Text

Initial Examination Report No. 50-188/OL-07-01, Kansas State University
	ML062910267
Person / Time
Site:	Kansas State University
Issue date:	10/25/2006
From:	Johnny Eads; NRC/NRR/ADRA/DPR/PRTB
To:	Whaley P; Kansas State University
	Young P, NRC/NRR/ADRA/DPR, 415-4094
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October 25, 2006 Mr. P. M. Whaley Nuclear Reactor Facility Manager Kansas State University 112 Ward Hall Manhattan, KS 66506-2500

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-188/OL-07-01, KANSAS STATE UNIVERSITY

Dear Mr. Whaley:

During the week of October 2, 2006, the NRC administered initial examinations to employees of your facility who had applied for a license to operate your Kansas State University reactor. The examination was conducted in accordance with NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1. At the conclusion of the examination, the preliminary findings were discussed with those members of your staff identified in the enclosed report.

In accordance with 10 CFR 2.390 of the Commission's regulations, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/NRC/ADAMS/index.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 internet e-mail pty@nrc.gov.

Sincerely,

/RA/

Johnny Eads, Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-188

Enclosures:

1. Initial Examination Report No. 50-188/OL-07-01

2. Facility comments with NRC resolution

3. Examination and answer key with facility comments incorporated.

cc w/encls: Please see next page

Kansas State University Docket No. 50-188 cc:

Office of the Governor State of Kansas Topeka, KS 66612 Mayor of Manhattan P.O. Box 748 Manhattan, KS 66502 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

October 25, 2006 Mr. P. M. Whaley Nuclear Reactor Facility Manager Kansas State University 112 Ward Hall Manhattan, KS 66506-2500

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-188/OL-06-01, KANSAS STATE UNIVERSITY

Dear Mr. Whaley:

During the week of October 2, 2006, the NRC administered initial examinations to employees of your facility who had applied for a license to operate your Kansas State University reactor. The examination was conducted in accordance with NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1. At the conclusion of the examination, the preliminary findings were discussed with those members of your staff identified in the enclosed report.

In accordance with 10 CFR 2.390 of the Commission's regulations, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/NRC/ADAMS/index.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 internet e-mail pty@nrc.gov.

Sincerely,

/RA/

Johnny Eads, Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-188

Enclosures:

1. Initial Examination Report No. 50-188/OL-07-01

2. Facility comments with NRC resolution

3. Examination and answer key with facility comments incorporated.

cc w/encls: Please see next page DISTRIBUTION w/ encls.:

PUBLIC RNRP\\R&TR r/f JEads DHughes Facility File (EBarnhill) O-6 F-2 ADAMS ACCESSION #: ML062910267 TEMPLATE #:NRR-074 OFFICE PRTB:CE IOLB:LA PRTB:SC NAME PYoung;tls*

EBarnhill JEads:tls*

DATE 10/18/2006 10/23/2006 10/25/2006 OFFICIAL RECORD COPY

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:

50-188/OL-07-01 FACILITY DOCKET NO.:

50-188 FACILITY LICENSE NO.:

R-88 FACILITY:

Kansas State University EXAMINATION DATES:

October 4, 2006 EXAMINERS:

Phillip T Young, Chief Examiner SUBMITTED BY:

/RA/

10/17/2006 Phillip T Young, Chief Examiner Date

SUMMARY

During the week of August 7, 2006, the NRC administered operator licensing examinations to one Reactor Operator and one Senior Reactor Operator (Upgrade) candidates. All candidates passed the examination.

ENCLOSURE 1

REPORT DETAILS 1.

Examiners:

Phillip T Young, Chief Examiner 2.

Results:

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

Exit Meeting:

Phillip T Young, NRC Chief Examiner Paul M. Whaley, Facility Manager The NRC thanked the facility staff for their cooperation during the examinations. No generic concerns were noted.

Facility Comments with NRC Resolution Facility Comment:

Question: A.006,

1. Integral worth of the control rods are fairly constant over time (based on annual measurements)

2. The TRIGA is a low-leakage core, so coolant temp has little effect on net core reactivity, but a significant amount of moderation occurs from hydride in the fuel and fuel temperature is a big component of the moderator temperature.

"Beta" symbol didn't print right, came out a backwards E -- I don't think it is a problem "Delta" symbol didn't print right -- I don't think it is a problem NRC Resolution:

Comments noted. Problems with Beta and Delta symbol printing corrected on official copy.

Facility Comment:

Question: C.004, No diagram; I used the key to generate a diagram, sent it with the package NRC Resolution:

Comments noted, diagram verified correct.

ENCLOSURE 2

KANSAS STATE UNIVERSITY WRITTEN EXAM w/ANSWER KEY OPERATOR LICENSING EXAMINATION OCTOBER 04, 2006 ENCLOSURE 3

Section A - Rx Theory, Thermo & Fac. Operating Characteristics QUESTION A.001

[2.0 points, 0.5 each] {2.0}

The listed isotopes are all potential daughter products due to the radioactive decay of 35Br87. Identify the type of decay necessary (Alpha, Beta, Gamma or Neutron emission) to produce each of the isotopes.

a.

33As83 b.

35Br86 c.

35Br87 d.

36Kr87 Answer:

A.001 a. = alpha;

b. = neutron;

c. = gamma;

d. = Beta

Reference:

Volume 1, Module 1, Modes of Radioactive Decay, pp. 22-29.

QUESTION A.002

[1.0 point] {3.0}

What is the kinetic energy range of a thermal neutron?

a. > 1 MeV

b. 100 KeV - 1 MeV c.

1 eV - 100 KeV

d. < 1 eV Answer:

A.002 d.

Reference:

Volume 1, Module 2, Neutron Moderation, p. 23.

QUESTION A.003

[1.0 point] {4.0}

Suppose the temperature coefficient of a core is -2.5 x 10-4 K/K/EC and the average control rod worth of the regulating control rod is 5.895 x 10-3 K/K/inch. If the temperature INCREASES by 50EC what will the automatic control command the regulating rod to do? Select the answer that is closest to the calculated value.

a. 5.6 inches in

b. 2.1 inches out c.

0.5 inches in

d. 4.3 inches out Answer:

A.003 b.

Reference:

The temperature increase will result in a change in reactivity of: -2.5 x 10-4 K/K/EC x 50EC

= -1.25 x 10-2 K/K. Since the temperature rise results in a negative reactivity insertion, the control rod will need to drive out to add positive reactivity. D = (1.25 x 10-2 K/K) ÷ (5.895 x 10-3 K/K/inch) = 2.12 inches. Reference 1, Volume 2, Module 3, Reactivity Coefficients,

p. 48.

Section A - Rx Theory, Thermo & Fac. Operating Characteristics QUESTION A.004

[1.0 point] {5.0}

Given the following data, which ONE of the following is the closest to the half life of the material?

TIME ACTIVITY 0

2400 cps 10 min.

1757 cps 20 min.

1286 cps 30 min.

941 cps 60 min.

369 cps

a. 11 minutes

b. 22 minutes

c. 44 minutes

d. 51 minutes Answer:

A.004 b.

Reference:

Standard NRC Question A = A0 e-T (22 minutes)

QUESTION A.005

[1.0 point] {6.0}

Initially Nuclear Instrumentation is reading 30 CPS and the reactor has a Keff of 0.90. You add an experiment which causes the Nuclear instrumentation reading to increase to 60 CPS. Which ONE of the following is the new Keff?

a.

0.91 b.

0.925 c.

0.95 d.

0.975 Answer:

A.005 c.

Reference:

CR2/CR1 = (1 - Keff1)/(1 - Keff2) 60/30 = (1 - 0.900)/(1 - Keff2) 1-Keff2 = 1/2 x 0.1 = 0.05 Keff2 = 1 - 0.05 = 0.95 QUESTION A.006

[1.0 point] {7.0}

During a fuel loading of the core, as the reactor approaches criticality, the value of 1/M:

a. Increases toward one

b. Decreases toward one c.

Increases toward infinity

d. Decreases toward zero Answer:

A.006 d.

Reference:

Module 4, L Theory (L Operations), E.O. 1.4, pg. 7 and DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Volumes 1 and 2, January 1993.

Section A - Rx Theory, Thermo & Fac. Operating Characteristics QUESTION A.007

[1.0 point] {8.0}

Which ONE of the following is the reason for an installed neutron source within the core? A startup without an installed neutron source

a. is impossible as there would be no neutrons available to start up the reactor.

b. would be very slow due to the long time to build up neutron population from so low a level.

c.

could result in a very short period due to the reactor going critical before neutron population built up high enough to be read on nuclear instrumentation.

d. can be compensated for by adjusting the compensating voltage on the source range detector.

Answer:

A.007 c.

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory.

QUESTION A.008

[1.0 point] {9.0}

By definition, an exactly critical reactor can be made prompt critical by adding positive reactivity equal to

a. the shutdown margin

b. the Kexcess margin c.

the eff value

d. 1.0 %K/K.

Answer:

A.008 c.

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory.

QUESTION A.009

[1.0 point] {10.0}

Reactor power doubles in 42 seconds. Based on the period associated with this transient, how long will it take for reactor power to increase by a factor of 10?

a. 80 seconds

b. 110 seconds c.

140 seconds

d. 170 seconds Answer:

A.009 c.

Reference:

P = P0 et/ 1st find. = time/(ln(2)) = 42/0.693 = 60.6 sec.

Time = x ln(10) = 60.6 x 139.5 sec DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory.

Section A - Rx Theory, Thermo & Fac. Operating Characteristics QUESTION A.010

[1.0 point] {11.0}

Which one of the following statements correctly describes the property of a GOOD MODERATOR?

a. It slows down fast neutrons to thermal energy levels via a large number of collisions.

b. It reduces gamma radiation to thermal energy levels via a small number of collisions.

c.

It slows down fast neutrons to thermal energy levels via a small number of collisions.

d. It reduces gamma radiation to thermal energy levels via a large number of collisions.

Answer:

A.010 c.

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume X, Module Y, Enabling Objective Z.Z QUESTION A.011

[1.0 point] {12.0}

Which of the following statements correctly describe the influence of DELAYED NEUTRONS on the neutron life cycle? Delayed neutrons

a. increase the time required for PU239 to moderate the fission process.

b. decrease the time required for the neutron population to change between generations.

c.

increase the time required for the neutron population to change between generations.

d. decrease the amount of reflection possible with a steel reflector.

Answer:

A.011

c.

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume X, Module Y, Enabling Objective Z.Z QUESTION A.012

[1.0 point] {13.0}

Why is the stable negative period following a scram always the same value, regardless of initial power level?

The rate of power change is dependent on the

a. mean lifetime of the longest lived delayed precursor.

b. constant decay rate of prompt neutrons.

c.

mean lifetime of the shortest lived delayed neutron precursor.

d. constant decay rate of prompt gamma emitters.

Answer:

A.012

a.

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume X, Module Y, Enabling Objective Z.Z

Section A - Rx Theory, Thermo & Fac. Operating Characteristics QUESTION A.013

[1.0 point] {14.0}

Which one of the following correctly describes the relationship between differential rod worth (DRW) and integral rod worth (IRW)?

a. DRW is the slope of the IRW curve at a given location.

b. DRW is the area under the IRW curve at a given location.

c. DRW is the square root of the IRW curve at a given location.

d. There is no relationship between DRW and IRW.

Answer A.013 a.

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume X, Module Y, Enabling Objective Z.Z QUESTION A.014

[1.0 point] {15.0}

Which one of the following accurately details a factor contributing to Xenon balance within the reactor?

a. Most Xe135 is formed by fission.

b. Te135 is a fission product which quickly decays to I135.

c. Within approximately 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after startup, Xe135 has reached its equilibrium value.

d. Several minutes following a reactor shutdown, Xe level is increasing because I135 is not being produced.

Answer:

A.014 b.

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume X, Module Y, Enabling Objective Z.Z QUESTION A.015

[1.0 point] {16.0}

Delayed neutrons comprise approximately what percent of all neutrons produced in the reactor?

a. 0.65%

b. 1.3%

c. 6.5%

d. 13%

Answer:

A.015 a.

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume X, Module Y, Enabling Objective Z.Z

Section A - Rx Theory, Thermo & Fac. Operating Characteristics QUESTION A.016

[1.0 point] {17.0}

Which of the following factors has the LEAST effect on rod worth?

a. number and location of adjacent rods.

b. temperature of the moderator.

c. temperature of the fuel.

d. core age.

Answer:

A.016 c.

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume X, Module Y, Enabling Objective Z.Z QUESTION A.017 [1.0 point] {18.0}

and eff both describe the total fraction of delayed neutrons. The difference between the two is that eff is

a. smaller than since delayed neutrons are born at lower energy levels than prompt neutrons.

b. larger than since delayed neutrons are born at lower energy levels than prompt neutrons.

c.

smaller than since delayed neutrons are born at higher energy levels than prompt neutrons.

d. larger than since delayed neutrons are born at higher energy levels than prompt neutrons.

Answer:

A.017 b.

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume X, Module Y, Enabling Objective Z.Z QUESTION A.018

[1.0 point] {19.0}

Which one of the following is the definition of the FAST FISSION FACTOR?

a. The ratio of the number of neutrons produced by fast fission to the number produced by thermal fission

b. The ratio of the number of neutrons produced by thermal fission to the number produced by fast fission c.

The ratio of the number of neutrons produced by fast and thermal fission to the number produced by thermal fission

d. The ratio of the number of neutrons produced by fast fission to the number produced by fast and thermal fission Answer:

A.018 c.

Reference:

Reference 1, Volume 2, Module 3, Neutron Life Cycle, p. 3.

Section A - Rx Theory, Thermo & Fac. Operating Characteristics QUESTION A.019 [1.0 point] {20.0}

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

a. 2.5 x 1011 fissions/sec.

b. 2.5 x 1013 fissions/sec.

c.

2.5 x 1011 fissions/cm3/sec.

d. 2.5 x 1013 fissions/cm3/sec.

Answer:

A.019 c

Referenced:

Reference 1, Volume 1, Module 2 Reaction Rate, p. 18.

NOTE: Where the question states Reference 1, it refers to the reference listed below.

Reference 1: DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Volumes 1 and 2, January 1993.

Section B - Normal/Emergency Procedures & Radiological Controls QUESTION B.001

[1.0 point]

(1.0)

Which of the following conditions is required to be met prior to the Annual Power Level Calibration?

a. The secondary cooling system will not be operated for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

b. The pool temperature will be 20 + 5 EC.

c.

The pool temperature will be 5 + 1 EC below ambient temperature.

d. The secondary cooling system will be in use, maintaining pool temperature at 22 EC for 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Answer: 001 b.

Reference:

Procedure No. 2 Annual Power Level Calibration QUESTION B.002

[1.0 point]

(2.0)

Which method is used to determine the void coefficient of an air filled capsule?

a. 1/M plot

b. rod drop method c.

positive period method

d. difference in critical rod positions Answer: 002 d.

Radiation Protection Program, page A-9.

Radiation area > 5 mrem/hour. 200 mrem at 3 feet -> 5 mrem at 18.3 feet.

QUESTION B.015

[1.0 point]

(15.0)

The dose rate from a mixed beta-gamma point source is 100 mrem/hour at a distance of one (1) foot, and is 0.1 mrem/hour at a distance of twenty (20) feet. What percentage of the source consists of beta radiation?

a. 20%

b. 40%

c.

60%

d. 80%

Answer: 015 c.

Reference:

10CFR20.

At 20 feet, there is no beta radiation. Gamma at 20 feet = 0.1 mrem/hour, gamma at 1 foot = 40 mrem/hour.

Therefore beta at 1 foot = 60 mrem/hour = 60%.

Section B - Normal/Emergency Procedures & Radiological Controls QUESTION B.016

[1.0 point]

(16.0)

A small radioactive source is to be stored in the reactor facility. The source activity is estimated to be 25 curies and emits a 1.33 Mev gamma. Assuming no shielding is used, the dose rate from the source at a distance of 10 feet would be approximately:

a. 0.33 Rem/hour.

b. 2.0 Rem/hour.

c.

6.0 Rem/hour.

d. 20.0 Rem/hour.

Answer: 016 b.

Reference:

Dose Rate = 6CiE/R2 = 6x25x1.33/100 = 2 Rem/hour.

QUESTION B.017

[1.0 point]

(17.0)

Which ONE of the following statements describe a reactivity limitation imposed on experiments?

a. The absolute reactivity worth of all experiments in the reactor shall not exceed $2.00.

b. An experiment which will not cause a 20-second period can be inserted in the core when the reactor is at power.

c.

When determining the absolute reactivity worth of an experiment, the reactivity effects associated with the moderator temperature are to be considered.

d. No experiment shall be inserted or removed unless all control blades are fully inserted.

Answer: 017 a.

Reference:

Technical Specifications,Section I.3.

QUESTION B.018

[1.0 point]

(18.0)

In accordance with Experiment No. 1, "Isotope Production," removal of any material from a region of significant neutron flux must be done in the presence of:

a. the Reactor Supervisor.

b. a Senior Reactor Operator.

c.

a representative of the University Radiation Safety Office.

d. a person approved by the Reactor Supervisor who is trained in the safe handling of radioactive materials.

Answer: 018 d.

Reference:

Experiment No. 1, page 4.

Section B - Normal/Emergency Procedures & Radiological Controls QUESTION B.019

[1.0 point]

(19.0)

In accordance with Procedure No. 8, "Calibration of Continuous Air Monitors," Technicium-99 is used as a source because:

a. its decay particles and energies are similar to Ar-41.

b. its decay particles and energies are similar to I-131.

c.

its half-life is long enough so that it does not decay appreciably.

d. it produces count rates large enough to be measured.

Answer: 019 b.

Reference:

Procedure No. 8, page 4.

QUESTION B.020

[1.0 point]

(20.0)

Which ONE of the following is expressly forbidden by the Operations Manual?

a. Carbon tetrachloride in the reactor bay.

b. Gasoline in the reactor bay.

c.

Acetone in the reactor.

d. Mercury-glass thermometer in the reactor pool.

Answer: 020 d.

Reference:

Training Manual, page A2-6.

Section C - Facility and Radiation Monitoring Systems QUESTION C.004

[2.0 points, 1/4 each]

(2.0)

Identify the components labeled a through h on the figure of a Control Blade Drive Mechanism provided.

(Note: Items are used only once. Only one answer per letter.)

a. ___

1. Foot

b. ___

2. Barrel

c. ___

3. Position Potentiometer

d. ___

4. Rod Down Limit Switch

e. ___

5. Drive Motor

f. ___

6. Pull Rod

g. ___

7. Armature

h. ___

8. Magnet Answer:

C.001 a. = 1; b. = 2; c. = 3; d. = 4; e. = 5; f. = 6; g. = 7; h. = 8

Reference:

KSU Facility Description page A.1.19 QUESTION C.002

[1.0 point]

(3.0)

What is the normal rod motion speed?

a. 16 inches per minute

b. 14 inches per minute c.

12 inches per minute

d. 10 inches per minute Answer:

KSU Training Manual, General Characteristics, Section 6, Coolant System, Figure 5.

Section C - Facility and Radiation Monitoring Systems QUESTION:

C.013

[2.0 points, 1/2 each]

(15.0)

Select from column B the actual rod movement that would result from attempting to simultaneously move the combination of rods in column A. (Items in column B may be used once, more than once or not at all. Only one answer may occupy a space in column A.) Four (4) answers required at 0.50 points each.

Column A (Attempted Rod Move)

Column B (Result)

a. Attempt to withdraw reg

1. Shim rod moves up.

rod (pulse mode).

2. Reg rod moves up.

b. Attempt to withdraw shim and reg rods (steady state

3. Shim and reg rods move up.

mode).

c.

Attempt to withdraw pulse and

4. Pulse rod moves up.

reg rod (steady state mode).

5. No rod motion.

d. Shim rod is up 250 units and attempt to raise pulse rod (steady state mode).

Answer:

C.013 a. = 5; b. = 5; c. = 4; d.= 4

Training Manual, page A1-11.

ML062910267

Text

SUBJECT:

Dear Mr. Whaley:

Enclosures:

SUBJECT:

Dear Mr. Whaley:

Enclosures:

SUMMARY

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