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Examination Report No. 50-150/OL-12-01, the Ohio State University
	ML12286A044
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Site:	Ohio State University
Issue date:	10/16/2012
From:	Gregory Bowman; Division of Policy and Rulemaking
To:	Kaufmann A; Ohio State University
	Morlang G
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October 16, 2012 Mr. Andrew Kaufmann, Associate Director OSU Nuclear Reactor Laboratory Ohio State University 142 Hitchcock Hall 2070 Neil Avenue Columbus, OH 43210

SUBJECT:

EXAMINATION REPORT NO. 50-150/OL-12-01, THE OHIO STATE UNIVERSITY

Dear Mr. Kaufmann:

During the week of September 17, 2012, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Ohio State University reactor. The examination was conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2, published in June 2007. Examination questions and preliminary findings were discussed at the conclusion of the examination with those members of your staff identified in the enclosed report.

In accordance with Title 10, Section 2.390 of the Code of Federal 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 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 Public Electronic Reading Room). The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. If you have any questions concerning this examination, please contact Gary Morlang at 301-415-4092 or via email at gary.morlang@nrc.gov.

Sincerely,

/RA/

Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-150

Enclosures:

1. Examination Report No. 50-150/OL-12-01

2. Corrected Written Examination cc w/o enclosures: See next page

October 16, 2012 Mr. Andrew Kaufmann, Associate Director OSU Nuclear Reactor Laboratory Ohio State University 142 Hitchcock Hall 2070 Neil Avenue Columbus, OH 43210

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-150/OL-12-01, THE OHIO STATE UNIVERSITY

Dear Mr. Kaufmann:

During the week of September 17, 2012, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Ohio State University reactor. The examination was conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2, published in June 2007. Examination questions and preliminary findings were discussed at the conclusion of the examination with those members of your staff identified in the enclosed report.

In accordance with Title 10, Section 2.390 of the Code of Federal 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 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 Public Electronic Reading Room). The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. If you have any questions concerning this examination, please contact Gary Morlang at 301-415-4092 or via email at gary.morlang@nrc.gov.

Sincerely,

/RA/

Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-150

Enclosures:

1. Examination Report No. 50-150/OL-12-01

2. Corrected Written Examination cc w/o enclosures: See next page DISTRIBUTION w/ enclosures.:

PUBLIC PROB r/f GBowman Facility File (CRevelle)

ADAMS ACCESSION #: ML OFFICE PROB:CE IOLB:LA PROB:BC NAME GMorlang CRevelle GBowman DATE 10/09/2012 10/15/2012 10/16/2012 OFFICIAL RECORD COPY

The Ohio State University Docket No. 50-150 cc:

Ohio Department of Health ATTN: Radiological Health Program Director 246 North High Street Columbus, OH 43216 Ohio Environmental Protection Agency Division of Planning Environmental Assessment Section P.O. Box 1049 Columbus, OH 43216 Dr. Thomas Blue, Director Nuclear Reactor Laboratory Ohio State University 1298 Kinnear Rd.

Columbus, OH 43210 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

EXAMINATION REPORT NO: 50-150/OL-12-01 FACILITY: The Ohio State University FACILITY DOCKET NO.: 50-150 FACILITY LICENSE NO.: R-75 SUBMITTED BY: __________/RA/_________ _10/09/12_

Gary Morlang, Chief Examiner Date

SUMMARY

During the week of September 17, 2012, the NRC administered an operator licensing examination to one Senior Reactor Operator (SRO) candidate. The candidate passed the examination.

REPORT DETAILS

1. Examiner: Gary Morlang, Chief Examiner

2. Results:

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

3. Exit Meeting:

Andrew Kaufman, The Ohio State University Gary Morlang, NRC, Examiner The NRC Examiner agreed to make the following changes to the written examination:

Question A.11 - Accept both C and D as correct answers Question B.16 - Delete the question due to no correct answer Question B.18 - Accept both C and D as correct answers Question C.12 - Delete the question as the equipment has been removed Enclosure #1

/

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR INITIAL LICENSE EXAMINATION FACILITY: Ohio State University REACTOR TYPE: Pool DATE ADMINISTERED: 9/18/2012 CANDIDATE: Susan White 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 Senior Operator Written Examination With ANSWER KEY OL-12-01 Ohio State University September 18, 2012 Enclosure #2

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

= 1 x 10 seconds 2 (k) 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 )

SDM = =

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 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months after a power increase from 0% to 50%.

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

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

d. 7 to 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months 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 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 rods are, respectively, $4.0, $3.5, and $1.5. The reactor is critical at 5 W after WITHDRAWING the following control rod worths: Shim/Safety1 $3.00, Shim/Safety2 $2.00, and Shim/Safety3 $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 plutoniurm decays to emit neutrons.

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

c. Alpha particles from plutonium 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% k/k. 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 B Normal and Emergency Procedures and Radiological Controls 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/safety 1 UP button and then the licensed operator presses the shim/safety 2 UP button ?

a. Shim/Safety 1 rod drives down.

b. Shim /Safety 1 rod drives down.

c. Nothing, as the rods are mechanically interlocked so that only one button can be pressed at any given time.

d. Shim/Safety 2 rod oscillates, going up, then down, then up, then down,

Section B Normal and Emergency Procedures and Radiological Controls 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 Ohio State reactor facility?

a. The area inside the reactor bay.

b. 250 feet from the center of the reactor.

c. The physical boundary of campus.

d. The reactor building and the area inside the fence surrounding it..

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 B Normal and Emergency Procedures and Radiological Controls 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-call 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 B Normal and Emergency Procedures and Radiological Controls 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 B Normal and Emergency Procedures and Radiological Controls Page 15 QUESTION B.13 [1.0 points]

. Operator Log entries must be initialed by the SRO for:

a. Any unplanned scram

b. Startup after loss of building power.

c. Using the low source bypass

d. All the above.

QUESTION B.14 [1.0 point]

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

a. 70% of full power; 70 °F

b. 80% of full power; 85 °F

c. 90% of full power; 95 °F

d. 95% of full power; 100 °F QUESTION B.15 [1.0 point]

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

a. The experiment contains 4 grains of gun powder.

b. A single movable experiment has an absolute value of reactivity worth of 0.2%. k/k

c. The experiment installed does not interfere with nuclear instrumentation.

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

QUESTION B.16 [1.0 point] DELETED Demineralizer resin may need to be changed when ____?

a. Inlet conductivity is decreasing.

b. Reactor pool water clarity is decreasing.

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

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

Section B Normal and Emergency Procedures and Radiological Controls Page 16 QUESTION B.17 [1.0 point]

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

a. Columbus Fire Department

b. NRC

c. Cincinnati Police Department

d. Davis-Besse Nuclear Power Station 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

b. Control room

c. Room 501 Research Center

d. Radiation Safety Office QUESTION B.19 [1point]

In the event of an emergency at the facility, who does the Emergency Response Team directly report to:

a. Chief, Regional Services

b. Emergency Director

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 Plant and Radiation Monitoring Page 17 Question C.01 [1.0 point]

Which ONE of the following describes a standard fuel element?

a. 19.5% enriched uranium contained within stainless steel plates.

b. 37.5% enriched uranium contained within aluminum plates.

c. 19.5% enriched uranium contained within aluminum plates.

d. 37.5% enriched uranium contained within stainless steel plates.

QUESTION: C.02 [1.0 point]

All positions in the core grid plate are occupied by some type of assembly. This is done so that:

a. there is an even weight distribution on the grid plate.

b. there is no uneven coolant flow distribution through the core.

c. the core is as symmetric as possible to maintain an even reactivity distribution.

d. a predictable control rod worth is maintained.

QUESTION: C.03 [1.0 point]

Which ONE of the following statements is true regarding operation of the neutron source?

a. The neutron source may be moved at any time.

b. The neutron source cannot be moved out of its storage cask while simultaneously withdrawing any control rod.

c. The source is a 5-curie Sb-Be source which provides about 1x107 neutrons/second.

d. When the source is in its fully raised position, it is located near the top of the fuel elements.

Section C Plant and Radiation Monitoring Page 18 QUESTION: C.04 [1.0 point]

Which ONE of the following channels has a signal which will generate a "FAST" scram?

a. Linear Power Monitoring Channel

b. Period Monitoring Channel

c. Period Safety Channel

d. Startup Channel QUESTION: C.05 [1.0 point]

The aluminum shrouds which surround each control rod have holes in the lower sections. The purpose of these holes is to:

a. provide viscous damping during reactor scrams.

b. provide a cooling water path through the shrouds.

c. provide points where a shroud lifting tool can be attached.

d. smooth out the thermal neutron flux distribution at the bottom of the core.

QUESTION: C.06 [ 2.00 points, 0.5 each]

Match the Area Radiation Monitor location listed in Column A with the correct detector listed in Column B. Items listed in Column B may be used more than once or not at all.

Column A Column B

a. Above reactor pool 1. Proportional counter

b. Thermal column and beam ports 2. Ionization Chamber

c. Primary coolant heat exchanger 3. GM detector

d. Water processing system 4. Scintillation detector

Section C Plant and Radiation Monitoring Page 19 QUESTION: C.07 [1.0 point]

The building evacuation system is activated by two switches. The switch located on the slow scram console in the control room only ______________________ while the switch located underneath the wall-mounted telephone in the control room only_____________________.

a. sounds the evacuation horn; turns off all ventilation fans exhausting to the outside of the building.

b. turns off all ventilation fans exhausting to the outside of the building; sounds the evacuation horn.

c. sounds the evacuation horn and turns off all ventilation fans exhausting to the outside of the building; sounds the evacuation horn.

d. sounds the evacuation horn; sounds the evacuation horn and turns off all ventilation fans exhausting to the outside of the building.

QUESTION: C.08 [1.0 point]

Which ONE of the following will prevent the withdrawal of a control rod?

a. Startup source moving out of the core.

b. Movement of fission chamber into the core.

c. Movement of fission chamber out of the core.

d. Green light on in Control Rod Positioning System.

QUESTION: C.09 [1.0 point]

For a control rod, the orange light is ON, the green light is OFF, and the white light is ON. These indicate that:

a. The rod and drive are not in contact, the rod is full out and the drive is full in.

b. The rod and drive are both full out.

c. The rod and drive are both full in.

d. The rod and drive are not in contact, the drive is full out and the rod is full in.

Section C Plant and Radiation Monitoring Page 20 QUESTION: C.10 [1.0 point]

When the building gaseous effluent monitor alarms, which ONE of the following occurs?

a. The reactor scrams.

b. The ventilation exhaust fan stops.

c. The building evacuation horn sounds.

d. No action occurs.

QUESTION: C.11 [2.00 points, 0.5 each]

Match the instrument channel listed in Column A with the correct detector listed in Column B. Items listed in Column B may be used more than once or not at all.

Column A Column B

a. Logarithmic Power 1. Proportional counter

b. Startup 2. Fission chamber

c. Linear power 3. GM detector

d. Power Level Safety 4. Compensated Ion Chamber

5. Uncompensated Ion chamber QUESTION: C.12 [1.0 point] DELETED Input to the servo system is provided by the:

a. Logarithmic Power Channel.

b. Linear Power Channel.

c. Power Level Channel #1.

d. Power Level Channel #2.

Section C Plant and Radiation Monitoring Page 21 QUESTION: C.13 [1.0 point]

Which ONE of the following switch positions will prohibit a startup?

a. Effluent Monitor Compressor On.

b. Period Generator Switch Position Off.

c. Log N Amplifier Calibrate Switch Test.

d. Log Period Amplifier Calibrate Switch Norm.

QUESTION: C.14 [1.0 point]

The reactor is operating at 500 kilowatts, when the SECONDARY coolant pump trips on overload.

Assuming NO OPERATOR ACTION, which ONE of the following trips would most likely cause a reactor scram?

a. High Flux

b. Short Period

c. High Coolant Inlet Temperature

d. High power, No pumps QUESTION: C.15 [1.0 point]

Water from the Makeup Water System is added to the reactor pool:

a. at the suction of the Water Process System pump.

b. at the inlet of the demineralizer in the Water Process System.

c. at the inlet of the ion exchange filters in the Water Process System.

d. at the outlet of the ion exchange filters in the Water Process System.

QUESTION: C.16 [1.0 point]

Which ONE of the following scram functions results in ONLY a slow scram?

a. Reactor fast period.

b. Reactor overpower.

c. Low count rate.

d. Core inlet temperature below setpoint.

Section C Plant and Radiation Monitoring Page 22 QUESTION: C.17 [1.0 point]

The gamma rays incident upon the Startup Channel do not cause a pulse to be counted. Which ONE of the following describes the reason gamma pulses are not counted?

a. The Startup Channel detector has compensating voltage to subtract the gamma pulses from the signal.

b. The design of the detector allows gamma rays to pass through the detector with no interaction.

c. The detector uses a pulse height discriminator, which prevents the smaller gamma pulses from being counted.

d. The number of gamma rays is much smaller than the number of neutrons.

QUESTION: C.18 [1.0 point]

An annunciator lamp switch flashes and an audible signal is emitted to alert the operator to a slow or fast scram condition. Acknowledging the condition will always:

a. silence the alarm and extinguish the light.

b. silence the alarm only if the condition has returned to normal.

c. silence the alarm.

d. extinguish the light.

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.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: Fuel Moderator Temperature Effects A.11 c or d accepted 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

A.17 b.

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.

A.20 a.

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: SAR 3.3.8 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 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months later, DR DR=1.5 Rem* e -0.623*(5)

DR=6.6*10 -2 Rem or ~65 mrem B.05 d.

REF: Emergency Plan B.06 c REF: TS, Section 3.1.1 B.07 a REF: 10 CFR 20 B.08 b REF: TS Section 6.1.3 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.

REF: TS 4.2.2 B.13 d.

REF: OM-08

Section B Normal, Emergency and Radiological Control Procedures Page 26 B.14 c REF: OM-16 B.15 d REF: Tech Specs 3.7.1 B.16 b. Deleted REF: SAR 3.2.4 B.17 a REF: Emergency Plan B.18 c or d accepted per facility comment REF: Emergency Plan B.19 b.

REF: Emergency Plan B.20 b REF: Tech Specs 5.4

Section C: Plant and Rad Monitoring Systems Page 27 C.1 c REF: SAR 3.1.1.2.

k C.2 b REF: SAR 3.1.1.3.

C.3 a REF: SAR 3.3.11.

C.4 c REF: OSU SAR, §§ 3.3.13, 14, 15 & 17 C.5 b REF: SAR 3.1.2.3 C.6 a, 3 b, 3 c, 3 d, 3 REF: SAR 3.7.

C.7 a REF: SAR 3.6.6 C.8 c REF: SAR 3.3.8.3 C.9 b REF: SAR Table 3.1.

C.10 d REF: EP-03.

C.11 a, 4 b, 2 c, 4 d, 5 REF: SAR 3.3.12, 13, 14, 15, 16.

C.12 b Deleted REF: SAR C.13 c REF: Technical Specifications, Section 3.2.3.

C.14 d REF: TS 3.2.3 C.15 d REF: SAR Figure 3.16.

C.16 c REF: SAR Table 3.2.

C.17 c

Section C: Plant and Rad Monitoring Systems Page 28 REF: SAR 3.3.14.

C.18 c REF: SAR 3.6.5.

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