ML20217D141

NRC Operator Licensing Exam Rept 50-151/OL-98-01 Conducted on 980302-03.Exam Results:Exam Was Administered to Two SRO Candidates.Both Passed Exam

ML20217D141
Person / Time
Site:	University of Illinois
Issue date:	03/24/1998
From:	Isaac P NRC (Affiliation Not Assigned)
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ML20217D115	List: ML20217D141
References
50-151-OL-98-01, 50-151-OL-98-1, NUDOCS 9803270324
Download: ML20217D141 (36)

Text

.

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-151/OL-98-01 FACILITY DOCKET NO.: 50-151 FACILITY LICENSE NO.: R-115 g FACILITY: University of Illinois EXAMINATION DATES: March 2 - 3,1998 EXAMINER: Patric Isaac ief E i r SUBMITTED BY: - & M 2 99

/

Patrick Isaac [iefpmine Dat'e

SUMMARY

During the week of March 2,1998, the NRC administered Operator Licensing Examinations to two Senior Reactor Operator Instant (SROI) candidates. Both candidates passed the examination.

REPORT DETAILS

1. Examiners: Patrick Isaac, Chief Examiner

2. Results:

RO PASS / Fall SRO PASS / Fall TOTAL PASS / Fall  !

Written N/A 2/0 2/0 l Operating Tests N/A 2/0 2/0  !

Overall N/A 2/0 2/0 l

3. Exit Meeting:

An exit meeting was conducted, on 3/3/98, between Mr. Rich Holm, University of Illinois reactor Supervisor and Mr. Patrick Isaac, Chief Examiner. Mr. Holm requested that question C.10 of the written examinatiori ba deleted from the examination due to the lack of a correct answer. He also requested that two correct answers, "a" and "c" be accepted for question B.15. The Chief Examiner agreed and the written examination has been modified accordingly.

ENCLOSURE 1 9903270324 990324 PDR ADOCK 05000151 y PDR I

a

I U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: University of Illinois REACTOR TYPE: TRIGA DATE ADMINISTERED: 03/02/98 REGION: 111 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 EL9_ A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 20.00 33.9 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS I I

i 19.00 . 32.2 C. FACILITY AND RADIATION MONITORING SYSTEMS  ;

59.00  % TOTALS FINAL GRADE 1

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

l l

Candidate's Signature j 1

ENCLOSURE 2 3

1

A. RX THEORY, THERM 0 & FAC OP CHARS ANSWER SHEET Multiple Choice (Circle or X your choice)

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

MULTIPLE CH0 ICE 001 a b c d _

002 a b c d _

003 a b c d _

004 a b c d _

005 a b c d _

006 a b c d _

007 a b c d _

008 a b c d _

009 a b c d _

010 a b c d _

011 a b c d _

012 a b c d _

013 a b c d 014 a b c d _

015 a b c d _

016 a b c d _

017 a b c d _

018 a- b- c d _

019 a_ b 'c d _

020~ a< b c d- _

(*****

END OF CATEGORY A *****)

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

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

MULTIPLE CHOICE 001 a b c d _

002 a b c d _

003 1 2 3 4 4

004 a b c d _

005 a b c d _

i 006 a b c d _

007 a b c d _

1 008 a b c d _

009 a b c d _

010 a b c d _

011 a b c d _

012 a b c d _

013 a b c d 014 a b c d _

015 a b c d _

016 a b c d _

017 a b c -d _

018 a b c d _

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

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.

001 a b c d _

002 a b c d _

003 a b c d _

004 a b c d _

005 a b c d _

006 a b c d _

007 'a b c d _

008 a b c d _

009 a b c d _

010 a b c d _

011 a b c d _

012 a b c d _

013 a b c d _

014 a b c d _

015 a b c d _

016 a b c d _

017 a b c d _

018 a b c d _

019 a b c d _

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

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

r.

EQUATION SHEET 0 - m c, AT RR - I

• N

• f 0 - m ah SCR - S/(1-Keff) 0 - UA AT CR (1-Keff)1 - CR, (1-Keff),

26.06 (N,,p) (1-Keff),

SUR - M-(D - p) (1-Keff)

SUR - 26.06/t M - 1/(1-Keff) - CR /CR, i

P - P, 10*" SDM - (1-Keff)/Keff P - Po e"'" Pwr - W, m p(1-p)

P- P, l' - 1 x 10d seconds 0-0

~

1 - (f*/p) + [(D-p)/A,,p] 1 - f*/(p IS) p - (Keff-1)/Keff p - 3/[( Ar,*t )]+1 p - AKeff/Keff 0.693 Tn-i ,

_s - 0.0073 A I DR3 D 3 2 - DR,D/ DR - DRo e "

6CiE(n)

DR - DR = , Ci = Curies. E = Mev, R = feet R2 l

1 Curie - 3.7x101' dps 1 kg - 2.21 lom 1 hp - 2.54x103 BTU /hr 1 Mw - 3.41x106 BTU /hr 1 BTU - 778 ft-lbf 'F - 9/5'C + 32 i

. 1 gal H,0 8' ibm *C - 5/9 ("F - 32) l Cp (H2O) - 0.146 Cp (D20) - 0.162 l

[ .

NRC RULES AND GUIDELINES i . FOR LICENSE EXAMINATIONS l-l

.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 not I received or 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. )

1

6. Fill in the date on the cover sheet of the examination (if necessary). ]

l

7. Print your name in the upper right hand corner of the first page of each j i

section of your answer sheets.

8. Before you turn in your examination, consecutively number each answer sheet, including any additional pages inserted when writing your answers on the examination question page..

9. The point value for each question is indicated in parentheses after the l question.

10. Partial credit will NOT be given.

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

i i

i I

Section A: R Theory. Thermo & Fac. Ooeratina Characteristics Page1 QUESTION (A.1) [1.0]

~ A mixed beta-gamma point source measures 200 mrem /hr at one foot and 0.1 mrem /hr at 20 feet. The beta emission has an energy of 1.0 MeV. What is the fraction of betas in the source?

a. 10%

b. 20 %

c. 80 %

d. 90 %

QUESTION (A.2) [1.0]

An element decays at a rate of 20% per day. Determine its half-life,

a. 3 hr.

b. 75 hr,

c. 108 hr.

d. 158 hr.

QUESTION (A.3) [1.0]

in a subcritical Rx, Keff is increased from 0.861 to 0.946. Which one of the following is the amount of reactivity that was added to the core?

a. 0.090 delta-K/K

b. 0.220 delta-K/K

c. 0.104 delta-K/K

d. 0.125 delta-K/K '

i Smetion A: R Theory. Thermo & Fac. Ooeratina Characteristics Page 2 QUESTION (A.4) [1.0]

Which one of the following is a correct statement concerning the factors affecting control rod worth? Assume constant reactor power.

a. Moderator temperature increase causes rod worth to decrease.

b. The withdrawal of an adjacent rod causes the rod worth of the stationary control rod to

- increase.

c. Samarium concentration increases over core life causes the rod worth to decrease in the periphery rods.

d. Fuel burnup causes the rod worth to increase in the center of the core.

QUESTION (A.5) [1.0]

A reactor startup is in progress by withdrawing a control rod and then waiting until count rate stabilizes. The reactor is not critical. Assume that the control rod is being withdrawn in equal amounts each time and each control rod withdrawal adds equivalent amounts of reactivity.

Compare two consecutive control rod withdrawals.

a. Time for power to stabilize will be equal for both withdrawals and the power increase will be the same for both withdrawals.

b. The power increase will be the same for both withdrawals but the time for power to stabilize will be less for the second withdrawal.

c. The power increase will be the same for both withdrawals but time for power to stabilize will be longer for the second withdrawal.

d. The power increase will be larger for the second withdrawal and the time for power to stabilize will be longer for the second withdrawal.

Section A: R Theory. Thermo & Fac. Ooeratina Characteristics Page 3 QUESTION (A.6) [1.0]

Which one of the following statements describes the effect of an increase in fuel temperature in a TRIGA fuel element.

a. The probability that a tnermal neutron will lose energy in a collision with an excited state hydrogen atom in UZrHx increases.

b. The probability that a neutron will escape from the element before being captured in the fuel meat increases.

c. A shift in the thermal neutron spectrum, towards lower energies, occurs in the fuel element.

d. The mean free path for fast neutrons in the fuel element in decreased.

QUESTION (A.7) [1.0]

Assume that reactor power is 50% and equilibrium Xenon is attained. Reactor power is then increased to 100%. Which one of the following correctly describes the new equilibrium Xenon value?

a. The 100% equilibrium xenon is half the 50% value

b. The 100% equilibrium xenon is equal to the 50% value.

c. The 100% equilibrium xenon is higher than the 50% value but not twice as high.

d. The 100% equilibrium xenon is twice as high as the 50% value.

QUESTION (A.8) [1.0]

Which of the following six factor formula terms are affected most by temperature?

a. Thermal utilization and resonance escape probability

b. Fast fission factor and resonance escape probability

c. Fast fission factor and reproduction factor

d. Reproduction factor and thermal utilization

_Sar*ian A: A Theory. Thermo & Fac. Ooeratina Characteristics Page 4

- QUESTION (A.9) [1.0)-

Which one of the following factors affects the size of the delayed neutron fraction in the reactor?

a. Power level b.- Temperature of the fuel

c. Type of fuel

d. Fuel to moderator ratio

. QUESTION (A.10) [1.0]

If reactor power is increasing by a decade every minute, it has a period of:

a. 13 sec

b. 26 sec

c. 52 sec

d. 65 sec QUESTION (A.11) [1.0]

Which one of the following is the primary reason a neutron source is installed in the core?

a. To allow for testing and irradiation experiments when the reactor is shutdown.

b. To supply the neutrons required to start the chain reaction for subsequent reactor startups.

c. To provide a neutron level high enough to be monitored for a controlled reactor startup.

d. - To increase the excess reactivity of the reactor which reduces the frequency for refueling.

S

._ m *-..

Section A R Theory. Thermo & Fac. Ooeratina Characteristics Page 5 QUESTION (A.12) [1.0)

If Keff equals 1.0, how much reactivity must be added to make the reactor prompt critical?

a. The beta fraction.

b. The amount to make Keff equal to 1.1.

c. The amount to make the reactor period infinite.

d. The amount needed to increase the mean neutron lifetime to 0.080 seconds.

QUESTION (A.13) [1.0)

The reactor is subcritical with a Keff of 0.95 and a source range count rate of 15 counts per second. Control rods are withdrawn until the source range count rate equals 45 counts per second.

Which of the following is the Keff of the core after the control rod withdrawal?

a. 0.953

b. 0.970

c. 0.983

d. 0.995 QUESTION (A.14) [1.0]

The reactor is operating at 500 KW. The reactor operator withdraws the Regulating Rod adding

$0.50 of reactivity and allowing power to increase. The operator then inserts the same rod to its original position, decreasing power.

In comparison to the rod withdrawal, the rod insertion will result in:

a, the same period due to equal amounts of reactivity being added.

b. a shorter period due long lived delayed neutron precursors.

c. the same period due to equal reactivity rates from the rod.

d. a longer period due to long lived delayed neutron precursors.

4 SaMion A: A Theory. Thermo & Fac1 Ooeratina Characteristics Page 6 QUESTION (A.15) . [1.0]

Following a scram, the value of the stable reactor period is:

a. approximately 50 seconds, because the rate of negative reactivity insertion rapidly approaches zero.

b. approximately -10 seconds, as determined by the rate of decay of the shortest lived delayed neutron precursors.

c. approximately -80 seconds, as determined by the rate of decay of the longest lived delayed neutron precursors.

- d. infinity, since neutron production has been terminated.

QUESTION (A.16) [1.0]

During a reactor startup, as the reactor approaches criticality, the value of 1/M:

a .- decreases toward zero

b. decreases toward one

c. increases toward infinity

d. increases toward one .1 QUESTION (A.17) [1.0]

Which one of the following is a violation of Technical Specifications with regard to conducting a SUBCRITICAL experiment?

a. The effective multiplication factor (keff) for a new Triga fuel element configuration is 0.97,

b. A safety control rod with scram capability based on neutron flux level is used for a new Triga fuel element cunfiguration with an expected keff of 0.90.

c. The reactor is used for the initial source of neutrons for a natural uranium fuel configuration.

d. The Inverse Multiplication Method is used to predict the critical mass of a new natural uranium fuel configuration.

9 Section A: R Theory. Thermo & Fac. Ooeratina Characteristics Page 7 QUESTION (A.18) [1.0)

The Technical Specification term " Shutdown Reactivity" describes:

a. the time required for the rods to fully insert.

9

b. the departure from K-effective = 1.00

c. the amount of reactivity obtained by the removal of the control rods.

d. the minimurn reactivity required to meet the shutdown margin.

QUESTION (A.19) [1.0)

The UlUC TRIGA reactor is not permitted to be pulsed from power levels above 250kw. The reason for this requirement is:

a. The additional fast neutron flux from the pelse could dangerously embrittle fuel cladding.

b. The additional heat from the pulse could cause pool temperature limits to exceed l operating specifications.

c. The additional thermal neutron flux from the pulse could dangerously embrittle fuel cladding.

d. The additional heat from the pulse could cause fuel temperature to exceed 1000 "C.

QUESTION (A.20) [1.0)

Based on the relationship between peak power during a pulse and the reactivity added, the i

peak power can be conservatively estimated for various reactivity additions. Given the following conditions estimate the peak power for the new pulse operation. Which ONE (1) of the following peak power levels corresponds to the estimate?

Peak Power (previous pulse) = 1050 MW Reactivity added (previous pulse) = $2.00 Reactivity added (new pulse) = $1.50

a. 590 MW

b. 653 MW

c. 787 MW

d. 922 MW l

r A

' Mian B: Normal /Emera. Procedures & Rad Con Page 8 QUESTION- (B.1) [1.0)

A small radioactive source is to be stored in the reactor building. The source is estimated to -

contain 2 curies and emit a 1.33 Mev gamma.

Assuming no shielding was to be used, a Radiation Area barrier would have to be erected from

' the source at a distance of approximately;

a. 56 feet -

b. 32 feet

c. 17 feet

. d. 2 feet QUESTION (B.2) [1.0) .

A room contains a source which, when exposed, results in a general area dose rate of 175 i millirem per hour. This source is scheduled to be exposed continuously for 35 days. Select an acceptable method for controlling radiation exposure from the source within this room.

a. Post the area with the words " Danger-Radiation Area".

b. ' Equip the room with a device to visually display the current dose rate within the room.

c. Equip the room with a motion detector that will alarm in the control room,

d. Lock the room to prevent inadvertent entry into the room.

QUESTION (B.3) -[2.0)'

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

Column A Column B

1. Renewal oflicense a. 1 year

~ 2. Medical Examination b. - 2 yeart.

3. - .Requalification Written examination - c. 4 years L 4; Requalification Operating Test d. 6 years

Section B: Normal /Emera. Procedures & Rad Con Page 9 QUESTION (B.4) [1.0]

Consider two point sources; each having the same curie strength. Source A's gammas have an energy of 1 MEV whereas Source B's gamma have an energy of 2 MEV. You obtain a reading from the same Geiger counter 10 feet from each source. Concerning the two readings, which one of the following statements is correct?

a. The reading from Source B is four times that of Source A.

b. The reading from Source B is twice that of Source A.

c. Both readings are the same.

d. The reading from Source B is half that of Source A.

QUESTION (B.5) [1.0]

Which one of the folbwing is the definition for " Annual Limit on intake" (All)? ,

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

b. 10 CFR 20 derived limit, based on a Committed Effective Dose Equivalent of 5 rems whole body or 50 rems to any individual organ, for the amount of radioactive material inhaled or ingested in a year by an adult worker.

c. The effluent concentration of a radionuclide in air which, if inhaled continuously over a year, would result in a total effective dose equivalent of 50 millirem for noble gases.

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

QUESTION (B.6) [1.0]

In order to ensure the health and safety of the public,10CFR50 allows the operator to deviate from Technical Specifications. What is the minimum level of authorization needed to deviate from Tech. Specs? .

a. USNRC

b. Reactor Supervisor l

c. Licensed Senior Reactor Operator.

d. Licensed Reactor Operator.

Section B: Normal /Emera. Procedures & Rad Con Page 10

. QUESTION (B.7) -[1.0)

Which one of the following is the MAXIMUM length of time the reactor may sustain continuous operation WITHOUT performing "The Daily Checklist"?

a. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />

b. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

c. 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />

d. 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> QUESTION (B.8) [1.0)

I A system or component is defined as " operable" by Technical Specifications if:

a. a channel check has been performed.

b. a functional check has been performed.

c. it is capable of performing its intended function.

d. it has no outstanding testing requirements.

QUESTION (B.9) [1.0)

The governor requests radiation workers to clean up an accident at La Salle. While helping out .

you receive a dose of 6 Rem.10 CFR 20 requires that this dose be tracked as a Planned Special Exposure. Who is responsible for maintaining a permanent record of this dose?

a. Federal Emergency Management Agency (FEMA).

b. University of Illinois Reactor Facility

c. Nuclear Regulatory Commission.

d. State of Illinois, (an agreement state).

1

Section B: Normal /Emera Procedures & Rad Con Page 11 QUESTION (B.10) [1.0)

Which one of the following describes the "EPZ"?

a. . The EPZ is the Operations Boundary defined by the Reactor Building Walls (Confinement).

b. The EPZ is located in the north entrance to the Nuclear Engineering Lab.

c. The geographical area cutside the walls (the confinement) of the Reactor Lab for which offsite emergency planning is performed.

d. The area whose size depends on the distance beyond the Operations Boundary at which Protective Act;on Guide could be exceeded.

QUESTION (8.11) [1.0)

Which one of the following will be cause to shutdown the UlUC TRIGA reactor which is operating at 250 kw for training? )

a. An experiment with a worth of $2.20 is suspended in a basket 1 foot above the core.

I

b. The ventilation exhaust blower is taken out of service for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to lubricate the filter diversion valve.

c. The total of the absolute values of the reactivity worth of all experiments in the reactor is

$3.25

d. A fuel temperature detector is bypassed for 15 minutes to perform a channel check.

Section B: NormayEmera. Procedures & Rad Con Page 12 QUESTION (B.12) [1.0)

Which one of the following precludes operating the reactor in the PULSE rnode?

a. The reactivity worth of the transient rods is such that their reactivity worth upon withdrawal is $4.20.

b. Temperatures of the fuelimmediately prior to the pulse:

"B". hexagonal - 225 degrees Celsius

'C"-hexagonal - 230 degrees Celsius "D"-hexagonal- 195 degrees Celsius

c. The shutdown margin with the highest rod fully withdrawn is $0.75

d. The drop time of the shim rod from the fully withdrawn position to 90 percent of full reactivity insertion is 2 seconds.

QUESTION (B.13) (2.0]

Identify each of tne actions listed below as either a Channel Check, Channel Test, or Channel Calibration.

a. Verifying overlap between Nuclear Instrumentation meters,

b. Replacing an RTD with a precision resistance decade box, to verify proper channel output for a given resistance.

c. Performing a calorimetric (heat balance) calculation on the primary system, then adjusting Nuclear Instrumentation to agree.

d. During shutdown you verify that the period meter reads -80 seconds.

t

P Section B: Normal /Emera. Procedures & Rad Con Page 13 QUESTION (B.14) [1.0)-

For accident analysis, Limiting Safety System Settings establish peak fuel element temperatures.

Which one of the following phenomena is the cause of clad failure if peak fuel element temperatures are exceeded?

a. Phase change in the type 304 stainless steel reducing yield strength.

b. Production of zirconium hydride which induces swelling.

c. Metallic creep in the type 304 stainless steel.

d. Hydrogen over pressurization from the disassociation of zirconium hydride.

QUESTION (B.15) [1.0)

Which one of the following does NOT require the notification of " UNUSUAL EVENT"?

1

a. The reactor fails to scram when the reactor operator depresses the manual scram button.  !

)

l

b. The reactor operator, fearing for the safety of the reactor, initiated a manual reactor scram when he felt a tremor that was caused by an unexpected earthquake i

c. A reactor operator received a localized dose of 27 rems to his feet. ]

d. A radical group of Students Against Nuclear Energy (SANE) is marching toward the Reactor Facility, it appears that some are carrying weapons. l l

I E__m_

3 s

S M ian B: Normal /Emera. Procedures & Rad Con . Page 14 '

QUESTION (B.16) [1.0)

Which one of the following is the Basis for requiring a MINIMUM of three (3) gpm Emergency Cooling System flow?

a. Sufficient to remove the decay heat generated by fission product decay without causing fuel damage.

b. Sufficient to remove the decay heat generated by fissions from delayed neutron L precursors without causing fuel damage.

c. ' Sufficient to restore pool level following an accident during which a beam port was sheared.

d.~ Sufficient to restore pool level fo lowing an accident during which a Primary Cooling line was sheared.

QUESTION (B.17) [1.0)

Which one of the following is the basis for the Technical Specification Safety Limit associated with Low Hydride Fuel Elements?

-a Ensures phase change in the zirconium hydride which can cause distortion of the fuel  !

element does not occur. j

b. Ensures phase change in the zirconium hydride which results in melting at the centerline of the fuel element does not occur.

c. . Ensures fission product gas pressure is below that which can cause cladding failure.  !

d. Ensures hydrogen gas pressure is below that which can cause cladding failure.  !

QUESTION (B.18) [1.0)  ;

~ Which one of the following is the PRIMARY reason for ma!ntaining Primary Cooling water ,

- conductivity below 4 micromho/cm?

a. Prevents chloride stress corrosion in the stainless steel fuel cladding.

b. Prevents dissolution of oxide layer on the stainless steel fuel cladding.

c,- . Limits radiation levels associated with N-16 activity in the Primary Cooling water.

. d.: Limits radiation levels associated with activation of impurities in the Primary Cooling water. i

4 Section C Plant and Rad Monitorino Systems QUESTION (C.1) [1.0)

When you switch from steady state mode to pulse mode on the TRIGA console's mode control panel, the following changes occur to the reactor safety system:

a. All HV scrams are bypassed.

b. DAC watchdog scram is bypassed.

c. NP1000 % power and HV scrams are bypassed.

d. One of the two fuel temperature scrams is bypassed.

QUESTION (C.2) [1.0]

Which one of the following statements regarding reactor Period is TRUE7

a. The UlUC TRIGA Technical Specifications require that the Period Trip be set at greater than 3 seconds.

b. The Period circuit provides an interlock that prevents the upward movement of the ,

manually driven control rods when reactor period is too short. j

c. The Feriod Trip is allowed to be bypassed only when the mode switch is in Pulse Mode.

I

d. The Period Circuit prevents the system from entering the Pulse Mode if reactor period is greater than 20 seconds.

QUESTION (C.3) [1.0]

Which one of the following will prevent the Pneumatic Transfer (RABBIT) System exhaust  ;

blower from starting? l

a. Room 222 Priority Control key switch in ON.

b. Oil level in the exhaust blower is high.

1 4- c. Room 222A Priority Control key switch in ON.

d. High Coolant Water Temperature Cutoff actuated.

l I

Section C Plant and Rad Monitorina Systems QUESTION '(C.4) [1.0] -

Which one of the following describes the operation of the primary cooling isolation valves .

located in the tunnel?

a. Air operated valves that are spring loaded to open.

b. Air operated valves that are spring loaded to close.

c. Motor operated valves that fail as is on a loss of power.

d. Motor operated lift check valves that close if reverse flow occurs.

QUESTION (C.5) - [1.0)

The reactor is operating at 1.5 MW with the cooling towers in service. Which one of the following will ri.sult from OPENING the access doors to the cooling towers?

a. A Secondary pump low flow trip that will result in a Primary flow trip which will scram the reactor,

b. Loss of Secondary Coolant pressure which could result in primary to secondary leakage.

c. Air entrainment in Secondary Coolant water which will result in oxidation of Secondary Coolant piping. I

d. Loss of vacuum in the cooling tower will result in loss of basin level.

QUESTION (C.6) [1.0}

Which one of the following would indicate loss of the air system? I a, Low air system pressure alarm actuates in the mechanical equipment room.

. b. Reactor scram observed in the control room.

- c.

Grey control rod color for FTR and ATR observed in the control room.

d. Primary and secondary DP cell flow rates indicate straight down in the mechanical

equipment room.

Section C Plant and Rad Monitorina Systems QUESTION (C.7) [2.0)

Given the following cooling system locations:

1. Entrance to the core.

2. Exit from the core.

3. Supply to the cooling tower.

4. Return from the cooling tower.

5. Primary exit from heat exchanger

6. Secondary exit from heat exchanger.

7. Reactor tank.

8. Exit from delay tank.

Which one of the following gives the location of the coolant temperature sensors?

a. 1,3,5,7.

b. 2,4,6,8.

c. 1,2,4,6.

d. 3,5,7,8.

QUESTION . (C.8) [1.0)

Half way through a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> reactor operation at 100% power, you discover that the normal ventilation exhaust damper has been blocked open. You cannot close the damper because it is damaged. Which one of the following actions should you take?

a. Immediately secure reactor operations and comply with the requirements for reportable events,

b. Continue with reactor operations. Up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is allowed to repair the ventilation system,

c. Continue with reactor operations. The CAM will offer adequate protection while the ventilation system is being repaired.

. d. Immediately secure the reactor. This event is not reportable if the ventilation system is repaired within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

Sechon C Plant and Rad Monitonng Systems QUESTION -(C.9) [1.0)~

The Continuous Air Particulate Monitor (CAM) has alarmed and the exhaust air has failed to divert through the Charcoal Filters.

- Which one of the following actions is necessary to divert the exhaust air flow?

a. - Isolate the air supply to the dampers,

b. Open the circuit breaker for the Exhaust System.

c. Trip the exhaust fan.

d. Trip a redundant monitor on the Tracerlab 5-Channel Geiger Tube System.

QUESTION (C.10) [1.0) DELETED Which one of the following describes an interlock associated with the rod control system?

a. In the steady-state mode, APPLICATION of air to the adjustable transient rod is

- PREVENTED unless the rod cylinder is fully inserted.

b. In the steady-state mode, the simultaneous withdrawal of MORE THAN ONE motor-driven rod is PREVENTED.

c. In the pulse mode, no rod movement is permitted above 250 kw.

d. The movement of either transient rod is prohibited when any other control rod is fully withdrawn.

QUESTION (C.11) - [1.0)

-Which one of the following of the reactor scram inputs is NOT active when in the SQUARE

.- WAVE mode?

a. Peak Reactor Power b.- Watchdog

c. Fuel Element Temperature

d. Reactor period

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c Smelian C' Plant and Rad Monitorina Systems QUESTION '(C.12) . [1.0)

- Which one of the following describes the operation of the adjustable transient control rod?

The Adjustable Trans'ent. Control Rod ...

a. is pneumatically inserted and withdrawn by either decreasing or increasing the pressure on the air cylinder.

b. remains inserted in the core except when air is removed from the air cylinder..

c. is electromechanically inserted and withdrawn by adjusting the position of the air cylinder.

d. is controlled by electromechanical positioning of a threaded rod connected to a shock absorbing piston.

QUESTION (C.13) [1.0]

With a normal system line-up and all automatic functions operating, which one of the following does not describe one of the possible results of opening the Core Spray Emergency Makeup valve (V-4) located outside the control room?

-a. 3 GPM of spray flow is provided from the demineralizers.

b. At 18 inches below normal level, 5-8 GPM of spray flow is provided from the domineralizers. I

c. City water is directly applied to the spray system.

d. At 6 inches below normal level,3 GPM of spray flow is provided from the domineralizers.

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Section C Plant and Rad Monitorino Systems QUESTION (C.14) [1.0]

The TRIGA reactor is being operated in the square wave mode. The adjustable transient rod is fired and power has stabilized at 500kW.

Which one of the following conditions would cause an automatic reactor scram?

a. Primary coolant pump trip.

{

b. A reactor period of 2 seconds occurs.

c. NM1000 High Voltage power supplies fail.

d. NP1000 channel fails upscale.

l QUESTION (C.15) [1.0]

I Which one of the following is the reason the Secondary Cooling System is always started prior to initiating Forced Convection Primary Cooling?

a. To prevent thermal shock to the Primary piping. I l

b. To prevent possible Primary to Secondary leakage.

c. To allow controlled heatup of Primary piping.

d. To allow for controlled heatup of Secondary Cooling Towers.

QUESTION (C.16) [1.0)

Which one of the following is the reason the Fast Transient Rod (FTR) contains double length of poison?

a. Allows the rod to reach a constant velocity prior to leaving the core so positive reactivity addition is at a constant rate.

b. The extra length allows for a more even flux shape when the rod is ejected.

c. Allows the rod to reach a constant velocity when falling back into the core so negative reactivity addition is at a constant rate.

d. The extra length allows for more negative reactivity addition when the rod falls back into the core.

Section C Plant and Rad Monitorino Systems QUESTION (C.17) [1.0)

The reactor is operating at 1 MW steady-state. The North beam port is in use.

Which one of the following groups of radiation monitors satisfy MINIMUM requirements for continued operation per Technical Specifications 3.4, Reactor Instrumentation"?

Reactor Tank Air Particulate Stack Beam Port Monitor Monitor Monitor Monitor

a. Yes Yes No No

b. No No Yes Yes

c. Yes No Yes No

d. Yes Yes Yes Yes l

QUESTION (C.18) [1.0)

Which one of the following is indicated by the fuel temperature thermocouple?

a. Fuel centerline temperature

b. Zirconium rod temperature

c. Fuel element cladding temperature

d. Fuel element surface temperature QUESTION - (C.19) [1.0)

Which one of the following is the reason a polyethylene vial may NOT be irradiated in the Central Thimble at high power levels without special approvals?

a. Large thermal neutron flux can cause excessive neutron activation. j

b. Excessive Gas pressure can cause the vials to explode.

c. Excessive heat buildup can cause the vials to deform or melt.

l d. Fast neutron activation can cause the vials to become brittle.

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Section A R Theory. Thermo & Fac. Ooeratina Characteristics ANSWER (A.1)

-c REFERENCE

~ At 20 feet, all measured radiation is from gammas.

D,r,8 = D,o r2o' D, (1)2 = 0.1 mr (20)2 D, = 40 mrem /hr gamma Ratio of beta to total = 1 -(40/200) = 80%

ANSWER ~ (A.2) b REFERENCE A = A, e " A = .693/T2 In(A/A ) = .693t/T2 -

T2 = .693 24hr/in 0.8 = 75 hr ANSWER (A.3) c REFERENCE Burn, R., introduction to Nuclear Reactor Operations, @ 1988, 9 3.3.4, p. 3-21.

ANSWER (A.4) b REFERENCE Lamarsh, J.R., introduction to Nuclear Engineering, Addison-Wesley Publishing, Reading, Massachusetts, 1983. & 7.2, p. 303.

Burn, R., Introduction to Nuclear Reactor Operations, @ 1982, 5 7.2 & 7.3, pp. 7 7-9.

ANSWER (A.5) d REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, C 1988, Chapt. 5, pp. 5 5-28.

ANSWER (A.6) b REFERENCE UlUC,Trng Materials pg.1-5 ANSWER (A.7) c REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, @ 1988, g9 8.2 - 8.4, pp. 8 8-14,

' Fig. 8-2

Section A R Theorv. Thermo & Fac. Ooeratina Characteristica ANSWER (A.8) a REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, @ 1988, S 3.3, pp. 3 3-19 ANSWER (A.9) c.

REFERENCE

" Training Notes", page 2.

ANSWER (A.10) b REFERENCE P = Po e'" 10 = 1e""

In 10 = 60/T 2.3 = 60/T T = 60/2.3 T = 26 seconds ANSWER (A.11) c REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, C 1982, G 5.2 (b), p. 5-4.

ANSWER (A.12) a REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, @ 1982, g 4.2, p. 4-1.

ANSWER (A.13) c REFERENCE CR,/CR2= (1-Keff2)/(1-Keff,)

15/45= (1-Keff,/(1-0.95) ~ (0.05)(0.3333)= 1-Keff, Keff,= 1- 0.016665= 0.983 ANSWER (A.14) d REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, @ 1988, SG 4.5.

ANSWER (A.15) c REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, C 1982, 4.6, p. 4-16.

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Section A: R Theorv. Thermo & Fac. ooeratina Characteristics Page 24 ANSWER - (A.16) a REFERENCE Glasstone, S. a'nd Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida, 1991, $$ 3.161 - 3.163, pp.191 - 192.

- ANSWER (A.17) [1.0]

b REFERENCE Technical Specification 3.9, "Suberitical Experiments Using the Reactor Thermal Column or Bulk Shielding Facility", page 19.

ANSWER (A.18) [1.0}

d-REFERENCE Volume 1, Training Materials and System Diagrams, Page 1-33 ANSWER (A.19) [1.0]

d REFERENCE UlUC T.S. 3.1.e Basis SAR pg.111-44 ANSWER (A.20) [1.0) a REFERENCE Reactor Theory - Fuchs-Nordheim Kinetics Model pg. 4 P,/p' = P,/p' 1050/(2)' = P,/(1.5)8 P, = 1050(1.5) /(2)2 = 590.63 MW

')

Section B: Normal /Emera. Procedures & Rad Con Page 25 ANSWER . (B.01) [1.0) a-REFERENCE Glasstone & Sesonske,9.41, p 525.

DR= 6CE/x2 = 0.005 = 6(2)(1.33)/x 2, x' = 3192, x = 56.5 feet ANSWER (B.02) [1.0) d REFERENCE 10CFR20.1601(a)(3)

ANSWER (B.03) [2.0]

1 .d_ 2 _b_ 3 _b_ 4 .a.

REFERENCE 10CFR55 ANSWER (8.04) [1.0]

c REFERENCE GM is not sensitive to energy.

ANSWER (B.05) [1.0]

b REFERENCE 10CFR20.1003 ANSWER (B.06) [1.0]

c REFERENCE 10CFR50.54(y)

ANSWER (8.07) [1.0) d REFERENCE 1994 Exam ANSWER (8.08) [1.0]

.c REFERENCE

' Tech. Specs Definition 1.6 ANSWER (B.9) [1,0]

b REFERENCE 10CFR20 4

Mian Cf Plant and Rad Monitorina Systems Page 26 ANSWER (B.10) [1.0]

a REFERENCE E-Plan; Definitions pg. 6 of 27 ANSWER (B.11) [1.0) .

a REFERENCE Technical Specification 3.1.b ANSWER (B.12) [1.0]

d REFERENCE Tech. Specs 3.3 and 3.1

' ANSWER (B.13) [2.0) a, check; b, test; c, calibration; d, check REFERENCE.

Tech. Specs, Definitions pg. 3 ANSWER (B.14) [1.0]

d REFERENCE-Technical Specification 2.1.a Bases.

~ ANSWER (B.15) [1.0]

a, c REFERENCE Emergency Plan pg.10 4

ANSWER (B.16) [1.0).

a.-

REFERENCE'

1. Tech. Spec. 3.4, " Emergency Removal Of Decay Heat", page 30.

2. SAR,Section IV.C.3.c, " Emergency Spray Cooling", pages IV-50 to IV-59.

ANSWER (B.17) [1.0]

.a.

REFERENCE Tech.l Spec. 2.1, " Safety Limit - Fuel Element Temperature", page 4. l ANSWER (B.18) [1.0]

- d.

- REFERENCE SAR VI.F. ' Water Purification Loop", page VI-21.

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Section C: Plant and Rad Monitorina Systems Page 27 ANSWER (C.1) [1.0) c REFERENCE Operator's Manual Pg. 6-1; Fig. 20 Scram Loop pg.1-35 ANSWER (C.2) [1.0) d REFERENCE Operator's Manual pg. 6-1 Prereq. 3 ANSWER (C.3) [1.0) d REFERENCE NRLOP-8, Section 6.a, pg.1. j

- ANSWER (C.4) [1.0) b REFERENCE SAR,Section VI, Safeguards, Subsection VI.C.2, System Design, pg. VI-13.

ANSWER (C.5) [1.0]

a REFERENCE

" Training Notes", Section 3.C.ll, page 17.

ANSWER (C.6) -[1.0) d REFERENCE Training Notes, Section 3.D, pg.18.

ANSWER (C.7) [2.0) c REFERENCE-SAR, Chapter Vil, Section Vll.B.S.d, pg. Vll-23.

ANSWER (C.8) [1.0) a REFERENCE T.S. 3.7, Ventilation System T.S. 6.7 b.3 ANSWER (C.9) [1.0) -

b REFERENCE

" Training Notes University Of Illinois Advanced Triga", Section 3.F-., page 19.

Ib n .,

t Section C: Plant and Rad Monitorina Systems Page 28 ANSWER (C.10) [1.0) DELETED a

REFERENCE SAR, Chapter Vil, Section Vll.B.10, pg. 29.

~ ANSWER (C.11) [1.0]

d REFERENCE "UlUC Operation and Maintenance Manual, Appendix A", page 5-3.

ANSWER (C.12) [1.0]

c REFERENCE SAR, Chapter Vil, Section Vll.B.3.b, pg.17.

ANSWER (C.13) [i.0]

c REFERENCE FSAR Sect. VI-B.2 and FIG VI-2 ANSWER (C.14) [1.0]

d>

REFERENCE UlUC Operation and Maintenance Manual pg.1-41 and Fig.19 p ANSWER (C.15) [1.0]

b REFERENCE

" Training Notes University Of Illinois Advanced Triga", Section 3.C.ll, page 17.

ANSWER (C.16) [1.0) a REFERENCE j

" Training Notes University Of Illinois Advanced Triga", Section 3.A.lll, page 13.

l l

' ANSWER (C.17) [1.0) l d

REFERENCE j SAR Section: XI.E.3., " Additional Requirements", page XI-25.

T.S. 3.4 - Reactor instrumentation ANSWER (C.18) [1.0]

a REFERENCE SAR lll.C.2.," Core Assembly", page lil-13. j

'(.

- Section C: Plant and Rad Monitorina Systems Page 29 -

ANSWER (C.19) '[1.0]

c REFERENCE'

" Training Notes University Of lilinois Advanced Triga", Section 3.B.I, page 14.

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