ML092020244

Initial Examination Report, No. 50-288/OL-09-01, Reed College

ML092020244
Person / Time
Site:	Reed College
Issue date:	07/28/2009
From:	Johnny Eads Research and Test Reactors Branch B
To:	Frantz S Reed College
Young P T, NRR/PRTB, 415-4094
References
50-288/OL-09-01
Download: ML092020244 (19)

Text

July 28, 2009 Mr. Steven G. Frantz, Director Reed Reactor Facility 3203 SE Woodstock Blvd.

Portland, OR 97202

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-288/OL-09-01, REED COLLEGE

Dear Mr. Frantz:

During the week of May 4, 2009, the NRC administered operator licensing examinations at your Reed College 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. 50-288

Enclosures:

1. Initial Examination Report No. 50-288/OL-09-01

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

Please see next page

July 28, 2009 Mr. Steven G. Frantz, Director Reed Reactor Facility 3203 SE Woodstock Blvd.

Portland, OR 97202

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-288/OL-09-01, REED COLLEGE

Dear Mr. Frantz:

During the week of May 4, 2009, the NRC administered operator licensing examinations at your Reed College 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. 50-288

Enclosures:

1. Initial Examination Report No. 50-288/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-13 D-07 ADAMS ACCESSION #: ML092020244 TEMPLATE #:NRR-074 OFFICE PRTB:CE IOLB:LA E PRTB:SC NAME PYoung: CRevelle JEads DATE 07/21/2009 07/24/2009 07/28/2009 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY

Reed College Docket No. 50-288 cc:

Mayor of the City of Portland 1220 Southwest 5th Avenue Portland, OR 97204 Reed College ATTN: Dr. Peter Steinberger Dean of Faculty 3203 S.E. Woodstock Boulevard Portland, OR 97202-8199 Reed College ATTN: Dr. Colin Diver, President 3203 S.E. Woodstock Boulevard Portland, OR 97202-8199 Ken Niles, Assistant Director Oregon Department of Energy 625 Marion Street NE Salem, OR 97301-3737 Terry D. Lindsey, Program Director Radiation Control Program Oregon Health Services Department of Human Services 800 NE Oregon Street, Suite 640 Portland, OR 97232-2162 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611 Mr. Stephen Frantz, Director Reed Reactor Facility Reed College 3203 S.E. Woodstock Boulevard Portland, OR 97202-8199

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-288/OL-09-01 FACILITY DOCKET NO.: 50-288 FACILITY LICENSE NO.: R-112 FACILITY: Reed College Reactor EXAMINATION DATES: May 4 - 8, 2009 SUBMITTED BY: __________________________ _________

Phillip T. Young, Chief Examiner Date

SUMMARY

During the week of May 4, 2009, the NRC administered operator licensing examinations to thirteen Reactor Operator (RO) candidates and nine Senior Operator Upgrade (SROU) candidates. All candidates passed all portions of the examination.

REPORT DETAILS

1. Examiners: Phillip T. Young, Chief Examiner, NRC Paul V. Doyle Jr., Examiner, NRC

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 13/0 0/0 13/0 Operating Tests 13/0 9/0 22/0 Overall 13/0 9/0 22/0

3. Exit Meeting:

Phillip T. Young, Chief Examiner, NRC Mr. Steven G. Frantz, Director The NRC examiner thanked the facility staff for their cooperation during the examination.

The examiner reported no generic weaknesses.

ENCLOSURE 1

Section A L Theory, Thermo & Facility Operating Characteristics Page 1 QUESTION A.01 [1.0 points] {1}

The delayed neutron fraction, , is defined as a ratio of:

a. Thermal utilization over fast fission factor.

b. The number of thermal neutrons over the number of fast neutrons in the core.

c. The number of delayed neutrons over the number of total neutrons in the core.

d. The number of thermal neutrons absorbed in fuel over the number of thermal neutrons absorbed in core materials including in fuel.

A.01 c REF Introduction to Nuclear Operation, Reed Burn, 1988, Sec 3.3.3, page 3-11.

QUESTION A.02 [1.0 point] {2}

Reactor power is rising on a 40 second period. Approximately how long will it take for power to triple?

a. 35 seconds.

b. 44 seconds.

c. 72 seconds.

d. 120 seconds.

A.02 b t/T REF: P = P0 e --> ln(3)*40sec = time; time = ln (3) x 40 sec 44 sec QUESTION A.03 [1 points] {3} Change made during administration of the exam.

In a just critical reactor, removing adding one dollar worth of reactivity will cause:

a. A sudden drop in neutron flux.

b. The reactor period to be equal to (-)/.

c. All prompt neutron term to become unimportant.

d. The resultant period to be a function of the prompt neutron lifetime.

A.03 d REF Introduction to Nuclear Operation, Reed Burn, 1988, Sec 4.2, page 4-4 ENCLOSURE 2

Section A L Theory, Thermo & Facility Operating Characteristics Page 2 QUESTION A.04 [1.0 point] {4}

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

a. From 1 W to 5 W.

b. From 10 W to 30 W.

c. From 10 kW to 20 kW.

d. From 100kW to 150 kW.

A.04 d t/T REF: P = P0 e --> t= T*Ln(P/ P0 ) assume constant period = 1 t= Ln(P/ P0 ) --> the smallest ratio of P/ P0 is the shortest time to complete; so it is 150kW/100kW.

QUESTION A.05 [1.0 point] {5}

Following a scram, the value of the stable reactor period is:

a. approximately -10 seconds, as determined by the rate of decay of the shortest lived prompt neutrons.

b. approximately -80 seconds, as determined by the rate of decay of the shortest lived delayed neutron precursor.

c. approximately -80 seconds, as determined by the rate of decay of the longest lived delayed neutron precursors.

d. infinity because the control rods absorb all neutrons.

A.05 c REF Introduction to Nuclear Operation, Reed Burn, 1988, Sec 4.5, page 4-12 QUESTION A.06 [1.0 point ] {6}

The neutron multiplication factor is defined as a ratio of:

a. The number of thermal neutrons absorbed in fuel over the number of thermal neutrons absorbed in core materials.

b. The number of neutrons produced by fission in a generation over the number of neutrons produced by fission in the previous generation.

c. The number of neutrons produced by fission in the previous generation over the number of neutrons produced by fission in a generation.

d. The number of thermal neutrons produced by fission in a generation over the number of thermal neutrons produced by fission in the previous generation.

A.06 b REF: REED Training Manual, September 2008, page 116.

Section A L Theory, Thermo & Facility Operating Characteristics Page 3 Question deleted during the administration of the exam, answer left identified on applicant exam.

QUESTION A.07 [1.0 point] {7}

Which ONE of the following statements best describes the MAJOR contributor to the production and depletion of Xenon respectively in a STEADY-STATE OPERATING reactor?

Production Depletion

a. Directly from fission Neutron absorption

b. Directly from fission Radioactive Decay

c. Radioactive decay of Iodine Neutron absorption

d. Radioactive decay of Iodine Radioactive Decay A.7 c (depletion: burn off by neutron)

REF Introduction to Nuclear Operation, Reed Burn, 1988, Sec 8-2, page 8-3.

QUESTION A.08 [1.0 point] {8}

Which ONE of the following materials is the best moderator for the reactor?

a. Water.

b. Beryllium.

c. graphite.

d. Uranium-238.

A.08 a REF REED Training Manual, September 2008, page 109.

QUESTION A.09 [1.0 point] {9}

The reactor (not at Reed College) is shutdown by $11.27. A rate of 1000 counts per second (cps) is measured when a control rod worth of -$4.06 is removed from the core. What is the previous count rate (cps)?

a. 656.

b. 753.

c. 1541.

d. 2173.

A.09 a REF k = 1/1-; = $* ; assume =0.007 --> 1=-$11.27*.007=-0.0789; Keff1=1/1- 1 Keff1 =1/(1-(-.0789)) -->Keff1= 0.927, Remove $4.06 from the core, means adding +$4.06 to the core; new worth = -$11.27 +4.06 =-$7.21, 2=-$7.21*.007=-0.0505; Keff2 = 1/1+0.0505; -->0.952 Count1*(1-Keff1) = Count2*(1-Keff2) Count1*(1-0.927) = Count2*(1-Keff2)

Count1*(1-0.927) = 1000(1-0.952); Count 1 = 656 cps

Section A L Theory, Thermo & Facility Operating Characteristics Page 4 QUESTION A.10 [1.0 point] {10}

Which ONE of the following reasons causes the reactor power to rapidly decrease in Zr-H-U mixture used in the TRIGA fuel due to a rapid power excursion (rapid reactivity change)?

a. By increasing of the reproduction factor.

b. By increasing of Doppler broadening of Zr.

c. By decreasing of the thermal utilization factor.

d. By increasing of Doppler broadening of U-235.

A.10 c REF no Doppler broadening for Zr or U-235, just for U-238.

QUESTION A.11 [1.0 point] {11}

Which ONE of the following describes the MAJOR contributor to the negative temperature coefficient of reactivity in the Reed TRIGA reactor?

a. Decreasing of fuel density.

b. Zr-H Moderator Effects.

c. Decreasing of water pool density.

d. Increasing the resonance absorption in the fuel.

A.11 b REF Reed Training Manual, pg. 167 QUESTION A.12 [1.0 point] {12}

Assume the following reactivity worth in the reactor core (not at Reed College):

Safety Rod 1 = $4.00 Shim Rod = $3.00 Reg Rod = $2.00 Safety Rod 2 = $3.50 Core excess = $1.50 Calculate the shutdown margin with safety rod 1 stuck all the way out.

a. $1.00.

b. $5.50.

c. $7.00.

d. $11.00.

A.12 c REF Total worth=$4+$3+$2+$3.5=$12.5; SDM = total worths - (core +safety rod 1)

= $12.5-($1.5+$4)

=$7

Section A L Theory, Thermo & Facility Operating Characteristics Page 5 QUESTION A.13 [1.0 point] {13}

Which ONE of the following parameters is MOST significant in determining the differential worth of a control rod?

a. Rod speed.

b. Flux Shape.

c. Fuel loading.

d. Reactor power.

A.13 b REF: Fund. Of Nuclear Engineering, Chapter 3, Section 4, page 75.

QUESTION A.14 [1.0 point] {14}

List from high to low by thermal neutron cross section of the following isotopes:

1. B-10 2. Sm-149 3. Xe-135 4. U-235

a. 3,2,1,4.

b. 2,3,4,1.

c. 3,1,4,2.

d. 3,1,2,4.

A.14 a REF Introduction to Nuclear Operation, Reed Burn, 1988, Table 2.5, page 2-59 QUESTION A.15 [1.0 point] {15}

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

a. Prompt gamma rays.

b. Decay of the fission fragments.

c. Kinetic energy of the fission neutrons.

d. Kinetic energy of the fission fragments.

A.15 d REF Introduction to Nuclear Operation, Reed Burn, 1988, Sec 3.2, page 3-5

Section A L Theory, Thermo & Facility Operating Characteristics Page 6 QUESTION A.16 [1.0 point] {16}

During a reactor startup, as K-effective approach criticality, the value of 1/M:

a. decreases toward one.

b. decreases toward zero.

c. increases toward one.

d. increase toward infinitive.

A.16 b REF Standard NRC question

Section B Normal, Emergency and Radiological Control Procedures Page 7 QUESTION B.01 [1.0 points] {1}

Which ONE of the following statements is NOT a limitation of experiments?

a. Any individual in-core experiment shall not exceed $1.35.

b. Total worth of in-core experiments shall not exceed $2.0.

c. Experiments having reactivity worths greater than $1.0 shall be secure experiments.

d. Maximum worth of all experiments shall be less than 2.25% delta k/k above cold, critical, and without xenon.

B.01 d REF Reed TS, Section J QUESTION B.02 [2.0 points, 0.5 each] {3}

Match the terms in column A with their respective definitions in column B.

Column A Column B

a. Radioactivity 1. To remove a facility or site safely from service and reduce residual radioactivity to a level that permits in 10 CFR 52.

b. Contamination 2. An impurity pollutes or adulterates another substance. The transferable radioactive materials are the sources of ionizing radiations.

c. Dose 3. The quantity of radiation absorbed per unit mass by the body or by any portion of the body.

d. Decommission 4. That property of a substance which causes it to emit ionizing radiation. This property is the spontaneous transmutation of the atoms of the substance.

B.02 a(4) b(2) c(3) d(1)

REF 10 CFR 20 QUESTION B.03 [1.0 point] {4}

A radioactive source reads 35 Rem/hr on contact. Five hours later, the same source reads 1.5 Rem/hr. How long is the time for the source to decay from a reading of 35 Rem/hr to 100 mRem/hr?

a. 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

b. 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

c. 8.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

d. 9.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

B.03 d

-t REF DR = DR*e

-(5hr) 1.5 rem/hr =35 rem/hr* e Ln(1.5/35) = -*5 --> =0.623; solve for t: Ln(.1/35)=-0.623 (t) t=9.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

Section B Normal, Emergency and Radiological Control Procedures Page 8 QUESTION B.04 [2.0 points, 1/2 each] {6}

Match each of emergency events listed in column A with the correct emergency classes listed in column B. Items in column B may be used once, more than once or not at all.

Column A Column B

a. Personnel injury with radiological complication. 1. Non-reactor safety related event.

b. Pool level alarm indicating loss of water. 2. Notification of unusual event.

c. A deep dose equivalent of 20 mRem/hr 3. Alert.

for 30 min at the site boundary.

d. Receipt of a bomb threat with possible radiological release implication.

B.04 a. = 1; b. = 2; c. = 3; d. = 2 REF EP, pages 20, 21, and 22 QUESTION B.05 [1.0 point] {7}

A radioactive material is decayed at a rate of 30% per day. Determine its half-life?

a. 1 day.

b. 2 days.

c. 3 days.

d. 5 days.

B.05 2 days

-t REF DR = DR*e

-(1day) 30% is decayed, so 70% is still there 70% =100%* e Ln(70/100) = -*1 -->=0.356 t1/2=Ln(2)/ -->.693/.356 t=1.94 days QUESTION B.06 [1.0 point] {8}

During an initial start-up, the RO calculates a core excess reactivity (CER) of 2.35% delta k/k above cold, critical, without xenon. For this CER value, which ONE of the following is the best action?

a. Continue the start-up; increase power to 1 kW and re-verify the result.

b. Continue the start-up; increase power to desire level because the CER value is within TS limit.

c. Shutdown the reactor; immediately report the result to the SRO due to CER value being above TS limit.

d Shutdown the reactor; immediately report the result to NRC.

B.06 c REF TS E.2

Section B Normal, Emergency and Radiological Control Procedures Page 9 QUESTION B.07 [1.0 point] {9}

An area in which radiation levels from radiation source to the body could result in an individual a dose equivalent in excess of 100 mRem/hr is defined as:

a. Radiation area

b. Unrestricted Area

c. High Radiation Area.

d. Very High Radiation Area B.07 c REF 10 CFR 20 QUESTION B.08 [1.0 point] {10}

Which ONE of the following conditions requires a radiation work permits (RWPs) in accordance with SOP 53?

a. Collect the pool sample for monthly test.

b. Go on the bridge during a beam irradiation.

c. A deep dose equivalent to an individual in excess of 2 mRem.

d. Remove samples from the lazy susan, central thimble, or rabbit.

B.08 b REF SOP 53, Sec 53.2 QUESTION B.09 [1.0 point] {11}

10 CFR 50.54(x) states that a licensee may deviate from its technical specifications to protect the public health and safety in case of an emergency. Which ONE of the following is the MINIMUM level that can authorize this deviation?

a. Reactor Director.

b. Reactor operator.

c. Reactor Manager.

d. Senior reactor operator.

B.09 d REF 10 CFR 50(x),(y)

Section B Normal, Emergency and Radiological Control Procedures Page 10 QUESTION B.10 [1.0 point] {12}

Which ONE of the following materials shall be doubly encapsulated in the Reed TRIGA reactor?

a. A volatile material.

b. An explosive material.

c. A short half-life material.

d. A liquid fissionable material.

B.10 d REF TS J.5 QUESTION B.11 [1.0 point] {13}

Which one of the following is the definition of Total Effective Dose Equivalent (TEDE) specified in 10 CFR Part 20?

a. The sum of thyroid dose and external dose.

b. The sum of the external deep dose and the organ dose.

c. The sum of the deep dose equivalent and the committed effective dose equivalent.

d. The dose that your whole body is received from the source, but excluded from the deep dose.

B.11 c REF 10 CFR 20.1003.

QUESTION B.12 [1.0 point] {14}

The Reed TRIGA reactor has been shutdown due to a fuel element leak. Which ONE of the following radioactive gases poses the most significant hazard during the research for the leaking fuel element? (Assume the fuel element is leaking during the search)?

a. Argon.

b. Tritium.

c. Xenon.

d. Nitrogen.

B.12 c REF Standard NRC question QUESTION B.13 [1.0 point] {15}

During an earthquake, the reactor operator must perform the following tasks, EXCEPT:

a. Isolate the demin tank.

b. Isolate the heat exchanger.

c. Stop the cooling system pumps.

d. Scam the reactor and remove the console key.

B.13 a REF EIP, Procedure D

Section B Normal, Emergency and Radiological Control Procedures Page 11 QUESTION B.14 [1.0 point] {16}

The derived limit for the amount of radioactive material taken into the body of an adult worker by inhalation or ingestion in a year is defined as:

a. Annual limit on intake (ALI)

b. Annual dose limit (ADI)

c. Derived air concentration (DAC)

d. Airborne radioactive limit (ARL)

B.14 a Ref 10CFR20

Section C Facility and Radiation Monitoring Systems Page 12 QUESTION C.01 [2.0 points, 0.5 each] {2}

Match the input signals listed in column A with their respective responses listed in column B. (Items in column B may be used more than once or not at all.)

Column A Column B

a. Manual scram. 1. Indication only.

b. 30-sec period. 2. Indication and scram only.

c. No neutron source. 3. Indication and interlock only.

d. 110% in linear channel. 4. Indication, scram, and interlock.

C.01 a(2) b(1) c(3) d(2)

REF Reed TS QUESTION C.02 [1.0 point, 0.25 each] {3} Descriptions added to c & d during exam.

Match the devices listed in column A with the operation status listed in column B during an isolation mode of the ventilation system. (Items in column B may be used more than once or not at all.)

Column A Column B

a. Exhaust Fan. 1. ON

b. Supply Fan. 2. OFF

c. Damper 11. (fresh supply inlet) 3. OPEN

d. Damper 14. (HEPA inlet) 4. CLOSED C.02 a(1) b(2) c(4) d(3)

REF REF Reed Training Manual, September 2008, page 194 QUESTION C.03 [1.0 point] {4}

Which ONE of the following best describes the reason for the high sensitive of Geiger-Mueller tube detector?

a. Coating with U-235.

b. A longer length tube, so target is larger for all incident events.

c. Lower voltage applied to the detector helps to amplify all incident events.

d. Any incident radiation event causing primary ionization results in ionization of entire detector.

C.03 d REF Training Manual, Sec 5.2

Section C Facility and Radiation Monitoring Systems Page 13 QUESTION C.04 [1.0 point] {5}

Graphite inserts are placed in the top and bottom of the fuel element. Which ONE of the following best describes the function of these inserts:

a. To absorb thermal neutrons.

b. To reduce neutron leakage.

c. To absorb fission product gases.

d. To increase fast neutron flux.

C.04 b REF Training Manual QUESTION C.05 [2.0 points, 0.5 each] {7}

Given the configuration of the lights associated with the safety rod listed in column A below, identify the condition of the safety rod and its motor.

COLUMN A COLUMN B RED (UP) WHITE (DOWN) BLUE (CONT)

a. OFF ON ON 1. Raising rod

b. ON OFF OFF 2. Rod dropping

c. ON OFF ON 3. Rod hits bottom

d. OFF OFF ON 4. Scram is reset C.05 a. = 4; b. = 3; c. = 2; d. = 1 REF Reed Training Manual, September 2008, page 178 QUESTION C.06 [1.0 point] {8}

Which ONE of the following is the best reason to prevent Ar-41 from the pneumatic transfer system leaking into the reactor control room?

a. The speed of the rabbit.

b. The exhaust stack height.

c. High efficient particulate air (HEPA) filters.

d. The rabbit system is negative pressure comparing to the reactor rooms.

C.06 d REF: Reed Training Manual, September 2008, page 181

Section C Facility and Radiation Monitoring Systems Page 14 QUESTION C.07 [1.0 points, 0.25 each] {9} change made during the examination administration Match each radiation detection system listed in column A with the type of detectors in column B. Items in column B is be used only once.

Column A Column B

a. RAM 1. Geiger-Mueller Tube

b. SGM GSM 2. Scintillation

c. Walk through monitor 3. Geiger Counter

d. Hand and shoe monitor 4. Proportional Detector C.07 a(1) b(4) c(2) d(3)

REF SOPs 40,41, and 42 QUESTION C.08 [1.0 point] {10}

Which ONE of the following events does not require the supervision of the SRO of Record?

a. Fuel movement.

b. First core excess of the day.

c. Maintenance on control system.

d. Maintenance primary cooling pump.

C.08 d REF SOP 1, Sec 1.3 QUESTION C.09 [1.0 point] {11}

The purpose of adding algaecide in the cooling system is:

a. Reduce radioactivity in the water.

b. Maintain the optical clarity of the reactor pool.

c. Suppress biological growth in the cooling system

d. Minimize corrosion of components in the reactor pool.

C.09 c REF Reed Training Manual, September 2008, page 186 QUESTION C.10 [1.0 point] {12}

Order the following equipments in the cooling system; start from the pool outlet and end at the pool inlet.

1. Heat exchanger 2. Primary pump 3. Flow meter 4. Demin Tank 5. Water filter

a. 1 2 3 4 5.

b. 2 3 1 5 4.

c. 4 2 3 1 5.

d. 2 1 5 4 3.

C.10 d REF Reed Training Manual, September 2008, Figure 11.13

Section C Facility and Radiation Monitoring Systems Page 15 QUESTION C.11 [1.0 point] {13}

Conductivity averaged over a month shall not exceed ____ micromhos per centimeter in the Reed Triga pool water.

a. 1

b. 2

c. 3

d. 4 C.11 b REF TS D.2 QUESTION C.12 [1.0 point] {14}

The ion chamber indications are correlated to the heat balance calculated thermal power by:

a. adjusting the circuit amplifier.

b. adjusting the detector high voltage.

c. physically adjusting the height of the detectors in the support assembly.

d. moving the graphite reflector to change the neutron flux near the detectors.

C.12 c REF SOP 33 QUESTION C.13 [1.0 point] {15}

The output of the Uncompensated Ion Chamber provides the signal:

a. for Linear Channel.

b. for Log-n Channel.

c. for the period circuit.

d. for % Power Channel.

C.13 d REF Reed Manual, Figure 11.10 QUESTION C.14 [1.0 point] {16}

Which ONE of the following experimental facilities provides the greatest neutron flux?

a. Beam Port.

b. Rabbit.

c. Lazy Susan.

d. Central thimble.

C.14 d REF SOP 14