Text

Examination Report, No. 50-288/OL-14-01, Reed Reactor Facility
	ML14163A067
Person / Time
Site:	Reed College
Issue date:	06/13/2014
From:	Gregory Bowman; Research and Test Reactors Licensing Branch
To:	Krahenbuhl M; Reed College
	Lamb T
Shared Package
ML4071A497	List: ML14163A067;
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June 13, 2014 Dr. Melinda Krahenbuhl, Director Reed Reactor Facility Reed College 3203 SE Woodstock Blvd.

Portland, OR 97202

SUBJECT:

EXAMINATION REPORT NO. 50-288/OL-14-02, REED COLLEGE

Dear Dr. Krahenbuhl:

During the weeks of May 5 and May 12, 2014, the Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your TRIGA 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 (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 Taylor Lamb at (301) 415-7128 or via electronic mail Taylor.Lamb@nrc.gov.

Sincerely,

/RA/

Gregory T. Bowman, 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-14-02

2. Facility Comments with NRC Resolution

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

June 13, 2014 Dr. Melinda Krahenbuhl, Director Reed Reactor Facility Reed College 3203 SE Woodstock Blvd.

Portland, OR 97202

SUBJECT:

EXAMINATION REPORT NO. 50-288/OL-14-02, REED COLLEGE

Dear Dr. Krahenbuhl:

During the weeks of May 5 and May 12, 2014, the Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your TRIGA 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 (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 Taylor Lamb at (301) 415-7128 or via electronic mail Taylor.Lamb@nrc.gov.

Sincerely,

/RA/

Gregory T. Bowman, 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-14-02

2. Facility Comments with NRC Resolution

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

PUBLIC RidsNrrDprPrta RidsNrrDprPrtb Facility File (CRevelle)

ADAMS ACCESSION No.: ML14163A067 NRR-079 OFFICE NRR/DPR/PROB NRR/DPR/PROB NRR/DPR/PROB NAME TLamb CRevelle GBowman DATE 06/12/2014 06/12/2014 06/13/2014 OFFICIAL RECORD COPY

Reed College Docket No. 50-288 cc:

Mayor of the City of Portland 1220 Southwest 5th Avenue Portland, OR 97204 Reed College ATTN: Dr. Nigel Nicholson, Dean of Faculty 3203 SE Woodstock Boulevard Portland, OR 97202-8199 Reed College ATTN: Mr. John Kroger, President 3203 SE Woodstock Boulevard Portland, OR 97202-8199 Division Administrator Nuclear Safety Division Oregon Department of Energy 625 Marion Street, NE Salem, OR 97301-3737 Program Director Radiation Control Program Oregon Health Services Department of Human Services 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-14-02 FACILITY DOCKET NO.: 50-288 FACILITY LICENSE NO.: R-112 FACILITY: Reed College EXAMINATION DATES: May 5-13, 2013 SUBMITTED BY: __/RA/________________________ 06/13/14 Taylor A. Lamb, Chief Examiner Date

SUMMARY

During the weeks of May 5 and May 12, 2013, the U.S. Nuclear Regulatory Commission (NRC) administered the operator licensing examinations to thirteen (13) Reactor Operator candidates and eleven (11) Senior Reactor Operator Upgrade candidates. All Reactor Operator candidates passed the written portion of the examination, two (2) Reactor Operator candidates failed the operating portion of the examination, and one (1) Senior Reactor Operator candidate failed the operating portion of the examination.

REPORT DETAILS

1. Examiners: Taylor Lamb, Chief Examiner Patrick Isaac, Examiner

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 13/0 N/A 13/0 Operating Tests 11/2 10/1 21/3 Overall 11/2 10/1 21/3

3. Exit Meeting:

Taylor Lamb, NRC, Chief Examiner Patrick Isaac, NRC, Examiner Dr. Melinda Krahenbuhl, Director, Reed Reactor Brian Fairchild, Reactor Operations Manager, Reed Reactor The examiners met with the facility staff to discuss the overall administration of the examination and thanked them for their support during the examination and for their comments on questions.

ENCLOSURE 1

Section A L Theory, Thermo, and Facility Characteristics Facility Comments with NRC Resolution Facility Comments May 16, 2014 Comments on written examination, 50-288/OL-14-02 Question A.13 Answer on the key is a. 300 N/sec. The answer should be c. 1250 N/sec.

SCR = S/(1-Keff )= 250/(1-0.8) = 250/0.2 = 1250 Question A.18 Answer on the key is a. the instantaneous jump in power due to a rod withdrawal. The answer should be b. The power does a 'jump" when rods are withdrawn due to prompt neutrons, however, the jump levels off due to delayed neutrons. Prompt critical is the condition when rho=beta and the reactor is critical on prompt neutrons alone. A prompt critical reactor the delayed neutrons have no impact on reactor control. Glasstone and Sesonske pages 238-246, Lamarsh chapter 7, and Burns page 4-1. The definitions were the same.

NRC Resolution:

Question A.13: Comment accepted. The answer on the key was changed.

Question A.18: Comment accepted. The answer on the key was changed.

ENCLOSURE 2

U. S. NUCLEAR REGULATORY COMMISSION RESEARCH AND TEST REACTOR OPERATOR LICENSING EXAMINATION FACILITY: Reed College REACTOR TYPE: TRIGA DATE ADMINISTERED: 05/05/2014 CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheets provided. Points for each question are indicated in brackets for each question. You must score 70% in each section to pass.

Examinations will be picked up three (3) hours after the examination starts.

% of Category % of Candidates Category Value Total Score Value Category 20.00 33.90 A. Reactor Theory, Thermodynamics and Facility Operating Characteristics 20.00 33.90 B. Normal and Emergency Operating Procedures and Radiological Controls 19.00 32.20 C. Plant and Radiation Monitoring Systems FINAL GRADE

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

Candidate's Signature ENCLOSURE 3

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

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

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

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

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

2

EQUATION SHEET

Q = m c p T = m H = UA T

( - )2 * -4

1 x 10 seconds P max

2 (k)

S CR 1 (1 - K eff 1 ) = CR 2 (1 - K eff 2 )

SCR =

1 - K eff eff = 0.1 sec-1 SUR = 26.06 eff

- 1 - K eff 0 1 CR1 M= M= =

1 - K eff 1 1 - K eff CR 2 P = P0 10 SUR(t) P = P0 e t

(1 - )

P= P0 (1 - K eff ) * -

SDM = = =

+

K eff -

eff K eff 2 - K eff 1 0.693 ( K eff - 1)

T=

k eff 1 x K eff 2 K eff 6CiE(n) 2 DR1 d 1 = DR 2 d 2 2

DR = DR0 e- t DR = 2 R

2

( 2 - )2 ( 1 - )

=

Peak 2 Peak 1 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lbm 3

1 Horsepower = 2.54 x 10 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 3

1 BTU = 778 ft-lbf EF = 9/5 EC + 32 1 gal (H2O) . 8 lbm EC = 5/9 (EF - 32) 4

Section A - Reactor Theory, Thermohydraulics & Facility Operating Characteristics ANSWER SHEET Multiple Choice (Circle or X your choice)

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

A001 a b c d __

A002 a b c d __

A003 a b c d __

A004 a b c d __

A005 a b c d __

A006 a b c d __

A007 a b c d __

A008 a b c d __

A009 a b c d __

A010 a b c d __

A011 a b c d __

A012 a b c d __

A013 a b c d __

A014 a b c d __

A015 a b c d __

A016 a __ b __ c __ d ___

A017 a b c d __

A018 a b c d __

A019 a b c d __

A020 a b c d __

- - - - END OF SECTION A *****

5

Section B - Normal/Emergency Procedures and Radiological Controls ANSWER SHEET Multiple Choice (Circle or X your choice)

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

B001 a b c d __

B002 a b c d __

B003 a b c d __

B004 a b c d __

B005 a b c d __

B006 a __ b __ c __ d ___

B007 a b c d __

B008 a b c d __

B009 a b c d __

B010 a b c d __

B011 a b c d __

B012 a b c d __

B013 a b c d __

B014 a b c d __

B015 a b c d __

B016 a b c d __

B017 a b c d __

B018 a b c d __

B019 a b c d __

B020 a b c d __

- - - - END OF SECTION B *****

6

Section C - Plant and Rad Monitoring Systems ANSWER SHEET Multiple Choice (Circle or X your choice)

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

C001 a b c d __

C002 a __ b __ c ___

C003 a b c d __

C004 a b c d __

C005 a b c d __

C006 a __ b __ c __ d ___

C007 a b c d __

C008 a b c d __

C009 a b c d __

C010 a b c d __

C011 a b c d __

C012 a b c d __

C013 a b c d __

C014 a __ b __ c __ d ___

C015 a b c d __

C016 a b c d __

C017 a b c d __

C018 a b c d __

C019 a b c d __

C020 a b c d __ removed during examination

- - - - END OF SECTION C *****

- - - - END OF EXAMINATION *****

7

Section A - Reactor Theory, Thermohydraulics & Facility Operating Characteristics QUESTION A.1 [1.0 point]

What is the definition of a cross section?

a. The probability that a neutron will be captured by the nucleus.

b. The most likely energy at which a charged particle will be captured.

c. The length a charged particle travels past the nucleus before being captured.

d. The area of the nucleus including the electron cloud.

QUESTION A.2 [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.3 [1.0 point]

Which ONE of the following describes the MAJOR contributor to the production and depletion of Xenon respectively in a STEADY-STATE OPERATING reactor?

Production Depletion

a. Radioactive decay of Iodine Radioactive Decay

b. Radioactive decay of Iodine Neutron Absorption

c. Directly from fission Radioactive Decay

d. Directly from fission Neutron Absorption 8

Section A - Reactor Theory, Thermohydraulics & Facility Operating Characteristics QUESTION A.4 [1.0 point]

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

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

b. would be very slow due to the long time to build up neutron population from such a low level.

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

d. can be compensated for by adjusting the compensating voltage on the source range detector.

Question A.5 [1.0 point]

Which of the following atoms will cause a neutron to lose the most energy during an elastic scattering reaction?

a. O16

b. C12

c. U235

d. H1 QUESTION A.6 [1.0 point]

Which ONE of the following explains the response of a SUBCRITICAL reactor to equal insertions of positive reactivity as the reactor approaches criticality?

a. Each insertion causes a SMALLER increase in the neutron flux resulting in a LONGER time to stabilize.

b. Each insertion causes a LARGER increase in the neutron flux resulting in a LONGER time to stabilize.

c. Each insertion causes a SMALLER increase in the neutron flux resulting in a SHORTER time to stabilize.

d. Each insertion causes a LARGER increase in the neutron flux resulting in a SHORTER time to stabilize.

9

Section A - Reactor Theory, Thermohydraulics & Facility Operating Characteristics QUESTION A.7 [1.0 point]

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

a. +5 x 10-4 K/K/ºF

b. -5 x 10-4 K/K/ºF

c. +2 x 10-5 K/K/ºF

d. -2 x 10-5 K/K/ºF QUESTION A.8 [1.0 point]

Several processes occur that may increase or decrease the available number of neutrons.

SELECT from the following the six-factor formula term that describes an INCREASE in the number of neutrons during the cycle.

a. Thermal utilization factor.

b. Resonance escape probability.

c. Thermal non-leakage probability.

d. Reproduction factor.

QUESTION A.9 [1.0 point]

Which one of the following describes the general shape of a differential rod worth curve?

a. Parabolic shaped, with the maximums at the top and bottom of the core height.

b. S shaped, with the maximum at the top of the core height.

c. Cosine shaped, with the maximum at the middle of the core height.

d. Exponentially shaped, with the maximum at the bottom of the core height.

10

Section A - Reactor Theory, Thermohydraulics & Facility Operating Characteristics QUESTION A.10 [1.0 point]

Reactor power doubles in 42 seconds. Based on the period associated with this transient, how long will it take for reactor power to increase by a factor of 10?

a. 80 seconds

b. 110 seconds

c. 140 seconds

d. 170 seconds Question A.11 [1.0 point]

Which ONE of the following best describes beta decay (-1) of a nucleus?

a. Atomic mass number increases by 1, and the number of protons increases by 1

b. Atomic mass number increases by 1, and the number of protons decreases by 1

c. Atomic mass number remains unchanged, and the number of protons increases by 1

d. Atomic mass number remains unchanged, and the number of protons decreases by 1 QUESTION A.12 [1.0 point]

Which of the following power manipulations would take the longest to complete assuming the same period is maintained?

a. 1 Kilowatt: from 1 kW to 2 kW

b. 1.5 Kilowatts: from 2 kW to 3.5 kW

c. 2 Kilowatts: from 3.5 kW to 5.5 kW

d. 2.5 Kilowatts: from 5.5 kW to 8 kW 11

Section A - Reactor Theory, Thermohydraulics & Facility Operating Characteristics QUESTION A.13 [1.0 point]

Suppose the source strength in the core is 250 neutrons per second (N/sec) and the effective multiplication factor is 0.80. Select the closest stable neutron count rate from the list below:

a. 300 N/sec

b. 750 N/sec

c. 1250 N/sec

d. 1500 N/sec QUESTION A.14 [1.0 point]

What is the approximate amount of time that it will take the amount of Xenon being produced to reach a peak after the reactor is shut down?

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

b. 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months

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

d. 33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months QUESTION A.15 [1.0 point]

Which ONE of the following is the DOMINANT factor in determining the differential reactivity worth of a control rod?

a. Radial and axial flux.

b. Total reactor power.

c. Control rod speed.

d. Delayed neutron fraction.

12

Section A - Reactor Theory, Thermohydraulics & Facility Operating Characteristics QUESTION A.16 [1.0 points, 1/4 each]

Match each term in column A with the correct definition in column B.

Column A Column B

a. Prompt Neutron 1. A neutron in equilibrium with its surroundings.

b. Fast Neutron 2. A neutron born directly from fission.

c. Thermal Neutron 3. A neutron born due to decay of a fission product.

d. Delayed Neutron 4. A neutron at an energy level greater than its surroundings.

QUESTION A.17 [1.0 point]

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

a. Insertion of a positive reactivity worth experiment

b. Lowering moderator temperature (Assume negative temperature coefficient).

c. Burnout of a burnable poison.

d. Fuel depletion.

QUESTION A.18 [1.0 point]

The term prompt critical refers to:

a. the instantaneous jump in power due to a rod withdrawal

b. a reactor which is critical using only prompt neutrons

c. a reactor which is critical using both prompt and delayed neutrons

d. a reactivity insertion which is less than eff 13

Section A - Reactor Theory, Thermohydraulics & Facility Operating Characteristics QUESTION A.19 [1.0 point]

The delayed neutron precursor () for U235 is 0.0065. However, when calculating reactor parameters you use eff with a value of ~0.0070. Why is eff larger than ?

a. Delayed neutrons are born at higher energies than prompt neutrons resulting in a greater worth for the neutrons.

b. Delayed neutrons are born at lower energies than prompt neutrons resulting in less leakage during slowdown to thermal energies.

c. The fuel also contains U238 which has a relatively large for fast fission.

d. U238 in the core becomes Pu239 (by neutron absorption), which has a higher for fission.

QUESTION A.20 [1.0 point]

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

a. The ability of U235 to fission source neutrons.

b. The half-life to the longest-lived group of delayed neutron precursors.

c. The amount of negative reactivity added on a scram is greater than the shutdown margin.

d. The Doppler Effect, which adds positive reactivity due to the temperature decrease following a scram.

- - - - END OF SECTION A *****

14

Section B - Normal/Emergency Procedures and Radiological Controls QUESTION B.1 [1.0 point]

Which ONE of the following Emergency classifications is NOT credible at Reed College?

a. Alert.

b. General Emergency.

c. Non-Safety Related Event.

d. Notification of Unusual Event.

QUESTION B.2 [1.0 point]

The CURIE content of a radioactive source is a measure of

a. the number of radioactive atoms in the source.

b. the amount of energy emitted per unit time by the source

c. the amount of damage to soft body tissue per unit time.

d. the number of nuclear disintegrations per unit time.

Question B.3 [1.0 point]

Prior to performing the Startup Checklist, how far back is the reactor operator required to review the Main Log?

a. The last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of reactor operation.

b. 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of reactor operation or to the last time that operator operated the reactor.

c. One week.

d. 30 days or to the last time that operator operated the reactor.

15

Section B - Normal/Emergency Procedures and Radiological Controls QUESTION B.4 [1.0 point]

The scram time for the scrammable control element were last measured on March 31, 2014.

Which one of the following dates is the latest the maintenance may be performed again without exceeding a Technical Specifications requirement?

a. Six months later, September 30, 2014

b. Nine months later, December 31, 2014

c. One year later, March 31, 2015

d. 15 months later, June 30, 2015 Question B.5 [1.0 point]

Two inches of shielding reduce the gamma exposure in a beam of radiation from 400 mR/hr to 100 mR/hr. If you add an additional four inches of shielding what will be the new radiation level? (Assume all readings are the same distance from the source.)

a. 6.25 mR/hr

b. 12.5 mR/hr

c. 25 mr/hr

d. 100 mr/hr QUESTION B.6 [1.0 point, 1/4 each]

Match the Condition listed in column A with the corresponding reactivity limit in column B.

Column A Column B

a. Maximum rate of reactivity insertion of a rod (per second) 1. $1.00

b. Total Reactivity worth of all experiments 2. $0.16

c. Maximum worth of an Unsecured Experiment 3. $2.00

d. Maximum Excess reactivity above the reference core condition 4. $3.00 (normal) 16

Section B - Normal/Emergency Procedures and Radiological Controls QUESTION B.7 [1.0 point]

During a fire, you recognize that the power to the facility needs to be turned off. This can be done at the key operated switches inside the reactor hallway door and

a. the switch at the reactor console.

b. the circuit breaker in the electrical closet next to the Facility Director's office in of the chemistry building.

c. by the circuit breaker behind the Assistant Facility Director's desk in Room 102 of the chemistry building.

d. the circuit breaker in the electrical closet in the Psychology Building hallway.

Question B.8 [1.0 point]

Which is the definition of the site boundary for the Reed reactor facility?

a. 250 feet from the center of the reactor.

b. The area inside the reactor bay.

c. The physical boundary of Reed College.

d. Within the confines of the psychology building.

Question B.9 [1.0 point]

Which ONE of the following items will ALLOW a reactor operator to continue to operate the reactor? (Assume today is the three year anniversary of receiving your RO license.)

a. Last physical was 20 months ago.

b. Number of reactivity manipulations last year was 7.

c. Hours on the console last quarter was 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

d. Operating exam administered by supervisor was 17 months ago.

17

Section B - Normal/Emergency Procedures and Radiological Controls Question B.10 [1.0 point]

When removing a control element (per SOP-34, Control Rod Inspection), you must first remove

[a] fuel element[s]. Which ONE of the following correctly describes the fuel element[s] required to be removed?

a. 2 from the B ring

b. 2 from the C ring

c. 1 from the A ring

d. 1 from the B ring Question B.11 [1.0 point]

For emergency actions, the EMERGENCY SUPPORT CENTER is located in the:

a. Psychology Building

b. Reactor Classroom

c. Chemistry Building Room 102

d. Reactor Breakroom Question B.12 [1.0 point]

During a rabbit irradiation at full power, which ONE of the following precautions must be followed as part of the procedure?

a. Do not allow the rabbit motor to be turned on after the reactor has been at power for a while.

b. The rabbit operator must not allow anyone except him/herself to have complete control over the insertion and removal of the sample in the core.

c. The reactor operator must scram the reactor if there is a power level change greater than 10% when the sample is inserted in the core.

d. Discolored rabbit tubes must be used since they are more brittle and will allow a greater percentage of neutrons to irradiate the sample.

18

Section B - Normal/Emergency Procedures and Radiological Controls Question B.13 [1.0 point]

Which ONE of the following radio-isotopes is of highest concern due to its ionizing energy?

3

a. H 16

b. N 41

c. Ar 235

d. U Question B.14 [1.0 point]

As a licensed reactor operator at the Reed Reactor Facility, who is allowed to operate the controls of the reactor under your direction?

a. A local college newspaper reporter who wants to write a story on the safety of nuclear reactors.

b. A new student participating in the Reed reactor operator seminar.

c. A health physicist who is trying to gain a certified health physicist (CHP) license.

d. An NRC inspector trying to make sure that all set points of the reactor are the same as those in the technical specifications.

Question B.15 [1.0 point]

Which ONE of the following conditions is a violation of Technical Specifications, Reactor Pool?

d. Conductivity of the pool water is 4 mhos per centimeter averaged over one month.

b. Radioactivity in the pool water is 0.2 micro Ci/ml.

c. Pool water pH is 5.7

d. Bulk temperature of the coolant is 45 degrees C during reactor operation.

19

Section B - Normal/Emergency Procedures and Radiological Controls Question B.16 [1.0 point]

Which ONE of the following activities must be carried out on a weekly basis?

a. Test the evacuation alarm.

b. Test the water level low/hi alarm.

c. Inventory licensed radioactive material.

d. Radiation Area Monitor (RAM) check.

Question B.17 [1.0 point]

Technical Specification 5.5, Fuel Storage, requires that all fuel elements or fueled devices shall be rigidly supported during storage in a safe geometry such that keff is less than ___ under all conditions of moderation.

a. 0.8

b. 0.85

c. 0.9

d. 0.95 Question B.18 [1.0 point]

After the reactor is at power from an initial start-up, core-excess reactivity is calculated. The calculation indicates the core excess reactivity is $2.95. Which one of the following is the correct action for this excess reactivity? The core excess reactivity value:

a. is less than the allowable maximum and operation may continue.

b. is greater than recent past values but less than maximum, so the reactor must be shutdown and the NRC informed prior to the next reactor startup.

c. is greater than recent past values but less than maximum, so the reactor must be shutdown, even though the reason has been determined.

d. is above the allowable maximum and the reactor must be shutdown.

20

Section B - Normal/Emergency Procedures and Radiological Controls Question B.19 [1.0 point]

Which ONE of the following situations requires a radiation work permit (RWP)?

a. Conducting fuel inspections with personnel around the pool.

b. Walking on the bridge during a beam irradiation.

c. Calibration of RAM using Ra-226 source.

d. Removal of lazy susan samples.

Question B.20 [1.0 point]

What is the definition of Total Effective Dose Equivalent (TEDE)?

a. Sum of external and internal dose.

b. Dose equivalent at tissue depth of 1 cm.

c. Dose equivalent to organs or tissues.

d. Sum of dose multiplied by weighting factors.

- - - - END OF SECTION B *****

21

Section C - Plant and Rad Monitoring Systems Question C.1 [1.0 point]

Flow through the demineralizer loop is limited to 12 gallons per minute. This limit is to

a. prevent blowing resin out of the demineralizer thereby clogging the filter.

b. creating channels through the demineralizer reducing efficiency.

c. overpressurization of the demineralizer.

d. blowing the upstream filter into the demineralizer.

Question C.2 [1.0 Point, Each]

Match the following materials with the mechanism used to remove them from the primary coolant.

a. Suspended solids 1. Demineralizer

b. Soluble impurities 2. Filter

c. Dust 3. Skimmer Question C.3 [1.0 point]

Which ONE of the following facility detectors does NOT have an input signal into the Multitrend?

a. CAM

b. Log-N Channel

c. Bulk Water Temperature

d. Primary Conductivity 22

Section C - Plant and Rad Monitoring Systems Question C.4 [1.0 point]

Which ONE of the following correctly describes how condensation is removed from the Lazy Susan?

a. Periodic draining of the pool, allowing the condensation to evaporate.

b. An electric heater is placed in an insulated specimen tube, which is inserted into the rack.

c. An inert gas is blown into the lazy susan to force the condensation out.

d. A water absorbent material is placed in a perforated specimen tube, which is inserted into the rack.

Question C.5 [1.0 point]

Where is the source of air for the pneumatic transfer system when inserting a sample into the reactor?

a. Mechanical room

b. Radiochemistry laboratory A

c. Outside air intake

d. Loft free air space Question C.6 [1.0 point, 1/4 Each]

Match the problems on the left with its possible plant conditions on the right. (No changes to any equipment have been made, e.g. no valves manipulated)

a. High radiation level in demineralizer tanks 1. Resin separation (channeling)

b. High radiation level on demineralizer outlet 2. Fission product release

c. High flow through demineralizer tanks 3. High water temperature

d. High pressure on demineralizer inlet 4. Clogging 23

Section C - Plant and Rad Monitoring Systems Question C.7 [1.0 point]

Where is the Zirconium Hydride located in the fuel element used in the Reed Reactor core?

a. Above and below the fuel material.

b. On the outside of the fuel material in the cladding.

c. In the middle of the fuel element.

d. Intimately mixed with the fuel material.

Question C.8 [1.0 point]

What is the purpose of the orifice in the Primary Cooling System?

a. To restrict coolant flow to 20 gpm through the demineralizers.

b. To prevent excessive coolant flow back into the core.

c. To restrict coolant flow to 100 gpm bypassing the demineralizers.

d. To prevent excessive backpressure on the heat exchanger.

Question C.9 [1.0 point]

Which ONE of the following neutron flux monitoring channels provides a signal indicating the period of the reactor?

a. Linear Channel

b. Count Rate Channel

c. Log Channel

d. Percent Power Channel 24

Section C - Plant and Rad Monitoring Systems Question C.10 [1.0 point]

In what region of the Pulse Size vs. Applied Voltage characteristic curve does the fission chamber operate?

a. Geiger Muller

b. Limited Proportionality

c. Proportional

d. Ionization Question C.11 [1.0 point]

What is the minimum amount of water that the central thimble is designed to operate with?

a. The entire thimble must be filled with water.

b. Half of the thimble has to be filled with water.

c. The active lattice portion of the thimble has to be filled with water.

d. The thimble can be operated without any water in it.

Question C.12 [1.0 point]

Which ONE of the following statements correctly describes the purpose of the potentiometer in the control rod drive assembly?

a. Provides rod position indication when the electromagnet engages the connecting rod armature.

b. Provides a variable voltage to the rod drive motor for regulating control rod speed.

c. Provides potential voltage as required for resetting the electromagnet current.

d. Provides the potential voltage to relatch the connecting rod.

25

Section C - Plant and Rad Monitoring Systems Question C.13 [1.0 point]

Which ONE of the following parameters is NOT measured in the Primary Cooling/Purification System Loops?

a. Temperature

b. Flow Rate

c. Conductivity

d. pH Question C.14 [2.0 point, 1/2 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 and Particulates

b. CAM 2. Particulates Only

c. APM 3. Radiation Level

d. GSM 4. Gases Only Question C.15 [1.0 point]

In order to minimize the effects of Ar41 from the pneumatic tube (rabbit) system, the

a. exhaust of the system is connected to the Ar-41 purge system.

b. piping is a recirculating loop with a CO2 purge.

c. piping is a recirculating loop with an N2 purge.

d. exhaust of the system is located in the facility exhaust stack..

26

Section C - Plant and Rad Monitoring Systems Question C.16 [1.0 point]

Which ONE of the following ranges of nuclear instrumentation utilizes an uncompensated ion chamber as the neutron detection device?

a. Count Rate channel

b. Log N channel

c. Linear Power channel

d. % Power channel Question C.17 [1.0 point]

Which ONE of the following is the method used to minimize mechanical shock to the standard control rods on a scram?

a. A small spring located at the bottom of the rod.

b. A piston, (part of the connecting rod) drives water out of a dashpot as the rod nears the bottom of its travel.

c. An electrical-mechanical brake energizes when the rod down limit switch is energized.

d. A piston (part of the connecting rod) drives air out of a dashpot as the rod nears the bottom of travel.

Question C.18 [1.0 point]

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

a. Failure of cooling water heat exchanger

b. Pool water temperature low

c. Reactor water system pressure greater than secondary water pressure

d. High reactor water pump flow 27

Section C - Plant and Rad Monitoring Systems Question C.19 [1.0 point]

The neutron absorber in Reeds reactor control rods is:

a. Aluminum oxide

b. Zirconium hydride

c. Graphite powder

d. Boron carbide

- - - - END OF SECTION C *****

- - - - END OF EXAMINATION *****

28

Section A - Reactor Theory, Thermohydraulics & Facility Operating Characteristics Answer Key A.1 Answer: a

Reference:

Reed Training Manual A.2 Answer: a

Reference:

Reed Reactor Facility Training Manual A.5 Answer: d

Reference:

Reed Training Manual A.10 Answer: c

Reference:

Reed Training Manual 29

Section A - Reactor Theory, Thermohydraulics & Facility Operating Characteristics A.12 Answer: a

Reference:

P = P0 et/

Question A.13 answer updated following the administration of the examination per facility comment.

A.13 Answer: a c

Reference:

Reed Training Manual A.14 Answer: a

Reference:

Reed Training Manual (Section 10.4)

A.15 Answer: a

Reference:

Reed Training Manual (Section 10.3)

A.16 Answer: a. 2; b. 4; c. 1; d. 3

Reference:

Reed Training Manual A.17 Answer: d

Reference:

Reed Training Manual Question A.18 answer updated following the administration of the examination per facility comment.

A.18 Answer: a b

Reference:

Reed Training Manual 30

Section B Normal, Emergency and Radiological Control Procedures Answer Key B.1 Answer: b

Reference:

Emergency Plan B.2 Answer: d

Reference:

Standard health physics definition B.3 Answer: d

Reference:

SOP-1, Reactor Operation B.4 Answer: d

Reference:

TS 4.2 B.5 Answer: a

Reference:

Nuclear Power Plant Health Physics and Radiation Protection, Research Reactor,

Reference:

TS, multiple B.7 Answer: d

Reference:

Emergency Plan B.8 Answer: a

Reference:

Emergency Plan B.9 Answer: a

Reference:

10 CFR 55 B.10 Answer: a

Reference:

SOP-34, Control Rod Inspection (section 7.6)

B.11 Answer: c

Reference:

Emergency Plan 31

Section B Normal, Emergency and Radiological Control Procedures B.12 Answer: c

Reference:

RRR SOP 1, Sections 1.9.1 and 1.9.2 B.13 Answer: c

Reference:

SOP-13, Rabbit B.14 Answer: b

Reference:

10 CFR 55.13 B.15 Answer: d

Reference:

TS Section 3.3 B.16 Answer: d

Reference:

SOP-23, Weekly Checklist B.17 Answer: a

Reference:

TS Section 5.5.a B.18 Answer: a

Reference:

TS Section 3.1.3 B.19 Answer: b

Reference:

SOP-53, Radiation Work Permits B.20 Answer: a

Reference:

10 CFR 20 32

Section C Plant and Radiation Monitoring Systems Answer Key C.1 Answer: b

Reference:

TRIGA MK I Reactor Mechanical Maintenance & Operating Manual C.2 Answer: a. 2; b. 1; c. 3

Reference:

Reed Training Manual C.3 Answer: d

Reference:

SOP-36, Multitrend C.4 Answer: d

Reference:

Reed Training Manual C.5 Answer: a

Reference:

Reed Training Manual C.6 Answer: a. 2; b. 3; c. 1; d. 4

Reference:

Reed Training Manual C.7 Answer: d

Reference:

Reed Training Manual C.8 Answer: a

Reference:

Reed Training Manual C.9 Answer: c

Reference:

Reed Training Manual C.10 Answer: c

Reference:

Reed Training Manual C.11 Answer: c

Reference:

Reed Training Manual C.12 Answer: a

Reference:

Reed SAR 33

Section C Plant and Radiation Monitoring Systems C.13 Answer: d

Reference:

Reed Training Manual C.14 Answer: a. 3; b. 2; c. 2; d. 4

Reference:

Reed SOP-40 B, C, and D and SOP-41 C.15 Answer: d

Reference:

Reed Training Manual C.16 Answer: d

Reference:

Reed Training Manual C.17 Answer: b

Reference:

Reed Training Manual C.18 Answer: a

Reference:

Reed Training Manual C.19 Answer: d

Reference:

Reed Training Manual

- - - - END OF THE EXAM ********************************

34

ML14163A067

Text

SUBJECT:

Dear Dr. Krahenbuhl:

Enclosures:

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Dear Dr. Krahenbuhl:

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SUMMARY

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