ML15160A590

Examination Report No 50-166/OL-15-01, University of Maryland

ML15160A590
Person / Time
Site:	University of Maryland
Issue date:	06/11/2015
From:	Kevin Hsueh Research and Test Reactors Branch B
To:	Koeth T Univ of Maryland - College Park
Isaac P
Shared Package
ML15042A082	List: ML15160A590 ML15160A658
References
50-166/15-001 50-166/OL-15-01
Download: ML15160A590 (36)

Text

June 11, 2015 Dr. Timothy Koeth, Director The University of Maryland Radiation Facilities and Nuclear Reactor Department of Materials Science and Engineering 2309D Chemical and Nuclear Engineering Building Building 090, Stadium Drive College Park, MD 20742-2115

SUBJECT:

EXAMINATION REPORT NO. 50-166/OL-15-01, UNIVERSITY OF MARYLAND

Dear Dr. Koeth:

During the week of April 7, 2015, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your University of Maryland 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 Mr. Vincent Adams of your staff 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 that will not be publicly released. Should you have any questions concerning this examination, please contact Mr. Patrick Isaac at (301) 415-1019 or via e-mail Patrick.Isaac@nrc.gov.

Sincerely,

/RA/

Kevin Hsueh, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-166

Enclosures:

1. Examination Report No. 50-166/OL-15-01

2. Facility Comments with NRC Resolution

3. Written examination cc: w/o enclosures: See next page

Dr. Timothy Koeth, Director June 11, 2015 The University of Maryland Radiation Facilities and Nuclear Reactor Department of Materials Science and Engineering 2309D Chemical and Nuclear Engineering Building Building 090, Stadium Drive College Park, MD 20742-2115

SUBJECT:

EXAMINATION REPORT NO. 50-166/OL-15-01, UNIVERSITY OF MARYLAND

Dear Dr. Koeth:

During the week of April 7, 2015, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your University of Maryland 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 Mr. Vincent Adams of your staff 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 that will not be publicly released. Should you have any questions concerning this examination, please contact Mr. Patrick Isaac at (301) 415-1019 or via e-mail Patrick.Isaac@nrc.gov.

Sincerely,

/RA/

Kevin Hsueh, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-166

Enclosures:

1. Examination Report No. 50-166/OL-15-01

2. Facility Comments with NRC Resolution

3. Written examination cc: w/o enclosures: See next page DISTRIBUTION w/ encls.:

PUBLIC RidsNRRDPRPROB ADAMS ACCESSION #: ML15160A590 TEMPLATE #:NRR-079 OFFICE NRR/DPR/PROB:CE NRR/DPR/ IOLB:OLA NRR/DPR/PROB:BC NAME PIsaac CRevelle KHsueh DATE 6/11/2015 6/09/2015 6/11/2015 OFFICIAL RECORD COPY

University Of Maryland Docket No. 50-166 cc:

Director, Dept. of Natural Resources Power Plant Siting Program Energy & Coastal Zone Administration Tawes State Office Building Annapolis, MD 21401 Mr. Roland Fletcher, Director Center for Radiological Health Maryland Department Environment 201 West Preston Street 7th Floor Mail Room Baltimore, MD 21201 Mr. Vincent Adams Facility Coordinator Chemical and Nuclear Engineering Building 090 University of Maryland College Park, MD 20742 Mary J. Dorman Radiation Safety Officer Department of Environmental Safety 3115 Chesapeake Building 338 University of Maryland College Park, MD 20742 Professor Robert Briber University of Maryland Department of Materials Science and Engineering Room 2135, Chem. & Nuclear Engineering Bldg (090)

College Park, MD 20742-2115 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-166/OL-15-01 FACILITY DOCKET NO.: 50-166 FACILITY: UMD EXAMINATION DATES: April 7-10, 2015 SUBMITTED BY: ___________/RA/___________ __05/19/15 Patrick Isaac, Chief Examiner Date

SUMMARY

During the week of April 7, 2015, the NRC administered operator licensing examinations to two Reactor Operator and three Senior Reactor Operator candidates. The candidates passed all applicable portions of the examinations.

REPORT DETAILS

1. Examiners: Patrick Isaac, Chief Examiner, NRC Michele DeSouza, Examiner Trainee

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 2/0 3/0 5/0 Operating Tests 2/0 3/0 5/0 Overall 2/2 3/0 5/0

3. Exit Meeting:

Patrick Isaac, Chief Examiner, NRC Michele DeSouza, Examiner Trainee, NRC Vincent Adams, Operations Manager At the conclusion of the examinations, the NRC examiners thanked the facility for their support in the administration of the examinations. The examiners reminded Mr. Adams that the written examination will not be graded until the facility licensees comments have been received by the NRC. Mr. Adams committed to provide any comments on the written examination in a timely manner.

ENCLOSURE 1

Facility Comments with NRC Resolution Question A.01 Facility Comment:

Either a or b can correct depending on whether you are talking about our reactor or reactors in general due to the sign of the moderator coefficient.

Please consider accepting both a and b as correct.

NRC Resolution:

Comment partially accepted. The answer key is corrected to accept a as the correct answer as this is the answer applicable to the facility.

Question A.04 Facility Comment:

The question does not specify over what time interval the factor is affected. Choice a is correct for short term effects and choice c is correct for long term effects.

Please consider accepting both a and c as correct.

NRC Resolution:

Comment accepted. The answer key is corrected to accept both a and c as correct.

Question: A.09 Facility Comment:

Both a and d should be correct since they describe the same characteristics on different scales Justification: Pages 17-18 of DOE Fundamentals Handbook Vol 2 Module 4 show a direct relation between reactor period and doubling time with a simple scalar proportional relationship of ln(2)

Please consider accepting both a and d as correct NRC Resolution:

Comment accepted. The answer key is corrected to accept both a and d as correct.

Question A.19 Facility Comment:

There is no specification of what the neutron is. If the neutron is the neutron that causes fission answers c and d would be correct since the number of neutrons produced is not effected by the energy of the fission causing neutron.

NRC Resolution:

Question deleted. The facility provided comments but did not provide a suggestion or recommendation. NRC agrees this question was not clear and agrees to delete the question.

Question A.20

Facility Comment:

When Beff is less than reactivity the reactor is both Prompt Critical and Supercritical. If Beff is less than reactivity then Keff must be greater than 1 and by definition the reactor is Supercritical.

Please consider answers c and d as correct NRC Resolution:

Comment accepted. The answer key is corrected to accept both c and d as correct.

Question B.11 Facility Comment:

There is a typo in choice d, the exponent should be -6 making it the correct answer.

There is no correct answer with typo, correct answer should read 5x10E-6mhos/cm.

NRC Resolution:

Comment accepted, however, no correction to the answer key is necessary.

The documentation submitted by the facility was used in the preparation of the written examination and did in fact have the answer as listed in the question. The candidates discussed with the proctor their belief that a correct answer was not present. After consultation, the proctor clarified to all the candidates that choice d should state 5 x 10-6 mhos/cm.

Question C.09 Facility Comment:

For our reactor both b and d are correct. We do not have an individual Purification System as it is a part of the Primary water system.

Please consider accepting both b and d as correct.

NRC Resolution:

Comment accepted. The answer key is corrected to accept both b and d as correct.

Question C.10 Facility Comment:

This question is worded in a confusing or incomplete manner. During the exam, candidates were unsure if this intended to mean a loss integrity of fuel cladding as opposed to the homogenous UZrH fuel contained within the cladding. Depending on interpretation both answers a and d are acceptable.

Please consider accepting both a and d as correct.

NRC Resolution:

Comment rejected. This question has only one correct answer and remains as written.

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: University of Maryland REACTOR TYPE: UMD TRIGA DATE ADMINISTERED: 4/07/2015 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 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 ENCLOSURE 3

Section A - Reactor Theory, Thermodynamics, & Facility Operating Characteristics ANSWER SHEET 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 ___ (0.25 each)

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 ___

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 SECTION A *****)

Section B - Normal/Emergency Operating Procedures and Radiological Controls ANSWER SHEET 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 ___ (0.25 each)

B05 a b c d ___

B06 a ___ b ___ c ___ (0.33 each)

B07 a b c d ___

B08 a b c d ___

B09 a ___ b ___ c ___ (0.33 each)

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 ___

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 SECTION B *****)

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.

C01 a b c d ___

C02 a b c d ___

C03 a ___ b ___ c ___ d ___ (0.25 each)

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 SECTION 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

( )2 eff = 0.1sec 1 Q = m cP T = m H =UAT Pmax =

(2 )

t P = P0 e S S SCR = * =1x104 sec 1 K eff eff +

SUR = 26 .06

( ) (

CR1 1 K eff1 = CR2 1 K eff 2 ) CR1 ( 1 ) = CR2 ( 2 )

(1 ) M=

1

= 2 CR P = P0 10SUR(t )

P= P0 1 K eff CR1 1 K eff1 1 K eff

• M= SDM = =

1 K eff 2 K eff

• 0.693 K eff 2 K eff1

+ T1 =

eff + 2 K eff1 K eff 2 K eff 1

= DR = DR0 e t 2 DR1 d1 = DR2 d 2 2

K eff 6 Ci E (n) ( 2 )2 = (1 )2 DR =

R2 Peak2 Peak1 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

Section A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.01 [1.0 point]

How will an increase in moderator temperature affect neutron multiplication?

a. Resonance escape probabilities, thermal and fast non leakage increase

b. Resonance escape probabilities, thermal and fast non leakage decrease

c. Slowing down and diffusion length decrease

d. Slowing down and diffusion length decrease with a decrease in rod worth as secondary QUESTION A.02 [1.0 point]

Which ONE of the following is the MAJOR source of energy released during fission?

a. Fission fragments

b. Fission product decay

c. Prompt gamma rays

d. Fission neutrons (kinetic energy)

QUESTION A.03 [1.0 point, 0.25 each]

Match the following Neutron Interactions (each used only once)

a. Fission 1. Neutron enters nucleus, forms a compound nucleus, then decays by gamma emission

b. Radiative capture 2. Particle enters nucleus, forms a compound nucleus and is excited enough to eject a new particle with incident neutron remaining in nucleus

c. Scattering 3. Nucleus absorbs neutron and splits into two similarly sized parts

d. Particle ejection 4. Nucleus is struck by a neutron and emits a single neutron

Section A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.04 [1.0 point]

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

a. Xenon build-up

b. Moderator temperature

c. Fuel burn-up

d. Fuel density QUESTION A.05 [1.0 point]

The following shows part of a decay chain for the radioactive element Pa-234:

234 91Pa 92U234 This decay chain is an example of _______ decay.

a. Alpha

b. Beta

c. Gamma

d. Neutron QUESTION A.06 [1.0 point]

Which ONE defines a differential rod worth curve?

a. Parabolic shaped with maximum at the top and bottom of the core height

b. Exponentially shaped with maximum at the bottom of the core height

c. S shaped with minimum at the middle of the core height

d. Cosine shaped with maximum at the middle of the core height

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

In a subcritical reactor, keff is increased from 0.914 to 0.965. Which one of the following is the amount of reactivity that was added to the core?

a. 3.64%k/k

b. 4.38%k/k

c. 5.78%k/k

d. 6.57%k/k QUESTION A.08 [1.0 point]

A reactor is operating at criticality. Instantaneously, all of the delayed neutrons are suddenly removed from the reactor. The Keff of the reactor in this state would be approximately:

a. 1.007

b. 1.000

c. 0.993

d. 0.000 QUESTION A.09 [1.0 point]

A rapid change in reactor power will result from a smaller value of _________.

a. Reactor period

b. Reactivity

c. Effective delayed neutron fraction

d. Doubling time QUESTION A.10 [1.0 point]

The fuel temperature coefficient of reactivity is -2.5x10-4 k/k/°C. When a control rod with an average rod worth of 0.2 % k/k/inch is withdrawn 12 inches, reactor power increases and becomes stable at a higher level. At this point, the fuel temperature has:

a. decreased by 96°C

b. increased by 96°C

c. decreased by 0.67°C

d. increased by 0.67°C

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

eff is defined as:

a. Ratio of delayed neutrons to total core neutrons once they have slowed down to thermal energies

b. Ratio of prompt neutrons to thermal neutrons

c. Probability of prompt neutrons becoming thermal neutrons

d. Probability of delayed neutrons becoming thermal neutrons QUESTION A.12 [1.0 point]

A reactor is operating at 5kW and is placed on a positive 3 second period. How long will it take for the power to increase 1.0MW?

a. 3.45 seconds

b. 10.88 seconds

c. 12.21 seconds

d. 15.89 seconds QUESTION A.13 [1.0 point]

Two common FISSION PRODUCTS that have especially large neutron cross sections and play a significant role in reactor physics are Sm-149 and _______.

a. Xe-135

b. Ar-41

c. N-16

d. I-131 QUESTION A.14 [1.0 point]

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

a. 5%, from 95% to 100%

b. 10%, from 80% to 90%

c. 15%, from 15% to 30%

d. 20%, from 60% to 80%

Section A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.15 [1.0 point]

What is the material called that is used for the purpose of thermalizing neutrons?

a. Absorber

b. Poison

c. Moderator

d. Void coefficient QUESTION A.16 [1.0 point]

During the time following a reactor scram, reactor power decreases on a negative 80 second period, which of the following corresponds to the half-life of the longest-lived delayed neutron precursors?

a. 80 seconds

b. 55 seconds

c. 40 seconds

d. 20 seconds QUESTION A.17 [1.0 point]

Which one of the following best represents a characteristic of subcritical multiplication?

a. The number of neutrons gained per generation increases by a factor of x2 for each succeeding generation.

b. For equal reactivity additions, it takes less time for the equilibrium subcritical neutron population level to be reached as Keff approaches one.

c. A constant neutron population is achieved when the total number of neutrons produced in one generation is equal to the number of source neutrons in the next generation

d. Doubling the indicated power will reduce the margin to criticality by approximately one half

Section A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.18 [1.0 point]

A reactor that has a reactivity of -$2.39 has a count rate of 50 cps on nuclear instrumentation.

Calculate what the neutron level (i.e., count rate) should be after a reactivity insertion of $1.21 from the withdrawal of the control rods. Assume =0.0070

a. 25 cps

b. 50 cps

c. 100 cps

d. 200 cps QUESTION A.19 [1.0 point] DELETED As the energy of the neutron is raised, the average number of neutrons released (both prompt and delayed) ___________.

a. Increases

b. Decreases

c. Stays the same

d. Has no effect QUESTION A.20 [1.0 point]

When Beff is less than reactivity the reactor is __________.

a. Subcritical

b. Critical

c. Supercritical

d. Prompt critical

(***** END OF SECTION A *****)

Section B: Normal and Emergency Operating Procedures and Radiological Controls QUESTION B.1 [1.0 point]

The following emergency class action levels pertain to which emergency class, sustained fire or minor explosion within the reactor building or failure of an experiment involving a significant release of radioactivity within the reactor building:

a. Class 0

b. Class 1

c. Class 2

d. Class 3 QUESTION B.2 [1.0 point]

Per UMD Radiation Safety Procedures, personnel monitoring TLD badges, or equivalent, will be exchanged:

a. Daily

b. Weekly

c. Monthly

d. Quarterly QUESTION B.3 [1.0 point]

The reactor shall NOT be operated unless the following measuring channels are operable:

a. 1 linear power channel and 1 fuel element temperature channel

b. 2 reactor power level channels and 1 fuel element temperature channel

c. 2 linear power channels and 2 fuel element temperature channels

d. 2 fuel element temperature channels and 2 log power channels

Section B: Normal and Emergency Operating Procedures and Radiological Controls QUESTION B.4 [1.0 point, 0.25 each]

Match the limitations on experiments from Column B (may be used more than once) with Column A:

Column A Column B

a. Non secured experiment 1. $0.50

b. Any single experiment 2. $1.00

c. Total in-core experiment 3. $2.00

d. Shutdown margin 4. $3.00 QUESTION B.5 [1.0 point]

How many hours per calendar quarter must you perform the functions of an RO or SRO to maintain an active RO or SRO license?

a. 4

b. 6

c. 8

d. 12 QUESTION B.6 [1.0 point, 0.33 each]

Match the appropriate item in column A with its definition in column B:

Column A Column B

a. Channel Calibration 1. Qualitative verification of acceptable performance by observation of channel behavior

b. Channel Check 2. An adjustment of the channel such that its output corresponds with acceptable accuracy to known values of the parameter that the channel measures

c. Channel Test 3. The introduction of a signal into the channel for verification that it is operable

Section B: Normal and Emergency Operating Procedures and Radiological Controls QUESTION B.7 [1.0 point]

How long will it take a 50 Curie source, with a half-life of 5.26 years, to decay to 2 Curie?

a. 10.5 Years

b. 15.5 Years

c. 24.5 Years

d. 35.5 Years QUESTION B.8 [1.0 point]

Why is pool water evaluated for gross gamma activity?

a. Detect particulates

b. Detect fission product release

c. Prevent heat exchanger issues

d. Prevent demineralizer clogging QUESTION B.9 [1.0 point, 0.33 each]

Per UMD Emergency Classification match the emergency class with the emergency action level (Use each only once):

Column A Column B

a. Severe or extensive fuel damage involving multiple 1. Personnel Emergency clad failures

b. An explosion or a fire in the reactor building 2. Class 1 - Notification of Unusual Events

c. Incidents involving one or more persons requiring 3. Class 2 - Alert medical treatment

Section B: Normal and Emergency Operating Procedures and Radiological Controls QUESTION B.10 [1.0 point]

10 CFR 20 limits the annual occupational exposure to the WHOLE BODY of an individual to:

a. 50 rem

b. 15 rem

c. 100 rem

d. 5 rem QUESTION B.11 [1.0 point]

Conductivity of pool water shall be no higher than ____________.

a. 2 x 10-3mhos/cm

b. 3 x 10-2mhos/cm

c. 4 x 10-1mhos/cm

d. 5 x 10-0mhos/cm QUESTION B.12 [1.0 point]

Calculate an individuals total whole body dose given the individual received the following doses: 5 mrad of alpha, 10 mrad of gamma, and 10mrad of neutron (unknown energy)

a. 190 mrem

b. 200 mrem

c. 210 mrem

d. 220 mrem QUESTION B.13 [1.0 point]

You are standing three feet from a radiation field of 250 mR/hr. What is your dose rate at 9 feet away from the source?

a. 24 mR/hr

b. 28 mR/hr

c. 32 mR/hr

d. 36 mR/hr

Section B: Normal and Emergency Operating Procedures and Radiological Controls QUESTION B.14 [1.0 point]

The emergency procedure uses the acronym SAVE to provide instructions for the evacuation of personnel from the Reactor Building. The acronym SAVE stands for:

a. Scram, alarms, vent, and evacuate

b. Secure, alert, vent, and execute

c. Safeguard, awareness, visualize, and education

d. Scram, alert, visualize, and execute QUESTION B. 15 [1.0 point]

Select the list that gives the order of types of radiation from the LEAST penetrating to the MOST penetrating (i.e. travels further in air)

a. Neutron, gamma, beta, alpha

b. Alpha, neutron, beta, gamma

c. Beta, alpha, gamma, neutron

d. Alpha, beta, neutron, gamma QUESTION B.16 [1.0 point]

After a building evacuation, who has the authority to allow reentry to the reactor building or allow access to the reactor building roof?

a. Senior Reactor Operator

b. Reactor Director

c. Emergency Director

d. NRC QUESTION B.17 [1.0 point]

Which one of the following DOES NOT require supervision by a senior reactor operator?

a. Initial startup following new fuel loading

b. Resuming operation after an unscheduled electrical shutdown

c. Removal of control rods in the core

d. In-core experiment manipulation of greater than $0.80

Section B: Normal and Emergency Operating Procedures and Radiological Controls QUESTION B.18 [1.0 point]

The statement, the excess reactivity relative to the cold critical conditions, with or without experiments in place shall not be >$3.50 is an example of __________.

a. Limiting condition for operation (LCO)

b. Limiting safety system settings (LSSS)

c. Safety limit

d. Administrative control QUESTION B.19 [1.0 point]

Which ONE of the following is the radiation dose limit for the public in an unrestricted area?

a. No limit

b. 2 rem in a year

c. 2 rem in any one hour

d. 2 mrem in any one hour QUESTION B.20 [1.0 point]

A two curie source emits a 2MeV gamma 100% of the time. The source will be placed in the reactor storage building. How far from the source should a high radiation area sign be posted?

a. Not required

b. 10.5 feet

c. 12.5 feet

d. 15.5 feet

(*****End of Section B *****)

Section C: Facility and Radiation Monitoring Systems QUESTION C.01 [1.0 point]

The beam ports are stepped to prevent ________.

a. Coolant leakage

b. Streaming radiation

c. Loss of experiment

d. Corroding piping systems QUESTION C.02 [1.0 point]

Primary coolant temperature is measured by the following EXCEPT_________.

a. Four thermocouples in the primary system

b. Two thermocouples before and two thermocouples after the heat exchanger

c. Two thermocouples in the reactor pool

d. Four thermocouples in the secondary system QUESTION C.03 [0.25 each point]

Match the following UMD control rod drive components with their corresponding definitions.

Answers are used only once.

Column A Column B

a. Potentiometer 1. Switch will reverse position according to whether the magnet is at or above its completely depressed position

b. Rod down limit switch 2. Provides rod position indications

c. Magnet up limit switch 3. Switch reverses position according to whether the magnet is at or below its full up position

d. Magnet down limit switch 4. Foot is depressed by armature when rod is fully lowered

Section C: Facility and Radiation Monitoring Systems QUESTION C.04 [1.0 point]

Which ONE of the followings interlocks prevents the withdrawal of two or more control rods in steady state mode?

a. Rod drive control interlock

b. Startup count rate interlock

c. Log power level interlock

d. Pulse power interlock QUESTION C.05 [1.0 point]

The difference between the total worth of all control rods in the core and the reactivity which needs to be inserted into the core in order for the reactor to become critical is the _________.

a. Shutdown margin

b. Thermal output

c. Excess reactivity

d. Coefficient of reactivity QUESTION C.06 [1.0 point]

Typical annual exposures at the pool surface are ________.

a. 100 mrem

b. 20 mrem

c. 1000 mrem

d. 50 mrem

Section C: Facility and Radiation Monitoring Systems QUESTION C.07 [1.0 point]

Which ONE of the following systems is used at UMD in the event of a rupture in the primary piping?

a. A diffuser system

b. A deionizer

c. A siphon break

d. A skimmer QUESTION C.08 [1.0 point]

What is the purpose of limiting conditions for operation?

a. Provide excess reactivity >$3.50

b. Provide a reactor scram to prevent reaching the safety limit

c. Ensure the reactor can be controlled and shut down at all times and not exceed safety limits

d. Ensure the fuel element temperature not exceed 1000oC QUESTION C.09 [1.0 point]

Which system is responsible for removing radioactive ions and particles, reducing conductivity, and maintaining optical clarity?

a. Makeup system

b. Purification system

c. Secondary system

d. Primary system QUESTION C.10 [1.0 point]

A loss in fuel integrity could result in a buildup of pressure between the _________ and the

a. Fuel moderator and reflector

b. Reflector and cladding

c. Primary and secondary coolant

d. Fuel moderator and cladding

Section C: Facility and Radiation Monitoring Systems QUESTION C.11 [1.0 point]

The ion chamber power indications are correlated to the heat balance calculated thermal power by:

a. Physically adjusting the height of the detectors in the support assembly

b. Moving the graphite reflectors to change the neutron flux near the detectors

c. Adjusting the circuit comparator voltage

d. Adjusting the detector high voltage QUESTION C.12 [1.0 point]

Which ONE of the following radiation monitoring systems SCRAM the reactor if the set point is exceeded?

a. Reactor bridge and glove box monitors

b. Reactor bridge and exhaust vent monitors

c. Exhaust vent and glove box monitors

d. Glove box monitor only QUESTION C.13 [1.0 point]

An experiment with corrosive or liquid fissionable materials shall be:

a. Limited to $0.50

b. Double encapsulated

c. No greater than 5 mCi

d. Supervised by Reactor Director

Section C: Facility and Radiation Monitoring Systems QUESTION C.14 [1.0 point]

When going to automatic from manual rod control the regulating rod will automatically be limited to a ________ reactor period until the power has reached the demand setpoint on the %

DEMAND controller for the current range selected on the REACTOR POWER RANGE SWITCH.

a. 15 second

b. 25 second

c. 10 second

d. 5 second QUESTION C.15 [1.0 point]

Where do the thermocouples in the instrumented fuel bundle measure temperature?

a. Interior of the fuel

b. Center of the zirconium rod

c. Interior surface of the cladding

d. Outer surface of the fuel QUESTION C.16 [1.0 point]

The purpose of the Nitrogen-16 diffuser is _______.

a. Assist with natural circulation through the reactor core

b. Reduce radiation levels at the pool surface

c. Sweep away fission products in order to prevent them from reaching the pool surface

d. Take a suction on the primary pool and discharge it to the purification system to remove activated impurities

Section C: Facility and Radiation Monitoring Systems QUESTION C.17 [1.0 point]

The fuel storage racks can hold up to 13 fuel clusters and criticality calculations show keff < 0.4.

keff must be < than what level?

a. 0.9

b. 0.8

c. 0.7

d. 0.6 QUESTION C.18 [1.0 point]

What radiation does the compensated ion chamber discriminate between?

a. Neutrons and gamma

b. Gamma and beta

c. Beta and alpha

d. Neutrons and fission fragments QUESTION C.19 [1.0 point]

Which ONE of the following types of detectors is used to detect surface contamination and determine radiation fields around the reactor?

a. Ionization chamber

b. Scintillation detector

c. Proportional counter

d. Geiger-Mueller meter QUESTION C.20 [1.0 point]

Pool water conductivity and ________ shall be determined monthly.

a. Neutron levels

b. Particulate activity

c. Gross gamma activity

d. Beta/gamma activity

(***** END OF SECTION C *****)

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

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

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 3.3.2(b), Page 3-18 A.02 Answer: a

Reference:

Burn, Introduction to Nuclear Reactor Operations, Table 3.2, Page 3-5 A.03 Answer: a 3; b 1; c 4; d 2

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 1, Module 1, Page 43-46 A.04 Answer: a or c

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 3.3.2, Page 3-18 A.05 Answer: b

Reference:

Chart of the Nuclides A.06 Answer: d

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 7.2, Page 7-4 A.07 Answer: c

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 3.3.4, Page 3-20&3-21

=(keff2-keff1)/(keff1*keff2) = (0.965-0.914)/(0.965*0.914) = 0.0578k/k=5.78%/k A.08 Answer: c

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 1, Module 2, Page 30 A.09 Answer: a or d

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 2, Module 4, Page 11 A.10 Answer: b

Reference:

Lamarsh, Introduction to Nuclear Engineering, Page 365 A.11 Answer: a

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 3.2.4, Page 3-12

Section A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.12 Answer: d

Reference:

P = P0 e(t/T); P=1MW, Po=5kW, T= 3seconds, t=(3sec)*ln(1000000W/5000W), t =15.89 seconds A.13 Answer: a

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 8.1, Page 8-1 A.14 Answer: c

Reference:

Time is related to ratio of final power to initial power. 2:1 is the largest ratio A.15 Answer: c

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 2, Module 2, Page 23 A.16 Answer: b

Reference:

LaMarsh, Introduction to Nuclear Engineering, Page 88 A.17 Answer: d

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 2, Module 4, Pages 1-6 A.18 Answer: c

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 2, Module 1 This question can be answered in two ways. One way is through the equations as shown below, or two, use a rule of thumb that if the reactor moves halfway from its subcritical state towards criticality, the count rate will double.

CR1/CR2=1-k2/1-k1CR2=CR1(1-k1/1-k2)=50cps(1-0.984/1-0.992)=100 Where, ($)=/, p1=(0.0070)x(-$2.39)= -0.01673, p2= (0.0070)x(1.21)=

0.00850= 821 pcm--> -0.00823 K1=1/1-p1=1/10.01673=0.984, k2=1/1-p2=1/1+0.00823=0.9918 A.19 Question deleted Answer: a

Reference:

LaMarsh, Introduction to Nuclear Engineering, Page 85 A.20 Answer: c or d

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 4.6, Page 4-16 &

Table 4.3

Section B: Normal and Emergency Operating Procedures and Radiological Controls B.1 Answer: b

Reference:

MUTR Emergency Plan B.2 Answer: c

Reference:

MUTR Radiation Safety Procedure B.3 Answer: b

Reference:

TS, Table 3-1a B.4 Answer: a (2), b (2), c (4), d (1)

Reference:

TS, 3.1 & 3.6 B.5 Answer: a

Reference:

10CFR55.53(e)

B.6 Answer: a (2), b (1), c (3)

Reference:

TS 1.2.1-1.2.3 Definitions B.7 Answer: c

Reference:

T A = A*e -t 2Ci = 50Ci* e -(t)

Ln(2/50) = -ln2/5.27 yr*(t) --> -3.2189/-0.1315 solve for t: 24.47 years B.8 Answer: b

Reference:

TS, 4.3 B.9 Answer: a (3), b (2), c (1)

Reference:

MUTR Emergency Plan B.10 Answer: d

Reference:

10 CFR 20.1201 B.11 Answer: d

Reference:

TS 3.4.1 B.12 Answer: c

Reference:

5mrad Alpha x 20=100mrem, 10mrad Gamma x 1=10mrem, 10mrad neutron x 10 = 100mrem 100mrem+10mrem+100mrem= 210mrem

Section B: Normal and Emergency Operating Procedures and Radiological Controls B.13 Answer: b

Reference:

I1D12=I2D22 250mR/hr@(3ft)2=I2@(9ft)2 28mR/hr B.14 Answer: a

Reference:

MUTR, EP-401 B.15 Answer: d

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 1, Module 1, Pages 64-66 B.16 Answer: c

Reference:

E-Plan B.17 Answer: b

Reference:

MUTR, training admin B.18 Answer: a

Reference:

TS 3.1(1&2)

B.19 Answer: d

Reference:

10CFR20.1301(a)(2)

B.20 Answer: d

Reference:

I=6CEn=R/hr@ft.2Ci x 2Mev x 100% = 24 R/hr@ (1ft)2 = 24 R/hr = 0.1 R/hr@

D2 = 240 R/hr = 15.5 ft

Section C: Facility and Radiation Monitoring Systems C.01 Answer: b

Reference:

SAR 10.2.2 C.02 Answer: d

Reference:

SAR 5.2 C.03 Answer: a, 2 b, 4 c, 3 d, 1

Reference:

SAR 4.2.2.3 C.04 Answer: a

Reference:

TS 3.3, Table 3-1a C.05 Answer: c

Reference:

ENNU 320, Volume 2, Section 7.5, Page 7-2 C.06 Answer: a

Reference:

SAR 4.2.2.b, Table 4.3, Page 4-12 C.07 Answer: c

Reference:

SAR 4.1, Page 4-2 C.08 Answer: c

Reference:

SAR 2.2 C.09 Answer: b or d

Reference:

TS 5.1 C.10 Answer: d

Reference:

TS 2.1 C.11 Answer: a

Reference:

ENNU 320, Volume 2, Section 7.3, Page 7-1 C.12 Answer: b

Reference:

SAR 7.7 C.13 Answer: b

Reference:

TS 3.6(4)

Section C: Facility and Radiation Monitoring Systems C.14 Answer: a

Reference:

ENNU 320, Volume 2, Section 6.2.2, Page 6-8 C.15 Answer: a

Reference:

ENNU 320, Volume 2, Section 3.1.2, Page 3-1 C.16 Answer: b

Reference:

ENNU 320, Volume 2, Section 7.5, Page 7-2 C.17 Answer: b

Reference:

TS 5.3 and ENNU 320, Volume 2, Section 7.1, Page 7-1 C.18 Answer: a

Reference:

ENNU 320, Volume 2, Section 3.3.5.3, Page 3-7 C.19 Answer: d

Reference:

ENNU 320, Volume 1, Section 10.5, Page 10-4 C.20 Answer: c

Reference:

TS 3.8.3, Page TS-21