ML22118A380
| ML22118A380 | |
| Person / Time | |
|---|---|
| Site: | University of Utah |
| Issue date: | 04/28/2022 |
| From: | Travis Tate NRC/NRR/DANU/UNPO |
| To: | Sjoden G Univ of Utah |
| Nguyen J, NRR/DANU, 415-4007 | |
| Shared Package | |
| ML22018A269 | List: |
| References | |
| 50-407/22-01, HQ-OLTS 50-407/OL-22-01 | |
| Download: ML22118A380 (1) | |
Text
April 28, 2022
Dr. Glenn E. Sjoden, Director Utah Nuclear Engineering Program Professor, Energy Solutions Presidential Endowed Chair Dept of Civil and Environmental Engineering University of Utah 110 Central Campus Drive, Rm 2000 Salt Lake City, UT 84112
SUBJECT:
EXAMINATION REPORT NO. 50-407/OL 01, UNIVERSITY OF UTAH
Dear Dr. Sjoden:
During the week of March 14, 2022, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your University of Utah 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 Mr. John T. Nguyen at (301) 415-4007 or via internet e-mail John.Nguyen@nrc.gov.
Sincerely,
Travis L. Tate, Chief Non-Power Production and Utilization Facility Oversight Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation
Docket No. 50-407
Enclosures:
- 1. Examination Report No. 50- 407/
OL-22-01
- 2. Written Examination
cc: w/o enclosures: See next page
ML22118A380 NRR- 079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME JNguyen ZTaru TTate DATE 04/01/2022 04/26/2022 04/28/2022 University of Utah Docket No. 50 -407
cc:
Mayor of Salt Lake City 451 South State Room 306 Salt Lake City, UT 84111
Dr. Andrew S. Weyrich Vice President for Research University of Utah 201 S Presidents Circle, Room 210 Salt Lake City, UT 84112-9011
Frederick A. Monette Interim Director and RSO Radiological Health 75 S 2000 E, Room 322 University of Utah Salt Lake City, UT 84112
Test, Research and Training Reactor Newsletter Attention: Ms. Amber Johnson Dept of Materials Science and Engineering University of Maryland 4418 Stadium Drive College Park, MD 20742-2115
Director, Division of Radiation Control Dept. of Environmental Quality 195 North 1950 West P.O. Box 14485 Salt Lake City, UT 84114-4850
Ms. Amanda Foley, Reactor Supervisor The University of Utah University of Utah Nuclear Engineering Program 50 South Central Drive, Room 1206 Salt Lake City, UT 84112
U.S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT
REPORT NO.: 50- 407 /OL-22-01
FACILITY DOCKET NO.: 50- 407
FACILITY LICENSE NO.: R-126
FACILITY: University of Utah
EXAMINATION DATES: March 18, 20 22
SUBMITTED BY: Jo hn Ng uyen 04 /01/2022 John T. Nguyen, Chief Examiner Date
SUMMARY
During the week of March 14, 2022, the NRC administered a retake examination to one Reactor Operator (RO) and one Senior Reactor Operator Instant (SROI) candidates who previously failed the category B of the written examination in September 2021. Both candidate s passed the retake examination.
REPORT DETAILS
- 1. Examiner: John T. Nguyen, Chief Examiner, NRC
- 2. Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 1/0 1/0 2/0 Operating Tests Excusal Excusal Excusal Overall 1/0 1/0 2/0
- 3. Exit Meeting:
John T. Nguyen, Chief Examiner, NRC Andrew Allison, Reactor Supervisor, UUTR
Facility comments were accepted prior to the administration of the written examination.
At the conclusion of the meeting, the NRC examiner thanked the facility for their support in the administration of the examinations.
ENCLOSURE 1 University of Utah
Operator Licensing Examination
Week of March 14, 20 22
ENCLOSURE 2 U.S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION
FACILITY: University of Utah
REACTOR TYPE: TRIGA
DATE ADMINISTERED: 03/ 18/2022
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 one hour after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY
20.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS
20.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL COGE NTROLS
20.00 33.3 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 Control s
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 ______ (0.25 each)
B08 a b c d ___
B09 a ______ b ______ c ______ d ______ (0.25 each)
B10 a ______ b ______ c ______ d ______ (0.25 each)
B11 a b c d ___
B12 a b c d ___
B13 a b c d ___
B14 a ______ b ______ c ______ d ______ (0.25 each)
B15 a ______ b ______ c ______ d ______ (0.25 each)
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 one (1) hour for completion of this examination.
EQUATION SHEET
( )2 Q P = mcT=mH=UATPmax = =0.1sec1
( )2 eff
t S S P 0=Pe SCR = 1* =1 4x10sec Keff
+ CR1 ( ) ( ) CR 1=22 SUR 06= 26.effCR ( ) ( )1 2K=CR 1 effeff K1 12
P =( )1 P M = 1 = CR2 SUR( )
0 1 K CR P = P0 10 t eff 1
- 1 K K =
eff 2 eff
= +
0.693 T1 = K K 2 eff2 eff1
= K K eff1 eff2
= K 1eff DR = 0DRet 2 2 Keff DR =1 dd1DR22
6 Ci E ( )n ( ) 2( )2 DR = 2 = 1 R2 Peak Peak 2 1
DR - Rem, Ci - curies, E - Mev, R - feet
1 Curie = 3.7 x 10 10 dis/sec 1 kg = 2.21 lb 1 Horsepower = 2.54 x 10 3 BTU/hr 1 Mw = 3.41 x 10 6 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
Category B: Normal/Emergency Operating Procedures and Radiological Controls
QUESTION B.01 [1.0 point]
Per UUTR Technical Specifications, which ONE of the following is the most correct statement regarding the basis of limiting 1000 °C temperature for stainless-steel clad?
- a. It is temperature limit for the reactor to reduce the time of reactor scram, therefore it prevents exceeding the safety limit.
- b. It is a temperature limit for a fuel cladding failure during Loss of Coolant Accident (LOCA).
- c. It is the temperature limit to ensure that the cladding surface of fuel rod has the maximum heat transfer, therefore maintaining the safety margin.
- d. It is the temperature limit to ensure that the stress in the cladding because of hydrogen pressure from the disassociation of zirconium hydride will remain below the ultimate stress.
QUESTION B.02 [1.0 point]
The exposure rate for a point source is 250 mR/hr at a distance of 1m. What is the exposure rate at a distance of 4m?
- a. 150 mR/hr
- b. 125 mR/hr
- c. 62.5 mR/hr
- d. 15.63 mR/hr
QUESTION B.03 [1.0 point]
What is a basis for the value of shutdown margin per UUTR Technical Specifications?
- a. The value ensures that the reactor can be restarted from any operating condition with the highest control rod in the fully withdrawn position.
- b. The value ensures that the reactor can be critical from any operating condition with the highest control rod in the fully withdrawn position.
- c. The value ensures that the reactor can be operated from any operating condition with the control rod lowest withdraw position.
- d. The value ensures that the reactor can be shut down from any permissible operating condition with the highest worth scrammable control rod in the fully withdrawn position.
Category B: Normal/Emergency Operating Procedures and Radiological Controls
QUESTION B.04 [1.0 point]
Which of the following events would be classified as Non-Reactor, Safety-Related Event?
- a. Fire within the reactor facility that cannot be extinguished within 15 minutes.
- b. Significant contamination of an individual of the UNEP or MEB facility.
- c. Significant failure of a fuel element initiates all radiation monitor alarms.
- d. A major leak in the primary system that cannot be made up with normal pool fill.
QUESTION B.05 [1.0 point]
Which ONE of the following will meet the MINIMUM staffing requirements during the reactor startup?
- a. 2 ROs in the control room.
- c. 1 RS or SRO in the control room + 1 designated person in the UNEF.
- d. 1 RO in the control room + 1 designated person in the UNEF + 1 SRO or RS at Washington D.C.
QUESTION B.06 [1.0 point]
A two-curie source, emitted 90% of 200 ke V gamma, is to be stored in the reactor building.
What is the dose rate at 10 ft?
- a. 21.6 mR/hr
- b. 216 mR/hr
- c. 2.16 R/hr
- d. 21.6 R/hr
Category B: Normal/Emergency Operating Procedures and Radiological Controls
QUESTION B.07 [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).
- b. You insert a check source to the Radiation Area Monitor to verify an alarm set point.
- c. You adjust Linear channel in accordance with recent data collected from a power channel calibration.
- d. During a steady state power, you compare the readings of the pool water temperature.
QUESTION B.08 [1.0 point]
Per 10 CFR20, a radiation area is defined as:
- a. Any area, accessible to personnel, in which there exists radiation at such levels that a major portion of the body could receive in excess of 100 mR/h.
- b. Any accessible area, controlled by the licensee, where an individual could receive a dose in excess of 5 mR/hr.
- c. Any area, accessible to personnel, in which there exists radiation at such levels that a major portion of the body could receive in 5 consecutive days a dose in excess of 100 mR.
- d. Any area, accessible to personnel, in which there exists radiation in excess of 25 percent of the amounts specified in Appendix B, Table I, Column I of 10 CFR 20.
QUESTION B.09 [1.0 point]
In accordance with the UUTR Technical Specifications, select the allowable surveillance intervals defined by the TS.
- a. Biennial interval not to exceed ______(24/26/30) months
- b. Annual interval not to exceed ________(12/15/16) months
- c. Semiannual interval not to exceed _______(7.0/7.5/8.0) months
- d. Quarterly interval not to exceed ________ (3.0/3.5/4.0) months
Category B: Normal/Emergency Operating Procedures and Radiological Controls
QUESTION B.10 [1.0 point, 0.25 each]
Identify the PRIMARY source (irradiation of air, irradiation of water, irradiation of reactor structure, or fission product) of EACH of the following radioisotopes.
- a. Al-28
- b. Ar-41
- c. N-16
- d. Br-87
QUESTION B.11 [1.0 point]
Per UUTR Technical Specifications, when is the direct presence of a Reactor Supervisor (RS) required?
- a. Control rod calibration.
- b. First reactor startup for the day.
- c. Movement of fuel within the reactor pool.
- d. Relocation of any in-core experiment with a reactivity worth less than one dollar.
QUESTION B.12 [1.0 point]
The MAIN purpose to encapsulate a corrosive material irradiated in the reactor core is to prevent:
- a. contamination in the pool water.
- b. pressure build up in the sample holder.
- c. release of corrosive gas to the reactor bay.
- d. contamination to a reactor operator while handling it.
Category B: Normal/Emergency Operating Procedures and Radiological Controls
QUESTION B.13 [1.0 point]
Which ONE of the following types of radiation detectors does not have an output intensity proportional to the incident radiation energy (e.g., as incident energy increases, the output intensity increases)?
- a. GM
- b. Ion chamber
- c. Scintillation
- d. Proportional counter
QUESTION B.14 [1.0 point, 0.25 each]
Match the Federal Regulation number in Column A with the appropriate topic in Column B.
Column A Column B
- a. 10 CFR 20 1. Operator Licenses
- b. 10 CFR 50 2. Facility Licenses
- c. 10 CFR 55 3. Radiation Protection
QUESTION B.15 [1.0 point, 0.25 each]
Fill out the blanks with correct value of the Limiting Conditions of Operation (LCO) listed in the UUTR Technical Specifications.
Safety System LCO
- a. Core Excess Reactivity ______ $ (1.00/1.20/2.00)
- b. Transverse bend of fuel ______ inches (0.055/0.0625/0.125)
- c. Reactor power ______ kW (90/100/110)
- d. Scram time ______ seconds (1/2/3)
Category B: Normal/Emergency Operating Procedures and Radiological Controls
QUESTION B.16 [1.0 point]
A 40-mm thick sheet of lead, placed at a certain location in a beam port, would reduce the gamma radiation level from 600 mR/hr to 150 mR/hr. How much additional lead would be needed to reduce the gamma radiation level to 75 mR/hr?
- a. 20 mm
- b. 40 mm
- c. 60 mm
- d. 80 mm
QUESTION B.17 [1.0 point]
Reactor Operator works in a high radiation area for eight (8) hours a day. The dose rate in the area is 80 mrem/hour. Which ONE of the following is the MAXIMUM number of days in which Reactor Operator may perform his duties WITHOUT exceeding 10 CFR 20 limits?
- a. 6 days
- b. 7 days
- c. 8 days
- d. 9 days
QUESTION B. 18 [1.0 point]
In case of Safety Limit violation, the reactor shall be shut down, and reactor operations shall not be resumed until authorized by _______.
- a. Level 1, UUTR Vice President for Research
- b. Level 2, UNEP Reactor Director
- c. Level 3, UNEP Reactor Supervisor
- d. U.S. NRC
Category B: Normal/Emergency Operating Procedures and Radiological Controls
QUESTION B.19 [1.0 point]
Radiation dose to e mergency personnel is limited to __________ TEDE for the protection of large populations by volunteers fully aware of risk involved.
- a. Up to 10 rem
- b. Up to 25 rem
- c. > 25 rem
- d. Up to 5 rem
QUESTION B.20 [1.0 point]
Per UUTR Technical Specifications, the control rod movement speed requires to be measured
_______ during control rod worth measurement.
- a. Biennially
- b. Annually
- c. Biannually
- d. Quarterly
(***** END OF CATEGORY B *****)
((***** END OF EXAM *****))
Category B: Normal/Emergency Operating Procedures and Radiological Controls
B.01 Answer: d
Reference:
B.02 Answer: d
Reference:
l2 = l1D12/d22 l2 = (250 mR/hr)(1m) 2 / (4m)2 l2 = 15.63 mR
B.03 Answer: d
Reference:
B.04 Answer: b
Reference:
B.05 Answer: c
Reference:
B.06 Answer: a
Reference:
6CEN = R/hr @ 1 ft. -> 6 x 2 x 0.9 x 0.2 = 2.16 R/hr at 1ft.
l2 = l1D12/d22 l2 = (2.16 R/hr)(1m) 2 / (10m)2 l2 = 2.16 R/hr ?100 = 0.0216 R/hr = 21.6 mR/hr
B.07 Answer: a, TEST b, TEST c, CAL d, CHECK
Reference:
B.08 Answer: b
Reference:
B.09 Answer: a, 30 b, 15 c, 7.5 d. 4.0
Reference:
B.10 Answer: a. = Structure; b. = Air; c. = Water, d. = Fission (0.25 each)
Reference:
NRC standard question
B.11 Answer: b
Reference:
UUTR Technical Specifications, Section 6.1.3
Category B: Normal/Emergency Operating Procedures and Radiological Controls
B.12 Answer: a
Reference:
NRC standard question
B.13 Answer: a
Reference:
NRC standard question
B.14 Answer: a. = 3; b. = 2; c. = 1; d. = 4. (0.25 each)
Reference:
Title 10 of the Code of Federal Regulations.
B.15 Answer: a. = $1.20; b. = 0.0625 ins; c. = 100 kW; d. = 2 sec (0.25 each)
Reference:
UUTR TS 3.1.1, TS 3.1.3, TS 3.1.6, TS 3.2.1
B.16 Answer: a
Reference:
DR = DR*e -X Find 150 = 600* e - *40 ; = 0.0346 If insertion of an HVL (thickness of lead), the original intensity will be reduced by half.
Find X: 1 = 2* e - 0.0346*X ; X= 20 mm
Find HVL by shortcut:
600mR-300 mR is the 1st HVL 300 mR - 150 mR is the 2nd HVL 150- mR - 75 mR is the 3rd HVL
B.17 Answer: b
Reference:
10CFR20.1201(a)(1) 5000 mr x 1 hr x day = 7.8 days 80 mr
- 8 hr You cannot round off to 8 days that will exceed 10CFR20 limits
B.18 Answer: d
Reference:
B.19 Answer: b
Reference:
B.20 Answer: b