Text

Examination Report Letter No. 50-288/OL-25-01, Reed College
	ML24255A084
Person / Time
Site:	Reed College
Issue date:	11/14/2024
From:	Travis Tate; NRC/NRR/DANU/UNPO
To:	Newhouse J; Reed College
References
	50-288/OL-25-01
	Download: ML24255A084 (1)
	v • d • e

Jerry Newhouse, Director Reed College Reed Research Reactor 3203 Southeast Woodstock Boulevard Portland, OR 97202-8199

SUBJECT:

EXAMINATION REPORT NO. 50-288/OL-25-01, REED COLLEGE

Dear Jerry Newhouse:

During the week of October 21, 2024, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Reed College research reactor. The examination was 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 component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC website 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 Michele DeSouza at 301-415-0747 or via email at Michele.DeSouza@nrc.gov.

Sincerely, Travis L. Tate, Chief Non-Power Production and Utilization Facility Oversight Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation Docket No. 50-288

Enclosures:

1. Examination Report No. 50-288/OL-25-01

2. Written examination cc: w/enclosures to GovDelivery Subscribers November 14, 2024 Signed by Tate, Travis on 11/14/24

ML24255A084 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME MDeSouza NJones TTate DATE 11/14/2024 11/14/2024 11/14/2024 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:

50-288/25-01 FACILITY DOCKET NO.:

50-288 FACILITY LICENSE NO.:

R-112 FACILITY:

Reed Research Reactor EXAMINATION DATES:

Week of October 21, 2024 SUBMITTED BY:

SUMMARY

During the week of 10/21/2024, the NRC administered operator licensing examinations to one Reactor Operator (RO), two RO written Category A retakes, and two Senior Reactor Operator-Upgrade (SROU) retake candidates. All candidates passed all applicable portions of the examinations.

REPORT DETAILS 1.

Examiner:

Michele DeSouza, Chief Examiner, NRC 2.

Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 3/0 NA 3/0 Operating Tests 1/0 2/0 3/0 Overall 3/0 2/0 5/0 3.

Exit Meeting:

Jerry Newhouse, Director, Reed Research Reactor Toria Ellis, Reactor Operations Manager, Reed Research Reactor Michele DeSouza, Chief Examiner, NRC Prior to administration of the written examination, based on facility comments, adjustments were accepted. Comments provided corrections and additional clarity to questions/answers and identified where changes were appropriate based on current facility conditions.

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

Michele DeSouza 10/28/2024 Name, Chief Examiner Date

Enclosure 2 Reed Research Reactor Operator Licensing Examination Week of October 21, 2024

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

Reed Research Reactor REACTOR TYPE:

TRIGA DATE ADMINISTERED:

10/23/2024 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 and a 70% overall is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

CATEGORY VALUE

% OF TOTAL CANDIDATE'S SCORE

% OF CATEGORY VALUE CATEGORY 20.00 33.0 A. REACTOR THEORY, THERMODYNAMICS, AND FACILITY OPERATING CHARACTERISTICS 20.00 33.0 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.0 C. FACILITY AND RADIATION MONITORING SYSTEMS 60.00 TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

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

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

A01 a b c d ___

A02 a b c d ___

A03 a b c d ___

A04 a b c d ___

A05 a b c d ___

A06 a b c d ___

A07 a b c d ___

A08 a b c d ___

A09 a b c d ___

A10 a b c d ___

A11 a b c d ___

A12 a b c d ___

A13 a ________ b _______ c ________ d ________

(0.25 each)

A14 a b c d ___

A15 a ________ b ________ c ________ d ________ (0.25 each)

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 ________

(0.25 each)

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

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

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

B01 a b c d ___

B02 a b c d ___

B03 a b c d ___

B04 a b c d ___

B05 a b c d ___

B06 a b c d ___

B07 a b c d ___

B08 a b c d ___

B09 a ________ b ________ c ________ d ________

(0.25 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 CATEGORY B *****)

Category C: Facility and Radiation Monitoring Systems A N S W E R S H E E T Multiple Choice (Circle or X your choice)

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

C01 a b c d ___

C02 a b c d ___

C03 a b c d ___

C04 a b c d ___

C05 a b c d ___

C06 a b c d ___

C07 a b c d ___

C08 a b c d ___

C09 a b c d ___

C10 a b c d ___

C11 a b c d ___

C12 a b c d ___

C13 a b c d ___

C14 a b c d ___

C15 a b c d ___

C16 a b c d ___

C17 a b c d ___

C18 a b c d ___

C19 a b c d ___

C20 a b c d ___

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

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

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

1.

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

2.

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

3.

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

4.

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

5.

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

6.

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

7.

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

8.

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

9.

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

10.

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

11.

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

12.

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

EQUATION SHEET

=

+

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

°F = 9/5 °C + 32 1 gal (H2O) 8 lb

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

2 2

max

P 1

sec 1.0

eff

te P

P 0

eff K

S S

SCR

1

sec 10 1

4

eff SUR 06 26

2 1

1 1

2 1

eff eff K

CR K

CR

2 2

1 1

CR CR 2

1 1

1 eff eff K

K M

1 2

1 1

CR CR K

M eff

)

(

0 10 t

SUR P

P

0 1

P P

eff eff K

K SDM

1

2 1

1 2

eff eff eff eff K

K K

K

693

.0 2

1 T

eff eff K

K 1

t e

DR DR

0

2 6

R n

E Ci DR 2

2 2

2 1

1 d

DR d

DR

1 2

2 2

Peak Peak

T UA H

m T

c m

Q P

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

[1.0 point]

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

a.

Nitrogen-16.

b.

Argon-41.

c.

Iodine-131.

d. Xenon-135.

QUESTION A.02

[1.0 point]

The product of number density and microscopic cross section of an element is defined as:

a.

Macroscopic Cross Section.

b.

Thermal Cross Section.

c.

Mean Free Path.

d.

Decay Constant.

QUESTION A.03

[1.0 point]

Which ONE of the following conditions would INCREASE the shutdown margin of a reactor?

a.

Depletion of Uranium fuel.

b.

Depletion of a burnable poison.

c.

Inserting an experiment adding positive reactivity.

d. Lowering moderator temperature if the moderator temperature coefficient is negative.

QUESTION A.04

[1.0 point]

Which factors of the six-factor formula are affected by an INCREASE in core moderator temperature and how are they affected? Lf - Fast non-leakage probability Lt - Thermal non-leakage probability - Fast fission factor p - Resonance escape probability - Reproduction factor f - Thermal utilization factor a.

Lf, Lt, p, f b.

, Lf, Lt, p.

c.

, Lf, Lt, p,, f d.

, Lf, Lt, p,, f

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.05

[1.0 point]

A radioactive material was removed from a reactor core, it reads 150.00 rem/hour. Forty-eight hours later, it reads 5.00 rem/hour. What is the materials half-life?

a.

9.78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months b.

22.14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months c.

40.13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months d.

56.11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months QUESTION A.06

[1.0 point]

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

a. Doppler broadening effect

b. Increases density of pool water

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

d. Sudden burn-up of Xenon in the fuel element QUESTION A.07

[1.0 point]

A reactor with k-eff = 0.8 contributes 1000 neutrons in the first generation. Changing from first generation to third generation, what is the total number of neutrons produced in all three generations?

a.

1940 neutrons b.

2040 neutrons c.

2440 neutrons d.

3640 neutrons

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

[1.0 point]

A reactor is shutdown with a shutdown margin of 2.5% k/k. If control rods are withdrawn until the count rate increases by a factor of 5, and the reactor is still subcritical, what is the new keff?

a.

0.990 b.

0.992 c.

0.995 d.

0.998 QUESTION A.09

[1.0 point]

Which ONE of the following is the definition of excess reactivity? The amount of reactivity ______.

a.

needed to achieve prompt criticality.

b.

associated with burnable poisons.

c.

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

d.

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

QUESTION A.10

[1.0 point]

Which ONE of the following factors is MOST affected by an increase in fission product poisoning?

a.

fast fission factor b.

reproduction factor c.

thermal utilization factor d.

resonance escape probability factor QUESTION A.11

[1.0 point]

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

a.

Rod speed b.

Flux shape in the fuel core c.

Reactor power d.

Fuel temperature

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

[1.0 point]

When the reactor is exactly critical, which ONE of the following is the MINIMUM reactivity that must be added to produce PROMPT criticality?

a.

0.005 k/k.

b.

0.065 k/k.

c.

eff.

d.

2 eff.

QUESTION A.13

[1.0 point, 0.25 each]

The listed isotopes are potential daughter products due to the radioactive decay of 35Br87.

Identify the type of decay to produce each of the isotopes: Alpha, Beta+, Beta-, Gamma or Neutron emission (Answers may be used once, more than once or not at all).

a. 33As83

b. 35Br86

c. 35Br87

d. 36Kr87 QUESTION A.14

[1.0 point]

In a subcritical reactor, k-eff is increased from 0.895 to 0.913 Which one of the following is the amount of reactivity that was added to the core?

a.

1.94 %k/k b.

2.21 %k/k c.

4.33 %k/k d.

6.83 %k/k

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.15

[1.0 point, 0.25 each]

Identify each one of the following isotopes as either a FERTILE or FISSILE material. (Answers may be used once, more than once, or not at all) a.

Thorium-232 b.

Uranium-235 c.

Uranium-238 d.

Plutonium-239 QUESTION A.16

[1.0 point]

Which ONE of the following is the expected stable neutron count rate, given a source strength of 690 neutrons per second (N/sec) and a multiplication factor of 0.3?

a.

330 neutrons/second b.

414 neutrons/second c.

757 neutrons/second d.

986 neutrons/second QUESTION A.17

[1.0 point]

Which ONE of the following is the definition for Differential Control Rod Worth? The reactivity a.

Due to control rod position (K/K).

b.

Change per unit of rod motion (K/K/in).

c.

Due to the difference in rod speed (K/K/in/min).

d.

Still available for shutdown after control rod withdrawal.

QUESTION A.18

[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.

From 1 Watt to 5 Watts b.

From 10 Watts to 30 Watts c.

From 10 kWatts to 20 kWatts d.

From 100 kWatts to 150 kWatts

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

[1.0 point]

Which ONE of the following is defined as the balance between absorption of thermal neutrons by the fuel and production of fast neutrons from thermal fission?

a.

Utilization factor b.

Reproduction factor c.

Infinite Multiplication factor d.

Effective Multiplication factor QUESTION A.20

[1.0 point, 0.25 each]

Identify each one of the following as either an ABSORBER (A), POISON (P), or REFLECTOR (R). (Answers may be used once, more than once, or not at all) a.

Beryllium b.

Graphite c.

Boron-10 d.

Xenon-135

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

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

[1.0 point]

A radioactive source currently has an activity of 5 Curies. The activity of the source 25 years ago was 300 Curies. What is the half-life of the radioactive source?

a.

4.2 years b.

5 years c.

7.5 years

d. 8 years QUESTION B.02

[1.0 point]

Which ONE of the following is NOT an action that should occur if an area in the reactor bay exceeds 100 mrem/hour at 30 cm?

a. Evacuate the area.

b. Notify the Radiation Safety Officer.

c. Post it as a Very High Radiation Area.

d. If the radiation area is caused by a sample, shield the sample.

QUESTION B.03

[1.0 point]

A survey instrument with a window probe is used to measure the beta-gamma dose rate from an irradiated experiment. The dose rate is 170 mrem/hour with the window open and 60 mrem/hour with the window closed. What is the gamma dose rate?

a.

60 mrem/hour b.

110 mrem/hour c.

170 mrem/hour d.

230 mrem/hour QUESTION B.04

[1.0 point]

In accordance with 10 CFR 20, which ONE of the following is counted as part of the 50 REM annual limit to any individual organ or tissue other than the lens of the eye?

a.

Shallow dose equivalent b.

Effective dose equivalent c.

Committed dose equivalent d.

Total effective dose equivalent

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

[1.0 point]

An individual receives 75 mrem of Beta, 25 mrem of gamma, and 5 mrem of neutron (unknown energy) radiation. Which ONE of the following is the total dose the individual received?

a.

105 mrem b.

130 mrem c.

150 mrem d.

210 mrem QUESTION B.06

[1.0 point]

Which ONE of the following conditions requires the US Nuclear Regulatory Commission approval prior to implementation of the changes?

a.

Minor changes of Administrative Procedures b.

Replace the primary coolant pump with an identical pump c.

Add responsibilities to the Radiation Safety Officer in the operational procedures d.

Minor changes to reduce the Reed Research Operations Committee members from three persons to two persons QUESTION B.07

[1.0 point]

Which ONE of the following occurrence reports shall be made by telephone or other communication systems to the US Nuclear Regulatory Commission Headquarters Operations Center within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ?

a.

Unscheduled shutdown of the reactor from a loss of power event b.

Abnormal and significant degradation in confinement boundary c.

The total amount of radioactive effluents and solid waste packaged d.

Summary of exposures received by facility personnel where exposures are greater than 25 percent of that allowed.

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

[1.0 point]

In accordance with 10 CFR 55, which ONE of the following is the frequency that licensed reactor operators are required to pass a comprehensive operating test?

a.

Biennially b.

Once every six years c.

Annually d.

For initial qualification only QUESTION B.09

[1.0 point, 0.25 each]

Identify the PRIMARY source (irradiation of AIR, irradiation of WATER, irradiation of reactor STRUCTURE or FISSION product) for EACH of the following radioisotopes.

a.

Argon-41 b.

Aluminum-28 c.

Nitrogen-16 d.

Iodine-135 QUESTION B.10

[1.0 point]

Which ONE of the following is NOT an expected action to be performed prior to becoming the Operator of Record?

a.

Review the Procedure Changes and Notifications (PCN) log for any changes.

b.

Review all requests for authorization to use radiation or radioactive material for the day c.

Review the days Startup Checklist (even if you performed part of the Startup Checklist) and anything else on the Daily Clipboard.

d.

Review the Main Logbook for changes during the last 30 days or back to the last time you reviewed the Main Logbook, whichever is more recent.

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.11

[1.0 point]

In accordance with the Reed Research Reactor Emergency Plan, which ONE of the following are NOT always required to be on the Emergency Notification Call List (ENCL)?

a.

Director b.

Radiation Safety Officer c.

Reactor Operations Manager d.

Senior Reactor Operator of Record QUESTION B.12

[1.0 point]

Which ONE of the following activities does NOT require the use of personal dosimetry?

a.

An individual conducting inventory of beta emitting sources.

b.

An individual disposing of inorganic H-3 insingle packages.

c.

An individual performing an experiment with millicurie level sources.

d.

An individual performing janitorial services near a radiation area.

QUESTION B.13

[1.0 point]

Which ONE of the following types of experiments are NOT permitted in the Reed Research Reactor?

a.

A secured experiment containing 10 mg of nitroglycerin b.

A movable experiment containing 25 mg of hydrochloric acid c.

An unsecured experiment containing material with a reactivity worth of $2.00

d. An in-tank experiment containing material with a boiling point above 54.4oC QUESTION B.14

[1.0 point]

In accordance with Reed Emergency Plan, which ONE of the following roles is responsible for establishing reentry requirements after an emergency evacuation?

a.

Dean, Reed College b.

Emergency Coordinator c.

Radiation Safety Officer d.

Reactor Operator

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

[1.0 point]

In accordance with 10 CFR 55.53, if a licensed operator has not actively performed functions of an operator, the licensee may not resume licensed activities until a MINIMUM of ______ hours has been completed under the instruction of an operator or senior operator, as appropriate.

a.

4 b.

6 c.

8 d.

10 QUESTION B.16

[1.0 point]

In accordance with Reed Research Reactor emergency plan, what emergency classification is a bomb located in the reactor facility?

a.

Alert b.

Notification of unusual event c.

Site Area Emergency d.

General Emergency QUESTION B.17

[1.0 point]

What is the dose rate at 1 foot given a 2 curie radioactive source results in emission of 150 keV gamma 60% of the time?

a.

90 mRem b.

180 mRem c.

1080 mRem d.

2160 mRem

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

[1.0 point]

Per Reed Research Reactor Technical Specifications, what is the MINIMUM shutdown margin with the most reactive control rod fully withdrawn, in reference core condition?

a.

$0.25 b.

$0.50 c.

$0.75 d.

$1.00 QUESTION B.19

[1.0 point]

In accordance with Reed Research Reactor Technical Specifications, which ONE of the following does NOT require an annual surveillance?

a.

Visual inspection of control rod poison section b.

Linear and percent power channel calibration c.

Visual inspection of control rod drives d.

Radiation Area Monitor channel calibration QUESTION B.20

[1.0 point]

In accordance with Reed Research Reactor Technical Specifications, which ONE of the following meets the MINIMUM staffing requirement when the reactor is NOT secured?

a.

1 RO in the control room, and the Reactor Operations Manager on call b.

1 SRO in the control room and the Reactor Operations Manager on call c.

1 RO in the control room, 1 SRO on call, and a second person to summon help d.

1 SRO in the control room and 1 SRO on call

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

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

[1.0 point]

Which ONE of the following is the material used for all the primary coolant piping and fittings?

a.

Nickel alloy b.

Carbon steel c.

Stainless steel d.

Aluminum alloy QUESTION C.02

[1.0 point]

Which ONE of the following represents the flow path of the primary coolant system?

a.

Core Heat Exchanger Primary Pump Flow Meter Orifice Filter b.

Core Filter Demineralizer Heat Exchanger Orifice Primary Pump c.

Core Deflector Primary Pump Filter Heat Exchanger Demineralizer d.

Core Primary Pump Heat Exchanger Filter Demineralizer Flow Meter QUESTION C.03

[1.0 point]

Which ONE of the following best describes the reason that fuel elements are spaced so that 33% of the core volume is occupied by water?

a.

To prevent boiling in the core b.

To accommodate future fuel additions c.

To compensate for excess reactivity during transients d.

To protect the Aluminum cladding from heat produced in the core QUESTION C.04

[1.0 point]

A fire in the material handling area of the reactor bay has the possibility of releasing radioactive materials in the form of which ONE of the following?

a.

Vapor b.

Aerosol c.

Radioactive flames d.

Undetectable gas

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

[1.0 point]

Which ONE of the following is the reason the Regulating Rod has a lower rod worth than the Shim or Safety Rods?

a.

Rod movement speed b.

Grid position in the core c.

Difference in cladding material d.

Difference in neutron absorber material QUESTION C.06

[1.0 point]

When the reactor is at full power, which ONE of the following experimental facilities provides an average thermal neutron flux of approximately 1.4x1013n/cm2s?

a.

In-pool b.

Central thimble c.

Rotating specimen rack d.

Pneumatic transfer system QUESTION C.07

[1.0 point]

Which ONE of the following is an indication that the potentiometer balance routine adjustment on the Safety and Shim Rods motor drive systems requires adjustment?

a.

Sparking from the rod down limit switch b.

Control Rod indication light is on in the control room c.

Clicking noise is heard when rods are being withdrawn

d. The motor creeping up and down without a demand signal QUESTION C.08

[1.0 point]

Which ONE of the following represents the MAXIMUM drop time of the control rods from the full withdrawn to the fully inserted position?

a.

0.5 seconds b.

1.0 seconds c.

2.5 seconds

d. 2.6 seconds

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

[1.0 point]

Which ONE of the following provides the main input for automatic demand control on the Regulating Rod?

a.

Linear Channel b.

Pulse Height Analyzer c.

Control Rod Drive Circuit d.

Log Channel Wide Range Period Signal QUESTION C.10

[1.0 point]

Which ONE of the following best describes how background radiation is subtracted in the Continuous Air Monitor (CAM)?

a.

It is subtracted from the preset calculated background radiation within the detector.

b.

Subtracting the readout from one detector sampling background and another detector sampling air near the filter.

c.

A pulse discriminator distinguishes the alpha particles produced from radon, which is subtracted from the total readout.

d.

Subtracting the interactions caused by alpha particles in the outer chamber from the total interactions in the inner chamber of the detector.

QUESTION C.11

[1.0 point]

Which ONE of the following is a safety related feature of the Log Channel?

a. Source interlock

b. High Power Scram

c. Power Level Interlock

d. Reactor Period Scram

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

[1.0 point]

Which ONE of the following is the surveillance requirement for fixed are dosimetry to be exchanged and evaluated?

a.

Monthly b.

Quarterly c.

Annually d.

Biannually QUESTION C.13

[1.0 point]

What instrumentation region is associated with the voltage is such that every primary ion produces an avalanche of secondary ions? This region also cannot differentiate between types of radiation.

a.

Region I, Recombination.

b.

Region II, Ionization.

c.

Region III, Proportional.

d.

Region IV, Geiger-Mueller.

QUESTION C.14

[1.0 point]

Which ONE of the following is the IMMEDIATE action that should be taken if linear power changes by more than 10% of the range when an experiment is leaving the reactor via the rabbit system?

a.

Scram the reactor b.

Return the experiment to the reactor c.

Evacuate the glove box lab room d.

No immediate actions are required, experiment reactivity worth is verified prior to insertion

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

[1.0 point]

Which ONE of the following locations within the Reed Research Reactor facility is MOST likely to have possible contamination?

a.

Control room b.

Lazy Susan insertion sample port c.

Floor entrance to the reactor bay from the control room d.

Rabbit sample preparation table QUESTION C.16

[1.0 point]

Which ONE of the following uses the compensated ion chamber to calculate reactor power signal?

a.

Source Range Channel b.

Multi-Range Linear Channel c.

Wide Range Logarithmic Channel d.

Full Scale Percent Power Channel QUESTION C.17

[1.0 point]

Which ONE of the following components measures the bulk pool temperature of the primary coolant system?

a.

Orifice b.

Thermometer c.

Thermocouple d.

Conductivity Probe QUESTION C.18

[1.0 point]

Which ONE of the following is NOT a function of the primary coolant system?

a.

Maintain core reactivity b.

Dissipate heat from the reactor core c.

Prevent corrosion of reactor systems

d. Provide radiation shielding from the reactor core

Category C: Facility and Radiation Monitoring Systems QUESTION C.19

[1.0 point]

Which ONE of the following is a valid statement when the ventilation system is operating in NORMAL mode?

a.

Air is recirculated to the control room through a HEPA filter.

b.

Air is drawn from the reactor room by an exhaust fan to the exhaust stack.

c.

Input fans are shut down to maintain the reactor bay at a negative pressure in respect to the control room.

d.

Air flow is moved through the reactor room, the control room, and the mechanical equipment room at 1,200 cfm.

QUESTION C.20

[1.0 point]

Which ONE of the following is the primary purpose for the diffuser?

a.

To allow for the decay of N-16.

b.

To reduce the probability of radioactive buildup.

c.

To filter particulates in the water before entering the core.

d.

To accelerate the flow of water being returned to the pool.

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

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

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

d

Burn, Introduction to Nuclear Reactor Operations, Section 5.3, page 5.6 For third generation = n + K*n + K2 n = 1000 + 800 + 640 = 2440 neutrons A.08 Answer:

c

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 5.7.10, page 5-33.

SCR1 = S/(1-K1eff); SCR2 = S/(1-K2eff); 1 = -2.5% K/K= -0.025 K/K K1eff = 1/(1 - 1) = 1/(1 + 0.025) = 0.976; SCR2/SCR1 = S(1-0.976)/S(1-K2eff) =

5 = 0.025/(1-K2eff); 5(1-K2eff) = 0.025; K2eff = 1- 0.025/5 = 0.995 A.09 Answer:

c

Reference:

DOE Handbook, Fundamentals of Nuclear Engineering, Volume 2, Module 2, page 50 A.10 Answer:

c

Reference:

DOE Fundamentals of Reactor Theory, Volume 2, page 34

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

b

Reference:

Burn, Introduction to Nuclear Reactor Operations, Volume 4, Section 7.2 A.12 Answer:

c

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 3.2.4, page 3-12, Section 4.2, page 4-1. Keff = 1 / (1- ) Keff = 1 when = eff, the reactor is "Prompt Critical" A.13 Answer:

a. Alpha b. Neutron c. Gamma d. Beta-

Reference:

Chart of the Nuclides A.14 Answer:

b

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 3.3.4, page 3-23. =

(Keff1-Keff2)/(Keff1*Keff2) = (0.913-0.895)/ (0.913*0.895) = 0.0221 k/k =

DOE Fundamentals of Reactor Theory, Volume 2, Module 3 & 4

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

Reference:

Reed SOP 50 B.13 Answer:

c

Reference:

Reed Research Reactor Technical Specifications 3.6 B.14 Answer:

b

Reference:

Reed Emergency Plan 3.4 B.15 Answer:

b

Reference:

10 CFR 55.53(f)(2)

Reed Research Reactor Technical Specifications 4.5

Reed Research Reactor SAR, Chapter 5

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

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

ML24255A084

Text

SUBJECT:

Dear Jerry Newhouse:

Enclosures:

SUMMARY

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Navigation menu

Search