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Initial Examination Report No. 50-184/OL-06-02, National Institute of Standards and Technology
	ML062580436
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Site:	National Bureau of Standards Reactor
Issue date:	09/22/2006
From:	Johnny Eads; NRC/NRR/ADRA/DPR/PRTB
To:	Richards W; US Dept of Commerce, National Institute of Standards & Technology (NIST)
	Young P, NRC/NRR/ADRA/DPR, 415-4094
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September 22, 2006 Dr. Wade J. Richards NIST Center for Neutron Research National Institute of Standards and Technology 100 Bureau Road Mail Stop 85601 Gaithersburg, MD 20899

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-184/OL-06-02, NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY

Dear Dr. Richards:

During the week of August 28, 2006, the NRC administered an operator licensing examination at your Center for Neutron Research. The examination was conducted in accordance with NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1.

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 Phillip T. Young at 301-415-4094 or via Internet e-mail at pty@nrc.gov.

Sincerely,

/RA/

Johnny Eads, 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-06-02

2. Facility Comments with NRC resolution

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

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

Montgomery County Executive County Office Building Rockville, MD 20858 Director Department of State Planning 301 West Preston Street Baltimore, MD 21201 Director Department of Natural Resources Power Plant Siting Program Energy and Coastal Zone Administration Tawes State Office Building Annapolis, MD 21401 Honorable Michael L. Subin Montgomery County Council Stella B. Werner Council Office Building Rockville, MD 20850 Dr. William Vernetson Director of Nuclear Facilities Department of Nuclear Engineering Sciences University of Florida Gainesville, FL 32611-8300

September 22, 2006 Dr. Wade J. Richards NIST Center for Neutron Research National Institute of Standards and Technology 100 Bureau Road Mail Stop 85601 Gaithersburg, MD 20899

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-184/OL-06-02, NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY

Dear Dr. Richards:

During the week of August 28, 2006, the NRC administered an operator licensing examination at your Center for Neutron Research. The examination was conducted in accordance with NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1.

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 Phillip T. Young at 301-415-4094 or via Internet e-mail at pty@nrc.gov.

Sincerely,

/RA/

Johnny Eads, 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. No. 50-184/OL-06-02

2. Facility Comments with NRC resolution

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

PUBLIC RNRP\R&TR r/f JEads AAdams Facility File (EBarnhill) O-6 F-2 ADAMS ACCESSION #: ML062580436 TEMPLATE #:NRR-074 OFFICE PRTB:CE IOLB:LA PRTB:SC NAME PYoung:tls* EBarnhill* JEads:tls*

DATE 09/19/2006 09/21/2006 09/22/2006 OFFICIAL RECORD COPY

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-184/OL-06-02 FACILITY DOCKET NO.: 50-184 FACILITY LICENSE NO.: TR-5 FACILITY: NIST EXAMINATION DATES: 08/31/2006 and 09/01/2006 EXAMINER: Phillip T. Young, Chief Examiner SUBMITTED BY: /RA/ 09/12/2006 Phillip T. Young, Chief Examiner Date

SUMMARY

During the week of August 28, 2006, NRC administered an Operator Licensing examination to two Senior Reactor Operators (SRO). Both SRO candidates passed the examinations.

REPORT DETAILS

1. Examiners: Phillip T. Young, Chief Examiner

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 0/0 2/0 2/0 Operating Tests 0/0 2/0 2/0 Overall 0/0 2/0 2/0

2. Exit Meeting:

Phillip T. Young, NRC Chief Examiner Dr. Wade Richards Chief, Operations and Engineering Tom Meyers, Deputy for Operations Tawfik Raby, NIST fellow The examiner thanked the facility for their support in conducting the examinations. The examiner did not have any generic observations to discuss with the facility.

ENCLOSURE 1

Facility Comments Regarding NRC Exam Administered on August 31, 2006 NONE ENCLOSURE 2

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION (Examination with Answer Key}

FACILITY: NIST REACTOR TYPE: TEST DATE ADMINISTERED: 08/31/2006 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 20.00 33.3 B. Normal and Emergency Operating Procedures and Radiological Controls 18.00 33.3 C. Facility and Radiation Monitoring Systems 58.00 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

Section A L Theory, Thermo & Fac. Operating Characteristics page 7 of 25 Question: A.001 [1.0 point] (1.0)

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.001 b.

Reference Standard NRC Reactor Theory Question Question: A.002 [1.0 point] (2.0)

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.002 c

Reference:

Lamarsh, J.R., Introduction to Nuclear Engineering, Addison-Wesley Publishing, Reading, Massachusetts, 1983. § 7.1, p. 289 Question: A.003 [1.0 point] (3.0)

The reactor is shutdown by 0.05 K/K, this would correspond to Keff of:

a. 0.9995.

b. 0.9524.

c. 0.7750.

d. 0.0500.

Answer: A.003 b.

Reference:

Lamarsh, J.R., Introduction to Nuclear Engineering, Addison-Wesley Publishing, Reading, Massachusetts, 1983. § 4,1,

p. 102 & § 7.1, p. 282. p=(k-1)/k; p= -0.05; -0.05k = k-1; 1 = k-(-0.05k) =

k(1+0.05); k=1/1.05; k=0.9524

Section A. Rx Theory, Thermodynamics &Facility Operating Characteristics Page 8 of 25 Question: A.004 [1.0 point] (4.0)

Which statement best describes Xe-135 behavior following a Rx 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.004 d.

Reference:

Standard NRC Reactor Theory Question Question: A.005 [1.0 point] (5.0)

An initial count rate of 100 is doubled five times during startup. Assuming an initial Keff = 0.950, what is the new Keff?

a. 0.957

b. 0.979

c. 0.988

d. 0.998 Answer: A.005 d.

Reference:

CR1/CR2 = (1 - Keff2)/(1 - Keff1) 1/32 (1 - 0.95) = 1 - Keff2 1 - 0.05/32 = Keff2 Keff2 = 0.9984 Question: A.006 [1.0 point] (6.0)

Which ONE of the following describes "EXCESS REACTIVITY"?

a. Extra reactivity into the core due to the presence of the source neutrons.

b. A measure of the resultant reactivity if all of the control elements were withdrawn.

c. The combined reactivity worth of control rods and other poisons needed to keep the reactor shutdown.

d. The maximum reactivity insertion with the reactor shutdown with control rods fully inserted under peak Xenon conditions.

Answer: A.006 b.

Reference:

Standard NRC Reactor Theory Question

Section A. Rx Theory, Thermodynamics &Facility Operating Characteristics Page 9 of 25 Question: A.007 [1.0 point] (7.0)

If reactor power is increasing by a decade every minute, it has a period of:

a. 13 sec

b. 26 sec

c. 52 sec

d. 65 sec Answer: A.007 b

Reference:

Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida, 1991, § 5.18, p. 234.

Question: A.008 [1.0 point] (8.0)

Which ONE of the following conditions would increase shutdown margin?

a. An experiment which added positive reactivity.

b. Depletion of the burnable poison added to the uranium fuel.

c. Depletion of uranium fuel.

d. Decreasing fuel temperature.

Answer: A.008 c.

Reference:

Adding negative reactivity increases the shutdown margin.

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

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.009 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

Section A. Rx Theory, Thermodynamics &Facility Operating Characteristics Page 10 of 25 Question: A.010 [1.0 point] (10.0)

The fuel temperature coefficient of reactivity is -1.25x10-4 K/K/EC. When a control rod with an average rod worth of 0.1 % K/K/inch is withdrawn 10 inches, reactor power increases and becomes stable at a higher level. At this point, the fuel temperature has:

a. increased by 80EC

b. decreased by 80EC

c. increased by 8EC

d. decreased by 8EC Answer: A.010 a.

Reference:

Lamarsh, Introduction to Nuclear Engineering, 2nd Edition, Page 306 Reactivity added by control rod = +(0.001 k/k/inch)(10 inches) = 0.01 k/k.

Fuel temperature change = -Reactivity added by rod / fuel temperature coefficient Fuel temperature change = (-0.01 k/k) / (-1.25x10-4 k/k/EC) = 80EC.

Question: A.011 [1.0 point] (11.0)

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.011 a.

Reference:

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

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 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months after a startup to 100% power

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

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

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

Answer: A.012 d.

Reference:

Section A. Rx Theory, Thermodynamics &Facility Operating Characteristics Page 11 of 25 Question: A.013 [1.0 point] (13.0)

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.013 a.

Reference:

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

Which factor in the six factor formula is represented by the ratio:

number of neutrons that reach thermal energy number of neutrons that start to slow down

a. fast non-leakage probability (Lf)

b. resonance escape probability (p)

c. reproduction factor ()

d. thermal utilization factor (f)

Answer: A.014 b.

Reference:

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

Which ONE of the following is true concerning the differences between prompt and delayed neutrons?

a. Prompt neutrons account for less than 1% of the neutron population while delayed neutrons account for approximately 99% of the neutron population.

b. Prompt neutrons are released during fast fissions while delayed neutrons are released during thermal fissions.

c. Prompt neutrons are released during the fission process while delayed neutrons are released during the decay process.

d. Prompt neutrons are the dominating factor in determining the reactor period while delayed neutrons have little effect on the reactor period.

Answer: A.015 c.

Reference:

Question: A.016 [1.0 point] (16.0)

Section A. Rx Theory, Thermodynamics &Facility Operating Characteristics Page 12 of 25 Which condition below describes a critical reactor?

a. K = 1, K/K = 1

b. K = 1, K/K = 0

c. K = 0, K/K = 1

d. K = 0, K/K = 0 Answer: A.016 b.

Reference:

Question: A.017 [1.0 point] (17.0)

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

a. 2.5 x 1011 fissions/cm/sec.

b. 2.5 x 1013 fissions/cm/sec.

c. 2.5 x 1011 fissions/cm3/sec.

d. 2.5 x 1013 fissions/cm3/sec.

Answer: A. 17 c.

Reference:

Standard EQB question. R = Ø f = (2.5 x 1012) x 0.1 = 2.5 x 1011 Question: A.018 [1.0 point] (18.0)

The term "Prompt Critical" refers to:

a. the instantaneous jump in power due to a rod withdrawal

b. a reactor which is supercritical using only prompt neutrons

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

d. a reactivity insertion which is less than eff Answer: A.018 b.

Reference:

Lamarsh, Introduction to Nuclear Engineering, 1975, Page 250

Section A. Rx Theory, Thermodynamics &Facility Operating Characteristics Page 13 of 25 Question: A.019 [1.0 point] (19.0)

Which ONE of the following describes the difference between reflectors and moderators?

a. Reflectors decrease core leakage while moderators thermalize neutrons

b. Reflectors shield against neutrons while moderators decrease core leakage

c. Reflectors decrease thermal leakage while moderators decrease fast leakage

d. Reflectors thermalize neutrons while moderators decrease core leakage Answer: A.019 a.

Reference:

Lamarsh, Introduction to Nuclear Engineering, 1975, Pages 57, 214 Question: A.020 [1.0 point] (20.0)

Which ONE of the following statements describes the difference between Differential (DRW) and Integral (IRW) rod worth curves?

a. DRW relates the worth of the rod per increment of movement to rod position. IRW relates the total reactivity added by the rod to the rod position.

b. DRW relates the time rate of reactivity change to rod position. IRW relates the total reactivity in the core to the time rate of reactivity change.

c. IRW relates the worth of the rod per increment of movement to rod position. DRW relates the total reactivity added by the rod to the rod position.

d. IRW is the slope of the DRW at a given rod position Answer: A.020 a.

Reference:

Lamarsh, Introduction to Nuclear Engineering, 1975, Page 270

Section B Normal/Emergency Procedures & Radiological Controls Page 14 of 25 Question: B.001 [1.0 point] (1.0)

Which ONE of the following is the LOWEST level of NIST management who may authorize reactor startup (to previous shim position) following a scram, where the cause of the scram remains unknown?

a. Reactor Operator

b. Senior Reactor Operator

c. Reactor Supervisor

d. Deputy Chief Engineer Answer: B.001 b.

Reference:

O.I. 1.1B (Checklist B) step I.B.

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

According to Emergency Instruction 1.2, 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.002 b.

Reference:

E.I.1.1 page 1, E.I.1.2 Question: B.003 [1.0 point] (3.0)

During Startup to full power, per procedure (O.P. 01) you are required to stop and take data at the 100 kilowatt, 1 megawatt, 5 megawatt and 10 megawatt levels. Which ONE by procedure requires you to hold the power level for an hour?

a. 100 kilowatt

b. 1 megawatt

c. 5 megawatt

d. 10 megawatt Answer: B.003 d.

Reference:

O.P. 1.1 § III steps 12, 13, and 14.

Section B Normal/Emergency Procedures & Radiological Controls Page 15 of 25 Question: B.004 [2.0 points, 1/2 point each] (5.0)

For Research and Test reactors we primarily worry about two isotopes N16 and Ar41. Identify the approximate half-life and gamma energy for each. (Each item has only one answer.)

Isotope Radiological Parameters

a. Ar41 half-life 1) 1.8 sec 2) 1.8 min 3) 1.8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 4) 1.8 day 41

b. Ar gamma energy 1) 10 KeV 2) 100 KeV 3) 1 MeV 4) 10 MeV

c. N16 half-life 1) 7 sec 2) 7 min 3) 7 hour8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months 4) 7 day

d. N16 gamma energy 1) 6 kev 2) 60 keV 3) 600 keV 4) 6 Mev Answer: B.004 a. = 3; b. = 3; c. = 1; d. = 4

Reference:

Technical Specifications § 4.0 (1) & (2), 3.3 (2)(b) and 3.4 Bases Question: B.005 [1.0 point] (6.0)

You use a Geiger-Müller detector at the same distance from two point sources having the same curie strength. Source As gammas have an energy of 1.0 MeV, while Source Bs gammas have an energy of 2.0 MeV. Which ONE of the following would you expect for the readings due to each source?

a. The reading from source B is four times that of source A.

b. The reading from source B is twice that of source A.

c. Both readings are the same.

d. The reading from source B is half that of source A.

Answer: B.005 c.

Reference:

Geiger-Müller detector output is independent of incident energy.

Question: B.006 [1.0 point] (7.0)

Approximately how many half-lives does it take to reduce radiation from an isotope by a factor of 1000?

a. 5

b. 10

c. 15

d. 20 Answer: B.006 b.

Reference:

Rewrite of NBSR Requalification Examination question January, 2000.

Section B Normal/Emergency Procedures & Radiological Controls Page 16 of 25 Question: B.007 [1.0 point] (8.0)

Rescue personnel, are authorized to receive a pre-established radiation exposure WITHOUT Emergency Director (ED) approval in order to save someone's life. What is this limit?

a. 5 Rem

b. 25 Rem

c. 50 Rem

d. 75 Rem Answer: B.007 b.

Reference:

Emergency Instructions Manual, E.I. 1.5, "General Information", Page 5 of 5 Question: B.008 [1.0 point] (9.0)

Which ONE of the following is the definition for Annual Limit on Intake (ALI)? A 10CFR20 derived limit based on

a. the concentration of a radio-nuclide in air which, if inhaled by an adult worker for a year, results in a total effective dose equivalent of 100 millirem.

b. a Committed Effective Dose Equivalent of 5 Rems whole body or 50 Rems to any individual organ, for the amount of radioactive material inhaled or ingested in a year by an adult worker.

c. the effluent concentration of a radio-nuclide in air which, if inhaled continuously over a year, would result in a total effective dose equivalent of 50 millirem for noble gases.

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

Answer: B.008 b.

Reference:

10CFR20

Section B Normal/Emergency Procedures & Radiological Controls Page 17 of 25 Question: B.009 [1.0 point] (10.0)

O.I. 6.4 NBSR Spent Fuel Cask Loading and Shipping specifies the closest a fueled section is allowed to be raised when loading a spent fuel cask as 48 inches. Given that a thumb rule for gamma attenuation is that 2 feet is equivalent to a tenth thickness, radiation from the fuel should be reduced by a factor of at least

a. 1/10th

b. 1/20th

c. 1/100th

d. 1/1000th Answer: B.009 c.

Reference:

Standard NRC question Question: B.010 [1.0 point] (11.0)

While operating one of the shim arms falls to its lower stop. Per Annunciator Procedure 0.3 Stuck or Faulty Operation of Shim Arms you should

a. maintain the reactor as is (subcritical) until Reactor Supervisor directs corrective action.

b. continue to operate if able to latch and shim out the fallen shim arm.

c. continue to operate using the remaining shim arms to stay critical.

d. shutdown the reactor.

Answer: B.010 d.

Reference:

Annunciator Procedures, A.P. 0.4.

Question: B.011 [1.0 point] {12.0}

The emergency plan allows the operator to take action which deviates from emergency procedures during an emergency. Which ONE of the following is the minimum level of staff who may authorize this action?

a. Reactor Operator

b. Senior Reactor Operator

c. Emergency Director

d. Emergency Coordinator Answer: B.011 c.

Reference:

Emergency Instructions Introduction, ¶ 2.

Section B Normal/Emergency Procedures & Radiological Controls Page 18 of 25 Question: B.012 [1.0 point] (13.0)

Which of the following radioisotopes is considered a fission product?

a. N16

b. Ar41

c. H3

d. I135 Answer: B.012 d.

Reference:

Standard NRC question Question: B.013 [1.0 point] (14.0)

The reactor is considered Shutdown if it contains less than

a. 2.2 lbm of U235

b. 2.2 Kg of U235

c. 10 lbm of U235

d. 10 Kg of U235 Answer: B.013 b.

Reference:

Technical Specification 1.6 Question: B.014 [1.0 point] (15.0)

During Reactor Startup, per SOP 0.1, the minimum allowable period allowed is

a. 10 seconds

b. 20 seconds

c. 30 seconds

d. 56 seconds Answer: B.014 b.

Reference:

Standard Operating Instructions O.I.1.1, Reactor Startup: § II.C.

Section B Normal/Emergency Procedures & Radiological Controls Page 19 of 25 Question: B.015 [2.0 points, 0.5 each] (17.0)

Identify the source (Irradiation of Air, Coolant (D2O) or Fission Product (FP)) for each of the radioisotopes listed below.

a. Xe135

b. Ar41

c. N16

d. H3 Answer: B.015 a. = FP; b. = Air; c. = D2O; d. = D2O

Reference:

Standard NRC Question Question: B.016 [1.0 point] (18.0)

A Radiation Work Permit (RWP) has been written to perform a non-repetitive task on potentially contaminated equipment. How long will this RWP remain in effect?

a. Until the job is completed.

b. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or until the end of the current shift.

c. A maximum of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

d. Indefinitely, if reviewed daily by Health Physics.

Answer: B.016 a.

Reference:

Health Physics Procedures, H.P. 2.4, "Radiation Work Permit (RWP), Page 1 of 2

Question: B.017 [2.0 points, 0.5 each] (20.0)

Match the 10CFR55 requirements for an active operator license in column A with the appropriate time periods in column B.

Column A (License requirement) Column B (years)

a. Renewal of license 1

b. Medical Examination 2

c. Requalification Written Examination 3

d. Requalification Operating Test 4 5

6 Answer: B.017 a. = 6; b. = 2; c. = 2; d. = 1

Reference:

10 CFR 55.xx

Section C Facility and Radiation Monitoring Systems Page 20 of 25 Question: C.001 [1.0 point] (1.0)

Which ONE of the following reactor instrumentation channels WILL NOT cause a reactor rundown, prior to activating a reactor scram?

a. Nuclear Power Channels

b. Nuclear intermediate channel (Log-N)

c. Reactor Primary Outlet Flow

d. Reactor Vessel Level Answer: C.001 c.

Reference:

TS 2.2 Limiting Safety System Setting - Specification Question: C.002 [2.0 points, 1/2 point each] (3.0)

Identify whether each of the listed signals will cause a Scram (S), a Major Scram (MS) or may cause either (E) type.

a. High flux level (2 of 3 or 1 of 2 logic only)

b. High activity effluent air exhaust

c. Low Reactor Vessel D2O Level.

d. Manual Pushbuttons in the control room.

Answer: C.002 a. = S; b. = MS; c. = S; d. = E

Reference:

T.S. § 3.4 Question: C.003 [2.0 points, 1/2 point each] (5.0)

Identify the valves listed below A 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.003 a. = MO; b. = MO; c. = AO; d. = MO

Reference:

NBSR Operations Training Guide, § 2.2.4 and Drawing 2.1

Section C Facility and Radiation Monitoring Systems Page 21 of 25 Question: C.004 [1.0 point] (6.0)

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.004 a.

Reference:

NBSR Training Manual, Figure 3.1.

Question: C.005 [1.0 point] (7.0)

During a reactor startup, the 123 Strainer Inlet Isolation valve SCV-200 is inadvertantly left closed. As the startup progresses, the reactor receives a rundown signal, the signal was due to

a. low secondary flow

b. low thermal shield flow

c. high inlet temperature

d. high outlet temperature Answer: C.005 d.

Reference:

NIST SAR Sections 5.2.2.7.1 Strainer & 5.2.4.1 Removal of Heat from the Fuel Question: C.006 [1.0 point] (8.0)

Which ONE of the following is the material used as a NEUTRON POISON in the safety-shim arms?

a. Erbium

b. Cadmium

c. Aluminum

d. Boron Answer: C.006 b.

Reference:

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

Section C Facility and Radiation Monitoring Systems Page 22 of 25 Question: C.007 [1.0 point] (9.0)

Which ONE of the following correctly describes where Critical Panel 1 (CP-1) receives power from?

a. Directly from MCCA-7

b. Directly from the 20 kVA uninterruptible power supplies (UPS)

c. Directly from either Scott Transformer T9 or T10.

d. Directly from the battery Answer: C.007 c.

Reference:

NBSR Reactor Operations Training Guide, § 5.0 NBSR Electrical Systems Question: C.008 [1.0 point] (10.0)

Reactor level is increasing above 168 inches. Which ONE of the following is the AUTOMATIC reactor scram which will occur?

a. High reactor D2O level.

b. High flux on NC-6, NC-7 or NC-8.

c. Low reactor D2O level.

d. High Reactor T Answer: C.008 c.

Reference:

Annunicator Procedures AN.3.1 Hi Reactor D2O level Question: C.009 [1.0 point] (11.0)

Which ONE of the following is the actual method that negative building pressure is maintained following a containment building isolation and normal ventilation shutdown due to high radiation? (Assume AC power is available and no operator actions, and the containment building pressure is being maintained by the emergency exhaust system.)

a. automatic fan cycling on and off to maintain a pressure of -0.25".

b. manual fan cycling on and off to maintain a pressure of -0.25".

c. automatic fan cycling on and off to maintain a pressure of -0.1".

d. manual fan cycling on and off to maintain a pressure of -0.1".

Answer: C.009 a.

Reference:

NBSR Training Guide, § 4.10.3, Ventilation System Under accident conditions.

Section C Facility and Radiation Monitoring Systems Page 23 of 25 Question: C.010 [2.0 points, 1/2 each] (13.0)

Match the Storage Pool cooling system components with their primary responsibiities.

a. Suspended Solids 1. Pre and Post Filters

b. Dissolved Solids 2. Ultraviolet Treatment Unit

c. Kill Biological Impurities 3. Collection Basin

d. Floating Detritus (Mosquito Larvae, dust etc.) 4. HOH Ion Exchanger Answer: C.010 a. = 1; b. = 4; c. = 2; d. = 3

Reference:

NBSR Training Guide, figure 4.10.

Question: C.011 [1.0 point] (14)

What type of detector does the T3 channel use?

a. Ion chamber

b. Geiger Counter

c. Scintillation Detector

d. Proportional Counter Answer: C.011 a.

Reference:

NBSR Training Guide, § 6.4.7.

Question: C.012 [1.0 point] (15.0)

In order to detect neutrons the Nuclear Instrumentation ion chambers are coated with 96%

enriched

a. Be10

b. Be11

c. B10

d. B11 Answer: C.012 c.

Reference:

NBSR Training Guide, § 6.2.3 and 6.2.4.

Section C Facility and Radiation Monitoring Systems Page 24 of 25 QUESTION DELETED - DIAGRAM NOT INCLUDED IN EXAMINATION PACKAGE Question: C.013 [1.0 point, 1/4 point each] (16.0)

Using the simplified diagram of the pneumatic tube (rabbit) system provided, identify the position of valves A through D (Open or Closed), on a sample INSERTION.

a. A

b. B

c. C

d. D Answer: C.013 a. = Closed; b. = Open; c. = Open; d. = Closed

Reference:

NBSR Reactor Operations Training Guide, Figure 8.3 Question: C.014 [1.0 point] (17.0)

Which ONE of the following is the gas used to move the samples in the Rabbit systems?

a. He

b. Air

c. CO2

d. N2 Answer: C.014 c.

Reference:

NBSR Operations Training Guide, § 8.2.5 Question: C.015 [1.0 point] (18.0)

Which ONE of the following is the purpose of the Bismuth shield within the Thermal Column?

Reduce _____ within the graphite region of the thermal column.

a. gamma radiation intensity

b. Intermediate neutron flux

c. Fast neutron flux

d. Thermal neutron flux Answer: C.015 a.

Reference:

NBSR Operations Training Guide, § 8.2.4.

Section C Facility and Radiation Monitoring Systems Page 25 of 25 Question: C.016 [1.0 point] {19.0}

Which ONE of the following core components bear all impact loads associated with the safety-shims?

a. Thermal Shield

b. Upper grid plate

c. Biological Shield

d. Lower grid plate Answer: C.016 c.

Reference:

NBSR Operations Training Guide, § 1.3.5 Question: C.017 [1.0 point] {20.0}

If a Secondary cooling pump trips off due to an overload, prior to restarting you must

a. place the control room switch to off to reset the pump electrically.

b. place the control room switch to the on position (the pump resets itself electrically).

c. have an auxiliary operator push a reset button on the controller locally at the pump.

d. have an auxiliary operator take the local, auto switch to local to reset the pump, then return the switch to auto.

Answer: C.017 a.

Reference:

NBSR Training Manual, § 3.2.1.

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