ML14328A451

Examination Report, No. 50-184/OL-15-01, National Institute of Standards and Technology Reactor

ML14328A451
Person / Time
Site:	National Bureau of Standards Reactor
Issue date:	12/02/2014
From:	Kevin Hsueh Research and Test Reactors Licensing Branch
To:	O'Kelly S US Dept of Commerce, National Institute of Standards & Technology (NIST)
Young P, DPR/PROB, 415-4094
Shared Package
ML14234A157	List: ML14234A211 ML14328A451 ML14328A476
References
50-184/15-001 50-184/OL-15-01
Download: ML14328A451 (28)

Text

December 2, 2014 Dr. Sean OKelly, 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:

EXAMINATION REPORT NO. 50-184/OL-15-01, NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY REACTOR

Dear Dr. OKelly:

During the week of November 10, 2014, the NRC administered operator licensing examinations at your NIST reactor. 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/

Kevin Hsueh, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-184

Enclosures:

1. Examination Report No. 50-184/OL-15-01

2. Written examination as administered cc without enclosures:

Please see next page

Dr. Sean OKelly, Manager of Operations and Engineering December 2, 2014 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:

EXAMINATION REPORT NO. 50-184/OL-15-01, NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY REACTOR

Dear Dr. OKelly:

During the week of November 10, 2014, the NRC administered operator licensing examinations at your NIST reactor. 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/

Kevin Hsueh, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-184

Enclosures:

1. Examination Report No. 50-184/OL-15-01

2. Written examination as administered cc without enclosures:

Please see next page DISTRIBUTION w/ encls.:

PUBLIC PRTB r/f Facility File (CRevelle) O-7 F-08 RidsNRRDPRPRTB RidsNRRDPRPRTA ADAMS ACCESSION #: ML14328A451 NRR-074 OFFICE NRR/DPR/PRTB:CE E NRR/DPR/IOLB:LA E NRR/DPR/PRTB:BC NAME PYoung CRevelle KHsueh DATE 11/24/2014 12/01/2014 12/02/2014 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY

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

Environmental Program Manager III Radiological Health Program Air & Radiation Management Adm.

Maryland Dept. of the Environment 1800 Washington Blvd, Suite 750 Baltimore, MD 21230-1724 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-15-01 FACILITY DOCKET NO.: 50-184 FACILITY LICENSE NO.: TR-5 FACILITY: NSBR EXAMINATION DATES: November 12, 2014 SUBMITTED BY: ___________/RA/ _______ ___11/24/2014_

Phillip T. Young, Chief Examiner Date

SUMMARY

During the week of November 10, 2014 the NRC administered licensing examinations to one Senior Reactor Operator-Instant (SROI) applicants. The applicant passed all portions of the examination.

ENCLOSURE 1

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:

An exit meeting was not conducted.

Section A Reactor Theory, Thermo, and Facility Characteristics U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: National Institute of Standards and Technology REACTOR TYPE: Heavy Water cooled and moderated Tank DATE ADMINISTERED: 11/12/2014 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 20.00 33.3 A. Reactor Theory, Thermodynamics and Facility Operating Characteristics 21.00 33.3 B. Normal and Emergency Operating Procedures and Radiological Controls 22.00 33.3 C. Facility and Radiation Monitoring Systems 63.00  % 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 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.

Section A Reactor Theory, Thermo, and Facility Characteristics

EQUATION SHEETs Q = m c p T = m H = UA T eff = 0.1 seconds-1 S S CR1 (1 - K eff 1 ) = CR 2 (1 - K eff 2 )

SCR =

SUR = 26.06 eff - 1 - K eff CR1 (- 1 ) = CR 2 (- 2 )

1 - K eff 0 1 M= CR1 1 - K eff 1 M= =

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

P= P0 (1 - K eff ) -

SDM = = = +

K eff eff

( K eff - 1)

K eff 2 - K eff 1 0.693 =

K eff k eff 1 x K eff 2 T

DR = DR0 e- t 6CiE(n)

DR = 2 2

DR1 d 1 = DR 2 d 2 2

R DR - Rem, Ci - curies, E - Mev, R - feet 2

( 2 - )2 ( 1 - )

=

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

Section A Reactor Theory, Thermo, and Facility Characteristics Question: A.001 [1.0 point] (1.0)

A reactor scram has resulted in the instantaneous insertion of .003 K/K of negative reactivity.

Which ONE of the following is the stable negative reactor period resulting from the scram?

a. 45 seconds

b. 56 seconds

c. 80 seconds

d. 112 seconds Answer: A.001 c

Reference:

Lamarsh, J.R., Introduction to Nuclear Engineering, Addison-Wesley Publishing, Reading, Massachusetts, 1983. § 7.1, p. 289 Question: A.002 [1.0 point] (2.0)

Which ONE of the following correctly describes the behavior of the reactor as it approaches criticality during a startup. (Assume equal reactivity additions)

Time to stabilize Size of change in neutron count equilibrium neutron count

a. longer larger

b. shorter larger

c. longer smaller

d. shorter smaller Answer: A.002 a.

Reference:

Standard NRC Reactor Theory Question Question: A.003 [1.0 point] (3.0)

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

Scattering Cross Section Absorption Cross Section

a. High High

b. Low High

c. High Low

d. Low Low Answer: A.003 c.

Reference:

Standard NRC Reactor Theory Question

Section A Reactor Theory, Thermo, and Facility Characteristics Question: A.004 [1.0 point] (4.0)

In a subcritical reactor, Keff is increased from 0.861 to 0.946. Which ONE of the following is the amount of reactivity that was added to the reactor core?

a. 0.085 K/K

b. 0.104 K/K

c. 0.161 K/K

d. 0.218 K/K Answer: A.04 b.

Reference:

Lamarsh, Introduction to Nuclear Engineering, 2nd Edition, Page 282 1 = (0.861 - 1)/0.861 = -0.161 k/k 2 = (0.946 - 1)/0.946 = -0.057 k/k

= 2 - 1 = -0.057 - (-0.161) = +0.104 k/k Question: A.005 [1.0 point] (5.0)

Starting cooling tower fans resulted in a primary average temperature decrease of 5ºF from 105ºF to 100ºF. The regulating rod moved inward from 13" to 10". The moderator temperature coefficient is:

a. 11/2¢/ F positive

b. 11/2¢/ F negative

c. 2 ¢/ F positive

d. 2 ¢/ F negative Answer: A.05 d.

Reference:

NSBR - Requal Examination Addendum Additional questions Question: A.006 [1.0 point] (6.0)

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.06 b.

Reference:

Standard NRC Question1

Section A Reactor Theory, Thermo, and Facility Characteristics Question: A.007 [1.0 point] (7.0)

A thin foil target of 10% aluminum atoms and 90% copper atoms is placed into a thermal neutron beam. Given s = 1.49 and a = 0.23 for aluminum and s = 7.9 and a = 3.79 for copper, determine the reaction with the highest probability. A neutron

a. scattering reaction with aluminum

b. scattering reaction with copper

c. absorption in aluminum

d. absorption in copper Answer: A.07 b.

Reference:

Standard NRC Reactor Theory Question Question: A.008 [1.0 point] (8.0)

Which one of the following characteristics of a material would result in the most efficient thermalization of neutrons?

a. LOW atomic mass number and HIGH scattering cross section.

b. HIGH atomic mass number and LOW scattering cross section.

c. LOW neutron absorption and LOW scattering cross section.

d. LOW neutron absorption and HIGH atomic mass number.

Answer: A.08 a.

Reference:

Intro to Nuc Eng, John R. Lamarsh © 1983, § 3.5, pp. 59-60.

Question: A.009 [1.0 point] (9.0)

Given secondary flow through HE-1A & B is 9650gpm, HE-1A & 1B (Secondary Inlet Temperature) both read 80 F, HE-1A &1B secondary Outlet Temperature both read 91 F, and the Thermal Power constants for water is 147 watts/gpm- F (H2O), determine the current operating power.

a. 78%

b. 71%

c. 65%

d. 59%

Answer: A.09 a.

Reference:

Previous NRC Exam administered 02/1991 Also: 9650gpm x 11 F x 142 watt/gpmºF= 15.6 x 106 watts; 15.6 x 106 ÷ 20.0 x 106 = 0.78 = 78%

Section A Reactor Theory, Thermo, and Facility Characteristics Question: A.010 [1.0 point] (10.0)

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.10 c.

Reference:

Standard NRC Question.

Also: period = (doubling time) ÷ (ln(2)) = 42/0.693 = 60.6 61 Question: A.011 [1.0 point] (11.0)

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.11 b.

Reference:

Standard NRC Question1 Question: A.012 [1.0 point] (12.0)

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.12 c.

Reference:

Standard NRC Question1

Section A Reactor Theory, Thermo, and Facility Characteristics Question: A.013 [1.0 point] (13.0)

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.13 d.

Reference:

Standard NRC Question Question: A.014 [1.0 point] (14.0)

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.14 c.

Reference:

Standard NRC Question1 Question: A.015 [1.0 point] (15.0)

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.15 b.

Reference:

Standard NRC Reactor Theory Question

Section A Reactor Theory, Thermo, and Facility Characteristics Question: A.016 [1.0 point] (16.0)

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.16 c.

Reference:

Standard NRC Reactor Theory Question Question: A.017 [1.0 point] (17.0)

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.017 d.

Reference:

DOE Fundamentals Handbook, Module X, Probability = f/(f+ a) = 582/(528 + 99) = 582/681 = 0.855 Question A.018 [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.018 b.

Reference:

Standard NRC Question

Section A Reactor Theory, Thermo, and Facility Characteristics Question A.019 [1.0 point] (19.0)

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.19 b.

Reference:

Standard NRC Question Question A.020 [1.0 point] (20.0)

Which statement best describes Xe-135 behavior following a Reactor Scram?

a. Xenon concentration decreases due to production rate from fission stops.

b. Xenon concentration decreases due to production rate from I-135 decay increasing.

c. Xenon concentration increases due to production rate from Pm-149 increasing.

d. Xenon concentration increases due to I-135 decay exceeding Xe-135 decay.

Answer: A.20 d.

Reference:

Standard NRC Reactor Theory Question

Section B Normal/Emergency Procedures & Radiological Controls Question B.001 [2.0 points, 0.4 each] (2.0)

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

a. Reactor Power 130%

b. Inner Plenum Flow 235 gpm/MW

c. D2 concentration at 4% in helium sweep system

d. Reactor vessel level at 24" below overflow line

e. Reactor Operation exceeding applicable temperature line on either Figure 2.1 or 2.2 of Technical Specifications.

Answer: B.01 a. = LSSS; b. = LSSS; c. = LCO; d. = LCO; e. = SL

Reference:

T.S. 2.0 through 2.3.

Question B.002 [2.0 points, 0.5 each] (4.0)

Identify each of the following actions as either an CHANNEL CHECK (CHECK), CHANNEL TEST (TEST) or CHANNEL CALIBRATION (CAL).

a. Verifying overlap between Nuclear Instrumentation channels.

b. Replacing a Resistance Temperature Detector (RTD) with a precision resistance decade box to verify proper channel output for a given resistance.

c. Performing a calorimetric (heat balance) on the primary system, then adjusting Nuclear Instrumentation to agree with results.

d. Placing a radioactive source next to a radiation detector, and verifying meter movement.

Answer: B.02 a. = CHECK; b. = TEST; c. = CAL; d. = TEST

Reference:

T.S. § 1.0 DEFINITIONS Question B.003 [1.0 points] (5.0)

During fuel movements in the vessel, which one of the following is NOT REQUIRED?

a. Confinement integrity shall be in force.

b. A Health Physics representative shall be present.

c. A licensed operator shall be stationed in the Control Room.

d. A communication system shall be in operation between the Control Room and the reactor top.

Answer: B.03 b.

Reference:

OI 6.1, Fueling and Defueling Procedures

Section B Normal/Emergency Procedures & Radiological Controls Question B.004 [1.0 points] (6.0)

During operation of the D2O AUXILIARY SYSTEMS, which of the following should be avoided?

a. The pressure drop across the pre-filter is 6.0 psig (flow is normal).

b. Flow through an IX column is 20 gpm.

c. D2O temperature of 135ºF

d. DWV-24 is closed Answer: B.04 d.

Reference:

OI 2.2, OPERATION OF THE D2O AUXILIARY SYSTEMS Question B.005 [1.0 points] (7.0)

Which ONE of the following correctly describes an automatic response of the Reactor Building Ventilation System?

a. SF-2 will shut down unit if the temperature on the outlet of the heating coils drops below 40oF

b. Filter F-2 on the suction of SF-2 has an automatic roll filter which will advance the filter when the P becomes 0.5" H2O across the filter.

c. Pressure switch 151 controls ACV-12, the building vacuum break - Open at 1.5" H2O negative.

d. SPC-3 controls discharge damper D-3 on EF-3 to maintain the first floor 0.1" H2O negative in relation to the High Bay area Answer: B.05 a.

Reference:

OI 4.8, REACTOR BUILDING VENTILATION SYSTEM Question B.006 [1.0 points] (8.0)

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 25

b. 5 50

c. 25 75

d. 25 100 Answer B.06 a.

Reference:

Emergency Plan, 7.6 PROTECTIVE ACTION EXPOSURE GUIDELINES

Section B Normal/Emergency Procedures & Radiological Controls Question B.007 [1.0 points] (9.0)

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.07 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.008 [1.0 points] (10.0)

According to Emergency Instructions, which one of the following lists the two individuals (by title) who may serve as Emergency Director until relieved by higher authority?

a. Reactor Supervisor, or in his absence the Reactor Operator on the console

b. Reactor Supervisor, or in his absence the Senior Reactor Operator.

c. Deputy Chief Engineer, or in his absence the Reactor Supervisor

d. Deputy Chief Engineer, or in his absence the Senior Reactor Operator Answer: B.08 a.

Reference:

E.I. Figure 6.1 NBSR Emergency And Support Organizations Question B.009 [1.0 points] (11.0)

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.09 d.

Reference:

Standard Health Physics Definition 10 CFR 20

Section B Normal/Emergency Procedures & Radiological Controls Question B.010 [2.0 points, 0.5 each] (13.0)

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.10 a. = 2; b. = 3; c. = 3; d. = 4

Reference:

10 CFR 20.1003, Definitions Question B.011 [1.0 point] (14.0)

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.11 d

Reference:

10CFR20.1601(a)(3)

Question B.012 [1.0 point] (15.0) 3 Although Tritium (H ) 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.12 b.

Reference:

Modified 1998 NBSR Requalification Examination.

Section B Normal/Emergency Procedures & Radiological Controls Question B.013 [1.0 point] (16.0)

A radiation survey instrument was used to measure an irradiated experiment. The results were 100 mrem/hr with the window open and 60 mrem/hr with the window closed. What was the beta dose?

a. 40 mrem/hr

b. 60 mrem/hr

c. 100 mrem/hr

d. 140 mrem/hr Answer: B.13 a.

Reference:

Instrument reads only dose with window closed. Instrument reads both and dose with window open. Therefore, dose is window open dose less window closed dose.

Question B.014 [1.0 point, 0.333 each] (17.0)

Match each of the Technical Specification Limits in column A with its corresponding value in column B.

(Each limit has only one answer, values in Column B may be used more once, more than once or not at all.)

Column A Column B

a. Absolute worth of any individual experiment 1. 15%

b. Maximum Core Excess Reactivity 2. 4.0%

c. The sum of the absolute Value of all experiments 3. 2.6%

4. 1.0%

5. 0.5%

Answer: B.14 a. = 0.5% ; b. = 15% ; c. = 2.6%

Reference:

Technical Specifications § 3.1.2 (1) and 3.8.1 (1) and 3.8.1 (2)

Question B.015 [1.0 point] (18.0)

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.15 a.

Reference:

Technical Specifications, § 3.8.2 Materials

Section B Normal/Emergency Procedures & Radiological Controls Question B.016 [1.0 point] (19.0)

During shipment of spent fuel, the truck door was closed whenever time was spent loading baskets in the pool. The truck door was closed to......

a. safeguard the fuel.

b. establish confinement integrity.

c. limit the spread of contamination.

d. prevent an unauthorized entry point.

Answer: B.16 b.

Reference:

TS, § 3.4.2 NBSR Reactor Operations Training Guide 8.1 Reactor Building And Confinement System Question B.017 [1.0 point] (20.0)

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 irradiated fuel movement from or to the reactor vessel.

Answer: B.17 d.

Reference:

A.R. 7.0 PROCESS ROOM AND SUB-PILE ROOM ENTRY Question B.018 [1.0 point] (21.0)

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.18 d.

Reference:

Annunciator Procedures 0.3.

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

Which of the following instruments provide the best backup for the primary outlet flow for both information and trip function?

a. Primary inlet and outlet temperature.

b. HE-1A and HE-1B primary flow.

c. Overflow.

d. Inner and outer plena flows.

Answer: C.001 d.

Reference:

NBSR 1998 Requal Exam Question C.012 Question C.002 [1.0 point] (2.0)

The reactor has been operating at full power for a week, when all commercial power is lost. How is decay heat removed from the core?

a. Natural Circulation flow due to large T across core and inlet higher than outlet.

b. Natural Circulation flow due to large T across core and outlet higher than inlet.

c. DC Shutdown pumps powered from emergency battery.

d. D2O injection from Emergency tank.

Answer: C.02 c.

Reference:

NBSR March 1994 Requalification examination Question C.003 [1.0 point] (3.0)

An important function of the tritium monitor is to....

a. Monitor the confinement building for tritium in the air.

b. Monitor the secondary to detect a primary to secondary leak.

c. Continuously measure the tritium level in the primary system.

d. Monitor the releases to radwaste to detect the presence of tritium system.

Answer: C.003 a.

Reference:

NBSR 1998 Requal Exam Question C.014

Section C Facility and Radiation Monitoring Systems Question C.004 [1.0 point] (4.0)

Even though virtually no fission products are found in the helium sweep system, the fission products monitor, in the helium sweep system, usually indicates greater than 10,000 cpm at full power. This indication is mainly caused by:

a. Radiolytic gasses.

b. Nitrogen-16 formation.

c. Argon-41 formation from trapped air.

d. Tritium vapor from the primary coolant.

Answer: C.04 c.

Reference:

NBSR 1998 Requal Exam Question Question C.005 [1.0 point] (5.0)

Rod drop testing is in progress with the reactor in rod test. One shim is fully withdrawn, what will the result be if the operator begins to withdraw a second shim?

a. A console alarm to alert the operator not to withdraw the rod.

b. A major scram.

c. A rundown.

d. A scram Answer: C.05 c.

Reference:

NBSR Requal Exam Question Question C.006 [1.0 point] (6.0)

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.06 d.

Reference:

NBSR 2006 Requailification Examination

Section C Facility and Radiation Monitoring Systems Question C.007 [1.0 point] (7.0)

Which ONE of the following is the method used to prevent over and under pressure conditions in the D2O experimental cooling system.

a. Backpressure regulator (DWV-25).

b. Manually increasing supply to other loads while shutting down one of the loads.

c. A surge tank with an air blanket (accumulator) maintains constant system pressure.

d. Overpressure - relief valve, underpressure, centrifugal pump (speed automatically increases)

Answer: C.07 a.

Reference:

NBSR Operations Training Guide, § 4.2.2.

Question C.008 [1.0 point] (8.0)

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.08 c.

Reference:

NBSR 2006 Requailification Examination Question C.009 [1.0 point] (9.0)

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 Question C.010 [2.0 point, 1/2 point each] (11.0)

Identify the type of detector (B10 Proportional Counter (B10), Fission Counter (FC), Compensated Ion Chamber (CIC) or Uncompensated Ion Chamber(UIC)) utilized by each of the Nuclear Instrumentation channels listed below. (Note detector types may be used more than once or not at all.)

a. Source Channels 1& 2

b. Intermediate Range (Log-N) Channels 3 & 4

c. Linear Power and Automatic Regulating Rod Control Channel 5

d. Power Range Channels 6, 7 & 8.

Answer: C.10 a. = B10; b. = CIC; c. = CIC; d. = UIC

Reference:

NBSR Reactor Operations Training Guide, Question C.011 [2.0 point, 1/2 point each] (13.0)

Match the instrumentation in column A with the type of protection afforded from column B.

Column A Column B

a. Nuclear Instrumentation 1. Rundown ONLY

b. Process Instrumentation 2. Scram ONLY

c. Air Radiation Monitors 3. Rundown and Scram

d. Area Radiation Monitors 4. Major Scram

5. NONE Answe:r C.11 a. = 3; b. = 3; c. = 4; d. = 5

Reference:

NBSR Requal exam.

Question C.012 [1.0 point] (14.0)

Which ONE of the following is the material used as a neutron poison in the Regulating Rod?

a. Erbium

b. Cadmium

c. Aluminum

d. Boron Answer: C.12 c.

Reference:

NBSR Reactor Operations Training Guide, § 1.1.5 2nd ¶.

Section C Facility and Radiation Monitoring Systems Question C.013 [1.0 point, 0.25 points each] (15.0)

Identify the valves listed below as either Motor Operated (MO)or Air Operated (AO).

a. DWV-1 Inner Plenum Flow Control (D2O Main Cooling System)

b. DWV-2 Outer Plenum Flow Control (D2O Main Cooling System)

c. DWV-40 D2O supply to Emergency Tank (D2O Auxiliary System)

d. DWV-19 Isolation between Core and Main Pump Piping (D2O Main Cooling System)

Answer: C.13 a. = MO; b. = MO; c. = AO; d. = MO

Reference:

NBSR Operations Training Guide, § 2.2.4 and Drawing 2.1 Question C.014 [1.0 point] (16.0)

WHICH ONE of the following correctly describes the lineup of Secondary Valves 1, 2 and 3?

a. SCV 1 & 2 supply suction to pumps 4, 5 and 6, SCV 3 supplies suction to pumps 1, 2 and 3.

b. SCV 2 & 3 supply suction to pumps 4, 5 and 6, SCV 1 supplies suction to pumps 1, 2 and 3.

c. SCV 1 & 2 supply suction to pumps 1, 2 and 3, SCV 3 supplies suction to pumps 4, 5 and 6.

d. SCV 2 & 3 supply suction to pumps 4, 5 and 6, SCV 1 supplies suction to pumps 1, 2 and 3.

Answer: C.14 a.

Reference:

NBSR Operations Training Guide, Figure 3.1.

Question C.015 [1.0 point] (17.0)

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.15 a.

Reference:

NBSR Reactor Operations Training Guide

Section C Facility and Radiation Monitoring Systems Question C.016 [1.0 points, 1/4 each] (18.0)

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.16 a. = 2; b. = 1; c.= 4; d. = 3

Reference:

NBSR Reactor Operations Training Guide, Question C.017 [1.0 point] (19.0)

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.17 d.

Reference:

NBSR 2006 Requailification Examination Question C.018 [1.0 point] (20.0)

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.18 d.

Reference:

NBSR Reactor Operations Training Guide 6.4 RADIATION MONITORING SYSTEMS.

Section C Facility and Radiation Monitoring Systems Question C.019 [1.0 point] (21.0)

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.19 d.

Reference:

NBSR 2006 Requailification Examination Question C.020 [1.0 point] (22.0)

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.20 c.

Reference:

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