ML083570104

Retake Examination Report No. 50-288/OL-09-01, Reed College Triga Reactor

ML083570104
Person / Time
Site:	Reed College
Issue date:	01/07/2009
From:	Johnny Eads Division of Policy and Rulemaking
To:	Frantz S Reed College
Doyle P, NRC/NRR/DPR/PRT, 415-1058
References
50-288/OL-09-01
Download: ML083570104 (14)

Text

January 7, 2009 Mr. Stephen G. Frantz, Director Reed Reactor Facility Reed College 3203 SE Woodstock Blvd.

Portland, OR 97202

SUBJECT:

RETAKE EXAMINATION REPORT NO. 50-288/OL-09-01, REED COLLEGE TRIGA REACTOR

Dear Mr. Frantz:

On December 12, 2008, you administered an NRC prepared operator licensing examination at your Reed College TRIGA reactor. The examination was prepared and proctored 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. Paul V. Doyle Jr. at (301) 415-1058 or via internet e-mail pvd@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. Retake Examination Report No. 50-288/OL-09-01

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

January 7, 2009 Mr. Stephen G. Frantz, Director Reed Reactor Facility Reed College 3203 SE Woodstock Blvd.

Portland, OR 97202

SUBJECT:

RETAKE EXAMINATION REPORT NO. 50-288/OL-09-01, REED COLLEGE TRIGA REACTOR

Dear Mr. Frantz:

On December 12, 2008, you administered an NRC prepared operator licensing examination at your Reed College TRIGA reactor. The examination was prepared and proctored 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. Paul V. Doyle Jr. at (301) 415-1058 or via internet e-mail pvd@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. Retake Examination Report No. 50-288/OL-09-01

2. Written examination with facility comments incorporated cc without enclosures: See next page DISTRIBUTION w/ encls.:

PUBLIC PRTB r/f RidsNRRDPRPRTA RidsNRRDPRPRTB Facility File (CRevelle) O-13 D-07 ADAMS ACCESSION #: ML083570104 TEMPLATE #:NRR-074 OFFICE PRTB:CE IOLB:LA E PRTB:SC NAME PDoyle pvd CRevelle car JEads jhe DATE 12/30/08 1/7/09 1/7/09 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 Ms. Vanessa E. Holfeltz, Associate 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 Reactor Facility EXAMINATION DATES: December 12, 2008 SUBMITTED BY: ________/RA/_______________ 12/31/2008 Paul V. Doyle Jr., Chief Examiner Date

SUMMARY

Mr. John Nguyen prepared Section A of a written examination for one candidate who had failed Section A of the NRC written examination administered in May 2008 at the Reed Reactor Facility. The candidate passed the examination.

REPORT DETAILS

1. Examiners:

Paul V. Doyle Jr., Chief Examiner, NRC John Nguyen, Examiner in Training, NRC

2. Results:

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

3. Exit Meeting:

Due to the nature of this examination there was no exit meeting.

ENCLOSURE 1

OPERATOR LICENSING RETAKE EXAMINATION With Answer Key REED COLLEGE DECEMBER 12, 2008 ENCLOSURE 2

Section A L Theory, Thermodynamics and Facility Operating Characteristics Page 6 QUESTION A.01 [2.0 points, 0.5 each]

Match each term in column A with the correct definition in column B.

Column A Column B

a. Prompt Neutron 1. a neutron in equilibrium with its surroundings.

b. Fast Neutron 2. a neutron born directly from fission.

c. Thermal Neutron 3. a neutron born due to decay of a fission product.

d. Delayed Neutron 4. a neutron at an energy level greater than its surroundings.

QUESTION A.02 [1.0 point]

Which one of the following combinations describes a reactor that is EXACTLY critical?

a. Keff = 0; k/k = 0

b. Keff = 0; k/k = 1

c. Keff = 1; k/k = 0

d. Keff = 1; k/k = 1 QUESTION A.03 [1.0 point]

Xenon-135 is produced in the reactor by two methods. One is directly from fission; the other is indirectly from the decay of:

a. Xenon-136

b. Samarium-136

c. Cesium-135

d. Iodine-135 QUESTION A.04 [1.0 point]

Which factor of the Six Factor formula is most affected when the REG rod material is changed from Boron to Samarium?

a. Thermal Utilization Factor (f)

b. Reproduction Factor ()

c. Fast Fission Factor ()

d. Fast Non-Leakage Factor (Lf)

Section A L Theory, Thermodynamics and Facility Operating Characteristics Page 7 QUESTION A.05 [1.0 point]

Which of the following does NOT affect the Effective Multiplication Factor (Keff)?

a. The moderator-to-fuel ratio.

b. The physical dimensions of the core.

c. The strength of installed neutron sources.

d. The current time in core life.

QUESTION A.06 [1.0 point]

The neutron interaction in the reactor core that is MOST efficient in thermalizing fast neutrons occurs with the:

a. Hydrogen atoms in the water molecules

b. Oxygen atoms in the water molecules

c. Boron atoms in the control rods

d. Xenon atoms in the fuel elements QUESTION A.07 [1.0 point]

Reactor power decreases on a stable negative period after a reactor scram, following an initial prompt drop. Which ONE (1) of the following is the reason for this?

a. This rate of power change is dependent on the MEAN lifetime of the longest lived delayed neutron precursor.

b. This rate of power change is dependent on the MEAN lifetime of the shortest lived delayed neutron precursor.

c. All prompt neutrons decay during the prompt drop, and the subsequent rate of power change is dependent ONLY on the half-life of the longest lived prompt gamma emitter.

d. This rate of power change is dependent on the CONSTANT decay rate of prompt neutrons following a scram.

QUESTION A.08 [1.0 point]

The total amount of reactivity added by withdrawing a control rod from a reference height to any other rod height is called?

a. differential rod worth

b. shutdown reactivity

c. integral rod worth

d. reference reactivity

Section A L Theory, Thermodynamics and Facility Operating Characteristics Page 8 QUESTION A.09 [1.0 point]

Keff for the reactor is 0.98. If you place an experiment worth +$1.00 ( = 0.0075) into the core, what will the new Keff be?

a. 0.982

b. 0.987

c. 1.013

d. 1.018 QUESTION A.10 [1.0 point]

About two minutes following a reactor scram, period has stabilized, and is decreasing at a CONSTANT rate. If

-5 reactor power is 10 % full power what will the power be in three minutes?

-6

a. 5 10 % full power

-6

b. 2 10 % full power

-6

c. 1 x 10 % full power

-7

d. 5 10 % full power QUESTION A.11 [1.0 point]

A reactor contains three safety blades and a regulating blade. Which one of the following would result in a determination of the excess reactivity of this reactor?

a. The reactor is critical at a low power level, with all safety blades full out and the regulating blade at some position. The reactivity remaining in the regulating blade (i.e. its worth from its present position to full out) is the excess reactivity.

b. The reactor is shutdown. Two safety blades are withdrawn until the reactor becomes critical. The total blade worth withdrawn is the excess reactivity.

c. The reactor is at full power. The total worth of all blades withdrawn is the excess reactivity.

d. The reactor is at full power. The total worth remaining in all the safety blades and the regulating blade (i.e. their worth from their present positions to full out) is the excess reactivity.

QUESTION A.12 [1.0 point]

INELASTIC SCATTERING is the process by which a neutron collides with a nucleus and

a. recoils with the same kinetic energy it had prior to the collision.

b. is temporarily absorbed, raising the nucleus to an excited state. The nucleus then emits a gamma ray and a neutron with a lower kinetic energy.

c. is permanently absorbed, raising the nucleus to an excited state. The nucleus then emits a gamma ray.

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

Section A L Theory, Thermodynamics and Facility Operating Characteristics Page 9 QUESTION A.13 [1.0 point]

For most materials the neutron microscopic cross-section for absorption a generally

a. increases as neutron energy increases

b. decreases as neutron energy increases

c. increases as target nucleus mass increases

d. decreases as target nucleus mass increases QUESTION A.14 [1.0 point]

Which one of the following is the correct reason that delayed neutrons enhance control of the reactor?

a. There are more delayed neutrons than prompt neutrons.

b. Delayed neutrons increase the average neutron generation time.

c. Delayed neutrons are born at higher energies than prompt neutrons and therefore have a greater effect.

d. Delayed neutrons take longer to reach thermal equilibrium.

QUESTION A.15 [1.0 point]

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.

QUESTION A.16 [1.0 point]

The term PROMPT JUMP refers to

a. the instantaneous change in power due to withdrawal of a control rod.

b. a reactor which has attained criticality on prompt neutrons alone.

c. a reactor which is critical on both prompt and delayed neutrons.

d. a negative reactivity insertion which is less than eff.

Section A L Theory, Thermodynamics and Facility Operating Characteristics Page 10 A.01 a, 2; b, 4; c, 1; d, 3 REF: Reference 1: volume 1, module 1, pg. 50, module 2, pg. 10 and module 2, pg. 29.

A.02 c REF: Reference 1: volume 2, module 3 pages 8 & 18.

A.03 d REF: Reference 1: volume 2, module 3 pg. 35 A.04 a REF: Reference 1: volume 1, module 2, pg. 5.

A.05 c REF: Reference 1: volume A.06 a REF: Reference 1: volume 1, module 2, pg. 27 A.07 a REF: Reference 1: volume 2, module 4, pg. 32 A.08 c REF: Reference 1: volume A.09 b REF: SDM = (1-keff)/keff = (1-0.98)/0.98 = 0.02041 or 0.02041/.0075 = $2.72. Adding +$1.00 new SDM = $2.72 -

$1.00 = $1.72, or .0129081 K/K Keff = 1/(1+SDM) = 1/(1 + 0.0129081) = 0.987 A.10 c

-T/ -5 (-180sec/80sec) -5 -2.25 -5 -6 REF: P = P0 e = 10 e = 10 e = 0.1054 10 = 1.054 10 A.11 a REF: Reference 1: volume 2, module 3, pg. 50 A.12 b REF: Reference 1: volume 1 module 1, pg. 45 A.13 b REF: Reference 1: volume 1, module 2, pg 9 A.14 b REF: Reference 1: volume 2, module 4, pg. 10 A.15 b REF: Reference 1: volume 1, module 1, pg. 6 A.16 a REF: Reference 1: volume 2, module 4, pg. 14 Reference 1: DOE Handbook Nuclear Physics and Reactor Theory

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: Reed Reactor Facility REACTOR TYPE: TRIGA DATE ADMINISTERED: 12/12/2008 CANDIDATE: _______________________

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheet provided. Points for each question are indicated in brackets for each question. A 70% is required to pass the examination. The Examination will be picked up one (1) hour after the examination starts.

Category  % of Candidates Candidates Value Total Score Grade (%) Category 17 100.0 _______ _______% L Theory, Thermodynamics and Facility Operating Characteristics TOTALS _______ _______%

Final Grade 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. 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.

13. When you have completed and turned in you examination, leave the examination area. If you are observed in this area while the examination is still in progress, your license may be denied or revoked.

EQUATION SHEET Q& = m& c P T = m& H =UAT Pmax =

( )2 eff = 0.1sec 1 (2 l )

t P = P0 e S S SCR = l* =1x10 4 sec 1 K eff SUR = 26 .06 eff + &

( ) (

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

(1 ) 1 CR P = P0 10SUR(t )

P= P0 M= = 2 1 K eff CR1 1 K eff1 1 K eff l*

M= SDM = =

1 K eff 2 K eff K eff 2 K eff1 0.693 l* = T1 =

= + K eff1 K eff 2 eff + &

2 K eff 1 DR = DR0 e t 2 DR1 d1 = DR2 d 2 2

=

K eff 6 Ci E (n )

( 2 )2 = (1 )2 DR = Peak2 Peak1 R2 DR - Rem, Ci - curies, E - Mev, R - feet 6

( 2.3x10 yr )

135 52Te (

19 sec) 135 ( 6.6 hr ) 135 ( 9.1 hr )

53 I 54 Xe 55 Cs 56 Ba 135 135 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lbm 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 1 BTU = 778 ft-lbf °F = 9/5 °C + 32 1 gal (H2O) 8 lbm °C = 5/9 (°F - 32) cP = 1.0 BTU/hr/lbm/°F cp = 1 cal/sec/gm/°C

Section A L Theory, Thermodynamics and Facility Operating Characteristics Page 14 A.01a 1 2 3 4 ___ A.08 a b c d ___

A.01b 1 2 3 4 ___ A.09 a b c d ___

A.01c 1 2 3 4 ___ A.10 a b c d ___

A.01d 1 2 3 4 ___ A.11 a b c d ___

A.02 a b c d ___ A.12 a b c d ___

A.03 a b c d ___ A.13 a b c d ___

A.04 a b c d ___ A.14 a b c d ___

A.05 a b c d ___ A.15 a b c d ___

A.06 a b c d ___ A.16 a b c d ___

A.07 a b c d ___