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Examination Report No. 50-223/OL-18-01, University of Massachusetts - Lowell
	ML18284A292
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Site:	University of Lowell
Issue date:	10/10/2018
From:	Anthony Mendiola; Research and Test Reactors Oversight Projects Branch
To:	Prosanta Chowdhury; Univ of Massachusetts - Lowell
	Ferguson A
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October 10, 2018 Dr. Partha Chowdhury, Director Nuclear Radiation Laboratory University of Massachusetts-Lowell One University Avenue Lowell, MA 01854

SUBJECT:

EXAMINATION REPORT NO. 50-223/OL-18-01, UNIVERSITY OF MASSACHUSETTS - LOWELL

Dear Dr. Chowdhury:

During the week of August 27, 2018, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your University of Massachusetts - Lowell research 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,

/RA/

Anthony J. Mendiola, Chief Research and Test Reactors Oversight Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 50-223

Enclosures:

1. Examination Report No. 50-223/OL-18-01

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

ML18284A292 NRR-079 OFFICE NRR/DLP/PROB/CE NRR/DLP/IOLB/OLA NRR/DLP/PROB/BC NAME JNguyen CJRandiki AMendiola (AFerguson for)

DATE 09/17/2018 10/01/2018 10/10/2018 University of Massachusetts - Lowell Docket No. 50-223 cc:

Mayor of Lowell City Hall Lowell, MA 01852 Mr. Leo Bobek Reactor Supervisor University of Massachusetts - Lowell One University Avenue Lowell, MA 01854 Department of Environmental Protection One Winter Street Boston, MA 02108 Jack Priest, Director Radiation Control Program Department of Public Health Schrafft Center, Suite 1M2A 529 Main Street Charlestown, MA 02129 John Giarrusso, Planning and Preparedness Division Chief Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399 Test, Research and Training Reactor Newsletter P.O. Box 118300 University of Florida Gainesville, FL 32611

U.S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-223/OL-18-01 FACILITY DOCKET NO.: 50-223 FACILITY LICENSE NO.: R-125 FACILITY: UMLRR-II EXAMINATION DATES: August 27 - 30, 2018 SUBMITTED BY: /RA/ 09/18/2018 John T. Nguyen, Chief Examiner Date

SUMMARY

During the week of August 27, 2018, the NRC administered an operator licensing examination to three Reactor Operator (RO) and two Senior Reactor Operator Upgrade (SROU) candidates.

One RO candidate failed part B of the written examination. All other candidates passed all applicable portions of the examination.

REPORT DETAILS

1. Examiner: John T. Nguyen, Chief Examiner, NRC

2. Results:

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

3. Exit Meeting:

John T. Nguyen, Chief Examiner, NRC Thomas Regan, Operations Supervisor, UMLRR Leo Bobek, Director, UMLRR Per discussion with the facility, prior to administration of the examination, adjustments were accepted. Upon completion of the examination, 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 1

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

Lowell REACTOR TYPE: Pool DATE ADMINISTERED: 08/30/2018 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 2

Category 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 ___ (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 ___ (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 ___ (0.25 each)

A19 a b c d ___

A20 a b c d ___

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

Category 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 ___ (0.25 each)

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 ___

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 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 ___

C04 a b c d ___

C05 a b c d ___

C06 a ___ b ___ c ___ d ___ (0.25 each)

C07 a b c d ___

C08 a b c d ___

C09 a ___ b ___ c ___ d ___ (0.5 each)

C10 a b c d ___

C11 a b c d ___

C12 a b c d ___

C13 a ___ b ___ c ___ d ___ (0.25 each)

C14 a b c d ___

C15 a b c d ___

C16 a b c d ___

C17 a ___ b ___ c ___ d ___ (0.25 each)

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

( )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

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.01 [1.0 point, 0.25 each]

Match the following Neutron Interactions in Column A with the appropriate definition in Column B (each used only once)

Column A Column B

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 QUESTION A.02 [1.0 point]

Which ONE of the following conditions will require the control rod withdrawal to maintain constant power level after the following change?

a. Adding of a fuel experiment such as U-235 into the core.

b. Insertion of an experiment containing borated graphite.

c. Decrease of pool water temperature.

d. Burnout of Xenon in the core.

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.03 [1.0 point]

The reactor is critical at 100 watts. A blade is withdrawn to insert a positive reactivity of 0.126%

k/k. Which ONE of the following will be the stable reactor period as a result of this reactivity insertion? Given beta effective = 0.0078

a. 13 seconds

b. 46 seconds

c. 52 seconds

d. 80 seconds QUESTION A.04 [1.0 point]

The reactor is operating at 100 W with a fuel temperature indication of 50 °F at the reactor console. When a control rod with an average rod worth of 0.4 %k/k /inch is withdrawn 5 inches, reactor power increases and becomes stable at a higher level. What is the final fuel temperature indication? Given the fuel temperature coefficient of reactivity of -1.25 E-4 k/k/ °F and ignoring any other temperature effects.

a. 25 °F

b. 63 °F.

c. 160 °F

d. 210 °F QUESTION A.05 [1.0 point]

Which ONE of the following best describes the likelihood of fission occurring in U-235 and U-238?

a. Neutron cross sections of U-235 and U-238 are independent from the neutron velocity.

b. Neutron cross section of U-235 increases with increasing neutron energy, whereas neutron cross section of U-238 decreases with increasing neutron energy.

c. Neutrons at low energy levels (eV) are more likely to cause fission with U-238 than neutrons at higher energy levels (MeV).

d. Neutrons at low energy levels (eV) are more likely to cause fission with U-235 than neutrons at higher energy levels (MeV).

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.06 [1.0 point]

Two critical reactors at low power are identical except that Reactor 1 has a beta fraction of 0.0072 and Reactor 2 has a beta fraction of 0.0060. An equal amount of positive reactivity is inserted into both reactors. Which ONE of the following will be the response of Reactor 1 compared to Reactor 2?

a. The final power level will be lower.

b. The final power level will be higher.

c. The resulting period will be longer.

d. The resulting period will be shorter.

QUESTION A.07 [1.0 point]

The reactor power is 500 W. Reactor operator makes a mistake by inserting a sample worth of 1.0 % k/k into the reactor core. Which ONE of the following best describes the reactor kinetic?

The reactor is:

a. subcritical

b. critical

c. supercritical

d. prompt critical QUESTION A.08 [1.0 point]

Reactor power is rising on a 10 second period. Approximately how long will it take for power to quadruple?

a. 14 seconds

b. 29 seconds

c. 55 seconds

d. 72 seconds

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.09 [1.0 point]

Shown below is a trace of reactor period as a function of time. Between points D and E reactor power is:

a. constant.

b. continually decreasing.

c. continually increasing.

d. increasing, then constant.

QUESTION A.10 [1.0 point, 0.25 each]

Match the following descriptions or graphs in Column A with the appropriate definition in Column B (integral control rod worth or differential rod worth).

Column A Column B

a. Total reactivity worth of the control rod at that height 1. Differential Rod Worth

b. Reactivity change per unit movement of a control rod 2. Integral Rod Worth c.

d.

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

If the multiplication factor, k, is increased from 0.800 to 0.950, the amount of reactivity added is:

a. 0.150 k/k

b. 0.197 k/k

c. 0.250 k/k

d. 0.297 k/k QUESTION A.12 [1.0 point]

The neutron microscopic cross-section for absorption a generally:

a. increases as neutron energy increases

b. decreases as neutron energy increases

c. increases as neutron velocity increases

d. decreases as target nucleus mass increases QUESTION A.13 [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

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.14 [1.0 point]

Which ONE of the following isotopes has the largest microscopic absorption cross-section for thermal neutrons?

a. Sm149

b. U235

c. Xe135

d. B10 QUESTION A.15 [1.0 point]

Which ONE of the following atoms will cause a neutron to lose the most energy in an elastic collision?

a. U-238

b. Ar-40

c. O-16

d. H-1 QUESTION A.16 [1.0 point]

Which ONE of the following statements correctly describes the concentration of Xenon in the core following a scram from extended operation of 1 Megawatts? Xenon concentration

a. initially decreases due to the loss of Iodine production, then increases to maximum concentration.

b. eventually decreases to zero in approximately 10 to 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months due to burn out.

c. increases to maximum in approximately 7 to 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months due to I-135 decay.

d. increases to maximum in approximately 7 to 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months due to Cs-135 decay.

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.17 [1.0 point]

Which ONE of the following is the stable reactor period which will result in a power rise from 50% to 100% power in 10 seconds?

a. 7.3 seconds

b. 14 seconds

c. 43 seconds

d. 69 seconds QUESTION A.18 [1.0 point, 0.25 each]

Replace X with the type of 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. 92U 238 90Th 234 +X

b. 83Bi 203 82Pb 203 + X

c. 2He 4 + 4Be9 6C +

12 X

d. 84Po 210 82Pb 206 +X QUESTION A.19 [1.0 point]

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

a. From 1 mW to 5 mW

b. From 10 W to 30 W

c. From 100 W to 200 W

d. From 100 kW to 150 kW

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.20 [1.0 point]

Reactor is at 100 % power. The following graph shows the reactor time behavior following a reactor scram. Which ONE of the following best describes the transition of power between point C and D after the initial rod insertion? .

a. An immediate decrease in the prompt neutron fraction due to leakage, absorption, and a reduction in the fission rate.

b. Fission product gases such as xenon begin to buildup causing the expansion of fuel density.

c. The longest lived delayed neutron precursor begins to effect.

d. The short lived delayed neutron precursors begin to effect.

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics

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

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.01 [1.0 point, 0.25 each]

Match the radiation reading from Column A with its corresponding radiation area classification (per 10 CFR 20) listed in Column B. Answer in Column B can be used more than once, or not at all.

Column A Column B

a. 1 mrem/hr at 1m 1. Public Area

b. 10 mrem/hr at 1m 2. Radiation Area

c. 100 mrem/hr at 1 m 3. High Radiation Area

d. 4.5 grays/hr at 1 m 4. Very High Radiation Area QUESTION B.02 [1.0 point]

How long will it take a 1 Curie source, with a half-life of 2 year, to decay to 0.1 Curie?

a. 4.6 Years

b. 6.6 Years

c. 10.6 Years

d. 16.6 Years QUESTION B.03 [1.0 point]

Which ONE of the following statements will meet the TS requirement? The conductivity of the pool water, averaged over a month, shall be kept:

a. below 5 micromhos/cm.

b. higher than 5 micromhos/cm.

c. below 50 micromhos/cm.

d. higher than 50 micromhos/cm.

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.04 [1.0 point]

Per UMLRR Technical Specifications, what is a minimum level of authority to approve temporary changes to the operating procedures that do not change the effectiveness or the original intent of the procedures?

a. Reactor Safety Subcommittee

b. Director of the Radiation Laboratory

c. Reactor Supervisor

d. Senior Reactor Operators QUESTION B.05 [1.0 point]

Per UMLRR Technical Specifications, when Radiation Area Monitor (RAM) over the reactor pool is inoperable, the reactor operations may continue only if:

a. Particulate Radiation Monitor is still operable.

b. Exhaust Gaseous Radiation Monitor is still operable.

c. Constant Air Monitor and Particulate Radiation Monitor are still operable.

d. Portable gamma sensitive instruments having their own alarm are substituted.

QUESTION B.06 [1.0 point]

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

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

b. The SL is a parameter that assures the integrity of the fuel cladding. The LSSS initiates protective actions to preclude reaching the SL.

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

d. The LSSS is a parameter that assures the integrity of the fuel cladding. The SL initiates protective action to preclude reaching the LSSS.

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.07 [1.0 point]

You are currently the licensed operator at UMLRR. Which ONE of the following will violate 10 CFR Part 55.53 Conditions of licenses?

a. Last requalification operating test was 13 months ago.

b. Last requalification written examination was 13 months ago.

c. Last quarter you were the licensed operator for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

d. Last licensed renewal was 36 months ago.

QUESTION B.08 [1.0 point]

If the measured dose at the site boundary reads between 10 to 15 mRem/hr accumulated over 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , this emergency event will be classified as:

a. Site Area Emergency

b. Alert

c. Unusual Events

d. Non-Reactor Safety Related Event QUESTION B.09 [1.0 point]

The dose rate from a mixed beta-gamma point source is 100 mrem/hour at a distance of one (1) foot, and is 0.1 mrem/hour at a distance of twenty (20) feet. What percentage of the source consists of beta radiation?

a. 20%

b. 40%

c. 60%

d. 80%

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

Per UMLRR Technical Specifications, which ONE of the following will violate the Limiting Safety System Settings for forced convection flow?

a. Height of water above center line of the core is at 25 ft.

b. Reactor coolant inlet temperature is at 110 °F.

c. Steady State reactor power is at 1.20 MW.

d. Coolant flow rate is at 1200 gpm.

QUESTION B.11 [1.0 point]

An irradiated sample provides a dose rate of 0.5 rem/hr at 2 ft. Approximately how far from the sample reads 5 mrem/hr?

a. 6 ft.

b. 9 ft.

c. 14 ft.

d. 20 ft.

QUESTION B.12 [1.0 point]

In accordance with 10CFR20.1301, individual members of the public are limited to a TEDE in one year of:

a. 50 mrem.

b. 100 mrem.

c. 500 mrem.

d. 1250 mrem.

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.13 [1.0 point, 0.25 each]

Identify each of the following as either a Safety Limit (SL) a Limiting Safety System Setting (LSSS) or a Limiting Condition for Operation (LCO).

a. The maximum reactor thermal power at low pool level shall be 1.25 KW (Natural convection flow)

b. The reactivity insertion rates of the control rods shall not exceed 0.025% k/k per second. (All Modes)

c. The True value of pool water temperature shall not be greater than 110 °F (Natural Convection Mode).

d. During steady-state operation a minimum of two Reactor Power Level (Linear N)

Channels shall be operable. (All Modes)

QUESTION B.14 [1.0 point]

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

a. Director of Reactor Operations

b. UMLRRSC

c. Licensed Senior Reactor Operator.

d. Licensed Reactor Operator.

QUESTION B.15 [1.0 point]

Which ONE of the following experiments is not allowed to be installed in the reactor or experiment facilities under ANY condition? The experiment:

a. contains corrosive materials.

b. contains 15 milligrams of TNT material.

c. causes a reduction in the reading for the startup channel.

d. causes the reactivity insertion rate of the regulating rod is 0.030% k/k per second.

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.16 [1.0 point]

Which ONE of the following items is NOT required to log in the console operator's log during insertion of a sample and removal of a sample from the core?

a. Sample identification number

b. Sample time in and out

c. Reactivity worth of sample

d. Dose rate of sample after removal from the reactor core QUESTION B.17 [1.0 point]

All applicants for an RO or SRO license must submit NRC Form 396 and 398 to the U.S. NRC before taking the examinations. This requirement is specified in 10 CFR:

a. Part 19

b. Part 20

c. Part 50

d. Part 55 QUESTION B.18 [1.0 point]

A radiation survey of an area reveals a general radiation reading of 1 mrem/hr. There is, however, a small pipe which reads 20 mrem/hr at one (1) meter. Which ONE of the following defines the posting requirements for the area in accordance with 10CFR20?

a. Control Access Area.

b. Caution, Radiation Area.

c. Caution, High Radiation Area.

d. Grave Danger, Very High Radiation Area.

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.19 [1.0 point]

During a reactor operation of 500 KW power in the forced convection, the reactor operator observes that the coolant flow rate decreases to 1170 gpm. For this flow rate, which ONE of the following is the best action?

a. Increase power to 1 MW in order to verify whether it scrams at setpoint.

b. Continue an operation because the flow rate is within TS limit.

c. Continue operation, but immediately report the result to the supervisor because of exceeding abnormal setpoint.

d Shutdown the reactor; immediately report the result to the supervisor for a potential TS violation.

QUESTION B.20 [1.0 point]

According to EO-7 Stuck Rod of Safety Blade, which ONE of the following is the console operator's primary responsibility?

a. To maintain power level constant.

b. To adjust the micro-switch of the stuck rod.

c. To run the unstuck blades and regulating rod in.

d. To determine the reactivity worth of the stuck rod.

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

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

Reactor is in operation. Using the drawing of the primary system provided, which ONE of the following correctly describes the reactor status if the valve P-12 is opened?

a. Normal (nothing happen)

b. Control blades run down

c. Interlock, control blades inhibit

d. Reactor scram

Category C: Facility and Radiation Monitoring Systems QUESTION C.02 [1.0 point]

Which one of the following combinations of detector alarms would cause to activate the "Limited Radiation Emergency Alarm"?

a. Stack Monitor (A) and Bridge Monitor (K).

b. Bridge Monitor (K) and Control Room Monitor (R).

c. Facilities Exhaust Monitor (F) and Pump Room Monitor (P).

d. Reactor Constant Air Monitor (C) and Fission Product Monitor (E).

QUESTION C.03 [1.0 point]

If a presence of ____ is found in the secondary side of the heat exchanger, a possible leak occurs from the primary system to the secondary system.

a. Na-24

b. Neutrons

c. Ar-41

d. N-16 QUESTION C.04 [1.0 point]

Which ONE of the following is the main purpose of the thermal column?

a. To enhance natural convection flow.

b. Provide a thermal neutron flux for experiments.

c. Provide a fast (high energy) neutron flux for experiments.

d. To shield a radiation dose from reactor core to the experiment area.

Category C: Facility and Radiation Monitoring Systems QUESTION C.05 [1.0 point]

Select the device that ensures the reactor pool will not be completely drained when a large leak develops in the primary coolant piping.

a. The primary coolant pump.

b. The pool divider gate.

c. The heat exchanger.

d. The break valve.

QUESTION C.06 [1.0 point, 0.25 each]

Reactor is at full power. Match the input signals listed in column A with their AUTOMATIC responses listed in column B. (Items in column B can be used once, more than once or not at all.)

Column A Column B

a. Reactor period = 14 seconds 1. Normal

b. Reactor Bridge moved 2 inches 2. Inhibit

c. Coolant gates open 3. Rod Run down

d. High Voltage chamber power supply = 750 V 4. Scram QUESTION C.07 [1.0 point]

Use the drawing of the control blade system provided. When the DS1 light is ON, it indicates that:

a. Control blades circuit is energized.

b. Control blades have reached the UP limit of travel (fully withdrawn).

c. Control blades have reached the DOWN limit of travel (fully inserted).

d. Scram magnet on the control drive is in proper mechanical contact.

Category C: Facility and Radiation Monitoring Systems Category C: Facility and Radiation Monitoring Systems QUESTION C.08 [1.0 point]

A control blade is partially withdrawn from the core. At this point, the source level, for some unknown reason, drops to 1 count per second. As a result:

a. the control blade cannot be withdrawn any further.

b. the control blade cannot be inserted any further.

c. the control blade stuck and cannot be moved in any direction.

d. the control blade can only be inserted by placing the key switch in the OFF position.

QUESTION C.09 [2.0 points, 0.5 each]

Match the item provided in column A, with the correct Nuclear Instrumentation Channel from column B. (Items in column B may be used once, more than once, or not at all.)

Column A Column B

a. < 1 cps rod withdrawal inhibit 1. Log N -Period Channel

b. Reactor period scram with 3 sec 2. Start-up Channel

c. Scram at 125% of range scale 3. Power Channel (Linear N)

d. Scram at 105 F 4. Reactor Pool Temperature

5. Reactor Coolant Inlet Temperature

Category C: Facility and Radiation Monitoring Systems QUESTION C.10 [1.0 point]

The reactor operator could NOT switch from the manual to the auto control mode because the:

a. Coolant flow rate is 1250 gpm.

b. Reactor Period is 35 seconds.

c. Power level is 500 KW and the demand power sets 650 KW.

d. Pool water level is 25 ft. above the center line of the core.

QUESTION C.11 [1.0 point]

A maximum reactivity additional rate of the Control Blade Drive is ______ a maximum reactivity additional rate of the Regulating Rod Drive. A Control Blade Worth is _____ a Regulating Rod Worth.

a. lower than Higher than

b. Higher than lower than

c. Higher than Higher than

d. lower than lower than QUESTION C.12 [1.0 point]

The Figure below depicts:

a. The Compensated Ion Chamber.

b. The Uncompensated Ion Chamber.

c. The Gamma Ion Chamber.

d. The Fission Chamber.

Category C: Facility and Radiation Monitoring Systems Category C: Facility and Radiation Monitoring Systems QUESTION C.13 [1.0 point, 0.25 each]

When the reactor is at 1 MW, identify the transfer mechanism (Forced Convection, Force Flow with no heat transfer, Natural Convection, or Conduction) for each of the following:

a. Cooling the Core.

b. Cooling the Pool.

c. Remove ions by demineralizer.

c. Transfer of heat across the tubes or plates of the heat exchanger.

QUESTION C.14 [1.0 point]

The UMLRR standard fuel element shall be flat plate MTR-type elements fueled with:

a. Low enrichment (<20% U-235) U3Si2, clad with aluminum.

b. Low enrichment (<30% U-235) U3Si2, clad with aluminum.

c. High enrichment (>20% U-235) U3Si2, clad with stainless steel.

d. Low enrichment (<30% U-235) U3Si2, clad with stainless steel.

QUESTION C.15 [1.0 point]

Which one of the following ventilation valves will fail OPEN on a loss of service air?

a. G, Sanitary System Vent Isolation Valve

b. D, Emergency Exhaust Isolation Valve

c. F, Ventilation Supply Bypass Valve

d. H, Acid Vent (Basement)

Category C: Facility and Radiation Monitoring Systems QUESTION C.16 [1.0 point]

Which ONE of the following conditions will NOT initiated the closure of the reactor ventilation system?

a. High power level scram.

b. Activating the LREA in the control room.

c. Loss of power and activation of ventilation freeze alarm.

c. Activating the GREA in the Reactor Supervisor's office.

QUESTION C.17 [1.0 point, 0.25 each]

Match the radiation monitor in Column A with its corresponding detector type from Column B.

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

Column A Column B

a. Bridge Area Radiation Monitor 1. PIPS

b. Stack Effluent Monitor (Gaseous) 2. Geiger-Müeller

c. Stack Effluent Monitor (Particulate) 3. Scintillation

d. Continuous Air Monitor 4. Ion Chamber QUESTION C.18 [1.0 point]

If any significant buildup of radioactivity from the reactor pool, the conductivity of the pool water will be:

a. increase.

b. decrease.

c. the same.

d. no relationship between radioactivity and conductivity in the pool water.

Category C: Facility and Radiation Monitoring Systems QUESTION C.19 [1.0 point]

The reactor is operating at 1 MW. Which ONE of the following trips would most likely cause a reactor scram when the SECONDARY coolant pump turns OFF? Assuming NO OPERATOR ACTION.

a. High Radiation

b. Short Period

c. Low Secondary Flow

d. High Coolant Inlet Temperature

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

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

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.01 Answer: a (3) b (1) c (4) d (2) (0.25 each)

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 1, Module 1, Page 43-46 A.02 Answer: b

Reference:

Reactivity added = 0.126 % k/k = 0.00126 k/k

= (-)/eff = 0.0078 - 0.00126 = 51.9 seconds (0.1) (0.00126)

A.04 Answer: d

Reference:

Reactivity added by control rod = +(0.004 k/k/inch)(5 inches) = 0.02 k/k Fuel temperature change = - reactivity of rod/fuel temperature coefficient.

(- 0.02 k/k)/(- 1.25E-4 k/k/°F) = 160 °F Final Fuel temperature = 50 °F + 160 °F = 210 °F A.05 Answer: d

Reference:

= +

eff A.07 Answer: d

Reference:

A.08 Answer: a

Reference:

P = P0 et/T --> ln(4) = time ÷ 10 seconds -> time = ln (4) x 10 sec. 1.386 x 10 13.8 sec.

A.09 Answer: d

Reference:

Reactor is increasing, then constant when reactor period reaches to infinitive.

A.10 Answer: a. 2; b. 1; c. 2; d. 1 (0.25 each)

Reference:

DOE Fundamentals Handbook, NPRT, Vol. 2, Mod 3, EO 5.4, 5.5, 5.6, p 51-53

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.11 Answer: b

Reference:

= keff1-keff2/(keff1 x keff2) = 0.95-0.8 /(0.8*0.95)=0.197 k/k A.12 Answer: b

Reference:

Introduction to Nuclear Operation, Reed Burn, 1988, Sec 8.1 A.15 Answer: d

Reference:

P = P0 e t/T --> T= t/Ln(P/ P0 )

T= 10/Ln(100/50 ); T = 14.4 sec.

A.18 Answer: a, alpha b, +1 0 c, neutron d, alpha (0.25 each)

A.19 Answer: d

Reference:

P=Poet/Tt=T*ln(P/Po) assume constant period=1; The smallest ratio of P/Po is the shortest time to complete A.20 Answer: c

Reference:

Category B: Normal/Emergency Operating Procedures and Radiological Controls B.01 Answer: a(2); b(3); c(3); d(3) (0.25 each)

Reference:

10 CFR 20.1003 Definitions 1 mrem/hr at 1m will be equal to 11.1 mrem/hr at 30 cm :=> radiation area 10 mrem/hr at 1m will be equal to 111 mrem/hr at 30 cm :=> high radiation area 100 mrem/hr at 1m will be equal to 1111 mrem/hr at 30 cm :=> high radiation area 4.5 grays 450 rad/hr at 1 m high radiation area Definition Radiation Area: 5 mrem/hr at 30 cm High Radiation Area: 100 mrem/hr at 30 cm Very High Radiation Area: 500 rads/hr at 1 m B.02 Answer: b

Reference:

A = A*e -t 0.1Ci = 1 Ci* e -(t)

= ln(2) / (half-life)

= 0.693 / 2 years = 0.3466 ln(0.1/1) = -0.3466*(t) --> -2.30/-0.3466 solve for t: 6.6 years B.03 Answer: a

Reference:

TS 3.8.1 B.04 Answer: c

Reference:

TS 6.3.10 B.05 Answer: d

Reference:

TS 3.4.3 B.06 Answer: b

Reference:

TS 2.1.2 and 2.2.1, Objective B.07 Answer: a

Reference:

10 CFR Part 55.53

55.53(i) - the licensee shall have a biennial medical examination.

55.53(h), 55.59(c) - annual operating tests

55.53(e) - the licensee shall actively perform the functions of a licensed operator for a minimum of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per calendar quarter.

55.53(h), 55.59(c)(1) - The requalification program must be conducted for a continuous period not to exceed 2 years License renewal : 6 years

Category B: Normal/Emergency Operating Procedures and Radiological Controls B.08 Answer: c

Reference:

Emergency Plan, Appendix A B.09 Answer: c

Reference:

10CFR20 - At 20 feet, there is no beta radiation. Gamma at 20 feet =

0.1 mrem/hour, gamma at 1 foot = 40 mrem/hour. Therefore beta at 1 foot = 60 mrem/hour = 60%.

B.10 Answer: b

Reference:

TS 2.2.1 B.11 Answer: d

Reference:

DR1*(D1 ) 2= DR2*(D2) 2 ;

500 mrem (2) 2 = 5 mrem (d) 2 D = 20 ft B.12 Answer: b

Reference:

10CFR20 B.13 Answer: a. = LSSS; b. = LCO; c. = SL; d. = LCO (0.25 each)

Reference:

TS 2.1, TS 2.2, TS 3.1, and TS 3.2 B.14 Answer: c

Reference:

10CFR50.54(y)

B.15 Answer: c

Reference:

TS 3.6 B.16 Answer: d

Reference:

SOP, RO-4 § 2.1.9 B.17 Answer: d

Reference:

10CFR55

Category B: Normal/Emergency Operating Procedures and Radiological Controls B.18 Answer: c

Reference:

DR1D12 = DR2D22 ;

20 mrem/hr at one meter (100 cm.)

results in 222.2 mrem/hr at 30 cm.

B.19 Answer: d

Reference:

TS 3.2 B.20 Answer: c

Reference:

SOP, EO-7

Category C: Facility and Radiation Monitoring Systems C.01 Answer: d

Reference:

SAR 4.2.2.4 C.02 Answer: b

Reference:

SAR, Appendix 10 C.03 Answer: a

Reference:

NRC Standard Questions C.04 Answer: b

Reference:

SAR 4.3.1 C.05 Answer: d

Reference:

SAR 4.2.2 C.06 Answer: a(2) b(4) c(4) d(1) (0.25 each)

Reference:

TS 3.3 C.07 Answer: c

Reference:

SAR, Table 4.2 C.08 Answer: a

Reference:

NRC Standard Questions C.09 Answer: a,2 b,1 c,3 d,4 (0.5 each)

Reference:

SAR 4.4.13, 4.4.14 and 4.4.15 (Table 4.4)

C.10 Answer: c

Reference:

SAR 4.4.12 Demand power > 20% of power level C.11 Answer: a

Reference:

SAR 4.1.7 and 4.1.8 C.12 Answer: a

Reference:

NRC Standard Questions

Category C: Facility and Radiation Monitoring Systems C.13 Answer: a = FC; b = FC; c = FF d = Con (0.25 each)

Reference:

Standard NRC question C.14 Answer: a

Reference:

TS 5.1.1 C.15 Answer: c

Reference:

SAR 3.4.2.2 C.16 Answer: a

Reference:

SAR 3.4.2.1 C.17 Answer: a. = 4; b. = 3; c. = 3; d. = 1 (0.25 each)

Reference:

EP 8.2.1 C.18 Answer: a

Reference:

TS 4.5 C.19 Answer: d

Reference:

When the secondary pump turns off, it exceeds the inlet temperature setpoint

ML18284A292

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SUBJECT:

Dear Dr. Chowdhury:

Enclosures:

SUMMARY

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