Text

Retake Examination Report No. 50-123/OL-05-01, University of Missouri-Rolla, February 14, 2005
	ML050950212
Person / Time
Site:	University of Missouri-Rolla
Issue date:	04/12/2005
From:	Madden P; NRC/NRR/DRIP/RNRP
To:	Crow M; Univ of Missouri - Rolla
	Doyle P, NRC/NRR/DRIP/RNRP, 415-1058
Shared Package
ML050950382	List: ML050950212; ML050950266;
References
	50-123/Ol-05-01, NUREG-1478 50-123/OL-05-01
	Download: ML050950212 (27)
	v • d • e

April 12, 2005 Dr. Mariesa Crow, Dean School of Materials, Energy and Earth Resources University of Missouri - Rolla 305 McNutt Hall Rolla, MO 65409-0810

SUBJECT:

RETAKE EXAMINATION REPORT NO. 50-123/OL-05-01, UNIVERSITY OF MISSOURI-ROLLA

Dear Dr. Crow:

During the week of February 14, 2005, the NRC administered operator licensing examinations at your University of Missouri-Rolla Reactor. The examinations were conducted according to NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1.

The last two initial examination reports for your facility (examinations administered in March 2003 and May 2004) listed concerns regarding the quality of your operator licensing program.

As a result, the NRC carefully reviewed this examination. The applications submitted for this retake examination had small problems, however, in general, they were substantially better than those received in support of the previous two initial examinations. The NRC is also encouraged to see that all candidates passed their respective retake written examinations, but we are still concerned that four of the five individuals scored just above passing. The NRC is pleased to note the overall improvements in your program, and looks forward to further improvements.

In accordance with 10 CFR 2.390 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/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 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 Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-123

Enclosures:

1. Initial Examination Report No. 50-123/OL-05-01

2. Examination with answer key (Section A Exam)

3. Examination with answer key (Section B Exam) cc w/encls: Please see next page

April 12, 2005 Dr. Mariesa Crow, Dean School of Materials, Energy and Earth Resources University of Missouri - Rolla 305 McNutt Hall Rolla, MO 65409-0810

SUBJECT:

RETAKE EXAMINATION REPORT NO. 50-123/OL-05-01, UNIVERSITY OF MISSOURI-ROLLA

Dear Dr. Crow:

During the week of February 14, 2005, the NRC administered operator licensing examinations at your University of Missouri-Rolla Reactor. The examinations were conducted according to NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1.

The last two initial examination reports for your facility (examinations administered in March 2003 and May 2004) listed concerns regarding the quality of your operator licensing program.

As a result, the NRC carefully reviewed this examination. The applications submitted for this retake examination had small problems, however, in general, they were substantially better than those received in support of the previous two initial examinations. The NRC is also encouraged to see that all candidates passed their respective retake written examinations, but we are still concerned that four of the five individuals scored just above passing. The NRC is pleased to note the overall improvements in your program, and looks forward to further improvements.

In accordance with 10 CFR 2.390 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/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 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 Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-123

Enclosures:

1. Initial Examination Report No. 50-123/OL-05-01

2. Examination with answer key (Section A Exam)

3. Examination with answer key (Section B Exam) cc w/encls: Please see next page DISTRIBUTION:

PUBLIC RNRP R&TR r/f PMadden Facility File (EBarnhill) O-6 F-2 PIsaac EXAMINATION PACKAGE ACCESSION NO.: ML050950382 EXAMINATION REPORT ACCESSION #: ML050950212 TEMPLATE #: NRR-074 OFFICE RNRP:CE IROB:LA E RNRP:SC NAME PDoyle EBarnhill PMadden DATE 4/ 6 /2005 4/ 6 /2005 4/ 11/2005 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY

University of Missouri - Rolla Docket No. 50-123 cc:

A-95 Coordinator Division of Planning Office of Administration P.O. Box 809 State Capitol Building Jefferson City, MO 65101 Dr. Mariesa Crow, Dean School of Mines and Metallurgy 305 McNutt Hall University of Missouri-Rolla Rolla, MO 65401 Dr. Akira T. Tokuhiro, Reactor Director University of Missouri-Rolla Department of Nuclear Engineering 226 Fulton Hall 1870 Miner Circle Rolla, MO 65409-0170 William E. Bonzer, Reactor Manager University of Missouri-Rolla Nuclear Reactor Facility 1870 Miner Circle Rolla, MO 65409-0630 Mr. Tim Daniel Homeland Security Suite 760 P.O. Box 809 Jefferson City, MO 65102 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.: 50-123/OL-05-01 FACILITY DOCKET NO.: 50-123 FACILITY LICENSE NO.: R-79 FACILITY: University of Missouri-Rolla EXAMINATION DATES: February 15, 2005 SUBMITTED BY: _______________________________ _____________

Paul V. Doyle Jr., Chief Examiner Date

SUMMARY

The NRC administered Operator Licensing retake examinations to four Reactor Operator (RO) and one Senior Reactor Operator (Instant) (SRO(I)) license candidates. All license candidates passed their respective written retake examinations. All but one will be issued licenses. One candidate must still pass an operating test to receive an RO license.

REPORT DETAILS

1. Examiners:

Paul V. Doyle Jr., Chief Examiner

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 4/0 1/0 5/0 Operating Tests 0/0 0/0 0/0 Overall 4/0 1/0 5/0

3. Exit Meeting:

Because of the nature of the examination (written only) the NRC did not have a formal exit meeting with the facility.

ENCLOSURE 1

U.S. Nuclear Regulatory Commission OPERATOR LICENSING EXAMINATION Section A ONLY With Answer Key UNIVERSITY OF MISSOURI-ROLLA RESEARCH REACTOR Week of February 14, 2005 ENCLOSURE 2

L Theory, Thermodynamics and Facility Operating Characteristics Page 2 QUESTION A.01 [2.0 points, 1/2 each]

The listed isotopes are all potential daughter products due to the radioactive decay of 35Br87. Identify the type of decay necessary (Alpha, Beta, Gamma or Neutron emission) to produce each of the isotopes.

a. 33 As83

b. 35 Br86

c. 35 Br87

d. 36 Kr87 QUESTION A.02 [1.0 point]

What is the definition of reactivity? A measure of the

a. number of neutrons being produced in the core.

b. number of neutrons being absorbed by the fuel.

c. reactors multiplication factor.

d. reactors departure from critical.

QUESTION A.03 [2.0 points, 1/2 each]

Using the drawing of the Integral Rod Worth Curve provided, identify each of the following reactivity worths.

a. Total Rod Worth 1. B - A

b. Actual Shutdown Margin 2. C - A

c. Technical Specification Shutdown Margin Limit 3. C - B

d. Excess Reactivity 4. D - C

5. E - C

6. E - D

7. E - A

L Theory, Thermodynamics and Facility Operating Characteristics Page 3 QUESTION A.04 [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.

QUESTION A.05 [1.0 point]

What is the kinetic energy range of a thermal neutron?

a. > 1 MeV

b. 100 KeV - 1 MeV

c. 1 eV - 100 KeV

d. < 1 eV QUESTION A.06 [1.0 point]

Which ONE of the following statements is correct with respect to why Xenon peaks following a shutdown?

a. Delayed neutrons continue causing fissions increasing the direct Xenon.

b. The decay constant for Xenon is longer than the decay constant for Iodine.

c. The decay constant for Xenon is longer than the decay constant for Cesium.

d. The decay constant for Cesium is essentially zero.

QUESTION A.07 [1.0 point]

Suppose the temperature coefficient of a core is -2.5 x 10-4 K/K/EC and the average control rod worth of the regulating control rod is 5.895 x 10-3 K/K/inch. If the temperature INCREASES by 50EC what will the automatic control command the regulating rod to do? Select the answer that is closest to the calculated value.

a. 5.6 inches in

b. 2.1 inches out

c. 0.5 inches in

d. 4.3 inches out

L Theory, Thermodynamics and Facility Operating Characteristics Page 4 QUESTION A.08 [1.0 point]

Given the following data, which ONE of the following is the closest to the half life of the material?

TIME ACTIVITY 0 2400 cps 10 min. 1757 cps 20 min. 1286 cps 30 min. 941 cps 60 min. 369 cps

a. 11 minutes

b. 22 minutes

c. 44 minutes

d. 51 minutes QUESTION A.09 [1.0 point]

During a fuel loading of the core, as the reactor approaches criticality, the value of 1/M:

a. Increases toward one

b. Decreases toward one

c. Increases toward infinity

d. Decreases toward zero QUESTION A.10 [1.0 point]

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

a. Absorption of prompt gamma rays

b. Slowing down of fission fragments

c. Neutrino interactions

d. Fission neutron scattering QUESTION A.11 [1.0 point]

Which one of the following is the definition of the FAST FISSION FACTOR?

a. The ratio of the number of neutrons produced by fast fission to the number produced by thermal fission

b. The ratio of the number of neutrons produced by thermal fission to the number produced by fast fission

c. The ratio of the number of neutrons produced by fast and thermal fission to the number produced by thermal fission

d. The ratio of the number of neutrons produced by fast fission to the number produced by fast and thermal fission

L Theory, Thermodynamics and Facility Operating Characteristics Page 5 QUESTION A.12 [1.0 point]

In a reactor at full power, the thermal neutron flux () is 2.5 x 1012 neutrons/cm2/sec. and the macroscopic fission cross-section Gf is 0.1 cm-1. The fission reaction rate is:

a. 2.5 x 1011 fissions/sec.

b. 2.5 x 1013 fissions/sec.

c. 2.5 x 1011 fissions/cm3/sec.

d. 2.5 x 1013 fissions/cm3/sec.

QUESTION A.13 [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)

QUESTION A.14 [1.0 point]

Which ONE of the following explains the response of a SUBCRITICAL reactor to equal insertions of positive reactivity as the reactor approaches criticality? Each insertion causes a

a. SMALLER increase in the neutron flux resulting in a LONGER time to stabilize.

b. LARGER increase in the neutron flux resulting in a LONGER time to stabilize.

c. SMALLER increase in the neutron flux resulting in a SHORTER time to stabilize.

d. LARGER increase in the neutron flux resulting in a SHORTER time to stabilize.

QUESTION A.15 [1.0 point]

Which ONE of the following atoms will cause a neutron to lose the most energy in an elastic collision?

a. Uranium238

b. Carbon12

c. Hydrogen2

d. Hydrogen1

L Theory, Thermodynamics and Facility Operating Characteristics Page 6 QUESTION A.16 [1.0 point]

A thin foil target of 10% copper and 90% aluminum is in a thermal neutron beam. Given a Cu = 3.79 barns, a Al = 0.23 barns, s Cu = 7.90 barns, and s Al =1.49 barns, which ONE of the following reactions has the highest probability of occurring? A neutron

a. scattering reaction with aluminum

b. scattering reaction with copper

c. absorption in aluminum

d. absorption in copper QUESTION A.17 [1.0 point]

When performing rod calibrations, many facilities pull the rod out a given increment, then measure the time for reactor power to double (doubling time), then calculate the reactor period. If the doubling time is 42 seconds, what is the reactor period?

a. 29 sec

b. 42 sec

c. 61 sec

d. 84 sec QUESTION A.18 [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.

A.03 a, 7; b, 2; c, 1; d, 5 REF:

A.04 a REF:

A.05 d REF: Glasstone, S., Nuclear Reactor Engineering, Kreiger Publishing, Malabar: Florida, 1991. 3rd Edition. pg. 13 A.06 b REF:

A.07 B REF: The temperature increase will result in a change in reactivity of: -2.5 x 10-4 K/K/EC x 50EC =

-1.25 x 10-2 K/K. Since the temperature rise results in a negative reactivity insertion, the control rod will need to drive out to add positive reactivity. D = (1.25 x 10-2 K/K) ÷ (5.895 x 10-3 K/K/inch) = 2.12 inches A.08 b REF:

A.09 d REF: Glasstone, S., Nuclear Reactor Engineering, Kreiger Publishing, Malabar: Florida, 1991. 3rd Edition. pg.

191 A.10 b REF: Glasstone, S., Nuclear Reactor Engineering, Kreiger Publishing, Malabar: Florida, 1991. 3rd Edition. pg.

R = Gf = (2.5 x 1012) x 0.1 = 2.5 x 1011 A.13 c REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1988, § A.14 b REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1988, § A.15 d REF: Lamarsh, J.R., Introduction to Nuclear Engineering, 1983. § Appendix II Table II.2, p. 643.

A.16 a REF: Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida, 1991,

§ A.17 c REF: ln (2) = -time/ = time/(ln(2)) = 60.59 . 61 seconds

L Theory, Thermodynamics and Facility Operating Characteristics Page 8 A.18 c REF: Primary Reference, Volume 2, Module 3, Reactor Theory (Nuclear Parameters), Enabling Objectives 4.1 through 4.15.

U. S. NUCLEAR REGULATORY COMMISSION RESEARCH AND TEST REACTOR OPERATOR LICENSING EXAMINATION FACILITY: University of Missouri - Rolla REACTOR TYPE: UMRR DATE ADMINISTERED: 2005/02/____

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% to pass. Examinations will be picked up one (1) hour after the examination starts.

% of Category % of Candidates Category Value Total Score Value Category 20.00 100.0 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.

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 proctor 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.

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 44444444444444444444444444444444444444444444444444444444444444444 Q'mcp T'mH'UAT Pmax'( &)2 2(k)R R('3x10 &5 secon eff'0.1seconds &1 SCR (Neq)'&S.1&S Kef CR1(1&Keff 1

)'CR 2(1&Keff2

)

CR 1(&1)'CR 2(&2)

SUR '26 .06eff& '26 .0 M'1 &Keff0 M'1&1K 'CR 1 1&K eff CR eff eff 1 2 P'P0 10 SUR(t) t P'(1 &)

P'P0 e

& P0 SDM '(1& Keff) ' R( 'R( % &

Keff &

eff

'K 2&K eff eff1 keff1xKeff2 T1/2'0.693 '(KK &1) eff eff DR 'DR 0e

&t DR '6Ci E(n)

R2 DR 1d1 'DR 2

2d2 2

DR - Rem, Ci - curies, E - Mev, R - feet (2&)2 '(1&)2 Peak 2 Peak 1 44444444444444444444444444444444444444444444444444444444444444444 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lbm 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.413 x 106 BTU/hr 1 BTU = 778 ft-lbf EF = 9/5 EC + 32 1 gal (H2O) . 8.272 lbm EC = 5/9 (EF - 32) cP = 0.998 BTU/hr/lbm/EF cp = 0.998 cal/sec/gm/EC T = -3.9 pcm/EF Pool Volume = 15650 gallons

Section A L Theory, Thermo, and Facility Characteristics Page 12 A.1a alpha neutron beta gamma ___ A.7 a b c d ___

A.1b alpha neutron beta gamma ___ A.8 a b c d ___

A.1c alpha neutron beta gamma ___ A.9 a b c d ___

A.1d alpha neutron beta gamma ___ A.10 a b c d ___

A.2 a b c d ___ A.11 a b c d ___

A.3a 1 2 3 4 5 6 7 ___ A.12 a b c d ___

A.3b 1 2 3 4 5 6 7 ___ A.13 a b c d ___

A.3c 1 2 3 4 5 6 7 ___ A.14 a b c d ___

A.3d 1 2 3 4 5 6 7 ___ A.15 a b c d ___

A.4 a b c d ___ A.16 a b c d ___

A.5 a b c d ___ A.17 a b c d ___

A.6 a b c d ___ A.18 a b c d ___

E Max Integral R Worth Cu D

Worth of Most Reactive Control Element CC Critical Rod Height Worth of Most Reactive Control Element B

A H Rod fully ou C

H

U.S. Nuclear Regulatory Commission OPERATOR LICENSING EXAMINATION Section B ONLY With Answer Key UNIVERSITY OF MISSOURI-ROLLA RESEARCH REACTOR Week of February 14, 2005 ENCLOSURE 3

Section B Normal/Emergency Procedures & Radiological Controls Page 2 QUESTION B.1 [1.0 point]

Which one of the following describes the Emergency Planning Zone (EPZ) for the UMRR? The EPZ

a. is the area that enclosed by the walls of the reactor facility.

b. specifies contamination levels of airborne, radiological dose or dose rates that may be used as thresholds for establishing emergency classes.

c. is the geographical area that is beyond the site boundary where the Reactor Director has direct authority over all activities.

d. lies within the site boundary and is bounded by a 150 meter radius from the UMRR exhaust stack.

QUESTION B.2 [1.0 point]

10CFR50.54(x) states: A licensee may take reasonable action that departs from a license condition or a technical specification (contained in a license issued under this part) in an emergency when this action is immediately needed to protect the public health and safety and no action consistent with license conditions and technical specifications that can provide adequate or equivalent protection is immediately apparent. 10CFR50.54(y) states that the minimum level of management which may authorize this action is

a. any Reactor Operator licensed at facility

b. any Senior Reactor Operator licensed at facility

c. Facility Manager (or equivalent at facility).

d. NRC Project Manager QUESTION B.3 [1.0 point]

Which ONE of the following is the 10 CFR 20 definition of TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE)?

a. The sum of the deep does equivalent and the committed effective dose equivalent.

b. The dose that your whole body receives from sources outside the body.

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

d. The dose to a specific organ or tissue resulting from an intake of radioactive material.

QUESTION B.4 [1.0 point]

Many research reactors use different methods to reduce the dose due to N16 at the pool top. If the method used keeps the N16 ten (10) feet below the surface of the water, and a half-thickness for the N16 gamma(s) is one foot for water, then the dose due to N16 is reduced (approximately) by a factor of (Note: Neglect any reduction in dose rate due to half-life.)

a. 20

b. 100

c. 200

d. 1000

Section B Normal/Emergency Procedures & Radiological Controls Page 3 QUESTION B.5 [1.0 point]

Which ONE of the following is the definition of Emergency Action Level?

a. a condition that calls for immediate action, beyond the scope of normal operating procedures, to avoid an accident or to mitigate the consequences of one.

b. Specific instrument readings, or observations; radiation dose or dose rates; or specific contamination levels of airborne, waterborne, or surface-deposited radioactive materials that may be used as thresholds for establishing emergency classes and initiating appropriate emergency methods.

c. classes of accidents grouped by severity level for which predetermined emergency measures should be taken or considered.

d. a document that provides the basis for actions to cope with an emergency. It outlines the objectives to be met by the emergency procedures and defines the authority and responsibilities to achieve such objectives.

QUESTION B.6 [1.0 point]

Which ONE of the following types of experiments maybe within the confines of the pool and does NOT require Radiation Safety Committee permission?

a. explosive materials greater than 25 milligrams.

b. fueled experiments which generates a power of 50 watts

c. corrosive materials

d. explosive materials less than 25 milligrams QUESTION B.7 [2.0 points, 1/2 each]

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

Column A Column B

a. Renew License 1 year

b. Medical Exam 2 years

c. Pass Requalification Written Examination 4 years

d. Pass Requalification Operating Test 6 years QUESTION B.8 [1.0 point]

The reactor scrams during operations after normal operating hours. The cause of the scram was an electrical storm which caused you to temporarily lose power. The power has been restored. What is the minimum level of management who may authorize restart of the reactor under these conditions. (Note: youve completed SOP 308.)

A. The Senior Operator on his/her own.

B. The Senior Operator on consultation with either the Reactor Manager or the Reactor Director.

C. The Reactor Manager after consultation with the Reactor Director.

D. The Reactor Director only.

Section B Normal/Emergency Procedures & Radiological Controls Page 4 QUESTION B.9 [1.0 points]

Which ONE of the following correctly defines a Safety Limit?

a. Limits on important process variables which are found to be necessary to reasonably protect the integrity of certain physical barriers which guard against the uncontrolled release of radioactivity.

b. The Lowest functional capability of performance levels of equipment required for safe operation of the facility.

c. Settings for automatic protective devices related to those variables having significant safety functions.

d. a measuring or protective channel in the reactor safety system.

QUESTION B.10 [1.0 point]

The CURIE content of a radioactive source is a measure of

a. the number of radioactive atoms in the source.

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

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

d. the number of nuclear disintegrations per unit time.

QUESTION B.11 [2.0 points, 1/2 each]

Identify each of the following reactor plant limitations as a Safety Limit (SL), Limiting Safety System Setting (LSSS) or a Limiting Condition for Operation (LCO). (Choices may be used more than once or not at all.)

a. Excess reactivity above the reference core condition will be no more than 1.5% k/k.

b. Reactor thermal power, P, shall be no greater than 300 kWt, or 150% of full power

c. The regulating rod shall be worth no more than 0.7% k/k in reactivity

d. The fuel element cladding temperature shall be less than 580EC (1067EF)

QUESTION B.12 [2.0 points, 2/5 each]

Match the Control Channel in column A with its respective rundown setpoint in column B.

Control Channel Setpoint

a. Linear power (%) 1. 15

b. Reactor period (seconds) 2. 20

c. Low CIC voltage (%) 3. 80

d. Radiation Monitors (mR/hr) 4. 120

e. Log power

Section B Normal/Emergency Procedures & Radiological Controls Page 5 QUESTION B.13 [1.0 point]

While working in an area marked "Caution, Radiation Area," you discover your dosimeter is off scale and leave the area.

Assuming you had been working in the area for 45 minutes, what is the maximum dose you would have received?

a. 3.8 mr

b. 35.6 mr

c. 75 mr

d. 100 mr QUESTION B.14 [1.0 point]

For the purposes of a reactor startup, the reactor is considered clean if it hasnt been operated if within the past 52 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br />, it hasnt exceeded

a. 2 kW-hr.

b. 10 kW-hr.

c. 20 kW-hr.

d. 100 kW-hr.

QUESTION B.15 [1.0 point]

An experimenter wishes to irradiate three specimens with reactivity worths of 0.5% k/k, 0.13% k/k and 0.27% k/k.

Can these specimens be placed in the reactor as UNSECURED experiments and why (why not).

a. Yes, the sum of the three specimens is less than 1.2% k/k.

b. No, the sum of the three specimens is greater than 0.8% k/k.

c. Yes, each specimen is less than 0.6% k/k.

d. No, one of the specimens is greater than 0.4% k/k.

QUESTION B.16 [1.0 point]

SOP 501 Emergency Procedures for Reactor Building Evacuation lists the actions for you (the RO) and the SRO on duty to take during this type of an emergency. The lowest level of management authorized to instruct you to proceed differently from the items listed in your checklist is

a. SRO on Duty

b. Reactor Manager

c. Reactor Director

d. NRC Project ManagerThe SRO on Duty may instruct the operator to proceed differently from the items listed in the checklist.

Section B Normal/Emergency Procedures & Radiological Controls Page 6 QUESTION B.17 [1.0 point]

While working on an experiment, you receive the following radiation doses: 100 mrem (), 25 mrem (), and 5 mrem (thermal neutrons). Which ONE of the following is your total dose?

a. 175 mrem

b. 155 mrem

c. 145 mrem

d. 130 mrem

Section B Normal/Emergency Procedures & Radiological Controls Page 7 B.1 a REF: Emergency Plan, § 6.0 Emergency Planning Zone B.2 b REF: 10CFR50.54(y)

B.3 a REF: 10 CFR 20.1003 Definitions B.4 d REF: Basic Radiological Controls knowledge: Half-Thickness and Tenth-Thickness". 210 = 1024 B.5 b REF: Emergency Plan, § 2.0 Definitions, p. 2-1.

B.6 c REF: UMRR Technical Specification 3.7(1), (2) and (3)

B.7 a, 6; b, 2; c, 2 or 1; d, 1 REF: 10CFR55. Second answer for c added per Requal Plan requirements.

B.8 a REF: SOP 103 Startup to Low Power, § B.8 B.9 a REF: Technical Specifications § 1, Definitions B.10 d REF: Standard Health Physics Definition.

B.11 a, LCO; b, LSSS; c, LCO; d, SL Ref: Technical Specifications 2.1, 2.2, 3.1(1) and 3.1(4).

B.12 a, 4; b, 1; c, 3; d, 2; e, 4 REF: Technical Specification Table 3.1 B.13 c REF: 10 CFR 20.1003 Maximum dose in a radiation area is 100 mr/hr. 100 mr/hr x 0.75 hr = 75 mr.

B.14 c REF: SOP 103 Startup to Low Power, § B.2.

B.15 d REF: Technical Specifications 3.7.1 B.16 b a Answer changed per facility comment (Typographical error).

REF: SOP 501 Emergency Procedures for Reactor Building Evacuation § C.I.6 B.17 d REF: A rem is a rem is a rem.

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: University of Missouri - Rolla REACTOR TYPE: UMRR DATE ADMINISTERED: 2005/12/24 CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

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

% of Category % of Candidates Category Value Total Score Value Category 20.00 100.0 B. Normal and Emergency Operating Procedures and Radiological Controls 20.00 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.