ML050450465

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

ML050450465
Person / Time
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
Shared Package
ML043200631	List: ML043210156 ML050450465 ML050450489
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50-602/05-01
Download: ML050450465 (36)

Text

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

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.

ENCLOSURE 1

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

Reference:

Answer: Question:

Which factor of

Reference:

theAnswer You Six Factor formula is and mostnoQuestion:

enter easily are the in rods variedcontrol motion.

by theroomWhic an reactor

d. c. b. a. d. c. b. a.

FastFast Fission Non-Leakage Factor Reproduction ThermalFactor Utilization Factor neutron

() (Lf )( Factor (f)TheThe The reactor The reactor source is reactor supercritical.

is has subcritical.

isbeen critical.

removed from th

)

A.002 A.002 A.001 A.001 3-18. Burn, R.,

a. [1.0 point]

Standard

c. NRC QUESTION [1.0 point]

{2.0} {

Introduction to Nuclear Reactor Operations,

© 1982, § 3.2, pp. 3-13 A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS

Reference:

Answer: Which Question:

collision? following one of the

Reference:

Answeratoms will cause a neutron to firstanswer lose startup.

difference conditions, You the most the Question:

phone.

perform between (coreenergy For two burnup, the the initial two an ela second instartup pool startup an st

d. c. b. a. d. c. b. a.

Hydrogen 2 12 1 Uranium Hydrogen Carbon 238 Rod Height A.004 A.004 A.003 Same Same Higher Lower A.003 Burn, R.,

d. 5-38. [1.0 point]

Burn, R.,

d. [1.0 point]

Count Rate

{4.0} Higher Lower Same Same {

Introduction to Nuclear Reactor Operations,

© 1982, § 5.7, pp. 5-28 Introduction to Nuclear Reactor Operations,

© 1988, § 2.5.3 p. 2-45.

A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS

Reference:

Answer: Question:

Which one of the

Reference:

following Answer:d. factors

c. b. has

a. the Question:

AsLEAST primaryeffect coolant temperature

Reference:

onAnswer:

Keff ? increases, Forrod worth:

Question:

most materials the neutro

d. c. b. a. remains increases decreases theincreases same due to due due the due to toincrease constant higher to higher neutron inpoison reflector thermal cross-section

d. absorption

c. diffusion efficiency. the of moderator.

b. a. inlength. the control rods.

Xenon Increase and Increase samarium Fuel in fuel burnup.

in moderator temperature.

fission products.

temperature. decreases increases decreases as increases as target target asnucleus neutron asnucleus neutron mass energy mass energy increase increa inc A.007 A.007 A.006 A.006 A.005 A.005 Burn, R.,

a. [1.0 point]

Burn, R.,

c. [1.0 point]

Burn, R.,

b. [1.0 point]

{7.0} {6.0} {

Introduction to Nuclear Reactor Operations, Introduction to Nuclear Reactor Operations, Introduction to Nuclear Reactor Operations,

© 1982, § 3.3.2, p. 3-18. © 1982, § 3.3.2, p. 3-18 © 1982, § 2.5.1 p. 2-36.

A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS

Reference:

Answer: result Additional been Question:

1/M curve ofAchanging loaded, elements theis

Reference:

the being initial count generated areAnswer:

then count rateloaded existing rate: and asatfuel the loaded thatisinverse time into reactor?

isWhich count taken the core.

Question:

one rate to beof ratio the After following some continues new initial is the to co fuc

d. c. b. a. d. c. b. a.

criticality criticality criticality willcriticality be willcompletely occur will occur willwith occur later the unpredictable.

earlier same (i.e., with number (i.e.,more fewer elements elements elements loaded.)

Delayed withofeffect. loaded.

Delayed There loaded.)

Delayed neutrons are neutrons neutrons bornmore take delayed at higher increase longer neutrons energies tothe reach average than therth A.009 A.009 A.008 A.008 UT-TRIGA

c. Trn Man, Vol. IV, Nuclear Physics Rx Theory, Burn,

[1.0&point] R.,

b. Module 4, pg. 6. [1.0 point]

{9.0} {

Introduction to Nuclear Reactor Operations,

© 1982, § 3.2.4, p. 3-12.

A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS

Reference:

Answer: reactors.

2 has Which TwoaQuestion:

critical

Reference:

beta fraction ONE ofAnswer:

ofthe reactors 0.0060.

arefollowing An will identical equal be amount except the of positive thatresponseinsertion Reactor of Reactor 1Which hasreactivity Question:

ONE a as the beta2 compared ofis reactor the inserted fraction following tointo Reac ofapproach 0.0072 db

d. c. b. a. d. c. b. a.

TheThe resulting The resulting The resulting period resulting period will power will be power shorter.

be level longer.

level will be willhigher.

lower.

be shorter Theamount time change The totime of reach change in time The toneutron time reach ato change new inThe reach change toneutron apopulation reach equilibrium new in a neutron new in neutron equilibrium apopulation new equilibrium per count population equilibrium population reactivity count per rate.count reactivity rate.

insertio count perrate.

rea ri A.011 A.011 A.010 A.010 UT-TRIGA

d. Trn Man, Vol. IV, Nuclear Physics & Rx Theory, UT-TRIGA

[1.0 point] b. TrnModule 4, pg.

Man, Vol. IV,11.

Nuclear Physics & Rx Theory,

[1.0 point]

{11.0} {

A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS

Reference:

Answer Question:

theAcore.

reactor At isthis

Reference:

Answer:

subcritical point, thewith reactor a Keff U235 is:of 0.955. Which atom?

Question:

A positive of the following ONEreactivity of 3.5%isd

d. c. b. a. d. c. b. a.

subcritical.

promptexactly critical.

supercritical.

critical. Kinetic Fission Kinetic energy Prompt product of energy gamma thedecay.

fission rays. the fission neutro offragments.

A.013 A.013 A.012 A.012 ForModule 3.50% 0.955, 3, pg.

K= =-1.21%, reactivity UT-TRIGA 19.

i.e. d. = (K-1)/K Training subcritical. = -0.045/0.955 Manual, Vol. IV,

= -4.71%

Nuclear Physics UT-TRIGA

[1.0 point] d. and Trn Reactor Theory, Man, Vol. IV, Nuclear Physics &

[1.0 point]

K/K; -4.71% +

{13.0} {

A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS

Reference:

Answer: Which Question:

Reference:

ONE of the reactions Answer below is an example of a photoneutron neutrons?

Which Question:

ONEsource?

of the following is

d. c. b. a. d. c. b. a.

4Be9 51Sb123 1H2

+ 92U238 51Sb124

+ n+->-> 35Br87 +

+ 57La148

+ neutrons 3n +Prompt released have Prompt neutrons duringPrompt little during Prompt neutrons neutrons effect neutrons thermal are thethe on decay are neutrons fissions.

the dominating account released reactor of are account released fission for period.

factor during during approximately products.

inthe less fast determinin forfission nint

-> 6C12 + ->n 1H1 + n A.015 A.015 A.014 A.014 Module 2, pg.UT-TRIGA

2. Module

a. Training Manual, Vol. [1.0 IV, 2,point]

pg.UT-TRIGA Nuclear29.

Physics Training

c. and Manual, Reactor Vol. IV, Nuclear Physics Theory, [1.0 and R point]

{15.0} {

A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS

Question:

Reference:

Answer: pulse Theperformed.

Question:

reactor is toIn

Reference:

be relation pulsed.

Answer:

to The the last projected pulse thewill pulse,Which projected add for Question:

ONE

Reference:

of TWICE thepulse:

Answer:

as much following reactivity conditions would the last INCREASE asThe Question:

effective the shutdown neutron multiplic

d. c. b. a. d. c. b. a. d. c. b. a.

peak peak power peak power peak will power will be power two be willfour times be willtwo times belarger four times larger times and larger and the larger and energy the and the energy released energy the Decreasing released energy Depletion released Depletion An fuelwill released be will two ofexperimentwill temperature.

uranium of burnable two times be befuel.willfour which times be larger.

four poisontimes addslarger.

times larger.

added larger.

positive absorption/(production to (absorption the reactivity.

(production uranium production/(absorption

+fuel.

leakage)/production

+ leakage)/absorption

+ leakage) + leakag A.019 A.018 A.018 A.017 A.017 A.016 A.016

[1.0UT-TRIGA IV, Pulsed point]c. Training Manual, Vol.reactivity Reactors.

[1.0 increases point]

UT-TRIGA the

c. shutdown Technicalmargin.

Specifications, Module 1.26.

[1.0 Any 3,point] a. Training pg.UT-TRIGA

8. process which adds Manual, negative Vol. IV, Nuclear

[1.0 point]

{19.0} {18.0} {17.0} {

A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS

Reference:

Answer: The major contributor to

d. c. b. a.

fromfrom thedirectly radioactive thedirectly fromfrom radioactive the decay fission decay of ofPro theoffissionUra of Iodine.

A.019 Module 3, pg.UT-TRIGA

35. d. Training Manual, Vol. IV, N A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS

Reference:

Answer: power Shown Question:

is: below is a trace of rea

d. c. b. a.

constant.

continually increasing, continually decreasing.

thenincreasing.

decreasing.

A.020 A.020 increasing.

Module 4, pg.UT-TRIGA

11. a. Training Manual, Vol. IV, Nuclear Ph

[1.0 point]

{

• • • • • END OF*****END SECTIONOF A*****

SECTION A*****

Since the period is always positive, power m A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS

B. NORMAL/EM

Reference:

Answer: licensed WhichQuestion:

Reactor Operator ONE of

Reference:

theAnswer:(RO)?

following persons is allowed WhichQuestion:

ONE to operate of the the listed facility radiois un

d. c. b. a. d. c. b. a.

An NRC A student, maintained. Ainspector, student, School in training as newspaper aspart part toof of certify ahis curriculum reporter, checking as a health writing for that physicist.

Nuclear Technical a story U a235 Ar Physics 41N 16on H Specifications 3the NETL class.

nuclear setpoints reactor.

are bei B.002 B.002 B.001 B.001

b. [1.0 point]

Chart ofb.the Nuclides [1.0 point]

{2.0} {1

B. NORMAL/EM

Reference:

Answer: Question:

Reference:

In accordance withAnswer:

10 CFR 20, the "Annual Limit lifeCommon on Intake for Question:

each radioisotopes is seconds refers (ALI)"(sec), to:

associa min

d. c. b. a. d. c. b. a.

limits hours, dose an individual on thethe the year equivalent would concentration release duringthe which of result theamount to would inorgans effluents aofof 50-year committed toresult radioactive given that aperiod an will radionuclide a effective committed be unrestricted infollowingNa 24 material received dose3 in taken environment.

the H isintake.

isAr 41 effective air from equivalent which, N into is an dose 16isthe intake if breathed body of equivalent five of by radioactive (5)inhalation for rems.

ofa five working material (5) or ingest rems.

year b

B.004 B.004 B.0003 B.003 Vol. II, a.

Radiological Safety [1.0 point]

Standard 15 a.12 NRC

=_____.

sec; Question 1.97_____.

_____. [1.0 points,

{4.0} b. = hr;

c. = yr;

d. = hr;

B. NORMAL/EM

Reference:

Answer: Which Question:

ONE temperature?

Reference:

statementAnswer:

below describes the basis with for the irradiated the Safety window Question:

A surveyexperiment.

closed. applicable LimitThe instrument The with gamma dose a windr

d. c. b. a. d. c. b. a.

integrity.

Pulsing explosive.

Excessive theHigh reactorExcessive element fuel hydrogen claddinggas attemperature high fuel pressure produced integrity.

temperatures combined as a between result with could 160 lackthe of the fuel-moderator resultmrem/hour.

40 60 100 mrem/hour.

ofzirconium-water adequate mrem/hour.

in mrem/hour.

loss and ofcooling fuel cladding element reaction could resultmay cladding result is potentially in fuel in loss melt.

B.006 B.006 B.005 B.005 SAR, Section

a. 4-1. dose [1.0 Vol.

rate point]

is 60 mrem/hour.

IV,b.Radiation Detection the window [1.0 stops the b point]

{6.0} {5

B. NORMAL/EM

Reference:

Answer: by: Question:

Prior to the

Reference:

Answer:

movement of fuel out of the reactor, movement WithQuestion: of any control regard to visitors, whichrodO

d. c. b. a. d. c. b. a.

de-energizing removing removing mechanically the theneutron power magnets.

from blocking source.

the drive the rod motor. moving.

emergency fromEach Authorization Physicist. Each visitor signals. Any member licensed for visitor is responsible aoperator offor tour access group or adherencetosenior the must rea ho to radi B.008 B.008 B.007 B.007 FUEL-1,c. Movement of Fuel. [1.0 point]

HP-1, Radiation

c. Monitoring - Personnel [1.0 point]

{8.0} {7

B. NORMAL/EM

Reference:

Answer YourQuestion:

Reference:

Reactor Operator Answer:

license expires after _____ years.

source.

R/hr atQuestion:

1 foot.

A small A Radiation radioactive sourceArea is to

d. c. b. a. d. c. b. a.

8 6 4 2 10 feet 20 feet 40 feet 400 feet B.010 B.010 B.009 B.009 10CFR55.55(a)

c. DR [1.0 point] c. [1.0 point]

1 ' DR2X2 ' DR 1X 2

{10.0} {9 2 2 X2 X1 DR 2

2 X22 '2000 f ft2X2 ' 20 5 x1 ' 400

B. NORMAL/EM

Reference:

Answer: While Question:

the

Reference:

reactor violation of Tech. Specs? Answer:

is operating and with experiments in oneBeam Inof orderPort Question:

the below 3, which to comply statements with oneTech. the of is cor Sf

d. c. b. a. d. c. b. a.

auxiliary The maintenance.

airThe purge confinement beparticulate found.

The system.

maintenance.

The HEPA The The system continuous aircontinuous filter Ar-41 monitor exhaust of The continuous the air has auxiliary monitor air auxiliary fan been monitor is air out out air (Ar-41) air monitor purge of of (particulate) purge service.

service issystem be in has system service.

for verifiedbeen Exhaust isthe isoperating.

isoperating.

out past of of of Adjustments Differences the difference by volume aout five pool service service follow-up between The (5) proper is areas to ispool days The for the greaterand acceptableis the for a

viareplacement coolant power calorimetric.

indicated constant mixing than past ofthe but and 5%.

ispoolseven arequires(7) measured function water. cannot instrumentation pumps shall thedays be of on powerfor cannot durin approval the pool greav B.012 B.012 B.011 B.011 Technical

b. Specifications 3.3.2 & 3.3.3 [1.0 point]

SURV-2 d. Reactor Pool Calibration [1.0 point]

{12.0} {1

B. NORMAL/EM

Reference:

Answer: Question:

Which ONE of

Reference:

theAnswer:

following is the Emergency Which Plan Question: definition of Action one of the following doesL

d. c. b. a. d. c. b. a.

as specified allowable measures classes by emergency concentrations applicable used should contamination of as accidents specific be conditions thresholds methods.

procedures, regulations.

taken ofreadings, grouped radioactive levels orfor that considered. call toestablishing ofavoid by orairborne, effluents observations; severity an for accident emergency Emergency immediate waterborne, level that may for Emergency Requalification action, radiological orwhich to be classes mitigateFacility Plan orreleased Implementation beyond License surface-deposited predetermined dose and theto or plan scope initiating consequences the dose theenvironment emergency rates; Procedures of normal appropriate radioactive orof oper specific one.

materi B.014 B.014 B.013 B.013 Emergency

b. Plan, § 1.1 Definitions [1.0 point]

10 CFRc.50.54 (q); 10 CFR 50.59; 10 [1.0CFR 55.

point]

{14.0} {1

B. NORMAL/EM

Reference:

Answer: Identify each Question: of the following

Reference:

Answer: as either or a Limiting Condition for Operation (LCO).a Safety Limit (SL) a Limiting CALIBRATION.

Identify Question: Safety System each of the following Se actio

d. c. b. a. d. c. b. a.

operable.

During than less The 2.2%The steady-state 500E Maximum temperature maximum operation excess transient a minimum of a reactivity fuel element reactivity of shall three shall be 4.9% insertion During not Instrumentation At Reactor exceed a reactor track power, Power 1150Ethe forDuringpulse Prior together.

shutdown you operation readings.

Levelstartup perform startup toyou you movement Channelsa heat noteofyou compare and balance athe reactor all second alarm beplace

-80 of known shall function be radi (calorimetric) ayourperiod nuclear ona operati C

k/k in the pulse mode. k

/k. Cmeter for fuel elementshall temperatures B.016 B.016 B.015 B.015 Tech Spec

a. = LSSS; [2.0 points,

§§ 2.1, 2.2.3, 3.1.1 and 3.2.4 (table). Technical 0.5

a. =each]

Specification Test; b. = Check; 1.2.1-3c. = Cal; d. = Check

[2.0 points, 0.5

b. = LCO;

c. = SL; {18.0}

d. = LCO

B. NORMAL/EM

Reference:

Answer: Following Question:

re-entry? an evacuation

Reference:

Answer:due to a radiological emergency, TheQuestion:

CURIE content who proce of abyradioac

d. c. b. a. d. c. b. a.

Emergency University Senior Emergency Director Police Reactorwith Operator Director the concurrence with on Duty concurrence with of concurrence thethe Health the of number the amount the Health number theamount the nuclear of Physicist ofPhysicist Health of radioactive of damage of energy Physicist disintegrations to soft emitted bodyatoms per tissue uniti B.018 B.018 B.017 B.017 Emergency

d. Plan, § 2.1.1, 4th ¶. [1.0 point]

Standard d. Health Physics Definition.[1.0 point]

{20.0} {1

• • • • • END OF SECTION B*****

SECTION C FA

Reference:

Answer: Classify Question:

the five

Reference:

beam Answer:

ports. Each Beam Port has Theonly Question one answer.

purpose of the differential

e. d. c. b. a. d. c. b. a.

Beam Beam Port Beam Port 5Beam Port Beam 4 Port 3 Port 2 1 maintain watermaintain system.

prevent primary maintain secondary temperature preventwater secondary coolant leaking chillmaintain primarylesscoolant than (chill into 120E secondary coolant water) the(chill primary.

leaking coolant tempe water (chill F, tointo prott C.002 C.002 C.001 C.001 Operation Support Systems §§ 3.4.1 - 3.4.3.

a. = Thru; [2.0 points, 0.4 each] [1.0 point]

SAR § a.

5.2.1, 3rd ¶.

Radial ThruTangential

b. = Tangential; {

{3.0}

c. = Radial; d, = Radial;

e. = Thru

SECTION C FA

Reference:

Answer: thethe automatic Question:

According

Reference:

tosignal Answer:

to isolate Technical the ventilation Specification environment?

3.3.3,system.

WHICH ONE If the of the Question: APD Air Particulate isfollowing not avail theDetector (Ad

d. c. b. a. d. c. b. a.

Ar41Ar41 monitor monitor Pool will system.

Level Poolbe will Areaused provide Level to manually Area automatic Radiation isolate Monitor anRadiation signal willthe Monitor to ventilation beStackisolate used will Bridge the provide Gas system.

toStack ventilation manually Area Monitor NONE, an isolate Particulate automatic Monitor system.

N16 hasthe ventilation Monitor signal too short to isolate syste a half-life the C.004 C.004 C.003 C.003 Technical

d. Specification 3.3.3. [1.0 point]

Standard a. NRC Question [1.0 point]

{5.0} {

SECTION C FA

Reference:

Answer: Question:

Which ONE of the following

Reference:

Answer: design features prevents water pool and uncovering the core in the event of a primary out...

coolant Which from Question:

pipe ONE being siphoned rupture?

of the following outm

d. c. b. a. d. c. b. a.

pool The surface.

surface.

small Theholes All suction primary The that and capacity are coolant discharge drilled ofpipes the in the lines primary and suctionproportional penetrate components water motor proportional andmakeup athe return to electrically reactorpotentiometer movement arealinesrodaposition.

located system.

tankto magnet determine rod coupled producing approximately above mechanically on rod the to approximately aposition.

lead core a position.

rod screw 1/2 signal height.

meterassembly a8set of feetcoupled movescontacts below below ofinto closes to rodpoolin thethe rod limit aposition.

coil, thero C.006 C.006 C.005 C.005 L

Description, § 3.7.1, p. 20.

SAR 5.2.1

d. [1.0 point] c. [1.0 point]

{7.0} {

SECTION C FA Answer: WhichQuestion: Answer:

one of the

Reference:

following devices is tested during Which the Question:

ONEICSofSystem the

Reference:

Answer:

PRESTART following checks?

is a control rod interlock?

result:

which Thethe Question:

reactor control is in system the AUTOMA receive

d. c. b. a. d. c. b. a. d. c. b. a.

PoolMagnet areaSource radiation Low power level water key monitor trip level switch OnlyTwoone Above control standard SQUAREreactor rods rod WAVE cannot Control power at a time rods mode.

be of withdrawn cannot 1can kW, the withdrawn transient at the bebewithdrawn reactor the thesameinrod unless control the the scrams.

time cannot the PULSEsystem control the failed above be count the drops system mode.

detector.

operated 1 kW rate control out of withdraws in the in the greater issystem the MANUAL PULSE theAUTOMATI than inserts regulating 1.2 themode.

mode.

CPS in tr regulati C.009 C.009 C.008 C.008 C.007 C.007

b. SCRAM[1.0Features.

point]

UT-TRIGAb. Training Manual, Vol.3.V, ICS UT-TRIGA

[1.0System point] b. Training Surveillance Manual, Interlock andVol. II, Control[1.0 Console point]

{10.0} {9.0} {

SECTION C FA

Reference:

Manual pg. 2-5 OPER-1 Star

SECTION C FA

Reference:

Answer: Question:

Reference:

Answer:

Which ONE of the following types of detector Question:

Whenisthe used

Reference:

reactor Answer:

in theisArea in theRadiation AUTOMATIC Pool Monitor mode, Question:

water system? conductivity the controlling is mea signal is:

d. c. b. a. d. c. b. a. d. c. b. a.

Geiger-Mueller Ionization Scintillation Proportional Chamber.

Tube.Detector.

Counter. reactor reactor power reactor power as period measured as reactor measured as measured power asby the by the measured fission by fission the discharge bychamber ion discharge thechamber chamber outlet ion ofin outlet the the ofininthe chamber coolant the NP-1000 of the the NM-1000 NM-1000 coolant system system.

inpurification the system.

system system.

system pump.

NPP-1000 filter pum heat system C.012 C.012 C.011 C.011 C.010 C.010 page 36. UT-TRIGA

d. Training Manual, Vol. II,[1.00] UT-TRIGA

c. Training Rx Instrumentation Manual,

& Control Vol. II,[1.00]

Systems, Rx Inst SAR & Control page

b. 5-8. Systems, page 34. [1.0 point]

{13.0} {12.0}

{

SECTION C FA

Reference:

Answer: ___________

Complete Question:

the hydride following

Reference:

Answer:

alloy statement.

containingFuel Which in the Question:

UT ofbythe TRIGA weight

Reference:

ringsis Answer:

ofinclude auranium homogeneous theenriched chromel-alumel mixture to <________%.

ofthermocouples?

uranium-Which Question:

ONE of the following st

d. c. b. a. d. c. b. a. d. c. b. a.

zirconium, graphite, zirconium, 8.5, graphite, 8.520, 20 20,20, 8.58.5 B and B and DA and CA and C B Reactor StateIf (Manual) the mode. The demand Reactor mode.power shim rods, power power ismust becan steady notregulating reached rod, increased (i.e.and bewithin infini 10 str C.015 C.015 C.014 C.014 C.013 C.013 SAR Section

d. 4.4.5.2 SURV-1 c. 5-3, 5-4. UT-TRIGA d. Training Manual, Vol. II, Control Consol

[1.00] [1.00] [1.00]

{16.0} {15.0} {14.0

SECTION C FA SECTION C FA Reference Answer:

TheQuestion: Answer:

neutron

Reference:

source For Question:

a indicates used in the UT-TRIGA standard reactor

Reference:

control Answer:

that:consists of: rod, the rod color is MAGENTA majority Which and Question:

ofone theofnegative thethe magnet following bo temperat phy

d. c. b. a. d. c. b. a. d. c. b. a.

californium plutonium antimony and americium and beryllium.

and beryllium.

beryllium. thedrive and beryllium. boththe the roddrive the and is between drive is thecompletely is drive completely limits, are between UP, andUP, and the and rod the Geometric limits.

is rod the Uranium-Zirconium DOWN.

is Thermal rodUP. Buckling Doppler is DOWN.Expansion broadening Hydride of the disadvantage moderator f C.018 C.018 C.017 C.017 C.016 C.016

a. Vol. II, a.

Rx Instrumentation & Control Systems, 4.1.2 SARpage

c. 26.

[1.00] [1.00] [1.00]

{19.0} {18.0} {17.0 Vol. II, Description of TRIGA Mark II Reactor, page 16.

SECTION C FA Reference Answer:

fuel Which element?

Question:

ONE of the following te

d. c. b. a.

Center Interior of Outer the of Surface zirconium the surface fuel.

of of therod.

the fuel fuel.

element cladding C.019 C.019 c.

[1.00]

{20.0

• • • • • END OF EXAMINATION*****

• • • • • END OF SECTION C*****

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