ML23198A022

Examination Report Letter No. 50-186/OL-23-02, University of Missouri - Columbia

ML23198A022
Person / Time
Site:	University of Missouri-Columbia
Issue date:	08/29/2023
From:	Travis Tate NRC/NRR/DANU/UNPO
To:	Sanford M Univ of Missouri - Columbia
References
50-186/23-02 50-186/OL-23
Download: ML23198A022 (37)

Text

August 29, 2023 Mr. Matthew Sanford, Interim Reactor Facility Director University of Missouri-Columbia Research Reactor Center 1513 Research Park Drive Columbia, MO 65211

SUBJECT:

EXAMINATION REPORT NO. 50-186/OL-23-02, UNIVERSITY OF MISSOURI-COLUMBIA

Dear Mr. Sanford:

During the week of July 24, 2023, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your University of Missouri-Columbia 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 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 John Nguyen at (301) 415-4007 or via email at John.Nguyen@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. 50-186

Enclosures:

1. Examination Report No. 50-186/OL-23-02

2. Written examination cc: w/ enclosures to GovDelivery Subscribers Signed by Tate, Travis on 08/29/23

ML23198A022 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME JNguyen NJones TTate DATE 8/22/2023 8/22/2023 8/22/2023 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT

REPORT NO.: 50-186/OL-23-02

FACILITY DOCKET NO.: 50-186

FACILITY LICENSE NO.: R-103

FACILITY: MURR

EXAMINATION DATES: July 24 - July 26, 2023

SUBMITTED BY: __John Nguyen____________ 08/16/2023___

John T. Nguyen, Chief Examiner Date

SUMMARY

During the week of July 24, 2023, the NRC administered operator licensing examinations to two Reactor Operator (RO) and three Senior Reactor Operator Upgrade (SROU) candidates. All candidates passed all applicable portions of the examinations.

REPORT DETAILS

1. Examiner: John T. Nguyen, Chief Examiner, NRC

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL

Written 2/0 N/A 2/0

Operating Tests 2/0 3/0 5/0

Overall 2/0 3/0 5/0

3. Exit Meeting:

John T. Nguyen, Chief Examiner, NRC Ron Astrino - Reactor Manager, MURR Rob Hudson - Assistant Reactor Manager - Training, MURR Russ Gibson - Assistant Reactor Manager - Operations, MURR Glenn Korbeck - Acting Health Physics Manager, MURR Matt Sanford - MURR Executive Director, MURR Michele Kennett - Associate Vice Chancellor-Research Compliance, MURR Patrick Smith - Assistant Vice Chancellor-Office of Research, MURR

Facility comments were accepted prior to the administration of the written examination.

At the conclusion of the meeting, the NRC thanked the facility staff members for their support in the administration of the examinations. The examiner discussed the weaknesses observed during the operating test to include questions related to the radiation monitoring equipment, the Technical Specifications license amendment, the radiation sources and hazards, and the uninterrupted power supply (UPS) circuit braker.

Enclosure 1 UNIVERSITY OF MISSOURI -

COLUMBIA

Operator Licensing Examination

Week of July 24, 2023

Enclosure 2 U.S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION

FACILITY: University of Missouri -

Columbia

REACTOR TYPE: TANK

DATE ADMINISTERED: 07/26/2023

CANDIDATE: _______________________

INSTRUCTIONS TO CANDIDATE:

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

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY

20.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS

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

20.00 33.3 C. FACILITY AND RADIATION MONITORING SYSTEMS

60.00 % TOTALS FINAL GRADE

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

Candidate's Signature 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 ___

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 ___

A19 a b c d ___

A20 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 __________

B19 a b c d ___

B20 a b c d ___

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

Category C - Plant And Rad Monitoring Systems

A N S W E R S H E E T

Multiple Choice (Circle or X your choice)

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

C01 a b c d ___

C02 a b c d ___

C03 a b c d ___

C04 a b c d ___

C05 a b c d ___

C06 a b c d ___

C07 a b c 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 ___

C19 a b c d ___

C20 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

2 0.1sec1 Q mcPT mH UAT Pmax 2 eff

t S S P P0e SCR *1104 sec 1 Keff

CR11 KeffCR2 1Keff CR1 1CR2 2 SUR 26.06 eff 1 2 1 CR P 1 P M 2 P P010SUR(t) 0 1 Keff CR1

M 1Keff1 1 Keff

• 1 K SDM K eff2 eff

= + T 0.693 Keff2Keff1

1 2 K K eff1eff2

Keff1 DR DR et 2 2 K 0 DR1 d1 DR2d2 eff

6Ci E n 2 2 DR 2 1 R2 Peak2 Peak1

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 QUESTION A.01 [1.0 point]

The reactor is operating at 100 W with a fuel temperature of 60 °F. When a control rod with an average rod worth of 0.2% delta k/k/inch is withdrawn by 2 inches, reactor power increases and becomes stable at a higher level. What is the final fuel temperature? Given the fuel temperature coefficient of reactivity of -1.25 E-4 k/k/ °F.

Given: Fuel temperature change

• fuel temperature coefficient = - reactivity of rod

a. 32 °F

b. 28 °F.

c. 88 °F

d. 92 °F

QUESTION A.02 [1.0 point]

Which ONE of the following is the correct reason why a reactor gets a negative 80-second period following a reactor scram?

a. The interaction between U235 and the neutron source during reactor scram.

b. The fuel temperature coefficient adds positive reactivity because of the decrease in moderator temperature following a scram.

c. The rate of power change is dependent on a mean lifetime of the longest-lived delayed neutron precursors.

d. The rate of power change is dependent on a mean lifetime of the short-lived delayed neutron precursors.

QUESTION A.03 [1.0 point]

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

a. The amount of reactivity added to the core when withdrawing the control rod at that position in the core.

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

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

d. The amount of reactivity that one unit (e.g. one inch, one percent) of rod motion would insert at that position in the core.

QUESTION A.04 [1.0 point]

What is the reactor period if the reactor power is increasing by a factor of 5 every 2 minutes?

a. 80 seconds

b. 75 seconds

c. 12 seconds

d. 1.2 seconds

QUESTION A.05 [1.0 point]

Which ONE of the following directly produces 95% of all Xenon in a nuclear reactor?

a. Fission products of U-235

b. Decay of Sm-149

c. Decay of I-135

d. Decay of Cs-135

QUESTION A.06 [1.0 point]

To thermalize neutrons in the MURR reactor core, which ONE of the following materials is mainly used?

a. Fissile material

b. Reflection material

c. Absorption material

d. Moderator material QUESTION A.07 [1.0 point] 238 The Uranium-238 nucleus ( U ) has a number of neutrons of _____.92

a. 92

b. 143

c. 146

d. 238

QUESTION A.08 [1.0 point]

A reactor is subcritical with a Keff of 0.945. A positive reactivity of 0.055 k/k is inserted into the core, which ONE of the following best describes the reactor kinetics?

a. The reactor is prompt critical.

b. The reactor is super-critical.

c. The reactor is critical.

d. The reactor is sub-critical.

QUESTION A.09 [1.0 point]

Giving a Reactor A with a Keff of 0.1 and a Reactor B with a Keff of 0.8, if a Keff is increased by 0.15 for each reactor (Keff of Reactor A = 0.25 and B=0.95), the amount of reactivity added in Reactor A is ______ in Reactor B for the same increment of 0.15.

a. less than

b. same

c. four times

d. thirty times QUESTION A.10 [1.0 point]

Which ONE of the following is the major source of heat generated after an operating reactor has been shut down and cooled down for several days?

a. Resonance capture.

b. Fission fragment decay.

c. Delayed neutron reactions.

d. Corrosion product activation.

QUESTION A.11 [1.0 point]

A multiplication factor during a fuel loading is 0.8, which produces the stable neutron count rate of 5000 neutrons per second (N/sec). A source strength is:

a. 100 N/sec

b. 400 N/sec

c. 1000 N/sec

d. 4000 N/sec

QUESTION A.12 [1.0 point]

Which ONE of the following conditions would DECREASE the shutdown margin of a reactor?

a. A major loss of primary coolant system.

b. Loading a fresh fuel to the reactor core.

c. Inserting a poison material experiment to the reactor core.

d. Increasing moderator temperature if the moderator temperature coefficient is negative.

QUESTION A.13 [1.0 point]

The Reactor is critical at 100 watts. A reactor operator makes a mistake by inserting a sample worth of 1 k/k into the reactor core. Which ONE of the following best describes the reactor kinetic?

a. Keff = 1 and = 1 k/k

b. Keff > 1 and = -eff

c. Keff > 1 and > -eff

d. Keff > 1 and 0 < < -eff

=z?-][D 'EX/ <XE:Dpoint#

Which ONE of the following is the stable reactor period which will result in a power rise from 15% to 50% power in 6 seconds?

a. 2 seconds

b. 5 seconds

c. 7 seconds

d. 13 seconds

QUESTION A.15 [1.0 point]

The neutron count rate is 1000 cps. A staff inserts an experiment into the core, and the count rate decreases to 600 cps. Given the initial Keff of the reactor was 0.92, what is the worth of the experiment?

a. = + 0.02

b. = - 0.02

c. = - 0.07

d. = + 0.07 QUESTION A.16 [1.0 point]

All atoms of a given element have the same _______.

a. Atomic Mass

b. Mass Number

c. Atomic Number

d. Number of Neutrons

QUESTION A.17 [1.0 point, 0.25 each]

Fill out the spaces below with INCREASE/DECREASE of the following values because of moderator temperature increase.

a. Control rod worth _________

b. Fast non-leakage probability _________

c. Resonance escape probability _________

d. Thermal non-leakage probability _________

QUESTION A.18 [1.0 point]

Reactor #1 increases power from 10% to 20% with a period of 25 seconds. Reactor # 2 increases power from 80% to 100% with a same period of 25 seconds. Compared to Reactor

1. 1, the time required for the power increase of Reactor #2 is:

a. longer than #1

b. exactly the same as #1

c. twice that of #1

d. shorter than #1 QUESTION A.19 [1.0 point]

Which ONE of the following is a true statement regarding the 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.20 [1.0 point]

For the fast energy range, 100 KeV - 10 MeV, the absorption cross section steadily decreases as the energy of the neutron increases. This region is called:

a. Slow neutron region.

b. Fast neutron region.

c. Increases the mass of the target region.

d. Destruction the mass of the target region.

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

QUESTION B.01 [1.0 point]

A five-curie source, emitting 100-Kev gamma with a yield of 70%, is to be stored in the reactor building. A dose rate at 5 ft is approximately:

a. 14 mR/hr

b. 84 mR/hr

c. 140 mR/hr

d. 420 mR/hr

QUESTION B.02 [1.0 point, 0.25 each]

Common radioisotopes associated with research reactors are H-3, Na-24, N-16, and Ar-41. Fill in the blank with their appropriate half-life (seconds (sec), minutes (min) hours (hr) or years (yr)).

a. H-3 is 12.0 _____.

b. N-16 is 7.0 _____.

c. Na-24 is 15.0 _____.

d. Ar-41 is 1.8 _____.

QUESTION B.03 [1.0 point]

Which ONE of the following radiation detectors does NOT have an output intensity proportional to the incident radiation energy?

a. Ion chamber

b. Scintillation

c. Proportional counter

d. Geiger Mueller (GM) Counter QUESTION B.04 [1.0 point]

Per MURR Technical Specifications, the experiment with listed below shall NOT be irradiated in the reactor, EXCEPT:

a. Corrosive material

b. Cryogenic liquids

c. 30 mg of TNT equivalent explosives

d. The sum of the absolute value of reactivity of all experiments in the center test hold exceeds 0.007 k/k

=z?-][ @E:L <XE:Dpoint#

If a Reactor Safety Subcommittee (RSS) review is NOT required prior to implementing the change on the proposed procedure, then WHO may approve the Modification Record and 50.59 Screen?

a. Senior Reactor Operator

b. A Reactor Health Physic

c. A Reactor Advisory Committee

d. Reactor Manager

QUESTION B.06 [1.0 point]

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

a. Post the area with the words "Controlled Radiation Area".

b. Lock the room to prevent inadvertent entry into the room.

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

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

QUESTION B.07 [1.0 point]

Per MURR Technical Specifications, when the Stack Radiation Monitor (SRM) may be placed out of service for calibration and maintenance, the reactor operations may continue only if:

a. The power level is less than 10 kW, and operation period does NOT exceed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

b. Reactor Bridge Radiation Monitor is still operable.

c. If portable instrument is substituted for the SRM for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

d. During the out of service of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, no experimental or maintenance activities is conducted which are likely to result in the release of airborne radioactivity.

QUESTION B.08 [1.0 point]

Per MURR AP-RO-110, who would approve the reactor startup if unscheduled scram occurred from an unknown cause?

a. Senior Reactor Operator

b. Designated Shift Supervisor

c. Reactor Manager

d. Reactor Director

QUESTION B.09 [1.0 point, 0.25 each)]

Select (YES/NO) to the following activities whether the licensed operator will violate 10 CFR Part 55.

Activity Violation (Y/N)

a. Last operator licensed renewal was 5 years ago ______

b. Last requalification operating test was 13 months ago _______

c. Last quarter the licensed operator has completed for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> _______

of requalification training

d. Last requalification written examination was 13 months ago _______

QUESTION B.10 [1.0 point]

Which ONE of the following conditions would NOT prevent sending a volunteer into a high radiation area in order to save a life?

a. A volunteer is a declared pregnant woman.

b. The radiation levels in the area are unknown.

c. A volunteer is man under the age of 45.

d. A volunteer is a new hire, not trained in the consequences of receiving an emergency dose.

QUESTION B.11 [1.0 point]

The four parameters used to evaluate the Limiting Safety System Setting on Mode I are:

a. reactor power level, core flow rate, reactor inlet water temperature, and water tank level.

b. reactivity, reactor power level, reactor inlet water temperature, and pressurizer pressure.

c. reactor power level, core flow rate, reactor inlet water temperature, and pressurizer pressure.

d. reactor power level, core flow rate, reactor outlet water temperature, and pressurizer pressure.

QUESTION B.12 [1.0 point]

Which ONE of the following surveillances is a channel test?

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

b. During a steady state power, you compare the readings of the primary coolant flow rate.

c. During a steady state power, you compare reactor inlet water temperatures.

d. You adjust the Safety channel in accordance with recent data collected from a power channel calibration.

QUESTION B.13 [1.0 point, 0.25 point each]

Match the events listed in Column A with its emergency classification listed in Column B. Items in Column B can be used once, more than once or not at all.

Column A Column B

a. Earthquake 1. Notification of Unusual Events.

b. Fire in the reactor room. 2. Alert.

c. Significant releases of radioactive materials because of experiment failures. 3. Site Area Emergency.

d. Major damage to fuel has occurred with actual or imminent failure of primary system integrity and containment integrity.

QUESTION B.14 [1.0 point]

A radioactive source currently has an activity of 2 Curies. The activity of the source 25 years ago was 120 Curies. What is the half-life of the radioactive source?

a. 4.2 years

b. 5.4 years

c. 7.5 years

d. 8.2 years

QUESTION B.15 [1.0 point]

In an emergency, 10 CFR 50.54 allows reasonable action that departs from a license condition or a technical specification in an emergency when this action is immediately needed to protect the public health and safety. In this case, what is the minimum level of authorization or approved needed to depart from a license condition or technical specification?

a. Reactor Administrator.

b. Chief Reactor Supervisor.

c. Licensed Senior Reactor Operator.

d. Reactor Safety Advisory Committee.

QUESTION B.16 [1.0 point]

Per MURR Technical Specifications, the calculated K-eff in the fuel storage shall be less than

_____ under all conditions of moderation.

a. 0.80

b. 0.85

c. 0.90

d. 0.95

QUESTION B.17 [1.0 point]

Which ONE of the following is the correct statement for the Shim Blade Operation?

a. Shim Blades could be moved in gang control during increasing power of 1 MW.

b. Gang Shim Blades could be withdrawn at the same time above 5 MW.

c. A single Shim Blade cannot be simultaneously withdrawn with the regulating blade.

d. Above 100 kW, the reactor could be operated so that the maximum distance between the highest and lowest shim blade would exceed 0.90 inches.

QUESTION B.18 [1.0 point, 0.25 point each]

Match the Federal Regulation number (Column A) with the appropriate topic (Column B).

Column A Column B

a. 10 CFR 20. 1. Operator Licensing.

b. 10 CFR 50. 2. Facility Licensing.

c. 10 CFR 55. 3. Radiation Protection.

d. 10 CFR 19. 4. Notices, Instructions and Reports to Workers.

QUESTION B.19 [1.0 point]

A radioactive source is to be stored in the reactor bay with no shielding. The source reads 2 Rem/hr at 1 foot. How far from the source does a barrier need to be placed for it to be considered a Radiation Area?

a. 723 cm

b. 610 cm

c. 142 cm

d. 36 cm

QUESTION B.20 [1.0 point]

Per MURR Technical Specifications, the maximum absolute value of the reactivity worth of each unsecured experiment shall be limited to __________.

a. 0.0010 k/k

b. 0.0020 k/k

c. 0.0025 k/k

d. 0.0060 k/k

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

QUESTION C.01 [1.0 point]

Which ONE of the following is a true statement regarding the regulating blade?

a. The regulating blade worth is higher than the Shim blade worth.

b. The regulating blade does NOT has a scram function.

c. The regulating blade is used for automatic control ONLY.

d. The regulating blade is constructed of formed Boral plate.

QUESTION C.02 [1.0 point]

With respect to the Reactor Core Assembly Support Structure, which ONE of the following Outer Reactor Pressure Vessel sections is referred as the spool piece?

a. The Concentric Reducer

b. The Vessel Tube

c. The Island Tube

d. The Lower Tee

QUESTION C.03 [1.0 point]

Non-Coincidence Logic Units (NCLUs) B receives signals directly from:

a. PRM 6

b. IRM 3

c. IRM 2

d. PRM 4 QUESTION C.04 [1.0 point]

In accordance with Emergency Air System Valve Line Up Checklist, which ONE of the following valves is in the CLOSED position for the Emergency Air System?

a. A-149, 16-inch B valve compressor outlet.

b. A-115, Vent.

c. A-137, Door-504 inlet.

d. A-164, Backup door isolation.

QUESTION C.05 [1.0 point]

In the event of high reactor coolant temperature exceeds its limit, the temperature detectors, TE 980A/B, will provide a reactor scram. If they fail to initiate a scram, a backup scram signal,

_______, will be initiated.

a. Reactor Loop A Lo Flow scram from FT 912E

b. Reactor Loop Hi Temp scram from TE 901B

c. Power Level Interlock scram from DPS 929

d. Power Level Interlock scram from Valve 507B

QUESTION C.06 [1.0 point]

The main purpose of the pool water hold-up tank is to provide:

a. A sufficient coolant for forced convection flow in Mode I.

b. A sufficient natural circulation of pool water in Mode III.

c. A sufficient time delay for Xenon build-up and Argon-41 activity in the reactor core.

d. A sufficient time delay for Oxygen and Nitrogen activities in the pool coolant system.

QUESTION C.07 [1.0 point]

The operation of the Plenum Natural Convection Valve (V547 in the Pool Coolant System) will use:

a. Spring to open and air to close.

b. Spring to close and air to open.

c. Motor to close and air to open.

d. Motor to close and spring to open.

QUESTION C.08 [1.0 point]

When the Low Pressurizer pressure sensor, PS 941, is activated, which ONE of the following occurs?

a. Valve 526 will automatically open, supplying nitrogen gas to the volume above the water surface to maintain the necessary operating pressure.

b. A scram signal and annunciation will be initiated.

c. Valve 545 will automatically open to vent nitrogen gas to the room 114 exhaust line.

d. An alarm is sounded on the control room annunciator ONLY.

QUESTION C.09 [1.0 point]

The Lab Impex stack monitor is designed to measure the airborne concentrations in the facility exhaust air of all the following, EXCEPT:

a. Iodine.

b. Noble Gas.

c. Cs-137 activity.

d. Radioactive Particulate.

QUESTION C.10 [1.0 point, 0.25 each]

Fill out the current set point of the Area Radiation Monitors listed below:

Column A

a. Room 114 ______ mR/hr (1,000/2100/2500)

b. Air Plenum #1 _______ mR/hr (3/30/50)

c. Bridge (ALARA-Alert) _______ mR/hr (50/300/1300)

d. East Beam Port Wall _______ mR/hr (3/20/30)

QUESTION C.11 [1.0 point]

If primary coolant flow instrument, FT 912A trips, it will initiate a scram, and ____________.

a. valves 507A/B to close

b. valves 546 A/B to open

c. a power level high scram

d. valves 507A/B to open

QUESTION C.12 [1.0 point]

Where can a reactor operator manually initiate a Reactor Isolation without a facility evaluation?

a. The front lobby

b. The control room console

c. The reactor bridge

d. Reactor Director office QUESTION C.13 [1.0 point]

Which ONE of the following is a correct statement when either Reactor Isolation relay (R2A or R2B) is de-energizing?

a. Containment building exhaust isolation valves 16A and 16B will close.

b. Containment building ventilation supply and exhaust isolation doors 504 and 505 will open.

c. Evacuation horns sound throughout MURR buildings.

d. De-energizing the Facility Evacuation relays R3 A/B.

QUESTION C.14 [1.0 point]

Prior to placing the regulating blade in automatic control, which ONE of the following conditions does NOT require to be satisfied?

a. Shim blades are 70% of full length.

b. Range Switch selected to, or above, the 5kW red scale position.

c. Reg. Blade 60% Withdrawn annunciator is lit.

d. WRM recorder indication greater than Auto Prohibit set point (currently 75%).

QUESTION C.15 [1.0 point]

Which ONE of the following best describes the flow path of the pool coolant loop?

a. Reactor Pool --> Holdup Tank -->Pool Outlet Isolate Valve (V509) -->Pool Pumps (P508 A/B) --> Pool Heat Exchanger --> Reactor Pool.

b. Reactor Pool --> Pool Outlet Isolate Valve (V509) --> Pool Pumps (P508 A/B) --> Holdup Tank --> Pool Heat Exchanger --> Reactor Pool.

c. Reactor Pool --> Pool Outlet Isolate Valve (V509) --> Holdup Tank --> Pool Heat Exchanger --> Pool Pumps (P508 A/B) --> Reactor Pool.

d. Reactor Pool --> Pool Outlet Isolate Valve (V509) --> Holdup Tank -->Pool Pumps (P508 A/B) --> Pool Heat Exchanger --> Reactor Pool.

QUESTION C.16 [1.0 point]

The Eberline stack monitor consists of three separate radiation detection systems in a series configuration. Which ONE of the following channels has a filter monitored by a plastic phosphor beta scintillation detector?

a. The Air Plenum # 1 channel.

b. The iodine channel.

c. The particulate channel.

d. The Air Plenum # 2 channel.

QUESTION C.17 [1.0 point]

The uncompensated ion chamber signal is fed directly to the ________ drawer in the Control Room Instrument Panel.

a. Wide Range Monitor (WRM)

b. Source Range (SRM1)

c. Power Range Monitor (PRM 6)

d. Intermediate Range (IRM 3)

QUESTION C.18 [1.0 point]

When the Pressurizer Lo Press annunciator alarms, it means that:

a. Valve 545 has opened, venting nitrogen gas to the exhaust line.

b. Valve 526 has opened, reducing pressure to 70 psi.

c. PS 945 has sensed a pressure of 64 psi.

d. Valve 527A has opened, allowing water to be drained from the pressurizer to the drain collection tank.

QUESTION C.19 [1.0 point]

The ventilation system has two backup doors located in the ventilation supply and return plenums which shut on containment isolation. Which ONE of the following is the method used to shut these doors? The doors are:

a. air motor operated, with their own emergency air supply tanks.

b. held open by air pistons, which when vented, the doors close via gravity.

c. motor operated, with air supplied from the emergency air supply system.

d. held open by solenoid, which when deenergized, the door closes via gravity.

QUESTION C.20 [1.0 point]

The reactor has been operating for six days straight at full power when the facility has a complete loss of power. How is damage to the fuel prevented?

a. Two thermally (temperature) actuated valves open, allowing steam to escape from the primary system, which is quenched in the pool water.

b. Two air operated valves fail open due to loss of electrical power, lining up the primary to an in-pool heat exchanger. Water flow is via natural convection.

c. Two thermally (temperature) actuated valves open, lining up the primary to an in-pool heat exchanger. Water flow is via natural convection.

d. Two motor operated valves (powered off the diesel) open, lining up the primary to an in-pool heat exchanger.

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

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

A.01 Answer: d

Reference:

Reactivity added by control rod = +(0.002 k/k/inch)((2 inches) = 0.004 k/k Fuel temperature change = - reactivity of rod/fuel temperature coefficient.

(- 0.004 k/k)/(- 1.25E-4 k/k/°F) = 32 °F Final Fuel temperature = 60 °F +32 °F = 92 °F

A.02 Answer: c

Reference:

Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 4.5

A.03 Answer: d

Reference:

Burns, R., Introduction to Nuclear Reactor Operations, Example 7.2(b), page 7-4

A.04 Answer: b

Reference:

P=P x e/, P/Po= e/ = 10, T = 120 sec/ln (5) = 75 sec.

A.05 Answer: c

Reference:

DOE Fundamentals Handbook, Volume 2, Module 3, Page 35

A.06 Answer: d

Reference:

DOE Fundamentals Handbook, Volume 1, Module 2, page 23

A.07 Answer: c

Reference:

Chart of Nuclides DOE Fundamentals of Reactor Theory, Vol. 1, page 11.

A.08 Answer: d

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 3.3.4, page 3-21.

p = (Keff-1)/Keff = (0.945-1)/0.945 = -0.0582 k/k. Reactor needs 0.0582 k/k for reaching to critical, since 0.055 the reactor is still in k/k < 0.0582 k/k, subcritical.

A.09 Answer: d

Reference:

Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 3.3.3, page 3-21.

reactor A = (Keff 1-Keff2)/(Keff1*Keff2). (0.25-0.1)/(0.25*0.1) = 6 k/k reactor B = (Keff 1-Keff2)/(Keff1*Keff2). (0.95-0.8)/(0.95*0.8) = 0.197 k/k 6/0.197 = 30

A.10 Answer: b

Reference:

DOE Fundamentals Handbook, NPRT, Vol. 2 NP-03, page 34 A.11 Answer: c

Reference:

CR = S/(1-0.8) S = 5000*(1 - 0.8) S = 1000 N/sec

A.12 Answer: b

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 6.2.3, page 6-4.

A.13 Answer: c

Reference:

Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 4.2

A.14 Answer: b

Reference:

P = P0 e t/T --> T= t/Ln(P/ P0 )

T= 6/Ln(50/15 ); T = 4.98 sec.

A.15 Answer: c

Reference:

CR1 / CR2 = (1 - Keff2) / (1 - Keff1) 1000 / 600 = (1 - Keff2) / (1 - 0.92)

Therefore Keff2 = 0.867

= (K eff2 - Keff1) / (Keff2

• Keff1)

= (0.867 - 0.92) / (0.867

• 0.92)

= - 0.0664

A.16 Answer: c

Reference:

DOE Handbook, Vol. 1, Mode 1, page 4

A.17 Answer: a, INCREASE b, DECREASE c, DECREASE d, DECREASE

Reference:

Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 3.3.1

A.18 Answer: d

Reference:

The power of reactor #1 increases by a factor of 2, while the power of reactor #2 increases by a factor of 1.25. Since the periods are the same (rate of change is the same), power increase #2 takes a shorter time.

A.19 Answer: d

Reference:

Burn, R., Introduction to Nuclear Reactor Operations, 1988, Table 5.5

A.20 Answer: b

Reference:

DOE Fundamentals Handbook, Volume 1, Module 2, 3rd paragraph, page 10

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

B.01 Answer: b

Reference:

6CEN = R/hr @ 1 ft. -> 6 x 5 x 0.7 x 0.1 = 2.1 R/hr at 1ft.

2100 mR/hr At 5 ft = 2100 mR/hr/ 25 = 84 mR/hr

B.02 Answer: a. = yr; b. = sec; c. = hr; d. = hr (0.25 each)

Reference:

NRC Standard Question

B.03 Answer: d

Reference:

Standard NRC HP question

B.04 Answer: a

Reference:

MURR Technical Specifications, Section 3.8

B.05 Answer: d

Reference:

MURR AP-RO-115, Section 5.2

B.06 Answer: b

Reference:

10CFR20.1601(a)(3)

B.07 Answer: d

Reference:

MURR Technical Specifications, Section 3.7

B.08 Answer: c

Reference:

MURR AP-RO-110, Conduct of Operation, Section 6.6.8

B.09 Answer: a (N) b(Y) c(N) d(N)

Reference:

10 CFR Part 55.53

B.10 Answer: c

Reference:

MURR EP-RO-018, Emergency Exposure Authorization

B.11 Answer: c

Reference:

MURR Technical Specifications, Section 2.2 B.12 Answer: a

Reference:

MURR Technical Specifications, Section 1.6

B.13 Answer: a. = 1; b. = 1; c. = 2; d. = 3 (0.25 each)

Reference:

MURR Emergency Plan, Section 3

B.14 Answer: a

Reference:

A= A0 exp( -*T ) = ln(2) /t 1/2 Ln(2ci/120ci) = (ln(2)/t 1/2) *25 year t 1/2=4.232 years

B.15 Answer: c

Reference:

10 CFR 50.54(y)

B.16 Answer: c

Reference:

MURR Technical Specifications, Section 5.4

B.17 Answer: c

Reference:

MURR AP-RO-110, Conduct of Operations, Section 6.6

B.18 Answer: a. = 3; b. = 2; c. = 1; d. = 4

Reference:

Title 10 of the Code of Federal Regulations

B.19 Answer: b

Reference:

1 = 2; 2= 2000 1 2 (30.48 )2 = = 609.6 2 2 2 5 2 2 1 1

Answer: c

Reference:

MURR Technical Specifications, Section 3.8

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

C.01 Answer: b

Reference:

MURR Operations Training Manual, Control Blade Drive Mechanisms, page 7.3-2

C.02 Answer: a

Reference:

MURR Operations Training Manual, Reactor Core Assembly Support Structure, page 7.2-2 C.03 Answer: b

Reference:

MURR Operations Training Manual, Reactor Safety System-Scram, page 10.4-2

C.04 Answer: b

References:

MURR OP-RO-515

C.05 Answer: b

Reference:

MURR Operations Training Manual, Safety Function, Page 4.1-3

C.06 Answer: d

Reference:

MURR Operations Training Manual, Pool Coolant System, Page 5.1-2

C.07 Answer: a

Reference:

MURR Operations Training Manual, The Primary & Pool Sample Station, page 5.1 - 2.

C.08 Answer: a

Reference:

MURR Operations Training Manual, Pressurizer System, Page 4.5-2

C.09 Answer: c

Reference:

MURR Operations Training Manual, Stack Monitor - Lab Impex, page 9.4 - 2.

Answer c is correct because Cs-137 is NOT a gaseous material.

C.10 Answer: a(2100), b(3), c(300), d(3)

Reference:

MURR Operations Training Manual, Area Radiation Monitor System, Page 9.2-1

C.11 Answer: b

Reference:

MURR Operations Training Manual, In-Pool Heat Exchanger, Page 4.2-3

Enclosure 2 C.12 Answer: b

Reference:

MURR Operations Training Manual, Reactor Isolation & Facility Evacuation, Page 3.4-2

C.13 Answer: a

Reference:

MURR Operations Training Manual, Reactor Isolation & Facility Evacuation, Page 3.4-2

C.14 Answer: a

Reference:

MURR Operations Training Manual, Rod Control system for the Regulating Blade, page 10.3-2

C.15 Answer: d

Reference:

MURR Operations Training Manual, Pool Coolant System, page 5.1-1

C.16 Answer: c

Reference:

MURR Operations Training Manual, Stack Monitor - Eberline, page 9.3 - 2.

C.17 Answer: c

Reference:

MURR Operations Training Manual, Nuclear Instrumentation, page 9.1-3.

C.18 Answer: c

Reference:

MURR Operations Training Manual, Pressurizer System, Page 4.5-2

C.19 Answer: b

Reference:

MURR Facility Walk-Through

C.20 Answer: b

Reference:

MURR Operations Training Manual, Primary Coolant System, Page 4.1-2

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