Text

Examination Report No 50-288/OL-15-02, Reed College
	ML15180A071
Person / Time
Site:	Reed College
Issue date:	08/12/2015
From:	Kevin Hsueh; Research and Test Reactors Branch B
To:	Krahenbuhl M; Reed College
	DeSouza M
Shared Package
ML:15078A300	List: ML15180A071;
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	No. 50-288/OL-15-02
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August 12, 2015 Dr. Melinda Krahenbuhl, Director Reed Reactor Facility 3203 SE Woodstock Blvd.

Portland, OR 97202

SUBJECT:

EXAMINATION REPORT NO. 50-288/OL-15-02, REED COLLEGE

Dear Dr. Krahenbuhl:

During the weeks of May 4 and May 11, 2015, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your Reed College reactor. The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with you and Ms. Christina Barrett, Operations Supervisor, at the conclusion of the examinations.

In accordance with Title 10 of the Code of Federal Regulations, Section 2.390, a copy of this letter and 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 publicly released. Should you have any questions concerning these examinations, please contact Ms. Michele DeSouza at (301) 415-1169 or via e-mail Michele.DeSouza@nrc.gov.

Sincerely,

/RA/

Kevin Hsueh, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-288

Enclosures:

1. Examination Report No. 50-288/OL-15-02

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

Dr. Melinda Krahenbuhl, Director August 12, 2015 Reed Reactor Facility 3203 SE Woodstock Blvd.

Portland, OR 97202

SUBJECT:

EXAMINATION REPORT NO. 50-288/OL-15-02, Reed College

Dear Dr. Krahenbuhl:

During the weeks of May 4 and May 11, 2015, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your Reed College reactor. The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with you and Ms. Christina Barrett, Operations Supervisor, at the conclusion of the examinations.

In accordance with Title 10 of the Code of Federal Regulations, Section 2.390, a copy of this letter and 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 publicly released. Should you have any questions concerning these examinations, please contact Ms. Michele DeSouza at (301) 415-1169 or via e-mail Michele.DeSouza@nrc.gov.

Sincerely,

/RA/

Kevin Hsueh, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-288

Enclosures:

1. Examination Report No. 50-288/OL-15-02

2. Written Examination cc: w/o enclosures: See next page DISTRIBUTION w/ encls.:

PUBLIC RidsNRRDPRPRTA RidsNRRDPRPRTB Facility File (CRevelle) O-07 F-08 ADAMS ACCESSION #: ML15180A071 TEMPLATE #:NRR-079 OFFICE NRR/DPR/PROB:CE NRR/DPR/PROB/OLA NRR/DPRPROB:BC NAME MDeSouza CRevelle KHsueh DATE 06/24/2015 07/30//2015 08/12/2015 OFFICIAL RECORD COPY

Reed College Docket No. 50-288 cc:

Mayor of the City of Portland 1220 Southwest 5th Avenue Portland, OR 97204 Dr. Nigel Nicholson, Dean of Faculty Reed College 3203 SE Woodstock Boulevard Portland, OR 97202-8199 Mr. John Kroger, President Reed College 3203 SE Woodstock Boulevard Portland, OR 97202-8199 Division Administrator Nuclear Safety Division Oregon Department of Energy 625 Marion Street NE Salem, OR 97304-3737 Program Director Radiation Protection Services Public Health Division Oregon Health Authority 800 NE Oregon Street, Suite 640 Portland, OR 97232-2162 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.: 50-288/OL-15-02 FACILITY DOCKET NO.: 50-288 FACILITY LICENSE NO.: R-112 FACILITY: Reed College EXAMINATION DATES: May 4-12, 2015 SUBMITTED BY: __________/RA/______________ _06/24/2015_____

Michele DeSouza, Chief Examiner Date

SUMMARY

During the weeks of May 4 and May 11, 2015, the NRC administered operator licensing examinations to fifteen Reactor Operator and seven Senior Reactor Operator candidates. The Reactor Operator and Senior Reactor Operator candidates passed all applicable portions of the examinations.

REPORT DETAILS

1. Examiners: Michele DeSouza, NRC Patrick Isaac, NRC John Nguyen, NRC

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 15/0 0/0 15/0 Operating Tests 15/0 7/0 22/0 Overall 15/0 7/0 22/0

3. Exit Meeting:

Michele DeSouza, Chief Examiner, NRC Melinda Krahenbuhl, Director Christina Barrett, Operations Supervisor Upon completion of the 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 examinations.

ENCLOSURE 1

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: Reed College REACTOR TYPE: Reed TRIGA DATE ADMINISTERED: 5/04/2015 CANDIDATE: _______________________

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the Answer sheet provided. Attach all Answer sheets to the examination. Point values are indicated in parentheses for each question. A 70% in each category is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 19.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 19.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.3 C. FACILITY AND RADIATION MONITORING SYSTEMS 58.00 % 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 ___

A02 a b c d ___

A03 a ___ b ___ c ___ d ___ (0.25 each)

A04 a b c d ___

A05 a b c d ___

A06 a b c d ___

A07 a b c d ___

A08 a b c d ___

A09 a b c d ___

A10 a b c d ___

A11 a b c d ___

A12 a b c d ___

A13 a b c d ___

A14 a b c d ___

A15 a b c d ___

A16 a b c d ___

A17 a b c d ___

A18 a b c d ___

A19 a b c d ___

A20 a b c d ___

(***** END OF 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 ___

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 ___ (0.33 each)

B10 a b c d ___

B11 a b c d ___

B12 a b c d ___

B13 a b c d ___

B14 a b c d ___

B15 a b c d ___

B16 a b c d ___

B17 a b c d ___

B18 a ___ b ___ c ___ (0.33 each)

B19 a b c d ___

B20 a b c d ___

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

Category C: Facility and Radiation Monitoring Systems ANSWER SHEET Multiple Choice (Circle or X your choice)

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

C01 a ___ b ___ c ___ d ___ (0.25 each )

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 ___ (0.25 each)

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.

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]

The reactor is shutdown after a 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months run at full power. What is the approximate time it will take Xenon to reach its peak?

a. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

b. 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months

c. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

d. 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months QUESTION A.02 [1.0 point]

Reactor is critical. What would be the corresponding keff when removing 0.05 k/k from its criticality?

a. 0.9951

b. 0.9524

c. 0.9750

d. 1.0526 QUESTION A.03 [1.0 point, 0.25 each]

Match the following Neutron Interactions (each used only once)

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

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

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

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

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

Which ONE of the following is a correct statement of how delayed neutrons enhance the ability to control reactor power?

a. Prompt neutrons can cause fissions in both U-235 and U-238 and delayed neutrons can only cause fissions in U-235

b. Delayed neutrons are born at higher energy levels than prompt neutrons

c. The average number of delayed neutrons produced per fission is higher than the average number of prompt neutrons

d. Delayed neutrons increase the average neutron lifetime that allows a reactor to be controlled QUESTION A.05 [1.0 point]

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

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

a. Alpha

b. Beta

c. Gamma

d. Neutron QUESTION A.06 [1.0 point]

Assume that the worths of the Shim rod is $3.70, Safety rod is $4.45, and Reg rod is $2.10.

The reactor is critical at 15 W after WITHDRAWING the following control rod worths: Shim

$2.10, Safety $3.50, and Reg $1.50. What is the CORE EXCESS?

a. $2.85

b. $3.15

c. $5.50

d. $7.10

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

An ideal moderator for thermalizing neutrons is light water. Which ONE of the following correctly describes the nuclear properties of an ideal moderator?

a. Small energy loss per collision

b. Small Doppler Broadening effect

c. Large scattering cross section

d. Large absorption cross section QUESTION A.08 [1.0 point]

Two common FISSION PRODUCTS that have especially large neutron cross sections and play a significant role in reactor physics are Xe-135 and _______.

a. Nitrogen-16

b. Argon-41

c. Iodine-131

d. Samarium-149 Question deleted prior to administration of the examination based on facility comment QUESTION A.09 [1.0 point]

Which ONE of the following best describes the effects moderator temperature increase has on neutron multiplication?

a. Resonance escape probability increase, thermal non-leakage decrease, and rod worth increase

b. Resonance escape probability increase, thermal non-leakage increase, and rod worth decrease

c. Resonance escape probability decrease, thermal non-leakage decrease, and rod worth increase

d. Resonance escape probability decrease, thermal non-leakage decrease, and rod worth decrease

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.10 [1.0 point]

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

a. The number of neutrons gained per generation increases by a factor of 2 for each succeeding generation

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

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

d. Doubling the indicated power will reduce the margin to criticality by approximately one half QUESTION A.11 [1.0 point]

A subcritical reactor, keff is increased from 0.914 to 0.96. Which ONE of the following is the amount of reactivity that was added to the core?

a. 3.64%k/k

b. 4.38%k/k

c. 5.78%k/k

d. 6.57%k/k QUESTION A.12 [1.0 point]

Which ONE of the following isotopes will absorb neutrons quickly when it interacts with neutrons?

a. Hydrogen-1

b. Oxygen-16

c. Boron-10

d. Uranium-235

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.13 [1.0 point]

Core excess reactivity changes with _________.

a. Fuel element burnup

b. Control rod height

c. Neutron energy level

d. Reactor power level QUESTION A.14 [1.0 point]

Which ONE of the following is the reason for the 80 second period following a reactor scram?

a. Amount of negative reactivity added on a scram exceeds the shutdown margin

b. Longest lived delayed neutron precursors decay constant

c. Fuel temperature coefficient adding positive reactivity

d. Uranium-235 affinity for source neutrons QUESTION A.15 [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 100 kW to 150 kW

b. From 10 kW to 20 kW

c. From 10 W to 30 W

d. From 1 W to 5 W

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.16 [1.0 point]

Which ONE of the following is the reason for an installed neutron source within the reactor core? A startup without an installed neutron source _______.

a. Is impossible as no neutrons would be available to start up the reactor

b. Can be compensated for by adjusting the compensating voltage on the source range detector

c. Could result in a very short period due to the reactor going critical before the neutron population is built up high enough to be read on nuclear instrumentation

d. Would be very slow due to the long time to build up the neutron population from such a low level QUESTION A.17 [1.0 point]

Which ONE of the following combinations of characteristics makes a good reflector?

Scattering Cross Section Absorption Cross Section

a. Low Low

b. Low High

c. High Low

d. High High QUESTION A.18 [1.0 point]

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

a. Fuel temperature

b. Flux shape

c. Reactor power

d. Rod speed

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.19 [1.0 point]

Given a source strength of 150 neutrons per second (N/sec) and a multiplication factor of 0.7, which ONE of the following is the expected stable neutron count rate?

a. 150 N/sec

b. 250 N/sec

c. 400 N/sec

d. 500 N/sec QUESTION A.20 [1.0 point]

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

a. Fission fragments

b. Fission product decay

c. Prompt gamma rays

d. Fission neutrons (kinetic energy)

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

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

Which ONE of the following conditions is a violation of Technical Specifications, reactor primary pool water?

a. Conductivity of the pool water is 4 uSiemens/cm averaged over one month

b. Bulk temperature of the coolant is 45oC during reactor operation

c. Radioactivity in the pool water is 0.2 µCi/ml

d. Pool water pH is 5.7 QUESTION B.02 [1.0 point]

Per Reed Emergency Plan, OFFSITE is defined as the geographical area that is _________.

a. 200 feet beyond the Reed College campus

b. 200 feet beyond the operations boundary

c. Beyond the Reed College campus

d. Beyond the site boundary QUESTION B.03 [1.0 point]

Which ONE of the following is the definition for Annual Limit on Intake?

a. 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 mrem

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 mrem for noble gases

c. 10CFR20 derived limit, based on a Committed Effective Dose Equivalent of 5 rem 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

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

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

Which ONE of the following is NOT a responsibility of the SRO and RO?

a. Review of fuel movement or core configuration changes

b. Insertion and removal of experiments

c. Participation in requalification program

d. Preparation of logs and records of reactor operations QUESTION B.05 [1.0 point]

Per Reed Technical Specifications, what is the MINIMUM level of management who may direct relocation of any in-core experiment with reactivity worth greater than one dollar?

a. Reactor Director

b. Operations Supervisor

c. SRO at the facility

d. SRO on call Question deleted prior to administration of the examination based on facility comment QUESTION B.06 [1.0 point]

Which medical facility is preferred to provide care for contaminated injured individuals?

a. Legacy Good Samaritan

b. Mount Sinai

c. Providence

d. Kaiser Permanente

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

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

a. 10.5 Years

b. 15.5 Years

c. 24.5 Years

d. 35.5 Years QUESTION B.08 [1.0 point]

Which ONE of the following logbook entries would be made in BLACK WITH GREEN UNDERLINE?

a. Removal of fuel element from core

b. Failure of primary water pump

c. Removal of neutron source from core

d. Reactor scram due to electrical transient QUESTION B.09 [1.0 point, 0.33 each]

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

Column A

a. Calculated radiological effluent, DDE of 20 mrem/hr for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

b. A fire in the control room

c. Significant personnel injury Column B

1. Not classified

2. Notification of Unusual Event

3. Alert

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

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

a. 50 rem

b. 15 rem

c. 100 rem

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

The steady state reactor power level shall not exceed 250 kW. This is an example of:

a. Safety Limit

b. Limiting Safety System Setting

c. Limiting Conditions for Operation

d. Safety Operational Limit QUESTION B.12 [1.0 point]

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

a. 190 mrem

b. 200 mrem

c. 210 mrem

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

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

a. 24 mR/hr

b. 28 mR/hr

c. 32 mR/hr

d. 36 mR/hr

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

Based on the Reed Requalification Plan, each operator must perform the functions of a licensed operator to maintain an active operators license a MINIMUM of ________.

a. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per year

b. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per quarter

c. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per month

d. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per quarter QUESTION B. 15 [1.0 point]

Which ONE of the following must be performed on a daily basis prior to reactor operations?

a. Test the low/hi water level alarm

b. Test the evacuation alarm

c. Inventory licensed radioactive material

d. Radiation area monitor check QUESTION B.16 [1.0 point]

After an emergency building evacuation, who has the authority to allow reentry to the reactor building?

a. Reed College Police Chief

b. Reed College Dean

c. Emergency Coordinator

d. U.S. NRC QUESTION B.17 [1.0 point]

How far back is the reactor operator required to review the main log prior to performing a reactor startup checklist?

a. 45 days or the last time that operator operated the reactor

b. 30 days or the last time that operator operated the reactor

c. 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or the previous time that operator operated the reactor

d. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or the previous time that operator operated the reactor

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.18 [1.0 point, 0.33 each]

Match the appropriate item in Column A with its definition in Column B.

Column A Column B

a. Channel Calibration 1. The introduction of a signal into the channel for verification that it is operable

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

c. Channel Check 3. Qualitative verification of acceptable performance by observation of channel behavior QUESTION B.19 [1.0 point]

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

a. No limit

b. 2 rem in a year

c. 2 rem in any one hour

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

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

a. Not required

b. 10.5 feet

c. 12.5 feet

d. 15.5 feet

(***** End of Category B *****)

Category C: Facility and Radiation Monitoring Systems QUESTION C.01 [1.0 point, 0.25 each]

Match the facility radiation detector in Column A with the type of radiological problem it detects in Column B.

Column A Column B

a. RAM 1. Gases Only

b. GSM 2. Radiation Level

c. APM 3. Particulates Only

d. CAM 4. Gases and Particulates QUESTION C.02 [1.0 point]

Which ONE of the following is the purpose of the diffuser on the return of the primary coolant system?

a. Increase heat transfer rate due to increased mixing within the core

b. Increase transport time for N16 to reach the surface of the pool

c. Breakup O16 bubbles in pool, thereby decreasing production of N16

d. Decrease the activation rate of O16 to N16 due to reduced time in the core QUESTION C.03 [1.0 point]

Which ONE of the following is the design feature that prevents siphoning of pool water on a failure of the purification system?

a. A valve downstream of the primary pump will shut automatically

b. A valve upstream of the primary pump will shut automatically

c. Vacuum breaks in the system that prevent draining the pool 40 inches below the surface of water

d. The emergency fill system will automatically maintain the pool level

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

During the thermal power calibration, if the percent power channel output is about 5% HIGHER than the calculated thermal power calibration, the reactor operator:

a. Does not need to adjust the percent power channel output

b. Needs to adjust the percent power channel output by physically LOWERING the height of the detectors in the support assembly

c. Needs to adjust the percent power channel output by physically RAISING the height of the detectors in the support assembly

d. Needs to adjust the percent power channel output by adjusting the percent power channel gain QUESTION C.05 [1.0 point]

Reed Technical Specifications requires fuel elements be stored in a safe array where the keff is less than _______.

a. 0.6

b. 0.7

c. 0.8

d. 0.9 QUESTION C.06 [1.0 point]

Which ONE of the following materials is inserted in the top and bottom of the active fuel portion of each fuel element to reduce neutron leakage?

a. Aluminum

b. Boron

c. Cadmium

d. Graphite

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

Which ONE of the following will cause a HIGH conductivity reading at the inlet of the demineralizer?

a. Pool water temperature low

b. High reactor water pump flow

c. Reactor water system pressure greater than secondary water pressure

d. Failure of fuel elements QUESTION C.08 [1.0 point]

The Log channel consists of:

a. A fission chamber, both pre-amplifier and amplifier, and period amplifier

b. A fission chamber, amplifier, and 110% scram

c. A compensated ion chamber, pre-amplifier, and period amplifier

d. An uncompensated ion chamber, amplifier, and 110% scram QUESTION C.09 [1.0 point]

Which ONE of the following parameters is NOT measured in the primary cooling/purification system loops?

a. Conductivity

b. Temperature

c. Flow rate

d. pH

Category C: Facility and Radiation Monitoring Systems QUESTION C.10 [1.0 point, 0.25 each]

Match the control rod drive mechanism from Column A with the correct function in Column B.

Column A Column B

a. Push Rod 1. Provide rod position indication when the electromagnet engages the armature

b. Pull Rod 2. Provide rod full withdrawn indication

c. Piston 3. Provide rod full bottom indication

d. Potentiometer 4. Work with dash pot to slow rod near bottom of its travel QUESTION C.11 [1.0 point]

What radiological monitoring systems will be inoperable if the stack sampling pump fails?

a. Air particulate monitor and radiation area monitor

b. Air particulate monitor and gaseous stack monitor

c. Radiation area monitor and continuous air monitor

d. Continuous air monitor and air particulate monitor QUESTION C.12 [1.0 point]

Which ONE of the following describes the correct state of operation when the Reed Reactor ventilation system is in isolation mode?

a. The recirculation damper: CLOSED; the HEPA inlet damper: CLOSED

b. The recirculation damper: CLOSED; the HEPA inlet damper: OPEN

c. The recirculation damper: OPEN; the HEPA inlet damper: OPEN

d. The recirculation damper: OPEN; the HEPA inlet damper: CLOSED

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

Reed Research Reactor uses the Compensated Ion Chamber as what measuring channel?

a. Linear power channel

b. Log power channel

c. Percent power channel

d. Startup channel QUESTION C.14 [1.0 point]

The reactor is operating at 100 kW. Which ONE of the following experimental facilities provides the HIGHEST neutron flux?

a. Pneumatic transfer system

b. Central thimble facility

c. Rotary specimen rack

d. Single element replacement located at C-ring QUESTION C.15 [1.0 point]

Which region of the pulse size versus applied voltage characteristic curve does the fission chamber operate?

a. Limited Proportional

b. Ion Chamber

c. Geiger-Mueller

d. Proportional

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

Per Reed SOP 30, what MAXIMUM water temperature would result in an alarm and require an immediate scram of the reactor?

a. 45oC

b. 35oC

c. 30oC

d. 25oC QUESTION C.17 [1.0 point]

Which ONE of the following statements describes the moderating properties of zirconium-hydride in the Reed TRIGA fuel elements when temperature increases?

a. The ratio of hydrogen atoms to zirconium atoms affects the moderating effectiveness for slow neutrons

b. The probability that a neutron will return to the fuel element before being captured elsewhere is a function of the temperature of the hydride

c. Elevation of the hydride temperature increases the probability that a thermal neutron will escape the fuel-moderator element before being captured

d. The hydride mixture is very effective in slowing down neutrons with energies below 0.025 eV QUESTION C.18 [1.0 point]

Which ONE of the following conditions will cause the operating reactor to automatically scram?

a. Reactor period = 6 seconds

b. 105% reactor power

c. Bulk pool water temperature = 40oC

d. Loss of high voltage to the percent power channel

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

Which ONE of the following is the neutron absorber in Reeds reactor control rods?

a. Graphite powder

b. Zirconium hydride

c. Boron powder

d. Aluminum oxide QUESTION C.20 [1.0 point]

Where is the majority of the facilitys Ar-41 produced?

a. Reactor lab

b. Reactor bay

c. Pneumatic transfer tube

d. Rotary specimen rack

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

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

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

Reference:

Reed Training Manual, Section 10.4 A.02 Answer: b

Reference:

=(k-1)/k-0.051=k-(-0.05k)=k(1+0.05)k=1/1.05 =0.9524 A.03 Answer: a3 b1 c4 d2

Reference:

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

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 3.3.2, Page 3-7 A.05 Answer: b

Reference:

Chart of the Nuclides A.06 Answer: b

Reference:

Total Worth = $3.70+$4.45+$2.10=$10.25 Reactivity at 15 W=$2.10+$3.50+$1.50 = $7.10 Core Excess = Total Worth - Reactivity@15 W = $10.25-$7.10= $3.15 A.07 Answer: c

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 1, Module 2, Page 24 A.08 Answer: d

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 8.1, Page 8-1 Question deleted prior to administration of the examination based on facility comment A.09 Answer: c

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 3.3.2, Page 7-15 A.10 Answer: d

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 2, Module 4, Pages 1-6

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

Reference:

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

=(keff2-keff1)/(keff1*keff2) = (0.965-0.914)/(0.965*0.914) = 0.0578k/k=5.78%k/k A.12 Answer: c

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 2.5.1, Pages 2-38-43 A.13 Answer: a

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 6.2.2, Page 6-2 A.14 Answer: b

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 4.5, Page 4-12 A.15 Answer: a

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.16 Answer: c

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 5.2.2, Pages 5 5-4 A.17 Answer: c

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 1, Module 2.0, Pages 7-10 A.18 Answer: b

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 7.2 A.19 Answer: d

Reference:

CR=S/(1-k)150/(1-0.7) = 500 N/sec A.20 Answer: a

Reference:

Burn, Introduction to Nuclear Reactor Operations, Table 3.2, Page 3-5

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

Reference:

Reed TS 3.3 B.2 Answer: d

Reference:

Reed Emergency Plan definitions B.3 Answer: c

Reference:

10CFR20.1003 B.4 Answer: a

Reference:

Reed Administrative Procedures 1.6 B.5 Answer: c

Reference:

Reed TS 6.1.3.c.5 Question deleted prior to administration of the examination based on facility comment B.6 Answer: a

Reference:

Reed Emergency Plan 3.1.13 B.7 Answer: c

Reference:

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

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

Reference:

Reed SOP 60.17 B.9 Answer: a (3), b (2), c (1)

Reference:

Reed Emergency Plan 4 B.10 Answer: d

Reference:

10 CFR 20.1201 B.11 Answer: c

Reference:

Reed TS 3.1.1 B.12 Answer: c

Reference:

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

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

Reference:

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

Reference:

10CFR55.59 B.15 Answer: d

Reference:

Reed, SOP 23 B.16 Answer: c

Reference:

Reed Emergency Plan 3.4 B.17 Answer: b

Reference:

Reed SOP 1 B.18 Answer: a (2), b (1), c (3)

Reference:

TS Chap 1, Definitions B.19 Answer: d

Reference:

10CFR20.1301(a)(2)

B.20 Answer: d

Reference:

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

24 R/hr = 0.1 R/hr@ D2 = 240 R/hr = 15.5 ft.

Category C: Facility and Radiation Monitoring Systems C.01 Answer: a (2), b (1), c (3), d (3)

Reference:

SOP-41A, RAM Calibration; SOP-40B,CAM Calibration; SOP-40C, APM Calibration §32.1; SOP-40D, GSM Calibration §33.1 C.02 Answer: b

Reference:

Reed SAR 5.2.6 C.03 Answer: c

Reference:

Reed Training Manual 11.6 C.04 Answer: c

Reference:

Reed SOP 33.7.1 C.05 Answer: d

Reference:

Reed Technical Specifications 5.5.a C.06 Answer: d

Reference:

Reed Training Manual 10.5 C.07 Answer: d

Reference:

Reed Training Manual 11.6 C.08 Answer: a

Reference:

Reed Training Manual 11.8 & Figure 11.12 C.09 Answer: d

Reference:

Reed Training Manual 11.6 C.10 Answer: a (2), b (3), c (4), d (1)

Reference:

Reed SAR 5.2.8, 5.3.1, & 5.3.3 C.11 Answer: b

Reference:

Reed Training Manual 5.2.3 C.12 Answer: b

Reference:

Reed Training Manual 11.9 C.13 Answer: a

Reference:

Reed Training Manual 5.2.2

Category C: Facility and Radiation Monitoring Systems C.14 Answer: b

Reference:

Highest flux in center of core C.15 Answer: d

Reference:

Reed Training Manual 5.2.2 Figure 5.2 C.16 Answer: b

Reference:

Reed SOP 30 and Reed SOP 33C C.17 Answer: c

Reference:

Reed SAR, Appendix E; Reed Training Manual 10.6 C.18 Answer: b or d

Reference:

Reed TS 3.2.2 & 3.2.3 C.19 Answer: c

Reference:

Reed SAR 8.3 & 11.3 C.20 Answer: d

Reference:

Reed SAR 7.5

ML15180A071

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