ML111170520

Retake Examination Report 50-326/OL-11-01, University of California - Irvine

ML111170520
Person / Time
Site:	University of California - Irvine
Issue date:	05/05/2011
From:	Johnny Eads Research and Test Reactors Branch B
To:	Geoffrey Miller University of California - Irvine
Shared Package
ml110730007	List: ML110730008 ML111170520
References
50-326/OL-11-001
Download: ML111170520 (19)

Text

May 5, 2011 Dr. George E. Miller Department of Chemistry 516 Physical Sciences 1 University of California, Irvine Irvine, CA 92697-2025

SUBJECT:

RETAKE EXAMINATION REPORT LETTER NO. 50-326/OL-11-01, UNIVERSITY OF CALIFORNIA - IRVINE

Dear Dr. Miller:

During the week of April 18, 2011, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your University of California - Irvine Triga reactor. 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 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 Mr. John T. Nguyen at (301) 415-4007 or via internet e-mail John.Nguyen@nrc.gov.

Sincerely,

/RA/

Johnny Eads, Chief Research and Test Reactors Oversight Branch Division of Policy and Rule Making Office of Nuclear Reactor Regulation.

Docket No. 50-326

Enclosures:

1. Examination Report No. 50-326/OL-11-01

2. Written Examination cc : See next page

May 5, 2011 Dr. George E. Miller Department of Chemistry 516 Physical Sciences 1 University of California, Irvine Irvine, CA 92697-2025

SUBJECT:

RETAKE EXAMINATION REPORT LETTER NO. 50-326/OL-11-01, UNIVERSITY OF CALIFORNIA - IRVINE

Dear Dr. Miller:

During the week of April 18, 2011, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your University of California - Irvine Triga reactor. 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 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 Mr. John T. Nguyen at (301) 415-4007 or via internet e-mail John.Nguyen@nrc.gov.

Sincerely,

/RA/

Johnny Eads, Chief Research and Test Reactors Oversight Branch Division of Policy and Rule Making Office of Nuclear Reactor Regulation.

Docket No. 50-326

Enclosures:

1. Examination Report No. 50-326/OL-11-01

2. Written Examination cc: See next page DISTRIBUTION:

PUBLIC RidsNrrDprPrta RidsNrrDprPrtb Facility File (CRevelle) O-07 F-08 ADAMS ACCESSION #: ML111170520 TEMPLATE #: NRR-079 Office PROB/CE IOLB/OLA PROB/BC Name JNguyen CRevelle JEads Date 4/26/11 5/4/11 05/5/11 OFFICIAL RECORD COPY

University of California at Irvine Docket No. 50-326 cc:

Dr. Scott Rychnovsky, Chair Department of Chemistry University of California, Irvine Irvine, CA 92697-2025 Mr. Steve Hsu Radiological Health Branch State Department of Health Services P.O. Box 9442732 Sacramento, CA 94234-7320 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

EXAMINATION REPORT NO: 50-326/OL-11-01 FACILITY: UNIVERSITY OF CALIFORNIA - IRVINE FACILITY DOCKET NO.: 50-326 FACILITY LICENSE NO.: R-116 SUBMITTED BY: _______/RA/ _______________ 04/23/2011 John T. Nguyen, Chief Examiner Date

SUMMARY

During the week of April 18, 2011, the NRC administered the retake written examination to one Senior Reactor Operator Instant (SRO-I) candidate. The candidate passed all portions of the examinations.

REPORT DETAILS

1. Examiner: John T. Nguyen, Chief Examiner

2. Results:

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

3. Exit Meeting:

Alf Karl Mikael Nilsson, UCI, Senior Reactor Operator John Nguyen, NRC, Examiner The NRC Examiner thanked the facility for their support in the administration of the examination. The facility licensee had no comments on the written examination.

ENCLOSURE 1

U. S. NUCLEAR REGULATORY COMMISSION RESEARCH AND TEST REACTOR OPERATOR LICENSING EXAMINATION FACILITY: UNIVERSITY OF CALIFORNIA - IRVINE REACTOR TYPE: TRIGA DATE ADMINISTERED: 04/19/2011 CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheets provided. Points for each question are indicated in brackets for each question. You must score 70% in each section to pass. Examinations will be picked up three (3) hours after the examination starts.

% of Category  % of Candidates Category Value Total Score Value Category 16.00 33.33 A. Reactor Theory, Thermodynamics and Facility Operating Characteristics 16.00 33.33 B. Normal and Emergency Operating Procedures and Radiological Controls 16.00 33.33 C. Plant and Radiation Monitoring Systems FINAL GRADE

% TOTALS All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

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. The point value for each question is indicated in [brackets] after the question.

7. If the intent of a question is unclear, ask questions of the examiner only.

8. To pass the examination you must achieve a grade of 70 percent or greater in each category.

9. There is a time limit of three (3) hours for completion of the examination.

10. When you have completed and turned in you examination, leave the examination area

Page 7 EQUATION SHEET

Q& = m& c p T = m& H = UA T ( - )2 P max = * -4 l = 1 x 10 seconds 2 (k)l S CR 1 (1 - K eff 1 ) = CR 2 (1 - K eff 2 )

SCR =

1 - K eff eff = 0.1 sec-1 SUR = 26.06 eff 1 - K eff 0 1 CR1

- M= M= =

1 - K eff 1 1 - K eff CR 2 P = P0 10 SUR(t) P = P0 e t

(1 - )

P= P0 (1 - K eff ) l * -

SDM = = =

l

+

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) 2 DR1 d 1 = DR 2 d 2 2

DR = DR0 e - t DR = 2 R

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

Page 8 1 BTU = 778 ft-lbf EF = 9/5 EC + 32 1 gal (H2O) . 8 lbm EC = 5/9 (EF - 32)

Section A L Theory, Thermo, and Facility Characteristics Page 9 ANSWER SHEET Multiple Choice (Circle or X your choice)

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

A001 a b c d __

A002 a b c d __

A003 a b c d __

A004 a b c d __

A005 a b c d __

A006 a b c d __

A007 a b c d __

A008 a b c d __

A009 a b c d __

A010 a b c d __

A011 a b c d __

A012 a b c d __

A013 a b c d __

A014 a b c d __

A015 a b c d __

Section B Normal/Emerg. Procedures & Rad Con Page 10 ANSWER SHEET Multiple Choice (Circle or X your choice)

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

B001 a b c d __

B002 a b c d __

B003 a b c d __

B004 a b c d __

B005 a b c d __

B006 a b c d __

B007 a b c d __

B008 a b c d __

B009 a b c d __

B010 a b c d __

B011 a b c d __

B012 a b c d __

B013 a b c d __

B014 a b c d __

B015 a b c d __

B016 a b c d __

Section C Facility and Radiation Monitoring Systems Page 11 ANSWER SHEET Multiple Choice (Circle or X your choice)

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

C001 a b c d __

C002 a b c d __

C003 a b c d __

C004 a b c d __

C005 a b c d __

C006 a b c d __

C007 a b c d __

C008 a b c d __

C009 a b c d __

C010 a b c d __

C011 a b c d __

C012 a b c d __

C013 a b c d __

C014 a b c d __

C015 a b c d __

• • • • • END OF EXAMINATION *****

Section B Normal/Emergency Procedures and Radiological Controls Page 12 Question B.1 [1.0 point]

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

a. all rods are inserted and the reactor console is secured.

b. the reactor is subcritical by at least $1.00 of reactivity 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.2 [1.0 point]

Two sheets of 1/4 inch thick lead reduce a radiation beam from 400 mRem/hr to 200 mRem/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. 50 mR/hr

b. 75 mR/hr

c. 100 mR/hr

d. 150 mR/hr Question B.3 [1.0 point]

A room contains a source which, when exposed, results in a general area dose rate of 175 mRem/hour. This source is scheduled to be exposed continuously for 35 days. Select an acceptable method for controlling radiation exposure from the source within this room.

a. Post the area with the words "Danger-Radiation Area".

b. Lock the room to prevent inadvertent entry into the room.

c. Equip the room with a motion detector that will alarm in the control room.

d. Equip the room with a device to visually display the current dose rate within the room.

Section B Normal/Emergency Procedures and Radiological Controls Page 13 Question B.4 [1.0 point]

The special unit for absorbed dose Rem is defined in 10 CFR Part 20 in terms of a dose equivalent. What does the term dose equivalent relate to?

a. It is derived by accounting for the amount of radioactive material taken into the body of an adult worker by inhalation or ingestion in one year.

b. It is equal to the absorbed dose (Rad) multiplied by the quality factor (Q) of the radiation.

c. It is equal to the absorbed dose (Rad) divided by the quality factor (Q) of the radiation.

d. It is the equivalent dose one would receive during the 50-year period following intake.

Question B.5 [1.0 point]

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

a. H3

b. N16

c. Ar41

d. U235 Question B.6 [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.

Section B Normal/Emergency Procedures and Radiological Controls Page 14 Question B.7 [1.0 point]

Using a calibrated source of 5 curies of Co-60, what is the exposure rate at 6 feet from the source? Co-60 emits two gamma photons per decay with energies of 1.17 Mev and 1.33 Mev.

a. 750 mR/hr

b. 2.1 R/hr

c. 8.3 R/hr

d. 12.5 R/hr Question B.8 [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 Question B.9 [1.0 point]

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

a. Iodine 135

b. Strontium 90

c. A short half-life material

d. 30 mg of explosive material

Section B Normal/Emergency Procedures and Radiological Controls Page 15 Question B.10 [1.0 point]

The standard fuel elements shall be measured for length and bend at intervals separated by not more than ________ of magnitude greater than $1.00 of reactivity, but the intervals shall not exceed _______.

a. 300 pulses, 60 months

b. 500 pulses, 60 months

c. 300 pulses, 36 months

d. 500 pulses, 36 months Question B.11 [1.0 point]

An example of Byproduct Material would be.

a. Pu-239

b. U-233

c. U-235

d. Co-60 Question B.12 [1.0 point]

The reactor shall not be operated unless the excess reactivity is less than $3.00. This is an example of a:

a. safety limit.

b. limiting safety system setting.

c. limiting condition for operation.

d. surveillance requirement.

Section B Normal/Emergency Procedures and Radiological Controls Page 16 Question B.13 [1.0 point]

Substantive changes to the installation/removal of fuel element procedure described in the SOP shall be made only with the approval of :

a. the Senior Reactor Operator (SRO)

b. the Reactor Supervisor (RS)

c. the Radiation Safety Officer (RSO)

d. the Reactor Operations Committee (ROC)

Question B.14 [1.0 point]

Which ONE of the following is the correct statement regarding modes of the operation (ON-startup or OFF-shut off) of reactor systems identified below when the Reactor Operator activates the CAM alarm in the EMERGENCY MODE?

a. pneumatic system blower: ON; purge exhaust fan: OFF; main air inlets: ON; central system alarm indication: OFF

b. pneumatic system blower: ON; purge exhaust fan: ON; main air inlets: ON; central system alarm indication: ON

c. pneumatic system blower: OFF; purge exhaust fan: OFF; main air inlets: ON; central system alarm indication: ON

d. pneumatic system blower: OFF; purge exhaust fan: ON; main air inlets: OFF; central system alarm indication: ON Question B.15 [1.0 point]

Per UCI Technical Specifications, which ONE of the following will prevent application of air to the transient rods during the pulse mode?

a. the REG rod is fully UP

b. the SHIM rod is fully UP

c. the steady state power is at 2 kW

d. Cylinder of the adjustable transient stays at 50% of full length

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

During an emergency, which ONE of the following is the line of succession regarding orderly authority of the Reactor Incident Commander?

a. Reactor Supervisor, Senior Reactor Operator, most technically experienced on-site member of reactor staff, Radiation Protection Officer, Facilities Manager for School of Physical Sciences

b. Most technically experienced on-site member of reactor staff, Reactor Supervisor, Senior Reactor Operator, Radiation Protection Officer, Facilities Manager for School of Physical Sciences

c. Radiation Protection Officer, Reactor Supervisor, Senior Reactor Operator, most technically experienced on-site member of reactor staff, Facilities Manager for School of Physical Sciences

d. Senior Reactor Operator, Reactor Supervisor, most technically experienced on-site member of reactor staff, Radiation Protection Officer, Facilities Manager for School of Physical Sciences

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

• • • • • • • • • • • • • • • • • • • End of the Exam ***************************

Section C Plant and Radiation Monitoring Systems Page 18 Answer Key B.1 Answer: b

Reference:

TS 1.1 B.2 Answer: c

Reference:

A 1/2 thickness is 2 sheets. Add another 2 sheets, a radiation level will reduce by another 1/2, or 100 mR/hr B.3 Answer: b

Reference:

10CFR20.1601(a)(3)

B.4 Answer: b

Reference:

10CFR20.1003 B.5 Answer: b.

Reference:

Chart of the Nuclides B.6 Answer: b

Reference:

NRC standard question B.7 Answer: b

Reference:

R/hr = 6CE/r2 = 6 x 5 x 1*(1.17+1.33)/ 62 = 2.08 R/hr B.8 Answer: b

Reference:

TS 2.1 B.9 Answer: d

Reference:

TS 3.8 B.10 Answer: b

Reference:

TS 4.1 B.11 Answer: d

Reference:

Byproduct material is radioactive material made radioactive by the process of using special nuclear material; 10 CFR Part 20.1003 B.12 Answer: c

Reference:

TS 3.3.1

Section C Plant and Radiation Monitoring Systems Page 19 B.13 Answer: d

Reference:

TS 6.3 B.14 Answer: d

Reference:

SOP 4.7.3 B.15 Answer: c

Reference:

TS 3.4 B.16 Answer: a

Reference:

EP 3.4