ML15026A065

Examination Report 50-607 OL-15-01 University of California-Davis Research Reactor

ML15026A065
Person / Time
Site:	University of California-Davis (R-130)
Issue date:	02/03/2015
From:	Kevin Hsueh Research and Test Reactors Licensing Branch
To:	Klein B McClellan Nuclear Research Center
Nguyen, John 415-4007
Shared Package
ML14323A261	List: ML14323A323 ML15026A065
References
50-607/15-01 50-607/OL-15
Download: ML15026A065 (18)

Text

February 3, 2015 Dr. Barry M. Klein, Reactor Director 5335 Price Avenue, Bldg. 258 McClellan AFB, CA 95652-2504

SUBJECT:

EXAMINATION REPORT NO. 50-607/OL-15-01, UNIVERSITY OF CALIFORNIA-DAVIS

Dear Dr. Klein:

During the week of January 12, 2015, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your University Of California-Davis TRIGA Reactor. The examination was conducted according to NUREG-1478, Operator Licensing Examiner Standards for Research and Test Reactors, Revision 2.

In accordance with Section 2.390 of Title 10 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 component of NRCs 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 Mr.

John T. Nguyen at (301) 415-4007 or via email John.Nguyen@nrc.gov.

Sincerely,

/RA Patrick Isaac acting for/

Kevin Hsueh, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-607

Enclosures:

1. Examination Report No. 50-607/OL-15-01

2. Written Examination cc: Walter Steingass, University of California-Davis cc w/o enclosures: See next page

University Of California-Davis Docket No. 50-607 cc:

Dr. Wesley Frey, Radiation Safety Officer 5335 Price Avenue, Bldg. 258 McClellan AFB, CA 95652-2504 California Energy Commission 1516 Ninth Street, MS-34 Sacramento, CA 95814 Radiological Health Branch California Department of Public Health P.O. Box 997414, MS 7610 Sacramento, CA 95899-7414 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

ML15026A065 OFFICE NRR/DPR/PROB NRR/DPR/PROB NRR/DPR/PROB NAME JNguyen CRevelle KHsuehPIsaac for DATE 01/28/2015 01/29 /2015 02/03/2015 ENCLOSURE 1 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:

50-607/OL-15-01 FACILITY DOCKET NO.:

50-607 FACILITY LICENSE NO.:

R-130 FACILITY:

University Of California-Davis TRIGA Reactor EXAMINATION DATES:

January 15, 2015 SUBMITTED BY:

__________/RA/ ______

02/03/2015 John T. Nguyen, Chief Examiner Date

SUMMARY

During the week of January 12, the NRC administered the written examination to one Reactor Operator-Retake license candidate. The candidate passed all applicable portions of the examinations.

REPORT DETAILS

1.

Examiner:

John T. Nguyen, Chief Examiner, NRC

2.

Results:

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

3.

Exit Meeting:

There was no exit meeting due to the type of the examination.

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:

University Of California-Davis REACTOR TYPE:

TRIGA DATE ADMINISTERED:

January 15, 2015 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% score is required to pass the examination. Examinations will be picked up one (1) hours after the examination starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 100 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

B. NORMAL/EMERG PROCEDURES & RAD CON A N S W E R S H E E T 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 ___ (0.25 each)

B05 a b c d ___

B06 a ___ b ___ c ___ d ___ (0.25 each)

B07 a b c d ___

B08 a b c d ___

B09 a ___ b ___ c ___ (0.33 each)

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 ___

B19 a b c d ___

B20 a b c d ___

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

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.

EQUATION SHEET DR - Rem, Ci - curies, E - Mev, R - feet 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

°F = 9/5 °C + 32 1 gal (H2O) 8 lbm

°C = 5/9 (°F - 32) cP = 1.0 BTU/hr/lbm/°F cp = 1 cal/sec/gm/°C

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ENCLOSURE 2 University Of California-Davis Operator Licensing Examination Week of January 12, 2015

Section B - Normal/Emergency Procedures and Radiological Controls QUESTION B.1

[1.0 point]

The following emergency class action levels pertain to which emergency class, a major injury such as a burn, a person experiencing a heart attack, or a person internally contaminated to a level greater than any occupational dose limit:

a. Class 0 - Personnel and Operational Levels

b. Class I - Notification of Unusual Events

c. Class II - Alert

d. Class III - Site Area Emergency QUESTION B.2

[1.0 point]

Per UCD-MNRC Radiation Safety Procedures, TLD badges, or equivalent, will be exchanged:

a. Daily

b. Weekly

c. Monthly

d. Quarterly QUESTION B.3

[1.0 point]

The reactor shall NOT be operated in pulse mode unless the following measuring channels are operable:

a. 1 linear power channel and 1 log power channel

b. 2 fuel temperature channels and 1 pulse channel

c. 1 reactor power level safety channel and 2 linear power channels

d. 1 log power channel, 1 linear power channel, and 1 reactor power level safety channel

Section B - Normal/Emergency Procedures and Radiological Controls QUESTION B.4

[1.0 point, 0.25 each]

Match the limiting condition for operations from Column B (each answer used only once) with Column A:

Column A Column B

a. Steady state operation

1. $0.90

b. Pulse mode operation

2. 2 MW

c. Square wave operation

3. $0.50

d. Shutdown margin

4. $1.75 QUESTION B.5

[1.0 point]

Which ONE of the following unplanned events would require a telephone call or similar conveyance within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC?

a. Violation of Safety Limit

b. A personnel change involving UCD-MNRC Director

c. A personnel change involving UCD-MNRC Vice Chancellor for Research

d. Any significant change in the transient or accident analysis as described in the SAR QUESTION B.6

[1.0 point, 0.25 each]

Match the following 10CFR parts:

Column A Column B

a. Operators Licenses

1. Part 19

b. Standards for Protection against Radiation

2. Part 20

c. Notices, Instructions, and Reports to Workers

3. Part 50

d. Domestic Licensing of Production and Utilization Facilities

4. Part 55

Section B - Normal/Emergency Procedures and Radiological Controls QUESTION B.7

[1.0 point]

How long will it take a 50 Curie source, with a half-life of 5.27 years, to decay to 2 Curie?

a. 10 Years

b. 15 Years

c. 25 Years

d. 35 Years QUESTION B.8

[1.0 point]

Which ONE of the following sections listed in TS describes minimum staffing requirements, selection and training of personnel, and review, audit, recommendation, and approval:

a. Design Features

b. Administrative Controls

c. Surveillance Requirement

d. Limiting Conditions for Operation QUESTION B.9

[1.0 point, 0.33 each]

Per UCD/MNRC Emergency Classification, match the emergency class with the emergency action level (use each only once):

Column A

a. Loss of greater than 80% of the reactor tank water

b. An explosion or a fire in the reactor building lasting more than 15 minutes

c. A person experiencing a heart attack, stroke, or other severe physical ailment of rapid onset Column B

1. Class 0 - Personnel and Operational Levels

2. Class I - Notification of Unusual Events

3. Class II - Alert

Section B - Normal/Emergency Procedures and Radiological Controls QUESTION B.10

[1 point]

10 CFR 20 limits the annual occupational exposure to the WHOLE BODY of an individual to:

a. 50 rem

b. 15 rem

c. 100 rem

d. 5 rem QUESTION B.11

[1.0 point]

During reactor operations, you received CSC DIS064 TIME-OUT. Per SOP 8, Reponses to Alarms Received while Operating, you should:

a. Notify the Reactor Supervisor and replace the CSC computer hard drive

b. Notify the SRO and attempt to reboot the CSC computer

c. Notify the SRO and attempt to reboot the DAC computer

d. No action required because the message showed after CSC computer rebooted.

QUESTION B.12

[1.0 point]

Assume an individual has received whole body occupational exposures of:

10 mrads of beta 10 mrads of alpha What would be the cumulative dose equivalent (HT) in mrem for this individual?

a. 20 mrem

b. 200 mrem

c. 210 mrem

d. 310 mrem

Section B - Normal/Emergency Procedures and Radiological Controls QUESTION B.13

[1.0 point]

You perform a fuel element inspection. In measuring the elongation, you find the length of one fuel element exceeds its initial length 0.135 inches. For this measurement, you will:

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

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

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

continue the fuel inspection because this length is within TS limit QUESTION B.14

[1.0 point]

Explosive materials of TNT equivalent irradiated in any radiography bay shall be limited such that the maximum amount is no greater than ______.

a. 1.5 curies

b. 25 milligrams

c. 3 pounds

d. 5 kilograms QUESTION B.15

[1.0 point]

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

a. Replace an identical Fuel Temperature Channel

b. Measure a control rod drop time with new technique

c. Revise a control rod calibration procedure

d. Replace a fission chamber with a compensated ion chamber for the NM-1000 Channel

Section B - Normal/Emergency Procedures and Radiological Controls QUESTION B.16

[1.0 point]

Per UCD/MNRC Technical Specifications 3.1.3.b, The MAXIMUM available excess reactivity in reference core condition for steady state operation shall NOT exceed _____.

a. $0.90

b. $1.75

c. $5.00

d. $9.50 QUESTION B.17

[1.0 point]

During reactor operations, you receive a DEMIN OUTLET CONDTVTY alarm. Per SOP 8, Reponses to Alarms Received while Operating, you should:

a. Notify the Reactor Supervisor and replace the resin canisters

b. Notify the SRO and switch to the spare of resin canisters

c. Turn primary pumps OFF and notify the SRO

d. Scram the reactor and notify the SRO QUESTION B.18

[1.0 point]

The reactor is in a SHUTDOWN condition, as defined by UCD/MNRC Technical Specifications, when:

a. all rods are inserted to the reactor core

b. the reactor is subcritical by at least $1.00 in the reference core condition, but EXCLUDED the reactivity worth of all installed experiments

c. the console key is OFF position and no work is in progress involving core fuel, core structure, installed control rods, or control rod drives

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

Section B - Normal/Emergency Procedures and Radiological Controls QUESTION B.19

[1.0 point]

Select the list that gives the order of types of radiation from the LEAST penetrating to the MOST penetrating (i.e. travels the further in air).

a. neutron, gamma, beta, alpha.

b. alpha, beta, neutron, gamma.

c. beta, alpha, gamma, neutron.

d. alpha, neutron, beta, gamma.

QUESTION B.20

[1.0 point]

Which ONE of the following meets the objective of Safety Limit?

a. Setting for an automatic protective device related to a variable having a significant safety function

b. Limits on important process variables to protect the fuel element cladding

c. Limits imposed on reactor core reactivity for a reference core condition

d. Constraints included in the Technical Specifications that are required for safe operation of the facility

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

Section B Normal, Emergency and Radiological Control Procedures B.1 Answer:

a

Reference:

UCD Emergency Plan, Table 5.1 B.2 Answer:

c

Reference:

UCD-MNRC Radiation Safety Procedure, 5.2.1.2 B.3 Answer:

b

Reference:

TS, Table 3.2.2 B.4 Answer:

a (2), b (4), c (1), d (3)

Reference:

TS 3.1.1 - 3.1.3 B.5 Answer:

a

Reference:

TS 6.7.2.a B.6 Answer:

a (4), b (2), c (1), d (3)

Reference:

10 CFR B.7 Answer:

c

Reference:

T A = A*e -t 2Ci = 50Ci* e -(t)

Ln(2/50) = -ln2/5.27 yr*(t) --> -3.2189/-0.1315 solve for t: 24.47 years B.8 Answer:

b

Reference:

TS, 6.0 B.9 Answer:

a (3), b (2), c (1)

Reference:

UCD Emergency Plan, Table 5.1 B.10 Answer:

d

Reference:

10 CFR 20.1201 B.11 Answer:

b

Reference:

SOP 8, Reponses to Alarms Received while Operating

B.12 Answer:

c

Reference:

10 CFR 20 B.13 Answer:

c

Reference:

TS 3.2.4 B.14 Answer:

c

Reference:

TS 3.8.2 B.15 Answer:

c

Reference:

10 CFR 50.59 B.16 Answer:

b

Reference:

SOP 4.4, Pulse Mode B.17 Answer:

b

Reference:

SOP 8, Reponses to Alarms Received while Operating B.18 Answer:

d

Reference:

TS 1.25 B.19 Answer:

b

Reference:

NRC standard question B.20 Answer:

b

Reference:

TS 2.1