Text

Examination Report Letter No. 50-128/OL 22-02, Texas A&M University
	ML22193A199
Person / Time
Site:	05000128
Issue date:	07/13/2022
From:	Travis Tate; NRC/NRR/DANU/UNPO
To:	Mcdeavitt S; Texas A&M Univ
	Nguyen J, 415-4007
Shared Package
ML22041A383	List: ML22038A961; ML22193A199;
References
	50-128/22-02, HQ-OLT 50-128/OL-22-02
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July 13, 2022 Dr. Sean McDeavitt, Director Texas A&M University System Nuclear Engineering and Science Center Texas Engineering Experiment Station 1095 Nuclear Science Road, MS 3575 College Station, TX 77843

SUBJECT:

EXAMINATION REPORT NO. 50-128/OL-22-02, TEXAS ENGINEERING EXPERIMENT STATION (TEES) - NUCLEAR SCIENCE CENTER (NSC)

Dear Dr. McDeavitt:

During the week of April 18, 2022, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your Texas Engineering Experiment Station (TEES) - Nuclear Science Center (NSC) reactor. The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors,"

Revision 2. Examination questions and preliminary findings were discussed 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 internet e-mail John.Nguyen@nrc.gov.

Sincerely, Travis L. Tate, Chief Non-Power Production and Utilization Facility Oversight Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation Docket No. 50-128

Enclosures:

1. Examination Report No. 50-128/

OL-22-02

2. Written Examination cc: w/o enclosures: See next page Travis L. Tate Digitally signed by Travis L. Tate Date: 2022.07.13 17:22:24

-04'00'

SUBJECT:

EXAMINATION REPORT NO. 50-128/OL-22-02, TEXAS ENGINEERING EXPERIMENT STATION (TEES) - NUCLEAR SCIENCE CENTER (NSC)

DATED: JULY 13, 2022 DISTRIBUTION:

PUBLIC JBowen, NRR CCarusone, NRR TTate, NRR JBorromeo, NRR MGawello, NRR PBoyle, NRR CBassett, NRR RAlexander, RGN-IV ADAMS ACCESSION No.: ML22193A199 NRR-079 OFFICE NRR/DANU/UNPO NRR/DANU/UNPO NRR/DANU/UNPO NAME JNguyen ZTaru TTate DATE 05/05/2022 07/11/2022 07/13/2022 OFFICIAL RECORD COPY

Texas A&M University Docket No. 50-128 cc:

Mayor, City of College Station P.O. Box Drawer 9960 College Station, TX 77840-3575 State Energy Conservation Office Comptroller of Public Accounts P.O. Box 13528 Austin, TX 78711-3528 Governors Budget and Policy Office PO Box 12428 Austin, TX 78711-2428 Scott Miller, Reactor Operations Manager Texas A&M University Nuclear Engineering and Science Center Texas Engineering Experiment Station 1095 Nuclear Science Road, MS 3575 College Station, TX 77843 Dr. Dimitris C. Lagoudas, Deputy Director Texas A&M University Texas Engineering Experiment Station 241 Zachry Engineering Center College Station, TX 77843 Radiation Program Officer Bureau of Radiation Control Department of State Health Services Division for Regulatory Services 1100 West 49th Street, MC 2828 Austin, TX 78756-3189 Ashley Forbes, Director Radiation Materials Division, MC 233 Texas Commission on Environmental Quality P.O. Box 13087 Austin, TX 78711-3087 Test, Research and Training Reactor Newsletter Attention: Ms. Amber Johnson Dept of Materials Science and Engineering University of Maryland 4418 Stadium Drive College Park, MD 20742-2115

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

50-128/OL-22-02 FACILITY DOCKET NO.:

50-128 FACILITY LICENSE NO.:

R-120 FACILITY:

Texas Engineering Experiment Station (TEES) - Nuclear Science Center (NSC)

EXAMINATION DATES:

April 18-22, 2022 SUBMITTED BY:

John Nguyen 05/05/2022 John T. Nguyen, Chief Examiner Date

SUMMARY

During the week of April 18, 2022, the NRC administered operator licensing examinations to three Reactor Operator (RO), three Senior Reactor Operator - Instant (SRO-I), and two Senior Reactor Operator - Upgrade (SRO-U) candidates. One SRO-I candidate failed the written exam; all other candidates passed all applicable portions of the examinations.

REPORT DETAILS

1.

Examiner:

John T. Nguyen, Chief Examiner, NRC

2.

Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 3/0 2/1 5/1 Operating Tests 3/0 5/0 8/0 Overall 3/0 4/1 7/1

3.

Exit Meeting:

Sean McDeavitt, Director, TEES-NSC Jere Jenkin, Assistant Director, TEES-NSC Scott Miller, Reactor Supervisor, TEES-NSC Dan Hoang, Reactor Engineer, NRC John T. Nguyen, Chief Examiner, NRC Facility comments were accepted prior to the administration of the written examination.

At the conclusion of the meeting, the NRC examiner thanked the facility for their support in the administration of the examinations. The examiner discussed the candidates weaknesses observed during the operating tests to include modifications to procedures and equipment, responses to tornado, nuclear instrumentation, and radiation sources and hazards.

ENCLOSURE 2 TEXAS A&M UNIVERSITY Operator Licensing Examination Week of April 18, 2022

U.S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:

Texas A&M University reactor REACTOR TYPE:

TRIGA DATE ADMINISTERED:

04/20/2022 CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the Answer sheet provided. Attach all Answer sheets to the examination. Point values are indicated in parentheses for each question. A 70% in each category is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 20.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL COGE NTROLS 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

Category A - Reactor Theory, Thermodynamics, & Facility Operating Characteristics A N S W E R S H E E T Multiple Choice (Circle or X your choice)

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

A01 a ______

b ______

c ______

d ______ (0.25 each)

A02 a b c d ___

A03 a b c d ___

A04 a b c d ___

A05 a b c d ___

A06 a b c d ___

A07 a b c d ___

A08 a b c d ___

A09 a b c d ___

A10 a b c d ___

A11 a ______

b ______

c ______

d ______ (0.25 each)

A12 a b c d ___

A13 a b c d ___

A14 a b c d ___

A15 a b c d ___

A16 a b c d ___

A17 a b c d ___

A18 a b c d ___

A19 a b c d ___

A20 a b c d ___

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

Category B - Normal/Emergency Operating Procedures and Radiological Controls A N S W E R S H E E T Multiple Choice (Circle or X your choice)

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

B01 a b c d ___

B02 a b c d ___

B03 a b c d ___

B04 a b c d ___

B05 a b c d ___

B06 a ______

b ______

c ______

d ______ (0.25 each)

B07 a b c d ___

B08 a b c d ___

B09 a b c d ___

B10 a b c d ___

B11 a b c d ___

B12 a b c d ___

B13 a b c d ___

B14 a ______

b ______

c ______

d ______ (0.25 each)

B15 a b c d ___

B16 a b c d ___

B17 a b c d ___

B18 a b c d ___

B19 a b c d ___

B20 a b c d ___

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

C. PLANT AND RAD MONITORING SYSTEMS A N S W E R S H E E T Multiple Choice (Circle or X your choice)

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

C01 a b c d ___

C02 a b c d ___

C03 a b c d ___

C04 a b c d ___

C05 a b c d ___

C06 a b c d ___

C07 a b c d ___

C08 a b c d ___

C09 a b c d ___

C10 a b c d ___

C11 a b c d ___

C12 a b c d ___

C13 a b c d ___

C14 a b c d ___

C15 a b c d ___

C16 a b c d ___

C17 a b c d ___

C18 a b c d ___

C19 a b c d ___

C20 a b c d ___

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

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

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

1.

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

2.

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

3.

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

4.

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

5.

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

6.

Mark your Answers on the Answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.

7.

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

8.

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

9.

When turning in your examination, assemble the completed examination with examination questions, examination aids and Answer sheets. In addition turn in all scrap paper.

10.

Ensure all information you wish to have evaluated as part of your Answer is on your Answer sheet. Scrap paper will be disposed of immediately following the examination.

11.

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

12.

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

EQUATION SHEET

=

+

DR - Rem, Ci - curies, E - Mev, R - feet 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lb 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 1 BTU = 778 ft-lb

°F = 9/5 °C + 32 1 gal (H2O) 8 lb

°C = 5/9 (°F - 32) cP = 1.0 BTU/hr/lb/°F cp = 1 cal/sec/gm/°C

(

)

(

)

2 2

max

=

P 1

sec 1.0

=

eff

=

te P

P 0

eff K

S S

SCR

=

1

sec 10 1

4

x

=

+

=

eff SUR 06 26

(

)

(

)

2 1

1 1

2 1

eff eff K

CR K

CR

=

(

)

(

)

2 2

1 1

=

CR CR 2

1 1

1 eff eff K

K M

=

1 2

1 1

CR CR K

M eff

=

)

(

0 10 t

SUR P

P =

(

)

0 1

P P

=

eff eff K

K SDM

=1

=

2 1

1 2

eff eff eff eff K

K K

K

=

693

.0 2

1 =

T eff eff K

K 1

=

t e

DR DR

=

0

( )

2 6

R n

E Ci DR =

2 2

1 1

d DR d

DR

=

(

)

(

)

1 2

2 2

Peak Peak

=

T UA H

m T

c m

Q P

=

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.01

[1.0 point, 0.25 each]

Match the term listed in Column A with its corresponding unit listed in column B.

Column A Column B

a.

1 barn

1. cm -1

b.

Macroscopic Cross Section

2. 10 -24 cm 2

c.

Neutron Flux

3. Neutrons / cm 2 /sec

d.

Delay neutron fraction

4.

QUESTION A.02

[1.0 point]

For the alpha decay of a nuclide, the number of protons will ___________ and its atomic mass number will __________.

a.

increase by 2 / increase by 2

b.

decrease by 2 /decrease by 4

c.

decrease by 4 / decrease by 2

d.

increase by 4 / increase by 2 QUESTION A.03

[1.0 point]

An experiment has been wrapped in cadmium to be placed in the reactor core. Which one of the following types of radiation will be most effectively blocked by the cadmium wrapping?

a.

Thermal neutrons

b.

Fast neutrons

c.

Gamma rays

d.

X-rays

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.04

[1.0 points]

Which ONE of the following is the stable reactor period which will result in a power rise from 1%

to 100% power in 2 minutes?

a.

0.5 second

b.

13 seconds

c.

26 seconds

d.

43 seconds QUESTION A.05

[1.0 point]

A reactor contains three safety rods and a regulating rod. Which ONE of the following would result in a determination of the excess reactivity of this reactor?

a.

The reactor is critical at a low power level, with all safety rods full out and the regulating rod at some position. The reactivity remaining in the regulating rod (i.e. its rod worth from its present position to full out) is the excess reactivity.

b.

The reactor is shutdown. Two safety rods are withdrawn until the reactor becomes critical. The total rod worth withdrawn is the excess reactivity.

c.

The reactor is at full power. The total worth of all rods withdrawn is the excess reactivity.

d.

The reactor is at full power. The total worth remaining in all the safety rods and the control rod (i.e. their worth from their present positions to full out) is the excess reactivity.

QUESTION A.06

[1.0 point]

The reactor is SHUTDOWN by 5 %k/k with the count rate of 1000 counts per second (cps).

The control rods are withdrawn until the count rate is quadrupled. What is the value of Keff?

a.

0.952

b.

0.976

c.

0.988

d.

1.002

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.07 [1.0 point]

The reactor is on a constant period, which ONE of the following changes in reactor power would take the LONGEST time?

a.

5% from 1% to 6%

b.

15% from 20% to 35%

c.

20% from 40% to 60%

d.

25% from 75% to 100%

QUESTION A.08

[1.0 point]

While a reactor is critical at 5 watts, the reactor operator is withdrawing a control rod to insert a positive reactivity of 0.156 %k/k. Which ONE of the following will be the stable reactor period as a result of this withdrawal? Given beta-effective = 0.0073 and eff= 0.1.

a.

17 seconds

b.

27 seconds

c.

37 seconds

d.

47 seconds QUESTION A.09

[1.0 point]

Inelastic scattering can be described as a process whereby a neutron collides with a nucleus and leaves the nucleus in an excited state. The nucleus later:

a.

emits a gamma ray and a neutron with lower energy.

b.

emits a beta particle and a neutron with lower energy.

c.

emits a neutron and a gamma ray of 1.04 Mev.

d.

emits an alpha particle ONLY.

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.10

[1.0 point]

A reactor is subcritical with a Keff of 0.927. If you add 7.875% k/k into the core, the reactor will be:

a.

subcritical

b.

critical

c.

supercritical

d.

prompt critical

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.11 [1.0 point]

Identify the descriptions and/or graphs in Column A whether it is integral rod worth (1) or differential control rod worth (2).

Column A

a. Total reactivity worth of the control rod at that height

b. Reactivity change per unit movement of a control rod

c. See curve below

d. See curve below

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.12

[1.0 point]

The following data was obtained during a reactor fuel load.

Step No. of Elements Detector A (count/sec) 1 0

100 2

4 120 3

8 140 4

12 200 5

15 400 The estimated number of additional elements required to achieve criticality is between:

a.

2 to 3

b.

4 to 5

c.

6 to 8

d.

8 to 10 QUESTION A.13

[1.0 point]

Which term is described by the following?

The increase in neutron population by providing a positive additional reactivity while the reactor is subcritical

a.

Inverse Multiplication

b.

Subcritical Multiplication

c.

Neutron Production

d.

Source Strength

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.14

[1.0 point]

Given a source strength of 1000 neutrons per second (N/sec) and a multiplication factor of 0.8, which ONE of the following is the expected stable neutron count rate?

a.

700 N/sec

b.

5000 N/sec

c.

10000 N/sec

d.

20000 N/sec QUESTION A.15

[1.0 point]

Several processes occur that may increase or decrease the available number of neutrons.

Which ONE of the following six-factor formula describes an INCREASE of the number of neutrons during the cycle?

a.

Reproduction factor.

b.

Thermal utilization factor.

c.

Resonance escape probability.

d.

Thermal non-leakage probability.

QUESTION A.16

[1.0 point]

Which ONE of the following types of neutrons has a mean neutron generation time of 12.5 seconds?

a.

Prompt

b.

Delayed

c.

Fast

d.

Thermal

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.17

[1.0 point]

During a startup, you increase reactor power from 50 watts to 1000 watts in 100 seconds. What is reactor period?

a.

25

b.

33

c.

41

d.

50 QUESTION A.18

[1.0 point]

A fissile material is one that will fission upon absorption of a THERMAL neutron. A fertile material is one which upon absorption of a neutron becomes a fissile material. Which ONE of the following isotopes is an example of a fertile material?

a.

U233

b.

U235

c.

U238

d.

Pu239 QUESTION A.19

[1.0 point]

Which ONE of the following describes the MAXIMUM amount of Xenon in the core?

a.

8 to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months following Power startup to 100%.

b.

4 to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following Power Increase, 50% to 100%.

c.

4 to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following Power Decrease, 100% to 50%.

d.

8 to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months following Power shutdown from 100%.

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.20

[1.0 point]

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

a.

Delayed neutrons are born at higher energy levels than prompt neutrons, so delayed neutron can easily cause fission in U-235 with their high energies.

b.

Delayed neutrons increase the average neutron lifetime that allows the reactor control rods to control the population of delayed neutrons.

c.

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

d.

The absorption cross section of delayed neutrons is lower than the absorption cross section of prompt neutrons with U-235.

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

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.01

[1.0 point]

Per NSCR SOP, Procedure I, what is the MAXIMUM fuel bundles to be allowed in the reactor core if only three scrammable control rods are operable during a fuel loading?

a.

6

b.

9

c.

12

d.

15 QUESTION B.02

[1.0 point]

Reactor Operator works in a high radiation area for eight (8) hours a day. The dose rate in the area is 80 mR/hour. Which ONE of the following is the MAXIMUM number of days in which Reactor Operator may perform his/her duties WITHOUT exceeding 10 CFR 20 limits?

a.

5 days

b.

6 days

c.

7 days

d.

8 days QUESTION B.03

[1.0 point]

You receive a quarterly dosimetry report stating that you have received whole body occupational exposures of:

1 mrad of beta 1 mrad of alphas 1 mrad of neutrons of unknown energy What would be the total effective dose equivalent?

a.

3 mrem

b.

12 mrem

c.

22 mrem

d.

31 mrem

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.04

[1.0 point]

Per NSCR Technical Specifications, which ONE of the following experiments shall NOT be irradiated in the reactor core?

a.

Absolute value of reactivity worth for non-secured experiment exceeds $1.00.

b.

Reactivity worth of secured experiment exceeds $1.50.

c.

Any explosive materials.

d.

Any corrosive materials.

QUESTION B.05

[1.0 point]

A radioactive source reads 5 Rem/hr on contact. Five hours later, the same source reads 1.25 Rem/hr. How long is the time for the source to decay from a reading of 5 Rem/hr to 625 mRem/hr?

a.

6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months

b.

7.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months

c.

8.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months

d.

9.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months QUESTION B.06

[1.0 point, 0.25 each]

Match the events listed in column A with its emergency classification listed in column B. Values in Column B can be used once, more than once or not at all.

Column A Column B

a.

Exceeding effluent product activity due to a loss of building electricity

1. Unusual Event

b.

Significant releases of radioactive materials

2. Alert as a result of experiment failures.

c.

Hurricane causing damage to the reactor building

3. Site Area Emergency and reactor pool (without pool leak).

d.

Receipt of a bomb threat directly to the reactor facility.

4. General Emergency

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.07

[1.0 point]

Which ONE of the following is NOT a guidance/recommendation when planning for occupational exposure under emergency conditions for Life Saving Actions?

a.

The exposure limit is authorized with preference given to the eldest able-bodied volunteer.

b.

The exposure limit can exceed up to 25 Rem whole body for life saving.

c.

Persons receiving exposures can receive multiple times in a future until exceeding 25 Rem TEDE.

d.

Persons receiving exposures shall receive medical attention as soon as possible after their exposure.

QUESTION B.08

[1.0 point]

An annual test of the nuclear instrument was performed. Which ONE of the following is the latest the test that must be performed again without violation of the Technical Specifications?

a.

Not to exceed 13 months

b.

Not to exceed 14 months

c.

Not to exceed 15 months

d.

Not to exceed 16 months QUESTION B.09

[1.0 point]

A radioactive material is decayed 35% after one hour. Determine its half-life?

a.

1.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

b.

3.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months

c.

4.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

d.

5.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.10

[1.0 point]

A system or component is defined as "OPERABLE" by NSCR Technical Specifications when:

a.

a system is operational when reactor is in the unsecured condition.

b.

a system is operational when reactor is in the shutdown condition.

c.

operating whenever it is not unsecured or shutdown.

d.

it is capable of performing its intended function.

QUESTION B.11

[1.0 point]

Per NSCR Technical Specifications, the MAXIMUM scram time for operable scrammable control rods shall NOT exceed ______.

a.

1.0 seconds

b.

1.2 seconds

c.

1.4 seconds

d.

1.6 seconds QUESTION B.12

[1.0 point]

A two-curie source emits 80% of a 500 K-ev gamma. What is the dose rate at 10 feet?

a.

48 mR/hr

b.

4.8 R/hr

c.

84 mR/hr

d.

8.4 R/hr

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.13

[1.0 point]

Per NESC Emergency Plan, the area for which off-site emergency planning is performed to assure that prompt and effective actions can be taken to protect the public in the event of an accident is called ___________.

a.

Controlled Access Area

b.

Operations Boundary

c.

Unescorted Area

d.

Emergency Planning Zone QUESTION B.14

[1.0 point, 0.25 each]

Choose the correct value for each of the NSCR Technical Specification Limits.

Column A

a.

Preset timer __________ seconds (10/15/20)

b.

Pool water temperature ________ °C. (50/55/60)

c.

Excess reactivity _________ %k/k (4.5/5.5/6.5)

d.

Transverse bend for a fuel inspection ______ inch (0.0625/0.125/1.125)

QUESTION B.15

[1.0 point]

The permissible annual occupational dose limit for radiation workers for total effective dose equivalent (TEDE) is:

a.

50 rems

b.

15 rems

c.

5 rems

d.

1 rem

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.16

[1.0 point]

The central exhaust system shall be considered operating when it creates a minimum of _____

of water negative pressure at the sample point in the central exhaust system duck work.

a.

0.1 inch

b.

1.0 inch

c.

0.5 inch

d.

5 inch QUESTION B.17

[1.0 point]

The below items are listed as a reportable occurrence, EXCEPT:

a.

Fuel cladding failure.

b.

An uncontrolled reactivity change of 0.6 %K/K.

c.

Reactor power exceeds 1.2 MW during steady state operation.

d.

Performance of Reactor operation without a completion of the startup checklist.

QUESTION B.18

[1.0 point]

The principal barrier to be used for specification of the safety limit is the:

a.

Reactor fuel temperature.

b.

Reactor thermal power.

c.

Bulk pool temperature.

d.

Coolant height.

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.19

[1.0 point]

Which ONE of the following changes must be submitted to NRC for approval prior to implementation?

a.

Replace a primary cooling pump with an identical pump.

b.

Add new limitation to the Pre-Startup Checklist Procedure.

c.

Add more responsibilities to the Radiation Protection Officer listed in the health physics procedure.

d.

Remove a definition of Channel Test listed in the NSCR Technical Specifications.

QUESTION B.20

[1.0 point]

The Annual Limit on Intake (ALI) is defined as:

a.

The concentration of a given radionuclide in air for which if its concentration breathed by an adult worker for a year, would result in a committed effective dose equivalent of 15 rems.

b.

The concentration of a given radionuclide in air which, if breathed by an adult worker for a year, would result in a committed effective dose equivalent of 5 rems.

c.

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

d.

The derived limit for the amount of radioactive material taken into the body of an adult worker by inhalation or ingestion in a year that would result in a committed effective dose equivalent of 5 rem whole body or 50 rem to any individual organ or tissue.

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

Category C: Facility and Radiation Monitoring Systems QUESTION C.01

[1.0 point]

Which one of the following describes a TRIGA LEU 30/20 fuel?

Cladding Hydrogen-to-zirconium atom ratio

a.

304 Stainless steel 1.6 H/1.0 Zr

b.

Zircaloy 1.6 H/1.0 Zr

c.

Erbium 1.0 H/1.6 Zr

d.

304 Stainless steel 1.0 H/1.6 Zr QUESTION C.02

[1.0 point]

Which ONE of the following will prevent rod insertion for a jammed rod?

a.

Magnet power

b.

Automatic power control

c.

Control rod interlock

d.

Carriage height position is fully up (100%)

Category C: Facility and Radiation Monitoring Systems QUESTION C.03

[1.0 point]

The following block diagram depicts:

a.

Wide Range Linear Channel

b.

Safety Power Channel

c.

Log Power Channel

d.

Pulse Channel QUESTION C.04

[1.0 point]

Which ONE of the following is the method use to get rid of radioactive low-level liquid waste at NSCR reactor? Radioactive low-level liquid waste is:

a.

immediately discharged to the sanitary sewer system.

b.

freed, then transferred to the Department of Energy.

c.

transferred by a sump pump to one of three storage tanks.

d.

transferred by a sump pump to the reactor primary coolant cleanup system.

Category C: Facility and Radiation Monitoring Systems QUESTION C.05

[1.0 point]

Which ONE of the following conditions will cause a reactor scram during reactor operations?

a.

Log Power channel is less than 2 cps.

b.

Initiate a pulse when the steady state power is at 2 kW.

c.

Conductivity of the bulk Water is higher than 5 X 107 ohms/cm.

d.

Failure of a power supply of the Safety channel during a steady state power of 5 W.

QUESTION C.06

[1.0 point]

What channel prevents pulsing when its power is above 1 kW?

a.

Wide Range Linear Channel

b.

Safety Power Channel

c.

Log Power Channel

d.

Pulse Channel QUESTION C.07

[1.0 point]

Which ONE of the following is the system design that mitigates most of the N-16 production at the NSCR reactor?

a.

Core diffuser system

b.

Pneumatic transfer system

c.

Secondary coolant system

d.

Demineralizer/recirculation system

Category C: Facility and Radiation Monitoring Systems QUESTION C.08

[1.0 point]

Which ONE of the following protective channels does NOT provide a scram function during the steady state mode?

a.

Wide Range Linear Channel

b.

Safety Power Channel

c.

Log Power Channel

d.

Fuel Temperature Channel QUESTION C.09

[1.0 point]

The following block diagram depicts:

a.

Regulating control rod

b.

Shim/Safety control rod

c.

TRIGA LEU 30/20 Fuel element

d.

Instrumented fuel element

Category C: Facility and Radiation Monitoring Systems QUESTION C.10

[1.0 point]

Per NSCR Technical Specifications, the central exhaust system shall be operable during the certain reactor operations. Which ONE of the following is NOT required for its operations?

Note: Assume that the central exhaust system is NOT in the maintenance mode.

a.

Reactor is at 5 watts.

b.

Movement of irradiated fuel elements or fuel bundles.

c.

Change in reactivity of $0.80 during a maintenance of control rod work.

d.

Handling of radioactive materials with the potential for airborne release.

Category C: Facility and Radiation Monitoring Systems QUESTION C.11

[1.0 point]

In the following diagram of the control rod drive mechanism for Shim/Safety control rods, identify the location of the upper limit stop.

a.

I

b.

II

c.

III

d.

IV

Category C: Facility and Radiation Monitoring Systems QUESTION C.12

[1.0 point]

What is the startup neutron source use at the NSCR TRIGA reactor?

a.

Antinmony-Beryllium (SbBe)

b.

Plutonium-Beryllium (PuBe)

c.

Polonium-Beryllium (PoBe)

d.

Americium-Beryllium (AmBe)

QUESTION C.13

[1.0 point]

Which ONE of the following will indicate the cleanest pool water?

a.

Highest pH

b.

Lowest pH

c.

Highest conductivity

d.

Highest resistivity QUESTION C.14

[1.0 point]

Which ONE of the following is the Main purpose for setting a conductivity limit of the pool water?

a.

Maintain the departure of nucleate boiling ratio (DNBR) greater than the unity.

b.

Minimize the possibility of corrosion on the fuel cladding.

c.

Extend integrity of resin bed on the demineralizer.

d.

Minimize Ar-41 released to the public.

Category C: Facility and Radiation Monitoring Systems QUESTION C.15

[1.0 point]

After firing a pulse, the Pulse Channel provides the indications of:

a.

Energy and fuel temperature

b.

Energy and Percent Power

c.

Peak Power and reactor period

d.

Peak Power and fuel temperature QUESTION C.16

[1.0 point]

The reactor control, display, and record systems allow operators to monitor and control operations on the reactor console. Which ONE of the following systems does NOT record its data during a reactor operation of 1 MW power?

a.

Fuel temperature

b.

Facility air monitor

c.

Pool temperature

d.

Area radiation monitor QUESTION C.17

[1.0 point]

The main purpose of the neutron source in the reactor core is to :

a.

Prevent the reactor changing from manual to automatic if the period exceeds 5 seconds.

b.

Enable the reactor to go from subcritical to critical without moving Shim/Safety control rods.

c.

Provide sufficient neutron population to ensure proper nuclear instrumentation response during initial startup.

d.

Provide sufficient neutron population to ensure proper 1/M calculation during fuel loading.

Category C: Facility and Radiation Monitoring Systems QUESTION C.18

[1.0 point]

Which of the following statements best describes the operation of the Compensated Ion Chamber (CIC) and the uncompensated Ion Chamber (UIC)?

a.

The CIC has two chambers: one is coated with U-235 for fission reaction and the other is coated with B-10 for (n,) reaction, whereas the UIC has only one chamber coated with U-235 for fission reaction.

b.

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

c.

The CIC has two chambers: both can sense gamma rays but only one is coated with B-10 for (n,) reaction, whereas the UIC has only one chamber coated with B-10 for (n,)

reaction.

d.

The CIC has only one chamber coated with U-235 for fission reaction, whereas the UIC has two chambers: both can sense gamma rays but only one is coated with B-10 for (n,) reaction.

QUESTION C.19

[1.0 point]

What is the maximum acceptable time between the initiation of a scram signal and the time that the SHIM rod is fully inserted in the core?

a.

2.4 sec

b.

2.1 sec

c.

1.2 sec

d.

1.0 sec

Category C: Facility and Radiation Monitoring Systems QUESTION C.20

[1.0 point]

Which ONE of the following is NOT a method of controlling radiation levels at the NSCR reactor?

a.

Maintaining the NSCR reactor building at a negative differential pressure such that effluent release is through the ventilation stack.

b.

Purging the pneumatic transfer system with CO2 when not in use.

c.

Collecting the facility liquid effluents in the holdup tanks.

d.

Using the diffuser system to control N-16 release.

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

((***** END OF EXAM *****))

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.01 Answer:

Reactivity added = 0.156 %k/k = 0.00156 k/k

= (-)/eff = (0.0073 - 0.00156)/ ((0.1)*(0.00156))

= 37 seconds A.09 Answer:

a

Reference:

29.

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.10 Answer:

b

Reference:

SDM = (1-keff)/keff = (1-0.927)/0.927 = 0.07875 k/k. So if you add the same amount of SDM, the reactor is critical.

Another method: you can find the new value of Keff when adding 0.07875 k/k to reactor.

p = (k2 -k1)/ k1*k2 0.07875 = (k2- 0.927)/(0.927* k2), solve for k2 K2 = 1, hence the reactor is critical A.11 Answer:

a 1 b 2 c 1 d 2 (0.25 each)

Reference:

a

Reference:

b

Reference:

b

Reference:

CR = S/(1-K) CR = 1000/(1 - 0.8) = 5000 N/sec A.15 Answer:

a

Reference:

b

Reference:

DOE Handbook Vol. 1 Module 2, Section 3.0 A.17 Answer:

b

Reference:

P = P0 et/ ln(P/P0) = t/ = t/(ln(P/P0) = 100/ln(20) = 33.381 A.18 Answer:

c

Reference:

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.19 Answer:

d

DR = DR*e -t 1.25 rem/hr =5 rem/hr* e -(5hr)

Ln(1.25/5) = -*5 --> =0.277; solve for t: Ln(.625/5)=-0.277 *t t=7.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months B.06 Answer:

a(1) b(2) c(1) d(1)

(0.25 each)

NSCR TS 3.2.3 B.12 Answer:

a

Reference:

6CEN = R/hr @ 1 ft. -> 6 x 2 x 0.8 x 0.5 = 4.8 R/hr at 1ft.

l2 = l1D12/d22 l2 = (4.8 R/hr)(1 ft)2 / (10 ft)2 l2 = 4800 mR/hr/100 = 48 mR/hr B.13 Answer:

d

Reference:

NESC EP 2.0 B.14 Answer:

a (15) b (60) c (5.5) d (0.125)

(0.25 each)

Reference:

NSCR TS 3.1 & TS 3.2 B.15 Answer:

NSCR TS 3.3.2

Category C: Facility and Radiation Monitoring Systems C.11 Answer:

b

Reference:

NSCR SAR, Figure 7-8 C.12 Answer:

a

Reference:

NSCR SAR 4.2.4 C.13 Answer:

d

Reference:

NRC Standard Question C.14 Answer:

b

NSCR SAR 11 and TS 3.7

ML22193A199

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