ML101680356

Initial Examination Report No. 50-274/OL-10-02, U.S. Geological Survey Triga Reactor

ML101680356
Person / Time
Site:	U.S. Geological Survey
Issue date:	06/24/2010
From:	Johnny Eads Research and Test Reactors Branch B
To:	Timothy Debey US Dept of Interior, Geological Survey (USGS)
References
50-274/10-002
Download: ML101680356 (39)

Text

June 24, 2010 Mr. Timothy DeBey Reactor Director U.S. Geological Survey Box 25046 - Mail Stop 424 Denver Federal Center Denver, CO 80225

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-274/OL-10-02, U.S. GEOLOGICAL SURVEY TRIGA REACTOR

Dear Mr. DeBey:

During the week of May 24, 2010, the Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your U.S. Geological Survey TRIGA Reactor. The examination was 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 Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-274

Enclosures:

1. Initial Examination Report No. 50-274/OL-10-02

2. Facility Comments with NRC Resolution

3. Corrected Written Exam cc: see next page

ML101680356 NRR-074 OFFICE PROB:CE IOLB:LA E PROB:SC NAME PYoung: CRevelle JEads DATE 06/22/2010 06/22/2010 06/24/2010 C = COVER E = COVER & ENCLOSURE N = NO COPY U.S. Geological Survey Docket No. 50-274 cc:

Mr. Brian Nielsen Environmental Services Manager 480 S. Allison Pkwy.

Lakewood, CO 80226 Mr. Eugene W. Potter State of Colorado Radiation Management Program HMWM-RM-B2 4300 Cherry Creek Drive South Denver, CO 80246 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.: 50-274/OL-10-02 FACILITY DOCKET NO.: 50-274 FACILITY LICENSE NO.: R-113 FACILITY: U.S. Geological Survey TRIGA Reactor EXAMINATION DATES: May 25-26, 2010 SUBMITTED BY: __________________________ _________

Phillip Young, Chief Examiner Date

SUMMARY

On May 25th the NRC administered an operator licensing examination to one Reactor Operator license candidate. The candidate passed all portions of the administered examination.

REPORT DETAILS

1. Examiners: Phillip Young, Chief Examiner, NRC Mike Morlang, Examiner Trainee, NRC

2. Results:

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

3. Exit Meeting:

Phillip Young, NRC, Examiner Timothy DeBey, USGS, Reactor Supervisor Mike Morlang, NRC Examiner Trainee The examiner thanked the facility staff for their support in the administration of the examination.

The examination included with this report has been corrected, per facility comment and examiner review.

ENCLOSURE 1

Facility comments with NRC Resolution Question A.11 Comment: The NRCs answer assumes that removing the source from the core causes a positive reactivity effect from the change in moderator caused by the source removal. In the USGS reactor, the moderator effect is essentially zero. Also, the absorption of neutrons in the source holder plays a factor in the net reactivity effect of removal of the source and this effect varies with power level. The observed effect of removing the source from the core at 5 watts is, for all practical purposes, that power does not change (answer c).

Question A.11 NRC Resolution: Comment accepted. Answer key corrected per facility comment.

Question A.18 Comment: Question is missing the units for the +17.6% value. I believe they should be k/k.

Question A.18 NRC Resolution: Comment noted for future exams.

Question B.5 Comment: The site boundary of the USGS reactor facility is defined in the emergency plan as:

Site boundary. The site boundary is that area within the Denver Federal Center bounded on the north by North Center Avenue, on the east by First Street, on the south by South Center Avenue, and on the west by Second Street. The Nuclear Science Building (Building 15) is the only structure within that area.

The answer given in the answer key for this question is: c. The physical boundary of the Denver Federal Center. The Denver Federal Center is about 500 acres. The most correct answer (although not completely correct) is d. Within the confines of the Building 15.

Question B.5 NRC Resolution: Comment accepted. Answer key corrected per facility comment.

Enclosure 2

Question B.12 Comment: The question asks for the calibration frequency of the linear power channel and the answer key gives the answer as: d. annually The correct answer is: c. semi-annually. (Ref:

USGS Tech Spec 12.e)

Question B.12 NRC Resolution: Comment accepted. Answer key corrected per facility comment.

Question B.13 Comment: The question asks about what items need to be recorded in red ink in the operations logbook. The answer key gives the answer as: c. There are actually two correct answers: b.

and c. All fuel movements need to be recorded in red ink, as specified in the GSTR fuel movement procedure.

Question B.13 NRC Resolution: Comment accepted. Answer key corrected per facility comment.

Question B.19 Comment: This question asks who the Reactor Supervisor reports directly to, in the event of an emergency.

The GSTR Emergency Plan and Procedures state, The Reactor Supervisor or, during his absence, the Senior Reactor Operator-In-Charge is responsible for dealing with any emergencies that arise at the facility. This includes liaison efforts with any personnel (both USGS and outside personnel) who arrive at the facility to assist in controlling the emergency.

Transfer of responsibility during emergency conditions at the facility will be made only when a more senior person arrives at the scene and personally informs the individual in charge that he or she is assuming responsibility.

In addition, the Emergency Plan states, The individual in charge will be responsible for notification of the Nuclear Regulatory Commission, if required. This individual will also notify the Chief of Regional Services of any conditions that might affect any personnel outside the Nuclear Science Building and will request assistance from support organizations, if required.

Protective action decisions will be made by the individual in charge, in consultation with the Health Physicist.

Therefore, the best answer would be: a. Chief, Regional Services, not the answer in the answer key, d. Reactor Health Physicist Question B.19 NRC Resolution: Comment accepted. Answer key corrected per facility comment.

Question C.14 Comment: Question asks about the verification test of a percent power scram and gives the answer as: a. a channel test. The USGS reactor documentation, including license, tech specs and procedures, do not use the terminologies of channel test, channel check, or channel calibration anywhere. Although this terminology is used in new, up-to-date tech specs, those do not currently exist at the USGS reactor Question C.14 NRC Resolution: Comment accepted. Question deleted per facility comment.

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR INITIAL LICENSE EXAMINATION FACILITY: USGS REACTOR TYPE: TRIGA DATE ADMINISTERED: 5/25/2010 CANDIDATE: Karl Frank 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 parentheses for each question. A 70% overall is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

% OF CATEGORY % OF CANDIDATE'S 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 20.00 33.3 C. PLANT AND RADIATION MONITORING SYSTEMS FINAL GRADE

% TOTALS ALL THE WORK DONE ON THIS EXAMINATION IS MY OWN. I HAVE NEITHER GIVEN NOR RECEIVED AID.

CANDIDATE'S SIGNATURE__________________

License Operator Written Examination With ANSWER KEY OL-10-02 USGS MAY 25, 2010 Enclosure 3

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 = UA T ( - )2 P max = * -4 l = 1 x 10 seconds 2 (k)l eff = 0.1 seconds-1 S S CR1 (1 - K eff 1 ) = CR 2 (1 - K eff 2 )

SCR =

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

1 - K eff 0 1 CR1 SUR = 26.06 eff M= M= =

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

P = P0 10 SUR(t) P= P0 (1 - K eff ) l SDM = = l K eff - = +

eff K eff 2 - K eff 1 0.693 ( K eff - 1)

T=

k eff 1 x K eff 2 K eff 6CiE(n)

DR = DR0 e- t DR = 2 2

DR1 d 1 = DR 2 d 2 2

R DR B Rem, Ci B curies, E B Mev, R B 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 EF = 9/5 EC + 32 1 gal (H2O) . 8 lbm EC = 5/9 (EF - 32) cP = 1.0 BTU/hr/lbm/EF cp = 1 cal/sec/gm/EC

Section A L Theory, Thermo & Facility Operating Characteristics Page 1 A.01 a b c d ___ A. 11 a b c d ___

A.02 a b c d ___ A. 12 a b c d ___

A.03 a b c d ___ A.13 a b c d ___

A.04 a b c d ___ A.14 a b c d ___

A.05 a b c d ___ A.15 a b c d ___

A.06 a b c d ___ A.16 a b c d ___

A.07 a b c d ___ A.17 a b c d ___

A.08 a b c d ___ A.18 a b c d ___

A.09 a b c d ___ A.19 a b c d ___

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

CANDIDATE'S SIGNATURE__________________

Section A L Theory, Thermo & Facility Operating Characteristics Page 2 B.01 a b c d ___ B.09 a b c d ___

B.02a 1 2 3 4 B.1 0 a b c d ___

B.02b 1 2 3 4 B.11 a b c d ___

B.02c 1 2 3 4 B.12 a b c d ___

B.02d 1 2 3 4 B.13 a b c d ___

B.03 a b c d ___ B.14 a b c d ___

B.04 a b c d ___ B.15 a b c d ___

B.05 a b c d ___ B.16 a b c d ___

B.06 a b c d ___ B.17 a b c d ___

B.07 a b c d ___ B.18 a b c d ___

B.08 a b c d ___ B.19 a b c d ___

B.20 a b c d ___

CANDIDATE'S SIGNATURE__________________

Section A L Theory, Thermo & Facility Operating Characteristics Page 3 C.01 a b c d ___ C.11 a b c d ___

C.02 a b c d ___ C.12 a b c d ___

C.03 a b c d ___ C.13 a b c d ___

C.04 a b c d ___ C.14 a b c d ___

C.05 a b c d ___ C.15 a b c d ___

C.06 a b c d ___ C.16 a b c d ___

C.07 a(__), b(__),c(__),d(__) C.17 a b c d ___

C.08 a b c d ___ C.18 a b c d ___

C.09 a b c d ___ C.19 a(__),b(__),c(__),d(__)

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

CANDIDATE'S SIGNATURE__________________

Section A L Theory, Thermo & Facility Operating Characteristics Page 4 QUESTION A.01 [1.0 point]

During a reactor startup, criticality occurred at a LOWER ROD HEIGHT than the last startup.

Which ONE of the following reasons could be the cause?

a. Xe135 increased.

b. Fuel temperature increased.

c. Pool temperature increased.

d. Moving an experiment with negative reactivity from the core.

QUESTION A.02 [1.0 point]

Which ONE of the following is the major source of energy (heat) generated after SHUTDOWN?

a. Prompt gamma ray.

b. Fission product decay.

c. Kinetic energy of the fission neutrons.

d. Kinetic energy of the fission fragments.

QUESTION A.03 [1 point]

Which ONE of the following best describes the beta decay (-1) of a nuclide?

a. The atomic mass number unchanged, and the number of protons increases by 1.

b. The atomic mass number unchanged, and the number of protons decreases by 1.

c. The atomic mass number increases by 1, and the number of protons decrease by 1.

d. The atomic mass number increases by 2, and the number of protons increase by 1.

Section A L Theory, Thermo & Facility Operating Characteristics Page 5 QUESTION A.04 [1.0 point]

Which ONE of the following is the stable reactor period which will result in a power rise from 1%

to 100% power in 60 seconds?

a. 6 seconds.

b. 13 seconds.

c. 28 seconds.

d. 80 seconds.

QUESTION A.05 [1.0 point]

Delayed neutrons are produced by:

a. decay of O-16.

b. Photoelectric Effect.

c. decay of fission fragments.

d. directly from the fission process.

QUESTION A.06 [1.0 point]

The FAST FISSION FACTOR is defined as a ratio of:

a. the number of fast neutrons produced by all fission events over the number of fast neutrons produced by thermal fission.

b. the number of fast neutrons produced by fission in a generation over the number of total neutrons produced by fission in the previous generation.

c. the number of fast neutrons produced by U-238 over the number of thermal neutrons absorbed in fuel.

d. the number of neutrons that reach thermal energy over the number of fast neutrons that start to slow down.

Section A L Theory, Thermo & Facility Operating Characteristics Page 6 QUESTION A.07 [1.0 point]

Which ONE of the following is the time period in which the MAXIMUM amount of Xe-135 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 power increase from 0% to 50%.

b. 7 to 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> after a power increase from 50% to 100%.

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

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% power.

QUESTION A.08 [1.0 point]

A reactor has a Keff of 1.1. What are the values of k and ?

a. k = 0.10 and = 0.09

b. k = 0.10 and = 0.10

c. k = 0.90 and = 0.10

d. k = 0.09 and = 0.01 QUESTION A.09 [1.0 point]

The reactor is SHUTDOWN by 5% k/k with the count rate of 100 counts per second (cps).

The Shim rods are withdrawn until the count rate is a steady 2000 cps. What is the value of Keff at this point?

a. 0.952.

b. 0.973.

c. 0.998.

d. 1.050.

Section A L Theory, Thermo & Facility Operating Characteristics Page 7 QUESTION A.10 [1.0 point]

Which ONE of the following is the reason that causes the reactor power to rapidly decrease in the TRIGA fuel due to a rapid power excursion (rapid reactivity change)?

a. By increasing of the reproduction factor.

b. By decreasing of Doppler broadening of U-238.

c. By increasing of the resonance escape probability.

d. By decreasing of the thermal non-leakage probability and fast non-leakage probability.

QUESTION A.11 [1.0 point]

The reactor has been stable at 5 W for about an hour. Removing the source from the core causes reactor power to:

a. increase due to an increase in the amount of moderator.

b. decrease since the reactor is under-moderated.

c. stay the same due to keff being constant.

d. decrease due to fast neutron leakage.

QUESTION A.12 [1.0 point]

Assume that the worths of the Safety, Shim, and Reg rods are, respectively, $4.0, $3.5, and

$1.5. The reactor is critical at 5 W after WITHDRAWING the following control rod worths:

Safety $3.00, Shim $2.00, and Reg $1.20. What is the core excess?

a. -$1.20.

b. $2.20.

c. $2.80.

d. $9.00.

Section A L Theory, Thermo & Facility Operating Characteristics Page 8 QUESTION A.13 [1.0 point]

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

Scattering Cross Section Absorption Cross Section

a. High High

b. Low High

c. High Low

d. Low Low QUESTION A.14 [1.0 point]

The reactor is exactly critical with eff = 0.0075. Which ONE of the following is the MINIMUM reactivity that must be added to produce prompt criticality?

a. Reactivity when Keff equals to 1.0075.

b. Reactivity equals to the eff.

c. Reactivity when the stable reactor period equals to 3 seconds.

d. Reactivity equals to $1.50.

QUESTION A.15 [1.0 point]

How does the reactor startup source function?

a. The polonium decays to emit neutrons.

b. Gamma rays from the core strike beryllium atoms that emit neutrons.

c. Alpha particles from polonium strike beryllium atoms that emit neutrons.

d. Alpha particles from americium strike beryllium atoms that emit neutrons.

Section A L Theory, Thermo & Facility Operating Characteristics Page 9 QUESTION A.16 [1.0 point]

Which ONE of the following is the MOST affected factor in the six factor formula when a poison in the control rods is changed from BORON (B) to CADMIUM (Cd)?

a. Fast fission factor.

b. Reproduction factor.

c. Thermal utilization factor.

d. Fast non leakage probability.

QUESTION A.17 [1.0 point]

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

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

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

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

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

QUESTION A.18 [1.0 point]

Keff for the reactor is 0.85. If you place an experiment worth +17.6% into the core, what will the new Keff be?

a. 0.995

b. 0.9995

c. 1.005

d. 1.05

Section A L Theory, Thermo & Facility Operating Characteristics Page 10 QUESTION A.19 [1.0 point]

Which of the following does NOT affect the Effective Multiplication Factor (Keff)?

a. The moderator-to-fuel ratio.

b. The physical dimensions of the core.

c. The strength of installed neutron sources.

d. The current time in core life.

QUESTION A.20 [1.0 point]

The term PROMPT JUMP refers to

a. the instantaneous change in power due to withdrawal of a control rod.

b. a reactor which has attained criticality on prompt neutrons alone.

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

d. a negative reactivity insertion which is less than eff.

• • • • • • • • • • • • • • • • • End of Section A ********************************

Section C Facility and Radiation Monitoring Systems Page 11 QUESTION B.01 [1.0 point]

The radiation from an unshielded Co-60 source is 500 mrem/hr. What thickness of lead shielding will be needed to lower the radiation level to 5 mrem/hr? The HVL (half-value-layer) for lead is 6.5 mm.

a. 26 mm.

b. 33 mm.

c. 38 mm.

d. 44 mm.

QUESTION B.02 [1.0 point, 0.25 each]

Match the Federal regulation in column A with the correct area covered in column B.

Column A Column B

a. 10 CFR 20. 1. Domestic licensing of production and utilization facilities.

b. 10 CFR 50. 2. Operators licenses.

c. 10 CFR 55. 3. Domestic licensing of special nuclear material

d. 10 CFR 70. 4. Protection against radiation.

QUESTION B.03 [1.0 point]

What will happen if an operator trainee presses the shim 1 UP button and then the licensed operator presses the shim 1 DOWN button such that both buttons are depressed at the same time?

a. Shim 1 rod drives down.

b. Shim 1 rod slowly drifts down.

c. Shim 1 rod stops and stays at its existing position.

d. Shim 1 rod oscillates, going up, then down, then up, then down,

Section C Facility and Radiation Monitoring Systems Page 12 QUESTION B.04 [1.0 point]

A radioactive source reads 35 Rem/hr on contact. Five hours later, the same source reads 1.5 Rem/hr.

What will the sample read in another five hours?

a. 55 mrem.

b. 65 mrem.

c. 75 mrem.

d. 750 mrem.

QUESTION B.5 [1.0 point]

Which ONE of the following is the definition of the site boundary for the USGS reactor facility?

a. The area inside the reactor bay.

b. 250 feet from the center of the reactor.

c. The physical boundary of Denver Federal Center.

d. Within the confines of the building 15.

QUESTION B.06 [1.0 point]

During a reactor startup, the reactor operator calculates that the maximum excess reactivity for reference core conditions is 5.2% k/k. For this excess reactivity, which ONE of the following is the best action?

a. Continue to operate because the excess reactivity is within TS limit.

b. Increase power to 100 W and verify the excess reactivity again.

c. Shutdown the reactor; immediately report the result to the supervisor due to excess being above TS limit.

d Continue operation, but immediately report the result to the supervisor since the excess reactivity is exceeding TS limit.

Section C Facility and Radiation Monitoring Systems Page 13 QUESTION B.07 [1.0 point]

An area in which radiation levels could result in an individual receiving a dose equivalent of 20 mRem/hr can be considered as a:

a. Radiation area.

b. Vital Area.

c. High Radiation Area.

d. Very High Radiation Area.

QUESTION B.08 [1.0 point]

What are the MINIMUM staffing requirements for reactor operations?

a. 1 RO on console and 1 person in the facility who can be contacted within 5 minutes.

b. 1 RO on console, 1 person in the facility, and 1 on-duty SRO .

c. 2 RO on console and 1 person in the facility.

d. 1 SRO on console and the Reactor Director.

QUESTION B.09 [1.0 point]

The Total Effective Dose Equivalent (TEDE) is defined as the sum of the deep-dose equivalent and the committed effective dose equivalent. The deep-dose equivalent is related to:

a. the dose to organs or tissues.

b. the external exposure to the skin or an extremity.

c. the external exposure to the lens of the eye.

d. the external whole-body exposure.

Section C Facility and Radiation Monitoring Systems Page 14 QUESTION B.10 [1.0 point]

Which ONE of the following radioisotopes will decay with the SHORTEST half-life?

a. Al28

b. N16

c. Ar41

d. Xe135 QUESTION B.11 [1.0 point]

Two sheets of 1/4 inch thick lead reduce a radiation beam from 200 mR/hr to 100 mR/hr at one foot.

Which ONE of the following will be the radiation measurement at one foot if you add another two (for a total of 4) 1/4 inch lead sheets?

a. 20 mR/hr.

b. 35 mR/hr.

c. 50 mR/hr.

d. 70 mR/hr.

QUESTION B.12 [1.0 point]

The linear power level channel shall be calibrated at least _______ by thermal power calibration.

a. monthly

b. quarterly

c. semi-annually

d. annually

Section C Facility and Radiation Monitoring Systems Page 15 QUESTION B.13 [1.0 points]

. Operator Log entries must be made in red ink for

a. Failure of primary water pump.

b. Removal of fuel element from core.

c. Reactor scram due to electrical transient.

d. Removal of neutron source from core.

QUESTION B.14 [1.0 point]

A reactor power calibration must be performed at an indicated power level between _______________ and the typical starting water temperature is ___________.?

a. 750 kW and 900 kW; 17 to 25 °C

b. 800 kW and 950 kW; 15 to 20 °C

c. 500 kW and 900 kW; 15 to 25 °C

d. 800 kW and 1000 kW; 17 to 20 °C QUESTION B.15 [1.0 point]

Which ONE of the following types of experiments shall NOT be irradiated at the USGS reactor?

a. The experiment contains 5 milligrams of explosive materials.

b. The movable experiment has a reactivity worth of - $0.10.

c. The experiment has an I-131 inventory of 0.3 curies.

d. The experiment contains a corrosive material in a single capsule.

QUESTION B.16 [1.0 point]

Demineralizer resin may need to be changed when ____?

a. Inlet conductivity is decreasing.

b. Reactor tank water clarity is decreasing.

c. The resin has been in use for 2 years.

d. Increasing amounts of dirt are on the reactor tank water surface.

Section C Facility and Radiation Monitoring Systems Page 16 QUESTION B.17 [1.0 point]

Which choice best describes the non-USGS emergency response organizations that are available, by agreement, to provide assistance for reactor emergencies?

a. St. Anthonys Hospital, FPS (Federal Protective Serv), GSA

b. FPS (Federal Protective Serv), GSA, West Metro Fire & Rescue

c. West Metro Fire & Rescue, Lakewood Police, JeffCo sheriffs dept

d. Rocky Flats RAP team, FPS (Federal Protective Serv), West Metro Fire & Rescue QUESTION B.18 [1.0 point]

Which choice describes the best locations where radiological instrumentation is available for responding to an emergency in the reactor room? (Assume instruments in reactor room are not usable.)

a. Rx Supervisors office, Counting room (157), Regional Safety Office

b. INAA lab (Room 153), Argon mass spec bay, Control room, Reactor HP office

c. GSA hazmat coordinators office, Bldg 21 hall cabinet, Regional Safety office

d. Counting room (157), Bldg 21 hall cabinet, reactor hallway, Regional Safety Office QUESTION B.19 [1point]

In the event of an emergency at the facility, who does the Reactor Supervisor directly report to:

a. Chief, Regional Services

b. Fire Chief

c. Senior Reactor Operator In Charge

d. Reactor Health Physicis QUESTION B.20 [1point]

All fuel elements or fueled devices in storage in a safe geometry shall have a Keff of less than ___.

a. 1.0

b. 0.9

c. 0.8

d. 0.7

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • End of Section B ********************************

Section C Facility and Radiation Monitoring Systems Page 17 QUESTION C.01 [1.0 points]

How many personnel are required to operate the overhead crane in the reactor room?

a. 1

b. 2

c. 1 in the reactor room and 1 in the control room

d. 4 QUESTION C.02 [1.0 point]

Which piece of equipment is NOT required for the stack gas analysis?

a. Multichannel analyzer.

b. Calibrated oscilloscope.

c. Germanium Detector.

d. Marinelli beaker.

QUESTION C.03 [1.0 point]

Which procedure is NOT required by Technical Specifications?

a. Moving Reactor Fuel.

b. Reactor Startup and Shutdown.

c. Demineralizer Resin Replacement.

d. Control Rod Removal and Replacement.

QUESTION C.04 [1.0 point]

Which of the following is NOT an interlock required for steady state operation?

a. No rod withdrawal if power is < 1e-7%

b. No operation unless the Continuous Air Monitor is operating.

c. No simultaneous manual withdrawal of 2 rods.

d. The Transient Rod cylinder must be full down to apply air pressure.

Section C Facility and Radiation Monitoring Systems Page 18 QUESTION C.05 [1.0 point]

The Technical Specification limits on exhausting gas from the reactor room are:

a. In Table 2 of the safety analysis report.

b. Discharge must be above the facility roof and sampled continuously.

c. Discharge limited to 4.8e-6 uCi/ml average radionuclide concentration.

d. Discharge must be at least 21 above ground level and analyzed quarterly.

QUESTION C.06 [1.0 point]

Which choice best describes the conditions that must be met for the reactor to be considered shutdown?

a. Operator logged off, key out and locked up, rods down

b. No samples being loaded or unloaded, key off, rods down.

c. Key out and with an operator, rods down, no fuel handling in progress.

d. No rod magnet current, no control rod maintenance, no fuel movement.

QUESTION C.07 [1.0 points, 0.25 each]

Match each monitor and instrument (channel) listed in column A with a specific purpose in column B.

Items in column B is to be used only once.

Column A Column B

a. Log Channel 1. Survey a laboratory.

b. Percent Power Channel. 2. Provide automatic control of the regulating rod

c. Rod Control. 3. Provide a high power scram

d. Portable Monitor. 4. Provide a reactor period.

Section C Facility and Radiation Monitoring Systems Page 19 QUESTION C.08 [1.0 point]

The reactor operator is measuring the reactivity worth of the Shim rod. Before withdrawing the Shim rod to the new height, the reactor operator needs to stabilize the reactor power at:

a. 2 W for delayed neutrons to reach equilibrium.

b. 2 W for thermal neutron to reach equilibrium.

c. 100 W for delayed neutrons to reach equilibrium.

d. 100 W for thermal neutrons to reach equilibrium.

QUESTION C.09 [1.0 point, 0.25 each]

Match the items in the left column with their Technical Specification Limit.

a. TNT in a pressure rated container (tested). 1. 1.5 curies

b. Dynamite in a pressure rated container (non-tested) 2. >25 milligrams

c. Maximum Iodine 131-135 in an experiment. 3. 5 millicuries

d. Maximum Strontium 90 inventory 4. <25 milligrams QUESTION C.10 [1.0 point]

Select the best completion for the following sentence, If more than one element is to be added to the core or changes to the core configuration involving multiple elements are to be made,

a. an estimated reactivity change shall be computed.

b. control rod calibrations must be performed after the changes.

c. a written sequence of moves will be developed prior to the fuel movement.

d. the movements must be approved, in writing, by the Reactor Supervisor prior to the fuel movement.

Section C Facility and Radiation Monitoring Systems Page 20 QUESTION C.11 [1.0 point]

What unique concern might you have about moving fuel directly from the core into storage rack HEX-1?

a. The HEX-1 rack is old and has a lot of oxidation built up on its surfaces, possibly causing elements to get stuck.

b. The HEX-1 rack is located near the pool water surface so that only elements with low decay heat should be placed there.

c. The HEX-1 rack is located near the pump tube and may cause high gamma levels in the pump tube even with the reactor shut down.

d. The HEX-1 rack should only have stainless steel clad elements stored in it so caution is needed to keep all aluminum clad elements out of it.

QUESTION C.12 [1.0 point]

Which one of the following correctly describes the operation of a Thermocouple? It is

a. a bi-metallic strip which winds/unwinds due to different thermal expansion constants for the two metals, one end is fixed and the other moves a lever proportional to the temperature change.

b. a junction of two dissimilar metals, generating a potential (voltage) proportional to temperature changes.

c. a precision wound resistor, placed in a Wheatstone bridge, the resistance of the resistor varies proportionally to temperature changes.

d. a liquid filled container which expands and contracts proportional to temperature changes, one part of which is connected to a lever.

QUESTION C.13 [1.0 point]

The reactor tank full of water gets circulated through the purification system approximately once every:

a. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

b. 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

c. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

d. 38 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br />.

Section C Facility and Radiation Monitoring Systems Page 21 QUESTION C.14 [1.0 point] Question deleted per facility comment.

During a startup, the reactor operator performs the Percent Power scram to verify whether the scram channel is operable. This action is considered to be:

a. a channel test.

b. a channel check.

c. a channel calibration.

d. a channel verification.

QUESTION C.15 [1 point]

Which detector provides a signal to the wide range channel and the period channel?

a. uncompensated ion chamber

b. compensated ion chamber

c. gamma ion chamber

d. fission chamber QUESTION C.16 [1 point]

The AUTO controller system uses a signal from:

a. NM1000

b. NP1000

c. NPP1000

d. Compensated Ion Chamber QUESTION C.17 [1 point]

Which of the following will NOT activate the fire alarm system?

a. smoke detectors

b. heat detectors

c. infrared sensors

d. radiation area monitors

Section C Facility and Radiation Monitoring Systems Page 22 QUESTION C.18 [1 point]

Which of the following will NOT activate the building 15 evacuation alarm?

a. High Pool Level Alarm

b. Fire Alarm

c. Continuous air monitor alarm

d. High Radiation Alarm QUESTION C.19 [1.0 points, 0.25 each]

Match each monitor and instrument (channel) listed in column A with a specific purpose in column B.

Items in column B is to be used only once.

Column A Column B

a. Linear Channel. 1. Provide a wide range of power on a linear meter.

b. Area Radiation Monitor. 2. Detect radioisotopes released due to fuel failure..

c. Pool Temperature. 3. Monitor radiation level in the reactor top.

d. Air Particulate Monitor. 4. Protect the demineralizer resins.

QUESTION C.20 [1.0 points]

Which one of the following is NOT considered an experimental facility?

a. Rotary specimen rack.

b. Horizontal tubes.

c. Central Thimble.

d. Pneumatic transfer system.

Section A L Theory, Thermo & Facility Operating Characteristics Page 23 A.01 d REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 8.4, page 8-9.

A.02 b REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 3.3.2, page 3-19.

A.03 a REF: Chart of the Nuclides A.04 b REF: P = P0 et/T --> T= t/Ln(P/ P0 )

t= 60/Ln(100 ); t = 13 sec.

A.05 c REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 3.2.

A.06 a REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 3.3.1, page 3-16.

A.07 d REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 8.4, page 8-9.

A.08 a REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 3.3.4.

A.09 c REF: Keff1=1/1- 1 Keff1 =1/(1-(-.05)) -->Keff1= 0.952, Count1*(1-Keff1) = Count2*(1-Keff2) Count1*(1-0.952) = Count2*(1-Keff2) 100*(1-0.952) = 2000(1- Keff2); Keff2 = 0.998 A.10 d REF: General Atomics TRIGA Fuel Moderator Temperature Effects A.11 a: Changed from a to c per facility comment.

REF: NRC Standard question.

A.12 c REF: Total worth=$4+$3.5+$1.5=$9; Reactivity at 5 W= $3.0 + $2.0 + $1.2 = $6.2 Core excess = Total worth - Reactivity at 5 W

$9.0-$6.2 = $2.8 A.13 c REF: Standard NRC Question A.14 b REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 4.2.

Section A L Theory, Thermo & Facility Operating Characteristics Page 24 A.15 d REF: USGS Requalification Training A.16 c REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 4.5.

A.17 b.

REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1988, § A.18 b.

REF Burn, R., Introduction to Nuclear Reactor Operations, © 1988, § SDM = (1-keff)/keff = (1-0.85)/0.85 = 0.15/0.85 = 0.1765, or a reactivity worth () of -0.1765.

Adding + 0.176 reactivity will result in a SDM of 0.1765 - 0.1760 = 0.0005. Keff = 1/(1+SDM) =

1/(1 + 0.0005) = 0.9995 A.19 c.

REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1982, § 3.3.4, p. 3-21.

A.20 a.

REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1988, § 4.7, p. 4-21

Section B Normal, Emergency and Radiological Control Procedures Page 25 B.01 d REF: DR = DR*e -X HVL ( =6.5 mm) means the original intensity will reduce by half when a lead sheet of 6.5 mm is inserted. Find if the HVL is given as follows: 1 = 2* e -*6.5 ; = 0.10664 Find X: 5 mrem/hr = 500 mrem/hr* e -0.10664*X ; X= 43.2 mm B.02 a(4) b(1) c(2) d(3)

REF: 10 CFR B.03 c REF: Requalification Training B.04 b REF DR = DR*e -t 1.5 rem/hr =35 rem/hr* e -(5hr)

Ln(1.5/35) = -*5 --> =0.623; solve for another 5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> later, DR DR=1.5 Rem* e -0.623*(5)

-2 DR=6.6*10 Rem or ~65 mrem B.05 c: Changed from c to d per facility comment.

REF: Emergency Plan B.06 c REF: TS, Section D, Reactor Core B.07 a REF: 10 CFR 20 B.08 b REF: Requalification Training B.09 d.

REF: 10 CFR 20.1201 B.10 b.

REF: Chart of the Nuclides B.11 c REF: A 1/2 thickness is 2 sheets. Add another 2 sheets, a radiation level will reduce by another 1/2, or 50 mR/hr B.12 d: Changed from d to c per facility comment.

REF: TS E.12, Control and Safety Systems B.13 c: Changed to c or b per facility comment.

REF: Requalification Training

Section B Normal, Emergency and Radiological Control Procedures Page 26 B.14 a REF: Requalification Training B.15 d REF: Tech Specs I.5 B.16 b.

REF: Resin Procedure B.17 b REF: Emergency Plan B.18 b REF: Emergency Plan B.19 d.: Changed from d to a per facility comment.

REF: Emergency Procedure Section 7 B.20 c:

REF: Tech Specs G.1

Section C Facility and Radiation Monitoring Systems Page 27 C.01 b REF: Overhead Crane Procedure C.02 b REF: Stack Gas Analysis Procedure C.03 c REF: Technical Specifications H.3 C.04 b .

REF: Technical Specifications Table II C.05 d REF: Technical Specifications Section B C.06 c REF: Technical Specifications A.1 C.07 a(4) b(3) c(2) d(1)

REF: Requalification Training C.08 a REF: Control Rod Calibration Procedure C.09 a(2), b(4), c(1), d(3)

REF: Technical SpecificationsSection I C.10 c.

REF: Fuel Movement Procedure C.11 c REF: Fuel Movement Procedure C.12 b REF: NRC Standard Question C.13 b REF: SAR Chapter 4 C.14 a Question deleted per facility comment.

REF: NRC Standard Question C.15 d REF: SAR Chapter 6 C.16 a REF: SAR Chapter 6 C.17 c REF: Emergency Procedure Section 7

Section C Facility and Radiation Monitoring Systems Page 28 C.18 a REF: Emergency Procedure Section 7 C.19 a(1) b(3) c(4) d(2)

REF: Requalification Training C.20 b REF: Technical Specifications A.7