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Examination Report Letter No. 50-128/OL-21-01, Texas A&M University
	ML21176A114
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Site:	05000128
Issue date:	06/25/2021
From:	Travis Tate; NRC/NRR/DANU/UNPO
To:	Mcdeavitt S; Texas A&M Univ
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ML21039A525	List: ML21039A530; ML21176A113; ML21176A114;
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June 25, 2021 Dr. Sean Mc Deavitt, Director Nuclear Science Center 1095 Nuclear Science Road, MS#3575 College Station, TX 77843-3575

SUBJECT:

EXAMINATION REPORT NO. 50-128/OL-21-01, TEXAS A&M UNIVERSITY

Dear Dr. McDeavitt:

During the week of April 5, 2021, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at the Texas A&M University Nuclear Science Center 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 you and 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. If you have any questions regarding the examination, please contact Michele DeSouza at (301) 415-0747 or Michele.DeSouza@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-21-01

2. Facility Comment on the Written Exam with NRC Resolution

3. Written Examination cc (w/o enclosures): See next page Travis L. Tate Digitally signed by Travis L. Tate Date: 2021.06.25 16:18:01 -04'00'

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

Mayor, City of College Station P.O. Box Drawer 9960 College Station, TX 77840-3575 Governors Budget and Policy Office PO Box 12428 Austin, Texas 78711-2428 Dr. Dimitris C. Lagoudas, Deputy Director Texas A&M University Texas Engineering Experiment Station 241 Zachry Engineering Center College Station, Texas 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 8756-3189 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 Scott Miller Interim Reactor Operations Manager Texas A&M University Texas Engineering Experiment Station 1095 Nuclear Science Road, MS 3575 College Station, TX 77843 State Energy Conservation Office Comptroller of Public Accounts P.O. Box 13528 Austin, TX 78711-3528

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

50-128/OL-21-01 FACILITY DOCKET NO.:

50-128 FACILITY LICENSE NO.:

R-83 FACILITY:

Texas A&M University NSC EXAMINATION DATES:

April 6-7, 2021 SUBMITTED BY:

Michele C DeSouza 4/29/2021 Michele C DeSouza, Chief Examiner Date

SUMMARY

During the week of April 5, the NRC administered operator licensing examinations to six Reactor Operator (RO) candidates; three new RO candidates and three retake RO candidates (two Category C and one Category A, B and C). Three new candidates failed all or portions of the written examination and one retake RO candidate failed portions of the written examination.

Two retake RO candidates passed the written examination.

REPORT DETAILS

1.

Examiners:

Michele C DeSouza, Chief Examiner, NRC

2.

Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 2/4 N/A 2/4 Operating Tests 3/0 N/A 3/0 Overall 2/4 N/A 2/4

3.

Exit Meeting:

Michele C DeSouza, Chief Examiner, NRC Jere Jenkins, Associate Director Texas A&M NSC Scott Miller, Reactor Operations Manager, Texas A&M NSC Rebecca Hernandez, Reactor Supervisor, Texas A&M NSC Prior to administration of the written examination, based on facility comments, adjustments were accepted. Comments provided corrections and additional clarity to questions/answers and identified where changes were appropriate based on current facility conditions. Two facility comments noted during grading is discussed in Enclosure 2. The facility inspector was informed regarding a recommendation to open an Inspector Follow Up Item (IFI). The examiner noted a lack of calibration documentation for area radiation monitors and facility air monitors as required by facility technical specifications and regulatory requirements in 10 CFR Part 20.

Upon completion of all operator licensing examinations, the NRC examiner met with facility staff representatives to discuss the results. At the conclusion of the meeting, the NRC examiner thanked the facility for their support in the administration of the examination.

ENCLOSURE 2 FACILITY COMMENTS ON THE WRITTEN EXAM WITH NRC RESOLUTION QUESTION C.01

[1.0 point]

If the reactor is to be operated at 400 kW, what is the required Reactor Bridge ARM alert setpoint?

a. 5 mR/hr

b. 6 mR/hr

c. 8 mR/hr

d. 10 mR/hr C.01 Answer:

c

Reference:

TEES NSC SOP Section II, Procedure C Facility Comment & Recommendation: This question is based on NSC-SOP Section II Procedure C, Rev. 5 per the Facility Review copy of the exam. When the reference materials were sent to the NRC with the examination request, a copy of the older Revision 5 of Procedure C was sent instead of the correct revision, Revision 6. The answer using Revision 5 would have been 8 mR/hr, which is how the exam is written. The correct answer using Revision 6, which is the currently active version and the one that the candidates have been using for study, is 14 mR/hr. Therefore, it is reasonable and appropriate to exclude this question. The Facility will ensure that the correct versions of the necessary reference documents are included in the materials sent for future exams. For reference, the relevant page from Revision 5 and Revision 6 of Procedure C have been included as Enclosures 1 and 2 to this letter, respectively.

The correct answer for this should be 14 mR/hr, which was not one of the given choices. The Facility recommends that this question be deleted, since there is no answer that matches the actual required value of 14 mR/hr.

NRC Resolution: The NRC agrees with the facility comment and recommendation, this question is deleted.

QUESTION C.07

[1.0 point]

What actions are required if the bulk pool conductivity is above 5 x 10 -6 mhos/cm?

a. No actions are necessary

b. Make a note in the main logbook only

c. Change the demineralizer resin out

d. Add chlorine to the pool until the level is greater than 5 µS/cm C.07 Answer:

c

Reference:

TEES NSC Technical Specification 3.8.1 Facility Comment & Recommendation: The specific text of the LCO in TS 3.8.1 reads, The reactor shall not be operated for a period exceeding two weeks if the two week averaged conductivity of the bulk pool water is higher than 5 x 10-6 mhos/cm. A copy of this page from the Technical Specifications is included as Enclosure 3 to this letter. The LCO prohibits operation of the reactor if the two-week averaged value of the conductivity of the bulk pool water is above that value; however, it lists no specific action to be taken. Therefore, it is reasonable and appropriate to exclude this question. This question is based on Technical Specification 3.8.1, which is a Limiting Condition for Operation (LCO). There are no associated actions listed in TS 3.8.1, so the test question isnt applicable. The Facility recommends that this question be deleted.

NRC Resolution: NRC does not accept deletion of this question and it remains. While the reference identifies the Technical Specification, this is a general knowledge question and stands as written.

ENCLOSURE 3 Texas A&M University Operator Licensing Examination Week of April 5, 2021

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

TXA&M REACTOR TYPE:

TRIGA DATE ADMINISTERED:

04/05/2021 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 CONTROLS 19.00 20.00 33.3 C. FACILITY AND RADIATION MONITORING SYSTEMS 59.00 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 ___

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 ___ (0.25 each)

A11 a b c d ___

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 ___

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 ______ (0.25 each)

B14 a b c d ___

B15 a ___ b ___ c ___ d ___ (0.25 each)

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 *****)

Category C: Facility and Radiation 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 ___ QUESTION DELETED 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 ___ (2 points, 0.5 each)

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 ___

(***** 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 = DR0 e-x 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]

Which ONE of the following is a correct statement describing prompt and delayed neutrons?

a. Are released when U-238 interacts with fast neutrons, while delayed neutrons are released when U-235 interacts with thermal neutrons

b. Account for less than 1% of the neutron population, while delayed neutrons account for the rest

c. Are released during the fission process, while delayed neutrons are released during the decay process

d. Are the dominating factor in determining reactor period, while delayed neutrons have no effect on reactor period QUESTION A.02

[1.0 point]

Which ONE of the following conditions will increase the Negative Temperature Coefficient in the reactor?

a. Doppler broadening effect

b. Increased density of pool water

c. Increased density of U-235 in the fuel element

d. Sudden burn-up of Xenon in the fuel element QUESTION A.03

[1.0 point]

You are conducting a reactor startup after installing 2 new fuel assemblies in the core. Given the following rod withdrawal data, estimate the rod position when criticality would occur. The initial count rate on the nuclear instrumentation prior to rod withdrawal is 55 cps.

a. 13 in

b. 15 in

c. 17 in

d. 19 in Rod Withdrawal (Inches)

Count Rate (cps) 0 55 2

58 4

60 6

61 8

69 10 78 12 137

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

[1.0 point]

Which type of neutron interaction (light nuclei) is most important in MODERATING fast neutrons to thermal neutrons?

a. Fission

b. Elastic Scattering

c. Inelastic Scattering

d. Neutron Capture QUESTION A.05

[1.0 point]

What is the reactivity (k/k) needed to bring the reactor to criticality when the Keff for the reactor is 0.955?

a. +0.0471

b. +0.0450

c. -0.0471

d. -0.0450 QUESTION A.06

[1.0 point]

Which of the following physical characteristics of the TRIGA fuel accounts for the majority of the negative temperature feedback?

a. Thermal expansion of the fuel matrix

b. Geometric buckling

c. Doppler broadening

d. Hardening of the neutron spectrum cased by heating the U-ZrH fuel QUESTION A.07

[1.0 point]

Which ONE of the following changes does not require a movement of control rods in order to maintain constant reactor power?

a. Nitrogen-16 formation

b. Xenon-135 buildup

c. Uranium-235 burnup

d. Pool water temperature decrease

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.08

[1.0 point]

Which ONE of the following provides the number of protons, neutrons and electrons in the Uranium-235 nucleus, 92U235?

a. 92, 92, 143

b. 92, 143, 92

c. 143, 143, 92

d. 143, 92, 143 QUESTION A.09

[1.0 point]

What is the meaning of any point on a differential rod worth curve?

a. The negative reactivity added as the rod is inserted

b. The cumulative area under the differential curve starting from the bottom of the core

c. The zero reactivity when the rod is on the bottom and the positive reactivity being added as the rod is withdrawn

d. The amount of reactivity that one unit (i.e. one inch, one percent) of rod motion would insert at that position in the core QUESTION A.10

[1.0 point, 0.25 each]

Replace X with the type of primary decay necessary (Alpha, Positron, Gamma or Neutron emission) to produce the following reactions. Choices may be used once, more than once, or not at all.

a.

92U238 90Th234 + X

b.

83Bi203 82Pb203 + X

c.

2He4 + 4Be9 6C12 + X

d.

84Po210 82Pb206 + X QUESTION A.11 [1.0 point]

Which ONE of the following is the primary mechanism for transferring heat through the cladding of a fuel rod?

a. Conduction

b. Convection

c. Radiation

d. Mass Transfer

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

[1.0 point]

The largest amount of energy released per fission event appears in the form of _____________.

a. Gamma radiation

b. Alpha and Beta radiation

c. Kinetic energy of fission fragments

d. Kinetic energy of prompt and delayed neutrons QUESTION A.13

[1.0 point]

A $1.50 insertion has been made into the cold-critical core. What is the k-effective?

a. 1.0070

b. 1.0098

c. 1.0105

d. 1.1500 QUESTION A.14

[1.0 point]

If a source strength is 10,000 neutrons per second (N/sec) and it produces the stable neutron count rate of 50,000 N/sec. What is a multiplication factor?

a. 0.70

b. 0.75

c. 0.80

d. 0.85 QUESTION A.15

[1.0 point]

The following shows part of a decay chain for the radioactive element Pb-190:

82Pb190 83Bi190 This decay chain is an example of _______ decay.

a. Alpha

b. Beta

c. Gamma

d. Neutron

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.16

[1.0 point]

Which ONE of the following is defined as the balance between production of neutrons and their absorption in the core for which core leakage can be neglected?

a. Utilization factor

b. Reproduction factor

c. Infinite multiplication factor

d. Effective multiplication factor QUESTION A.17 [1.0 point]

A reactor is slightly SUPERCRITICAL with the thermal utilization factor = 0.800. A control rod is inserted to bring the reactor back to critical. Assuming all other factors remain unchanged, the new value for the thermal utilization factor is:

a. 0.798

b. 0.800

c. 0.802

d. 0.804 QUESTION A.18

[1.0 point]

In a subcritical reactor, keff is increased from 0.885 to 0.943. Which ONE of the following is the amount of reactivity that was added to the core?

a. 4.68 % k/k

b. 5.58 % k/k

c. 6.94 % k/k

d. 7.45 % k/k QUESTION A.19

[1.0 point]

Which ONE of the following conditions will DECREASE the core excess reactivity of a reactor?

a. Fuel depletion

b. Burnout of a burnable poison

c. Insertion of a positive reactivity worth experiment

d. Lowering moderator temperature (assume a negative temperature coefficient)

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

[1.0 point]

FAST FISSION FACTOR is defined as a ratio of which ONE of the following?

a. The number of neutrons that reach thermal energy over the number of fast neutrons that start to slow down.

b. The number of fast neutrons produced from fission in a generation over the number of fast neutrons produced from fission in the previous generation.

c. The number of fast neutrons produced from U-238 over the number of thermal neutrons produced from U-235.

d. The number of fast neutrons produced from all fission over the number of fast neutrons produced from thermal fission.

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

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

[1.0 point]

The radiation level from an unshielded source is 1 rem/hr. Using a 50 mm thick shield (made from various materials) reduces the radiation level to 625 mrem/hr.

What is the approximate half-value layer (HVL) of the shielding for this source?

(HVL: thickness of shielding required to reduce the original source intensity by half)

a. 64mm

b. 70mm

c. 74mm

d. 80mm QUESTION B.02

[1.0 point]

TXA&M Technical Specification 3.6 states that the sum of the absolute value of reactivity of all experiments shall be < ________ and the reactivity of any single unsecured experiment shall be

a. $1.00 and $2.00

b. $1.00 and $3.00

c. $5.00 and $1.00

d. $5.00 and $2.00 QUESTION B.03

[1.0 point]

Which ONE of the following is NOT a review function of the Reactor Safety Board (RSB)?

a. Review proposed changes to the Technical Specifications or license

b. Review audit reports

c. Review non-substantive changes to existing procedures

d. Review operating abnormalities having safety significance QUESTION B.04

[1.0 point]

What is the dose rate at 12 feet (in mRem/hr) from an irradiated sample that reads 0.7 Rem/hr at 5 feet?

a. 6

b. 12

c. 62

d. 122

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.05

[1.0 point]

Which ONE of the following safety channels is NOT required in steady state mode?

a. Preset Timer

b. Console Scram Button

c. Pool Water Temperature

d. Fuel Element Temperature QUESTION B.06

[1.0 point]

In accordance with TEES Emergency Response Procedures, which ONE of the following is responsible for the minimizing personnel exposures?

a. Reactor Operator

b. Senior Reactor Operator

c. Community Safety Officer

d. Emergency Director QUESTION B.07 [1.0 point]

What frequency is the required interval for TEES NSC Research Reactor personnel to complete an emergency drill and familiarize themselves with all emergency procedures?

a. Monthly

b. Quarterly

c. Semi-annual

d. Annually QUESTION B.08

[1.0 point]

Which ONE of the following TEES Emergency Classifications would apply given the following condition? An intruder has a hostage held at gun point in the reactor bay.

a. General Emergency

b. Site Area Emergency

c. Alert

d. Notification of Unusual Event

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.09

[1.0 point]

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

Time (Minutes)

Counts per Minute (cpm)

Initial count 840 30 740 60 615 90 512 180 270

a. 110 minutes

b. 170 minutes

c. 210 minutes

d. 323 minutes QUESTION B.10 [1.0 point]

If a scram resulted in a reportable occurrence, who must review and approve startup?

a. Training Supervisor

b. Nuclear Regulatory Commission

c. Senior Reactor Operator

d. TEES NSC Director QUESTION B.11

[1.0 point]

Which ONE of the following does NOT require NRC approval prior to being implemented?

a. Changes to an operating procedure that will change the intent of the procedure

b. Changes to Section 6, Administrative Controls of the Technical Specifications

c. Changing the number of required scram channels

d. Changing the passing grade of the written examination for the requalification program from 70% to 60%

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.12

[1.0 point]

Which ONE of the following is the minimum number of hours you must complete before resumption of functions authorized by your license if, during the previous calendar quarter, you were unable to perform the functions of an operator for the minimum number of hours?

a. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

b. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

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

d. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months QUESTION B.13

[1.0 point, 0.25 each]

Identify each of the following surveillances as a channel check (CHECK), a channel test (TEST) or a channel calibration (CAL). Write the correct answer on your answer sheet next to the space given for each example listed below.

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

b. Verifying overlap between Nuclear Instrumentation channels.

c. Replacing a Resistance Temperature Detector (RTD) with a precision resistance decade box to verify proper channel output for a given resistance.

d. Placing radioactive source next to a radiation detector and verifying meter movement.

QUESTION B.14

[1.0 point]

In accordance with the TEES NSC Emergency Preparedness Plan, what are the Protective Action Guidelines (PAG) for Deep Dose Equivalent (DDE) and Committed Dose Equivalent (CDE)?

a. 1 rem DDE and 5 rem thyroid (CDE)

b. 10 rem DDE and 15 rem thyroid (CDE)

c. 5 rem DDE and 50 rem thyroid (CDE)

d. 15 rem DDE and 50 rem thyroid (CDE)

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.15

[1.0 point, 0.25 each]

Select the MAXIMUM allowed value in accordance with the TEES NSC Technical Specifications.

Safety System Maximum Value

a.

Fuel element temperature

______°F (950/965/985) (Max)

b.

Pool water temperature

______ ° C (59/67/71)

c.

Linear High Reactor Power

______ MW (1.10/1.20/1.28)

d.

Control rod scram time

______ sec (0.8/0.9/1.1)

QUESTION B.16

[1.0 point]

Which ONE of the following emergency situations would result in an emergency classification of an Alert?

a. Earthquake felt within the facility.

b. Fire that results in high offgas activity.

c. Security breaches directed toward the reactor.

d. Fueled experiment that fails and causes significant releases of radioactive materials.

QUESTION B.17

[1.0 point]

Which ONE of the following is the requalification operating test requirement for maintaining an active operator license?

a. 1 year

b. 2 years

c. 4 years

d. 6 years QUESTION B. 18 [1.0 point]

Which ONE of the following instruments is the best to check your hands and clothing for Beta-Gamma contamination upon leaving a contamination area?

a. Alpha Scintillation Detector

b. Gas-Flow Proportional Counter

c. HPGe Gamma Spectroscopy System

d. Portable Pancake Probe GM Survey Meter

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

[1.0 point]

TEES NSC Technical Specification states every fuel element used in operation of the reactor shall be inspected how frequently?

a. Annually at least 1/5th

b. Biennial at least 1/4th

c. Biannually at least 1/4th

d. Annually at least 1/5th QUESTION B.20

[1.0 point]

In an emergency, 10 CFR 50.54 allows reasonable action that departs from a license condition or a technical specification when this action is immediately needed to protect the public health and safety. In this case, what is the minimum level of authorization or approval needed to depart from a license condition or technical specification?

a. Senior Reactor Operator

b. Reactor Director

c. Radiation Safety Officer

d. Vice Chancellor for Academic Affairs

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

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

[1.0 point]

QUESTION DELETED If the reactor is to be operated at 400 kW, what is the required Reactor Bridge ARM alert setpoint?

a. 5 mR/hr

b. 6 mR/hr

c. 8 mR/hr

d. 10 mR/hr QUESTION C.02

[1.0 point]

What is the approximate primary pump pressure with the pool full (33 feet)?

a. 15 psig

b. 20 psig

c. 27 psig

d. 32 psig QUESTION C.03

[1.0 point]

A neutron flux will activate isotopes in air. What is the primary isotope we worry about if prolonged opening introduces air into the pneumatic transfer system?

a. N16 (O16 (n,p) N16)

b. Kr80 (Kr79 (n, ) Kr80)

c. Ar41 (Ar40 (n, ) Ar41)

d. H2 (H1 (n, ) H2)

QUESTION C.04

[1.0 point]

Which ONE of the following is the best description on how the Compensated Ion Chamber (CIC) gets its signal to the Linear channel?

Material used in CIC Interact with Results

a.

Pu-239 +

neutron B-10 + alpha --> N-14 + gamma

b.

Am-239 +

neutron Be-9 + gamma --> Li-8 + beta

c.

U-235 +

neutron Fission fragments + gamma

d.

B-10 +

neutron B-11 --> Li-7 + alpha

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

[1.0 point]

Where does the fuel temperature scram come from (located on the console in the Control Room)?

a. Cell Thermocouple

b. Digital Fuel Temperature Meter

c. Pool Thermocouple

d. Digital Temperature Meter QUESTION C.06

[1.0 point]

The annual average concentration of Argon-41 discharged into the unrestricted area shall not exceed ________ at the site boundary?

a. 1 x 10 -8 µCi/ml

b. 2.5 x 10 -7 µCi/ml

c. 1 x 10 -6 µCi/ml

d. 1 x 10 -9 µCi/ml QUESTION C.07

[1.0 point]

QUESTION DELETED What actions are required if the bulk pool conductivity is above 5 x 10 -6 mhos/cm?

a. No actions are necessary

b. Make a note in the main logbook only

c. Change the demineralizer resin out

d. Add chlorine to the pool until the level is greater than 5 µS/cm QUESTION C.08

[1.0 point]

The ARM and FAM require a ________ shall be performed ________.

a. Channel calibration and biannually

b. Channel test and weekly

c. Channel check and monthly

d. Not required except after shutdown

Category C: Facility and Radiation Monitoring Systems QUESTION C.09

[2.0 points, 0.5 each]

Fill out the blank with the time interval specified in the Technical Specifications.

a. Annually - Interval not to exceed ____ months (14/15/16).

b. Semiannually - Interval not to exceed ___ months (7/7.5/8).

c. Quarterly - Interval not to exceed _____ months (4/4.5/5).

d. Monthly - Interval not to exceed ____ weeks (4/6/7).

QUESTION C.10

[1.0 point]

Which ONE of the following prevents withdrawing control rods in the pulse mode?

a. Rod Out Interlock

b. Shim Safety Interlock

c. Low Count Interlock

d. Logic Control Interlock QUESTION C.11

[1.0 point]

What is IMMEDIATELY required for a Facility Air Monitor (FAM) Channel 2 unexpected alarm?

a. No notification or action is required

b. Notify Senior Reactor Operator

c. Scram the reactor and evacuate

d. Notify Radiation Safety Officer QUESTION C.12

[1.0 point]

Which ONE of the following is the location where unirradiated fuel may be stored?

a. Fuel Element Pool Rack

b. Pool Wall Storage Racks

c. Pool Floor Storage Rack

d. Fuel Element Storage Room

Category C: Facility and Radiation Monitoring Systems QUESTION C.13

[1.0 point]

What color badge does a LIMITED ACCESS individual receive?

a. Blue

b. Orange

c. Green

d. Yellow QUESTION C.14

[1.0 point]

Which ONE of the following is NOT a method that can be used in Control Rod Calibration?

a. Rod Drop Method

b. Positive Period Method

c. Differential Worth Method

d. Subcritical Multiplication Method QUESTION C.15

[1.0 point]

What is the poison section of the control rods?

a. Argon

b. Steel

c. Boron

d. Stainless Steel QUESTION C.16

[1.0 point]

Which ONE of the following records is NOT required to be kept for the lifetime of the facility?

a. Offsite environmental surveys

b. Drawings of the reactor facility

c. Radiation exposures for all personnel monitored

d. Principal maintenance activities

Category C: Facility and Radiation Monitoring Systems QUESTION C.17

[1.0 point]

Which ONE of the following produces significant quantities of Nitrogen-16 in the reactor pool?

a. Argon - 41

b. Cobalt - 60

c. Oxygen - 16

d. Iodine - 131 QUESTION C.18 [1.0 point]

Who is the only individual allowed to make changes to the Controlled Access List (CAL) or the Facility Access List (FAL)?

a. Reactor Operator

b. Senior Reactor Operator

d. TEES Dean of Admissions

d. TEES NSC NRC Approved Reviewing Official QUESTION C.19

[1.0 point]

What is the primary function of the graphite sections on both sides of the fuel element?

a. Reduces neutron leakage

b. Absorb fission product gases

c. Absorb thermal neutrons

d. Increases fast neutron flux

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

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

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

c

Reference:

a

Reference:

b

Reference:

b

Reference:

Lamarsh 3rd ed., Section 3.6, page 68-71 Basic Nuclear Engineering 4th ed., Slowing Down of Neutrons, page 226-227 A.05 Answer:

a

Reference:

= (Keff1 - Keff2) / (Keff1

Keff2)

= (1.0000-0.9550) / (0.9550

1.0000)

= 0.0450 / 0.9550 = 0.0471 k/k A.06 Answer:

d

Reference:

NRC standard question; General Atomics 78.82 A.07 Answer:

a

Reference:

Burns, R., Introduction to Nuclear Reactor Operations, Problem 7.7.4, page 7-17 A.08 Answer:

b

Reference:

Chart of the Nuclides; 92 protons, 143 neutrons, 92 electrons A.09 Answer:

d

Reference:

Burns, R., Introduction to Nuclear Reactor Operations, Example 7.2(b), page 7-4 A.10 Answer:

a. Alpha, b. Positron, c. Neutron, d. Alpha (0.25 each)

Reference:

a

Reference:

LaMarsh, 3rd ed, Section 8.3, page 417 A.12 Answer:

c

Reference:

Glasstone, Nuclear Reactor Engineering, Section 1.47

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.13 Answer:

c

Reference:

NRC standard question; Burn, R., Introduction of Nuclear Reactor Operations A.14 Answer:

c

Reference:

CR = S/(1-K) 50,000 = 10,000/(1 - X) 1 - X = 10,000/50,000; K = 0.8 A.15 Answer:

b

Reference:

Chart of the Nuclides A.16 Answer:

c

Reference:

DOE Fundamentals Handbook, NP-03, page 2 A.17 Answer:

a

Reference:

c

Reference:

= (keff1 - keff2) / (keff1

keff2) = (0.943 - 0.885) / (0.943

0.885) 0.0694 k/k = 6.94%k/k A.19 Answer:

Reference:

Glasstone, Nuclear Reactor Engineering, Section 9.88, page 537 B.19 Answer:

a or d (NRC identifies and accepts two correct answers)

Reference:

TEES NSC Technical Specification 4.1.5 B.20 Answer:

a

Reference:

10 CFR Part 50.54(y)

TEES NSC SOP Section II, Procedure H.5

TEES NSC Security Procedures C.19 Answer:

a

Reference:

TEES NSC Technical Specification 5.4

ML21176A114

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