ML093410606

National Institute of Standards and Technology, No. 50-184/OL-10-01, Initial Examination Report

ML093410606
Person / Time
Site:	National Bureau of Standards Reactor
Issue date:	12/10/2009
From:	Johnny Eads Research and Test Reactors Branch B
To:	Richards W US Dept of Commerce, National Institute of Standards & Technology (NIST)
Young P T, NRR/PRTB, 415-4094
References
50-184/OL-10-01
Download: ML093410606 (39)

Text

December 10, 2009 Dr. Wade Richards, Manager of Operations and Engineering NIST Center for Neutron Research National Institute of Standards and Technology U.S. Department of Commerce 100 Bureau Drive, Mail Stop 8561 Gaithersburg, MD 20899-8561

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-184/OL-10-01, NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY

Dear Dr. Richards:

During the weeks of November 9, and November 30, 2009, the NRC administered a senior operator licensing examination at your NSBR facility. The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with Title 10 of the Code of Federal Regulations Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Mr. Phillip T. Young at (301) 415-4094 or via internet e-mail phillip.young@nrc.gov.

Sincerely,

/RA/

Johnny H. Eads, Jr., Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-184

Enclosures:

1. Initial Examination Report No. 50-184/OL-10-01

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

Please see next page

December 10, 2009 Dr. Wade Richards, Manager of Operations and Engineering NIST Center for Neutron Research National Institute of Standards and Technology U.S. Department of Commerce 100 Bureau Drive, Mail Stop 8561 Gaithersburg, MD 20899-8561

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-184/OL-10-01, NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY

Dear Dr. Richards:

During the weeks of November 9, and November 30, 2009, the NRC administered a senior operator licensing examination at your NSBR facility. The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with Title 10 of the Code of Federal Regulations Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Mr. Phillip T. Young at (301) 415-4094 or via internet e-mail phillip.young@nrc.gov.

Sincerely,

/RA/

Johnny H. Eads, Jr., Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-184

Enclosures:

1. Initial Examination Report No. 50-184/OL-10-01

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

Please see next page DISTRIBUTION w/ encls.:

PUBLIC PRTB r/f RidsNRRDPRPRTA RidsNRRDPRPRTB Facility File (CRevelle) O-7 F-8 ADAMS ACCESSION #: ML093410606 TEMPLATE #:NRR-074 OFFICE PRTB:CE IOLB:LA E PRTB:SC NAME PYoung: CRevelle JEads DATE 12/8/2009 12/9/2009 12/10/2009 OFFICIAL RECORD COPY

National Institute of Standards and Technology Docket No. 50-184 cc:

Director, Department of State Planning 301 West Preston Street Baltimore, MD 21201 Director, Air & Radiation Management Adm.

Maryland Dept of the Environment 1800 Washington Blvd., Suite 710 Baltimore, MD 21230 Director, Department of Natural Resources Power Plant Siting Program Energy and Coastal Zone Administration Tawes State Office Building Annapolis, MD 21401 President Montgomery County Council 100 Maryland Avenue Rockville, MD 20850 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.: 50-184/OL-10-01 FACILITY DOCKET NO.: 50-184 FACILITY LICENSE NO.: TR-5 FACILITY: National Institute of Standards and Technology EXAMINATION DATES: 11/12/09, and 12/01/2009 SUBMITTED BY: __________________________ _________

Phillip T. Young, Chief Examiner Date

SUMMARY

REPORT DETAILS

1. Examiners: Phillip T. Young, Chief Examiner, NRC

2. Results:

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

3. Exit Meeting:

Phillip T. Young, Chief Examiner, NRC Tom Meyers, Deputy for Operations The examiner thanked the facility for their support during the examination and their comments on questions C.013 and C.020 ENCLOSURE 1

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: National Institute of Standards and Technology REACTOR TYPE: NBSR DATE ADMINISTERED: 12/01/2009 REGION: I 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% in each section is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

% of Category % of Candidates Category Value Total Score Value Category 21.00 33.3 A. Reactor Theory, Thermodynamics and Facility Operating Characteristics 22.00 33.3 B. Normal and Emergency Operating Procedures and Radiological Controls 22.00 33.3 C. Facility and Radiation Monitoring Systems 65.00 100.0 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. 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 ( )2 eff = 0.1sec 1 Pmax =

(2 l )

t P = P0 e S S SCR = l* =1x10 4 sec 1 K eff eff + & CR1 ( 1 ) = CR2 ( 2 )

SUR = 26 .06

( ) (

CR1 1 K eff1 = CR2 1 K eff 2 )

(1 ) M=

1

= 2 CR P = P0 10SUR P= P0 1 K eff CR1 1 K eff1 1 K eff M= l*

1 K eff 2 SDM = =

K eff l* 0.693 K eff 2 K eff1

+ T1 =

eff + & 2 K eff1 K 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 =

R2 Peak2 Peak1 DR - Rem, Ci - curies, E - Mev, R - feet 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

ANSWER SHEET MULTIPLE CHOICE (Circle or X your choice) If you change your answer, write your selection in the blank.

A.01 A B C D A.02 A B C D A.03 A B C D A.04 A B C D A.05 A B C D A.06 A B C D A.07 A B C D A.08 A B C D A.09 A B C D A.10 A B C D A.11 A B C D

A. Reactor Theory, Thermodynamics and Facility Operating Characteristics ANSWER SHEET MULTIPLE CHOICE (Circle or X your choice) If you change your answer, write your selection in the blank.

A.12a 1 2 3 4 A.12b 1 2 3 4 A.12c 1 2 3 4 A.12d 1 2 3 4 A.13 A B C D A.14 A B C D A.15 A B C D A.16 A B C D A.17 A B C D A.18 A B C D A.19 A B C D A.20 A B C D

ANSWER SHEET MULTIPLE CHOICE (Circle or X your choice) If you change your answer, write your selection in the blank.

B.01a SL LSSS LCO B.01b SL LSSS LCO B.01c SL LSSS LCO B.01d SL LSSS LCO B.02 A B C D B.03 A B C D B.04 A B C D B.05 A B C D B.06 A B C D B.07 A B C D B.08a A B C D B.08b A B C D B.08c A B C D B.08d A B C D

B. Normal & Emerg Operating Procedures & Radiological Controls ANSWER SHEET MULTIPLE CHOICE (Circle or X your choice) If you change your answer, write your selection in the blank.

B.09 A B C D B.10 A B C D B.11 A B C D B.12 A B C D B.13 A B C D B.14 A B C D B.15 A B C D B.16 A B C D B.17 A B C D B.18 A B C D B.19 A B C D B.20 A B C D

ANSWER SHEET MULTIPLE CHOICE (Circle or X your choice) If you change your answer, write your selection in the blank.

C.01 A B C D C.02 A B C D C.03 A B C D C.04a 1 2 3 4 C.04b 1 2 3 4 C.04c 1 2 3 4 C.04d 1 2 3 4 C.05 A B C D C.06 A B C D C.07 A B C D C.08 A B C D C.09 A B C D C.10 A B C D C.11 A B C D C.12 A B C D

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.

A/C C.13a A/C D/C D/C A/C C.13b A/C D/C D/C A/C C.13c A/C D/C D/C A/C C.13d A/C D/C D/C C.14 A B C D C.15 A B C D C.16 A B C D C.17 A B C D C.18 A B C D C.19 A B C D C.20a S R/D N C.20b S R/D N C.20c S R/D N C.20d S R/D N

Question: A.001 [1.0 point] (1.0)

Which ONE of the following is the time period in which the maximum amount of Xe135 will be present in the core?

a. 7 to 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> after a startup to 100% power

b. 3 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a power increase from 50% to 100%.

c. 3 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a power decrease from 100% to 50%.

d. 7 to 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> after a scram from 100%

Answer: A.001 d.

Reference:

Intro to Nuc Eng, John R. Lamarsh © 1983, § 7.4 Figure 7.13, p. 322.

Question: A.002 [1.0 point] (2.0)

Which ONE of the following statements describes the Nuclear Instrumentation response for a rod withdrawal while the reactor is subcritical? (Assume the reactor remains subcritical)

a. Count rate will rapidly increase (prompt jump), then gradually increase to a new stable value.

b. Count rate will rapidly increase (prompt jump), then gradually decrease to the initial value.

c. Count rate will rapidly increase (prompt jump) to a new stable value.

d. Count rate will not change until criticality is reached.

Answer: A.002 a.

Reference:

Intro to Nuc Eng, John R. Lamarsh © 1983, § 7.1, pp. 286-258.

Question A.003 [1.0 point] (3.0)

Which ONE of the four listed factors (of the six-factor formula) is greater than one for the NIST reactor?

a. Fast Fission Factor ()

b. Thermal Utilization Factor (f)

c. Thermal Non-Leakage probability (£th)

d. Resonance Escape probability (p)

Answer: A.003 a.

Reference:

Standard NRC Question1

Section A Reactor Theory, Thermo, and Facility Characteristics Question A.004 [1.0 point] (4)

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

a. More delayed neutrons are produced than prompt neutrons.

b. Delayed neutrons increase the mean neutron lifetime.

c. Delayed neutrons take longer to thermalize than prompt neutrons.

d. Delayed neutrons are born at higher energies than prompt neutrons.

Answer: A.004 b.

Reference:

Standard NRC Question1 Question A.005 [1.0 point] (5.0)

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 Answer: A.005 c.

Reference:

Standard NRC Question1 Question A.006 [1.0 point] (6.0)

To calibrate the shim arms, you measure doubling time then calculate period. If the doubling time was 42 seconds, which ONE of the following is the period?

a. 29 seconds

b. 42 seconds

c. 61 seconds

d. 84 seconds Answer: A.006 c.

Reference:

Standard NRC Question1.

Also: period = (doubling time) ÷ (ln(2)) = 42/0.693 = 60.6 61

Question A.007 [1.0 point] (7.0)

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

a. per generation.

b. per generation corrected for leakage.

c. per generation corrected for time after the fission event.

d. per generation corrected for both leakage and time after the fission event.

Answer: A.007 b.

Reference:

Standard NRC Question1 Question A.008 [1.0 point] (8.0)

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)

Answer: A.008 c.

Reference:

Standard NRC Question1 Question A.009 [1.0 point] (9.0)

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.

Answer: A.009 a.

Section A Reactor Theory, Thermo, and Facility Characteristics

Reference:

Standard NRC Question

Question A.010 [1.0 point] (10.0)

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.

Answer: A.010 c.

Reference:

Standard NRC Question1 Question A.011 [1.0 point] (11.0)

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

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

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

c. recoils with the a lower kinetic energy than it had prior to the collision.

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

Answer: A.011 c.

Reference:

Standard NRC Reactor Theory Question Question A.012 [2.0 points, 0.5 each] (13.0)

Match the neutron terms in column A with their corresponding description in Column B.

Column A Column B

a. Fast neutrons 1. Neutrons released within 10-5 sec of fission

b. Prompt neutrons 2. High energy neutrons

c. Slow neutrons 3. Neutrons released by decay of fission products

d. Delayed neutrons 4. Low energy neutrons Answer: A.012 a, 2; b, 1; c, 4; d, 3

Reference:

Standard NRC Reactor Theory

Section A Reactor Theory, Thermo, and Facility Characteristics Question A.013 [1.0 point] (14.0)

You are performing a startup from a very low reactor power level. If you establish a 26 second period, approximately how long will it take to increase reactor power by a factor of 1000?

a. 1 minutes

b. 3 minutes

c. 10 minutes

d. 30 minutes Answer: A.013 b.

Reference:

Standard NRC Question: SUR = 26/ 26/26 = 1 SUR = time in[1.0] minutes to increase power by a factor of 10. 1000 = three decades 3 x 1 = 3 minutes.

Question A.014 [1.0 point] (14.0)

For U235, the thermal fission cross-section is 582 barns, and the capture cross-section is 99 barns. When a thermal neutron is absorbed by U235, the probability that fission will occur is:

a. 0.146

b. 0.170

c. 0.830

d. 0.855 Answer: A.014 d.

Reference:

DOE Fundamentals Handbook, Module X, Probability = f/(f+ a) = 582/(528 + 99) = 582/681 = 0.855 Question A.015 [1.0 point] (16.0)

Given the Count Rate and number of fuel elements for a 1/M plot. Determine when the reactor will be critical.

Count Rate # of Elements in Core 50 2 67 4 100 6

a. 8

b. 10

c. 12

d. 14 Answer: A.015 b.

Reference:

Standard NRC Reactor Theory Question Section A Reactor Theory, Thermo, and Facility Characteristics Question A.016 [1.0 point] (17.0)

The reactor is operating at 10 mW in steady-state and in automatic mode. Which one of the following describes the stable reactor period if the control rods drop fully into the core?

a. -34 seconds due to the rapid decrease in prompt neutrons

b. -34 seconds due to the rapid decay of the short lived delayed neutron precursors

c. -80 seconds due to the slowing down length of prompt neutrons

d. -80 seconds due to the decay half life of the long lived delayed neutron precursors Answer: A.016 d.

Reference:

The amount of reactivity inserted by the blades much larger than beta; therefore, maximum stable negative period of -80 seconds results.

Question A.017 [1.0 point] (18.0)

Inserting a shim arm predominantly affects Keff by changing the

a. fast fission factor

b. thermal utilization factor

c. neutron reproduction factor

d. resonance escape probability.

Answer: A.017 b.

Reference:

Standard NRC Question Question A.018 [1.0 point] (19.0)

Which ONE of the following reactor changes requires a control rod INSERTION to return reactor power to its initial level following the change?

a. Buildup of Xe135

b. Formation of N16 in the coolant.

c. Removal of an experiment with positive reactivity from the reactor.

d. A fault in the automatic system resulting in a primary coolant temperature decrease.

Answer: A.018 d.

Reference:

Standard NRC Question

Question A.019 [1.0 point] (20.0)

As a reactor continues to operate over time, for a CONSTANT power level, the average THERMAL neutron flux

a. decreases, due to the increase in fission product poisons.

b. increases, in order to compensate for fuel depletion.

c. decreases, because the fuel is being depleted.

d. remains the same Answer: A.019 b.

Reference:

Standard NRC Question Question A.020 [1.0 point] (21.0)

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 Answer: A.020 d.

Reference:

Standard NRC Question

Section B Normal/Emergency Procedures & Radiological Controls Question B.001 [2.0 points, 0.5 each] (2.0)

Identify each of the following Technical Specification Requirements as being either a Safety Limit (SL) Limiting Safety System Setting (LSSS) or a Limiting Condition for Operation (LCO).

a. Minimum Coolant Flow (inner plenum) 60 gpm/MW

b. The reactor shall not be operated unless all four shim safety arms are operable.

c. The reactor shall not be operated unless at least one shutdown cooling pump is operable.

d. The reactor may be operated at power levels of up to 10 kW with reduced flow (including no flow) if decay heat is insufficient to cause significant heating of the reactor coolant.

Answer: B.001 a. = LSSS b. = LCO c. = LCO; d. = SL

Reference:

Technical Specifications, 2.1 2nd specification, 3.2 1st specification, 3.4 1st specification and 2.2 3rd specification.

Question B.002 [1.0 point] (3.0)

Per the definition in the Emergency Plan, Emergency Action Level(s) is (are)

a. projected radiological dose or dose commitment values to individuals that warrant protective action following a release of radioactive material.

b. the person or persons appointed by the Emergency Coordinator to ensure that all personnel have evacuated the facility or a specific part of the facility.

c. a condition or conditions which call(s) for immediate action, beyond the scope of normal operating procedures, to avoid an accident or to mitigate the consequences of one.

d. specific instrument readings, or observations; radiological 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 measures.

Answer: B.002 d

Reference:

E-Plan, 2.0 DEFINITIONS page 4.

Question B.003 [1.0 point] (4.0)

In which of the following examples is entry into the Process Room and Sub-Pile Room NOT allowed:

a. with addition portable survey instruments.

b. during operations to check on a D2O leak alarm or excessive noise

c. initial entry, after reactor shutdown upon approval of the person in charge of the shift or higher authority

d. entry into the Sub-pile is permitted during fuel transfer with fuel in the transfer chute or during fuel movement within the reactor vessel Answer: B.003 d

Reference:

A.R. 7.0 PROCESS ROOM AND SUB-PILE ROOM ENTRY Question B.004 [1.0 point] (5.0)

Which ONE of the following experiments does NOT require double encapsulation or a doubled walled container?

a. Fueled Experiment

b. Explosive experiment

c. Material corrosive to reactor

d. Material corrosive to experimental coolant Answer: B.004 a.

Reference:

Technical Specifications, § 3.8.2 Materials Question B.005 [1.0 point] (6.0)

The Emergency Plan allows which of the following voluntary radiation exposure limits without Emergency Director approval. Serious events _____ Rem or to save a life ____ Rem.

Column A Column B

a. 5 and 25

b. 5 and 50

c. 25 and 75

d. 25 and 100 Answer B.005 a.

Reference:

Emergency Plan, 7.6 PROTECTIVE ACTION EXPOSURE GUIDELINES

Section B Normal/Emergency Procedures & Radiological Controls Question B.006 [1.0 point] (7.0)

If estimated critical position differs from actual critical position by more than one degree you must:

a. stop and recalculate the estimated critical position prior to further rod withdrawal.

b. shut down the reactor.

c. notify the Reactor Supervisor.

d. notify the Chief Nuclear Engineer.

Answer: B.006 c.

Reference:

OI 1.1 Question B.007 [1.0 point] {8.0}

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.

Answer: B.007 d.

Reference:

Standard Health Physics Definition 10 CFR 20 Question: B.008 [2.0 points, 0.5 each] (10.0)

Match the radiation reading from column A with its corresponding radiation area classification (per 10 CFR 20) listed in column B. (Assume gamma radiation)

COLUMN A COLUMN B

a. 10 mRem/hr 1. Unrestricted Area

b. 150 mRem/hr 2. Radiation Area

c. 10 Rem/hr 3. High Radiation Area

d. 550 Rem/hr 4. Very High Radiation Area Answer: B.008 a. = 2; b. = 3; c. = 3; d. = 4

Reference:

10 CFR 20.1003, Definitions

Question B.009 [1.0 point] (11.0)

Youve detected a stuck regulating rod. Which ONE of the following is your immediate action(s) according to Annunciator Instruction 0.3?

a. Attempt to drive the regulating rod in until power decreases by 2%.

b. Drive all shim arms in verifying the stuck regulating rod fails to move.

c. Scram the reactor, noting the position of the stuck rod.

d. Control reactor power using the shim arms.

Answer: B.009 d.

Reference:

Annunciator Procedures 0.3.

Question B.010 [1.0 point] (12.0)

A room contains a source which, when exposed, results in a general area dose rate of 175 millirem per hour. This source is scheduled to be exposed continuously for 35 days. Select an acceptable method for controlling radiation exposure from the source within this room.

a. Post the area with the words "Danger-Radiation Area".

b. Equip the room with a device to visually display the current dose rate within the room.

c. Equip the room with a motion detector that will alarm in the control room.

d. Lock the room to prevent inadvertent entry into the room.

Answer: B.010 d

Reference:

10CFR20.1601(a)(3)

Question B.011 [1.0 point] (13.0)

Although Tritium (H3) has a radioactive half-life of 12 years, the relative damage to the body is less than many other radioisotopes with this long a half-life because

a. it is a beta emitter.

b. it has a short (12 day) biological half-life.

c. it is not readily absorbed by the body.

d. it is an alpha emitter.

Answer: B.011 b.

Reference:

Modified 1998 NBSR Requalification Examination.

Section B Normal/Emergency Procedures & Radiological Controls Question B.012 [1.0 point] (14.0)

In regards to Emergency Health Physics Equipment located at the control room area, Which of the pairs of items would you expect to find.

a. protective clothing and an air sampler

b. portable emergency radios and an air sampler

c. a personnel decontamination kit and protective clothing.

d. a personnel decontamination kit and portable emergency radios Answer: B.012 d.

Reference:

Emergency Instructions E.I. 4.4, § II.C. {Modified from question B.15 on 05/22/02 NRC Exam, due to Facility comment.}

Question B.013 [1.0 point] (15.0) 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) state that this may be authorized by a senior operator. Per the note in the front of the Operating Instructions, the minimum level of management who may authorize a deviation from the Operating Instructions is

a. a licensed SRO

b. the Reactor Supervisor

c. the Chief of Reactor Operations

d. the highest level of management available at the time.

Answer: B.013 d.

Reference:

Note in the front of the Operating Instructions

Question B.014 [1.0 point] (16.0)

Per Annunciator Procedure 0.1 D2O System Rupture, Immediate Action, you would stop and isolate the shutdown cooling pumps and initiate top feed if vessel level falls below

a. 60 inches.

b. 100 inches.

c. 140 inches.

d. 180 inches.

Answer: B.014 c.

Reference:

Annunciator Procedures, A.P. 01 § III.A.

Question B.015 [1.0 point] (17.0)

Given a failure in the Secondary System, the operator is instructed to maintain primary temperature less than:

a. 110°F

b. 112°F

c. 120°F

d. 125°F Answer: B.015 b.

Reference:

A.P.0.9 - SECONDARY SYSTEM FAILURE Question B.016 [1.0 point] (18.0)

Operator "A" works a standard forty (40) hour work week. His duties require him to work in a radiation area for (4) hours a day. The dose rate in the area is 10 mR/hour. Which one of the following is the MAXIMUM number of days Operator "A" may perform his duties without exceeding 10CFR20 limits?

a. 12 days

b. 25 days

c. 31 days

d. 125 days Answer: B.016 d.

Reference:

10CFR20.1201(a)(1) 5000 mr x 1 hr x day = 125 days { 10 mr 4 hr}

Section B Normal/Emergency Procedures & Radiological Controls Question B.017 [1.0 point] (19.0)

The dose rate from a mixed beta-gamma point source is 100 mrem/hour at a distance of one (1) foot, and is 0.1 mrem/hour at a distance of twenty (20) feet. What percentage of the source consists of beta radiation?

a. 20%

b. 40%

c. 60%

d. 80%

Answer: B.017 c.

Reference:

10CFR20.

At 20 feet, there is no beta radiation. Gamma at 20 feet = 0.1 mrem/hour, gamma at 1 foot = 40 mrem/hour. Therefore beta at 1 foot = 60 mrem/hour = 60%.

Question B.018 {1.0 point} (20.0)

A radioactive sample which initially was reading 50 R/hr has decayed over 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to 25 R/hr.

What will the sample read in another 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />?

a. 12.5 R/hr

b. 17.8 R/hr

c. 18.8 R/hr

d. 22.9 R/hr Answer: B.018 b.

Reference:

A = AO

• e exp(-lambda

• time) 25 = 50

• e exp(-lambda

• 8

• 3600);

lambda = 2.4 exp-5/sec A = 25

• e exp(-2.4 exp-5

• 4

• 3600); A = 17.7 Question B.019 [1.0 point] (21.0)

If estimated critical position differs from actual critical position by more than one degree you must:

a. stop and recalculate the estimated critical position prior to further rod withdrawal.

b. shut down the reactor.

c. notify the Reactor Supervisor.

d. notify the Chief Nuclear Engineer.

Answer: B.019 c.

Reference:

OI 1.1 § II.I p. 4 {Modified 1996 NBSR Requalification Examination Question}

Question B.020 [1.0 point] {22.0}

For fuel to be self-protecting, the level of radiation emitted must be at least 100 R/hr at 3 feet without intervening shielding. A recent shipment of spent fuel had the following characteristics:

• Number of pieces per cask 84

• Total activity per cask 26,000 Ci

• Average radiation emission energy 1 Mev Assume that each fuel piece has the same activity level, the radiation emitted per piece at three feet without intervening shielding is about:

a. six times the allowable limit.

b. four times the allowable limit

c. twice the allowable limit

d. the allowable limit Answer: B.020 c.

Reference:

NBSR 1998 Requal Exam Question B.017 26000/84 = 309.5; R/Hr = 6CE/ft2 = 6 x 309.5 x 1 / 32; 1857/9 = 206.3 R/hr

Section C Facility and Radiation Monitoring Systems Question C.001 [1.0 point] (1.0)

Select the condition resulting in regulating rod control swapping from automatic to manual.

a. A control limit alarm is received

b. Servo deviation of 8%

c. Slight movement of the shim arm bank switch

d. Slight movement of the regulating rod switch Answer: C.001 d.

Reference:

NBSR 2006 Requailification Examination Question C.002 [1.0 point] (2.0)

A ventilation Radiation Monitor located on the B1 level is supplied with air drawn by a blower from 10 points within the ventilation system. The primary purpose of this monitor is to monitor the concentration of

a. H3

b. Ar41

c. Xe133 & I135 (Fission Gases)

d. N16 Answer: C.002 a.

Reference:

NBSR Reactor Operations Training Guide, 6.4.7 Ventilation Tritium Monitor.

Question C.003 [1.0 point] (3.0)

Upon receipt of a major scram, RM 3-4 shifts from its normal measuring point to

____________________ , and RM 3-5 shifts from its normal measuring point to

a. the outlet of SF-19; outlet of EF-5 and EF-6.

b. the outlet of EF-5; outlet of EF-6.

c. the outlet of SF-19; the outlet of EF-2.

d. the outlet of EF-5 and EF-6; the outlet of SF-19.

Answer: C.003 a.

Reference:

NBSR Reactor Operations Training Guide

Section C Facility and Radiation Monitoring Systems Question C.004 [2.0 points, 0.5 each] (5.0)

Match each type of gas listed with its correct purpose.

Gas Purpose

a. Air 1. Gas used in the Pneumatic Tube (Rabbit) System.

b. CO2 2. Used to operate ventilation system butterfly valves.

c. N2 3. Cover gas on primary system to prevent loss of D2O.

d. He 4. Backup to operate ventilation system butterfly valves.

Answer: C.004 a. = 2; b. = 1; c.= 4; d. = 3

Reference:

NBSR Reactor Operations Training Guide, Question C.005 [1.0 point] (6.0)

When operating at power, leakage from the primary coolant system to the secondary cooling system would be first detected by:

a. RM 3-2.

b. tritium monitors.

c. RM 3-1 and RM 3-3.

d. RM 4-1.

Answer: C.005 c.

Reference:

NBSR 2006 Requailification Examination Question C.006 [1.0 point] (7.0)

The MAIN purpose of the activated charcoal filters in the emergency exhaust systems is to absorb radioactive

a. Tritium

b. Iodine

c. Argon

d. Nitrogen Answer: C.006 b.

Reference:

NBSR Reactor Operations Training Guide, 4.10.3 Ventilation System Under Accident Conditions.

Section C Facility and Radiation Monitoring Systems Section C Facility and Radiation Monitoring Systems Question C.007 [1.0 point] (8.0)

It is desired to provide emergency cooling via bottom feed. In order to accomplish this, the operator opens valves:

a. DWV-32 and DWV-33.

b. DWV-32 and DWV-34.

c. DWV-33 and DWV-35.

d. DWV-34 and DWV-35.

Answer: C.007 d.

Reference:

NBSR 2006 Requailification Examination Question C.008 [1.0 point] (9.0)

Which ONE of the following signals does NOT generate a MAJOR SCRAM?

a. High Irradiated Air Monitor Activity Level

b. High Normal Air Monitor Activity Level

c. High Stack Monitor Activity Level

d. High Fission Products Monitor Activity Level Answer: C.008 d.

Reference:

NBSR Reactor Operations Training Guide 6.4 RADIATION MONITORING SYSTEMS.

Question C.009 [1.0 point] (10.0)

In the event of a complete loss of all heavy water cooling, core cooling can still be accomplished by:

a. the helium sweep system.

b. the CO2 system.

c. the secondary cooling system.

d. potable water by installing spool piece.

Answer: C.009 d.

Reference:

NBSR 2006 Requailification Examination

Section C Facility and Radiation Monitoring Systems Question C.010 [1.0 point] (11.0)

You discover several scratches on the outer plate of a fuel element. You inform the Reactor Supervisor who decides to use the element. The decision to use this element was

a. appropriate because the outer plates contain no fuel.

b. inappropriate because of the higher fuel loading of the outer plates.

c. inappropriate because it could lead to fission product release from the plate due to reduced cladding.

d. appropriate because the outer two plates are thicker than the inner plates, due to thicker cladding.

Answer C.010 a.

Reference:

NBSR Requalification Exam administered April 1998.

Question C.011 [1.0 point] (12.0)

Following a major scram the ventilation system lineup

a. reconfigures automatically, the dilution fan energizes to maintain confinement pressure at no less than 0.25 inches negative.

b. must be reconfigured manually, the operator must start the dilution fan to maintain confinement pressure at no less than 0.25 inches negative.

c. reconfigures automatically, normal ventilation secures, and the emergency exhaust system maintains confinement pressure at no less than 0.25 inches negative.

d. must be reconfigured manually, the operator must secure the normal ventilation and start the emergency exhaust system which maintains confinement pressure at no less than 0.25 inches negative.

Answer: C.011 c.

Reference:

NBSR Reactor Operations Training Guide, 4.10.3 Ventilation System Under Accident Conditions.

Section C Facility and Radiation Monitoring Systems Question C.012 [1.0 point] (13.0)

Operation with the shim safety arms less than 12° is prohibited because

a. the worth of the shim arms below this level is insignificant

b. the scram spring force is insufficient to overcome shock absorber resistance.

c. there is too much stress on the shim arm below this angle.

d. the scram spring force is insufficient to overcome the pressure differential due to full core flow.

Answer: C.012 b.

Reference:

NBSR Reactor Operations Training Guide Question C.013 [2.0 points, 0.5 each] (15.0)

Identify each of the essential electrical loads listed as being powered by AC Only (AC), DC Only, (DC) or AC or DC (AC/DC).

a. Emergency Cooling Sump

b. D2O Shutdown Pumps

c. Emergency Exhaust Fans (EF 5 and EF 6)

d. Annunciator Power and Evacuation Alarm Answer: C.013 a. = AC; b. = AC/DC; c. = AC/DC; d. = DC AC/DC

Reference:

NBSR Reactor Operations Training Guide Per Facility comment: Annunciator Power is AC and Evacuation Power is DC.

Answer: should be AC/DC.

Question C.014 [1.0 point] (16.0)

Which ONE of the following Reactor Rundown Signals can NOT be bypassed?

a. Cold Source flow

b. Cold Source pressure

c. Reactor Outlet Temperature

d. Reactor Thermal Power.

Answer: C.014 c.

Reference:

NBSR Reactor Operations Training Guide

Section C Facility and Radiation Monitoring Systems Question C.015 [1.0 point] (17.0)

WHICH ONE of the listed components within the Helium Sweep Gas system is responsible for the recombination of disassociated D2 and O2?

a. The 1/4 thick aluminum vessel containing alumina-palladium pellets.

b. The 1/4 aluminum plate tank containing an activated charcoal filter.

c. The 6061 aluminum cylinder Gas Holder.

d. The 304 Stainless Steel cold Trap.

Answer: C.015 a.

Reference:

NBSR Training Guide, 4.7 HELIUM SWEEP GAS SYSTEM Question C.016 [1.0 point] (18.0)

Which ONE of the following is the method used to get rid of radioactive liquid waste?

Radioactive liquid waste is sent to Health Physics where it is

a. held, for decay of short lived isotopes then sampled for 10CFR20 limits and if satisfactory, pumped to the sewer system.

b. put through evaporators, filters ion exchangers, reducing the liquid waste to proper solid form.

c. diluted to less than 10CFR20 limits, then pumped to the sewer system.

d. tested for 10CFR20 limits, then pumped to the sewer system.

Answer: C.016 b.

Reference:

NBSR Training Guide, § 4.1.2.2. 3rd ¶.

Question C.017 [1.0 point] (19.0)

The Compensated Ion Chambers used at NIST do not have the compensating voltage connected. The reason that compensating voltage is not required is because

a. the Deuterium in the primary absorbs many gammas (gamma-neutron reaction).

b. the Tritium in the primary absorbs many gammas (gamma-neutron reaction).

c. there are lead windows located between the core and the detectors which absorb many gammas.

d. a D2O moderated core must be larger than an H2O moderated core resulting in greater self-shielding of gammas.

Answer: C.017 c.

Section C Facility and Radiation Monitoring Systems

Reference:

NBSR Training Guide, §§ 6.2.3 and 6.2.4, p. 46

Section C Facility and Radiation Monitoring Systems Question C.018 [1.0 point] (20.0)

Which ONE of the following is the purpose of the thermal shield?

a. To thermalize neutrons for detection by nuclear instrumentation

b. To reduce the amount of gamma radiation heating of the biological shield.

c. To reduce the amount of gamma radiation reaching the nuclear instrumentation.

d. To reduce the amount of neutron radiation heating of the biological shield.

Answer: C.018 b.

Reference:

NBSR Operations Training Guide, § 7.2 Thermal Shield Question C.019 [1.0 point] (21.0)

Which ONE of the following is the reason that many D2O valves are equipped with spark plugs?

a. To recombine D2 and O leaking from the primary, thereby reducing explosion risk.

b. To detect primary leak due to a diaphragm rupture.

c. To detect valve vibration due to excessive flow.

d. To detect open/closed position of valve.

Answer: C.019 b.

Reference:

NBSR Operations Training Guide, § 2.4.2 Question C.020 [1.0 point] (22.0)

Identify each of the following conditions as a Scram, RunDown or Neither.

a. Period on NC-6 at 5 sec (currently <10% of full power.)

b. Thermal power at 22 MW.

c. Reactor outlet temperature at 135ºF

d. Reactor level at 142 Answer: C.020 a. = S RD; b. = N; c. = RD; d. = RD

Reference:

AP 6.1 - Scram and AP 6.2 - Rundown Answer a. changed per facility comment.