

During reactor operation, you accidentally open the door of the Beam Port #1. Your action will cause:

a. an annuciator light in the control room

b. a reactor interlock

c. a reactor scram

d. no indication

- - - - End of Section C *****************************

- - - - End of the Exam ***************************

Section A L Theory, Thermo & Facility Operating Characteristics Page 27 A.1 Answer d

Reference:

=$* =$0.25*0.007 =0.00175 k T = (-)/

T = (0.0070 - 0.00175)/0.1 x 0.00175 = 30 seconds A.5 Answer b

Reference:

NRC Standard Question A.6 Answer: a

Reference:

Tech Spec SDM = 3total rod worth removed at critical - most reactivity control rod worth= $6.7 -$4.0 = $2.7 A.7 Answer d

Reference:

Chart of the Nuclides A.8 Answer: a, Increase b, Decrease c, Decrease d, Increase

Reference:

Section A L Theory, Thermo & Facility Operating Characteristics Page 28 A.9 Answer: d 2

( 2 - )2 ( 1 - )

=

Peak 2 Peak 1

=($)*; 1=$1.20*0.007= 0.0084 k/k 2=$2.0*0.007= 0.014 k/k Peak2 = Peak1*(0.014-.007/.0084-.007)2 = 5000 MW Or Peak2 = Peak1*($2-$1 / $1.2-$1)2 = 5000 MW A.10 Answer: d

Reference:

TRIGA Fuel Design A.11 Answer: a

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2 A.12 Answer: b

Reference:

A.13 Answer: b

Reference:

Using equations provided in the equation sheet:

= (1.01-1)/1.01

( K eff - 1)

= = 0.01 K eff For prompt,

= 0.0001/0.01 = 0.01 sec

=

A.14 Answer: c

Reference:

= (Keff1-Keff2)/(Keff1*Keff2). 0.017 = (x-0.931)/(x*0.931); 0.017*0.931*x =x-0.931 0.01583x=x-0.931; 0.98417x =0.931; x=0.931/0.98417; x=0.946

Section A L Theory, Thermo & Facility Operating Characteristics Page 29 A.15 Answer: a

Reference:

Glasstone & Sesonke, Nuclear Reactor Engineering, Chapter 1 A.16 Answer: d

Reference:

NRC Standard Question A.17 Answer: b

Reference:

P=Poet/ J = 60 sec/ln(5) = 37.28 sec A.18 Answer: a

Reference:

Time is related to ratio of final power to initial power. 2:1 is the largest ratio.

A.20 Answer: b

Reference:

NRC Standard Question

Section B Normal, Emergency and Radiological Control Procedures Page 30 B.1 Answer: c

Reference:

NSC Technical Specification, Section 3.6.1 and 3.6.3 B.2 Answer: b

Reference:

Standard NRC question B.3 Answer: b

Reference:

Technical Specifications 6.1.3 B.4 Answer: d

Reference:

Emergency Plan, Section 2.3 B.5 Answer: c

Reference:

10 CFR 20.1003 B.6 Answer: d

Reference:

TS 6.6.2 and TS1.28 B.7 Answer: d

Reference:

Emergency Procedure,Section IX B.8 Answer: d

Reference:

SOP II- C B.9 Answer: d

Reference:

TS 3.1 B.10 Answer: b

Reference:

DR = DR*e -t 5.0 rem/hr =50 rem/hr* e -(5hr)

Ln(5.0/50) = -*5 --> =0.4605; solve for t: Ln(.05/50)=-0.4605 (t) t=15 hours or Reduce from 50 Rem to 5 Rem: 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months From 5 Rem to 0.5 Rem: 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months From 0.5 Rem to 0.05 Rem: 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Total: 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months

Section B Normal, Emergency and Radiological Control Procedures Page 31 B.11 Answer: d

Reference:

TS 6.2.1 and 10 CFR 50.59 B.12 Answer: b

Reference:

DR = DR*e -X Find : 125 = 1000* e -*60 ; = 0.03466 If insertion of an HVL (thickness of lead), the original intensity will be reduced by half.

Find X: 1 = 2* e -0.03466*X ; X= 20 mm Find HVL by shortcut:

1000mR- 500 mR is the 1st HVL 500 mR - 250 mR is the 2nd HVL 500mR-125 mR is the 3rd HVL So HVL=60mm/3 = 20 mm B.13 Answer: a(2) b(1) c(4) d(3)

Reference:

SOP VII-D, page 2 B.14 Answer: c

Reference:

SAR, Figure 4-9 B.15 Answer: d

Reference:

SOP VIII-H and 10 CFR Part 73 B.16 Answer: c

Reference:

10 CFR 20.

B.17 Answer: d

Reference:

System Tag Procedure B.18 Answer: b

Reference:

Basic Radiation Instrumentation B.19 Answer: I, C II, B III,D IV,A

Reference:

SAR 4.2.2 B.20 Answer: d.

Reference:

10CFR20.1003 Definitions

Section C Facility and Radiation Monitoring Systems Page 32 C.1 Answer: a

Reference:

SOP VII-B4 C.2 Answer: d

Reference:

SOP III-O, Reactor Pool Surveillance C.3 Answer: a

Reference:

SOP III-J, Air Supply System Maintenance C.4 Answer: a(2) b(3) c(1) d(2)

Reference:

SAR table 7.1 C.5 Answer: b

Reference:

SOP II-J, Power Calibration C.6 Answer: c

Reference:

TS 3.5 C.7 Answer: a

Reference:

SAR 7.2.3.1 C.8 Answer: b

Reference:

SOP II-K, Control Rod Calibration C.9 Answer: b

Reference:

SOP VII-B7 C.10 Answer: c

Reference:

TS 4.2.4 C.11 Answer: d

Reference:

Information during a walkthrough

Section C Facility and Radiation Monitoring Systems Page 33 C.12 Answer: a(3) b(1) c(2) d(4)

Reference : SAR 7.2 C.13 Answer: c

Reference:

SOP II-k, Section 3 C.14 Answer: a

Reference:

Information during a walkthrough C.15 Answer: d

Reference:

SOP II-L C.16 Answer: d

Reference:

SAR 5.1 and figure 5-4 C.17 Answer: a

Reference:

SAR 7.2.3.2 and figure 7-1 C.18 Answer: c

Reference:

TS 2.2 C.19 Answer: a

Reference:

SOP IV-D

ML12250A704

Text

SUBJECT:

Dear Dr. Reece:

Enclosures:

SUMMARY

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