Text

Examination Report No. 50-288/OL-18-02, Reed College
	ML18099A302
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Site:	Reed College, 05572651, 05573533, 05573548, 05573558, 05573559, 05573560, 05573561, 05574666, 05574667, 05574669, 05574688, 05574689, 05574692, 05574693, 05574694
Issue date:	04/20/2018
From:	Anthony Mendiola; Research and Test Reactors Oversight Projects Branch
To:	Krahenbuhl M; Reed College
	Mendiola A
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 20, 2018 Dr. Melinda Krahenbuhl, Director Reed Reactor Facility 3203 SE Woodstock Blvd.

Portland, OR 97202

SUBJECT:

EXAMINATION REPORT NO. 50-288/OL-18-02, REED COLLEGE

Dear Dr. Krahenbuhl:

During the weeks of March 12 and March 19, 2018, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Reed College research reactor.

The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with Title 10 of the Code of Federal Regulations, Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Mr. John T. Nguyen at (301) 415-4007 or via electronic email at John.Nguyen@nrc.gov.

Sincerely,

/RA/

Anthony J. Mendiola, Chief Research and Test Reactors Oversight Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 50-288

Enclosures:

1. Examination Report No. 50-288/OL-18-02

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

ML18099A302 NRR-074 OFFICE NRR/DLP/PROB/CE*

NRR/DIRS/IOLB/OLA NRR/DLP/PROB/BC NAME JNguyen CJRandiki AMendolia DATE 04/03/2018 04/13/2018 04/20/2018

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 John Kroger, President Reed College 3203 SE Woodstock Boulevard Portland, OR 97202-8199 Ken Niles, Assistant Director for Nuclear Safety Oregon Department of Energy 550 Capitol Street N.E., 1st Floor Salem, OR 97301 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 P.O. Box 118300 University of Florida Gainesville, FL 32611 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:

50-288/OL-18-02 FACILITY DOCKET NO.:

50-288 FACILITY LICENSE NO.:

R-112 FACILITY:

Triga EXAMINATION DATES:

March 12-20, 2018 SUBUCITED BY:

_________/RA/_________________

_4/3/2018_

John T. Nguyen, Chief Examiner Date

SUMMARY

During the weeks of March 12 and March 19, 2018, the NRC administered operator licensing examinations to 14 Reactor Operator (RO) candidates and one Senior Reactor Operator Upgrade (SROU) Retake candidate who failed the previous operating test. All candidates passed all applicable portions of the examinations.

REPORT DETAILS

1.

Examiners:

John T. Nguyen, Chief Examiner, NRC

2.

Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 14/0 N/A 14/0 Operating Tests 14/0 1/0 15/0 Overall 14/0 1/0 15/0

3.

Exit Meeting:

Melinda Krahenbuhl, Director, Reed College Ilana Novakoski, Reactor Operations Manager, Reed College Michele DeSouza, Examiner, NRC John T. Nguyen, Chief Examiner, NRC At the conclusion of the meeting, the NRC Examiner thanked the facility for their support in the administration of the examinations. The facility licensee had no comments on the written examination. The examiner noticed that the facility has significantly improved the training program. The examiner also discussed the weaknesses observed from the operating tests including the generic weaknesses in a basic understanding of the damper operation when a loss of AC power.

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

Pool REACTOR TYPE:

TRIGA DATE ADMINISTERED:

3/12/2016 CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

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

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 20.00 33.3 B.

NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.3 C.

FACILITY AND RADIATION MONITORING SYSTEMS 60.00 _____%

TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

A. RX THEORY, THERMO & FAC OP CHARS 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 ___ (0.25 each)

A13 a b c d ___

A14 a ___ b ___ c ___ d ___ (0.25 each)

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 *****)

B. NORMAL/EMERG PROCEDURES & RAD CON 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 ___ (0.25 each)

B03 a ___ b ___ c ___ d ___ (0.25 each)

B04 a b c d ___

B05 a b c d ___

B06 a ___ b ___ c ___ d ___ (0.25 each)

B07 a b c d ___

B08 a b c d ___

B09 a b c d ___

B10 a b c d ___

B11 a b c d ___

B12 a ___ b ___ c ___ d ___ (0.25 each)

B13 a b c d ___

B14 a b c d ___

B15 a ___ b ___ c ___ d ___ (0.25 each)

B16 a b c d ___

B17 a b c d ___

B18 a b c d ___

B19 a b c d ___

B20 a b c d ___

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

C. PLANT AND RAD MONITORING SYSTEMS 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 ___ (0.33 each)

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 ___ (0.5 each)

C18 a b c d ___

C19 a b c d ___

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

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

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

1.

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

2.

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

3.

Restroom trips are to be UCI 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 Q = m cp T Q = m h SCR = S/(1-Keff)

Q = UA T CR1 (1-Keff)1 = CR2 (1-Keff)2 26.06 (eff)

(1-Keff)0 SUR = -------------

M = -------------------

( - )

(1-Keff)1 SUR = 26.06/

M = 1/(1-Keff) = CR1/CR0 P = P0 10SUR(t)

SDM = (1-Keff)/Keff P = P0 e(t/)

I = Io e-ux (1-)

P = ---------- Po

= 1 x 10-4 seconds

= (*/) + [(-)/eff]

= */(-)

= (Keff-1)/Keff R = 6 C E n/r2

= Keff/Keff 0.693 T1/2 = -----------

0.007 DR1D12 = DR2D22 DR = DRoe-t Cp (H20) = 0.146 kw P = S / (1 - Keff) gpm F eff = 0.1/sec 1 Curie = 3.7x1010 dps 1 kg

2.21 lbm 1 hp = 2.54x103 BTU/hr 1 Mw = 3.41x106 BTU/hr 1 BTU = 778 ft-lbf F = 9/5C + 32 931 Mev = 1 amu C = 5/9 (F - 32) 2 1

1 2

eff eff eff eff K

K K

K

=

Section A: Theory, Thermo & Fac. Operating Characteristics QUESTION A.01

[1.0 point]

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

a.

Sm149

b.

U235

c.

Xe135

d.

B10 QUESTION A.02

[1.0 point]

You're increasing reactor power on a steady +15 second period. How long will it take to increase power by a factor of five?

a.

10 seconds

b.

24 seconds

c.

33 seconds

d.

43 seconds QUESTION A.03

[1.0 point]

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

a.

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

b.

Insertion of an experiment containing borated graphite.

c.

Decrease of pool water temperature.

d.

Burnout of Xenon in the core.

Section A: Theory, Thermo & Fac. Operating Characteristics QUESTION A.04

[1.0 point]

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

a.

constant.

b.

continually increasing.

c.

increasing, then decreasing.

d.

increasing, then constant.

QUESTION A.05

[1.0 point]

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

a.

0.150

b.

0.163

c.

0.184

d.

0.197 QUESTION A.06

[1.0 point]

Which ONE of the following correctly describes the SIX-FACTOR FORMULA at the Reed College reactor? The multiplication factor between generation, K-effective, is the product of k-infinitive and the:

a.

Reproduction factor.

b.

Thermal utilization factor.

c.

Resonance escape probability.

d.

Total non-leakage probability.

Section A: Theory, Thermo & Fac. Operating Characteristics QUESTION A.07

[1.0 point]

Which ONE of the following best describes the reactor kinetic if the reactor changes from critical to prompt critical?

a.

Keff = 1 and = 0

b.

Keff = 1 and = -eff

c.

Keff > 1 and > 1

d.

Keff > 1 and -eff < 1 QUESTION A.08

[1.0 point]

The reactor is critical at 10 W. A rod is pulled to insert a positive reactivity of $0.18. Which ONE of the following will be the stable reactor period as a result of this reactivity insertion?

Given beta effective = 0.007.

a.

10 seconds

b.

46 seconds

c.

55 seconds

d.

66 seconds QUESTION A.09

[1.0 point]

Which ONE of the following is the MINIMUM amount of reactivity that makes the Reed College (finite) critical reactor to be a prompt critical reactor? This MINIMUM amount is equal to:

a.

the shutdown margin

b.

the k-effective value

c.

1.0 % K/K

d.

the -effective value

Section A: Theory, Thermo & Fac. Operating Characteristics QUESTION A.10

[1.0 point]

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

a.

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

b.

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

c.

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

d.

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

QUESTION A.11

[1.0 point]

Reactor A increases power from 10% to 30% with a period of 25 seconds. Reactor B increases power from 70% to 100% with a period of also 25 seconds. Compared to Reactor A, the time required for the power increase of Reactor B is:

a.

longer than A

b.

exactly the same as A

c.

twice that of A

d.

shorter than A QUESTION A.12

[1.0 point, 0.25 each]

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

Column A Column B

a. Fission

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

b. Radiative capture

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

c. Scattering

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

d. Particle ejection

4. Nucleus is struck by a neutron and emits a single neutron

Section A: Theory, Thermo & Fac. Operating Characteristics QUESTION A.13

[1.0 point]

On the average, how many neutrons are produced for each fission of U-235?

a.

2.00 neutrons

b.

2.09 neutrons

c.

2.43 neutrons

d.

2.93 neutrons QUESTION A.14

[1.0 point, 0.25 each]

Replace X with the type of decay necessary (Alpha, Positron, Gamma or Neutron emission) to produce the following reactions. Choices may be used once, more than once, or not at all.

a.

92U238 90Th234 + X

b.

83Bi203 82Pb203 + X

c.

2He4 + 4Be9 6C12 + X

d.

84Po210 82Pb206 + X QUESTION A.15

[1.0 point]

Given the following Core Reactivity Data (not at Reed College):

Control Rod Total Worth ($)

Core Excess ($) (reactor at 10 watts)

Rod 1 1.60 Full Up ($0.0)

Rod 2 3.00 1.20 Rod 3 2.70 0.70 Rod 4 1.20 0.80 Which one of the following is the calculated shutdown margin that would satisfy the Technical Specification Minimum Shutdown Margin? Assume that all rods are scrammable.

a.

2.7

b.

2.8

c.

5.8

d.

8.5

Section A: Theory, Thermo & Fac. Operating Characteristics QUESTION A.16

[1.0 point]

Which ONE of the following describes the term PROMPT JUMP?

a.

A reactor is subcritical at negative 80-second period

b.

A reactor has attained criticality on prompt neutrons alone

c.

The instantaneous change in power level due to inserting a control rod

d.

The instantaneous change in power level due to withdrawing a control rod QUESTION A.17

[1.0 point]

Which ONE of the following is a correct statement describing prompt and delayed neutrons?

Prompt neutrons:

a.

are released during U-238 interacts with fast neutrons, while delayed neutrons are released during U-235 interacts with thermal neutrons.

b.

account for less than 1% of the neutron population, while delayed neutrons account for the rest.

c.

are released during the fission process, while delayed neutrons are released from precursors.

d.

are the dominating factor in determining reactor period, while delayed neutrons have no effect on reactor period.

QUESTION A.18

[1.0 point]

What is the condition of the reactor when k =

?

a.

Subcritical

b.

Critical

c.

Super critical

d.

Prompt critical

Section A: Theory, Thermo & Fac. Operating Characteristics QUESTION A.19

[1.0 point]

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

a.

Lowering moderator temperature (assume negative temperature coefficient).

b.

Insertion of a positive reactivity worth experiment.

c.

Burnout of a burnable poison.

d.

Fuel depletion.

QUESTION A.20

[1.0 point]

Select the dominant contributor for the prompt negative temperature coefficient in the TRIGA fuel.

a.

As the fuel heats up the resonance absorption peaks broaden and increases the likelihood of neutron absorption in U-238

b.

As the fuel heats up a rapid increase in moderator temperature occurs through conduction and convection heat transfer mechanisms which adds negative reactivity

c.

As the fuel heats up fission product poisons (e.g., Xe) increase in concentration within the fuel matrix and add negative reactivity via neutron absorption

d.

As the fuel heats up the oscillating hydrogen in the ZrH lattice imparts energy to a thermal neutron, thereby increasing its mean free path and probability of escape

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

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

[1.0 point]

Per Reed College Emergency Plan, the individual who is responsible for the termination of an emergency related to the nuclear operations is the:

a.

Campus Police Chief

b.

USNRC

c.

Radiation Protection Officer

d.

Emergency Coordinator QUESTION B.02

[1.0 point, 0.25 each]

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

Column A Column B

a.

2 mrem/hr at 30 cm

1. Public Area

b.

70 mrem/hr at 30 cm

2. Radiation Area

c.

20 mrem/hr at 1 m

3. High Radiation Area

d.

4.5 grays/hr at 1 m

4. Very High Radiation Area QUESTION B.03

[1.0 point, 0.25 each]

Identify each of the following surveillances as a channel check (CHECK), a channel test (TEST), or a channel calibration (CAL).

a.

During the startup, you verify a reactor manual scram.

b.

During the startup, you verify the reactor interlock system by performing simultaneous manual withdrawal of two control rods.

c.

During reactor operation, you compare reading of radiation monitors.

d.

Adjust the scram set point of the CAM with recent data collected on the calibration.

Section B: Normal/Emergency Procedures and Radiological Controls QUESTION B.04

[1.0 point]

A room contains a source which, when exposed, results in a general area dose rate of 150 millirem per hour. This source is scheduled to be exposed continuously for a month. Select an acceptable method for controlling radiation exposure from the source within this room.

a.

Post the area with the words "Danger-Radiation Area".

b.

Lock the room to prevent inadvertent entry into the room.

c.

Equip the room with a device to monitor who entries into the room.

d.

Equip the room with a motion detector that will alarm in the control room.

QUESTION B.05

[1.0 point]

Reactor Operator works in a high radiation area for eight (8) hours a day. The dose rate in the area is 100 mR/hour. Which ONE of the following is the MAXIMUM number of days in which Reactor Operator may perform his duties WITHOUT exceeding 10 CFR 20 limits?

a.

5 days

b.

6 days

c.

7 days

d.

12 days QUESTION B.06

[1.0 point, 0.25 each]

Fill out the blanks with the Limiting Conditions of Operation (LCO) listed in the Reed College Technical Specifications.

Safety Channel LCO

a.

Core Excess

b.

Reactor Power level

c.

Reactivity addition rate

d.

Pool Water Temperature

Section B: Normal/Emergency Procedures and Radiological Controls QUESTION B.07

[1.0 point]

Per Reed College Technical Specifications, which ONE of the following will violate the Limiting Safety System Settings?

a.

An unanticipated change in reactivity of one dollar.

b.

Instrumented fuel temperature exceeds 250 °C.

c.

Maximum power exceeds 300 kw(t).

d.

Shutdown margin exceeds $3.00.

QUESTION B.08

[1.0 point]

Which ONE of the following changes must be submitted to NRC for approval prior to implementation?

a.

Replace a primary cooling pump with an identical pump.

b.

Add new limit to the Pre-Startup Checklist Procedure.

c.

Delete Section 5.5, Fuel Storage, listed in the Technical Specifications.

d.

Add more responsibilities to the Radiation Protection Officer listed in the health physics procedure.

QUESTION B.09

[1.0 point]

A two-curie source, emitted 80% of 500 ev gamma, is to be stored in the reactor building. How far from the source will it read 100 mrem/hr?

a.

7 feet

b.

13 feet

c.

17 feet

d.

24 feet

Section B: Normal/Emergency Procedures and Radiological Controls QUESTION B.10

[1.0 point]

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

a.

Reactor Director

b.

Reactor Supervisor

c.

Licensed Senior Reactor Operator

d.

Licensed Reactor Operator QUESTION B.11

[1.0 point]

Which ONE of the following correctly describes the limitations of experiment? The experiment with _____ shall NOT be irradiated in the reactor.

a.

The absolute reactivity of any single unsecured experiment exceeding $1.0

b.

The sum of the absolute value of reactivity of all experiments in the reactor and facilities exceeding $1.5

c.

explosive materials

d.

corrosive materials QUESTION B.12

[1.0 point, 0.25 each]

Match the annual dose limit values to the type of exposure. Answer in Column B can be used more than once, or not at all.

Type of Exposure Annual Dose Limit Value

a.

Extremities

1.

0.1 rem.

b.

Lens of the Eye

2.

0.5 rem.

c.

Occupational Total Effective Dose Equivalent (TEDE)

3.

5.0 rem.

d.

TEDE to a member of the public

4.

15.0 rem.

5.

50.0 rem.

Section B: Normal/Emergency Procedures and Radiological Controls QUESTION B.13

[1.0 point]

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

a.

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

b.

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

c.

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

d.

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

QUESTION B.14

[1.0 point]

The SITE BOUNDARY is defined as:

a.

The area, including the Psychology Building and extending 250 feet in every direction from the center of the reactor.

b.

The area, including the Psychology Building and extending 100 feet in every direction from center of the reactor.

c.

The area, that consists of the control room, the reactor bay, and Mech. room

d.

The area for which offsite emergency planning is performed to assure that prompt and effective actions can be taken to protect public in the event of an accident.

QUESTION B.15

[1.0 point, 0.25 each]

Match type of radiation listed in column A with their quality factor listed in column B. Items in column B can be used once, more than once or not at all.

Column A Column B

a.

X-ray

1.

1

b.

Gamma

2.

5

c.

Alpha particles

3.

10

d.

High-energy photons

4.

20

Section B: Normal/Emergency Procedures and Radiological Controls QUESTION B.16

[1.0 point]

Which ONE of the following is the definition of Total Effective Dose Equivalent (TEDE)?

a.

The sum of thyroid dose and external dose

b.

The sum of the external deep dose and the organ dose

c.

The sum of the deep dose equivalent and the committed effective dose equivalent

d.

The dose that your whole body is received from the source, but excluded from the deep dose QUESTION B.17

[1.0 point]

According to Reed College procedures and Technical Specifications, which ONE of the following is NOT considered an UNEXPLAINED SHUTDOWN?

a.

Reactor scram during the High Voltage Loss calibration.

b.

Reactor scram due to a suddenly loss of the building electrical power.

c.

The operator was not watching the reactor power increase and caused all the control rods to scram.

d.

The operator inadvertently leaned on the scram bar with their elbow and caused all the control rods to scram.

QUESTION B.18 [1.0 point]

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

a.

Continuous Air Monitor is still operable.

b.

Environmental Dosimeters are still operable.

c.

Only if portable instruments are substituted for the normally installed monitor within one hour of discovery for periods not to exceed one month.

d.

only if portable instruments are substituted for the normally installed monitor within one day of discovery for periods not to exceed one month.

Section B: Normal/Emergency Procedures and Radiological Controls QUESTION B.19

[1.0 point]

The operator licensing candidate requires submitting the NRC Form 396, Certification of Medical Examination by Facility Licensee, to the NRC Chief Examiner before the start date of the examination. This requirement can be found in:

a.

10 CFR Part 19

b.

10 CFR Part 20

c.

10 CFR Part 50

d.

10 CFR Part 55 QUESTION B.20

[1.0 point]

Per Technical Specifications, temporary deviations from the procedures may be made by the responsible ______ when the procedure contains errors or in order to deal with special conditions. Such deviation shall be documented and reported by ______ to _________.

a.

RO / the next working day / SRO on duty

b.

SRO / the next working day / Director (or Associate Director)

c.

SRO / the five working days / Director (or Associate Director)

d.

Director (or Associate Director) / within 14 days / NRC

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

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

[1.0 point]

In preparation of the Reactor Thermal Power Calibration, which ONE of the following prerequisites is required prior to the calibration?

a.

Turn the underwater lights ON.

b.

Adjust the Percent Power Channel gain.

c.

No operations above 5 watts for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

d.

Turn the secondary water system ON for at least one hour.

QUESTION C.02

[1.0 point]

A fuel element shall be considered damaged and must be removed from the core if:

a.

Visual inspection identifies tanned color surrounding fuel section.

b.

The traverse bend exceeds 0.025 inches over the length of the cladding.

c.

The length exceeds its original length by 0.100 inches.

d The burn-up of U-235 in the fuel matrix exceeds 50% of the initial concentration.

QUESTION C.03

[1.0 point]

The fuel element used at Reed College is a mixture of U-Zr-H alloy:

a.

containing 8.5% weight of uranium enriched to 20% U 235

b.

containing 20% weight of uranium enriched to 8.5% U 235

c.

containing 10% weight of uranium enriched to 30% U 235

d.

containing 30% weight of uranium enriched to 10% U 235

Section C: Facility and Radiation Monitoring Systems QUESTION C.04

[1.0 point]

The demineralizer is a mixed-bed type that removes both positive and negative ions from the circulating water. Which ONE of the following best describes on how these ions are replaced?

a.

Both negative and positive ions are replaced by hydroxyl (OH) ions.

b.

Both negative and positive ions are replaced by hydrogen (H) ions.

c.

The positive ions are replaced by hydrogen (H) ions and the negative ions are replaced by hydroxyl (OH) ions.

d.

The positive ions are replaced by hydroxyl (OH) ions and the negative ions are replaced by hydrogen (H) ions.

QUESTION C.05

[1.0 point]

While a rabbit is going into or out of the core, a power indication changes more than 10% of the linear power range. The MAIN reason in which the Operator of Record must scram the reactor and notify the Reactor Manager is to avoid:

a.

Violating the percent change limit in SOP.

b.

Exceeding the excess sample reactivity worth.

c.

Creating an unbalanced power distribution.

d.

Violate the Safety Limit.

QUESTION C.06

[1.0 point]

Which ONE of the following best describes the shim and safety rod drive motors? The shim and safety rod drive motors are:

a.

non-synchronous, single-phase.

b.

synchronous, single-phase.

c.

non-synchronous, double-phase.

d.

synchronous, double-phase.

Section C: Facility and Radiation Monitoring Systems QUESTION C.07

[1 point, 0.33 each]

Match the control rod in column A with their guide tube location listed in column B.

Column A Column B

a.

Safety rod C9

b.

Shim rod C5

c.

Regulating rod E1 QUESTION C.08

[1.0 point]

The fission chamber provides a signal for:

a.

Automatic Rod Control

b.

Percent Power Channel.

c.

Log Power Channel.

d.

Linear Power Channel.

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

[1.0 point]

The below figure depicts the:

a.

Pneumatic Transfer System Terminus.

b.

Pneumatic Transfer System Controller.

c.

Central Thimble System Controller.

d.

Rotary Specimen System Controller.

Section C: Facility and Radiation Monitoring Systems QUESTION C.10

[1.0 point]

Significant quantities of Nitrogen-16 are produced by the irradiation of:

a.

air in the beam ports

b.

oxygen-16 in the reactor pool

c.

air in irradiation cell

d.

Ar-40 in the rabbit system QUESTION C.11

[1.0 point]

The Main purpose for setting a conductivity limit of the pool water is to:

a.

Maintain the departure of nucleate boiling ratio (DNBR) greater than the unity.

b.

Minimize the possibility of corrosion of the cladding on the fuel elements.

c.

Extend integrity of resin bed on the demineralizer.

d.

Minimize Ar-41 released to the public.

QUESTION C.12

[1.0 point]

Which ONE of the following best describes the reactor status when the CAM or GSM exceeds its limit?

a.

automatically shutdown all ventilation systems (no air circulate).

b.

switches the ventilation to the isolation mode (air will circulate to HEPA filter).

c.

automatically scram the reactor.

d.

indication ONLY.

Section C: Facility and Radiation Monitoring Systems QUESTION C.13

[1.0 point]

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

a.

The Emergency Core Cooling System will automatically activate and maintain the pool level.

b.

A downstream valve of the primary pump will shut automatically.

c.

An emergency pump turns ON, pump the water storage tank to the reactor pool.

d.

Vacuum breaks are located in the system which prevents draining the pool 40 inches below the surface of water.

QUESTION C.14

[1.0 point]

The purpose of the orifice of the primary coolant system is to:

a.

limit the amount of water that bypasses the purification loop.

b.

limit the amount of water that bypasses the heat exchanger.

c.

increase the amount of water that bypasses the purification loop.

d.

remove insoluble particulate matter from the primary water.

QUESTION C.15

[1.0 point]

Per Technical Specifications, the k-eff limit in the fuel storage is less than _____ for all conditions of moderation and reflection.

a.

0.9

b.

0.8

c.

0.7

d.

0.6

Section C: Facility and Radiation Monitoring Systems QUESTION C.16

[1.0 point]

Which one of the following designs that helps to reduce the MAJOR radiation level at the top of the reactor tank?

a.

The primary pump takes a suction three feet below the surface of the reactor pool to prevent Nitrogen-16 from reaching the pool surface.

b.

The reactor water purification system takes a suction three feet below the surface of the reactor pool to prevent Ar-41 from reaching the pool surface.

c.

The primary pump discharges through a diffuser nozzle directing water currents downward over the core to slow N-16 from reaching the pool surface.

d.

The demineralizer absorbs Ar-41 and N-16 thus reducing their activities from reaching the pool surface.

QUESTION C.17

[2.0 points, 0.5 each]

The Shim rod is continuously rising. Select (Open/Closed) for the Limit Switches and (ON/OFF) for the lights. Note: OPEN means the limit switch does NOT activate.

a.

Rod DOWN limit switch (Open/Close)

b.

Motor UP limit switch (Open/Close)

c.

DOWN (white) light (ON/OFF)

d.

CONT (blue) light (ON/OFF)

QUESTION C.18

[1.0 point]

Which ONE of the following is the primary function of the graphite sections on both sides of the fuel element?

a.

Absorbing thermal neutrons

b.

Reducing neutron leakage

c.

Increasing neutron/gamma ratio

d.

Absorbing fission product gases if a fuel leak

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

[1.0 point]

The pool water serves all of the following functions EXCEPT:

a.

Allows for cooling of the reactor core through natural convection.

b.

Shields the reactor bay from radiation generated in the core.

c.

Minimize corrosion of all reactor components.

d.

Moderates neutrons in the core.

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

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

Section A L Theory, Thermo & Fac. Operating Characteristics A.01 Answer c

Reference:

Introduction to Nuclear Operation, Reed Burn, 1988, Sec 8.1 A.02 Answer:

b

Reference:

Reference:

b

Reference:

Reactivity added = $0.18 x.007 = 0.00126

= (-)/eff =.007 -.00126 = 45.6 seconds (0.1) (.00126)

A.09 Answer:

d

Reference:

d

Reference:

Section A L Theory, Thermo & Fac. Operating Characteristics A.11 Answer:

d

Reference:

The power of reactor A increases by a factor of 3, while the power of reactor B increases by a factor of 1.43. Since the periods are the same (rate of change is the same), power increase of reactor B takes a shorter time.

A.12 Answer:

A.17 Answer:

EP 3.3 B.02 Answer:

a(1);

b(2);

c(3);

d(3)

Reference:

10 CFR 20.1003 Definitions For part c, 20 mrem/hr at 1m will be equal to 222 mrem/hr at 30 cm :=> high radiation area 4.5 grays 450 rad/hr at 1 m high radiation area Definition High Radiation Area: 100 mrem/hr at 30 cm Radiation Area : 5 mrem/hr at 30 cm Very High Radiation Area: 500 rads/hr at 1 m B.03 Answer:

a = TEST; b = TEST; c = CHECK; d = CAL

Reference:

Technical specification, Definitions B.04 Answer:

b

Reference:

10CFR20.1601(a)(3)

B.05 Answer:

b

Reference:

10CFR20.1201(a)(1) [5000 mr x 1 hr x day = 6.25 days 100 mr 8 hr B.06 Answer:

a, $3.0 b,250 kw(t) c,$0.16 per second d,40°C

Reference:

TS 3.1.3, 3.2.1, and 3.3 B.07 Answer:

c

Reference:

TS 2.2 B.08 Answer:

c

Reference:

TS change requires an amendment.

B.09 Answer:

a

Reference:

6CEN = R/hr @ 1 ft. -> 6 x 2 x 0.8 x 0.5 = 4.8 R/hr at 1ft.

I0D02 = I*D2 4.8 R/hr*(1 ft) 2 = 0.1 R/hr *D 2 D= sqrt(4.8/0.1) = 6.9 ft.

B.10 Answer:

c

Reference:

10CFR50.54(y)

TS 6.4

Reed Training Manual 11.9

Reed Training Manual 11.2 C.19 Answer:

c

Reference:

Reed Training Manual 11.6

ML18099A302

Text

SUBJECT:

Dear Dr. Krahenbuhl:

Enclosures:

SUMMARY

0.007 DR1D12 = DR2D22 DR = DRoe-t Cp (H20) = 0.146 kw P = S / (1 - Keff) gpm F eff = 0.1/sec 1 Curie = 3.7x1010 dps 1 kg

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