Text

Initial Examination Report, No. 50-223/OL-09-01, University of Massachusetts - Lowell
	ML092390145
Person / Time
Site:	University of Lowell
Issue date:	09/09/2009
From:	Young P; Research and Test Reactors Branch B
To:	Kegel G; Univ of Massachusetts - Lowell
	Young P T, NRR/PRTB, 415-4094
References
	50-223/09-01 50-223/09-01
	Download: ML092390145 (28)
	v • d • e

September 9, 2009 Dr. Gunter Kegel, Director Nuclear Radiation Laboratory University of Massachusetts Lowell One University Avenue Lowell, MA 01854

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-223/OL-09-01, UNIVERSITY OF MASSACHUSETTS - LOWELL.

Dear Dr. Kegel:

During the week of August 17, 2009, the NRC administered operator licensing examinations at your University of Massachusetts - Lowell 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. Phillip T. Young at (301) 415-4094 or via internet e-mail Phillip.Young@nrc.gov.

Sincerely,

/RA/

Johnny H. Eads, Jr., Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-223

Enclosures:

1. Initial Examination Report No. 50-223/OL-09-01

2. Written examination with facility comments incorporated cc: without enclosures:(Please see next page)

September 9, 2009 Dr. Gunter Kegel, Director Nuclear Radiation Laboratory University of Massachusetts Lowell One University Avenue Lowell, MA 01854

SUBJECT:

INITIAL EXAMINATION CORPORATE NOTIFICATION LETTER NO. 50-223/OL-09-01, UNIVERSITY OF MASSACHUSETTS - LOWELL.

Dear Dr. Kegel:

During the week of August 17, 2009, the NRC administered operator licensing examinations at your University of Massachusetts - Lowell 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. Phillip T. Young at (301) 415-4094 or via internet e-mail Phillip.Young@nrc.gov.

Sincerely,

/RA/

Johnny H. Eads, Jr., Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-223

Enclosures:

1. Initial Examination Report No. 50-223/OL-09-01

2. Written examination with facility comments incorporated cc: without enclosures: (Please see next page)

DISTRIBUTION w/ encls.:

PUBLIC PRTB r/f RidsNRRDPRPRTA RidsNRRDPRPRTB Facility File (CRevelle) O-07 F-13 ADAMS ACCESSION #: ML092390145 TEMPLATE #:NRR-074 OFFICE PRTB:CE IOLB:LA E

PRTB:BC NAME PYoung:

CRevelle JEads DATE 08/27/2009 09/1/2009 09/9/2009 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY

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 Director Radiation Control Program Department of Public Health 90 Washington Street Dorchester, MA 02121 Nuclear Preparedness Manager Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399 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.:

50-223/OL-09-01 FACILITY DOCKET NO.:

50-223 FACILITY LICENSE NO.:

R-125 FACILITY:

University of Massachusetts - Lowell EXAMINATION DATES:

August 18 - 19, 2009 SUBMITTED BY:

Phillip T. Young, Chief Examiner Date

SUMMARY

During the week of August 17, 2009, the NRC administered operator licensing examinations to one Reactor Operator and two Senior Operator candidates. All applicants passed all portions of the examination REPORT DETAILS

1.

Examiners:

Phillip T. Young, Chief Examiner, NRC

2.

Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 1/0 0/0 1/0 Operating Tests 1/0 2/0 3/0 Overall 1/0 2/0 3/0

3.

Exit Meeting:

Phillip T. Young, Chief Examiner, NRC Mr. Leo Bobek, Reactor Supervisor, University of Massachusetts - Lowell Thomas Regan, Reactor Engineer, University of Massachusetts - Lowell At the conclusion of the site visit, the examiner met with representatives of the facility staff to discuss the results of the examinations. The examiner thanked the facility for their support of the examination. The facility stated that they would submit comments on the written examination, and these comments have been incorporated into the examination attached to this report.

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

University of Massachusetts - Lowell REACTOR TYPE:

GE - Pool DATE ADMINISTERED: August 18, 2009 REGION:

I CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

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

% of Category

% of Candidates Category Value Total Score Value Category 20.00 33.3 A. Reactor Theory, Thermodynamics and Facility Operating Characteristics 21.00 33.3 B. Normal and Emergency Operating Procedures and Radiological Controls 23.00 33.3 C. Facility and Radiation Monitoring Systems 64.00 TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

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.

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

If you are observed in this area while the examination is still in progress, your license may be denied or revoked.

Section A - Reactor Theory, Thermo & Facility Operating Characteristics Question A.001

[1.0 point]

{1.0}

With the reactor on a constant positive period, which ONE of the following power changes will take the SHORTEST time?

a. 5% power, from 1% to 6% power

b. 10% power, from 10% to 20% power

c. 15% power, from 20% to 35% power

d. 20% power, from 40% to 60% power Answer:

A.001 d.

Reference:

[1.0 point]

{2.0}

Which ONE of the following statements describes the subcritical reactor response as Keff approaches unity?

a. A LARGER change in neutron level results from a given change in Keff and a SHORTER period of time is required to reach the equilibrium neutron level for a given change in Keff.

b. A LARGER change in neutron level results from a given change in Keff and a LONGER period of time is required to reach the equilibrium neutron level for a given change in Keff.

c. A SMALLER change in neutron level results from a given change in Keff and a SHORTER period of time is required to reach the equilibrium neutron level for a given change in Keff.

d. A SMALLER change in neutron level results from a given change in Keff and a LONGER period of time is required to reach the equilibrium neutron level for a given change in Keff.

Answer:

A.002 b.

Reference:

Question A.003

[1.0 point]

{3.0}

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

a. Thermal neutrons

b. Fast neutrons

c. Gamma rays

d. X-rays Answer:

A.003 a.

Reference:

Section A - Reactor Theory, Thermo & Facility Operating Characteristics Question A.004

[1.0 point]

{4.0}

The reactor is operating at 500 KW in steady-state and in manual mode. Which one of the following describes the stable reactor period if a control blade drops fully into the core and no operator action is taken?

a. -34 seconds due to the rapid decrease in prompt neutrons.

b. -34 seconds due to the rapid decay of the short lived delayed neutron precursors.

c. -80 seconds due to the slowing down length of prompt neutrons.

d. -80 seconds due to the decay half life of the long lived delayed neutron precursors.

Answer:

A.004 d.

Reference:

The amount of reactivity inserted by the blade is much larger than beta; therefore, maximum stable negative period of -80 seconds results.

Question A.005

[1.0 point]

{5.0}

The following data was obtained during a reactor fuel load.

No. of Elements Detector A (cps) 0 20 8

28 16 30 24 32 32 42 40 80 Which one of the following represents the number of fuel elements predicted to reach criticality?

Graph paper provided at the end of the Section A questions.

a. 48

b. 52

c. 56

d. 60 Answer:

A.005 a.

Reference:

Section A - Reactor Theory, Thermo & Facility Operating Characteristics Question A.006

[1.0 point]

{6.0}

What is the kinetic energy range of a thermal neutron?

a. > 1 MeV

b. 100 KeV - 1 MeV

c. 1 eV - 100 KeV

d. < 1 eV Answer:

A.06

d.

Reference:

Question A.007

[1.0 point]

{7.0}

A reactor with an initial population of 24000 neutrons is operating with Keff = 1.01. Of the CHANGE in population from the current generation to the next generation, how many are prompt neutrons?

a. 25

b. 238

c. 2500

d. 24240 Answer:

A.007 b.

Reference:

24000 x 1.01 = 24240 neutrons in next generation 24240 - 24000 = 240 neutrons added 240 neutrons added -

0.7% delayed neutron fraction = 238 prompt neutrons added Question A.008

[1.0 point]

{8.0}

Which ONE of the following is the correct reason that delayed neutrons enhance control of the reactor?

a. There are more delayed neutrons than prompt neutrons.

b. Delayed neutrons take longer to reach thermal equilibrium.

c. Delayed neutrons increase the average neutron generation time.

d. Delayed neutrons are born at higher energies than prompt neutrons and therefore have a greater effect.

Answer:

A.008 c.

Reference:

Section A - Reactor Theory, Thermo & Facility Operating Characteristics Question A.009

[1.0 point]

{9.0}

Regulating rod worth for a reactor is 0.001 K/K/inch. Moderator temperature INCREASES by 9°F, and the regulating rod moves 41/2 inches inward to compensate. The moderator temperature coefficient Tmod is

a. +5 x 10-4 K/K/°F

b. -5 x 10-4 K/K/°F

c. +2 x 10-5 K/K/°F

d. -2 x 10-5 K/K/°F Answer:

A.009 a.

Reference:

[1.0 point]

{10.0}

INELASTIC SCATTERING is the process by which a neutron collides with a nucleus and

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

b. recoils with the same kinetic energy it had prior to the collision.

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

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

Answer:

A.010 c.

Reference:

[1.0 point]

{11.0}

Excess reactivity is the amount of reactivity

a. associated with burnable poisons.

b. needed to achieve prompt criticality.

c. available above that which is required to keep the reactor critical.

d. available below that which is required to make the reactor subcritical.

Answer:

A.011 c.

Reference:

Section A - Reactor Theory, Thermo & Facility Operating Characteristics Question A.012

[1.0 point]

{12.0}

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

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

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

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

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

Answer:

A.012 d.

Reference:

Burn, R. R., Introduction or Nuclear Reactor Operations, June 1984, § 8.4, pp. 8-12 to 8-19.

Question A.013

[1.0 point]

{13.0}

Core excess reactivity changes with

a. fuel element burnup.

b. control rod height.

c. neutron energy level.

d. reactor power level.

Answer:

A.013 a.

Reference:

[1.0 point]

{14.0}

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

a. Rod Speed

b. Reactor Power

c. Flux Shape

d. Fuel Loading Answer:

A.014 c.

Reference:

Burn, R. R., Introduction or Nuclear Reactor Operations, June 1984, § 7.2, p. 7-4.

Section A - Reactor Theory, Thermo & Facility Operating Characteristics Question A.015

[1.0 point]

{15.0}

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

a. U233

b. U235

c. U238

d. Pu239 Answer:

A.015 c.

Reference:

Question A.016

[1.0 point]

{16.0}

Given:

Primary Flow rate through heat exchanger = 1400 GPM; Secondary Flow rate through heat exchanger = 1200 GPM; TPrimary = 13°F Secondary INLET temperature is 73°F.

Which one of the following should be the secondary OUTLET temperature?

a. 58°F

b. 62°F

c. 84°F

d. 88°F Answer:

A.016 d.

Reference:

Tsec = 1400/1200

13°F = 7/6

13 = 15.2°F TOUT = 73 + 15.2 = 88.2 Question A.017

[1.0 point]

{17.0}

Which ONE of the following is the cause of the indicated power to stabilize several hours following a reactor scram. (Assume source inserted in core, source range instrument on and reading 3 counts/second and no reactivity changes, i.e. no temperature changes, no fuel movement, no experiments added, etc.)

a. Subcritical multiplication of source neutrons.

b. Gamma saturation of the source range detector.

c. Neutron activation of the Source Range Detector.

d. Continuing decay of the shortest lived delayed neutron precursor.

Answer:

A.017 a.

Reference:

Burn, R. R., Introduction or Nuclear Reactor Operations, June 1984, § 5.3

Section A - Reactor Theory, Thermo & Facility Operating Characteristics Question A.018

[1.0 point]

{18.0}

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

a. 25

b. 33

c. 41

d. 50 Answer:

A.018 b.

Reference:

P = P0 et/ ln(P/P0) = t/ = t/(ln(P/P0) = 100/ln(20) = 33.381 Question A.019

[1.0 point]

{19.0}

As primary coolant (moderator) temperature increases, control rod worth

a. decreases due to lower reflector efficiency.

b. increases due to the increase in thermal diffusion length.

c. decreases due to higher neutron absorption in the moderator.

d. remains the same due to constant poison cross-section of the control rods.

Answer:

A.019 b.

Reference:

Question A.020

[1.0 point]

{20.0}

The Chief Reactor Operator tells you that the reactor is shutdown with a Shutdown Margin of 12.0%.

Nuclear Instrumentation reads 100 cpm. The CRO inserts an experiment into the core and counts increase to 200 cpm. What is the resulting Keff for the core?

a. 0.920

b. 0.946

c. 0.973

d. 1.000 Answer:

A.020 b

Reference:

Keff(I) = 1/(1+SDM) = 1/1.120 = 0.892857 CR(I)[1 - Keff(I)] = CR(f)[1 - Keff(f)]

100(1 - 0.893) = 200 (1 - x) 1/2(1 - 0.893)= 1 - x 1 - x = 0.0535714; x = 1 - 0.0535714 = 0.94643

Section B - Normal, Emergency and Radiological Control Procedures Question B.001

[1.0 point]

{1.0}

Upon discovery that no Area Radiation Monitors on the experimental levels are operable, you may continue steady-state operation providing you replace the inoperable monitor with a portable gamma-sensitive monitor having its own alarm within ________ discovery of the condition.

a. 15 minutes

b. 30 minutes

c. an hour

d. eight hours Answer:

B.001 a.

Reference:

Technical Specifications 3.4.3.

Question B.002

[1.0 point]

{2.0}

Which ONE of the following is the lowest level of permission required to restart the reactor following violation of a Safety Limit?

a. Licensed Senior Operator on call.

b. Reactor Supervisor

c. Facility Director

d. Nuclear Regulatory Commission Answer:

B.002 d.

Reference:

Technical Specification 6.5 1st ¶ Question B.003

[1.0 point]

{3.0}

You (a licensed Reactor Operator) and a Senior Reactor Operator (SRO) are operating the reactor on the weekend. No one else is available. In order to meet Technical Specifications requirements if you are on the console the SRO must be

a. within the reactor containment.

b. within the confines of the North Campus.

c. within 15 minutes walk of the reactor facility.

d. within the reactor containment or the Pinanski Building.

Answer:

B.003 d.

Reference:

T.S. 6.0

Section B Normal, Emergency and Radiological Control Procedures Question B.004

[1.0 point]

{4.0}

Which ONE of the following types of experiments is required to be doubly encapsulated?

Experiments which contain

a. explosive materials.

b. corrosive materials.

c. fissionable materials.

d. compounds highly reactive with water.

Answer:

B.004 b.

Requalification Plan, Sect. 3.3 Question B.008

[1.0 point]

{8.0}

You are the reactor operator during operations at 90% power. Workers are preparing to secure the containment emergency exhaust system for maintenance. Which one of the following statements is applicable for this condition?

a. The reactor may continue running with all isolation valves closed.

b. The reactor must be shutdown prior to taking out the emergency exhaust system.

c. The Reactor Supervisor may authorize reactor operation with the system out of service.

d. The Radiation Safety Officer must approve reactor operation with the system out of service.

Answer:

B.008 b.

Reference:

T.S. 3.5

Section B Normal, Emergency and Radiological Control Procedures Question B.009

[1.0 point]

{9.0}

Which one of the following is the definition for Annual Limit on Intake (ALI)?

a. 10 CFR 20 derived limit, based on a Committed Effective Dose Equivalent of 5 rems whole body or 50 rems to any individual organ, for the amount of radioactive material inhaled or ingested in a year by an adult worker.

b. The effluent concentration of a radionuclide in air which, if inhaled continuously over a year, would result in a total effective dose equivalent of 50 millirem for noble gases.

c. The concentration of a radionuclide in air which, if inhaled by an adult worker for a year, results in a total effective dose equivalent of 100 millirem.

d. Projected dose commitment values to individuals that warrant protective action following a release of radioactive material.

Answer:

B.009 a.

Emergency Plan Chapter 2.0, Definitions, § 2.11.

Question B.013

[1.0 point]

{13.0}

Which ONE of the following is the definition of a CHANNEL TEST?

a. an adjustment of the channel such that it output corresponds with acceptable accuracy to known values of the parameter which the channel measures. This shall encompass the entire channel, including equipment actuation, alarm, or trip.

b. a qualitative verification of acceptable performance by observation of channel behavior.

This verification, where possible, shall include a comparison of the channel with other Independent channels or systems measuring the same variable.

c. the combination of sensor, line, amplifier, and output devices which are connected for the purpose of measuring the value of a parameter.

d. the introduction of a signal into the channel for verification that it is operable.

Answer:

B.013 d.

Reference:

Technical Specifications §§ 1.2, 1.3, 1.4 and 1.5.

Section B Normal, Emergency and Radiological Control Procedures Question B.014

[1.0 point]

{14.0}

Consider two point sources, each having the SAME curie strength. Source As gammas have an energy of 0.5 MeV, while Source Bs gammas have an energy of 1.0 MeV. Using a Geiger-Müller detector the reading from source B will be (NOTE: Ignore detector efficiency.)

a. four times that of source A.

b. twice that of source A.

c. the same.

d. half that of source A.

Answer:

B.14

c.

Reference:

Standard NRC Health Physics Question.

Question B.015

[1.0 point]

{15.0}

While working on an experiment, you receive the following radiation doses: 100 mrem (), 25 mrem (), and 5 mrem (thermal neutrons). Which ONE of the following is your total dose?

a. 175 mrem

b. 155 mrem

c. 145 mrem

d. 130 mrem Answer:

B.015 d.

Reference:

A rem is a rem is a rem.

Question B.016

[1.0 point]

{16.0}

After a reactor scram, neither you nor the SRO is able to determine the cause of the scram.

What is the minimum level of management who may authorize restart of the reactor under this condition?

a. The Senior Reactor Operator on his/her own.

b. The Reactor Supervisor after consultation with the Reactor Director.

c. The Chief Reactor Operator after consultation with the Reactor Supervisor.

d. The Senior Reactor Operator on consultation with either the Chief Reactor Operator or the Reactor Supervisor.

Answer:

B.016 d.

Reference:

RO-7, Reactor Shutdown, § 7.32.4. pp. RO7-2 & 3.

Section B - Normal, Emergency and Radiological Control Procedures Question B.017

[1.0 point]

{17.0}

Which ONE of the following classifications for an emergency is not credible for the U. Mass.-

Lowell reactor? (Note: Items are listed alphabetically, NOT in order of severity!)

a. Alert

b. Non-Reactor Safety Related Event

c. Notification of Unusual Event

d. Site Area Emergency Answer:

B.017 d.

Reference:

Emergency Plan §§ 4.0 through 4.5.

Question B.018

[1.0 point]

{18.0}

When taking logs readings, you must inform the Chief Reactor Operator when you notice a discrepancy between power channels greater than

a. 2%

b. 3%

c. 4%

d. 5%

Answer:

B.018 b.

Reference:

Standing Order #4, Sequence of Operations during Startup and at Rated Power.

Question B.019

[1.0 point]

{19.0}

An experiment irradiated in the pool reads 50mr/hr at 2 feet below the pool surface and 100 mr/hr at 1 foot below the pool surface. You decide to place the experiment at 20 feet below the surface of the pool. Based on the attenuation you noted between the 2 foot and 1 foot levels, you would expect the shielding due to 20 feet of water to reduce the dose by a factor of approximately (Note: Ignore dose decrease due to distance.)

a. 1000

b. 10,000

c. 100,000

d. 1,000,000 Answer:

B.019 d.

Reference:

220 = 1,048,756 1,000,000

Section B Normal, Emergency and Radiological Control Procedures Question B.020

[2.0 points 0.5 each]

{21.0}

Match the general area radiation levels listed in column A with the corresponding type of radiation area listed in column B. (Note: Only one answer for each item in column A. Items from column B may be used more than once or not at all.)

Column A Column B

a. 2 mRem/hr.

1. High Radiation Area

b. 65 mRem/hr.

2. Radiation Area

c. 203 mRem/hr.

3. Unrestricted Area

d. 520 mRem/hr.

4. Very High Radiation Area Answer:

B.020 a. = 3;

b. = 2;

c. = 1;

d. = 4 1

SAR § Question C.006

[1.0 point]

{6.0}

Which ONE of the following correctly describes the manual operation of Valve A in the ventilation system? The valve is opened

a. by air acting on a piston against a spring. The valve is closed by opening a quick release valve which bleeds air off of an auxiliary piston which in turn opens a port bleeding air off the main piston.

b. by air acting on a piston against a spring. The valve is closed by opening a quick release valve which bleeds off air from the piston.

c. by spring pressure. The valve is closed by an explosive blast of high pressure air from an accumulator.

d. and closed via an air motor, using higher pressure air from an accumulator for quick closure.

Answer:

C.006 a.

Reference:

SAR figure 3.7, page 3-16

Section C - Facility and Radiation Monitoring Systems Question C.007

[1.0 point]

{7.0}

Which ONE of the following correctly describes the operation of the RTD (temperature detector used for the temperature recorder).

a. A precision wound resistor, which changes resistance proportional to temperature.

b. A precision wound inductor, which changes inductance proportional to temperature.

c. A bimetallic junction, which generates a potential (micro-volt range) proportional to temperature.

d. A bimetallic strip which because of differing thermal expansion coefficients causes the strip to bend proportional to temperature.

Answer:

C.007 a

Reference:

SAR § 4.4.17.5 Question C.008

[1.0 point]

{8.0}

Which ONE of the following correctly describes how a compensated ion chamber detects neutrons? A neutron interacts with the

a. B10 lining of the tube.

b. U235 lining of the tube.

c. N2 gas which fills the tube.

d. BF3 gas which fills the tube.

Answer:

C.008 a.

Reference:

Standard NRC Question Question C.009

[2.0 points, 0.5 each]

{10.0}

The liquid radwaste system divides cooling water into four sections for the purpose of performance checks/monitoring. Match the cooling water sections in Column A with its appropriate performance checks from Column B. Note that some performance checks in Column B may be used more than once or not at all.

Column A Column B

a. Pool

1. External gamma monitor and delayed neutron detector.

b. Primary Loop

2. Continuous conductivity measurements.

c. Cleanup Loop

3. Periodic sampling for quality and presence of radionuclides.

d. Secondary Loop

4. Daily sampling for Na24.

Answer:

C.009 a. = 3;

b. = 1;

c. = 2;

d. = 4

Reference:

SAR § 7.2.4, Page 7-5

Section C - Facility and Radiation Monitoring Systems Question C.010

[1.0 point]

{11.0}

Which ONE of the following communications systems allows all stations to talk to each other simultaneously?

a. phone system

b. main intercom system

c. public address system

d. sound powered headset system Answer:

C.010 c.

Reference:

UMLR Safety Analysis Report, § 6.3.1, Communications System Question C.011

[1.0 point]

{12.0}

Which ONE of the following loads is supplied from the air compressor located on the intermediate level inside the reactor building?

a. Air lock doors.

b. Thermal column door.

c. Pneumatic tube system.

d. Containment isolation valves.

Answer:

C.011 a.

Reference:

ULR SAR, § 6.2, p 6-5 Question C.012

[1.0 point]

{13.0}

Which ONE of the following is the type of startup neutron source use for your reactor?

a. Californium

b. Plutonium-Beryllium

c. Neptunium-Antimony

d. Americium-Beryllium Answer:

C.012 d.

Reference:

SAR § 4.1.4, page 4-6

Section C - Facility and Radiation Monitoring Systems Question C.013

[1.0 point]

{14.0}

Which ONE of the following describes how the signal for regulating rod position indication is generated?

a. A tachometer that counts the revolutions of the lead screw.

b. A series of magnetic switches which respond to lead screw position.

c. A mechanical position transmitter that is chain driven by the drive motor.

d. A series of limit switches that are actuated by the ball bearing screw assembly.

Answer:

C.013 c.

Reference:

ULR SAR, §4.1.8, p 4-11; Figures 4.6 and 4.7. C.14 Question C.014

[1.0 point]

{15.0}

The purpose of the filter in the reactor pool cleanup system is to

a. prevent demineralizer resin fines from entering the pool.

b. prevent larger particles from plugging the demineralizer resin.

c. remove particles that could clog the cleanup system pump seals.

d. remove crud from the coolant limiting the radiation levels associated with the demineralizer.

Answer:

C.014 a.

Reference:

ULR SAR, §4.2.5, p 4-29.

Question C.015

[1.0 point]

{16.0}

Which ONE of the following is an "ELECTRONIC" scram?

a. High flux

b. Seismic

c. Low pool water level

d. High temperature primary coolant Answer:

C.015 a.

Reference:

ULR SAR, §4.4.15.2, p 4-74.

Section C - Facility and Radiation Monitoring Systems Question C.016

[2.0 points, 0.33 each]

{18.0}

Using the drawing of the primary system provided, if the reactor is in position 1, with the coolant system in the cross-stall mode (preferred line-up). Identify the position of the valves listed (Open, Closed, Throttled).

a. P-1

b. P-2

c. P-3

d. P-4

e. P-9

f. P-11 Answer:

C.016 a. = Open;

b. = Open;

c. = Closed;

d. = Closed;

e. = Open;

f. = Throttled

Reference:

SAR § 4.2.2, also, Training Handout section on Primary System, and drawing.

Question C.017

[2.0 points, 1/4 each]

{20.0}

Using the drawing of the ventilation system provided, give the status of the following valves (OPEN, SHUT) and fans (ON, OFF) upon receipt of a GRVS signal.

a. Valve A

b. Valve B

c. Valve C

d. Fans 3 through 6

e. Valve E

f. Valve F

g. Fan EF-12

h. Fan AC-2 Answer:

C.017 a. = SHUT;

b. = SHUT;

c. = SHUT;

d. = OFF;

e. = SHUT;

f. = OPEN;

g. = OFF;

h. = ON

U. Mass. Lowell Reactor, FSAR, § 3.4.2.2

ML092390145

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SUBJECT:

Dear Dr. Kegel:

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