Text

Examination Report No. 50-288/OL-13-02, Reed College
	ML13155A489
Person / Time
Site:	Reed College
Issue date:	06/07/2013
From:	Gregory Bowman; Research and Test Reactors Branch B
To:	Krahenbuhl M; Reed College
	Lichatz, T
Shared Package
ML13042A419	List: ML13042A421; ML13155A489; ML13155A500;
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	Download: ML13155A489 (42)
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June 7, 2013 Dr. Melinda Krahenbuhl, Director Reed Reactor Facility Reed College 3203 SE Woodstock Blvd.

Portland, OR 97202

SUBJECT:

EXAMINATION REPORT NO. 50-288/OL-13-02, REED COLLEGE

Dear Dr. Krahenbuhl:

During the weeks of May 6 and May 13, 2013, the Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your TRIGA Reactor. The examination was 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 NRCs 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 Taylor Lichatz at (301) 415-7128 or via electronic mail Taylor.Lichatz@nrc.gov.

Sincerely,

/RA/

Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-288

Enclosures:

1. Examination Report No. 50-288/OL-13-02

2. Facility Comments with NRC Resolution

3. Written examination cc without enclosures: See next page

June 7, 2013 Dr. Melinda Krahenbuhl, Director Reed Reactor Facility Reed College 3203 SE Woodstock Blvd.

Portland, OR 97202

SUBJECT:

EXAMINATION REPORT NO. 50-288/OL-13-02, REED COLLEGE

Dear Dr. Krahenbuhl:

During the weeks of May 6 and May 13, 2013, the Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your TRIGA Reactor. The examination was 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 NRCs 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 Taylor Lichatz at (301) 415-7128 or via electronic mail Taylor.Lichatz@nrc.gov.

Sincerely,

/RA/

Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-288

Enclosures:

1. Examination Report No. 50-288/OL-13-02

2. Facility Comments with NRC Resolution

3. Written examination cc without enclosures: See next page DISTRIBUTION:

PUBLIC RidsNrrDprPrta RidsNrrDprPrtb PYoung, NRR Facility File (CRevelle) O-07 F-08 PIsaac, NRR TLichatz, NRR ADAMS ACCESSION #: ML13155A489 TEMPLATE #: NRR-079 Office PROB/OLE PROB/CE IOLB/OLA PROB/BC Name TLichatz PYoung CRevelle GBowman Date 5/31/13 6/4/13 6/4/13 6/7/13 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. Ellen Stauder, Dean of Faculty 3203 SE Woodstock Boulevard Portland, OR 97202-8199 Reed College ATTN: Dr. Colin Diver, President 3203 SE 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

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-288/OL-13-02 FACILITY DOCKET NO.: 50-288 FACILITY LICENSE NO.: R-112 FACILITY: Reed College EXAMINATION DATES: May 6-14, 2013 SUBMITTED BY: _________/RA/_________________ 6/4/2013__

Philip T. Young, Chief Examiner Date

SUMMARY

During the weeks of May 6 and May 13, 2013, the NRC administered the operator licensing examinations to fifteen (15) Reactor Operator candidates and six Senior Reactor Operator Upgrade candidates. One (1) Reactor Operator candidate failed the written portion of the examination and one (1) Senior Reactor Operator candidate failed the operating portion of the examination.

REPORT DETAILS

1. Examiners: Philip T. Young, Chief Examiner Patrick Isaac, Examiner Taylor A. Lichatz, Examiner

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 14/1 N/A 14/1 Operating Tests 15/0 5/1 20/1 Overall 14/1 5/1 19/2

3. Exit Meeting:

Taylor Lichatz, NRC, Examiner Dr. Melinda Krahenbuhl, Director, Reed Reactor Reuven Lazarus, Reactor Supervisor, Reed Reactor The examiner met with the facility staff to discuss the overall administration of the examination and thanked them for their support during the examination and for their comments on questions.

ENCLOSURE 1

Facility Comments with NRC Resolution Facility Comments May 14, 2013 Comments on written examination, 50-288/OL-13-02 Question C.7 Schematics of the ventilation system in normal and isolation modes (from RRR SOPs 32A and 32B) are attached. When the system enters isolation, damper 13 (HEPA Bypass) closes but damper 14 (HEPA Inlet) opens. These are both exhaust dampers.

Since the exhaust dampers open and the exhaust dampers close imply that all the exhaust dampers are opening or closing, no answer is correct.

We propose to delete this question.

Question C.20 Answer (b) was correct until April 2012. As of our license renewal, the 1.64 curie AmBe source is the only source specifically mentioned in the facility license.

Because no answer is correct, we propose to delete this question.

NRC Resolution:

Question C.7: Comment accepted. This question was deleted from the examination.

Question C.20: Comment accepted. This question was deleted from the examination.

ENCLOSURE 2

U. S. NUCLEAR REGULATORY COMMISSION RESEARCH AND TEST REACTOR OPERATOR LICENSING EXAMINATION FACILITY: Reed College REACTOR TYPE: TRIGA DATE ADMINISTERED: 05/06/2013 CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheets provided. Points for each question are indicated in brackets for each question. You must score 70% in each section to pass. Examinations will be picked up three (3) hours after the examination starts.

% of Category % of Candidates Category Value Total Score Value Category 20.00 33.33 A. Reactor Theory, Thermodynamics and Facility Operating Characteristics 20.00 33.33 B. Normal and Emergency Operating Procedures and Radiological Controls 20.00 33.33 C. Plant and Radiation Monitoring Systems FINAL GRADE

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

Candidate's Signature

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

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

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

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

10. When you have completed and turned in you examination, leave the examination area.

EQUATION SHEET

Q = m c p T = m H = UA T

( - )2 * -4

1 x 10 seconds P max

2 (k)

S CR 1 (1 - K eff 1 ) = CR 2 (1 - K eff 2 )

SCR =

1 - K eff eff = 0.1 sec-1 SUR = 26.06 eff 1 - K eff 0 1 CR1

- M= M= =

1 - K eff 1 1 - K eff CR 2 P = P0 10 SUR(t) P = P0 e t

(1 - )

P= P0 (1 - K eff ) * -

SDM = = =

+

K eff -

eff K eff 2 - K eff 1 0.693 ( K eff - 1)

T=

k eff 1 x K eff 2 K eff 6CiE(n) 2 DR1 d 1 = DR 2 d 2 2

DR = DR0 e- t DR = 2 R

2

( 2 - )2 ( 1 - )

=

Peak 2 Peak 1 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lbm 3

1 Horsepower = 2.54 x 10 BTU/hr 1 Mw = 3.41 x 106 BTU/hr

1 BTU = 778 ft-lbf EF = 9/5 EC + 32 1 gal (H2O) . 8 lbm EC = 5/9 (EF - 32)

Section A L Theory, Thermo, and Facility Characteristics ANSWER SHEET Multiple Choice (Circle or X your choice)

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

A001 a b c d __

A002 a b c d __

A003 a b c d __

A004 a b c d __

A005 a b c d __

A006 a b c d __

A007 a b c d __

A008 a b c d __

A009 a b c d __

A010 a b c d __

A011 a b c d __

A012 a b c d __

A013 a b c d __

A014 a b c d __

A015 a b c d __

A016 a b c d __

A017 a b c d __

A018 a b c d __

A019 a b c d __

A020 a b c d __

- - - - END OF SECTION A *****

Section B Normal/Emerg. Procedures & Rad Con ANSWER SHEET Multiple Choice (Circle or X your choice)

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

B001 a __ b __ c ___

B002 a b c d __

B003 a b c d __

B004 a b c d __

B005 a b c d __

B006 a b c d __

B007 a b c d __

B008 a b c d __

B009 a b c d __

B010 a b c d __

B011 a b c d __

B012 a b c d __

B013 a b c d __

B014 a b c d __

B015 a b c d __

B016 a b c d __

B017 a b c d __

B018 a b c d __

B019 a b c d __

B020 a __ b __ c __ d ___

- - - - END OF SECTION B *****

Section C Facility and Radiation Monitoring Systems ANSWER SHEET Multiple Choice (Circle or X your choice)

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

C001 a b c d __

C002 a b c d __

C003 a b c d __

C004 a b c d __

C005 a b c d __

C006 a b c d __

C007 a b c d __

C008 a b c d __

C009 a b c d __

C010 a b c d __

C011 a __ b __ c __ d ____

C012 a b c d __

C013 a __ b __ c __ d ____

C014 a b c d __

C015 a b c d __

C016 a b c d __

C017 a b c d __

C018 a b c d __

C019 a b c d __

C020 a b c d __

- - - - END OF SECTION C *****

- - - - END OF EXAMINATION *****

Section A L Theory, Thermo, and Facility Characteristics Question A.1 [1.0 point]

Which statement properly describes a thermal neutron?

a. A neutron at an energy level greater than its surroundings.

b. A neutron born directly from fission.

c. A neutron in equilibrium with its surroundings.

d. A neutron born due to decay of a fission product.

Question A.2 [1.0 point]

Reactor power is increasing on a 35-second period. Approximately how long will it take for power to double?

a. 17 seconds

b. 24 seconds

c. 51 seconds

d. 70 seconds Question A.3 [1.0 point]

The Reed College TRIGA Reactor is slightly UNDERMODERATED. Which ONE of the following statements correctly describes the reactor operating characteristic of UNDERMODERATED?

a. An increase in core water temperature will cause a positive reactivity response.

b. A decrease in core water temperature will cause a negative reactivity response.

c. A decrease in core water density will cause a negative reactivity response.

d. Reducing the amount of moderation will cause a positive reactivity reponse.

Section A L Theory, Thermo, and Facility Characteristics Question A.4 [1.0 point]

Which ONE of the following combinations of characteristics makes a good reflector?

Scattering Cross Section Absorption Cross Section

a. High Low

b. Low High

c. High High

d. Low Low Question A.5 [1.0 point]

Which ONE of the following is the time period in which the MAXIMUM amount of Xe-135 will be present in the core?

a. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after a startup to 100% power

b. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after a scram from 100% power

c. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after a power increase from 50% to 100%

d. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after a power decrease from 100% to 50%

Question A.6 [1.0 point]

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

a. Infinity because the control rods absorb all neutrons

b. Approximately -80 seconds, due to the rate of decay of the longest lived delayed neutron precursors

c. Approximately -80 seconds, due to the rate of decay of the shortest lived delayed neutron precursors

d. Approximately -10 seconds, due to the rate of decay of the shortest lived prompt neutrons

Section A L Theory, Thermo, and Facility Characteristics Question A.7 [1.0 point]

During a reactor startup, as Keff approaches criticality, the value of 1/M:

a. Decreases toward zero

b. Decreases toward one

c. Increases toward one

d. Increases towards infinity Question A.8 [1.0 point]

In a subcritical reactor, Keff is increased from 0.918 to 0.965. Which one of the following is the amount of reactivity that was added to the core?

a. 3.63 %k/k

b. 5.31 %k/k

c. 7.28 %k/k

d. 8.93 %k/k

Section A L Theory, Thermo, and Facility Characteristics Question A.9 [1.0 point]

Which ONE of the following statements best describes how an INCREASE in moderator temperature affects the core operating characteristics?

a. Will DECREASE the neutron multiplication factor due to the resonance escape probability DECREASE

b. Will INCREASE the neutron multiplication factor due to the resonance escape probability INCREASE

c. Will INCREASE the neutron multiplication factor due to the reproduction factor DECREASE

d. Will DECREASE the neutron multiplication factor due to the reproduction factor INCREASE Question A.10 [1.0 point]

Which ONE of the following best describes beta decay (-1) of a nucleus?

a. Atomic mass number increases by 1, and the number of protons increases by 1

b. Atomic mass number increases by 1, and the number of protons decreases by 1

c. Atomic mass number remains unchanged, and the number of protons increases by 1

d. Atomic mass number remains unchanged, and the number of protons decreases by 1 Question A.11 [1.0 point]

Assume that the worths of the Safety, Shim, and Reg rods are $4.50, $3.75, and $2.00, respectively. The reactor is critical at 15 W after WITHDRAWING the following control rod worths: Safety $3.50, Shim $2.00, and Reg $1.50. What is the CORE EXCESS?

a. $2.75

b. $3.25

c. $6.50

d. $7.00

Section A L Theory, Thermo, and Facility Characteristics Question A.12 [1.0 point]

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

a. Reactor power

b. Rod speed

c. Fuel temperature

d. Flux shape Question A.13 [1.0 point]

What has the greatest affect on the THERMAL UTILIZATION FACTOR in the six factor formula?

a. Xenon buildup

b. Moderator temperature

c. Control rods

d. Fuel density Question A.14 [1.0 point]

Element X has a cross section of 85 barns for 0.030 keV neutrons. If it is a 1/v absorber, what is the cross section for 0.75 keV neutrons?

a. 57 barns

b. 28 barns

c. 21 barns

d. 17 barns

Section A L Theory, Thermo, and Facility Characteristics Question A.15 [1.0 point]

In a just critical reactor, the MOST LIKELY result of ADDING $1.00 of reactivity will cause:

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

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

c. A sudden increase in delayed neutrons

d. A sudden drop in neutron flux Question A.16 [1.0 point]

ELASTIC SCATTERING is the process by which a neutron collides with a ground state nucleus and:

a. is absorbed, with the nucleus emitting a gamma ray and a neutron with a lower kinetic energy

b. recoils with a higher kinetic energy than it had prior to the collision with the nucleus emitting a gamma ray

c. is absorbed, with the nucleus emitting a gamma ray

d. recoils with the same kinetic energy it had prior to the collision Question A.17 [1.0 point]

During a reactor startup, criticality occurred at a LOWER ROD HEIGHT than the last startup.

Which ONE of the following reasons could be the cause?

a. Moving an experiment with negative reactivity from the core

b. Fuel temperature increased

c. Pool temperature is increased

d. Xe135 increased

Section A L Theory, Thermo, and Facility Characteristics Question A.18 [1.0 point]

In a reactor with Keff = 0.7, the source contributes 1500 neutrons in the first generation.

Changing from the first generation to the third generation, the number of TOTAL neutrons in the THIRD generation is:

a. 2550

b. 3285

c. 4335

d. 4500 Question A.19 [1.0 point]

The scram setpoint of a reactor is 1100 kW and the scram delay time is 0.05 seconds. If the injection of a sample results in a 100 millisecond period, which ONE of the following is the peak power of the reactor at SHUTDOWN?

a. 1105 Kw

b. 1156 kW

c. 1813 kW

d. 1856 kW Question A.20 [1.0 point]

Which ONE of the following describes how delayed neutrons are produced?

a. Directly from fission

b. Decay of fission fragments

c. Decay of O-16

d. Photoelectric effect

- - - - END OF SECTION A *****

Section B Normal, Emergency and Radiological Control Procedures Question B.1 [1.0 point, 0.33 each]

Match the appropriate item in column A with its definition in column B.

Rod Type Definition

a. Channel Calibration 1. Qualitative verification of acceptable performance by observation of channel behavior

b. Channel Check 2. An adjustment of the channel such that its output corresponds with acceptable accuracy to known values of the parameter that the channel measures

c. Channel Test 3. The introduction of a signal into the channel for verification that it is operable Question B.2 [1.0 point]

What is the regulatory limit on the total effective dose equivalent for a radiation worker in one year?

a. 50 mRem

b. 500mRem

c. 5 Rem

d. 50 Rem Question B.3 [1.0 point]

Which ONE of the following events would be classified as a Non-Reactor Safety Related Event?

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

b. Abnormal increase in pool water level

c. Significant facility or individual contamination

d. A fire in the Psychology Building lasting more than 10 minutes

Section B Normal, Emergency and Radiological Control Procedures Question B.4 [1.0 point]

A survey instrument with a window probe is used to measure the beta-gamma dose rate from an irradiated experiment. The dose rate is 250 mrem/hour with the window opened and 80 mrem/hour with the window closed. The gamma dose rate is:

a. 330 mrem/hour

b. 250 mrem/hour

c. 170 mrem/hour

d. 80 mrem/hour Question B.5 [1.0 point]

According to SOP 10, Irradiation Preparation, which material does NOT need special approval before irradiation?

a. Materials with atomic numbers less than 83

b. Material containing more than 1 mg of uranium or thorium per sample container

c. Organic solvents

d. Samples containing elemental mercury Question B.6 [1.0 point]

Which one of the following actions by the facility director requires the NRC APPROVAL for changes?

a. Revising the Reed Research Reactor Standard Operating Procedure 1, Reactor Operation

b. Revising the requalification written examination

c. Revising the Reed Research Reactor Standard Operating Procedure 2, Scram or Dropped Rod

d. Reducing the Technical Specifications minimum number of Reactor Operations Committee members from three to two

Section B Normal, Emergency and Radiological Control Procedures Question B.7 [1.0 point]

A radioactive material decays at a rate of 20% per day. Determine its half life.

a. 1 day

b. 2 days

c. 3 days

d. 4 days Question B.8 [1.0 point]

Algaecide is added weekly to the secondary cooling loop. Why is this?

a. Minimizes corrosion of the pipes

b. Increases the thermal conductivity of the water

c. Suppresses biological growth in the cooling tower

d. Prevents the water from freezing in cold temperatures Question B.9 [1.0 point]

Based on the Reed Requalification Plan, each operator must perform the functions of a licensed operator to maintain an active operators license a minimum of:

a. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per quarter.

b. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per quarter.

c. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per month.

d. 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months per year.

Section B Normal, Emergency and Radiological Control Procedures Question B.10 [1.0 point]

You are performing the weekly survey and come across a sign that says, Caution - Radiation Area. What is the minimum radiation level that would be detected in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at 30cm from the radiation source?

a. 0.0005 Rem

b. 0.005 Rem

c. 0.05 Rem

d. 0.100 Rem Question B.11 [1.0 point]

For emergency actions, the EMERGENCY SUPPORT CENTER is located in the:

a. Psychology Building

b. Chemistry Building Room 102

c. Reactor classroom

d. Reactor Breakroom

Section B Normal, Emergency and Radiological Control Procedures Question B.12 [1.0 point]

While performing RRR SOP 1, Reactor Operation, and the reactor is in manual mode, what is the initial position at which the control rods should be withdrawn and what is the ideal period when you are approaching your desired power level?

a. 15%; +10 to +20 seconds

b. 10%; +30 seconds

c. 10%; +10 to +20 seconds

d. 15%; +30 seconds Question B.13 [1.0 point]

The reactor shall not be operated unless the minimum number of radiation monitoring channels are operable. This is an example of a:

a. Safety Limit

b. Limiting Safety System Setting

c. Limiting Condition for Operation

d. Surveillance Requirement Question B.14 [1.0 point]

The MINIMUM staffing requirement when a RO is performing the INITIAL reactor startup is:

a. RO with SRO present in the facility

b. RO with SRO on call within 5 minutes of the facility and a second person in the building

c. RO with SRO on call within 5 minutes of the facility

d. RO with second person in the building

Section B Normal, Emergency and Radiological Control Procedures Question B.15 [1.0 point]

What is the HALF LIFE of the isotope contained in a sample which produces the following count rates?

Time (Minutes) Counts per Minute (cpm)

Initial 950 60 702 120 518 180 383 240 283

a. 124 minutes

b. 137 minutes

c. 201 minutes

d. 558 minutes Question B.16 [1.0 point]

Which ONE of the following is TRUE regarding crane operation while the Reed Reactor is operating?

a. The crane trolley may not be moved over the reactor.

b. The crane bridge may not be moved over the reactor.

c. Permission to operate the crane must be obtained from the RO on duty.

d. Permission to operate the crane must be obtained from the SRO on duty.

Section B Normal, Emergency and Radiological Control Procedures Question B.17 [1.0 point]

What type of radiation detector is PREDOMINATELY used for surveying contaminated areas?

a. Proportional counter

b. Geiger-Mueller tube

c. Ionization chamber

d. Scintillation detector Question B.18 [1.0 point]

Which ONE of the following is an example of a LIMITING SAFETY SYSTEM SETTING?

a. Reactor power shall be equal to or less than 300 kW as measured by a power measuring channel

b. Reactor pool water conductivity and pH shall be measured monthly

c. The reactor shall not be operated unless the shutdown margin provided by control rods is greater than $0.50

d. The maximum fuel temperature shall not exceed 1000 °C Question B.19 [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 LSSS is a limit on important process variables that assures the integrity of the fuel cladding. The SL initiates protective action to preclude reaching the LSSS.

b. The SL is a limit on important process variables that assures the integrity of the fuel cladding. The LSSS initiates protective actions to preclude reaching the SL.

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

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

Section B Normal, Emergency and Radiological Control Procedures Question B.20 [1.0 point, 0.25 each]

Match the type of radiation (Column A) with the proper penetrating power (Column B). Each item may be used only once.

Column A Column B

a. Neutron 1. Stopped by a thin sheet of metal

b. Gamma 2. Stopped by a thin sheet of paper

c. Alpha 3. Best shielded by heavy (high-z) material

d. Beta 4. Best shielded by light (low-z) material

- - - - END OF SECTION B *****

Section A L Theory, Thermo, and Facility Characteristics Question C.1 [1.0 point]

The majority of the facilitys Ar-41 is produced in the:

a. Rotary specimen rack

b. Reactor bay

c. Pneumatic transfer tube

d. Reactor lab Question C.2 [1.0 Point]

At Reed College reactor, the output of the fission chamber provides the signal to:

a. Linear Amplifier

b. Rod Control Servo

c. Log-n Amplifier

d. Percent Power Amplifier Question C.3 [1.0 point]

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

a. Siphon breaks (holes) located in the pump suction piping

b. Closure of an automatic valve sensitive to pool level

c. Level in pool drops below the minimum required to supply suction pressure to the pump

d. Level in pool drops below the bottom of the suction piping

Section A L Theory, Thermo, and Facility Characteristics Question C.4 [1.0 point]

The upper end fixture of each fuel element consists of a:

a. knob for attaching the fuel handling tool and a rectangular spacer to prevent the fuel handling tool from damaging the fuel cladding

b. knob for attaching the fuel handling tool and a triangular spacer to allow cooling water to flow through the upper grid plate

c. a rectangular spacer to allow the top grid to provide lateral support and a triangular opening to allow sampling for fuel element failure

d. a triangular spacer to allow the top grid to provide lateral support and a rectangular opening to allow sampling for fuel element failure Question C.5 [1.0 point]

If the stack sampling pump fails, the ________ will be inoperable.

a. Continuous Air Monitor (CAM) and Air Particulate Monitor (APM)

b. Continuous Air Monitor (CAM) and Radiation Area Monitor (RAM)

c. Air Particulate Monitor (APM) and Gaseous Stack Monitor (GSM)

d. Radiation Area Monitor (RAM) and Gaseous Stack Monitor (GSM)

Section A L Theory, Thermo, and Facility Characteristics Question C.6 [1.0 point]

What is the purpose of the orifice in the PRIMARY COOLING SYSTEM?

a. To prevent excessive coolant flow back into the core

b. To restrict coolant flow to 20 gpm through the demineralizers

c. To prevent excessive backpressure on the heat exchanger

d. To restrict coolant flow to 100 gpm bypassing the deminerlizers Question C.7 deleted following the administration of the examination per facility comments.

Question C.7 [1.0 point]

If the airborne particulate radioactivity exceeds the CAM setpoint, which ONE of the following is the correct ventilation system response?

a. The exhaust dampers open and the supply dampers close

b. The exhaust dampers close and the supply dampers open

c. The exhaust and supply dampers close

d. The exhaust and supply dampers open Question C.8 [1.0 point]

Which ONE of the following conditions will cause the operating reactor to automatically SCRAM per the Technical Specification requirements?

a. Reactor period = 6 seconds

b. Loss of high voltage to the percent power channel

c. 105% reactor power

d. Bulk pool water temperature = 40 °C

Section A L Theory, Thermo, and Facility Characteristics Question C.9 [1.0 point]

The technical specifications limit the pool conductivity. The best conductivity probe location to measure this limit is at the:

a. outlet of the purification system filter

b. outlet of the coolant system heat exchanger

c. discharge of the purification system pump

d. inlet of the purification system filter Question C.10 [1.0 point]

Which ONE of the following statements correctly describes the purpose of the PULL ROD in the control rod drive assembly?

a. Provides rod bottom indication

b. Provides rod full out position indication

c. Provides a means for manually adjusting rod position by pulling out

d. Automatically engages the control rod on a pull signal Question C.11 [1.0 point, 0.25 each]

Match the each of area listed in column A with the correct heat transport mechanism listed in column B. Items in column B may be used once, more than once, or not at all.

Column A Column B

a. Within the fuel 1. Radiation

b. Within the clad 2. Conduction

c. From the clad to the pool 3. Natural Convection

d. From the pool to the heat exchanger 4. Forced Convection

Section A L Theory, Thermo, and Facility Characteristics Question C.12 [1.0 point]

Per the Reed Technical Specifications, the pH averaged over one month shall be between

______, and the conductivity averaged over a month shall not exceed ______ microsiemens/cm in the Reed TRIGA pool water.

a. 4 - 6.5 ; 4 microsiemens/cm

b. 5 - 7.5; 5 microsiemens/cm

c. 5.5 - 8; 5 microsiemens/cm

d. 5 - 7.5; 4 microsiemens/cm Question C.13 [1.0 point, 0.25 each]

Given the configuration of the lights associated with the safety rod listed in column A below, match it with the appropriate condition of the safety rod and its motor in Column C.

Column A Column B Red (UP) White (Down) Blue (CONT)

a. OFF ON ON 1. Rod dropping

b. ON OFF OFF 2. Raising rod

c. ON OFF ON 3. Rod hits bottom

d. OFF OFF ON 4. SCRAM is reset Question C.14 [1.0 point]

Which ONE of the following experimental facilities is BEST used for applications with extremely short-lived radioisotopes?

a. Central thimble

b. Rotary specimen rack

c. Pneumatic specimen tube

d. Beam port

Section A L Theory, Thermo, and Facility Characteristics Question C.15 [1.0 point]

Which ONE of the following best describes the design of fuel element used at Reed reactor?

a. The fuel contains more than 8.5% weight of uranium enriched to less than 20% U 235.

b. The fuel contains more than 20% weight of uranium enriched to less than 8.5% U 235.

c. The fuel contains less than 8.5% weight of uranium enriched to less than 20% U 235.

d. The fuel contains less than 20% weight of uranium enriched to more than 8.5% U 235.

Question C.16 [1.0 point]

As stated in TS 5.5, all fuel elements shall be stored in a geometrical array where the effective multiplication is less than _____ for all conditions of moderation.

a. 0.7

b. 0.75

c. 0.8

d. 0.9 Question C.17 [1.0 point]

Which ONE of the following statements describes the moderating properties of zirconium-hydride in the Reed TRIGA fuel elements?

a. The ratio of hydrogen atoms to zirconium atoms affects the moderating effectiveness for slow neutrons

b. The probability that a neutron will return to the fuel element before being captured elsewhere is a function of the temperature of the hydride

c. The hydride mixture is very effective in slowing down neutrons with energies below 0.025 eV

d. Elevation of the hydride temperature increases the probability that a thermal neutron will escape the fuel-moderator element before being captured

Section A L Theory, Thermo, and Facility Characteristics Question C.18 [1.0 point]

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. 12345

b. 21543

c. 23154

d. 42315 Question C.19 [1.0 point]

Which ONE of the following events can be performed WITHOUT the presence of an SRO?

a. Relocation of ANY incore experiment

b. Fuel relocations in the core

c. $0.20 reactivity addition

d. Initial startup and approach to power Question C.20 deleted following the administration of the examination per facility comments.

Question C.20 [1.0 point]

The Reed College Facility License grants permission for possession of 2 specific sources.

Which one of the following describes these sources?

a. A 2 mg Ra-226 and a 1 curie americium-beryllium source

b. A 1.64 curie americium-beryllium and a 1 curie plutonium-beryllium source

c. A 2 mg Ra-226 and a 1.64 curie plutonium-beryllium source

d. A 1 curie americium-beryllium and a 1.64 curie plutonium-beryllium source.

- - - - END OF EXAMINATION *****

- - - - END OF SECTION C *****

- - - - END OF EXAM*****

Section A L Theory, Thermo, and Facility Characteristics Section A L Theory, Thermo, and Facility Characteristics Answer Key A.1 Answer: c

Reference:

P = Poet/T, time = ln(2)*35 = ~24 seconds A.3 Answer: c

Reference:

= (Keff1-Keff2)/(Keff1*Keff2) = (0.965-0.918)/((0.965*0.918) = 0.0531k/k = 5.31%k/k

Section A L Theory, Thermo, and Facility Characteristics A.9 Answer: a

Reference:

Chart of Nuclides A.11 Answer: b

Reference:

Total Worth = $4.50 + $3.75 + $2.00 = $10.25 Reactivity at 15W = $3.50 + $2.00 + $1.50 = $7.00 Core Excess = Total Worth - Reactivity at 15W = $10.25 - $7.00 = $3.25 A.12 Answer: d

Reference:

Reed Training Manual: Cross section is inversely proportional to the velocity of neutrons. Energy is proportional to v2, so the 0.75 keV neutrons are 5 times as fast as the 0.030 keV neutrons. Therefore, their cross section is 1/5 as large. 85/5 = 17 A.15 Answer: a

Reference:

1500) = 2550 3rd Gen = n + K*n = 1500 + (0.7

2550) = 3285

Section A L Theory, Thermo, and Facility Characteristics A.19 Answer: c

Reference:

P = P0et/T = 1100kW

e(0.05/0.1) = 1813 kW A.20 Answer: b

Reference:

Section B Normal, Emergency and Radiological Control Procedures Answer Key B.1 Answer: a=2, b=1, c=3

Reference:

TS Chapter 1, Definitions B.2 Answer: c

Reference:

10 CFR 20.1003 B.3 Answer: c

Reference:

E-Plan Sections 4.1, 4.2 B.4 Answer: d

Reference:

Basic radiation instrumentation B.5 Answer: a

Reference:

Standard Operating Procedure 10, Irradiation Preparation, Section 10.4.3 B.6 Answer: d

Reference:

TS 6.2.1 B.7 Answer: c

Reference:

DR = DRo x e-t 20% decayed means 80% left 65 = 100 x e-()(1 day) ln(65/100) = - x (1day)

= 0.223 t1/2 = ln(2)/ = 0.223/0.431 = 3.10 days B.8 Answer: c

Reference:

Reed Reactor Training Manual B.9 Answer: a

Reference:

10 CFR 55 B.10 Answer: b

Reference:

10 CFR 20.1003 B.11 Answer: b

Reference:

Reed E-Plan Section 8.1

Section B Normal, Emergency and Radiological Control Procedures B.12 Answer: c

Reference:

RRR SOP 1, Sections 1.9.1 and 1.9.2 B.13 Answer: c

Reference:

TS Section 3.5.1 B.14 Answer: a

Reference:

RRR SOP 1, Section 1.3, TS 6.1.3 B.15 Answer: b

Reference:

, , , = 0.00505 B.16 Answer: a

Reference:

Reed Research Reactor SOP 38, Section 38.4 B.17 Answer: b

Reference:

Reed Reactor Training Manual B.18 Answer: a

Reference:

TS Section 2.2 B.19 Answer: b

Reference:

TS Section 1 B.20 Answer: a=4 , b=3, c=2 , d=1

Reference:

Section C Plant and Radiation Monitoring Systems Answer Key C.1 Answer: a

Reference:

SAR Section 7.5 C.2 Answer: c

Reference:

RRR Facility Training Manual, Figure 11.12 C.3 Answer: a

Reference:

TRIGA MK I Reactor Mechanical Maintenance & Operating Manual, 5.11.10, p. 85 C.4 Answer: b

Reference:

SAR Section 5.2.2 C.5 Answer: c

Reference:

RRR Training Manual, Section 5.2 C.6 Answer: d

Reference:

RRR Training Manual, Section 11.6 Question C.7 deleted following the administration of the examination per facility comment.

C.7 Answer: c

Reference:

SAR Section 4.4 C.8 Answer: b

Reference:

TS Section 3.2.3 C.9 Answer: a

Reference:

SAR Section 5.2.6 C.10 Answer: a

Reference:

RRR Training Manual, Figure 11.6 C.11 Answer: a=2, b=2, c=3, d=4

Reference:

RRR Training Manual, Section 10.7 C.12 Answer: b

Reference:

TS Section 3.3

Section C Plant and Radiation Monitoring Systems C.13 Answer: a = 4, b = 3, c = 1, d = 2

Reference:

RRR Training Manual, Section 11.3 C.14 Answer: c

Reference:

SAR Section 5.2.5 C.15 Answer: c

Reference:

SAR Section 5.2.2 C.16 Answer: c

Reference:

TS 5.5 C.17 Answer: d

Reference:

SAR Appendix E C.18 Answer: b

Reference:

Reed Training Manual C.19 Answer: a

Reference:

TS 6.1.3 Question C.20 deleted following the administration of the examination per facility comment.

C.20 Answer: b

Reference:

Reed Facility License

- - - - END OF THE EXAM ********************************

ML13155A489

Text

SUBJECT:

Dear Dr. Krahenbuhl:

Enclosures:

SUBJECT:

Dear Dr. Krahenbuhl:

Enclosures:

SUMMARY

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