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Examination Report No. 50-602/OL-13-01, University of Texas at Austin
	ML13116A142
Person / Time
Site:	University of Texas at Austin
Issue date:	05/02/2013
From:	Gregory Bowman; Research and Test Reactors Branch B
To:	Whaley P; University of Texas at Austin
	Lichatz, T
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ML13030A497	List: ML13030A492; ML13116A142; ML13116A256;
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May 2, 2013 Paul Whaley, Associate Director Nuclear Engineering Teaching Lab University of Texas at Austin NETL-PRC Bldg 159 10100 Burnet Rd Austin, TX 78758

SUBJECT:

EXAMINATION REPORT NO. 50-602/OL-13-01, UNIVERSITY OF TEXAS AT AUSTIN

Dear Mr. Whaley:

During the week of April 8, 2013, the Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your TRIGA Reactor. The examination was conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with Title 10 of the Code of Federal Regulations Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. The 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 Mr. John T. Nguyen at (301) 415-4007 or via electronic mail John.Nguyen@nrc.gov.

Sincerely,

/RA/

Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-602

Enclosures:

1. Examination Report No. 50-602/OL-13-01

2. Written examination with facility comments incorporated cc: Michael Krause, Reactor Supervisor cc w/o enclosures: See next page

University of Texas - Austin 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 Dr. William Powers, Jr., President University of Texas at Austin Nuclear Engineering teaching Laboratory Austin, TX 78758 Mr. Roger Mulder Office of the Governor P.O. Box 12428 Austin, TX 78711 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

May 2, 2013 Paul Whaley, Associate Director Nuclear Engineering Teaching Lab University of Texas at Austin NETL-PRC Bldg 159 10100 Burnet Rd Austin, TX 78758

SUBJECT:

EXAMINATION REPORT NO. 50-602/OL-13-01, UNIVERSITY OF TEXAS AT AUSTIN

Dear Mr. Whaley:

During the week of April 8, 2013, the Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your TRIGA Reactor. The examination was conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with Title 10 of the Code of Federal Regulations Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. The 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 Mr. John T. Nguyen at (301) 415-4007 or electronic mail John.Nguyen@nrc.gov.

Sincerely,

/RA/

Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-602

Enclosures:

1. Examination Report No. 50-602/OL-13-01

2. Written examination with facility comments incorporated cc: Michael Krause, Reactor Supervisor cc w/o enclosures: See next page DISTRIBUTION:

PUBLIC RidsNrrDprPrta RidsNrrDprPrtb Facility File (CRevelle) O-07 F-08 JNguyen, NRR TLichatz, NRR ADAMS ACCESSION #: ML13116A142 TEMPLATE #: NRR-079 Office PROB/EIT PROB/CE IOLB/OLA PROB/BC Name TLichatz JNguyen CRevelle GBowman Date 4/24/13 4/24/13 05/01/2013 05/02/2013 OFFICIAL RECORD COPY

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-602/OL-13-01 FACILITY DOCKET NO.: 50-602 FACILITY LICENSE NO.: R-129 FACILITY: UNIVERSITY of TEXAS at AUSTIN EXAMINATION DATES: April 9-10, 2013 SUBMITTED BY: ________/GBowman for/________ _04/24/2012__

John T. Nguyen, Chief Examiner Date

SUMMARY

During the week of April 8, 2013, the NRC administered the operator licensing examinations to three Reactor Operator candidates and one Senior Reactor Operator Upgrade candidate. All candidates passed all portions of the examination.

REPORT DETAILS

1. Examiners: John T. Nguyen, Chief Examiner, NRC Taylor A. Lichatz, Examiner-in-Training, NRC

2. Results:

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

3. Exit Meeting:

John Nguyen, NRC Taylor Lichatz, NRC Michael Krause, Reactor Manager The examiner thanked the facility for their support during the examination and their comments on questions. The examiner indicated no generic weaknesses were noted during the operating examination.

ENCLOSURE 1

U. S. NUCLEAR REGULATORY COMMISSION RESEARCH AND TEST REACTOR OPERATOR LICENSING EXAMINATION FACILITY: UNIVERSITY of TEXAS at AUSTIN REACTOR TYPE: TRIGA DATE ADMINISTERED: 04/09/2013 CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

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

% of Category % of Candidates Category Value Total Score Value Category 20.00 33.33 A. Reactor Theory, Thermodynamics and Facility Operating Characteristics 20.00 33.33 B. Normal and Emergency Operating Procedures and Radiological Controls 20.00 33.33 C. Plant and Radiation Monitoring Systems FINAL GRADE

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

Candidate's Signature 1 ENCLOSURE 2

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

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

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

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

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

5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each answer sheet.

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

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

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

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

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

2

EQUATION SHEET

Q = m c p T = m H = UA T

( - )2 * -4

1 x 10 seconds P max

2 (k)

S CR 1 (1 - K eff 1 ) = CR 2 (1 - K eff 2 )

SCR =

1 - K eff eff = 0.1 sec-1 eff SUR = 26.06 1 - K eff 0 1 CR1

- M= M= =

1 - K eff 1 1 - K eff CR 2 P = P0 10 SUR(t) t (1 - )

P = P0 e P= P0 (1 - K eff ) * -

SDM = = =

+

K eff -

eff K eff 2 - K eff 1 0.693 ( K eff - 1)

T=

k eff 1 x K eff 2 K eff 6CiE(n) 2 DR1 d 1 = DR 2 d 2 2

DR = DR0 e- t DR = 2 R

2

( 2 - )2 ( 1 - )

=

Peak 2 Peak 1 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lbm 3

1 Horsepower = 2.54 x 10 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 3

1 BTU = 778 ft-lbf EF = 9/5 EC + 32 1 gal (H2O) . 8 lbm EC = 5/9 (EF - 32) 4

Section A L Theory, Thermo, and Facility Characteristics ANSWER SHEET Multiple Choice (Circle or X your choice)

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

A001 a b c d __

A002 a b c d __

A003 a b c d __

A004 a b c d __

A005 a b c d __

A006 a b c d __

A007 a b c d __

A008 a b c d __

A009 a b c d __

A010 a b c d __

A011 a b c d __

A012 a b c d __

A013 a b c d __

A014 a b c d __

A015 a b c d __

A016 a b c d __

A017 a b c d __

A018 a b c d __

A019 a b c d __

A020 a b c d __

5

Section 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.

B001 a __ b __ c __ d ___ (typo)

B002 a b c d __

B003 a b c d __

B004 a b c d __

B005 a b c d __

B006 a b c d __

B007 a b c d __

B008 a b c d __

B009 a b c d __

B010 a b c d __

B011 a b c d __

B012 a b c d __

B013 a b c d __

B014 a b c d __

B015 a b c d __

B016 a b c d __

B017 a b c d __

B018 a b c d __

B019 a b c d __

B020 a __ b __ c __ d ___

6

Section C Facility and Radiation Monitoring Systems ANSWER SHEET Multiple Choice (Circle or X your choice)

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

C001 a b c d __

C002 a b c d __

C003 a b c d __

C004 a b c d __

C005 a b c d __

C006 a b c d __

C007 a b c d __

C008 a b c d __

C009 a b c d __

C010 a b c d __

C011 a b c d __

C012 a b c d __

C013 a __ b __ c __ d __

C014 a b c d __

C015 a b c d __

C016 a b c d __

C017 a b c d __

C018 a b c d __

C019 a b c d __

C020 a b c d __

- - - - END OF EXAMINATION *****

7

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

Which statement properly describes a thermal neutron?

a. A neutron at an energy level greater than its surroundings.

b. A neutron born directly from fission.

c. A neutron in equilibrium with its surroundings.

d. A neutron born due to decay of a fission product.

Question A.2 [1.0 point]

Reactor power is increasing on a 35-second period. Approximately how long will it take for power to double?

a. 17 seconds

b. 24 seconds

c. 51 seconds

d. 70 seconds Question A.3 [1.0 point]

You are the reactor operator performing two pulsing operations. The first pulse has a reactivity worth of $1.20 which results in a peak power of 200 MW. If the second pulse has a peak power of 5000 MW, the corresponding reactivity worth is:

Given:

=0.0070

a. $1.50

b. $1.75

c. $2.00

d. $2.25 8

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

Which ONE of the following combinations of characteristics makes a good reflector?

Scattering Cross Section Absorption Cross Section

a. High Low

b. Low High

c. High High

d. Low Low Question A.5 [1.0 point]

Which ONE of the following is the time period in which the MAXIMUM amount of Xe-135 will be present in the core?

a. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after a startup to 100% power

b. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after a scram from 100% power

c. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after a power increase from 50% to 100%

d. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after a power decrease from 100% to 50%

Question A.6 [1.0 point]

Which ONE of the following is the stable reactor period which will result in a power rise from 25% to 100% power in 75 seconds?

a. 27 seconds

b. 54 seconds

c. 68 seconds

d. 134 seconds 9

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

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

a. Decreases toward zero

b. Decreases toward one

c. Increases toward one

d. Increases towards infinity Question A.8 [1.0 point]

In a subcritical reactor, Keff is increased from 0.918 to 0.965. Which one of the following is the amount of reactivity that was added to the core?

a. 3.63 %k/k

b. 5.31 %k/k

c. 7.28 %k/k

d. 8.93 %k/k 10

Section A L Theory, Thermo, and Facility Characteristics Question A.9 [1.0 point]

Which ONE of the following statements best describes on how an INCREASE in moderator temperature affects the core operating characteristics?

a. Will DECREASE the neutron multiplication factor due to the resonance escape probability DECREASE

b. Will INCREASE the neutron multiplication factor due to the resonance escape probability INCREASE

c. Will INCREASE the neutron multiplication factor due to the reproduction factor DECREASE

d. Will DECREASE the neutron multiplication factor due to the reproduction factor INCREASE Question A.10 [1.0 point]

Which ONE of the following best describes beta decay (-1) of a nucleus?

a. Atomic mass number increases by 1, and the number of protons increases by 1

b. Atomic mass number increases by 1, and the number of protons decreases by 1

c. Atomic mass number remains unchanged, and the number of protons increases by 1

d. Atomic mass number remains unchanged, and the number of protons decreases by 1 Question A.11 [1.0 point]

Assume that the worths of the Safety, Shim, and Reg rods are $4.50, $3.75, and $2.00, respectively. The reactor is critical at 15 W after WITHDRAWING the following control rod worths: Safety $3.50, Shim $2.00, and Reg $1.50. What is the CORE EXCESS?

a. $2.75

b. $3.25

c. $6.50

d. $7.00 11

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

Which ONE of the following parameters is MOST significant in determining the differential rod worth of a control rod?

a. Reactor power

b. Rod speed

c. Fuel temperature

d. Flux shape Question A.13 [1.0 point]

What has the greatest affect on the THERMAL UTILIZATION FACTOR in the six factor formula?

a. Xenon buildup

b. Moderator temperature

c. Control rods

d. Fuel density Question A.14 [1.0 point]

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

a. From 1W to 5W

b. From 10W to 40W

c. From 10kW to 20kW

d. From 100kW to 250kW 12

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

In a just critical reactor, the MOST LIKELY result of ADDING $1.00 of reactivity will cause:

a. The resultant period to be a function of the prompt neutron lifetime

b. The reactor period to be equal to ( - )/(*)

c. A sudden increase in delayed neutrons

d. A sudden drop in neutron flux Question A.16 [1.0 point]

ELASTIC SCATTERING is the process by which a neutron collides with a ground state nucleus and:

a. is absorbed, with the nucleus emitting a gamma ray and a neutron with a lower kinetic energy

b. recoils with a higher kinetic energy than it had prior to the collision with the nucleus emitting a gamma ray

c. is absorbed, with the nucleus emitting a gamma ray

d. recoils with the same kinetic energy it had prior to the collision Question A.17 [1.0 point]

Which ONE of the following is the MOST reason that causes the reactor power to rapidly decrease in the U-ZrH material used in the TRIGA fuel due to a rapid power excursion (rapid reactivity change)?

a. By increasing of the reproduction factor

b. By decreasing of the reproduction factor

c. By increasing of the thermal utilization factor

d. By decreasing of the thermal utilization factor 13

Section A L Theory, Thermo, and Facility Characteristics Question A.18 [1.0 point]

A reactor with Keff = 0.7 contributes 1500 neutrons in the first generation. Changing from the first generation to the third generation, the number of TOTAL neutrons in the THIRD generation is:

a. 2550

b. 4335

c. 4500

d. 5100 Question A.19 [1.0 point]

The scram setpoint of a reactor is 1100 kW and the computer system delay prior to initiation of the rod drop is 0.05 seconds. If an injection of a sample results in a 100 millisecond period, which ONE of the following is the peak power of the reactor at SHUTDOWN?

a. 1105 Kw

b. 1156 kW

c. 1813 kW

d. 1856 kW Question A.20 [1.0 point]

Which ONE of the following describes how delayed neutrons are produced?

a. Directly from fission

b. Decay of fission fragments

c. Decay of O-16

d. Photoelectric effect 14

Section B Normal, Emergency and Radiological Control Procedures Question B.1 [1.0 point, 0.33 each]

Match the appropriate rod with its definition.

Rod Type Definition

a. Transient Rod 1. Regulating and shim rods

b. Regulating Rod 2. Control rod with an electric motor drive that does not perform a special function

c. Shim Rod 3. A control rod used to maintain an intended power level and may be varied manually or by a servo-controller.

4. Control rod used to initiate a power pulse that is operated by a motor drive and/or air pressure.

Question B.2 [1.0 point]

Annual limit on intake (ALI) means the derived limit for the amount of radioactive material taken into the body of an adult worker by inhalation or ingestion in a year. What is the regulatory limit on the total effective dose equivalent for an individual in one year?

a. 50 mRem

b. 500mRem

c. 5 Rem

d. 50 Rem Question B.3 [1.0 point]

Which ONE of the following events would NOT be classified as a Notification of Unusual Event?

a. Civil disturbances directed toward the reactor facility.

b. Severe natural events being experienced that are causing observable damage to reactor systems.

c. Loss of core coolant at a rate of 5 gallons per week.

d. Sustained fire in the reactor bay area.

15

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

A survey instrument with a window probe is used to measure the beta-gamma dose rate from an irradiated experiment. The dose rate is 250 mrem/hour with the window opened and 80 mrem/hour with the window closed. The gamma dose rate is:

a. 330 mrem/hour

b. 250 mrem/hour

c. 170 mrem/hour

d. 80 mrem/hour Question B.5 [1.0 point]

According to NETL Procedure FUEL-2, which is NOT specifically a requirement for movement of experiments?

a. Reactivity effects of $1.20 shall require supervision by a licensed senior operator.

b. Removal or replacement of experiment or facilities into or from the reactor core shall be recorded in the reactor logbook.

c. All experiments in the reactor tank shall be secured as required by reactivity constraints.

d. A licensed senior operator shall supervise all experiment facility or experiment movements in the reactor pool.

Question B.6 [1.0 point]

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

a. Revise the NETL Procedure OPER-1, Startup - Shutdown Checks

b. Revise the written examination

c. Revise the NETL Procedure Main-1, Interlock and SCRAM Features

d. Reduce the minimum number of Nuclear Reactor Committee members from three to two 16

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

Which ONE of the following surveillances is a channel check (CHECK)?

a. You disconnect the communication cable to verify the reactor scram.

b. During 1 MW power, you compare the readings of the Percent Power Channel and Linear Power Channel.

c. You expose a 2 mCi check source to the continuous air monitor (CAM) detector to verify that its output is operable.

d. During performance of the Daily Checklist, you press a button on the NPP-1000 to verify the reactor scram.

Question B.8 [1.0 point]

Which one of the following is the next FOUR CORRECT SEQUENCE of actions, following immediate reactor shutdown, which should be taken for a Non-Reactor Specific Event according to NETL Procedure PLAN-E?

a. SECURE radioactive materials as necessary; NOTIFY all persons in the immediate areas; render immediate ASSISTANCE to any victim; IDENTIFY the responsible person to be designated emergency director

b. SECURE radioactive materials as necessary; NOTIFY and/or verify notification of University Radiation Safety Officer and the NETL Director; NOTIFY all persons in the immediate areas; IDENTIFY the responsible person to be designated emergency director

c. NOTIFY all persons in the immediate areas; render immediate ASSISTANCE to any victim; SECURE radioactive materials as necessary; IDENTIFY the responsible person to be designated emergency director

d. Render immediate ASSISTANCE to any victim; SECURE radioactive materials as necessary; NOTIFY all persons in the immediate areas; IDENTIFY the responsible person to be designated emergency director 17

Section B Normal, Emergency and Radiological Control Procedures Question B.9 [1.0 point]

Based on 10 CFR Part 55, what are the MINIMUM operation requirements to maintain an active operators license?

a. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per quarter.

b. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per quarter.

c. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per month.

d. 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months per year.

Question B.10 [1.0 point]

You are performing the weekly survey and come across a sign that says, Caution - Radiation Area. What is the minimum radiation level that would be detected in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at 30cm from the radiation source?

a. 0.0005 Rem

b. 0.005 Rem

c. 0.05 Rem

d. 0.100 Rem Question B.11 [1.0 point]

For an emergency that requires evacuation of a room or area of the building, what is the location of the PRIMARY emergency assembly area?

a. Parking Lot

b. NETL Annex

c. Facility Receptionist Office Area

d. Health Physics Laboratory 18

Section B Normal, Emergency and Radiological Control Procedures Question B.12 [1.0 point]

While performing NETL Procedure OPER-2, Reactor Startup and Shutdown, and the reactor is in manual mode, what is the guideline for withdrawing shim rods and what is the ideal period?

a. 60 units or less; +20 seconds

b. 50 units or less; +10 seconds

c. 50 units or less; +20 seconds

d. 60 units or less; +10 seconds Question B.13 [1.0 point]

A continuous air monitor (Ar-41) shall be operable with readout and audible alarms. This is an example of a:

a. Safety Limit

b. Limiting Safety System Setting

c. Limiting Condition for Operation

d. Surveillance Requirement Question B.14 [1.0 point]

Per NETL Procedure OPER-2, the MINIMUM staffing required for an RO performing the INITIAL reactor startup are:

a. RO with SRO present

b. RO with SRO on call within 30 minutes and a second person in the building

c. RO with SRO in the building

d. RO with second person in the building 19

Section B Normal, Emergency and Radiological Control Procedures Question B.15 [1.0 point]

What is the HALF LIFE of the isotope contained in a sample which produces the following count rates?

Time (Minutes) Counts per Minute (cpm)

Initial 950 60 702 120 518 180 383 240 283

a. 124

b. 137

c. 201

d. 558 Question B.16 [1.0 point]

Which of the following accurately represents the surveillance requirements for the reactor safety system AS STATED IN Technical Specification 4.2.3?

a. The minimum safety channels shall be calibrated annually or after repair or modification.

b. All of the safety channels shall be calibrated annually or after repair or modification.

c. The minimum safety channels shall be calibrated semiannually or after repair or modification.

d. All of the safety channels shall be calibrated semiannually.

20

Section B Normal, Emergency and Radiological Control Procedures Question B.17 [1.0 point]

Which ONE of the following would be an initiating condition for a NON-Reactor Specific Emergency?

a. Discovery of a forced entry or SNM theft

b. Damage to building reactor systems or facility utilities

c. Nearby, threatening, or impending natural disaster

d. > 20mr/hr at operations boundary from unknown source Question B.18 [1.0 point]

Which ONE of the following actions is an example of a CHANNEL CHECK?

a. Placing a source next to a radiation detector and observing meter movement

b. Observing the overlap between two different neutron detectors as power increases

c. Immersing a thermometer in an ice bath, then in boiling water and noting the output

d. Performing a determination of reactor power with a heat balance, then adjusting a power meter to correspond to the heat balance 21

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

Which ONE of the following statements correctly describes the relationship between the Safety Limit (SL) and the Limiting Safety System Setting (LSSS)?

a. The LSSS is a limit on important process variables that assures the integrity of the fuel cladding. The SL initiates protective action to preclude reaching the LSSS.

b. The SL is a limit on important process variables that assures the integrity of the fuel cladding. The LSSS initiates protective actions to preclude reaching the SL.

c. The SL is a maximum operationally limiting value that prevents exceeding the LSSS during normal operations.

d. The SL is a maximum setpoint for instrumentation response. The LSSS is the minimum number of channels required to be operable.

Question B.20 [1.0 point, 0.25 each]

Match the type of radiation (Column A) with the proper penetrating power (Column B). Each item may be used only once.

Column A Column B

a. Neutron 1. Stopped by a thin sheet of metal

b. Gamma 2. Stopped by a thin sheet of paper

c. Alpha 3. Best shielded by heavy (high-z) material

d. Beta 4. Best shielded by light (low-z) material 22

Section C Plant and Radiation Monitoring Systems Question C.1 [1.0 point The majority of the facilitys Ar-41 is produced in the:

a. Experimental facilities

b. Reactor room area

c. Fume sorting hood area

d. Reactor pool Question C.2 [1.0 point]

Which ONE of the following would best describe the beam tube facilities of the UT TRIGA reactor? Five beam tubes of 6 inch diameter with:

a. THREE beam ports are tangential to the reactor core, all terminating at the tangential point to the core, and TWO radial beam ports that terminate at the outer edge of the reflector.

b. ONE beam port tangential to the reactor core, extending both directions from the reflector and out opposite sides of the reactor shield, and THREE radial beam ports that terminate at the outer edge of the reflector.

c. TWO beam ports are tangential to the reactor core, one terminating at the tangential point to the core and the other extending both directions from the reflector and out opposite sides of the reactor shield, and ONE radial beam port that terminates at the outer edge of the reflector and ONE radial beam port that terminates at the inner shroud

d. THREE beam ports are tangential to the reactor core, all terminating at the tangential point to the core, and TWO radial beam ports that terminate at the outer edge of the reflector.

23

Section C Plant and Radiation Monitoring Systems Question C.3 [1.0 point]

Which ONE of the following is the designed goal for the radiological exposure constraint for the accessible areas of the pool and shield system during full power operation?

a. 1 mrem/hour

b. 2 mrem/hour

c. 5 mrem/hour

d. 10 mrem/hour Question C.4 [1.0 point]

Which ONE of the following changes will have an effect on the NM-1000 indications when operating in the steady state mode?

a. Primary flow rate transmitters

b. Cambelling portion of the fission chamber signal processing circuitry provides no signal at 200 kW

c. NVT circuit failed and is indicating 50 MWS on the bargraph

d. Loss of power to the water temperature transmitters Question C.5 [1.0 point]

What is the alarm set point for the continuous air monitor (Argon-41) according to Technical Specification 3.3.3?

a. 2 x 10-5 Ci/cm3

b. 2 x 10-6 Ci/cm3

c. 2.5 x 10-5 Ci/cm3

d. 3 x 10-6 Ci/cm3 24

Section C Plant and Radiation Monitoring Systems Question C.6 [1.0 point]

Which ONE of the following statements correctly describes the reactor pool?

a. Siphon break holes in suction and discharge lines are above the 7.60 meter level to protect against excess radiation at the pool surface and should not extend below 2 meters from the top of the tank.

b. Siphon break holes in suction and discharge lines are above the 7.60 meter level to protect against pool water loss and suction line should not extend below 2 meters from the top of the tank.

c. Siphon break holes in suction and discharge lines are above the 6.00 meter level to protect against excess radiation at the pool surface and should not extend below 3 meters from the top of the tank.

d. Siphon break holes in suction and discharge lines are above the 6.00 meter level to protect against pool water loss and should not extend below 3 meters from the top of the tank.

Question C.7 [1.0 point]

If the airborne particulate radioactivity exceeds the CAM setpoint, which ONE of the following is the correct ventilation system response?

a. The exhaust dampers open and the supply dampers close

b. The exhaust dampers close and the supply dampers open

c. The exhaust and supply dampers close

d. The exhaust and supply dampers open Question C.8 [1.0 point]

Which ONE of the following conditions will cause the operating reactor to automatically SCRAM?

a. Reactor period = 6 seconds

b. 20% loss of high voltage on the NP-1000

c. Reactor power NP-1000 = 1020 kW (change made during the administration of the examination)

d. Fuel temperature = 495 °C 25

Section C Plant and Radiation Monitoring Systems Question C.9 [1.0 point]

The Technical Specifications limit the pool conductivity. The BEST conductivity probe location to measure this limit is at the:

a. outlet of the purification system filter

b. outlet of the coolant system heat exchanger

c. discharge of the purification system pump

d. inlet of the purification system filter Question C.10 [1.0 point]

Which ONE of the following channels provides the wide range log power and multi-range linear power from source level to full power information displayed on the control system computer?

a. NM-1000

b. NP-1000

c. NPP-1000

d. Pulse frequency translator Question C.11 [1.0 point]

How does the transient rod drive assembly function?

a. In steady-state mode via an electric stepping-motor-actuated linear drive equipped with a magnetic coupler and positive feedback potentiometer.

b. In pulse mode via an electric stepping-motor-actuated linear drive equipped with a magnetic coupler and positive feedback potentiometer.

c. In steady-state mode and pulse mode solely via a single-acting pneumatic cylinder.

d. In steady-state mode via operation of an electric motor and pulse mode via a single acting pneumatic cylinder.

26

Section C Plant and Radiation Monitoring Systems Question C.12 [1.0 point]

Per the UT NETL SAR, the typical water conductivity found is ______ mho/cm, but the conductivity averaged over a month shall not exceed ______ mho/cm per the Technical Specifications in the UT TRIGA pool water.

a. 3 mho/cm; 5 mho/cm

b. 2 mho/cm; 5 mho/cm

c. 2 mho/cm; 6 mho/cm

d. 3 mho/cm; 6 mho/cm Question C.13 [1.0 point, 0.25 each]

Match the input signals listed in column A with their respective responses listed in column B.

(Note: Items listed in column B may be used more than once or not at all.)

Column A Column B

a. Watchdog circuit failure 1. Indication only

b. No neutron source 2. Indication and scram

c. 30-second period 3. Indication and interlock

d. High neutron flux NM-1000 = 1050 kW (change made during the administration of the examination)

Question C.14 [1.0 point]

Which ONE of the following facilities permits applications with short-lived radioisotopes?

a. Central thimble

b. Rotary specimen rack

c. Pneumatic specimen tube

d. Beam port 27

Section C Plant and Radiation Monitoring Systems Question C.15 [1.0 point]

Which ONE of the following best describes the design of fuel element used at NETL reactor?

a. The fuel contains more than 8.5% weight of uranium enriched to less than 20% U 235.

b. The fuel contains more than 20% weight of uranium enriched to less than 8.5% U 235.

c. The fuel contains less than 8.5% weight of uranium enriched to less than 20% U 235.

d. The fuel contains less than 20% weight of uranium enriched to more than 8.5% U 235.

Question C.16 [1.0 point]

As stated in TS 5.4, all fuel elements shall be stored in a geometrical array where the effective multiplication is less than _____ for all conditions of moderation.

a. 0.7

b. 0.75

c. 0.8

d. 0.9 Question C.17 [1.0 point]

Which ONE of the following represents the zirconium-hydride ratio for the UT TRIGA fuel elements?

a. Nominal 1.9 hydrogen to zirconium

b. Nominal 1.6 hydrogen to zirconium

c. Nominal 1.3 hydrogen to zirconium

d. Nominal 1.0 hydrogen to zirconium 28

Section C Plant and Radiation Monitoring Systems Question C.18 [1.0 point]

Which ONE of the following pressure settings in the heat exchanger helps to prevent the possible spread of contaminated water to the environment?

a. Setting up the pressure difference cannot prevent the contamination

b. The pressure of the shell outlet is higher than the pressure of the tube inlet

c. The pressure of the shell outlet is lower than the pressure of the tube inlet

d. The pressure of the shell outlet is equal to the pressure of the tube inlet Question C.19 [1.0 point]

Which ONE of the following events does NOT require the direct supervision of a SRO?

a. Relocation of an experiment of $0.95

b. Fuel movement

c. Significant power reduction

d. First core excess of the day Question C.20 [1.0 point]

During operation, you receive a message SCRAM-CSC DIS64 Timeout. This message means that communication is disrupted between:

a. DAC Network and CSC Network

b. DAC Computer and DAC Digital Scanner board

c. DAC Computer and CSC Digital Scanner board

d. CSC Computer and CSC Digital Scanner board

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

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

29

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

Reference:

P = Poet/T, time = ln(2)*35 = ~24 seconds A.3 Answer: c 2

( 2 - )2 ( 1 - )

=

Peak 2 Peak 1

=($)*; 1=$1.20*0.007= 0.0084 k/k (Peak1 /Peak2)*(0.0084-.007)2 = (1- ) 2 0.000049=(1- ) 2 ;0.007= 1- or 1=0.007+0.007= 0.014 k/k or $2.0 Or Peak2 ($1-$1) 2 = Peak1*( $2-$1 /)2

($1-$1.0) 2 = (5000/200)*( $1.20-$1.0)2

$1-$1.0 = $1.0, $1 = $2.0 A.4 Answer: a

Reference:

P = P0et/T, T = t / (ln(P/P0) = 75 / (ln(4)) = 54 seconds A.7 Answer: a

Reference:

= (Keff1-Keff2)/(Keff1*Keff2) = (0.965-0.918)/((0.965*0.918) = 0.0531k/k = 5.31%k/k 30

Section A L Theory, Thermo, and Facility Characteristics A.9 Answer: a

Reference:

Chart of Nuclides A.11 Answer: b

Reference:

Total Worth = $4.50 + $3.75 + $2.00 = $10.25 Reactivity at 15W = $3.50 + $2.00 + $1.50 = $7.00 Core Excess = Total Worth - Reactivity at 15W = $10.25 - $7.00 = $3.25 A.12 Answer: d

Reference:

Assume constant period = 1, P = P0et/T, t = T*ln(P/P0), smallest ratio of P/P0 takes the least time to complete A.15 Answer: a

Reference:

SAR Chapter 3 A.18 Answer: b

Reference:

1500) = 2550 3rd Gen = n + K*n = 2550 + (0.7

2550) = 4335 A.19 Answer: c

Reference:

P = P0et/T = 1100kW

e(0.05/0.1) = 1813 kW 31

Section A L Theory, Thermo, and Facility Characteristics A.20 Answer: b

Reference:

Section B Normal, Emergency and Radiological Control Procedures Answer Key B.1 Answer: a=4, b=3, c=2

Reference:

TS Section 1.22 B.2 Answer: c

Reference:

10 CFR 20.1003 B.3 Answer: c

Reference:

E-Plan Section 1.2 B.4 Answer: d

Reference:

Basic radiation instrumentation B.5 Answer: d

Reference:

NETL Procedure FUEL-2 B.6 Answer: d

Reference:

TS 6.2.1 B.7 Answer: b

Reference:

TS 3.2.2 B.8 Answer: d

Reference:

NETL Procedure PLAN-E B.9 Answer: a

Reference:

10 CFR 55 B.10 Answer: b

Reference:

10 CFR 20.1003 B.11 Answer: d

Reference:

Procedure PLAN-E 33

Section B Normal, Emergency and Radiological Control Procedures B.12 Answer: c

Reference:

NETL Procedure OPER-2, step B.1 B.13 Answer: c

Reference:

TS Section 3.3.3 B.14 Answer: a

Reference:

NETL Procedure OPER-2 B.15 Answer: b

Reference:

, , , = 0.00505 B.16 Answer: a

Reference:

TS Section 4.2.3 B.17 Answer: c

Reference:

NETL Procedure PLAN-E, Emergency Classification B.18 Answer: b

Reference:

NETL TS Chapter 1 B.19 Answer: b

Reference:

TS Section 1 B.20 Answer: a=4 , b=3, c=2 , d=1

Reference:

Section C Plant and Radiation Monitoring Systems Answer Key C.1 Answer: a

Reference:

SAR Section 7.4.2, page 7-27 C.2 Answer: c

Reference:

SAR Section 8.1.4, page 8-4 C.3 Answer: a

Reference:

SAR Section 7.2.1, page 7-2 C.4 Answer: b

Reference:

SAR Section 6.1.1 C.5 Answer: a

Reference:

TS 3.3.3b C.6 Answer: b

Reference:

SURV-4; SAR Section 5.2.1, page 5-6 C.7 Answer: c

Reference:

SAR Section 7.2.2, page 7-5 C.8 Answer: b

Reference:

SAR 6.1.5, page 6-13 C.9 Answer: a

Reference:

SAR Figure 5-2, page 5-8 C.10 Answer: a

Reference:

SAR Section 6.1, page 6-2 C.11 Answer: d

Reference:

SAR Section 4.4.8.3 C.12 Answer: b

Reference:

SAR Section 5.1.4, page 5-6 35

Section C Plant and Radiation Monitoring Systems C.13 Answer: a = 2, b = 3, c = 1, d = 2 1 (change made during exam)

Reference:

TS Section 3.2, SAR 6.1.4 + 6.1.5, pages 6-12 + 6-13, respectively C.14 Answer: c

Reference:

SAR Section 8.1.3, page 8-1 C.15 Answer: c

Reference:

TS 5.3 C.16 Answer: c

Reference:

TS 5.4(a)

C.17 Answer: b

Reference:

SAR Table 1-1 (page 1-2); TS 5.3.1(b)

C.18 Answer: b

Reference:

SAR Table 5-1, page 5-9 C.19 Answer: a

Reference:

TS 6.1.3 C.20 Answer: d

Reference:

MAIN-1, Section 7.1

- - - - END OF THE EXAM ********************************

36

ML13116A142

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SUBJECT:

Dear Mr. Whaley:

Enclosures:

SUBJECT:

Dear Mr. Whaley:

Enclosures:

SUMMARY

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