ML100760391

Retake Examination Report, No. 50-123/OL-10-02, Missouri University of Science and Technology

ML100760391
Person / Time
Site:	University of Missouri-Rolla
Issue date:	03/22/2010
From:	Johnny Eads Research and Test Reactors Branch B
To:	Frimpong S Missouri Univ of Science & Technology
Nguyen JT, DPR/PRTB, 301-415-4007
References
50-123/OL-10-02
Download: ML100760391 (13)

Text

March 22, 2010 Dr. Samuel Frimpong, Chair Mining and Nuclear Engineering 226 McNutt Hall Missouri University of Science and Technology Rolla, MO 65409-0450

SUBJECT:

RETAKE EXAMINATION REPORT NO. 50-123/OL-10-02, MISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY

Dear Dr. Frimpong:

On March 9, 2010, Mr. Bill Bonzer administered an NRC prepared operator licensing examination at your Missouri University of Science and Technology reactor. The examination was prepared and proctored 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. John T. Nguyen at (301) 415-4007 or via internet e-mail at John.Nguyen@nrc.gov.

Sincerely,

/RA by Thomas Blount for/

Johnny H. Eads, Jr., Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-123

Enclosures:

1. Retake Examination Report No. 50-123/OL-10-02

2. Written examination with facility comments cc: w/o enclosures: see next page

March 22, 2010 Dr. Samuel Frimpong, Chair Mining and Nuclear Engineering 226 McNutt Hall Missouri University of Science and Technology Rolla, MO 65409-0450

SUBJECT:

RETAKE EXAMINATION REPORT NO. 50-123/OL-10-02, MISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY

Dear Dr. Frimpong:

On March 9, 2010, Mr. Bill Bonzer administered an NRC prepared operator licensing examination at your Missouri University of Science and Technology reactor. The examination was prepared and proctored 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. John T. Nguyen at (301) 415-4007 or via internet e-mail at John.Nguyen@nrc.gov.

Sincerely,

/RA by Thomas Blount for/

Johnny H. Eads, Jr., Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-123

Enclosures:

1. Retake Examination Report No. 50-123/OL-10-02

2. Written examination with facility comments cc: w/o enclosures: see next page DISTRIBUTION w/encls.:

PUBLIC PROB r/f RidsNRRDPRPRLB RidsNRRDPRPROB Facility File (CRevelle) O-07 F-08 ADAMS ACCESSION #: ML100760391 TEMPLATE #:NRR-074 OFFICE PROB:CE IOLB:LA E

PROB:BC NAME JNguyen CRevelle JEads (TBlount)

DATE 03/16/10 03/18/10 03/22/10

OFFICIAL RECORD COPY

University of Missouri - Rolla Docket No. 50-123 cc:

Bill Bonzer Missouri University of Science and Technology Nuclear Reactor Facility 1870 Miner Circle Rolla, MO 65409-0630 Homeland Security Coordinator Missouri Office of Homeland Security P.O. Box 749 Jefferson City, MO 65102 Planner, Dept of Health and Senior Services Section for Environmental Public Health 930 Wildwood Drive, P.O. Box 570 Jefferson City, MO 65102-0570 Deputy Director for Policy Department of Natural Resources 1101 Riverside Drive Fourth Floor East Jefferson City, MO 65101 A-95 Coordinator Division of Planning Office of Administration P.O. Box 809 State Capitol Building Jefferson City, MO 65101 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

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

50-123/OL-10-02 FACILITY DOCKET NO.:

50-123 FACILITY LICENSE NO.:

R-79 FACILITY:

Missouri University of Science and Technology EXAMINATION DATES:

March 9, 2010 SUBMITTED BY:

03/16/2010 John T. Nguyen, Chief Examiner Date

SUMMARY

Mr. Bill Bonzer administered an NRC prepared operator licensing examination for one candidate who had failed Section B of the NRC written examination administered in November 2009 at the Missouri University of Science and Technology. The candidate passed the examination.

REPORT DETAILS

1.

Examiner:

John Nguyen, Chief Examiner, NRC

2.

Results:

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

3.

Exit Meeting:

Due to the nature of this examination there was no exit meeting ENCLOSURE 1

License Operator Written Examination With ANSWER KEY OL-10-02 MISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY March 9, 2010 ENCLOSURE 2

Section B Normal, Emergency and Radiological Control Procedures Page 2 QUESTION B.01

[1.0 points]

During the emergency, who has responsibility for determining the appropriate emergency classification and procedures?

a.

Senior Reactor Operator.

b.

Reactor Manager.

c.

Reactor Director.

d.

Chair Mining and Nuclear.

QUESTION B.02

[1.0 points, 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]

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.

Section B Normal, Emergency and Radiological Control Procedures Page 3 QUESTION B.04

[1.0 points]

Given that the following emergency conditions occur at MSTR:

(a) Low level of coolant alarms (b) Particulate monitor alarms (c) Radiation levels at the site boundary indicate 100 mRem for one hour.

Which ONE of the following is the appropriate Emergency Classification?

a.

Notification of Unusual Event.

b.

Alert.

c.

Site Area Emergency.

d.

General Emergency.

QUESTION B.05

[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.06

[1.0 point]

Per MSTR Technical Specifications, the regulating rod shall be worth no more than

a.

0.7 % k/k.

b.

1.0 % k/k.

c.

1.5 % k/k.

d 1.6 % k/k.

Section B Normal, Emergency and Radiological Control Procedures Page 4 QUESTION B.07

[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.08

[1.0 point]

Trainees may operate the reactor controls under the direct supervision of a Senior Reactor Operator when the excess reactivity is

a.

less than 1.6 % delta k/k.

b.

greater than 0.7% delta k/k.

c.

greater than 0.7% delta k/k and less than 1.0% delta k/k.

d.

greater than 0.7% delta k/k and less than 1.5% delta k/k.

QUESTION B.09

[1.0 point]

Per MSTR Technical Specifications, the Radiation Safety Committee shall meet at least ______ per calendar year.

a.

once

b.

two times

c.

three times

d.

fourth times QUESTION B.10

[1.0 point]

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

a.

A corrosive material.

b.

A short half-life material.

c.

30 mg of explosive material.

d.

Fueled experiment which generates 100 mW power.

Section B Normal, Emergency and Radiological Control Procedures Page 5 QUESTION B.11

[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.

QUESTION B.12

[1.0 point]

What is the MINIMUM level of management who may authorize a key bypass of the control channel automatic function?

a.

The Reactor Operator on Duty.

b.

The Senior Reactor Operator on Duty.

c.

The Reactor Manager.

d.

The Reactor Director.

QUESTION B.13

[1.0 point]

Per MSTR Technical Specifications, which ONE of the following reactor periods will cause the reactor RUNDOWN?

a.

5 seconds.

b.

15 seconds.

c.

30 seconds.

d.

50 seconds.

Section B Normal, Emergency and Radiological Control Procedures Page 6 QUESTION B.14

[1.0 point]

During a reactor startup, the reactor operator (RO) withdraws the Shim rods to positions of 13 inches and the Reg rod to 15 inches. The RO observes that the Startup Channel count rate has no response. For this observation, which ONE of the following is the best action?

a.

Withdraw the Reg rod to 18 inches because the reactor is still sub-critical.

b.

Withdraw the Shim rods to 18 inches and then verify its response.

c.

Stop the startup; immediately report the result to the SRO on Duty.

d Shutdown the reactor; immediately report the result to NRC since the Startup Channel count rate doesnt work.

QUESTION B.15

[1.0 point]

The reactor is in a SHUTDOWN condition, as defined by MSTR Technical Specifications, when.

a.

all rods are inserted and the reactor console is secured.

b.

the reactor is subcritical by at least $1.00 in the reference core condition with the reactivity worth of all installed experiments included.

c.

the reactor console is secured and no work is in progress involving core fuel, core structure, installed control rods, or control rod drives.

d.

no experiments are being moved or serviced that have, on movement, a reactivity worth exceeding the maximum value allowed for a single experiment of $1.00.

QUESTION B.16

[1.0 point]

Before unloading of fuel elements from the core to the fuel storage rack, which ONE of the following tasks needs to be performed FIRST?

a.

Calculate the shutdown margin.

b.

Complete a startup checklist.

c.

Turn off the Constant Air Monitor (CAM).

d.

Withdraw Shim rods 1,2 and 3 to Shim range.

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

Section B Normal, Emergency and Radiological Control Procedures Page 7 ANSWER KEY B.01 c

REF:

Emergency Procedure 502.A, Emergency Action Levels B.02 a(4) b(1) c(2) d(3)

REF:

10 CFR B.03 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)

DR=6.6*10 -2 Rem or ~65 mrem B.04 c

REF Emergency Plan, Table 1, page 10 B.05 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.06 a

REF TS 3.1 B.07

b.

REF Chart of the Nuclides B.08 d

REF SOP 101, Sec B.3 B.09 a

REF TS 6.2.1 B.10 c

REF TS 3.7.2 B.11

d.

REF 10 CFR 20.1201 B.12 b

REF SOP 101.B.9 B.13 b

REF TS 3.1 B.14 c

REF SOP 103.C

Section B Normal, Emergency and Radiological Control Procedures Page 8 B.15 b

REF TS 1.2, Definitions B.16 b

REF SOP 207