Text

Examination Report No. 50-225/OL-19-01
	ML18319A107
Person / Time
Site:	Rensselaer Polytechnic Institute
Issue date:	11/14/2018
From:	Anthony Mendiola; Research and Test Reactors Oversight Projects Branch
To:	Ji W; Rensselaer Polytechnic Institute
	Randiki C
Shared Package
ML18243A315	List: ML18243A317; ML18319A107;
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	50-225/19-001
	Download: ML18319A107 (39)
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November 14, 2018 Dr. Wei Ji, Director Reactor Critical Facility Rensselaer Polytechnic Institute 110 8th Street NES Building 1-10 Troy, NY 12180 3590

SUBJECT:

EXAMINATION REPORT NO. 50-225/OL-19-01, RENSSELAER POLYTECHNIC INSTITUTE

Dear Dr. Ji:

During the week of October 29, 2018, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Rensselaer Polytechnic Institute research reactor. The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

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

Sincerely,

/RA/

Anthony J. Mendiola, Chief Research and Test Reactors Oversight Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 50-225

Enclosures:

1. Examination Report No. 50-225/OL 19-01

2. Written examination cc: Glenn Winters, RPI cc: w/o enclosures: See next page

ML18319A017 NRR-079 OFFICE NRR/DLP/PROB/CE NRR/DLP/IOLB/OLA NRR/DLP/PROB/BC NAME JNguyen CJRandiki AMendiola DATE 11/7/2018 11/13/2018 11/14/2018 Rensselaer Polytechnic Institute Docket No. 50-225 cc:

Mayor of the City of Schenectady RCF Supervisor Schenectady City Hall NES Building, Room 1-10, 105 Jay St. MANE Department Schenectady, NY 12305 Rensselaer Polytechnic Institute 110 8th St.

Dr. Shekhar Garde Troy, NY 12180 Dean, School of Engineering Rensselaer Polytechnic Institute Annette Chism, Director EH&S 110 8th Street Rensselaer Polytechnic Institute Troy, NY 12181-3590 21 Union Street Gurley Building 2nd Floor Reactor Operations Supervisor Troy, NY 12180 JEC Room 2049 Department of Mechanical Aerospace State Liaison Officer Designee and Nuclear Engineering Senior Project Manager Rensselaer Polytechnic Institute Radioactive Waste Policy and Nuclear 110 8th Street Coordination Troy, NY 12180-3590 New York State Energy Research &

Development Authority Chief, Radiation Section 17 Columbia Circle Division of Environmental Remediation Albany, NY 12203-6399 NY State Dept. of Environmental Conservation Test, Research and Training 625 Broadway Reactor Newsletter Albany, NY 12233-7255 P.O. Box 118300 University of Florida Radiation Safety Officer Gainesville, FL 32611 NES Building, Room 1-10, MANE Department Rensselaer Polytechnic Institute 110 8th St.

Troy, NY 12180-3590

U.S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-225/OL-19-01 FACILITY DOCKET NO.: 50-225 FACILITY LICENSE NO.: CX-22 FACILITY: Critical EXAMINATION DATES: October 30, 2018 SUBMITTED BY: /RA/ 11/07/2018 John T. Nguyen, Chief Examiner Date

SUMMARY

During the week of October 29, 2018, the NRC administered an operator licensing examination to one Senior Reactor Operator candidate. The candidate passed all applicable portions of the examination.

REPORT DETAILS

1. Examiner: John T. Nguyen, 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:

John T. Nguyen, Chief Examiner, NRC Glenn Winters, Operations Supervisor, RPI Upon completion of the 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.

ENCLOSURE 1

U.S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: Rensselaer Polytechnic Institute REACTOR TYPE: Critical Facility DATE ADMINISTERED: 10/30/2018 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 ENCLOSURE 2

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

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

A01 a b c d ___

A02 a b c d ___

A03 a b c d ___

A04 a b c d ___

A05 a b c d ___

A06 a b c d ___

A07 a b c d ___

A08 a b c d ___

A09 a b c d ___

A10 a b c d ___

A11 a b c d ___

A12 a ___ b ___ c ___ d ___ (0.25 each)

A13 a b c d ___

A14 a b c d ___

A15 a b c d ___

A16 a b c d ___

A17 a ___ b ___ c ___ d ___ (0.25 each)

A18 a b c d ___

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

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

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

B01 a b c d ___

B02 a b c d ___

B03 a b c d ___

B04 a b c d ___

B05 a b c d ___

B06 a b c d ___

B07 a b c d ___

B08 a b c d ___

B09 a b c 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 *****)

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.

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 ___ (0.50 each)

C07 a b c d ___

C08 a ___ b ___ c ___ d ___ (0.25 each)

C09 a ___ b ___ c ___ d ___ (0.50 each)

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 ___ (0.25 each)

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

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

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

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

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

3. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

4. Use black ink or dark pencil only to facilitate legible reproductions.

5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each Answer sheet.

6. Mark your Answers on the Answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.

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

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

9. When turning in your examination, assemble the completed examination with examination questions, examination aids and Answer sheets. In addition turn in all scrap paper.

10. Ensure all information you wish to have evaluated as part of your Answer is on your Answer sheet. Scrap paper will be disposed of immediately following the examination.

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

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

EQUATION SHEET

( )2 eff = 0.1sec 1 Q&= m&cP T = m&H =UAT Pmax =

(2 )

t P = P0 e S S SCR = * =1x104 sec 1 K eff eff + &

SUR = 26 .06

( ) (

CR1 1 K eff1 = CR2 1 K eff 2 ) CR1 ( 1 ) = CR2 ( 2 )

(1 ) M=

1

= 2 CR P = P0 10SUR(t )

P= P0 1 K eff CR1 1 K eff1 1 K eff

M= SDM = =

1 K eff 2 K eff

0.693 K eff 2 K eff1

+ T1 =

eff + & 2 K eff1 K eff 2 K eff 1

= DR = DR0 e t 2 DR1 d1 = DR2 d 2 2

K eff 6 Ci E (n) ( 2 )2 = (1 )2 DR =

R2 Peak2 Peak1 DR - Rem, Ci - curies, E - Mev, R - feet 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lb 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 1 BTU = 778 ft-lb °F = 9/5 °C + 32 1 gal (H2O) 8 lb °C = 5/9 (°F - 32) cP = 1.0 BTU/hr/lb/°F cp = 1 cal/sec/gm/°C

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.01 [1.0 point]

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

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

a. Reproduction Factor.

b. Thermal Utilization Factor.

c. Resonance Escape Probability.

d. Thermal Non-leakage Probability.

QUESTION A.02 [1.0 point]

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

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

b. Removal of an experiment containing borated graphite.

c. Increase of pool water temperature.

d. Burnout of Xenon in the core.

QUESTION A.03 [1.0 point]

The reactor is critical at 1.0 watts. A control rod is withdrawn to insert a positive reactivity of 0.10% k/k. Which ONE of the following will be the stable reactor period as a result of this reactivity insertion? Given beta effective = 0.0078

a. 22 seconds

b. 46 seconds

c. 68 seconds

d. 80 seconds

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

Five minutes after shutting down the reactor, reactor power is 3 x 106 counts per minute. Which ONE of the following is the count rate you would expect to three minutes later?

a. 1 x 106 cpm

b. 8 x 105 cpm

c. 5 x 105 cpm

d. 3 x 105 cpm QUESTION A.05 [1.0 point]

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

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

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

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

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

QUESTION A.06 [1.0 point]

The delayed neutron precursor () for U235 is 0.0065. However, when calculating reactor parameters you use eff with a value of ~0.0076. Which ONE of the following is a main reason why eff is larger than ?

a. Since the fuel also contains U-238 which has a relatively large for fast fission.

b. U-238 in the core becomes Pu-239 (by neutron absorption), which has a higher for fission.

c. Delayed neutrons are born at higher energies than prompt neutrons resulting in a greater a number of delayed neutrons.

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

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

Reactor power is critical at 1 mW. Reactor operator makes a mistake by inserting a sample worth of +0.008 k/k into the reactor core. Which ONE of the following best describes the reactor kinetic? The reactor is:

a. subcritical

b. critical

c. supercritical

d. prompt critical QUESTION A.08 [1.0 point]

Reactor power is rising on a 10 second period. Approximately how long will it take for power to quadruple?

a. 14 seconds

b. 29 seconds

c. 55 seconds

d. 72 seconds QUESTION A.09 [1.0 point]

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

a. constant.

b. continually decreasing.

c. continually increasing.

d. increasing, then constant.

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

Graph below depicts the different regions of operation for gas-filled detectors. Which ONE of the following labels is the Geiger-Mueller region?

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.11 [1.0 point]

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

a. 0.150 k/k

b. 0.197 k/k

c. 0.250 k/k

d. 0.297 k/k QUESTION A.12 [1.0 point, 0.25 each]

A fissile material is one that causes fission upon absorption of a thermal neutron. A fertile material is one that will become a fissile material upon absorption of a thermal neutron. Identify each of the listed isotopes as either fissile or fertile.

a. Th-232

b. U-235

c. U-238

d. Pu-239 QUESTION A.13 [1.0 point]

The Keff for the reactor is 0.955. The reactivity needed to bring the reactor to the criticality is:

a. +0.0471

b. +0.0450

c. -0.0471

d. -0.0450

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.14 [1.0 point]

A thermal neutron is a neutron which:

a. is produced as a result of thermal fission.

b. possesses thermal rather than kinetic energy.

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

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

QUESTION A.15 [1.0 point]

The reactor is critical and increasing in power. Power has increased from 20 mW to 80 mW in 60 seconds. How long will it take at this rate for power to increase from 0.080 W to 160 W?

a. 0.5 minute

b. 2.5 minutes

c. 5.5 minutes

d. 10.5 minutes QUESTION A.16 [1.0 point]

Control Rod withdrawal mainly changes Keff by changing the

a. fast fission factor ().

b. thermal utilization factor (f).

c. neutron reproduction factor ().

d. resonance escape probability (p).

QUESTION A.17 [1.0 point, 0.25 each]

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

a. 92U 238 90Th 234 +X

b. 83Bi 203 82Pb 203 + X

c. 2He 4 + 4Be9 6C +

12 X

d. 84Po 210 82Pb 206 +X

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.18 [1.0 point]

Reactor is at 100 % power. The following graph shows the reactor time behavior following a reactor scram. Which ONE of the following best describes the transition of power between point C and D after the initial rod insertion? .

a. An immediate decrease in the prompt neutron fraction due to leakage, absorption, and a reduction in the fission rate.

b. Fission product gases such as xenon begin to buildup causing the expansion of fuel density.

c. The longest lived delayed neutron precursor begins to effect such as Bromine-87.

d. The short lived delayed neutron precursors begin to effect such as Iodine-137, Cesium-144, and Krypton-95.

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics

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

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

The MAIN purpose to encapsulate a corrosive material irradiated in the reactor core is to prevent:

a. damage on the fuel cladding.

b. pressure build up in the sample holder.

c. possibility of fires in the vicinity of the reactor.

d. maximum reactivity change during removal or insertion of experiment.

QUESTION B.02 [1.0 point]

How long will it take a 1 Curie source, with a half-life of 2 year, to decay to 0.1 Curie?

a. 4.6 Years

b. 6.6 Years

c. 10.6 Years

d. 16.6 Years QUESTION B.03 [1.0 point]

Which ONE of the following statements is NOT true for the Limiting Conditions for Operation?

a. The maximum reactivity worth of any clean fuel pin shall be $0.20.

b. The thermal power level shall be controlled so as not to exceed 1 kW, and the integrated thermal power for any consecutive 365 days shall not exceed 2 kW-hr.

c. The auxiliary reactor scram (moderator-reflector water dump) shall add negative reactivity within one minute of its activation.

d. The scram time for each control rod from its fully withdrawn position to its fully inserted position shall be less than or equal to 900 milliseconds. This includes a maximum 50 millisecond magnetic clutch release time.

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

Per RCF Technical Specifications, what is a minimum level of authority to approve minor changes to previous approved experiments that do not change the effectiveness or the original intent of the experiments?

a. Nuclear Safety and Review Board (NSRB)

b. Radiation Safety Officer

c. Operations Supervisor

d. Senior Reactor Operators QUESTION B.05 [1.0 point]

Per RCF Technical Specifications, when the Area Gamma Monitor (AGM) over the reactor room (high level monitor) is inoperable, the reactor operations may continue only if:

a. Control room AGM is still operable.

b. Critical detector system is still operable.

c. Constant Air Monitor and the control room AGM are still operable.

d. Portable gamma sensitive instrument having their own alarm is substituted.

QUESTION B.06 [1.0 point]

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

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

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

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

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

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

You are currently the licensed operator at RCF. Which ONE of the following will violate 10 CFR Part 55.53 Conditions of licenses?

a. Last requalification operating test was 14 months ago.

b. Last requalification written examination was 20 months ago.

c. Last quarter you were the licensed operator for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

d. Last licensed renewal was 48 months ago.

QUESTION B.08 [1.0 point]

A radiation survey of an area reveals a general radiation reading of 1 mrem/hr. There is, however, a small pipe which reads 20 mrem/hr at one (1) meter. Which ONE of the following defines the posting requirements for the area in accordance with 10CFR20?

a. Control Access Area.

b. Caution, Radiation Area.

c. Caution, High Radiation Area.

d. Grave Danger, Very High Radiation Area.

QUESTION B.09 [1.0 point]

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

a. 0.10

b. 0.53

c. 0.67

d. 1.54

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

Per RCF Technical Specifications, which ONE of the following will NOT violate the TS?

a. The minimum operating temperature = 50 °F

b. The excess reactivity = 0.60 $

c. Steady State reactor power = 1200 mW

d. Reactor Period = 5 seconds QUESTION B.11 [1.0 point]

An irradiated sample provides a dose rate of 0.5 rem/hr at 2 ft. Approximately how far from the sample reads 5 mrem/hr?

a. 6 ft.

b. 9 ft.

c. 14 ft.

d. 20 ft.

QUESTION B.12 [1.0 point]

In accordance with 10CFR20.1301, individual members of the public are limited to a TEDE in one year of:

a. 50 mrem.

b. 100 mrem.

c. 500 mrem.

d. 1250 mrem.

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.13 [1.0 point]

According to emergency classification guide, the event associated with the contaminated moderator is defined as:

a. Operational Event

b. Unusual Event

c. Alert

d. Site Area Emergency QUESTION B.14 [1.0 point]

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

a. Alpha

b. Beta

c. Proton (high energy)

d. Neutron (unknown energy)

QUESTION B.15 [1.0 point]

Which ONE of the following experiments is NOT allowed to be installed in the reactor or experiment facilities under ANY condition? The experiment:

a. contains corrosive materials.

b. contains 15 milligrams of TNT material.

c. contains a movable worth of $0.50.

d. causes the reactivity insertion rate to exceed $0.10 per second.

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.16 [1.0 point]

The reactor power shall NOT exceed the minimum reactor period of 5 seconds. This is an example of:

a. Safety Limit (SL)

b. Limiting Safety System Setting (LSSS)

c. Limiting Conditions for Operation (LCO)

d. Surveillance Requirement (SR)

QUESTION B.17 [1.0 point]

All applicants for an RO or SRO license must submit NRC Form 396 and 398 to the U.S. NRC before taking the examinations. This requirement is specified in 10 CFR:

a. Part 19

b. Part 20

c. Part 50

d. Part 55 QUESTION B.18 [1.0 point]

Specific instrument readings, or observations; radiological dose or dose rates; or specific contamination levels of airborne or surface-deposited radioactive materials that may be used as thresholds for establishing emergency classes and initiating appropriate emergency measures.

The above statement is defined as:

a. Emergency Procedures.

b. Emergency Action Levels.

c. Emergency Planning Zones.

d. Protective Action Guides.

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

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

According to the Pre-Startup Procedures, which ONE of the following is the material used as a source check for the area gamma monitors?

a. U-235

b. Pu-240

c. Cs-137

d. Na-24 QUESTION C.02 [1.0 point]

The reactor operation is completed for the day. Which ONE of the following items is NOT required to be checked on the Reactor Secured Checklist?

a. All control rods are fully inserted.

b. The vault is closed and locked.

c. Turn off the ventilation system.

d. Turn off all instrumentation.

QUESTION C.03 [1.0 point]

All of the following are interlocks that prevent control rod withdrawal during reactor operations EXCEPT:

a. Moderator-Reflector Water Fill ON

b. Line Voltage to Recorders = 120 V

c. Reactor period = 10 seconds.

d. Neutron Flux = 1 cps QUESTION C.04 [1.0 point]

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

a. the source is inserted to the reactor core.

b. the reactivity addition does not exceed $0.50

c. the reactor period does not exceed 12 seconds.

d. the reactivity addition does not exceed $0.12 per second up to 10 times the source.

Category C: Facility and Radiation Monitoring Systems QUESTION C.05 [1.0 point]

Use the drawing of the Scram Block Diagram provided. The function of the Full Wave rectifier is to:

a. Convert the AC voltage to the DC voltage for the Instrument Scram circuit.

b. Convert the DC voltage to the AC voltage for Key, Red Button, and Reactor Door Scrams.

c. Provide the AC voltage to Key, Red Button, and Reactor Door Scrams; and provide the DC voltage to Instrument Scram circuit.

d. Provide the DC voltage to Key, Red Button, and Reactor Door Scrams; and provide the AC voltage to Instrument Scram circuit.

Category C: Facility and Radiation Monitoring Systems QUESTION C.06 [2.0 points, 0.5 each]

For the area radiation monitoring system, match the alarm settings in Column B with the appropriate channel in Column A. Items in Column B may be used once, more than once, or not at all.

Column A Column B

a. Control room 1. 10 mR/hr

b. Equipment hallway 2. 20 mR/hr

c. Vault criticality monitor 3. 40 mR/hr

d. Reactor deck 4. 100 mr/hr

5. 200 mR/hr QUESTION C.07 [1.0 point]

Use the drawing of the Interlock Block Diagram provided. Which ONE of the following conditions is allowed to move the control rods?

a. Fill Pump: OFF + Recorder: ON + Reactor Period >15 sec + Startup Channel < 2 cps

b. Fill Pump: OFF + Recorder: OFF + Reactor Period <15 sec + Startup Channel > 2 cps

c. Fill Pump: ON + Recorder: ON + Reactor Period >15 sec + Startup Channel > 2 cps

d. Fill Pump: OFF + Recorder: ON + Reactor Period >15 sec + Startup Channel > 2 cps

Category C: Facility and Radiation Monitoring Systems Category C: Facility and Radiation Monitoring Systems QUESTION C.08 [1.0 point, 0.25 each]

Select YES/NO to the following systems that have a bypass provision.

a. Linear Power High Neutron Level Scram (Y/N)

b. Moderator Dump Valve Scram (Y/N)

c. Reactor Door Scram (Y/N)

d. Log N Period Scram (Y/N)

QUESTION C.09 [2.0 points, 0.5 each]

Match the item provided in column A, with the correct Nuclear Instrumentation from column B.

(Items in column B can be used only once.)

Column A Column B

a. < 2 cps rod withdrawal inhibit 1. Log N

b. Reactor period scram 2. Start-up Channel

c. High Flux Scram 3. Linear Power Channel

d. Reactor Key Switch 4. AC Power Supply QUESTION C.10 [1.0 point]

Control rods are partially withdrawn from the core. At this point, the Fill Pump is turned ON by the operator. As a result:

a. the control rods cannot be withdrawn any further.

b. the control rods cannot be inserted any further.

c. the control rods stuck and cannot be moved in any direction.

d. the control rods can only be inserted by placing the key switch in the OFF position.

Category C: Facility and Radiation Monitoring Systems QUESTION C.11 [1.0 point]

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

a. An aluminum oxide (Al2O3) insulator.

b. A reflector section made of graphite.

c. An absorber section made of boron.

d. An absorber section made of cadmium.

QUESTION C.12 [1.0 point]

The Figure below depicts:

a. The Compensated Ion Chamber.

b. The Uncompensated Ion Chamber.

c. The Gamma Ion Chamber.

d. The Fission Chamber.

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

The RCF neutron startup source is:

a. Americium-Beryllium (Am-Be)

b. Uranium-Beryllium (U-Be)

c. Radon-Beryllium (Ra-Be)

d. Plutonium-Beryllium (Pu-Be)

QUESTION C.14 [1.0 point]

The RCF fuel element shall consist of:

a. uranium fuel in the form of 4.8 weight percent or less enriched UO2 pellets in stainless steel cladding.

b. uranium fuel in the form of 8.4 weight percent or less enriched UO2 pellets in stainless steel cladding.

c. uranium fuel in the form of 4.8 weight percent or less enriched UO2 pellets in aluminum cladding.

d. uranium fuel in the form of 8.4 weight percent or less enriched UO2 pellets in aluminum cladding.

QUESTION C.15 [1.0 point]

Per RCF Technical Specifications, the main reason to have the minimum number of 4 control rods is to:

a. Control the thermal power from exceeding 100 W.

b. Reduce the effect of flux tilting due to uneven power distribution.

c. Prevent conditions which would cause fuel element failure in SPERT fuel.

d. Ensure there is adequate shutdown margin, even for a stuck rod condition.

Category C: Facility and Radiation Monitoring Systems QUESTION C.16 [1.0 point, 0.25 each)]

The storage tank needs to be refilled with fresh water from the city water supply. Therefore, you need to turn or check these valves in OPEN or CLOSE. Select the following valves status during the refill of the water.

a. Valves #15 (city water supply) Open/Close

b. Valves #16 (city water supply Open/Close

c. Valves #18 (vent) Open/Close

d. Valves #7 (to storage tank) Open/Close

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

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

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

Reference:

Reactivity added = 0.1 % k/k = 0.001 k/k

= (-)/eff = 0.0078 - 0.001 = 68 seconds (0.1) (0.001)

A.04 Answer: d

Reference:

P = P0 et/ = 3 x 106 e-180/80 = 3.162x 105 A.05 Answer: d

Reference:

A.08 Answer: a

Reference:

P = P0 et/T --> ln(4) = time ÷ 10 seconds -> time = ln (4) x 10 sec. 1.386 x 10 13.8 sec.

A.09 Answer: d

Reference:

Reactor is increasing, then constant when reactor period reaches to infinitive.

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

Reference:

A Manual of Experiment, MANE-4440, Section 1.2 A.11 Answer: b

Reference:

= keff1-keff2/(keff1 x keff2) = 0.95-0.8 /(0.8*0.95)=0.197 k/k A.12 Answer: a. = fertile; b. = fissile; c. = fertile; d. = fissile

Reference:

= (Keff1 - Keff2) ÷ (Keff1

Keff2)

= (1.0000-0.9550) ÷ (0.9550

1.0000)

= 0.0450 ÷ 0.9550 = 0.0471 A.14 Answer d

Reference:

Introduction to Nuclear Operation, Reed Burn, 1988, Sec 2.45 A.15 Answer: c

Reference:

P = Poet/T 80 = 20e60 sec/T T = 43.28 sec 160 watts = 0.080et/43.28 t = 329 sec = 5.5 minutes A.16 Answer: b

Reference:

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.17 Answer: a = alpha b = +1 0 c = neutron d = alpha (0.25 each)

A.18 Answer: c

Reference:

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

Reference:

TS 3.8, Bases B.02 Answer: b

Reference:

A = A*e -t 0.1Ci = 1 Ci* e -(t)

= ln(2) / (half-life)

= 0.693 / 2 years = 0.3466 ln(0.1/1) = -0.3466*(t) --> -2.30/-0.3466 solve for t: 6.6 years B.03 Answer: b

Reference:

TS 3.2 B.04 Answer: c

Reference:

TS 6.5 B.05 Answer: d

Reference:

TS 3.7.1 B.06 Answer: b

Reference:

TS 2.1 and 2.2, Objective B.07 Answer: a

Reference:

10 CFR Part 55.53

55.53(i) - the licensee shall have a biennial medical examination.

55.53(h), 55.59(c) - annual operating tests

55.53(e) - the licensee shall actively perform the functions of a licensed operator for a minimum of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per calendar quarter.

55.53(h), 55.59(c)(1) - The requalification program must be conducted for a continuous period not to exceed 2 years License renewal : 6 years B.08 Answer: c

Reference:

DR1D12 = DR2D22 ;

20 mrem/hr at one meter (100 cm.)

results in 222.2 mrem/hr at 30 cm.

Category B: Normal/Emergency Operating Procedures and Radiological Controls B.09 Answer: c

Reference:

10CFR20 - At 20 feet, there is no beta radiation. Gamma at 20 feet =

0.1 mrem/hour, gamma at 1 foot = 40 mrem/hour. Therefore a ratio = 40 mrem/hr/60 mrem/hr = 0.67 B.10 Answer: c

Reference:

TS 2.2 and 3.1 B.11 Answer: d

Reference:

DR1*(D1 ) 2= DR2*(D2) 2 ;

500 mrem (2) 2 = 5 mrem (d) 2 D = 20 ft B.12 Answer: b

Reference:

10CFR20 B.13 Answer: b

Reference:

Emergency Plan, Section 5 B.14 Answer: b

Reference:

10CFR20 B.15 Answer: b

Reference:

TS 3.8 B.16 Answer: b

Reference:

TS 2.2 B.17 Answer: d

Reference:

10CFR55 B.18 Answer: b

Reference:

EP, Definitions

Category C: Facility and Radiation Monitoring Systems C.01 Answer: c

Reference:

Pre-Startup Procedures, Section I C.02 Answer: c

Reference:

SOP, Section D, Securing the Reactor C.03 Answer: b

Reference:

TS 3.2, Table 2 C.04 Answer: d

Reference:

SOP, Section A, Reactor Startup C.05 Answer: a

Reference:

SAR 7.3 C.06 Answer: c

Reference:

a. = 1 b. = 3 c. = 2 d. = 4 (0.5 each)

SAR, 7.7 Radiation Monitoring System C.07 Answer: d

Reference:

SAR, Figure 7.2 C.08 Answer: a=N b=Y c=Y d=N (0.25 each)

Reference:

TS 3.2 C.09 Answer: a=2 b=1 c=3 d=4 (0.5 each)

Reference:

TS 3.2 C.10 Answer: a

Reference:

SAR 7.3 C.11 Answer: c

Reference:

SAR 4.2.2

Category C: Facility and Radiation Monitoring Systems C.12 Answer: a

Reference:

NRC Standard Questions C.13 Answer: d

Reference:

SAR 4.1 C.14 Answer: a

Reference:

TS 5.3 and SAR 4.2.1 C.15 Answer: d

Reference:

TS 3.2.2 C.16 Answer: a = Open b = Open c = Close d = Open (0.25 each)

Reference:

SOP, Section J, Water Refill

ML18319A107

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Enclosures:

SUMMARY

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