ML16291A017
| ML16291A017 | |
| Person / Time | |
|---|---|
| Site: | University of New Mexico |
| Issue date: | 10/20/2016 |
| From: | Anthony Mendiola Research and Test Reactors Oversight Branch |
| To: | Busch R Univ of New Mexico |
| Anthony Mendiola | |
| Shared Package | |
| ML16204A033 | List: |
| References | |
| 50-252/OL-16 | |
| Download: ML16291A017 (17) | |
Text
October 20, 2016 Dr. Robert Busch, Chief Reactor Supervisor Nuclear Engineering Department 209 Farris Engineering, MSC 01-1120 University of New Mexico Albuquerque, NM 87131-0001
SUBJECT:
EXAMINATION REPORT NO. 50-252/OL-16-02, UNIVERSITY OF NEW MEXICO
Dear Dr. Busch:
During the week of September 12, 2016, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your University of New Mexico 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 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 Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-252
Enclosures:
- 1. Examination Report No. 50-252/OL-16-02
- 2. Written examination cc: w/o enclosures: See next page
Dr. Robert Busch, Chief Reactor Supervisor October 20, 2016 Nuclear Engineering Department 209 Farris Engineering, MSC 01-1120 University of New Mexico Albuquerque, NM 87131-0001
SUBJECT:
EXAMINATION REPORT NO. 50-252/OL-16-02, UNIVERSITY OF NEW MEXICO
Dear Dr. Busch:
During the week of September 12, 2016, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your University of New Mexico 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 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 Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-252
Enclosures:
- 1. Examination Report No. 50-252/OL-16-02
- 2. Written examination cc: w/o enclosures: See next page DISTRIBUTION PUBLIC AMendiola JEads AAdams Eallen ADAMS ACCESSION #: ML16291A017 TEMPLATE #:NRR-079 OFFICE NRR/DPR/PROB/CE NRR/DRP/PROB/OLA NRR/DPR/PROB/BC NAME MDeSouza/JNguyen for CRevelle AMendiola DATE 09/20/2016 10/11/2016 10/20/2016 OFFICIAL RECORD COPY
University of New Mexico Reactor Docket No. 50-252 cc:
City Manager City of Albuquerque City Hall Albuquerque, NM 87101 Dr. Anil Prinja, Chair Nuclear Engineering Department 209 Farris Engineering, MSC 01-1120 1 University of New Mexico Albuquerque, NM 87131-0001 Salmen Locksen, Radiation Safety Officer 1 University of New Mexico MCS08 4560 Albuquerque, NM 87131 Chief, Radiation Control Bureau Field Operations Division Environment Department Harold S. Runnels Bldg.
1190 St. Francis Drive, Rm S2100 Santa Fe, NM 87505-4173 Deputy Secretary, Office of the Secretary New Mexico State Environment Department 1190 St. Francis Drive, Suite 4050N Santa Fe, NM 87502-6110 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611
ENCLOSURE 1 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-252/OL-16-02 FACILITY DOCKET NO.:
50-252 FACILITY LICENSE NO.:
R-102 FACILITY:
University of New Mexico Reactor EXAMINATION DATES:
September 14, 2015 SUBMITTED BY:
__________/RA/_____________
_09/19/2016_
Michele DeSouza, Chief Examiner Date
SUMMARY
During the week of September 12, 2016 the NRC administered a retake licensing examination to one Reactor Operator (RO) candidate. The candidate passed Category B of the retake examination.
REPORT DETAILS
- 1.
Examiner:
Michele DeSouza, Chief Examiner, NRC
- 2.
Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 1/0 0/0 1/0 Operating Tests N/A 0/0 N/A Overall 1/0 0/0 1/0
- 3.
Exit Meeting:
Michele C. DeSouza, Chief Examiner, NRC Ken Carpenter, UNM Facilities Manager Upon completion of the examination, the NRC Examiner met with facility staff representative to discuss the results. At the conclusion of the meeting, the NRC examiner thanked the facility for their support in the administration of the examination.
ENCLOSURE 2 U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
University of New Mexico REACTOR TYPE:
AGN-201 DATE ADMINISTERED:
09/14/2016 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 WAIVE NA WAIVE A.
REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 20.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS WAIVE NA _ WAIVE C.
FACILITY AND RADIATION MONITORING SYSTEMS 20.00 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature
Category B - Normal/Emergency Operating Procedures and Radiological Controls 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 ___
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 ____ (0.25 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 ___ (0.25 each)
B17 a b c d ___
B18 a b c d ___
B19 a b c d ___
(***** END OF CATEGORY B *****)
(********** END OF EXAMINATION **********)
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 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
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Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.01
[1.0 point]
Which ONE of the following reactor conditions is a violation of UNM Technical Specifications?
- a. Absolute reactivity is 0.55%k/k
- b. Shutdown margin is $0.50
- c. Shield water temperature is 15oC
- d. Excess reactivity is 0.20%k/k QUESTION B.02
[1.0 point]
In accordance with UNM emergency plan, which ONE of the following is the MAXIMUM exposure and intake limit for life threatening situations, or to deal with situations which are likely to lead to life-threatening situations?
- a. 25 Rem
- b. 30 Rem
- c. 45 Rem
- d. 50 Rem QUESTION B.03
[1.0 point]
Which ONE of the following surveillances DOES NOT require a maximum annual frequency?
- a. Manual SCRAM
- b. Control rods and drives
- c. Control rod SCRAM
- d. Power level measuring channels calibration
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.04
[1.0 point, 0.25 each]
Match the emergency situation listed in Column A with the classification level listed in Column B. (Answers may be used more than once or not at all)
Column A Column B
- a. Tornado
- 1. Notification of UNM police
- b. Civil disturbance to the reactor facility
- 2. Abnormal levels of radiation
- c. Nuclear Engineering lab fire extinguished in 5 minutes 3. No Classification
- d. Site boundary level of 15MPC QUESTION B.05
[1.0 point]
Per UNM Technical Specifications, how often is a channel test of the seismic displacement interlock required to be performed?
- a. Daily
- b. Quarterly
- c. Semi-annually
- d. Annually QUESTION B.06
[1.0 point]
According to the UNM Emergency Plan, transportation of injured personnel, including those who may be radioactively contaminated requiring transport to the hospital will be by____________?
- a. Senior Reactor Operator
- b. Reactor Safety Committee
- c. UNM Police Department
- d. Albuquerque Fire Department
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.07
[1.0 point]
A radioactive source has a current activity of 3 Curies. The activity 30 years ago was 300 Curies. What is the half-life of the radioactive source?
- a. 4.5 years
- b. 10.5 years
- c. 15 years
- d. 20 years QUESTION B.08
[1.0 point]
How many hours (MINIMUM) are Test and Research Reactors licensed operators required to perform the functions of a licensed operator to resume activities if a licensee has not been actively performing the functions of a reactor operator or senior reactor operator?
- a. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
- b. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
- c. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
- d. 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> QUESTION B.09
[1.0 point, 0.25 each]
Identify each of the following surveillances as a channel check (CHECK), a channel test (TEST),
or a channel calibration (CAL). Write the correct answer on your answer sheet next to the space given for each example listed below.
- a. During performance of the daily checklist, you compare the readings of radiation area monitor one and radiation monitor two
- 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 monitor channel in accordance with recent data collected during a reactor power calibration
- d. You expose a 2 mCi check source to the continuous air monitor detector to verify that its output is operable
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.10
[1.0 point]
UNM Technical Specification basis for the MAXIMUM core temperature limit is to prevent which ONE of the following?
- a. Instrument inaccuracies
- b. Boiling of the shield water
- c. Release of fission products
- d. Breakdown of the graphite reflector QUESTION B.11
[1.0 point]
Which ONE of the following meets the MINIMUM staffing requirement when the reactor is NOT secured?
- a. 1 RO in the control room, 1 person in NRL, 1 rad safety, and one on call reactor supervisor
- b. 1 SRO in the control room, 1 rad safety, and one on call reactor supervisor
- c. 1 RO in the control room, 1 person in control room, and one on call reactor supervisor
- d. 1 SRO in the control room and one on call reactor supervisor QUESTION B.12
[1.0 point]
Calculate an individuals total whole body dose given the individual received the following doses: 20 mrad of alpha, 10 mrad of gamma, and 5 mrad of neutron (unknown energy)
- a. 35 mrem
- b. 415 mrem
- c. 435 mrem
- d. 460 mrem QUESTION B.13
[1.0 point]
A radiation field is 330 mR/hr at 4 feet. What is your dose rate at 2 feet away from the source?
- a. 499 mR/hr
- b. 580 mR/hr
- c. 660 mR/hr
- d. 1320 mR/hr
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.14
[1.0 point]
Which ONE of the following experiments is NOT allowed in accordance with UNM Technical Specifications?
- a. Liquid fissionable materials
- b. Radioactive materials
- c. Explosive materials
- d. Corrosive materials QUESTION B.15
[1.0 point]
Which ONE of the following locations is the normal Emergency Support Center per the Emergency Plan?
- a. Reactor Control Room
- b. Reactor Shop
- c. Nuclear Engineering Lab, room 60
- d. Reactor Supervisors Office QUESTION B.16
[1.0 point, 0.25 each]
Match the appropriate 10CFR part in Column A with the requirements in Column B.
Column A Column B
- a. 10CFR19
- 1. Technical information including the proposed maximum power level
- b. 10CFR20 2. Individual radiation exposure data
- c. 10CFR50
- 3. Postings of notices to workers
- d. 10CFR55
- 4. Medical examination by a physician every two years
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.17
[1.0 point]
Which ONE of the following would be considered a non-routine operation?
- a. Safety interlock checks
- b. Whenever the console is energized
- c. Calibration of Nuclear Instrumentation
- d. Core excess reactivity and the worth of the coarse and fine control rods are measured QUESTION B.18
[1.0 point, 0.33 each]
Match the following limitations in Column A with its specification in Column B (Assume natural convection; Answers may be used more than once or not at all)
Column A Column B
- a. Safety Limit
- 1. Maximum shutdown margin $1.00
- b. Limiting Safety System Setting
- 2. Maximum core temperature 200oC
- c. Limiting Condition for Operation
- 3. Maximum high power of 6W QUESTION B.19
[1.0 point]
A 2.5 curie source emits a 1.332MeV gamma and a 1.173MeV gamma 100% of the time. The source will be placed in the reactor storage room. How far from the source should a high radiation area sign be posted?
- a. Not required
- b. 10 feet
- c. 15 feet
- d. 20 feet
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B. 20
[1.0 point]
Which ONE of the following radiation levels at the console requires the operator to order an evacuation?
- a. 25
- b. 50
- c. 75
- d. 100
(***** End of Category B *****)
(******End of Examination******)
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.1 Answer:
c
Reference:
UNM Technical Specifications 2.2 and 3.2 B.2 Answer:
a
Reference:
10CFR20.1206 and UNM Emergency Plan 7.3.3 B.3 Answer:
a
Reference:
UNM Technical Specifications 4.1 and 4.2 B.4 Answer:
a(1),b(1),c(3),d(2)
Reference:
UNM Emergency Plan B.5 Answer:
d
Reference:
UNM Technical Specifications 4.2 B.6 Answer:
d
Reference:
UNM Emergency Plan 8.3.2 B.7 Answer:
a
Reference:
T A = A*e -t 3Ci = 300Ci* e -(t)
Note: = -ln2/t1/2 Ln(3/300) = -ln2/X yr*(30 years) --> -4.605/-1.021 solve for t: 4.51 years B.8 Answer:
b
Reference:
B.9 Answer:
a (check), b (test), c (cal), d (test)
Reference:
UNM Technical Specifications 1, definitions B.10 Answer:
c
Reference:
UNM Technical Specifications 2.1 B.11 Answer:
a
Reference:
UNM Technical Specifications 6.1.3 B.12 Answer:
d
Reference:
20mrad Alpha x 20 = 400mrem, 10mrad Gamma x 1 = 10mrem, 5mrad neutron x 10 = 50mrem 400mrem + 10mrem + 50mrem = 460mrem
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.13 Answer:
d
Reference:
I1D12=I2D22 330mR/hr@(4ft)2=I2@(2ft)2 1320mR/hr B.14 Answer:
c
Reference:
UNM Technical Specifications 3.3 B.15 Answer:
c
Reference:
UNM Emergency Plan 8.1 B.16 Answer:
a (3), b(2), c(1), d(4)
Reference:
10CFR19.11, 10CFR20.1501(2)(i), 10CFR50.34(1)(ii)(A), 10CFR55.21 B.17 Answer:
b
Reference:
UNM Reactor Operation and Training Manual III, Operating Procedures B.18 Answer:
a(2),b(3),c(1)
Reference:
UNM Technical Specifications 2.1, 2.2, and 3.1 B.19 Answer:
d
Reference:
I=6CEn=R/hr@ft. 6 x 25Ci x [(1.332Mev x 100%)+(1.173 x 100%)] = 375.75 R/hr@ (1ft)2 = 0.1 R/hr@ D2 = 376 R/hr = 19.4 ft.
B.20 Answer:
d
Reference:
UNM Emergency Plan 7.3.2