ML15020A588

Examination Report 50-225/OL-15-01, January 13, 2015, Rensselaer Polytechnic Institute

ML15020A588
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Site:	Rensselaer Polytechnic Institute
Issue date:	02/03/2015
From:	Kevin Hsueh Research and Test Reactors Licensing Branch
To:	Caracappa P Rensselaer Polytechnic Institute
Young, Phillip 415-4094
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ML14336A170	List: ML14336A174 ML15020A588 ML15020A597
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50-225/OL-15-01
Download: ML15020A588 (28)

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February 3, 2015 Peter F. Caracappa, Ph.D, CHP Department of Mechanical, Aerospace and Nuclear Engineering, Building JEC- Room 2032, Rensselaer Polytechnic Institute 110 8th Street Troy, NY 12180-3590

SUBJECT:

EXAMINATION REPORT NO. 50-225/OL-15-01, RENSSELAER POLYTECHNIC INSTITUTE

Dear Dr. Caracappa:

During the week of January 12, 2015, the NRC administered operator licensing examinations at Rensselaer Polytechnic Institute 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. Phillip T. Young at (301) 415-4094 or via e-mail at phillip.young@nrc.gov.

Sincerely, Kevin Hsueh, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-225

Enclosures:

1. Examination Report No. 50-225/OL-15-01

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

Peter F. Caracappa, Ph.D, CHP February 3, 2015 Department of Mechanical, Aerospace and Nuclear Engineering, Building JEC- Room 2032, Rensselaer Polytechnic Institute 110 8th Street Troy, NY 12180-3590

SUBJECT:

EXAMINATION REPORT NO. 50-225/OL-15-01, RENSSELAER POLYTECHNIC INSTITUTE

Dear Dr. Caracappa:

During the week of January 12, 2015, the NRC administered operator licensing examinations at Rensselaer Polytechnic Institute 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. Phillip T. Young at (301) 415-4094 or via e-mail at phillip.young@nrc.gov.

Sincerely,

/RAPatrick Isaac acting for/

Kevin Hsueh, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-225

Enclosures:

1. Examination Report No. 50-225/OL-15-01

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

PUBLIC RidsNrrDprPrta RidsNrrDprPrtb ADAMS Accession No.: ML15020A588; Package ML14336A170 OFFICE NRR/DPR/PROB NRR/DPR/PROB NRR/DPR/PROB NAME PYoung CRevelle KHsueh PIsaac for DATE 01/27/2015 01/29/2015 02/03/2015

OFFICIAL RECORD COPY U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-225/OL-15-01 FACILITY DOCKET NO.: 50-225 FACILITY LICENSE NO.: CX-22 FACILITY: Rensselaer Polytechnic Institute EXAMINATION DATES: January 13, 2015 SUBMITTED BY:

/RA Patrick Isaac acting for/ 02/03/2015 Phillip T. Young, Chief Examiner DATE

SUMMARY

During the week of January 13, 2015 the NRC administered licensing examinations to two Senior Operator Instant (SROI) applicants. The applicants passed all portions of the examination.

REPORT DETAILS

1. Examiners: Phillip T. Young, Chief Examiner, NRC

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 0/0 2/0 2/0 Operating Tests 0/0 2/0 2/0 Overall 0/0 2/0 2/0

3. Exit Meeting:

Phillip T. Young, U.S. NRC Glenn Winters, RPI, Reactor Supervisor The examiner thanked the facility for their assistance ensuring the examination administration went smoothly and their feedback on the written examination.

Enclosure 1

FACILITY COMMENTS:

Dear Mr. Young,

I had time to more closely review the written exam, and, perhaps, be more critical toward the questions. Some could have been better worded, or made more applicable to our facility.

COMMENT: Question A.10:

As a reactor continues to operate over time, for a constant power level, the average neutron flux:

A) decreases, due to the increase in fission product poisons B) decreases, because fuel is being depleted C) increases, in order to compensate for fuel depletion D) remains the same At the RCF, the low power does not create enough burn-up to deplete fuel and the neutron flux remains constant. For our facility, then, D would be correct. A reactor which depletes fuel would respond differently.

NRC Resolution:

Since the question is not applicable to the operation of the RCF reactor, the question is deleted from the examination and grading adjusted accordingly.

COMMENT: Question A.11:

The neutron microscopic cross section for absorption, sigma_a, generally:

A) increases as neutron energy increases B) decreases as neutron energy increases C) increases as the mass of the target nucleus increases D) decreases as the mass of the target nuclear increases Depends on the energy range in question. Epithermal resonances cause both increases and decreases of absorption cross-section. True, the thermal energy region sees a decrease with increased energy, but the question didnt limit energy to just thermal values. Considering resonances, the question has no completely correct answer.

NRC Resolution:

The question states generally and the reference is correct, comment not accepted.

COMMENT: Question A.12:

A reactor is operating at criticality. Instantaneously, all of the delayed neutrons are suddenly removed from the reactor. The K_eff of the reactor in this state would be approximately:

A) 1.007 B) 1.000 C) 0.993 D) 0.000 FACILITY COMMENTS: (continued)

If I define Keff as production/(absorption + leakage) [coincidently, the next question], the correct answer is B since the question only removes the existing delayed neutrons, and does not change the production of additional delayed neutrons. If the delayed neutron precursors, or the production rate were removed, then C is correct. I realize the question was intended to determine the magnitude of the delayed neutron fraction, but the awkward scenario makes this an easy question to overthink, leading to potentially two correct answers.

NRC Resolution:

The point of the question is to test the applicant on the value of the beta fraction, the answer as stated is correct. The comment is not accepted.

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: RPI REACTOR TYPE: Critical Experimental DATE ADMINISTERED: 01/13/2015 CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheet provided. Attach the answer sheets to the examination. Points for each question are indicated in parentheses for each question. A 70%

in each section 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 15.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 16.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 16.00 33.3 C. FACILITY AND RADIATION MONITORING SYSTEMS 48.00  % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature Enclosure 2

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 Q = m cp T CR1 (1-Keff)1 = CR2 (1-Keff)2 SUR = 26.06/ P = P0 10SUR(t)

P = P0 e(t/) = (*/) + [(-)/eff]

eff = 0.1 seconds-1 DR1D12 = DR2D22 DR = DRoe-t DR = 6CiE/D2

= (Keff - 1)/Keff 1 eV = 1.6x10-19 watt-sec.

1 gallon water = 8.34 pounds 1 Btu = 778 ft-lbf F = 9/5 C + 32 1 Mw = 3.41x106 BTU/hr C = 5/9 ( F - 32)

DR - Rem, Ci - curies, E - Mev, R - feet 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lbm 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 1 BTU = 778 ft-lbf ºF = 9/5 ºC + 32 1 gal (H2O) . 8 lbm ºC = 5/9 (ºF - 32) cP = 1.0 BTU/hr/lbm/ºF cp = 1 cal/sec/gm/ºC Section A - Reactor Theory, Thermo & Facility Operating Characteristics Question A.001 (1.0 point) {1.0}

A reactor fuel consisting of only U-235 and U-238 is 20% enriched. This means that:

a. 20% of the volume of the fuel consists of U-235.

b. 20% of the weight of the fuel consists of U-235.

c. the ratio of the number of U-235 atoms to the number of U-238 atoms is 0.20 (20%).

d. 20% of the total number of atoms in the fuel consists of U-235.

Answer: A.01 b.

Reference:

Lamarsh, Introduction to Nuclear Engineering, 2nd Edition, page 112.

Question A.002 (1.0 point) {2.0}

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 Beta-effective Answer: A.02 b.

Reference:

Lamarsh, Introduction to Nuclear Engineering, 3rd Edition, Section 7.2, page 340.

Question A.003 (1.0 point) {3.0}

With the reactor critical at 10 watts, a rod withdrawal results in a power increase with a doubling time of 40 seconds. Reactor power two minutes later is:

a. 30 watts

b. 60 watts

c. 80 watts

d. 90 watts Answer: A.03 c.

Reference:

Laboratory 3 Experiment. Period = (Doubling Time)/0.693 = 57.7 sec.

P = Poe120/57.7 = 10e2.08 = 80 watts Section A - Reactor Theory, Thermo & Facility Operating Characteristics Question A.004 (1.0 point) {4.0}

A thermal neutron is a neutron which:

a. is produced as a result of thermal fission.

b. has been produced several seconds after its initiating fission occurred.

c. possesses thermal rather than kinetic energy.

d. experiences no net change in its energy after several collisions with atoms of the diffusing medium.

Answer: A.04 d.

Reference:

Laboratory 5 Experiment Question A.005 (1.0 point) {5.0}

The factor in the six-factor formula which is most affected by control rod position is:

a. Resonance escape probability

b. Fast fission factor

c. Neutron reproduction factor

d. Thermal utilization factor Answer: A.05 d.

Reference:

Lamarsh, Introduction to Nuclear Engineering, 3rd Ed, Section 6.1, page 269.

Question A.006 (1.0 point) {6.0}

Which ONE statement below describes a positive moderator temperature coefficient?

a. When moderator temperature increases, positive reactivity is added.

b. When moderator temperature decreases, positive reactivity is added.

c. When moderator temperature increases, negative reactivity is added.

d. When moderator temperature increases, reactor power decreases.

Answer: A.06 a.

Reference:

Laboratory 6 Experiment.

Section A - Reactor Theory, Thermo & Facility Operating Characteristics Question A.007 (1.0 point) {7.0}

Core excess reactivity changes with

a. Fuel burnup

b. Control Rod Height

c. Neutron Level

d. Reactor Power Level Answer: A.07 a.

Reference:

Burn, R., Introduction to Nuclear Reactor Operations, © 1982, § 6.2 p. 6-1 6-4.

Question A.008 (1.0 point) {8.0}

Which condition below describes a reactor which is exactly critical.

a. k = 1; delta k/k = 1

b. k = 1; delta k/k = 0

c. k = 0; delta k/k = 1

d. k = 0; delta k/k = 0 Answer: A.08 b.

Reference:

Standard NRC Question Question A.009 (1.0 point) {9.0}

As a result of beta decay:

a. The atomic mass number decreases by 1, and the number of protons remains constant.

b. The atomic mass number remains constant, and the number of protons increases by 1.

c. The atomic mass number decreases by 1, and the number of protons decreases by 1.

d. The atomic mass number remains constant, and the number of protons remains constant Answer: A.09 b.

Reference:

Lamarsh, Introduction to Nuclear Engineering, 2nd Edition, page 71.

Section A - Reactor Theory, Thermo & Facility Operating Characteristics Question A.010 (1.0 point) {10.0} DELETED As a reactor continues to operate over time, for a constant power level, the average neutron flux:

a. decreases, due to the increase in fission product poisons.

b. decreases, because fuel is being depleted.

c. increases, in order to compensate for fuel depletion.

d. remains the same.

Answer: A.10 c.

Reference:

Burn, Introduction to Nuclear Reactor Operations, page 2-50.

Question A.011 (1.0 point) {11.0}

The neutron microscopic cross section for absorption, a , generally:

a. increases as neutron energy increases.

b. decreases as neutron energy increases.

c. increases as the mass of the target nucleus increases.

d. decreases as the mass of the target nucleus increases.

Answer: A.11 b.

Reference:

Burn, Introduction to Nuclear Reactor Operations, page 2-36.

Question A.012 (1.0 point) {12.0}

A reactor is operating at criticality. Instantaneously, all of the delayed neutrons are suddenly removed from the reactor. The Keff of the reactor in this state would be approximately:

a. 1.007

b. 1.000

c. 0.993

d. 0.000 Answer: A.12 c.

Reference:

DOE Fundamentals Handbook, Module 2, page 30.

Section A - Reactor Theory, Thermo & Facility Operating Characteristics Question A.013 (1.0 point) {13.0}

The effective neutron multiplication factor, Keff, is defined as:

a. absorption/(production + leakage)

b. (production + leakage)/absorption

c. (absorption + leakage)/production

d. production/(absorption + leakage)

Answer: A.13 d.

Reference:

Lamarsh, Introduction to Nuclear Engineering, 2nd Edition, page 195.

Question A.014 (1.0 point) {14.0}

Which ONE of the following statements describes the difference between Differential (DRW) and Integral (IRW) rod worth curves?

a. DRW relates the worth of the rod per increment of movement to rod position. IRW relates the total reactivity added by the rod to the rod position.

b. DRW relates the time rate of reactivity change to rod position. IRW relates the total reactivity in the core to the time rate of reactivity change.

c. IRW relates the worth of the rod per increment of movement to rod position. DRW relates the total reactivity added by the rod to the rod position.

d. IRW is the slope of the DRW at a given rod position Answer: A.14 a.

Reference:

Laboratory 4 Experiment.

Section A - Reactor Theory, Thermo & Facility Operating Characteristics Question A.015 (1.0 point) {15.0}

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

a. Sm149

b. U235

c. Xe135

d. B10 Answer: A.15 c.

Reference:

Lamarsh, J. Introduction to Nuclear Engineering p. 738 Sm149 (41,000 b);

U235 (687 b); Xe135 (2.65 x 106 b); B10 (3840 b)

Question A.016 (1.0 point) {16.0}

If eff =0.00765, then what would the reactivity be in k/k if $1.75 were added to a reactor core?

a. 0.0019 k/k

b. 0.0134 k/k

c. 1.0134 k/k

d. 1.737 k/k Answer: A.16 b

Reference:

NEEP 234 Reactor Physics II pg. 2

(*** End of Section A ***)

Section B - Normal/Emergency Operating Procedures & Radiological Controls Question B.001 (1.0 point) {1.0}

Which ONE of the following describes the Technical Specifications limits pertaining to control rod operability?

a. All four control rods must be operable for reactor operation.

b. One control rod may be inoperable provided it is fully inserted.

c. One control rod may be inoperable provided a $0.9 shutdown margin is maintained with the inoperable rod withdrawn.

d. Two control rods may be inoperable provided they are not adjacent AND the moderator dump scram is operable.

Answer: B.01 a.

Reference:

Technical Specifications, Section 3.2.

Question B.002 (1.0 point) {2.0}

"The excess reactivity of the reactor core above cold, clean critical shall not be greater than

$0.60." This is an example of a(n):

a. safety limit.

b. limiting safety system setting.

c. limiting condition for operation.

d. surveillance requirement.

Answer: B.02 c.

Reference:

Technical Specifications, Section 3.1.

Section B - Normal/Emergency Operating Procedures & Radiological Controls Question B.003 (1.0 point) {3.0}

In accordance with 10 CFR Part 50.54(x), under what conditions can an operator take reasonable action that departs from a license condition or a Technical Specification?

a. In any emergency.

b. In an emergency, when the action is needed to protect health and safety and no other action is immediately apparent.

c. In an emergency declared by the Emergency Director.

d. In an emergency declared by the Emergency Director along with the approval of the Senior Reactor Operator on site.

Answer: B.03 b.

Reference:

10CFR50.54 (x)

Question B.004 (1.0 point) {4.0}

In accordance with Technical Specifications, a REACTOR SHUTDOWN condition requires all control rods are fully inserted and:

a. the console key is removed.

b. the reactor is shutdown by at least $1.00.

c. no operations are in progress which involve control rod maintenance.

d. no operations are in progress which involve moving fuel pins in the reactor vessel.

Answer: B.04 b.

Reference:

Technical Specifications, Definitions.

Question B.005 (1.0 point) {5.0}

The reactor parameter which is protected by Safety Limits is:

a. steady state power level.

b. fuel pellet temperature.

c. moderator level.

d. fuel clad temperature.

Answer: B.05 b.

Reference:

Technical Specifications, 2.1.

Section B - Normal/Emergency Operating Procedures & Radiological Controls Question B.006 (1.0 point) {6.0}

The gamma radiation level from a point source is 10 R/hour at a distance of 1 foot from the source. The radiation level 8 feet from the source is approximately:

a. 19 mR/hour

b. 156 mR/hour

c. 625 mR/hour

d. 1250 mR/hour Answer: B.06 b.

Reference:

DR1D12 = DR2D22 (10)(1) = DR2(64) ; DR2 = 10/64 = 0.156 R/hr = 156 mR/hr.

Question B.007 (1.0 point) {7.0}

If smoke or fire is detected, the operator must immediately:

a. stop all rod withdrawal and notify the Senior Reactor Operator.

b. determine the location, and close down all fans.

c. notify the Operations Supervisor.

d. shutdown and secure the reactor.

Answer: B.07 d.

Reference:

RPI Emergency Procedures, Section 6.2.

Question B.008 (1.0 point) {8.0}

Which ONE of the following Non-Radiological Emergencies does NOT require that the reactor be shut down and secured?

a. Act of civil disorder.

b. Smoke or fire.

c. Human injury.

d. Bomb threat.

Answer: B.08 c.

Reference:

RPI Emergency Procedures, Section 6.6.

Section B - Normal/Emergency Operating Procedures & Radiological Controls Question B.009 (1.0 point) {9.0}

Two point sources have the same curie strength. Source As gammas have an energy of 1 Mev, whereas Source Bs gammas have an energy of 2 Mev. You obtain a reading from the same GM tube 10 feet from each source. Concerning the two readings, which ONE of the following statements is correct?

a. The reading from Source B is four times that of Source A.

b. The reading from Source B is twice that of Source A.

c. Both readings are the same.

d. The reading from Source B is half that of Source A.

Answer: B.09 c.

Reference:

GM tube cannot distinguish between energies.

Question B.010 (1.0 point) {10.0}

The dose rate from a mixed beta-gamma source is 100 mr/hour at a distance of one (1) foot, and is 0.1 mr/hour at a distance of twenty (20) feet. What percentage of the source consists of beta radiation?

a. 20%

b. 40%

c. 60%

d. 80%

Answer: B.10 c.

Reference:

At 20 feet, there is no beta radiation. Gamma at 20 feet = 0.1 mr/hour, gamma at 1 foot = 40 mr/hour. Therefore beta at 1 foot = 60 mr/hour = 60%.

Section B - Normal/Emergency Operating Procedures & Radiological Controls Question B.011 (1.0 point) {11.0}

In accordance with the Power Calibration Procedure, if the absolute power level of the log power chamber does not agree within 10% of the log power recorder:

a. The log power recorder scale must be recalibrated.

b. The position of the chamber must be adjusted to give the proper indication.

c. The high voltage to the chamber must be adjusted to give the proper indication.

d. The compensating voltage of the chamber must be adjusted to give the proper indication.

Answer: B.11 a.

Reference:

Surveillance Procedures, Power Calibration.

Question B.012 (1.0 point) {12.0}

Two Emergency classes for the Critical Facility are:

a. Protective Action Guide and Emergency Action Level.

b. Personnel Emergency and Protective Action Guide.

c. Emergency Action Level and Emergency Alert.

d. Personnel Emergency and Emergency Alert.

Answer: B.12 d.

Reference:

Emergency Plan, Section 4.

Question B.013 (1.0 point) {13.0}

"Area for which offsite emergency planning is performed to assure that prompt and effective actions can be taken to protect the public in the event of an accident" defines a (an):

a. site boundary

b. operations boundary

c. emergency support center

d. emergency planning zone Answer: B.13 d.

Reference:

Emergency Plan, Definitions.

Section B - Normal/Emergency Operating Procedures & Radiological Controls Question B.014 (1.0 point) {14.0}

A KNOWN CORE is one for which:

a. the core has been critical and the critical bank position has been measured.

b. fuel movement may occur with only three control rods and rod drives operational.

c. the inverse multiplication method is used for fuel addition in the initial approach to criticality.

d. the addition, movement or removal of fuel is limited to $0.30 of reactivity or four fuel pins,whichever is smaller.

Answer: B.14 a.

Reference:

Operating Procedures, G, Fuel Handling.

Question B.015 (1.0 point) {15.0}

Prior to the disposal of water from the reactor tank, storage tank or sump, it must be tested to ensure:

a. the activity is within limits

b. the pH is between 4.7 and 7.0

c. the temperature is less than 70 deg. F

d. the particulate concentration is within limits Answer: B.15 a.

Reference:

Operating Procedures, I, Water Disposal.

Section C: Facility and Radiation Monitoring Systems Question B.016 (1.0 point) {1.0}

The following is an example of a portable ?

a. Neutron detector

b. Alpha detector

c. Geiger-Mueller detector

d. Air sampler Answer: B.16 a

Reference:

http://www.deqtech.com/Ludlum_Medical_Physics/Products/m2241-4.htm

(*** End of Section B ***)

Section C: Facility and Radiation Monitoring Systems Question C.001 (1.0 point) {1.0}

Which ONE of the following will result in a control rod withdrawal interlock (i.e., rod remains as is)?

a. Neutron flux < 2 cps

b. Failure of the power supply

c. Reactor period > 20 seconds

d. Water level in tank > 11 inches above top grid Answer: C.01 a.

Reference:

Technical Specifications, 3.2 - Reactor Control and Safety Systems Question C.002 (1.0 point) {2.0}

If control rod sensitivity is known, withdrawal of the rods as a bank is permitted as long as:

a. reactor period is greater than 20 seconds

b. the reactivity addition does not exceed $0.05 per second

c. the reactivity addition does not exceed $0.20 per second

d. the source level channel has increased by less than one decade Answer: C.02 b.

Reference:

Operating Procedures, Section A.

Question C.003 (1.0 point) {3.0}

The reactor will scram if one of the following interlocks is not satisfied:

a. Reactor Period > 15 sec

b. Reactor Console keys(2) on

c. Line voltage to records > 110V

d. Moderator-Reflector water fill off Answer: C.03 b.

Reference:

Technical Specification (3.2) Table 2 (interlock)

Section C: Facility and Radiation Monitoring Systems Question C.004 (1.0 point) {4.0}

Which of the following is the RPI RCF TS temperature minimum limit for the reactor tank water?

a. 40°F

b. 50°F

c. 80°F

d. 100°F Answer: C.04 b.

Reference:

Technical Specifications 3.1 - Reactor Core Parameters Question C.005 (1.0 point) {5.0}

You are conducting a reactor startup and begin to pull rods. When doing so you observe that there is no outward rod motion. Which of the following is most likely the cause for the inability to move rods outward?

a. Reactor water tank temperature is below the minimum setpoint value

b. Startup Channel A count rate reads 1 cps

c. Reactor period is 20 seconds

d. Reactor water fill pump is on Answer: C.05 d.

Reference:

RPI SAR, Figure 7.2, November 2002 & June 2011 Question C.006 (1.0 point) {6.0}

Which of the following would you most likely find in the control rod baskets?

a. Lead cement which supports the absorber section

b. A reflector section made of graphite

c. An absorber section made of boron

d. An aluminum oxide (Al2O3) insulator Answer: C.06 c.

Reference:

RPI SAR, Section 4.2.1, November 2002 & June 2011 Section C: Facility and Radiation Monitoring Systems Question C.007 (1.0 point) {7.0}

By RPI RCF TS, which of the following is considered the auxiliary reactor scram?

a. Turning the reactor key to the off position

b. Intentionally opening the reactor door

c. The moderator-reflector water dump

d. Opening the breaker which disconnects the electrical power of the facility from the reactor Answer: C.07 c.

Reference:

Technical Specifications, 3.2 - Reactor Control and Safety Systems Question C.008 (1.0 point) {8.0}

What is the maximum fill capacity of the reactor water tank?

a. >70 inches

b. <68 inches

c. <50 inches

d. <19.5 inches Answer: C.08 b.

Reference:

RPI RCF Operating Procedures Section 8.1 Question C.009 (1.0 point) {9.0}

What is the setpoint for the control room radiation monitor alarm?

a. 5 mr/hr

b. 10 mr/hr

c. 40 mr/hr

d. 100 mr/hr Answer: C.09 b.

Reference:

RPI RCF Operating Procedures Section 8.1 Section C: Facility and Radiation Monitoring Systems Question C.010 (1.0 point) {10.0}

The SPERT fuel elements consist of:

a. 4.8% enriched uranium with stainless steel clad.

b. 35.2% enriched uranium with stainless steel clad.

c. 8% enriched uranium with aluminum clad.

d. 35.2% enriched uranium with aluminum clad.

Answer: C.10 a.

Reference:

SAR, 4.2.1 Reactor Fuel Question C.011 (1.0 point) {11.0}

At the RPI CRF when the reactor is in the Standard configuration, you would expect fuel pins in an octagonal array.

a. 332

b. 327

c. 323

d. 319 Answer: C.11 a.

Reference:

RPI SAR, Section 4. Reactor Description, November 2002 & June 2011 Question C.012 (1.0 point) {12.0}

When there is a loss of power, the reactor tank pump:

a. suction valve fails OPEN, and the discharge valve fails CLOSED.

b. suction valve fails OPEN, and the discharge valve fails OPEN.

c. suction valve fails CLOSED, and the discharge valve fails CLOSED.

d. suction valve fails CLOSED, while the discharge valve fails OPEN.

Answer: C.12 a.

Reference:

SAR Figure 5.1.

Section C: Facility and Radiation Monitoring Systems Question C.013 (1.0 point) {13.0}

The area gamma monitoring system has detectors located in the control room, in the reactor room:

a. on the reactor deck and outside the reactor room window.

b. in the counting room and outside the reactor room window.

c. on the reactor deck and in the fuel storage vault.

d. in the counting room and in the fuel storage vault.

Answer: C.13 a.

Reference:

SAR 7.7 Radiation Monitoring System Question C.014 (1.0 point) {14.0}

The structure within the core that forms the base of the three-tiered core-support structure is the:

a. carrier plate.

b. plastic spacer plate.

c. fuel pin lattice plate.

d. unistrut support plate.

Answer: C.14 a.

Reference:

SAR - Figure 4.12: Core Support Structure Question C.015 (1.0 point) {15.0}

The reactor room ventilation system:

a. shares a vent with the control room ventilation system

b. exhaust fan starts up in response to high radiation alarms

c. exhaust vent closes in response to high radiation alarms

d. operates by natural circulation, with its own vent to the outside stack Answer: C.15 d.

Reference:

SAR page 9-1 Section C: Facility and Radiation Monitoring Systems Question C.016 (1.0 point) {16.0}

A linear power channel (LP1 or LP2) uses a (an):

a. fission chamber

b. boron-trifluoride detector

c. compensated ion chamber

d. uncompensated ion chamber Answer: C.16 d.

Reference:

SAR - 7.2 Design of Instrumentation and Control Systems

(*** End of Examination ***)