ML050450465

Initial Examination Report No. 50-602/OL-05-01, University of Texas, January 24, 2005

ML050450465
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Site:	University of Texas at Austin
Issue date:	02/28/2005
From:	Madden P NRC/NRR/DRIP/RNRP
To:	Landsberger S Univ of Texas
Young P, NRC/NRR/DRIP/RNRP, 415-4094
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50-602/05-01
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February 28, 2005 Dr. Sheldon Landsberger Nuclear Engineering Teaching Laboratory 10100 Burnet Road University of Texas at Austin Austin, TX 78758

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-602/OL-05-01, UNIVERSITY OF TEXAS

Dear Dr. Landsberger:

During the week of January 24, 2005, the NRC administered operator licensing examinations at your Nuclear Engineering Teaching Laboratory. The examination was conducted in accordance with NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards,"

Revision 1.

In accordance with 10 CFR 2.390 of the Commission's 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 document system (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/NRC/ADAMS/indesx.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Phillip T. Young at 301-415-4094 or via Internet e-mail at pty@nrc.gov.

Sincerely,

/RA/

Patrick M. Madden, Section Chief Research and Test Reactors Section New, Research and Test Reactors Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-602

Enclosures:

1. Initial Examination Report No. NO. 50-602/OL-05-01

2. Facility comments with NRC resolution

3. Examination and answer key (RO/SRO) cc w/encls.: Please see next page

University of Texas Docket No. 50-602 cc:

Governors Budget and Planning Office P.O. Box 13561 Austin, TX 78711 Bureau of Radiation Control State of Texas 1100 West 49th Street Austin, TX 78756 Mr. Roger Mulder Office of the Governor P.O. Box 12428 Austin, TX 78711 Dr. Sheldon Landsberger, Director Nuclear Engineering Teaching Laboratory The University of Texas at Austin 10100 Burnet Road Austin, TX 78758 Dr. William Vernetson Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

February 28, 2005 Dr. Sheldon Landsberger Nuclear Engineering Teaching Laboratory 10100 Burnet Road University of Texas at Austin Austin, TX 78758

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-602/OL-05-01, UNIVERSITY OF TEXAS

Dear Dr. Landsberger:

During the week of January 24, 2005, the NRC administered operator licensing examinations at your Nuclear Engineering Teaching Laboratory. The examination was conducted in accordance with NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards,"

Revision 1.

In accordance with 10 CFR 2.390 of the Commission's 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 document system (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/NRC/ADAMS/indesx.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Phillip T. Young at 301-415-4094 or via Internet e-mail at pty@nrc.gov.

Sincerely,

/RA/

Patrick M. Madden, Section Chief Research and Test Reactors Section New, Research and Test Reactors Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-602

Enclosures:

1. Initial Examination Report No. NO. 50-602/OL-05-01

2. Facility comments with NRC resolution

3. Examination and answer key (RO/SRO) cc w/encls.: Please see next page DISTRIBUTION w/ encls.:

PUBLIC RNRP\\R&TR r/f PMadden AAdams Facility File (EBarnhill) O-6 F-2 ADAMS Package Accession No.: ML043200631 ADAMS Report Accession No.: ML050450465 TEMPLATE #: NRR-074 OFFICE RNRP:E/UI E

IROB:LA RNRP:SC NAME PYoung EBarnhill PMadden DATE 02/ 14 /2005 02/ 16 /2005 02/ 16 /2005 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY

ENCLOSURE 1 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:

50-602/OL-05-01 FACILITY DOCKET NO.:

50-602 FACILITY LICENSE NO.:

R-129 FACILITY:

University of Texas EXAMINATION DATES:

01/26/2005 EXAMINER:

Phillip T. Young, Chief Examiner SUBMITTED BY:

/RA/

02/ 14 /2005 Phillip T. Young, Chief Examiner Date

SUMMARY

During the week of January 24, 2005, NRC administered Operator Licensing examinations to one Senior Reactor Operator (SRO). The one SRO candidate passed the examinations.

REPORT DETAILS 1.

Examiners:

Phillip T. Young, Chief Examiner 2.

Results:

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

Exit Meeting:

Personnel attending:

Sean O'Kelly, Associate Director Michael G. Krause, Reactor Supervisor Phillip Young, NRC The examiner thanked the facility for their support in conducting the examinations.

Facility Comments Regarding NRC Exam Administered on January 26, 2005 NONE

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION (Examination with Answer Key}

FACILITY:

University of Texas REACTOR TYPE:

TRIGA DATE ADMINISTERED:

01/26/2005 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 brackets for each question. A 70% in each section is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

% of Category % of 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.

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

A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS Question:

A.001

[1.0 point]

{1 You enter the control room and and no rods are in motion. Which a.

The reactor is critical.

b.

The reactor is subcritical.

c.

The reactor is supercritical.

d.

The neutron source has been removed from the Answer A.001 c.

Reference:

Standard NRC QUESTION Question:

A.002

[1.0 point]

{2.0}

Which factor of the Six Factor formula is most easily varied by the reactor a.

Thermal Utilization Factor (f) b.

Reproduction Factor (

)

c.

Fast Fission Factor (

)

d.

Fast Non-Leakage Factor (Lf )

Answer:

A.002 a.

Reference:

Burn, R.,

Introduction to Nuclear Reactor Operations

, © 1982, § 3.2, pp. 3-13 3-18.

A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS Question:

A.003

[1.0 point]

{3 You perform two initial startups conditions, (core burnup, pool and difference between the two startups answer the phone. For the second sta first startup.

Rod Height Count Rate a.

Higher Same b.

Lower Same c.

Same Lower d.

Same Higher Answer A.003 d.

Reference:

Burn, R.,

Introduction to Nuclear Reactor Operations

, © 1982, § 5.7, pp. 5-28 5-38.

Question:

A.004

[1.0 point]

{4.0}

Which one of the following atoms will cause a neutron to lose the most energy in an elas collision?

a.

Uranium 238 b.

Carbon 12 c.

Hydrogen 2 d.

Hydrogen 1 Answer:

A.004 d.

Reference:

Burn, R.,

Introduction to Nuclear Reactor Operations,

© 1988, § 2.5.3 p. 2-45.

A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS Question:

A.005

[1.0 point]

{5 For most materials the neutron a.

increases as neutron energy incr b.

decreases as neutron energy increas c.

increases as target nucleus mass increas d.

decreases as target nucleus mass increases Answer:

A.005 b.

Reference:

Burn, R.,

Introduction to Nuclear Reactor Operations

, © 1982, § 2.5.1 p. 2-36.

Question:

A.006

[1.0 point]

{6.0}

As primary coolant temperature increases, rod worth:

a.

increases due to higher reflector efficiency.

b.

decreases due to higher neutron absorption in the moderator.

c.

increases due to the increase in thermal diffusion length.

d.

remains the same due to constant poison cross-section of the control rods.

Answer:

A.006 c.

Reference:

Burn, R.,

Introduction to Nuclear Reactor Operations

, © 1982, § 3.3.2, p. 3-18 Question:

A.007

[1.0 point]

{7.0}

Which one of the following factors has the LEAST effect on Keff ?

a.

Fuel burnup.

b.

Increase in moderator temperature.

c.

Increase in fuel temperature.

d.

Xenon and samarium fission products.

Answer:

A.007 a.

Reference:

Burn, R.,

Introduction to Nuclear Reactor Operations

, © 1982, § 3.3.2, p. 3-18.

A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS Question:

A.008

[1.0 point]

{8 Which one of following is the co reactor?

a.

There are more delayed neutrons tha b.

Delayed neutrons increase the average c.

Delayed neutrons take longer to reach therm d.

Delayed neutrons born at higher energies than p effect.

Answer:

A.008 b.

Reference:

Burn, R.,

Introduction to Nuclear Reactor Operations

, © 1982, § 3.2.4, p. 3-12.

Question:

A.009

[1.0 point]

{9.0}

A 1/M curve is being generated as fuel is loaded into the core. After some fue been loaded, the count rate existing at that time is taken to be the new initial cou Additional elements are then loaded and the inverse count rate ratio continues to d result of changing the initial count rate:

a.

criticality will occur earlier (i.e., with fewer elements loaded.)

b.

criticality will occur later (i.e., with more elements loaded.)

c.

criticality will occur with the same number of elements loaded.

d.

criticality will be completely unpredictable.

Answer:

A.009 c.

Reference:

UT-TRIGA Trn Man, Vol. IV, Nuclear Physics & Rx Theory, Module 4, pg. 6.

A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS Question:

A.010

[1.0 point]

{1 Which ONE of the following de insertion as the reactor approach a.

The change in neutron population p time to reach a new equilibrium count ra b.

The change in neutron population per reac time to reach a new equilibrium count rate.

c.

The change in neutron population per reactivity in amount of time to reach a new equilibrium count rate.

d.

The change in neutron population per reactivity insertion shorter time to reach a new equilibrium count rate.

Answer:

A.010 b.

Reference:

UT-TRIGA Trn Man, Vol. IV, Nuclear Physics & Rx Theory, M Question:

A.011

[1.0 point]

{11.0}

Two critical reactors are identical except that Reactor 1 has a beta fraction of 0.0072 a 2 has a beta fraction of 0.0060. An equal amount of positive reactivity is inserted into bo reactors. Which ONE of the following will be the response of Reactor 2 compared to React a.

The resulting power level will be lower.

b.

The resulting power level will be higher.

c.

The resulting period will be longer.

d.

The resulting period will be shorter.

Answer:

A.011 d.

Reference:

UT-TRIGA Trn Man, Vol. IV, Nuclear Physics & Rx Theory, Module 4, pg. 11.

A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS Question:

A.012

[1.0 point]

{1 Which ONE of the following is t U235 atom?

a.

Kinetic energy of the fission neutron b.

Prompt gamma rays.

c.

Fission product decay.

d.

Kinetic energy of the fission fragments.

Answer:

A.012 d.

Reference:

UT-TRIGA Trn Man, Vol. IV, Nuclear Physics & R Question:

A.013

[1.0 point]

{13.0}

A reactor is subcritical with a Keff of 0.955. A positive reactivity of 3.5% d the core. At this point, the reactor is:

a.

supercritical.

b.

exactly critical.

c.

prompt critical.

d.

subcritical.

Answer A.013 d.

Reference:

UT-TRIGA Training Manual, Vol. IV, Nuclear Physics and Reactor Theory, Module 3, pg. 19.

For K = 0.955, reactivity = (K-1)/K = -0.045/0.955 = -4.71%

K/K; -4.71% +

3.50% = -1.21%, i.e. subcritical.

A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS Question:

A.014

[1.0 point]

{1 Which ONE of the following is t neutrons?

a.

Prompt neutrons account for less th neutrons account for approximately nine b.

Prompt neutrons are released during fast f during thermal fissions.

c.

Prompt neutrons are released during the fission p released during the decay of fission products.

d.

Prompt neutrons are the dominating factor in determinin neutrons have little effect on the reactor period.

Answer A.014 c.

Reference:

UT-TRIGA Training Manual, Vol. IV, Nuclear Physics and Re Module 2, pg. 29.

Question:

A.015

[1.0 point]

{15.0}

Which ONE of the reactions below is an example of a photoneutron source?

a.

1H2 +

-> 1H1 + n b.

92U238 -> 35Br87 + 57La148 + 3n +

c.

51Sb123 + n -> 51Sb124 +

d.

4Be9 +

-> 6C12 + n Answer:

A.015 a.

Reference:

UT-TRIGA Training Manual, Vol. IV, Nuclear Physics and Reactor Theory, Module 2, pg. 2.

A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS Question:

A.016

[1.0 point]

{1 The effective neutron multiplica a.

production/(absorption + leakage b.

(production + leakage)/absorption c.

(absorption + leakage)/production d.

absorption/(production + leakage)

Answer:

A.016 a.

Reference:

UT-TRIGA Training Manual, Vol. IV, Nuclear P Module 3, pg. 8.

Question:

A.017

[1.0 point]

{17.0}

Which ONE of the following conditions would INCREASE the shutdown m a.

An experiment which adds positive reactivity.

b.

Depletion of burnable poison added to the uranium fuel.

c.

Depletion of uranium fuel.

d.

Decreasing fuel temperature.

Answer:

A.017 c.

Reference:

UT-TRIGA Technical Specifications, 1.26. Any process which adds negative reactivity increases the shutdown margin.

Question:

A.018

[1.0 point]

{18.0}

The reactor is to be pulsed. The projected pulse will add TWICE as much reactivity as the last pulse performed. In relation to the last pulse, for the projected pulse:

a.

peak power will be four times larger and the energy released will be four times larger.

b.

peak power will be two times larger and the energy released will be four times larger.

c.

peak power will be four times larger and the energy released will be two times larger.

d.

peak power will be two times larger and the energy released will be two times larger.

Answer:

A.018 c.

Reference:

UT-TRIGA Training Manual, Vol. IV, Pulsed Reactors.

Question:

A.019

[1.0 point]

{19.0}

A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS The major contributor to a.

directly from the fission of b.

directly from the fission of Ura c.

from the radioactive decay of Prom d.

from the radioactive decay of Iodine.

Answer:

A.019 d.

Reference:

UT-TRIGA Training Manual, Vol. IV, Nu Module 3, pg. 35.

A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS Question:

A.020

[1.0 point]

{2 Shown below is a trace of reac power is:

a.

continually increasing.

b.

increasing, then decreasing.

c.

continually decreasing.

d.

constant.

Answer:

A.020 a.

Reference:

UT-TRIGA Training Manual, Vol. IV, Nuclear Phy Module 4, pg. 11.

Since the period is always positive, power m increasing.

• • • • • END OF SECTION A*****

• • • • • END OF SECTION A*****

B. NORMAL/EME Question:

B.001

[1.0 point]

{1.

Which ONE of the listed radioiso a.

H 3 b.

N 16 c.

Ar 41 d.

U 235 Answer:

B.001 b.

Reference:

Chart of the Nuclides Question:

B.002

[1.0 point]

{2.0}

Which ONE of the following persons is allowed to operate the facility und licensed Reactor Operator (RO)?

a.

School newspaper reporter, writing a story on the NETL nuclear reactor.

b.

A student, as part of a curriculum for a Nuclear Physics class.

c.

A student, in training to certify as a health physicist.

d.

An NRC inspector, as part of his checking that Technical Specifications setpoints are bein maintained.

Answer:

B.002 b.

Reference:

B. NORMAL/EME Question:

B.003

[1.0 points, 1/4 Common radioisotopes associat life for each is seconds (sec), minu a.

N 16 is 7 _____.

b.

Ar 41 is 1.9 _____.

c.

H 3 is 12 _____.

d.

Na 24 is 15 _____.

Answer:

B.0003

a. = sec;

b. = hr;

c. = yr;

d. = hr;

Reference:

Standard NRC Question Question:

B.004

[1.0 point]

{4.0}

In accordance with 10 CFR 20, the "Annual Limit on Intake (ALI)" refers to:

a.

the amount of radioactive material taken into the body by inhalation or ingesti year which would result in a committed effective dose equivalent of five (5) rems.

b.

the concentration of a given radionuclide in air which, if breathed for a working year hours, would result in a committed effective dose equivalent of five (5) rems.

c.

the dose equivalent to organs that will be received from an intake of radioactive material by an individual during the 50-year period following the intake.

d.

limits on the release of effluents to an unrestricted environment.

Answer:

B.004 a.

Reference:

Vol. II, Radiological Safety

B. NORMAL/EME Question:

B.005

[1.0 point]

{5.

A survey instrument with a windo irradiated experiment. The dose ra with the window closed. The gamma a.

100 mrem/hour.

b.

60 mrem/hour.

c.

40 mrem/hour.

d.

160 mrem/hour.

Answer:

B.005 b.

Reference:

Vol. IV, Radiation Detection the window stops the be dose rate is 60 mrem/hour.

Question:

B.006

[1.0 point]

{6.0}

Which ONE statement below describes the basis for the Safety Limit applicable t temperature?

a.

Excessive gas pressure between the fuel-moderator and cladding may result in loss o element cladding integrity.

b.

High fuel temperature combined with lack of adequate cooling could result in fuel melt.

c.

Excessive hydrogen produced as a result of the zirconium-water reaction is potentially explosive.

d.

Pulsing the reactor at high fuel temperatures could result in loss of fuel element cladding integrity.

Answer:

B.006 a.

Reference:

SAR, Section 4-1.

B. NORMAL/EME Question:

B.007

[1.0 point]

{7.

With regard to visitors, which ON a.

Any licensed operator or senior op b.

Each member of a tour group must ha c.

Authorization for visitor access to the reac Physicist.

d.

Each visitor is responsible for adherence to radio emergency signals.

Answer:

B.007 c.

Reference:

HP-1, Radiation Monitoring - Personnel Question:

B.008

[1.0 point]

{8.0}

Prior to the movement of fuel out of the reactor, movement of any control rod d by:

a.

mechanically blocking the rod from moving.

b.

removing power from the drive motor.

c.

removing the neutron source.

d.

de-energizing the magnets.

Answer:

B.008 c.

Reference:

FUEL-1, Movement of Fuel.

B. NORMAL/EME DR 1

X22 ' DR 2

X21X22 ' DR 1

DR 2X X22'2000 5 x12 '400 ft2X2 '20f Question:

B.009

[1.0 point]

{9.

A small radioactive source is to b R/hr at 1 foot. A Radiation Area b source.

a.

400 feet b.

40 feet c.

20 feet d.

10 feet Answer:

B.009 c.

Reference:

Question:

B.010

[1.0 point]

{10.0}

Your Reactor Operator license expires after _____ years.

a.

2 b.

4 c.

6 d.

8 Answer B.010 c.

Reference:

10CFR55.55(a)

B. NORMAL/EME Question:

B.011

[1.0 point]

{11 In order to comply with Tech. Sp one of the below statements is corr a.

The coolant pumps shall be on during proper mixing of pool water.

b.

The pool constant is a function of the pool v volume is acceptable but requires the approval o c.

Adjustments to the power instrumentation cannot b the difference is greater than 5%.

d.

Differences between indicated and measured power great be verified by a follow-up calorimetric.

Answer:

B.011 d.

Reference:

SURV-2 Reactor Pool Calibration Question:

B.012

[1.0 point]

{12.0}

While the reactor is operating and with experiments in Beam Port 3, which one of the fo violation of Tech. Specs?

a.

The Ar-41 continuous air monitor has been out of service for the past seven (7) days for maintenance. The auxiliary air purge system is operating.

b.

The HEPA filter of the auxiliary air purge system is out of service and a replacement cannot be found. The continuous air monitor (particulate) is operating.

c.

The particulate air monitor has been out of service for the past five (5) days for maintenance. The continuous air monitor (Ar-41) is in service.

d.

The air confinement system exhaust fan is out of service. Exhaust of pool areas is via the auxiliary air purge system.

Answer:

B.012 b.

Reference:

Technical Specifications 3.3.2 & 3.3.3

B. NORMAL/EME Question:

B.013

[1.0 point]

{13 Which one of the following does a.

Facility License b.

Requalification plan c.

Emergency Implementation Procedures d.

Emergency Plan Answer:

B.013 c.

Reference:

10 CFR 50.54 (q); 10 CFR 50.59; 10 CFR 55.5 Question:

B.014

[1.0 point]

{14.0}

Which ONE of the following is the Emergency Plan definition of Action Le a.

conditions that call for immediate action, beyond the scope of normal opera procedures, to avoid an accident or to mitigate the consequences of one.

b.

specific readings, or observations; radiological dose or dose rates; or specific contamination levels of airborne, waterborne, or surface-deposited radioactive materia used as thresholds for establishing emergency classes and initiating appropriate emergency methods.

c.

classes of accidents grouped by severity level for which predetermined emergency measures should be taken or considered.

d.

allowable concentrations of radioactive effluents that may be released to the environment as specified by applicable regulations.

Answer:

B.014 b.

Reference:

Emergency Plan, § 1.1 Definitions

B. NORMAL/EME Question:

B.015

[2.0 points, 0.5 Identify each of the following action CALIBRATION.

a.

Prior to startup you place a known radio meter movement and alarm function operatio b.

During startup you compare all of your nuclear track together.

c.

At power, you perform a heat balance (calorimetric) a Instrumentation readings.

d.

During a reactor shutdown you note a -80 second period on Answer:

B.015

a. = Test; b. = Check; c. = Cal; d. = Check

Reference:

Technical Specification 1.2.1-3 Question:

B.016

[2.0 points, 0.5 each]

{18.0}

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

a.

The maximum transient reactivity insertion for the pulse operation of the reactor shall be 2.2%

k/k in the pulse mode.

b.

Maximum excess reactivity shall be 4.9%

k/k.

c.

The temperature of a fuel element shall not exceed 1150 E

C for fuel element temperatures less than 500 E

C d.

During steady-state operation a minimum of three Reactor Power Level Channels shall be operable.

Answer:

B.016

a. = LSSS;

b. = LCO;

c. = SL;

d. = LCO

Reference:

Tech Spec §§ 2.1, 2.2.3, 3.1.1 and 3.2.4 (table).

B. NORMAL/EME Question:

B.017

[1.0 point]

{19 The CURIE content of a radioac a.

the number of radioactive atoms in b.

the amount of energy emitted per unit c.

the amount of damage to soft body tissue d.

the number of nuclear disintegrations per unit Answer:

B.017 d.

Reference:

Standard Health Physics Definition.

Question:

B.018

[1.0 point]

{20.0}

Following an evacuation due to a radiological emergency, who by proced re-entry?

a.

Emergency Director with concurrence of the Health Physicist b.

Senior Reactor Operator on Duty with concurrence of the Health Physicist c.

University Police with the concurrence of the Health Physicist d.

Emergency Director Answer:

B.018 d.

Reference:

Emergency Plan, § 2.1.1, 4th ¶.

• • • • • END OF SECTION B*****

SECTION C FAC Question C.001

[1.0 point]

{1 The purpose of the differential a.

maintain secondary coolant (chill prevent primary coolant leaking into th b.

maintain secondary coolant (chill water) prevent chill water leaking into the primary.

c.

maintain secondary coolant (chill water) tempe water system.

d.

maintain primary temperature less than 120 E

F, to prote Answer:

C.001 a.

Reference:

SAR § 5.2.1, 3rd ¶.

Question:

C.002

[2.0 points, 0.4 each]

{3.0}

Classify the five beam ports. Each Beam Port has only one answer.

a.

Beam Port 1 Tangential b.

Beam Port 2 Thru c.

Beam Port 3 Radial d.

Beam Port 4 e.

Beam Port 5 Answer:

C.002

a. = Thru;

b. = Tangential;

c. = Radial; d, = Radial;

e. = Thru

Reference:

Operation Support Systems §§ 3.4.1 - 3.4.3.

SECTION C FAC Question:

C.003

[1.0 point]

{4 WHICH ONE of the following d environment?

a.

NONE, N16 has too short a half-life b.

Stack Particulate Monitor c.

Bridge Area Monitor d.

Stack Gas Monitor Answer:

C.003 a.

Reference:

Standard NRC Question Question:

C.004

[1.0 point]

{5.0}

According to Technical Specification 3.3.3, the Air Particulate Detector (AP the automatic signal to isolate the ventilation system. If the APD is not availa the a.

Pool Level Area Radiation Monitor will provide an automatic signal to isolate the v system.

b.

Pool Level Area Radiation Monitor will be used to manually isolate the ventilation system c.

Ar41 monitor will provide an automatic signal to isolate the ventilation system.

d.

Ar41 monitor will be used to manually isolate the ventilation system.

Answer:

C.004 d.

Reference:

Technical Specification 3.3.3.

SECTION C FAC Question:

C.005

[1.0 point]

{6 Which ONE of the following me out...

a.

a lead screw moves into a coil, the c determine rod position.

b.

a magnet on the rod assembly closes limit movement producing a signal of rod position.

c.

a potentiometer mechanically coupled to the rod d proportional to rod position.

d.

a motor electrically coupled to a set of contacts in the rod proportional to rod position.

Answer:

C.005 c.

Reference:

L Description, § 3.7.1, p. 20.

Question:

C.006

[1.0 point]

{7.0}

Which ONE of the following design features prevents water from being siphoned out o pool and uncovering the core in the event of a primary coolant pipe rupture?

a.

The capacity of the primary water makeup system.

b.

All primary coolant pipes and components are located above core height.

c.

The suction and discharge lines penetrate the reactor tank approximately 8 feet below pool surface.

d.

The small holes that are drilled in the suction and return lines approximately 1/2 meter below pool surface.

Answer:

C.006 d.

Reference:

SAR 5.2.1

SECTION C FAC Question:

C.007

[1.0 point]

{8 The reactor is in the AUTOMAT which the control system receives result:

a.

the control system inserts the regulatin the failed detector.

b.

the control system withdraws the regulating ro c.

the control system drops out of the AUTOMATIC d.

the reactor scrams.

Answer:

C.007 b.

Reference:

UT-TRIGA Training Manual, Vol. II, Control Console O 3.

Question:

C.008

[1.0 point]

{9.0}

Which ONE of the following is a control rod interlock?

a.

Control rods cannot be withdrawn unless the count rate is greater than 1.2 CPS in th SQUARE WAVE mode.

b.

Above reactor power of 1 kW, the transient rod cannot be operated in the PULSE mode.

c.

Two control rods cannot be withdrawn at the same time above 1 kW in the MANUAL mode.

d.

Only one standard rod at a time can be withdrawn in the PULSE mode.

Answer:

C.008 b.

Reference:

UT-TRIGA Training Manual, Vol. V, ICS System Surveillance Interlock and SCRAM Features.

Question:

C.009

[1.0 point]

{10.0}

Which one of the following devices is tested during the ICS System PRESTART checks?

a.

Low water level b.

Source level trip c.

Magnet power key switch d.

Pool area radiation monitor Answer:

C.009 b.

SECTION C FAC

Reference:

OPER-1 Start Manual pg. 2-5

SECTION C FAC Question:

C.010

[1.0 point]

{1 Pool water conductivity is meas a.

outlet of the coolant system heat b.

outlet of the purification system filter.

c.

discharge of the purification system pump d.

discharge of the coolant system pump.

Answer:

C.010 b.

Reference:

SAR page 5-8.

Question:

C.011

[1.00]

{12.0}

When the reactor is in the AUTOMATIC mode, the controlling signal is:

a.

reactor power as measured by the ion chamber in the NPP-1000 system.

b.

reactor period as measured by the ion chamber in the NM-1000 system.

c.

reactor power as measured by the fission chamber in the NM-1000 system.

d.

reactor power as measured by the fission chamber in the NP-1000 system.

Answer:

C.011 c.

Reference:

UT-TRIGA Training Manual, Vol. II, Rx Inst & Control Systems, page 34.

Question:

C.012

[1.00]

{13.0}

Which ONE of the following types of detector is used in the Area Radiation Monitor system?

a.

Proportional Counter.

b.

Scintillation Detector.

c.

Ionization Chamber.

d.

Geiger-Mueller Tube.

Answer:

C.012 d.

Reference:

UT-TRIGA Training Manual, Vol. II, Rx Instrumentation & Control Systems, page 36.

SECTION C FAC Question:

C.013

[1.00]

{14.0}

Which ONE of the following sta a.

Reactor power can be increased b.

The shim rods, regulating rod, and tra c.

Reactor power must be steady (i.e. infinit mode.

d.

If the demand power is not reached within 10 se State (Manual) mode.

Answer:

C.013 d.

Reference:

UT-TRIGA Training Manual, Vol. II, Control Console 5-3, 5-4.

Question:

C.014

[1.00]

{15.0}

Which of the rings include the chromel-alumel thermocouples?

a.

A and B b.

A and C c.

B and C d.

B and D Answer:

C.014 c.

Reference:

SURV-1 Question:

C.015

[1.00]

{16.0}

Complete the following statement. Fuel in the UT TRIGA is a homogeneous mixture of uranium-

___________ hydride alloy containing _______% by weight of uranium enriched to <________%.

a.

graphite, 20, 8.5

b.

zirconium, 20, 8.5

c.

graphite, 8.5, 20

d.

zirconium, 8.5, 20 Answer:

C.015 d.

Reference:

SAR Section 4.4.5.2

SECTION C FAC

SECTION C FAC Question:

C.016

[1.00]

{17.0}

Which one of the following phy majority of the negative temperatu a.

Doppler broadening b.

Thermal Expansion of the moderator c.

Uranium-Zirconium Hydride disadvantage fa d.

Geometric Buckling Answer:

C.016 c.

Reference:

SAR 4.1.2 Question:

C.017

[1.00]

{18.0}

For a standard control rod, the rod color is MAGENTA and the magnet box indicates that:

a.

the drive is completely UP, and the rod is DOWN.

b.

the drive is completely UP, and the rod is UP.

c.

the drive is between limits, and the rod is DOWN.

d.

both the rod and the drive are between limits.

Answer:

C.017 a.

Reference:

Vol. II, Rx Instrumentation & Control Systems, page 26.

Question:

C.018

[1.00]

{19.0}

The neutron source used in the UT-TRIGA reactor consists of:

a.

americium and beryllium.

b.

antimony and beryllium.

c.

plutonium and beryllium.

d.

californium and beryllium.

Answer:

C.018 a.

Reference Vol. II, Description of TRIGA Mark II Reactor, page 16.

SECTION C FAC Question:

C.019

[1.00]

{20.0}

Which ONE of the following tem fuel element?

a.

Surface of the fuel element cladding.

b.

Outer surface of the fuel.

c.

Interior of the fuel.

d.

Center of the zirconium rod.

Answer:

C.019 c.

Reference Vol. II, Description of TRIGA Mark II Reactor, page 16.

• • • • • END OF SECTION C*****

• • • • • END OF EXAMINATION*****