Text

Examination Report No. 50-225/OL-24-01, Rensselaer Polytechnic Institute Critical Experiments Facility
	ML24058A356
Person / Time
Site:	Rensselaer Polytechnic Institute
Issue date:	03/07/2024
From:	Travis Tate; NRC/NRR/DANU/UNPO
To:	Ji W; Rennselaer Polytechnic Institute
References
	50-225/OL-24-01 OL-24-01
	Download: ML24058A356 (1)
	v • d • e

Dr Wei Ji, Director Rensselaer Walthousen Reactor Critical Care Facility Rensselaer Polytechnic Institute JEC 5040, MANE Dept.

Troy, NY 12180

SUBJECT:

EXAMINATION REPORT NO. 50-225/OL-24-01, RENSSELAER POLYTECHNIC INSTITUTE

Dear Dr. Ji:

During the week of January 29, 2024, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Rensselaer Polytechnic Institute Critical Experiments Facility. 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 component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Dan V. Hoang at 301-415-3054 or via email at Dan.Hoang@nrc.gov.

Sincerely, Travis L. Tate, Chief Non-Power Production and Utilization Facility Oversight Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation Docket No. 50-225

Enclosures:

1. Examination Report No. 50-225/OL-24-01

2. Written examination cc: w/enclosures to GovDelivery Subscribers March 7, 2024 Signed by Tate, Travis on 03/07/24

ML24058A356 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME DHoang NJones TTate DATE 2/27/2024 3/6/2024 3/7/2024 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:

50-225/OL-24-01 FACILITY DOCKET NO.:

50-225 FACILITY LICENSE NO.:

CX-22 FACILITY:

Critical EXAMINATION DATES:

Week of January 30, 2024 SUBMITTED BY:

SUMMARY

During the week of January 29, 2024, the NRC administered operator licensing examinations to one Senior Reactor Operator-Instant (SRO-I) candidate. The candidate passed all applicable portions of the examinations.

REPORT DETAILS 1.

Examiner:

Dan V. Hoang, Chief Examiner, NRC 2.

Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written N/A 1/0 1/0 Operating Tests N/A 1/0 1/0 Overall N/A 1/0 1/0 3.

Exit Meeting:

Peter Kowal, Reactor Supervisor, RCF Katelyn Cook, Senior Reactor Operator, RCF Camden Blake, Senior Reactor Operator, RCF Dan V. Hoang, Chief Examiner, NRC Facility comments were accepted prior to the administration of the written examination. Upon completion of an operator licensing examination, the NRC examiner met with facility staff representatives to discuss the results. At the conclusion of the meeting, the NRC examiner thanked the facility for their support in the administration of the examination Danvhoang 2/9/2024 Dan V. Hoang, Chief Examiner Date U.S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:

Rensselaer Polytechnic Institute REACTOR TYPE:

Critical Facility.

DATE ADMINISTERED:

01/30/2024.

CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the Answer sheet provided. Attach all Answer sheets to the examination. Point values are indicated in parentheses for each question. A 70% in each category 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 18.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 18.00 33.3 B.

NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 18.00 33.3 C.

FACILITY AND RADIATION MONITORING SYSTEMS 54.00 %

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

Candidate's Signature

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

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

A01 a b c d ___

A02 a b c d ___

A03 a b c d ___

A04 a b c d ___

A05 a b c d ___

A06 a b c d ___

A07 a ___ b ____ c ___ d ___ (0.25 each)

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 ___

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

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

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

B01 a b c d ___

B02 a b c d ___

B03 a b c d ___

B04 a b c d ___

B05 a b c d ___

B06 a b c d ___

B07 a b c d ___

B08 a b c d ___

B09 a b c d ___

B10 a b c d ___

B11 a b c d ___

B12 a b c d ___

B13 a b c d ___

B14 a b c d ___

B15 a b c d ___

B16 a b c d ___

B17 a b c d ___

B18 a b c d ___

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

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

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

C01 a b c d ___

C02 a b c d ___

C03 a b c d ___

C04 a b c d ___

C05 a b c d ___

C06 a b c d ___

C07 a b c d ___

C08 a b c d ___

C09 a b c d ___

C10 a b c d ___

C11 a b c d ___

C12 a b c d ___

C13 a b c d ___

C14 a b c d ___

C15 a b c d ___

C16 a b c d ___

C17 a b c d ___

C18 a b c d ___

(***** 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

=

+

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

°F = 9/5 °C + 32 1 gal (H2O) 8 lb

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

2 2

max

P 1

sec 1.0

eff

te P

P 0

eff K

S S

SCR

1

sec 10 1

4

eff SUR 06 26

2 1

1 1

2 1

eff eff K

CR K

CR

2 2

1 1

CR CR 2

1 1

1 eff eff K

K M

1 2

1 1

CR CR K

M eff

)

(

0 10 t

SUR P

P

0 1

P P

eff eff K

K SDM

1

2 1

1 2

eff eff eff eff K

K K

K

693

.0 2

1 T

eff eff K

K 1

t e

DR DR

0

2 6

R n

E Ci DR 2

2 2

2 1

1 d

DR d

DR

1 2

2 2

Peak Peak

T UA H

m T

c m

Q P

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

[1.0 point]

During Reg Rod calibration, doubling time was recorded to be 78 seconds. What was reactor period?

a. 39 seconds

b. 54 seconds c.

113 seconds

d. 156 seconds QUESTION A.02

[1.0 point]

While a reactor is at 5 W, the reactor operator is withdrawing a control rod to insert a positive reactivity of 0.00156 (K/K). Which ONE of the following will be the stable reactor period as a result of this withdrawal? Given beta-effective= 0.0073 and eff = 0.1.

a. 17 seconds

b. 27 seconds c.

37 seconds

d. 47 seconds QUESTION A.03

[1.0 point]

What is the meaning of any point on a differential rod worth curve?

a. The negative reactivity added as the rod is inserted.

b. The cumulative area under the differential curve starting from the bottom of the core.

c. The amount of reactivity that one inch of rod motion would insert at that position in the core.

d. The zero reactivity when the rod is on the bottom and the positive reactivity being added as the rod is withdrawn.

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.04

[1.0 point]

Which ONE of the following changes does NOT require a movement of control rods in order to maintain constant reactor power?

a. Pool water temperature decrease.

b. U-235 burnup.

c. Xe-135 buildup.

d. N-16 formation.

QUESTION A.05

[1.0 point]

The effective multiplication factor (Keff) can be determined by dividing the number of neutrons produced from fission in the fourth generation by the number of neutrons produced from fission in the _________ generation.

a. First

b. Second

c. Third

d. Fifth QUESTION A.06

[1.0 point]

Most textbooks list for a U235 fueled reactor as 0.0065 K/K and eff as being 0.0075 K/K.

What is a main reason that eff is larger than ?

a.

The fuel includes U238 which has a relatively large cross section for fast fission.

b.

Some U238 in the core becomes Pu239 (by neutron absorption) which has a larger cross section for fission.

c.

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

d. Delayed neutrons are born at lower energies than prompt neutrons resulting in less loss due to leakage for these neutrons.

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.07

[1.0 point, 0.25 each]

Match the items in Column A with the isotopes in Column B.

The most important fission product poison is 135Xe. The process that shows how this isotope is formed and its decay is:

Column A Column B 1.

135 Ba 2.

135 Cs 3.

135 I a

fission 11 0

1 +

b fission 6.7 0

1+ 135 fission 9.2 0

1+ c 2.36 d()

4.

135 Te QUESTION A.08

[1.0 point]

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

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

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

c. Recoils with a lower kinetic energy than it had prior to the collision, with the nucleus emitting gamma ray.

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

QUESTION A.09

[1.0 point]

Which ONE of the following is the number of neutrons in the Uranium-235 nucleus (92U235)?

a. 92.

b. 143.

c. 235.

d. The U-235 doesnt have a constant number of neutrons, it fluctuates between 95 and 140.

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.10

[1.0 point]

Reactor period is defined as ____________.

a.

The time required for a reactor power to double.

b. The time required for a reactor power to change by a factor of e.

c. The number of factors of ten that reactor power changes in one minute.

d. The fraction of all neutrons that are born as delayed neutrons.

QUESTION A.11

[1.0 point]

Which ONE of the following describes the production of fission neutrons resulting from thermal neutrons being absorbed in the fuel?

a. Fast Non-Leakage Probability (Lf).

b. Resonance Escape Probability (p).

c. Thermal Utilization Factor (f).

d. Reproduction Factor ().

QUESTION A.12

[1.0 point]

If a source strength is 5000 neutrons per second (N/sec) and it produces the stable neutron count rate of 20000 N/sec. What is the multiplication factor?

a. 0.70

b. 0.75

c. 0.85

d. 0.90

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.13

[1.00 point]

Which ONE of the following best describes the relationship between reactor power and neutron flux?

a.

Reactor power is two times greater than the fission rate of the fuel.

b.

Reactor power increases exponentially as the fission rate increases.

c.

The rate of energy produced by the reactor is linearly proportional to the fission rate in the core.

d.

Thermal power can be calculated by multiplying the neutron flux by the total volume of the core.

QUESTION A.14

[1.00 point]

Which ONE is true about subcritical multiplication? As the reactor approaches criticality, the parameter a.

keff approaches zero.

b.

approaches infinity.

c.

M approaches one.

d.

1/M approaches zero.

QUESTION A.15

[1.0 point]

The reaction 93Np239 _____ + 94Pu239 is an example of:

a. Alpha Decay

b. Beta Decay

c. Gamma Emission

d. Electron Capture

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.16

[1.0 point]

Some neutrons do not come directly from fission, but from fission product decay. These neutrons are called:

a.

Thermal neutrons.

b.

Delayed neutrons.

c.

Neutron Production.

d.

Fission neutrons.

QUESTION A.17

[1.0 point]

Excess reactivity is the amount of reactivity ________.

a.

associated with burnable poisons.

b.

needed to achieve prompt criticality.

c.

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

d.

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

QUESTION A.18

[1.00 point]

What is the kinetic energy range of a thermal neutron?

a.

> 1 MeV b.

100 KeV - 1 MeV c.

1 eV - 100 KeV d.

< 1 eV

(***** END OF SECTION A *****)

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

[1.00 point]

Which ONE of the following correctly describes the limitations of experiment? The experiment with shall NOT be placed inside the reactor experimental facilities.

a.

Total unsecured experiment worth < $0.60.

b.

Total secured reactivity worth exceeding $0.35.

c.

Explosive materials.

d.

Fissionable materials.

QUESTION B.02

[1.0 point]

In an emergency in order to protect the public health and safety, 10 CFR 50 allows the operator to depart from a license condition or a technical specification. What is the minimum level of authorization needed to deviate from this action?

a.

Facility Director b.

Operations Supervisor c.

Licensed Reactor Operator

d. Licensed Senior Reactor Operator QUESTION B.03

[1.0 point]

The exposure rate for a point source is 100 mR/hr at a distance of 4 m. What is the exposure rate at 2 m?

a.

200 mR/hr b.

400 mR/hr c.

600 mR/hr

d. 800 mR/hr

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

[1.00 point]

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

a.

1 rem in a year.

b.

100 mrem per quarter.

c.

5 mrem in any one hour.

d.

2 mrem in any one hour.

QUESTION B.05

[1.0 point]

As a research reactor licensed operator, you were unable to perform the functions of an operator for the minimum number of hours during the previous calendar quarter. What are the minimum number of hours you must complete before resumption of functions authorized by your license?

a. 4

b. 6

c. 8

d. 12 QUESTION B.06

[1.00 point]

Which ONE of the following Safety System Channels requires a minimum number of 2?

a.

Log Count Rate b.

Linear Power c.

Log-N; Period

d. Control Panel 1 Power

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

[1.0 point]

Which ONE of the following surveillances is a channel check?

a. During a startup, you depress a scram button to verify a manual scram.

b. You turn the console key OFF to verify the reactor scram.

c. You adjust Linear channel in accordance with recent data collected from a thermal power calibration.

d. During a steady state power, you compare the readings of the Linear channel and the Log-N channel.

QUESTION B.08

[1.0 point]

The OPERATIONS BOUNDARY is defined as:

a.

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

b.

The area, that extends 500 feet in every direction from center of the reactor.

c.

The area within the site boundary such as the reactor building (or the nearest physical personnel barrier in cases where the reactor building is not a principal physical personnel barrier) where the reactor chief administrator (Facility Director for the RCF) has direct authority over all activities.

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.09

[1.0 point]

A channel of the safety system channels, and visual inspection of the reactor shall be performed daily prior to reactor startup.

a.

Check b.

Test

c. Calibration

d. Maintenance

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

[1.0 point]

Equipment controlled by CP-1 include the following EXCEPT:

a.

NIM bins b.

Compressor c.

High Voltage power supplies

d. Manual scram QUESTION B.11

[1.00 point]

Which ONE of following types of radiation is the HIGHEST Quality Factor specified in 10 CFR 20?

a.

Alpha.

b.

Beta.

c.

Gamma.

d.

Neutron (unknown energy).

QUESTION B.12

[1.0 point]

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

a. Replace a cooling pump with an identical one.

b.

Add additional item in the reactor pre-startup checklist.

c.

Add additional requirement to bypass the Water Dump Valve SCRAM in the RCF Operating Procedure.

d.

Delete Section 5, Design Features, listed in the RCF Technical Specifications because you think this Section is no longer needed.

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

[1.0 point]

Per procedure, all of the following are necessary steps of the Pre-Startup Checklist EXCEPT:

a.

Reactor tank fill b.

Fast dump valve opened.

c.

Core loading

d. Interlock check QUESTION B.14

[1.0 point]

In accordance with the Technical Specifications, which ONE situation below is NOT permissible?

a.

A power level trip setting of 95 watts.

b. Operating coolant temperature of 45 degrees F.

c.

excess reactivity of the reactor less than $0.50.

d.

Criticality detector system removed from service but replaced by an equivalent portable.

QUESTION B.15

[1.00 point]

Per RCF Technical Specifications, which ONE of the following is the specification of the Safety Limit (SL)?

a. The steady state reactor power level shall not exceed 100 W.

b. The maximum fuel pellet temperature shall not exceed 1000 °C.

c. The minimum reactor period shall not less than 5 seconds.

d. The maximum available excess reactivity based on the reference core condition shall not exceed $0.60.

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

[1.0 point]

Which ONE of the following emergencies is categorized as an ALERT?

a.

Loss of off-site electrical power.

b.

Detection of smoke or flames within the RCF Building or Boiler House.

c.

Area Monitor exceeds Alarm Levels when the reactor is shutdown or secured.

d. Phone or other message threatening damage to the facility with an explosive device.

QUESTION B. 17 [1.0 point]

Per RCF 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.

replaced by an equivalent portable unit.

d.

a thin-window GM detector is available to check for personnel or area contamination.

QUESTION B.18

[1.00 point]

The RPI occupational limits is established as:

a.

2% of the legal limit b.

10% of the legal limit c.

20 % of the legal limit

d. Not applicable. Same as the NRC limit

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

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

[1.0 point]

The Uncompensated Ion Chamber powered from:

a.

120 volt AC outlets.

b.

120 volt DC power supply.

c.

300 volt DC battery.

d.

480 volt, three-phase power from the utility grid.

QUESTION C.02

[1.0 point]

Which ONE of the following types of detector is utilized in the area gamma radiation monitoring system?

a.

Geiger-Mueller tube.

b.

Scintillation detector.

c.

Ionization chamber.

d.

Proportional counter.

QUESTION C.03

[1.0 point]

One of the amplifier/single channel amlyzer functions in the Startup channel is to:

a.

Count a total number of neutron and gamma pulses.

b.

Separate gamma pulses from neutron pulses.

c.

Convert a number of pulses to a current in amps.

d.

Convert a number of pulses to a reactor period in seconds.

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

[1.0 point]

Which of the following scrams have bypass provisions?

a.

Door scram and the Water Dump Valve scram.

b.

Log-N period scram and the Water Dump Valve scram.

c.

Door scram and the Linear Power high level scram.

d.

Log-N scram and the Linear Power high level scram.

QUESTION C.05

[1.0 point]

The excess reactivity of the reactor above cold, critical shall not be greater than 0.60$ is an example of:

a.

Safety Limit b.

Limiting Safety System Setting c.

Limiting Conditions for Operation d.

Surveillance Requirement QUESTION C.06

[1.0 point]

Which ONE of the following is TRUE about the facility ventilation system?

a.

In normal mode, all the air is exhausted through a series of charcoal and CWS filters before going out through the stack.

b.

In normal mode, the off-gas system blowers are secured.

c.

Air circulation occurs via natural circulation.

d.

Ventilation system is not required.

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

[1.0 point]

Per RCF Lab Manual, the facility will use ____ foils for the absolute power measurement.

a.

copper b.

nickel c.

gold d.

aluminum QUESTION C.08

[1.0 point]

Which ONE of the following materials is the control rods absorbers?

a. Aluminum.

b. Boron.

c. Cadmium.

d. Stainless Steel.

QUESTION C.09

[1.0 point]

Which ONE of the following is considered an alternate scram mechanism?

a.

Fast moderator dump b.

Reactor room door c.

Reactor power console

d. High current trip

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

[1.0 point]

Following a loss of building electrical power, which ONE of the following best describes on how the reactor tank water is quickly drained to the storage tank?

a.

The filled drain valve and the quick dump valve will fail OPEN, allowing water flow from reactor tank to the storage tank.

b.

Reactor tank water can be quickly drained through the fill line by deenergizing of the air-operated drain valve.

c.

Reactor tank water can be quickly drained by energizing of the quick drain valve that are operated by motor control.

d.

The 50 GPM pump will turn ON and pumping water from the reactor tank to the storage tank.

QUESTION C.11

[1.0 point]

Which ONE of the following is a correct alarm set point for the area gamma monitor located in the control room?

a.

10 mrem/hr.

b.

20 mrem/hr.

c.

40 mrem/hr.

d.

50 mrem/hr.

QUESTION C.12

[1.0 point]

Which ONE of the following is the RCF neutron startup source?

a.

Americium-Beryllium (Am-Be).

b.

Uranium-Beryllium (U-Be).

c.

Radon-Beryllium (Ra-Be).

d.

Plutonium-Beryllium (Pu-Be).

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

[1.0 point]

A signal to indicate the control rod position comes from:

a. Optical encoders.

b. A rack and pinion drive are indicated in percentage of total travel.

c. Three limit switches determine the relative movement of the control rod.

d. A radio-frequency detector measures the height of the control rod extension tube above the piston.

QUESTION C.14

[1.0 point]

When a failure of fuel pins occurs, the Continuous Air Monitor (CAM) alarms due to the release of:

a.

N-16.

b.

Ar-41.

c.

Na-24.

d.

I-135.

QUESTION C.15

[1.0 point]

In accordance with Technical Specifications, which is not a possible requirement for a SECURE Conditions.

a.

The console keys are removed.

b.

Power is unavailable to the control rod drive by the magnet clutches from the safety amplifiers.

c.

There is insufficient moderator available in the reactor to attain criticality.

d. All fuel pins have removed from the reactor.

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

[1.0 point]

Which ONE of the following conditions will cause the reactor interlock?

a.

Reactor period exceeds 25 seconds.

b.

Source range reading is 10 cps.

c.

Fill pump ON.

d.

Chart recorder power ON.

QUESTION C.17

[1.0 point]

The should be energized when the immersion heaters are energized.

a.

Agitator b.

Impeller c.

Neutron source

d. Heating elements QUESTION C.18

[1.0 point]

When not in use, the SPERT (F-1) fuel shall be stored within the storage vault located in the reactor room. The fuel shall be stored in cadmium clad steel tubes with a minimum center-to-center separation of _______ and with no more than ___ SPERT (F-1) fuel pins per tube mounted on a steel wall rack.

a.

8.5 inches, 15.

b.

8.0 inches, 15.

c.

8.5 inches, 10.

d. 8.0 inches, 10.

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

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

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

c REF:

T = Doubling Time/ln(2) = 78 seconds/0.693 = 112.55 113 seconds A.02 Answer:

c REF:

Reactivity added = 156 pcm = 0.00156 k/k T = (-)/et1p = (0.0073 - 0.00156)/((0.1)*(0.00156)) = 37 seconds A.03 Answer:

c REF:

Burns, Example 7.2 (b), page 7-4.

A.04 Answer:

d REF:

Burns, Problem 7.7.4, page 7-17.

A.05 Answer:

c REF:

Burns, Section 3.3.1, page 3-16.

A.06 Answer:

d REF:

Burns, Section 3.2.4, page. 3-12.

A.07 Answer:

a-4; b-3; c-2; d-1.

REF:

Burns, Figure 8.1, page 8-6.

A.08 Answer:

c REF:

DOE Volume 1, NP-01, page 45.

A.09 Answer:

b REF:

Nuclides and Isotopes N = A - Z, 235-92 = 143.

A.10 Answer:

B.17 Answer:

c

RCF Operating procedure, Section C.2.a.

C.18 Answer:

a

Reference:

RCF TS 5.4, page 20.

ML24058A356

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