ML032410295

Retake Examination Report No. 50-186/OL-03-01R, University of Missouri-Columbia

ML032410295
Person / Time
Site:	University of Missouri-Columbia
Issue date:	10/03/2003
From:	Madden P NRC/NRR/DRIP/RORP
To:	Rhonda Butler Univ of Missouri - Columbia
Doyle P, NRC/NRR/DRIP/RNRP, 415-1058
Shared Package
ML032410275	List: ML032410295 ML032410319
References
50-186/03-01R 50-186/03-01R
Download: ML032410295 (21)

Text

October 3, 2003 Mr. Ralph A. Butler, Chief Operating Officer Research Reactor Facility University of Missouri Columbia, MO 65211

SUBJECT:

RETAKE EXAMINATION REPORT NO. 50-186/OL-03-01R, UNIVERSITY OF MISSOURI-COLUMBIA

Dear Mr. Butler:

During the week of June 30, 2003, your staff administered an NRC prepared operator licensing examination at your University of Missouri - Columbia Reactor. The examination was conducted according to NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1.

In accordance with 10 CFR 2.790 of the Commission's regulations, 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 document system (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/NRC/ADAMS/indesx.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 Paul Doyle at (301) 415-1058 or via internet E-mail at pvd@nrc.gov.

Sincerely,

/RA/

Patrick M. Madden, Section Chief Research and Test Reactors Section New, Research and Test Reactors Program (RNRP)

Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-186

Enclosures:

1. Initial Examination Report No. 50-186/OL-03-01R

2. Examination and answer key (RO/SRO) cc w/encls: Please see next page

October 3, 2003 Mr. Ralph A. Butler, Chief Operating Officer Research Reactor Facility University of Missouri Columbia, MO 65211

SUBJECT:

RETAKE EXAMINATION REPORT NO. 50-186/OL-03-01R, UNIVERSITY OF MISSOURI-COLUMBIA

Dear Mr. Butler:

During the week of June 30, 2003, your staff administered an NRC prepared operator licensing examination at your University of Missouri-Columbia Reactor. The examination was conducted according to NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards,"

Revision 1.

In accordance with 10 CFR 2.790 of the Commissions regulations, 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 NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/NRC/ADAMS/indesx.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 Paul Doyle at (301) 415-1058 or via internet E-mail at pvd@nrc.gov.

Sincerely,

/RA/

Patrick M. Madden, Section Chief Research and Test Reactors Section New, Research and Test Reactors Program (RNRP)

Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-186

Enclosures:

1. Initial Examination Report No. 50-186/OL-03-01R

2. Examination and answer key (RO/SRO) cc w/encls: Please see next page DISTRIBUTION w/ encls.:

PUBLIC RNRP\R&TR r/f PMadden AAdams Facility File (EBarnhill) O6-D17 ADAMS PACKAGE ACCESSION NO.: ML032410275 TEMPLATE #:NRR-074 ADAMS REPORT ACCESSION NO.: ML032410295 OFFICE RNRP:CE IROB:LA E RNRP:SC NAME PDoyle:rdr EBarnhill PMadden DATE 09/ 27 /2003 09/ 26 /2003 09/ 29 /2003 C = COVER E = COVER & ENCLOSURE N = NO COPY

OFFICIAL RECORD COPY University of Missouri-Columbia Docket No. 50-186 cc:

University of Missouri Associate Director Research Reactor Facility Columbia, MO 65201 A-95 Coordinator Division of Planning Office of Administration P.O. Box 809, State Capitol Building Jefferson City, MO 65101 Mr. Ron Kucera, Director Intergovernmental Cooperation and Special Projects Missouri Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102 Mr. Tim Daniel Homeland Security Suite 760 P.O. Box 809 Jefferson City, MO 65102

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-186/OL-03-01R FACILITY DOCKET NO.: 50-186 FACILITY LICENSE NO.: R-103 FACILITY: University of Missouri-Columbia EXAMINATION DATES: July 3, 2003 SUBMITTED BY: _________/RA/__________________ 07/08/2003 Paul Doyle, Chief Examiner Date

SUMMARY

On July 3, 2003, the facility administered an NRC prepared written examination (Section A only) to one Reactor Operator Retake candidate. The candidate passed the examination.

REPORT DETAILS

1. Examiners:

Paul Doyle, Chief Examiner

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 ENCLOSURE 1

UNIVERSITY OF MISSOURI-COLUMBIA With Answer Key OPERATOR LICENSING EXAMINATION Week of June 30, 2003 Enclosure 2

Section A / Theory, Thermo & Fac. Operating Characteristics Page 2 QUESTION A.1 [1.0 point]

The reactor is at a power of 1 watt, with a 26 second stable period. How long will it take for power to reach 1000 watts?

a. .180 seconds

b. .153 seconds

c. .121 seconds

d. .78 seconds QUESTION A.2 [1.0 point]

With the reactor on a constant period, which of the following changes in reactor power would take the LONGEST time?

a. 5% from 1% to 6%

b. 15% from 20% to 35%

c. 20% from 40% to 60%

d. 25% from 75% to 100%

QUESTION A.3 [1.0 point]

If the primary flow rate is 3700 gpm and the T across the primary side of the heat exchanger is 15.5EF, what is the power being transferred to the secondary side of the heat exchanger? (Assume no losses to the ambient surroundings, including the pool).

a. 12 megawatts.

b. 10 megawatts.

c. 8 megawatts.

d. 6 megawatts.

QUESTION A.4 [1.0 point]

An experimenter makes an error loading a rabbit sample. Sample injection results in a 100 millisecond period.

If the scram set point is 12.5 MW and the scram delay time is 0.1 seconds, WHICH ONE of the following is the peak power of the reactor at shutdown. (Assume Rabbit system is operational for this question.)

a. 12.5 MW

b. 25 MW

c. 34 MW

d. 125 MW

Section A / Theory, Thermo & Fac. Operating Characteristics Page 3 QUESTION A.5 [1.0 point]

The reactor had been running for 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> straight at 10 megawatts when it was shutdown for maintenance.

The maintenance took six hours, and you have just restarted the reactor and raised power to 10 megawatts and placed the reactor in auto control. Which ONE of the following is the expected response of the regulating rod for the next half hour? (Assume no fuel replacement during shutdown.)

a. Drive in

b. Drive out

c. Not move

d. Drive out then back in QUESTION A.6 [1.0 point]

You perform two startups with exactly the same conditions (temperature, xenon, samarium, rod speed, etc.).

For the first startup you proceed directly to criticality. For the second startup, you stop after pulling the rods in gang to 10 inches, to speak on the phone for 10 minutes. Which ONE of the following best describes the rod height and power at criticality for the second startup relative to the first startup?

a. Rod height will be lower, Power will be the same.

b. Rod height will be higher, Power will be the same.

c. Rod height will be the same, Power will be higher.

d. Rod height will be the same, Power will be the same.

QUESTION A.7 [1.0 point]

You enter the control room and note that all nuclear instrumentation show a steady neutron level, and no rods are in motion. Which ONE of the following conditions CANNOT be true?

a. The reactor is critical.

b. The reactor is subcritical.

c. The reactor is supercritical.

d. The neutron source has been removed from the core.

QUESTION A.8 [1.0 point]

The number of neutrons passing through a one square centimeter of target material per second is the definition of which one of the following?

a. Neutron Population (np)

b. Neutron Impact Potential (nip)

c. Neutron Flux (nv)

d. Neutron Density (nd)

Section A / Theory, Thermo & Fac. Operating Characteristics Page 4 QUESTION A.9 [1.0 point]

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

QUESTION A.10 [1.0 point]

Which ONE of the following statements concerning reactor poisons is NOT true?

a. Following shutdown, Samarium concentration will increase to some value then stabilize.

b. Following shutdown, Xenon concentration will initially increase to some value then decrease exponentially

c. During reactor operation, Samarium concentration is independent of reactor power level.

d. During reactor operation, Xenon concentration is dependent on reactor power level.

QUESTION A.11 [1.0 point]

Which of the following statements describes the concentration of Xenon in the core after a scram from extended operation at 10 MW? Xenon concentration

a. initially decreases due to the loss of Iodine production then increases to maximum concentration

b. decreases to a Xenon free condition in approximately ten (10) hours

c. increases to maximum in approximately ten (10) hours due to the reduction in Xenon burnup

d. remains at equilibrium value since power level has no effect on Xenon concentration QUESTION A.12 [1.0 point]

Reactivity is

a. a measure of the cores deviation from criticality.

b. a measure of the cores fuel depletion.

c. negative when Keff is greater than 1.0.

d. equal to 5% K/K when the reactor is prompt critical.

Section A / Theory, Thermo & Fac. Operating Characteristics Page 5 QUESTION A.13 [1.0 point]

Which ONE of the following conditions will INCREASE the shutdown margin of a reactor.

a. Insertion of a positive reactivity worth experiment

b. Lowering moderator temperature (Assume negative temperature coefficient).

c. Burnout of a burnable poison.

d. Fuel depletion.

QUESTION A.14 [1.0 point]

The effective neutron multiplication factor, Keff is defined as

a. absorption/(production + leakage)

b. (production + leakage)/absorption

c. (absorption + leakage)/production

d. production/(absorption + leakage)

QUESTION A.15 [1.0 point]

Shown below is a trace of reactor period as a function of time. Between points A and B reactor power is:

a. continually increasing.

b. continually decreasing.

c. increasing, then decreasing.

d. constant.

Section A / Theory, Thermo & Fac. Operating Characteristics Page 6 QUESTION A.16 [1.0 point]

Which ONE of the following factors is the most significant in determining the differential worth of a control rod?

a. The rod speed.

b. Reactor power.

c. The flux shape.

d. The amount of fuel in the core.

QUESTION A.17 [1.0 point]

A reactor is slightly supercritical with the following values for each of the factors in the six-factor formula Fast Fission Factor ( ) = 1.03 Fast Non-Leakage probability (üf) = 0.84 Resonance Escape probability (p) = 0.96 Thermal Non-Leakage probability (üth) = 0.88 Thermal Utilization Factor (f) = 0.70 Reproduction Factor ( ) = 1.96 A control rod is inserted to bring the reactor back to critical. Assuming all other factors remain unchanged, the new value for the thermal utilization factor (f) is

a. 0.698

b. 0.702

c. 0.704

d. 0.708 QUESTION A.18 [1.0 point]

Using the Integral Rod Worth Curve provided identify which ONE of the following represents Kexcess?

a. Area under curve B.

b. C

c. max - C

d. Areas under curve A & B QUESTION A.19 [1.0 point]

Which ONE of the following is the correct definition of effective ? The number of delayed neutrons compared to the total number of neutrons per generation

a. corrected for resonance escape.

b. corrected for leakage.

c. corrected for time after the fission event.

d. corrected for both leakage and resonance escape.

Section A / Theory, Thermo & Fac. Operating Characteristics Page 7 QUESTION A.20 [1.0 point]

To make a just critical reactor PROMPT CRITICAL, by definition you must add reactivity equal to

a. eff

b. eff

c. eff

d. Keff

Section A / Theory, Thermo & Fac. Operating Characteristics Page 8 A.1 a, P = P0 et/T ln(1000/1) = t/26sec 26sec x 6.9078 = 179.6 . 180 REF: Primary Reference, Volume 2, Module 4, Reactor Theory (Reactor Operations), Enabling Objective 2.1.

A.2 a REF: Primary Reference, Volume 2, Module 4, Reactor Theory (Reactor Operations), Enabling Objective 2.1.

A.3 c Q ' mcP T gallons lbm minutes BTU 1Mw&Hr.

Q0 ' 3700 x8 x 60 x1 x 15.5EF x E & 6 REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory.

A.4 c, P = P0 et/ , P = 12.5 Mwatt x e0.1/0.1 = 12.5 x e = 33.979.

REF: Primary Reference, Volume 2, Module 4, Reactor Theory (Reactor Operations), Enabling Objective 2.6.

A.5 a REF: Primary Reference, Volume 2, Module 3, Reactor Theory (Nuclear Parameters), Enabling Objective 4.5.

A.6 c REF: Primary Reference, Volume 2, Module 4, Reactor Theory (Reactor Operations), Enabling Objective 1.1.

A.7 c REF: Primary Reference, Volume 2, Module 4, Reactor Theory (Reactor Operations), Enabling Objectives 1.1, and 3.3.

A.8 c REF: Primary Reference, Volume 1, Module 2, Reactor Theory (Nuclear Characteristics), Enabling Objective 2.1.b.

A.9 a REF: Primary Reference, Volume 1, Module 1, Atomic and Nuclear Physics, Enabling Objective 3.1 A.10 c REF: Primary Reference, Volume 2, Module 3, Reactor Theory (Nuclear Parameters), Enabling Objectives 4.1 through 4.15.

A.11 c REF: Primary Reference, Volume 2, Module 3, Reactor Theory (Nuclear Parameters), Enabling Objective 4.5.

A.12 a REF: Primary Reference, Volume 2x, Module 4, Reactor Theory (Nuclear Parameters), Enabling Objective 1.9.

A.13 d REF: Primary Reference, Volume 2, Module 4, Reactor Theory (Reactor Operations), Enabling Objective 3.6 A.14 d REF: Primary Reference, Volume 2, Module 4, Reactor Theory (Reactor Operations), Enabling Objective 1.1 A.15 a REF: Standard NRC Question A.16 c REF: Primary Reference, Volume 2, Module 4, Reactor Theory (Reactor Operations), Enabling Objective 5.4 A.17 a REF: Primary Reference, Volume 2, Module 3, Reactor Theory (Nuclear Parameters), Enabling Objective 1.2

Section A / Theory, Thermo & Fac. Operating Characteristics Page 9 A.18 c REF: Standard NRC Question covering Technical Specification Parameter.

A.19 d REF: Primary Reference, Volume 2, Module 4, Reactor Theory (Reactor Operations), Enabling Objective 2.2 A.20 c REF: Primary Reference, Volume 2, Module 4, Reactor Theory (Reactor Operations), Enabling Objective 2.8 Primary

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory.

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: University of Missouri-Columbia REACTOR TYPE: TANK DATE ADMINISTERED: Week of June 30, 2003 CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

Circle correct answers on the answer sheets provided. If you wish to change your answer, cross out the incorrect answer and write the correct answer on the line provided to the right. If you wish to change your answer again, cross out the incorrect answer and write the correct answer to the right of the last answer.

Points for each question are indicated in brackets for each question number. You must achieve a grade of 70% in each section is required to pass the examination. Examinations will be picked up three (1) hour after the examination starts.

% of Category % of Candidates Category Value Total Score Value Category 20.00 33.3 A. Reactor Theory, Thermodynamics and Facility Operating Characteristics 20.00  % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidates 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 one (1) hour 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



Q0 ' mc 0 p T ' m0 H ' UA T ( & )2 Pmax ' R( ' 1 x 10&4 seconds 2 (k)R eff ' 0.1 seconds &1 SCR '

S S R1(1&Keff ) ' CR2(1&Keff )

1 2

& 1&Keff CR1(& 1) ' CR2(& 2) eff 1&Keff 1 CR1 SUR ' 26.06 M ' 0 M ' '

& 1&Keff 1&Keff CR2 1

P ' P0 10SUR(t) t (1& )

P ' P0 e P ' P0 (1&Keff) R( R( -&

SDM ' ' '  %

Keff & - eff Keff & Keff 0.693 (Keff&1)

' 2 1 T1/2 ' '

keff xKeff Keff 1 2 6CiE(n) DR1d12 ' DR2d22 DR '

DR 'DR0 e & t R2 DR - Rem, Ci - curies, E - Mev, R - feet

( 2& ) 2 ( 1& ) 2 Peak2 Peak1 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 EF = 9/5 EC + 32 1 gal (H2O) . 8 lbm EC = 5/9 (EF - 32) cP = 1.0 BTU/hr/lbm/EF cp = 1 cal/sec/gm/EC

Section A / Theory, Thermo, and Facility Characteristics Page 13 A.1 a b c d ___ A.11 a b c d ___

A.2 a b c d ___ A.12 a b c d ___

A.3 a b c d ___ A.13 a b c d ___

A.4 a b c d ___ A.14 a b c d ___

A.5 a b c d ___ A.15 a b c d ___

A.6 a b c d ___ A.16 a b c d ___

A.7 a b c d ___ A.17 a b c d ___

A.8 a b c d ___ A.18 a b c d ___

A.9 a b c d ___ A.19 a b c d ___

A.10 a b c d ___ A.20 a b c d ___

Max Integral Rod Worth Curve C Critical Rod Height B

A 0

0 HC Rod fully out