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Kansas State University, Examination Report 50-188/OL-18-02
	ML19074A070
Person / Time
Site:	Kansas State University
Issue date:	03/18/2019
From:	Anthony Mendiola; Research and Test Reactors Oversight Projects Branch
To:	Cebula A; Kansas State University
	Chen Q
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March 18, 2019 Dr. Alan Cebula, Reactor Manager Kansas State University 3002 Rathbone Hall Manhattan, KS 66506

SUBJECT:

EXAMINATION REPORT NO. 50-188/OL-18-02, KANSAS STATE UNIVERSITY

Dear Dr. Cebula:

During the weeks of July 9, 2018 and February 25, 2019, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Kansas State University nuclear reactor facility. The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors,"

Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with Title 10 of the Code of Federal Regulations, Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Ms. Michele DeSouza at (301) 415-0747 or via internet e-mail Michele.DeSouza@nrc.gov.

Sincerely,

/RA/

Anthony J. Mendiola, Chief Research and Test Reactors Oversight Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 50-188

Enclosures:

1. Examination Report No. 50-188/OL-18-02

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

ML19074A070 NRR-079 OFFICE NRR/DLP/PROB/CE NRR/DLP/IOLB/OLA NRR/DLP/PROB/BC NAME MDeSouza QLChen AMendiola DATE 03/08/2019 03/15/2019 03/18/2019 Kansas State University Docket No. 50-188 cc:

Office of the Governor State of Kansas 300 SW 10th Avenue, Suite 212 S Topeka, KS 66612-1590 Kim Steves Radiation Control Section Kansas Department of Health and Environment 1000 SW Jackson, Suite 330 Topeka, KS 66612-1365 Mayor of Manhattan City Hall 1101 Poyntz Avenue Manhattan, KS 66502 Robert Seymour Reactor Supervisor Kansas State University 117 Ward Hall Manhattan, KS 66506 Test, Research and Training Reactor Newsletter Attention: Amber Johnson Dept. of Materials Science and Engineering University of Maryland 4418 Stadium Drive College Park, MD 20742-2115

U.S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-188/OL-18-02 FACILITY DOCKET NO.: 50-188 FACILITY LICENSE NO.: R-88 FACILITY: TRIGA EXAMINATION DATES: July 9-11, 2018 and February 28, 2019 SUBMITTED BY: Michele DeSouza 03/08/2019 Michele DeSouza, Chief Examiner Date

SUMMARY

During the weeks of July 9, 2018 and February 25, 2019 the NRC administered an operator licensing examination to one Senior Reactor Operator Instant (SROI) and two Reactor Operator (RO) candidates. The SROI and RO candidates passed all applicable portions of the examination(s).

REPORT DETAILS

1. Examiner: Michele DeSouza, Chief Examiner, NRC

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 2/0 1/0 3/0 Operating Tests 2/0 1/0 3/0 Overall 2/0 1/0 3/0

3. Exit Meeting #1:

Michele DeSouza, Chief Examiner, NRC Max Nager, Reactor Supervisor, KSU Dr. Alan Cebula, Reactor Manager, KSU Ken Shultis, Professor, KSU Jeremy Roberts, Assistant Professor Bill Dunn, Department Head and Reactor Safeguards Committee, KSU Ronald Bridges, Radiation Safety Officer, KSU Jeremy Schmit, Assistant Professor, KSU Brett DePaola, Head Physics Professor, KSU Exit Meeting #2:

Michele DeSouza, Chief Examiner, NRC Robert Seymour, Reactor Supervisor, KSU Dr. Alan Cebula, Reactor Manager, KSU ENCLOSURE 1

Per discussion with the facility, prior to administration of the written examination, adjustments were accepted. During the week of July 9, 2018 examinations, operational issues with the KSU reactor caused the suspension and postponement of the candidates operational examinations. During the week of February 25, 2019 the candidates operational examinations were conducted. Upon completion of the examination, the NRC Examiner met with facility staff representatives to discuss the results. NRC Inspector Follow-Up Item (IFI) was identified for Pulse instrumentation operational issues. A facility training issue was identified as the majority of candidates could not identify the location of the pool level float. At the conclusion of the meeting, the NRC examiner thanked the facility for their support in the administration of the examination.

U.S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: Kansas State University REACTOR TYPE: TRIGA DATE ADMINISTERED: 07/09/2018 CANDIDATE: _______________________

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the Answer sheet provided. Attach all Answer sheets to the examination. Point values are indicated in parentheses for each question. A 70% in each category 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. FACILITY AND RADIATION MONITORING SYSTEMS 60.00 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature 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 your 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.

Category A - Reactor Theory, Thermodynamics, & Facility Operating Characteristics ANSWER SHEET Multiple Choice (Circle or X your choice)

If you change your Answer, write your selection in the blank.

A01 a b c d ___

A02 a b c d ___

A03 a ___ b ___ c ___ d ___ (0.25 each)

A04 a b c d ___

A05 a b c d ___

A06 a b c d ___

A07 a b c d ___

A08 a b c d ___

A09 a b c d ___

A10 a b c d ___

A11 a b c d ___

A12 a b c d ___

A13 a b c d ___

A14 a b c d ___

A15 a b c d ___

A16 a b c d ___

A17 a ___ b ___ c ___ d ___ (0.5 each)

A18 a b c d ___

A19 a b c d ___

(***** END OF CATEGORY A *****)

Category B - Normal/Emergency Operating Procedures and Radiological Controls ANSWER SHEET Multiple Choice (Circle or X your choice)

If you change your Answer, write your selection in the blank.

B01 a b c d ___

B02 a b c d ___

B03 a b c d ___

B04 a b c d ___

B05 a b c d ___

B06 a b c d ___

B07 a b c d ___

B08 a b c d ___

B09 a b c d ___

B10 a b c d ___

B11 a b c d ___

B12 a b c d ___

B13 a b c d ___

B14 a b c d ___

B15 a b c d ___

B16 a b c d ___

B17 a b c d ___

B18 a ___ b ___ c ___ d ___ (0.50 each)

B19 a b c d ___

(***** END OF CATEGORY B *****)

Category C - Facility and Radiation Monitoring Systems ANSWER SHEET Multiple Choice (Circle or X your choice)

If you change your Answer, write your selection in the blank.

C01 a ___ b ___ c ___ d ___ (0.50 each)

C02 a b c d ___

C03 a b c d ___

C04 a b c d ___

C05 a b c d ___

C06 a b c d ___

C07 a b c d ___

C08 a ___ b ___ c ___ (0.33 each)

C09 a b c d ___

C10 a b c d ___

C11 a b c d ___

C12 a b c d ___

C13 a b c d ___

C14 a b c d ___

C15 a b c d ___

C16 a b c d ___

C17 a b c d ___

C18 a b c d ___

C19 a b c d ___

(***** END OF CATEGORY C *****)

(********** END OF EXAMINATION **********)

EQUATION SHEET

( )2 eff = 0.1sec 1 Q = m cP T = m H =UAT Pmax =

(2 )

t P = P0 e S S SCR = * =1x104 sec 1 K eff eff +

SUR = 26 .06

( ) (

CR1 1 K eff1 = CR2 1 K eff 2 ) CR1 ( 1 ) = CR2 ( 2 )

(1 ) M=

1

= 2 CR P = P0 10SUR(t )

P= P0 1 K eff CR1 1 K eff1 1 K eff

M= SDM = =

1 K eff 2 K eff

0.693 K eff 2 K eff1

+ T1 =

eff + 2 K eff1 K eff 2 K eff 1

= DR = DR0 e t 2 DR1 d1 = DR2 d 2 2

K eff 6 Ci E (n) ( 2 )2 = (1 )2 DR =

R2 Peak2 Peak1 DR - Rem, Ci - curies, E - Mev, R - feet 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lb 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 1 BTU = 778 ft-lb °F = 9/5 °C + 32 1 gal (H2O) 8 lb °C = 5/9 (°F - 32) cP = 1.0 BTU/hr/lb/°F cp = 1 cal/sec/gm/°C

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.01 [1.0 point]

Which ONE of the following is the number of neutrons in a tritium nucleus (1T3 or 1 H3 )?

a. 1 b.

b. 2

c. 3

d. 4 QUESTION A.02 [1.0 point]

Which ONE of the following nuclides will cause a fast neutron to lose its most energy per collision?

a. H-1

b. B-10

c. C-12

d. U-235 QUESTION A.03 [1.0 point, 0.25 each]

Match the term in Column A with its correct definition in Column B.

Column A Column B

a. Prompt Neutron 1. Neutron in equilibrium with its surroundings

b. Fast Neutron 2. Neutron born directly from fission

c. Thermal Neutron 3. Neutron born due to decay of a fission product

d. Delayed Neutron 4. Neutron at an energy level greater than its surroundings QUESTION A.04 [1.0 point]

Which ONE of the following factors in the six factor formula is the MOST affected by the MODERATOR?

a. Fast fission factor

b. Reproduction factor

c. Thermal utilization factor

d. Resonance escape probability

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.05 [1.0 point]

Which ONE of the following physical characteristics of the TRIGA fuel is the main contributor for the prompt negative temperature coefficient?

a. As the fuel heats up the resonance absorption peaks broaden and increases the likelihood of neutron absorption in U-238

b. As the fuel heats up a rapid increase in moderator temperature occurs through conduction and convection heat transfer mechanisms which adds negative reactivity

c. As the fuel heats up fission product poisons (e.g., Xe) increase in concentration within the fuel matrix and add negative reactivity via neutron absorption

d. As the fuel heats up the oscillating hydrogen in the ZrH lattice imparts energy to a thermal neutron, thereby increasing its mean free path and probability of escape QUESTION A.06 [1.0 point]

A reactor is subcritical with Keff of 0.955. Which ONE of the following is the MINIMUM reactivity (K/K) that must be added to PROMPT criticality? Given eff=0.007

a. 0.0045

b. 0.0047

c. 0.0540

d. 0.1000 QUESTION A.07 [1.0 point]

The reactor is on a CONSTANT positive period. Which ONE of the following power changes will take the longest time to complete?

a. 5%, from 95% to 100%

b. 10%, from 80% to 90%

c. 15%, from 15% to 30%

d. 20%, from 60% to 80%

QUESTION A.08 [1.0 point]

Which ONE of the following describes the term PROMPT JUMP?

a. A reactor is subcritical at negative 80-second period

b. A reactor has attained criticality on prompt neutrons alone

c. The instantaneous change in power level due to inserting a control rod

d. The instantaneous change in power level due to withdrawing a control rod

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.09 [1.0 point]

Reactor is increasing power from 10 W to 10 kW in the Steady State Mode. Which ONE of the following best describes the values of Keff and during the power increment?

a. Keff < 1 and 0< < 1

b. Keff = 1 and = 0

c. Keff > 1 and 0 < < -eff

d. Keff > 1 and -eff < < 1 QUESTION A.10 [1.0 point]

Delayed neutrons are produced by:

a. decay of Ar-41

b. Photoelectric Effect

c. decay of fission fragments

d. directly from the fission process QUESTION A.11 [1.0 point]

The MAJOR source of energy released during fission comes from:

a. Fission neutrons

b. Fission fragments

c. Prompt gamma rays

d. Fission product gamma decay QUESTION A.12 [1.0 point]

A few minutes following a reactor scram at full power, the reactor period has stabilized and the power level is decreasing at a CONSTANT rate. Reactor power is decreasing, what will it be one minute later from 10 kW?

a. 0.2 kW

b. 4.7 kW

c. 7.5 kW

d. 21 kW

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.13 [1.0 point]

Two common FISSION PRODUCTS that have especially large neutron capture cross sections and play a significant role in reactor physics. One is Sm-149 and the other is:

a. B-10

b. Ar-41

c. Xe-135

d. Cs-137 QUESTION A.14 [1.0 point]

Which ONE of the following correctly describes the SIX- FACTOR FORMULA?

a. K = Keff

the utilization factor

b. K = Keff

the total leakage probability

c. Keff = K

the total non-leakage probability

d. Keff = K * (the resonance escape probability

the reproduction factor)

QUESTION A.15 [1.0 point]

In a just critical reactor, the reactor operator immediately inserts a rabbit of $0.50 reactivity worth into the core. This insertion will cause:

Given:

T: reactor period, *: Prompt neutron lifetime; : reactivity insertion; : beta fraction; -eff:

delayed neutron precursor constant

a. A sudden drop in delayed neutrons

b. A number of prompt neutrons is twice as much as a number of delayed neutrons

c. The resultant period is a function of the prompt neutron lifetime (T=*/)

d. The resultant period is a function of the delayed neutron precursors =

eff

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.16 [1.0 point]

Which factor, in the six-factor formula, is represented by the following ratio?

of neutrons that reach thermal energy total # of neutrons before thermalization

a. Fast fission factor

b. Reproduction factor

c. Thermal utilization factor

d. Resonance escape probability QUESTION A.17 [2.0 points, 0.5 each]

Given a mother isotope of 35Br87 identify each of the daughter isotopes as a result of: , +, -,

, or n? (Answers may be used once, more than once or not at all).

a. 33As 83

b. 34Se 87

c. 35Br 86

d. 36Kr 87 QUESTION A.18 [1.0 point]

You are the reactor operator performing two pulsing operations. The first pulse has a reactivity worth of $1.20 which results in a peak power of 200 MW. If the second pulse has a reactivity worth of $2.00, the corresponding peak power is:

Given:

=0.0070

a. 1000 MW

b. 1750 MW

c. 2500 MW

d. 5000 MW

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.19 [1.0 point]

Reactor A with a Keff of 0.1 and reactor B with a Keff of 0.8, Keff is increased by 0.1 for each reactor. The amount of reactivity added in reactor A is ______ in reactor B for the same increment.

a. less than

b. same

c. eight times

d. thirty-six times

(***** END OF CATEGORY A *****)

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.01 [1.0 point]

In the event of a suspected fuel leak, which ONE of the following nuclides would most likely be found in a Continuous Air Monitor?

a. Ar-41

b. Kr-85

c. N-16

d. Co-60 QUESTION B.02 [1.0 point]

You plan to perform a pulse. Per KSU Technical Specifications, The MAXIMUM rod drive positioned for reactivity insertion (upon withdrawal) is _____.

a. $1.5

b. $2.0

c. $3.0

d. $4.0 QUESTION B.03 [1.0 point]

The reactor room shall contain a minimum free volume of 144,000 cubic feet. This is an example of:

a. Design Features

b. Surveillance Requirements

c. Limiting Conditions for Operation (LCO)

d. Limiting Safety System Setting (LSSS)

QUESTION B.04 [1.0 point]

A significant loss of water occurs in the reactor pool during a rupture of the pool wall. Per SAR-Chapter 13, which ONE of the following is most likely the greatest concern as a result of this event?

a. Zirconium-Hydrides interact with oxygen in air, releasing explosive hydrogen gas due to TRIGA fuel overheat

b. Cladding rupture, fission products release

c. Groundwater contamination to the surrounding water table

d. Increased personnel exposure due to higher amounts of radiation

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.05 [1.0 point]

Which ONE of the following modifications would be considered a 50.59 and the KSU Reactor Facility must file a request to NRC for change? The facility plans to:

a. Replace an identical NPP-1000

b. Change a control rod worth calibration from stop watch to computer

c. Replace a fission chamber with a compensated ion chamber for the Wide Range Log Channel

d. Measure a control rod drop time with new technique QUESTION B.06 [1.0 point]

Each fuel experiment, except for a standard TRIGA instrumented element, shall be limited such that the total radioactivity inventory of iodine isotopes 131 through 135 is no greater than

a. 1 millicuries

b. 5 millicuries

c. 10 millicuries

d. 50 millicuries QUESTION B.07 [1.0 point]

You perform a fuel element inspection. In measuring the lateral bend, you find the bend of one fuel element exceeds the original bend by 0.135 inches. For this measurement, you will:

a. continue the fuel inspection because this bend is within TS limit

b. continue the fuel inspection because the Technical Specifications require the elongation measurement only

c. stop the fuel inspection; you immediately report the result to the supervisor because it is considered a damaged fuel element

d. stop the fuel inspection, you immediately report the result to the U.S. NRC since it is a reportable occurrence

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.08 [1.0 point]

Which ONE of the following requires the NRC APPROVAL for changes?

a. Revise the Procedure 10 - Fuel Element Inspection

b. Change a frequency of the requalification written examination from once per year to twice per year

c. Delete one of the procedures listed in the KSU Test and Maintenance Procedures

d. Reduce a minimum of the Reactor Safeguards Committee from seven to five members QUESTION B.09 [1.0 point]

Which ONE of the following surveillances is classified as a Channel Test?

a. During performance of the daily checklist, you compare the prestart readings of the radiation area monitors to the previous day readings

b. During performance of the daily checklist, you press the scram button to verify a scram on the safety system channel

c. Adjustment of the wide range linear channel in accordance with recent data collected during a reactor power calibration

d. You expose a detector to a check source to verify that it responds QUESTION B.10 [1.0 point]

Which ONE of the following materials shall NOT be irradiated at KSU?

a. Any corrosive material

b. Any short half-life material

c. Any explosive material

d. A moveable experiment with $1.50 worth QUESTION B.11 [1.0 point]

Per SOP 27, which ONE of the following is a MINIMUM staffing requirement during the fuel movement?

a. 2 trainees in the reactor bay + 1 RO at console

b. 1 RO at console + 2 trainees in the reactor bay + 1 SRO on call

c. 1 RO at console + 1 SRO and 1 trainee in the reactor bay

d. 1 SRO at console + 1 RO and 1 trainee in the reactor bay

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.12 [1.0 point]

A radioactive source reads 2 Rem/hr on contact. Five hours later, the same source reads 1.0 Rem/hr. How long is the time for the source to decay from a reading of 2 Rem/hr to 20 mRem/hr?

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

b. 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months

c. 33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months

d. 41 hours4.74537e-4 days 0.0114 hours 6.779101e-5 weeks 1.56005e-5 months QUESTION B.13 [1.0 point]

What is your dose rate at 1 foot away from the source, if you are receiving 250 mR/hr at 3 feet away from the source?

a. 2.25 R/hr

b. 2.85 R/hr

c. 3.05 R/hr

d. 3.25 R/hr QUESTION B.14 [1.0 point]

The radiation from an unshielded source is 1 rem/hr. When you insert 60 mm thickness of lead sheet, the radiation level reduces to 250 mrem/hr. What is the half-value-layer of lead? (HVL:

thickness of lead required so that the original intensity will be reduced by half)?

a. 10 mm

b. 20 mm

c. 30 mm

d. 40 mm QUESTION B. 15 [1.0 point]

Which ONE of the following federal regulations establish procedures and criteria for the issuance of licenses to Reactor Operators and Senior Reactor Operators?

a. 10 CFR 19

b. 10 CFR 20

c. 10 CFR 50

d. 10 CFR 55

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.16 [1.0 point]

Which ONE of the listed radioisotopes produces the highest ionizing energy gamma?

a. H3

b. N16

c. Ar41

d. U235 QUESTION B.17 [1.0 point]

Assume that there is no leak from outside of the demineralizer tank. You use a survey instrument with a window probe to measure the dose rate from the demineralizer tank.

Compare to the reading with a window CLOSED, the reading with a window OPEN will :

a. increase, because it can receive an additional alpha radiation from (Al-27) (n,), (Na-24) reaction

b. remain the same, because the Quality Factors for gamma and beta radiation are the same

c. increase, because the Quality Factor for beta and alpha is greater than for gamma

d. remain the same, because the survey instrument would not be detecting beta and alpha radiation from the tank QUESTION B.18 [2.0 points, 0.50 each]

Match each of the Technical Specification Limits in column A with its corresponding value in column B. (Each limit has only one answer, values in Column B can be used once, more than once or not at all.)

Column A Column B (limit shall not exceed)

a. Maximum excess reactivity 1. $0.25

b. Maximum individual experiment worth 2. $0.50

c. Minimum Shutdown Margin 3. $2.00

d. Maximum Reactivity Insertion 4. $3.00 in Pulse Mode

5. $4.00

6. $5.00

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.19 [1.0 point]

A radiation survey of an area reveals a general radiation reading of 10 mRem/hr. However, a small section of pipe (point source) reads 100 mRem/hr at one foot. Which ONE of the following is the posting requirement for the area, in accordance with 10CFR20? (2.54cm=1inch)

a. CAUTION - RADIATION AREA

b. CAUTION - HIGH RADIATION AREA

c. CAUTION - RADIOACTIVE MATERIAL

d. CAUTION - AIRBORNE RADIOACTIVITY AREA

(***** End of Category B *****)

Category C: Facility and Radiation Monitoring Systems QUESTION C.01 [2.0 points, 0.50 each]

Reactor is at 100 kW. Match the input signals listed in column A with the reactor AUTOMATIC responses listed in column B. (Items in column B may be used more than once or not at all.)

Column A Column B

a. Loss of NPP-1000 High Voltage 1. Just indication ONLY

b. Exhaust fan turned OFF by operator 2. Alarm ONLY

c. Pool water conductivity = 0.5 µmho/cm 3. Interlock

d. Perform a pulse with regulating rod full out 4. Scram QUESTION C.02 [1.0 point]

The air to the piston of the Transient Rod mechanism is controlled by a _________ solenoid valve mounted below the support structure.

a. one-way

b. two- way

c. three- way

d. four- way QUESTION C.03 [1.0 point]

Which ONE of the following is NOT a basic function of the secondary automatic control system?

a. Maintain the primary water at a set temperature

b. Control the cooling tower fan speed to maintain secondary water temperature within a set range

c. Prevent cooling water freeze-up during cold weather operations

d. Control the primary pressure during reactor operations QUESTION C.04 [1.0 point]

The MAIN purpose to measure the pressure drop across the filter of the water clean up system is to determine whether:

a. the filter is clogging

b. the demineralizer is clogging

c. the primary pump motor is overheated

d. the heat exchanger is clogging

Category C: Facility and Radiation Monitoring Systems QUESTION C.05 [1.0 point]

The MAIN purpose for placing a Geiger-Mueller detector near the demineralizer and cartridge filter is to detect a present of _____ in the primary water.

a. N-16

b. A-41

c. Tritium

d. Fission Products QUESTION C.06 [1.0 point]

The Annual Power Level Calibration for NPP-1000 is performed at 100 KW/ hour and the initial temperature of 20 °C. After 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months run, the temperature reaches 26 °C. After obtaining the calibration data, which ONE of the following is a correct method for power adjustment? You should: Given pool constant = 0.0526 °C per kWh

a. raise the Uncompensated Ion Chamber position to obtain the true power

b. lower the Uncompensated Ion Chamber position to obtain the true power

c. adjust the gain of NPP-1000 Channel to obtain the true power

d. No adjustment of detector is required because the actual power and indicated power are within the range QUESTION C.07 [1.0 point]

What is the MAIN purpose of the dashpot installed at the bottom of the barrel?

a. Prevent structure damage to the barrel

b. Reduce bottoming impact during a scram

c. Increase the rod scram time for the rod drop test

d. Increase the rod speed during an initial withdrawal

Category C: Facility and Radiation Monitoring Systems QUESTION C.08 [1.0 point, 0.33 each]

Use the following diagram of the control rod. Match the three limit switches listed in Column A to the appropriate labels in Column B?

Column A Column B

a. Magnet Down 1.

b. Rod Down 2.

c. Magnet Up 3.

Category C: Facility and Radiation Monitoring Systems QUESTION C.09 [1.0 point]

Attached is the KSU Cooling System Layout. Which ONE of the following labels is indicated a location of the N-16 diffuser?

a. Label A

b. Label B

c. Label C

d. Label D QUESTION C.10 [1.0 point]

The source interlock system will prevent rod withdrawal unless source level is above a preset level. Which ONE of the following detectors provides the source interlock information?

a. Fission Chamber

b. Compensated Ion Chamber

c. Uncompensated Ion Chamber

d. Fuel Element Thermocouple

Category C: Facility and Radiation Monitoring Systems QUESTION C.11 [1.0 point]

Using the diagram of an instrumented fuel element, select the appropriate materials associated with its locator.

Column A Column B I A. Zirconium Hydride-Uranium II B. Stainless steel III C. Erbium Burnable Poison IV D. Graphite Reflector E. Zirconium Rod F. Spacer G. Thermocouples

a. I.A, II.E, III.C, IV.G

b. I.D, II.G, III.A, IV.F

c. I.D, II.E, III.A, IV.G

d. I.C, II.A, III.B, IV.G

Category C: Facility and Radiation Monitoring Systems QUESTION C.12 [1.0 point]

Which ONE of following experimental facilities provides the HIGHEST fast flux?

a. Central Thimble

b. Pneumatic Transfer System

c. Piercing Beam Port next to core

d. Rotary Specimen Rack QUESTION C.13 [1.0 point]

Which ONE of the following is an indication of a clog in the demineralizer tank?

a. High Radiation level at the pool surface

b. High Flow Rate through Demineralizer

c. High Temperature within Demineralizer

d. High pressure Upstream of Demineralizer QUESTION C.14 [1.0 point]

Where is the Reg Rod located in the reactor core?

a. E ring

b. D ring

c. C ring

d. B ring QUESTION C.15 [1.0 point]

Per KSU Technical Specifications, which ONE of the following safety system functions must be operable for both steady-state and pulsing operations?

a. Manual Scram

b. Pulse Rod Interlock

c. Reactor Power Level Scram

d. Control Rod (standard) Position Interlock

Category C: Facility and Radiation Monitoring Systems QUESTION C.16 [1.0 point]

Where does the pulse peak power information come from after pulsing?

a. NMP 1000

b. NLW 1000

c. NPP 1000

d. PA 1000 QUESTION C.17 [1.0 point]

PA-1000 Preamplifier is a part of:

a. Fuel Temperature Channel

b. NLW-1000 Wide Range Log Channel

c. NMP-1000 Multi Range Linear Channel

d. NPP-1000 Percent Power and Pulsing Channel QUESTION C.18 [1.0 point]

In event of a power loss, which ONE of the following systems will receive emergency battery backup power?

a. Primary coolant pump

b. Secondary coolant pump

c. Telephone systems

d. Fire alarm system

Category C: Facility and Radiation Monitoring Systems QUESTION C.19 [1.0 point]

Attached is the gas-filled detector curve (detector effect vs. voltage). Different regions of this curve are useful for different detectors. Which ONE of the following is the Geiger Mueller region?

a. Region II

b. Region III

c. Region IV

d. Region V

(***** END OF CATEGORY C *****)

((***** END OF EXAM *****))

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.01 Answer: b

Reference:

Nuclides and Isotopes, N = A - Z 3-1 = 2 A.02 Answer: a

Reference:

Standard NRC Question A.04 Answer: c

Reference:

TRIGA Fuel Design A.06 Answer: c

Reference:

from k=0.955 to criticality (k=1), = (k-1)/k = -0.047 k/k or = 0.047 k/k needed to reach criticality. From criticality to JUST prompt, k/k = eff required, so minimum reactivity added to produce prompt criticality will be: 0.047+0.007=

0.054 A.07 Answer: c

Reference:

Time is related to ratio of final power to initial power. 2:1 is the largest ratio.

A.08 Answer: d

Reference:

A.11 Answer: b

Reference:

P = P0 et/T = 10 kW e(60sec/-80sec) = 10 kW

e-0.75 = 0.472 10 kW = 4.7 kW

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.13 Answer c

Reference:

LaMarsh, Introduction to Nuclear Engineering, 3rd Edition, Section 6.5, page 287 A.17 Answer: a. b. + c. n d. -

Reference:

Standard NRC question A.18 Answer: d

Reference:

=($)*; 1=$1.20*0.007= 0.0084 k/k; 2=$2.0*0.007= 0.014 k/k Peak2 = Peak1*(0.014-.007/.0084-.007)2 = 5000 MW Or Peak2 = Peak1*($2-$1 / $1.2-$1)2 = 5000 MW 2

( 2 - )2 ( 1 - )

=

Peak 2 Peak 1 A.19 Answer: d

Reference:

reactor A = (Keff1-Keff2)/(Keff1*Keff2). (0.2-0.1)/(0.2*0.1) = 5 k/k reactor B = (Keff1-Keff2)/(Keff1*Keff2). (0.9-0.8)/(0.9*0.8) = 0.139 k/k 5/0.139 = 36

Category B: Normal/Emergency Operating Procedures and Radiological Controls B.1 Answer: b

Reference:

NRC standard question for TRIGA design B.2 Answer: c

Reference:

KSU TS 3.2 B.3 Answer: a

Reference:

KSU TS 5.3 B.4 Answer: d

Reference:

KSU SAR 13.1 B.5 Answer: c

Reference:

10 CFR 50.59 B.6 Answer: b

Reference:

KSU TS 5.4 B.7 Answer: c

Reference:

KSU TS 3.7 B.8 Answer: d

Reference:

TS 6.2 (TS changes require an amendment)

B.9 Answer: b

Reference:

KSU TS 1.0 Definitions B.10 Answer: d

Reference:

KSU Technical Specification 5.4.3 B.11 Answer: c

Reference:

KSU SOP 27 B.12 Answer: c

Reference:

DR = DR*e -t;1 rem/hr =2 rem/hr* e -(5hr); Ln(1.0/2) = -*5 --> =0.1386; solve for t: Ln(.02/2)=-0.1386 (t) t=33 hours B.13 Answer: a

Reference:

I1D12=I2D22 250mR/hr@(3ft)2=I2@(1ft)2 2250 mR/hr or 2.25 R/hr

Category B: Normal/Emergency Operating Procedures and Radiological Controls B.14 Answer: c

Reference:

DR = DR*e -X; Find : 250 = 1000* e -*60 ; = 0.0231 If insertion of an HVL (thickness of lead), the original intensity will be reduced by half. Find X: 1 = 2* e -0.0231*X ; X= 30 mm; Find HVL by shortcut: 1000mR- 500 mR is the 1st HVL; 500 mR - 250 mR is the 2nd HVL; So HVL=60mm/2 = 30 mm B.15 Answer: d

Reference:

10CFR55.1(a)

B.16 Answer: b

Reference:

Chart of the Nuclides B.17 Answer: d

Reference:

BASIC Radiological Concept (Betas and alpha won't make it through the demineralizer tank)

B.18 Answer: a. 5, b. 3, c. 2, d. 4

Reference:

KSU TS 3.1, 3.2, and 3.6 B.19 Answer: b

Reference:

10 CFR 20.1003; S=So(ro/r)2, therefore for a point source, 100 mrem/hr at 1 ft =

103.23mrem/hr at 30 cm

Category C: Facility and Radiation Monitoring Systems C.01 Answer: a. 4, b. 1, c. 1, d. 3

Reference:

KSU TS 3.5 and KSU SAR Chapter 7 C.02 Answer: c

Reference:

KSU Training Manual, Transient Rod Drive Mechanism C.03 Answer: d

Reference:

KSU Training Manual, Reactor Cooling System C.04 Answer: a

Reference:

KSU Training Manual, Reactor Cooling System C.05 Answer: d

Reference:

KSU Training Manual, Reactor Cooling System C.06 Answer: b

Reference:

Delta T at true 100 kWh =0.0526 °C per kWh *100 kW =5.26 °C at 100 kWh True power = (6 °C/5.26 °C)*100 kW =114 kW, so you need to lower the detector to obtain the true power at 114 kW C.07 Answer: b

Reference:

NRC Standard Question C.08 Answer: a. 1, b. 3, c. 2.

Reference:

KSU Training Manual, Figure 9 C.09 Answer: b

Reference:

KSU SAR Figure 5.1 C.10 Answer: a

Reference:

KSU Training Manual, Figure 8 C.11 Answer: c

Reference:

KSU Triga Fuel Element C.12 Answer: a

Reference:

KSU Training Manual 5.7

Category C: Facility and Radiation Monitoring Systems C.13 Answer: d

Reference:

Standard NRC question C.14 Answer: a

Reference:

KSU SAR C.15 Answer: a

Reference:

KSU TS 3.3 and 3.4 C.16 Answer: c

Reference:

KSU Training Manual, Chapter 7 C.17 Answer: b

Reference:

KSU SAR, Chapter 7.3 C.18 Answer: d

Reference:

KSU SAR, Chapter 8.2 C.19 Answer: d

Reference:

Bevelacqua, J. Basic Health Physics

ML19074A070

Text

SUBJECT:

Dear Dr. Cebula:

Enclosures:

SUMMARY

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