Text

Initial Examination Report, No. 50-407/OL-09-01, University of Utah
	ML092020487
Person / Time
Site:	University of Utah
Issue date:	08/04/2009
From:	Johnny Eads; Research and Test Reactors Branch B
To:	Choe D; Univ of Utah
	Young P T, NRR/PRTB, 415-4094
References
	OL-09-01
	Download: ML092020487 (22)
	v • d • e

August 4, 2009 Dr. Dongok Choe Reactor Supervisor 122 S. Central Campus Drive University of Utah Salt Lake City, UT 84112

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-407/OL-09-01, UNIVERSITY OF UTAH

Dear Dr. Choe:

During the week of June 29, 2009, the NRC administered operator licensing examinations at your University of Utah 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 internet e-mail Phillip.Young@nrc.gov.

Sincerely,

/RA/

Johnny H. Eads, Jr., Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-407

Enclosures:

1. Initial Examination Report No. 50-407/OL-09-01

2. Written examination with facility comments incorporated cc without enclosures:

Please see next page

August 4, 2009 Dr. Dongok Choe Reactor Supervisor 122 S. Central Campus Drive University of Utah Salt Lake City, UT 84112

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-407/OL-09-01, UNIVERSITY OF UTAH

Dear Dr. Choe:

During the week of June 29, 2009, the NRC administered operator licensing examinations at your University of Utah 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 internet e-mail Phillip.Young@nrc.gov.

Sincerely,

/RA/

Johnny H. Eads, Jr., Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-407

Enclosures:

1. Initial Examination Report No. 50-407/OL-09-01

2. Written examination with facility comments incorporated cc without enclosures:

Please see next page DISTRIBUTION w/ encls.:

PUBLIC PRTB r/f RidsNRRDPRPRTA RidsNRRDPRPRTB Facility File (CRevelle) O-07 F-08 ADAMS ACCESSION #: ML092020487 TEMPLATE #:NRR-074 OFFICE PRTB:CE IOLB:LA E PRTB:SC NAME PYoung: CRevelle JEads DATE 07/28/2009 07/28/2009 08/4/2009 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY

University of Utah Docket No. 50-407 cc:

Mayor of Salt Lake City 451 South State Room 306 Salt Lake City, UT 84111 Dr. Raymond F. Gesteland Vice President for Research 201 S. Presidents Circle, Room 210 University of Utah Salt Lake City, UT 84112-9011 Ms. Karen Langley Director, University of Utah Radiological Health 100 OSH, University of Utah Salt Lake City, UT 84112 Dr. Ronald J. Pugmire Associate Vice President for Research 210 Park, University of Utah Salt Lake City, UT 84112 Test, Research, and Training Reactor Newsletter Universities of Florida 202 Nuclear Sciences Center Gainesville, FL 32611 Director, Division of Radiation Control Dept. Of Environmental quality 168 North 1959 West P.O. Box 144850 Salt Lake City, UT 84114-4850

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-407/OL-09-01 FACILITY DOCKET NO.: 50-407 FACILITY LICENSE NO.: R-126 FACILITY: University of Utah Reactor EXAMINATION DATES: June 30, 2009 SUBMITTED BY: __________________________ _________

Phillip T. Young, Chief Examiner Date

SUMMARY

During the week of June 29, 2009, the NRC administered operator licensing examinations to one Senior Reactor Operator candidate. The applicant passed the written examination, but was not successful on the Operating Test.

REPORT DETAILS

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

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 0/0 1/0 1/0 Operating Tests 0/0 0/1 0/1 Overall 0/0 0/1 0/1

3. Exit Meeting:

Phillip T. Young, Chief Examiner, NRC John T. Nguyen, Examiner Trainee, NRC Dr. Dongok Choe, Reactor Administrator, CENTER/NEP, University of Utah At the conclusion of the site visit, the examiner met with representatives of the facility staff to discuss the some pre-determination results of the examinations. The examiner thanked the facility for their support of the examination.

ENCLOSURE 1

University of Utah Operator License Examination Written Exam with Answer Key June 30, 2009 ENCLOSURE 2

Section A - Reactor Theory, Thermodynamics, and Facility Characteristics Page 6 of 22 Question A.001 [1.0 point] {1.0}

WHICH ONE of the following is the MAJOR source of energy released during fission?

a. Kinetic energy of the fission neutrons.

b. Kinetic energy of the fission fragments.

c. Decay of the fission fragments.

d. Prompt gamma rays.

Answer: A.001 b.

Reference:

WHICH ONE of the following describes the MAJOR contributions to the production and depletion of xenon in the reactor?

a. Produced directly from fission and depletes by neutron absorption only.

b. Produced from radioactive decay of iodine and depletes by neutron absorption only.

c. Produced directly from fission and depletes by radioactive decay and neutron absorption.

d. Produced from radioactive decay of iodine and depletes by radioactive decay and neutron absorption.

Answer: A.002 d.

Reference:

Core excess reactivity changes with

a. Fuel burnup

b. Neutron Level

c. Control Rod Height

d. Reactor Power Level Answer: A.003 a.

Reference:

Section A - Reactor Theory, Thermodynamics, and Facility Characteristics Page 7 of 22 Question A.004 [1.0 point] {4.0}

Control Rod withdrawal predominantly changes Keff by changing the

a. fast fission factor ().

b. thermal utilization factor (f).

c. neutron reproduction factor ().

d. resonance escape probability (p).

Answer: A.004 b.

Reference:

The reactor supervisor tells you the reactor is shutdown with a shutdown margin of 12%. An experimenter inserts an experiment in the core and nuclear instrumentation increases form 100 counts per minute to 200 counts per minute. What is the new Keff of the reactor?

a. 0.920

b. 0.946

c. 0.973

d. 1.000 Answer: A.005 b.

1 1 K eff1 = = = 0.892857 1+ SDM 1+ 0.12 CR1(1 K eff1 ) = CR 2 (1 K eff2 );

Reference:

100 1 K eff2 = (1 0.892857)= (0.0535715) 200 K eff2 = 0.9464285 Question A.006 [1.0 point] {6.0}

The term Keff is defined as

a. absorption/(production + leakage)

b. (production + leakage)/absorption

c. (absorption + leakage)/production

d. production/(absorption + leakage)

Answer: A.006 d.

Reference:

Section A - Reactor Theory, Thermodynamics, and Facility Characteristics Page 8 of 22 Question A.007 [2.0 points, 1/2 each] {8.0}

Match each of the terms in column A with the correct definition from column B.

Column A Column B

a. Fast neutrons 1. Neutrons released directly from fission.

b. Prompt neutrons 2. High energy neutrons.

c. Slow neutrons 3. Neutrons releases from decay of fission products.

d. Delayed neutrons 4. Low energy neutrons.

Answer: A.007 a. = 2; b. = 1; c. = 4; d. = 3

Reference:

Reactor power increases from 30 watts to 60 watts in one minute. Reactor period is

a. 30 seconds

b. 42 seconds

c. 60 seconds

d. 87 seconds Answer: A.008 d.

Reference:

Question A.009 [1.0 point] {10.0}

Which ONE of the following is an example of alpha decay?

87 83

a. 35Br 33As 87 87

b. 35Br 35Br 87 86

c. 35Br 34Se 87 87

d. 35Br 36Kr Answer: A.009 a.

Reference:

Section A - Reactor Theory, Thermodynamics, and Facility Characteristics Page 9 of 22 Question A.010 [1.0 point] {11.0}

When compared to , eff is

a. smaller, because delayed neutrons are born at lower energies than prompt neutrons.

b. larger, because delayed neutrons are born at lower energies than prompt neutrons.

c. smaller, because delayed neutrons are born at higher energies than prompt neutrons.

d. larger, because delayed neutrons are born at higher energies than prompt neutrons.

Answer: A.010 b.

Reference:

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

a. 106

b. 8 x 105

c. 5 x 105

d. 3 x 105 Answer: A.011 d.

Reference:

The reactor is on a CONSTANT positive period. Which ONE of the following power changes will take the longest time to complete?

a. 5%, from 95% to 100%

b. 10%, from 80% to 90%

c. 15%, from 15% to 30%

d. 20%, from 60% to 80%

Answer: A.012 c.

Reference:

Section A - Reactor Theory, Thermodynamics, and Facility Characteristics Page 10 of 22 Question A.013 [1.0 point] {14.0}

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

a. O16

b. C12

c. U235

d. H1 Answer: A.013 d.

Reference:

The reactor supervisor tells you that the Keff for the reactor is 0.955. How much reactivity must you add to the reactor to reach criticality?

a. +0.0471

b. +0.0450

c. -0.0471

d. -0.0450 Answer: A.014 a.

Reference:

= (Keff1 - Keff2) ÷ (Keff1

Keff2) = (0.9550 - 1.0000) ÷ (0.9550

1.0000)

= -0.0450 ÷ 0.9550 = -0.0471

Section A - Reactor Theory, Thermodynamics, and Facility Characteristics Page 11 of 22 Question A.015 [1.0 point] {16.0}

Following a significant reactor power increase, the moderator temperature coefficient becomes increasingly more negative. This is because:

a. as moderator density decreases, less thermal neutrons are absorbed by the moderator than by the fuel.

b. the change in the thermal utilization factor dominates the change in the resonance escape probability.

c. a greater density change per degree F occurs at higher reactor coolant temperatures.

d. the core transitions from an under-moderated condition to an over-moderated condition.

Answer: A.015 c.

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory Volume 2, Module 3, Enabling Objective 2.4, p. 26.

Section C - Plant and Radiation Monitoring Systems Page 12 of 22 Question B.001 [2.0 points, 1/2 each] {2.0}

Identify each of the following as either a Safety Limit (SL), Limiting Safety System Setting (LSSS) or a Limiting Condition for Operation (LCO)

a. The rate of reactivity insertion shall not exceed 30¢ per second.

b. The temperature in a stainless-steel-clad high hydride fuel element shall not exceed 1000°C.

c. During steady-state operation a minimum of two reactor power level channels shall be operable.

d. The temperature in an aluminum-clad low hydride fuel element located in the B-hexagonal ring shall not exceed 460°C.

Answer: B.001 a. = LCO; b. = SL; c. = LCO; d. = LSSS

Reference:

R Question B.002 [1.0 point] {3.0}

The CURIE content of a radioactive source is a measure of

a. the number of radioactive atoms in the source.

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

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

d. the number of nuclear disintegrations per unit time.

Answer: B.002 d.

Reference:

Basic Radiation principles Question B.003 [1.0 point] {4.0}

Which ONE of the following scrams built in to the Mark III console is NOT required by Technical Specifications?

a. Reactor Period

b. Fuel Temperature

c. Reactor Tank Water Level

d. Reactor Power Level (Nuclear Instrumentation)

Answer: B.003 a.

Reference:

Modification Authorization MA-2, and Technical Specifications, § 3.3.3 Table.

Section B - Normal, Emergency and Radiological Control Procedures Page 13 of 22 Question B.004 [1.0 point] {5.0}

Two sheets of 1/4 inch thick lead shielding reduces a radiation beam from 200 mR/hr to 100 mR/hr at 1 foot. What will the radiation read at 1 foot if you add another 1/4 inch thick lead sheet (for a total of 3 sheets)?

a. 71 mR/hr

b. 50 mR/hr

c. 35 mR/hr

d. 17 mR/hr Answer: B.004 a.

Reference:

From the stem 2 sheets equal 1 half thickness I = I0 (1/2)1.5 = 200 x 0.3535 =

70.71 Question B.005 [1.0 points, 1/4 each] {6.0}

Match the 10CFR55 requirements for maintaining an active operator license in column A with the corresponding time period from column B.

Column A Column B

a. Renew License 1 year

b. Medical Exam 2 years

c. Pass Requalification Operating Test 4 years

d. Pass Requalification Written Examination 6 years Answer: B.005 a. = 6; b. = 2; c. = 1; d. = 2

Reference:

10CFR55.

Section C - Plant and Radiation Monitoring Systems Page 14 of 22 Question B.006 [2.0 points, 1/2 each] {8.0}

Identify each of the following actions as either a CHANNEL CHECK, CHANNEL TEST or a CHANNEL CALIBRATION.

a. Verifying overlap between Nuclear Instrumentation channels.

b. During reactor shutdown you verify the period meter reads -80 seconds.

c. Performing a calorimetric (heat balance) calculation on the primary system, then adjusting the Nuclear Instrumentation to agree.

d. Replacing a Resistance Temperature Detector (RTD) with a precision resistance decade box, to verify proper channel output for a given resistance.

Answer: B.006 a. = CHECK; b. = CHECK; c. = CAL; d. = TEST

Reference:

T.S. DEFINITIONS Question B.007 [1.0 points, 1/4 each] {9.0}

Match the type of radiation in column A with its associated Quality Factor (10CFR20) from column B.

Column A Column B

a. alpha 1

b. beta 2

c. gamma 5

d. neutron (unknown energy) 10 20 Answer: B.007 a. = 20; b. = 1; c. = 1; d. = 10

Reference:

10CFR20.100x

Section B - Normal, Emergency and Radiological Control Procedures Page 15 of 22 Question B.008 [1.0 point] {10.0}

Following an evacuation of the facility during an emergency. Who by title, may authorize reentry (according to the Emergency Plan)?

a. CENTER Director

b. Reactor Supervisor, with advice of Radiation Safety Officer

c. Any Senior Operator, with advice of Radiation Safety Officer

d. Any NRC licensed Operator, with advice of any health physics technician.

Answer: B.008 b.

Reference:

Emergency Plan, § 3.4 Question B.009 [1.0 point] {11.0}

Which ONE of the following correctly identifies the Technical Specification experiment reactivity limits for single unsecured and secured experiments respectively?

a. 57¢ and $1.00

b. $1.00 and $1.80

c. $1.00 and $2.80

d. $2.00 and $3.80 Answer: B.009 c.

Reference:

Technical Specification 3.1(3) and (5)

Question B.010 [1.0 point] {12.0}

Who may authorize reactor restart following an accident which causes a Safety Limit to be exceeded.

a. Licensed Senior Operator on call.

b. Reactor Supervisor

c. CENTER Director

d. U.S. NRC Answer: B.010 d.

Reference:

Technical Specification 6.7

Section C - Plant and Radiation Monitoring Systems Page 16 of 22 Question B.011 [1.0 point] {13.0}

Per Technical Specifications the maximum amount of time the ventilation system may be out of service (with the reactor running) is

a. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

b. 1 days

c. 2 days

d. one week Answer: B.011 c.

Reference:

Technical Specification 3.5 Question B.012 [1.0 point] {14.0}

Per the Emergency Plan, Emergency Action Level(s) is (are)

a. Projected radiological dose or dose commitment values to individuals that warrant protective action following a release of radioactive material.

b. the person or persons appointed by the Emergency Coordinator to ensure that all personnel have evacuated the facility or a specific part of the facility.

c. A condition that requires immediate action, beyond the scope of normal operating procedures, to avoid or mitigate an accident or event and its consequences.

d. Radiological dose rates; specific contamination levels of airborne, waterborne, or surface deposited concentrations of radioactive materials; or specific instrument readings that may be used as thresholds for initiating specific emergency measures.

Answer: B.012 c.

Reference:

Technical Specifications Question B.013 [1.0 point] {15.0}

CAM alarms are set at

a. 10% of MPC

b. 50% of MPC

c. 100% of MPC

d. 5 times MPC Answer: B.013 b.

Reference:

VI Auxiliary Surveillance Equipment, § II.A p. 97.

Section B - Normal, Emergency and Radiological Control Procedures Page 17 of 22 Question B.014 [1.0 point] {16.0}

The Emergency Response Plan defines Emergency Planning Zone (EPZ) as

a. the area within a 100 meter radius of the reactor core centerline.

b. within the walls of the CENTER (Rooms 1205A-G).

c. within the walls of the Merrill Engineering Building.

d. Geographical Area within the U of U campus Answer: B.014 c.

Reference:

Emergency Response Plan § 1.0 Definitions: Emergency Planning Zone.

Question B.015 [1.0 point] {17.0}

Which ONE of the following is the MINIMUM number of hours per calendar quarter per 10CFR55 you must perform the duties of an SRO to maintain your license active?

a. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

b. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

c. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

d. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Answer: B.015 b.

Reference:

10CFR55.

Section C - Plant and Radiation Monitoring Systems Page 18 of 22 Question C.001 [1.0 point] {1.0}

WHICH ONE of the following detectors is used primarily to measure N16 release to the environment?

a. NONE, N16 has too short a half-life to require environmental monitoring.

b. TA BAM-3H Continuous Air Monitor Particulate Channel

c. TA BAM-3H Continuous Air Monitor Gaseous Channel

d. TA BAM-3H Continuous Air Monitor Iodine Channel Answer: C.001 a.

Reference:

Chart of the Nuclides.

Question C.002 [1.0 point] {2.0}

Fuel temperature must be limited in the aluminum clad, low hydride fuel elements in order to avoid fuel element failure due to which of the following mechanisms?

a. Melting the aluminum cladding due to high temperature.

b. Distortion of the fuel element due to a phase change of the zirconium hydride.

c. Damage to fuel cladding due to excessive pressure from expansion of fission product gasses.

d. Damage to fuel cladding due to excessive pressure from hydrogen produced by disassociation of the zirconium and hydrogen.

Answer: C.002 b.

Reference:

Technical Specifications Section 2.1 bases.

Question C.003 [1.0 point] {3.0}

How long will the single phase backup generator operate, before it must be refueled?

a. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

b. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

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

d. 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Answer: C.003 c.

Reference:

VI, Auxiliary Surveillance Equipment, § III. Auxiliary Power System, 3rd ¶.

Section C - Plant and Radiation Monitoring Systems Page 19 of 22 Question C.004 [1.0 point] {4.0}

A pipe flange fails just downstream of the primary pump. What design feature of the primary system prevents draining of the pool?

a. Signal from a float switch shuts off the primary pump.

b. Signal from a float switch shuts a valve in the pump suction line.

c. Level in the pool drops below siphon break holes in the primary suction pipe.

d. Level in the pool drops below the Net Positive Suction Head pressure minimum required to operate the pump.

Answer: C.004 c.

Reference:

III, Maintenance and Surveillance, § I.B.7.d 1st ¶, p. 41 Question C.005 [1.0 point] {5.0}

Which ONE of the following is NOT an input signal into the AUTOMATIC circuit for the regulating rod?

a. Power Demand Level

b. Log-N Period

c. Linear Power

d. Count Rate Answer: C.005 d.

Reference:

Modification Authorization MA-1, figure 6.

Question C.006 [2.0 points, 1/2 each] {7.0}

For each of the gasses listed in column A identify its primary source (i.e. neutron irradiation of air, neutron irradiation of Water or Fission Product).

a. H3

b. N16

c. Ar41

d. Xe138 Answer C.006 a = W; b = W; c = Air; d = FP

Reference:

Standard NRC Question

Section C - Plant and Radiation Monitoring Systems Page 20 of 22 Question C.007 [1.0 point] {8.0}

Which ONE of the following may be used for the storage of UNIRRADIATED Fuel, but NOT used for the storage of IRRADIATED Fuel?

a. Reactor Tank

b. Secured Storage Pits

c. Cf252 room (room 1205B)

d. Radio Chem Lab (room 1205K)

Answer: C.007 c.

Reference:

II, Reactor Operations, § F.3 Question C.008 [1.0 point] {9.0}

Which ONE of the following is the reason that the ventilation system maintains a negative pressure in the reactor room?

a. To reduce pressure on the reactor tank.

b. To ensure proper operation of the Continuous Air Monitor.

c. To facilitate opening of the door between the control room and the reactor room.

d. To ensure that any radioactive contaminants go through the stack, vice through any cracks in the room.

Answer: C.008 d.

Reference:

III, Maintenance and Surveillance, § I.B.7.c, 1st ¶ Question C.009 [1.0 point] {10.0}

CENTER-015, specifies equipment required to be on-hand for an emergency. It requires a Radiation-Exposure survey meter to be in the control room. This meter is a

a. Personnel Dosimeter

b. Scintillation radiation detector

c. Ion Chamber radiation detector

d. Geiger-Muller radiation detector Answer: C.009 c.

Reference:

Standard NRC question

Section C - Plant and Radiation Monitoring Systems Page 21 of 22 Question C.010 [1.0 point] {11.0}

To prevent serious damage never allow the water temperature to drop below about ___ while the recirculation system is on.

a. 0º C

b. 5º C

c. 10º C

d. 20º C Answer: C.010 b

Reference:

V. TRIGA Reactor Console pg. 77, ¶ Water Temperatures Question C.011 [1.0 point] {12.0}

The purpose of removing the source at 1 watt is to

a. minimize depletion of the Plutonium.

b. minimize depletion of the Beryllium.

c. prevent invalid readings on nuclear instrumentation.

d. minimize radiation hazards due to the activation of the source.

Answer C.011 a.

Reference:

Procedure 13.1.4 Question C.012 [1.0 point] {13.0}

The purpose of the cleanup system is to minimize corrosion of the cladding on the fuel elements and to minimize the

a. need for cooling the pool

b. growth of algae in the pool

c. generation of tritium (1H3) in the pool.

d. activation of dissolved materials in the pool.

Answer: C.012 d.

Reference:

Modification MA-2, Reactor Control System 3rd ¶.

Section C - Plant and Radiation Monitoring Systems Page 22 of 22 Question C.013 [2.0 points, 1/2 each] {15.0}

Identify the type of heat mechanism (listed in column B) primarily responsible for removing heat for each of the facility regions listed in column A.

Column A Column B

a. Centerline to outside edge of fuel 1. Conduction

b. Core to pool water 2. Forced Convection

c. Pool water to heat exchanger 3. Natural Convection

d. Heat exchanger to Freon 4. Radiative Answer: C.013 a = 1; b = 3; c = 2; d = 2

Reference:

Standard NRC question Question C.014 [1.0 point] {16.0}

What design feature of the purification system prevents draining of the pool on a piping break.

a. The piping has a vacuum breaker at the its highest point.

b. No piping extends into the pool more than 5 feet below the pool surface.

c. All piping has small holes (siphon breaks) located about 2 feet below the pool surface.

d. All piping either has small holes (siphon breaks) 2 feet below the pool surface or does not extend more than 5 feet below the pool surface.

Answer: C.014 d.

Reference:

SER § 5.1, Technical Specifications § 5.7.

Question C.015 [1.0 point] {17.0}

The pneumatic tube system uses ___ to move the sample.

a. High pressure air from an air receiver pressurized by an air compressor.

b. Compressed Nitrogen from 2000 psi bottles.

c. Freon supplied by a compressor.

d. Air from a blower.

Answer C.015 a.

Reference:

IV.C, Pg. 54

ML092020487

Text

SUBJECT:

Dear Dr. Choe:

Enclosures:

SUBJECT:

Dear Dr. Choe:

Enclosures:

SUMMARY

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