ML022400833
| ML022400833 | |
| Person / Time | |
|---|---|
| Site: | 05000128 |
| Issue date: | 09/05/2002 |
| From: | Madden P NRC/NRR/DRIP/RORP |
| To: | Bill Russell Texas A&M Univ |
| Isaac P, NRC/NRR/DRIP/RORP, 301-415-1019 | |
| Shared Package | |
| ML022400846 | List: |
| References | |
| 50-128/OL-02-03 50-128/OL-02-03 | |
| Download: ML022400833 (16) | |
Text
September 5, 2002 Dr. B. Don Russell, Deputy Director Texas Engineering Experiment Station Texas A&M University Nuclear Science Center, Bldg. 1095 College Station, TX 77843-3575
SUBJECT:
INITIAL EXAMINATION REPORT LETTER NO. 50-128/OL-02-03, TEXAS A&M UNIVERSITY, AUGUST 2002
Dear Dr. Russell:
During the week of August 19, 2002, the NRC administered examinations to employees of your facility who had applied for a license to operate your Texas A&M University Reactor. The examination was conducted in accordance with NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1.
In accordance with 10 CFR 2.790 of the Commissions 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 NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/NRC/ADAMS/indesx.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 Patrick Isaac at 301-415-1019.
Sincerely,
/RA/
Patrick M. Madden, Section Chief Research and Test Reactors Section Operating Reactor Improvements Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-128
Enclosures:
- 1. Initial Examination Report No. 50-128/OL-02-03
- 2. Examination and answer key cc w/encls:
Please see next page
Texas A&M University System Docket No. 50-128 cc:
Texas A&M University System ATTN: Dr. Warren D. Reece, Director Nuclear Science Center Texas Engineering Experiment Station F.E. Box 89, M/S 3575 College Station, TX 77843 Texas State Department of Health Radiation Control Program Director Bureau of Radiation Control 1100 West 49th Street Austin, TX 78756-3189 Test, Research, and Training Reactor Newsletter 202 Nuclear Sciences Center University of Florida Gainesville, FL 32611 U.S. Customs Service Safety Branch ATTN: Mr. Rick Whitman 6026 Lakeside Boulevard Indianapolis, IN 46278 U.S. Department of Transportation Mr. Raymond Lamagdelaine, Special Investigations Chief Office of Hazardous Materials Enforcement DHR-40 400 7th Street, S.W.
Washington, DC 20590
September 5, 2002 Dr. B. Don Russell. Deputy Director Texas Engineering Experiment Station Texas A&M University Nuclear Science Center, Bldg. 1095 College Station, TX 77843-3575
SUBJECT:
INITIAL EXAMINATION REPORT LETTER NO. 50-128/OL-02-03, TEXAS A&M UNIVERSITY, AUGUST 2002
Dear Dr. Russell:
During the week of August 19, 2002, the NRC administered examinations to employees of your facility who had applied for a license to operate your Texas A&M University Reactor. The examination was conducted in accordance with NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1.
In accordance with 10 CFR 2.790 of the Commissions 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 NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/NRC/ADAMS/indesx.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 Patrick Isaac at 301-415-1019.
Sincerely,
/RA/
Patrick M. Madden, Section Chief Research and Test Reactors Section Operating Reactor Improvements Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-128
Enclosures:
- 1. Initial Examination Report No. 50-128/OL-02-03
- 2. Examination and answer key cc w/encls:
Please see next page DISTRIBUTION:
PUBLIC RORP/R&TR r/f Facility File EBarnhill (O6-D17)
ADAMS ACCESSION #: ML022400833 TEMPLATE #: NRR-074 OFFICE RORP:CE IEHB:LA RORP:SC NAME PIsaac:rdr EBarnhill PMadden DATE 08/ 29 /2002 08/ 30 /2002 09/ 03 /2002 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY
ENCLOSURE 1 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-128/OL-02-03 FACILITY DOCKET NO.:
50-128 FACILITY LICENSE NO.:
R-129 FACILITY:
Texas A&M University EXAMINATION DATES:
August 19, 2002 EXAMINER:
Patrick Isaac, Chief Examiner SUBMITTED BY:
/RA/
08/27/2002 Patrick Isaac, Chief Examiner Date
SUMMARY
During the week of August 19, 2002, NRC administered retakes of Section A of the written examinations and operating test to one Reactor Operator (RO) candidate. The candidate passed the examinations.
REPORT DETAILS 1.
Examiner: Patrick Isaac, Chief Examiner 2.
Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 1/0 N/A 1/0 Operating Tests 1/0 N/A 1/0 Overall 1/0 N/A 1/0 3.
Exit Meeting:
Personnel attending:
Michael Spellman, Assistant Director, TAMU Patrick Isaac, Chief Examiner, USNRC Mr. Spellman commented on a well written examinations and declined to make any comments. The Chief Examiner thanked Mr. Spellman for his assistance during the examinations.
U. S. NUCLEAR REGULATORY COMMISSION
ENCLOSURE 2 NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
Texas A&M REACTOR TYPE:
TRIGA DATE ADMINISTERED:
2002/08/19 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% is required to pass the examination. Examinations will be picked up one (1) hour after the examination starts.
% OF CATEGORY % OF CANDIDATES CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 100 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 20.00 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.
Candidates Signature
A. RX THEORY, THERMO & FAC OP CHARS 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.
001 a b c d ___
002 a b c d ___
003 a b c d ___
004 a b c d ___
005 a ____ b ____ c ____ d ____
006 a b c d ___
007 a b c d ___
008 a b c d ___
009 a b c d ___
010 a b c d ___
011 a b c d ___
012 a b c d ___
013 a b c d ___
014 a b c d ___
015 a b c d ___
016 a b c d ___
017 a b c d ___
018 a b c d ___
019 a b c d ___
(***** END OF CATEGORY A *****)
(********** 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.
12.
There is a time limit of one (1) hour for completion of the examination.
EQUATION SHEET
Q = m cp T
Q = m h SCR = S/(1-Keff)
Q = UA T CR1 (1-Keff)1 = CR2 (1-Keff)2 26.06 (
eff )
(1-Keff)0 SUR =
M =
( - )
(1-Keff)1 SUR = 26.06/
M = 1/(1-Keff) = CR1/CR0 P = P0 10SUR(t)
SDM = (1-Keff)/Keff P = P0 e(t/ )
I = Io e-ux (1- )
P = Po
* = 1 x 10-4 seconds
= (*/ ) + [( - )/
eff ]
= */( - )
= (Keff-1)/Keff R = 6 C E n
= Keff/Keff 0.693 T1/2 =
= 0.0075 DR1D1 2 = DR2D2 2
DR = DRoe-t Cp (H20) = 0.146 kw P = S / (1 - Keff) gpm F 1 Curie = 3.7x1010 dps 1 kg = 2.21 lbm 1 hp = 2.54x103 BTU/hr 1 Mw = 3.41x106 BTU/hr 1 BTU = 778 ft-lbf
F = 9/5C + 32 931 Mev = 1 amu
C = 5/9 (F - 32)
Section A Theory, Thermo & Fac. Operating Characteristics QUESTION: 001 (1.00)
Given a source strength of 100 neutrons per second (N/sec) and a multiplication factor of 0.8, the expected neutron count rate would be:
- a. 125 N/sec
- b. 250 N/sec
- c. 400 N/sec
- d. 500 N/sec QUESTION: 002 (1.00)
With the reactor critical at 10 KW a rod is pulled to insert a positive reactivity of 0.00126 K/K.
Which one of the following will be the stable reactor period as a result of this reactivity insertion?
- a. 10 seconds
- b. 50 seconds
- c. 60 seconds
- d. 70 seconds QUESTION: 003 (1.00)
An initial count rate of 100 is doubled five times during a startup. Assuming an initial Keff of 0.950, which one of the following is the new Keff?
- a. 0.957
- b. 0.979
- c. 0.985
- d. 0.998 QUESTION: 004 (1.00)
Consider two identical critical reactors, with the exception that one has a beta of 0.0072 and the other has a beta of 0.0060. Each reactor is operating a 10 watts. Which one of the following compares the response of the reactors to a +0.1% delta k/k reactivity insertion?
- a. The resulting period will be shorter for the reactor with the 0.0072 beta fraction
- b. The resulting period will be shorter for the reactor with the 0.0060 beta fraction
- c. The resulting power level will be higher for the reactor with the 0.0072 beta fraction
- d. The resulting power level will be higher for the reactor with the 0.0060 beta fraction
Section A Theory, Thermo & Fac. Operating Characteristics QUESTION: 005 (2.00, 0.5 each)
Match the terms in column A with the correct definition in column B Column A Column B a.
Fast Neutrons 1.
Neutrons released promptly from fission.
b.
Prompt Neutrons 2.
High energy neutrons.
c.
Slow Neutrons 3.
Neutrons released from decay after fission.
d.
Delayed Neutrons 4.
Low energy neutrons.
QUESTION: 006 (1.00)
The reactor is critical and increasing in power. Power has increased from 20 watts to 80 watts in 60 seconds. How long will it take at this rate for power to increase from 0.080 KW to 160 KW?
- a. 0.5 minute
- b. 2.5 minutes
- c. 5.5 minutes
- d. 10.5 minutes QUESTION: 007 (1.00)
A reactor with an initial population of 24000 neutrons is operating with Keff = 1.01. Of the CHANGE in population from the current generation to the next generation, how many are prompt neutrons?
- a. 25
- b. 238
- c. 2500
- d. 24240 QUESTION: 008 (1.00)
Which one of the following conditions would INCREASE the shutdown margin of a reactor?
- a. Inserting an experiment adding positive reactivity.
- b. Lowering moderator temperature if the moderator temperature coefficient is negative.
- c. Depletion of a burnable poison.
- d. Depletion of uranium fuel.
Section A Theory, Thermo & Fac. Operating Characteristics QUESTION: 009 (1.00)
Which one of the following is the PRIMARY reason that delayed neutrons are so effective at controlling reactor power?
- a. Delayed neutrons make up a very large fraction of the fission neutrons in the core.
- b. Delayed neutrons have a much longer mean lifetime than prompt neutrons.
- c. Delayed neutrons are born at thermal energies.
- d. Delayed neutrons are born at lower energies than prompt neutrons.
QUESTION: 010 (1.00)
Which one of the following is the principal source of heat in the reactor after a shutdown from extended operation at 1 MW?
- a. Production of delayed neutrons
- b. Kinetic energy of fission fragments
- c. Spontaneous fission of U-238
- d. Gamma interactions
Section A Theory, Thermo & Fac. Operating Characteristics QUESTION: 011 (1.00)
The following data was obtained during a reactor fuel load.
No. of Elements Detector A (cps) 0 20 8
28 16 30 24 32 32 42 40 80 Which one of the following represents the number of fuel elements predicted to reach criticality?
- a. 48
- b. 52
- c. 56
- d. 60 1.0
0.9
0.8
0.7
0.6
0.5
0.4
0.3
0.2
0.1
0.0
4 8 12 16 20 24 28 32 36 40 44 48 52 56 60 NUMBER OF ELEMENTS INSTALLED QUESTION: 012 (1.00)
Following 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> at 1 MW, the reactor operator reduces reactor power to 50%. Rod control is placed in manual mode and all rod motion is stopped. Which one of the following describes the response of reactor power, without any further operator actions, and the PRIMARY reason for its response?
- a. Power increases due to the burnout of xenon.
- b. Power increases due to the burnout of samarium.
- c. Power decreases due to the buildup of xenon.
- d. Power decreases due to the buildup of samarium.
Section A Theory, Thermo & Fac. Operating Characteristics QUESTION: 013 (1.00)
Which one of the following is a correct statement concerning the factors affecting control rod worth?
- a. Fuel burn up causes the rod worth for periphery rods to decrease.
- b. Fuel burn up causes the rod worth to increase in the center of the core.
- c. The withdrawal of a rod causes the rod worth of the remaining inserted rods to increase.
- d. As Rx power increases rod worth increases.
QUESTION: 014 (1.00)
Pool temperature increases by 20F. Given Tmoderator = -0.0005 K/K/F and an average regulating rod worth of 0.004 K/K/inch. By how much and in what direction did the regulating rod move to compensate for the temperature change?
- a. 0.25 inches in
- b. 0.25 inches out
- c. 2.5 inches in
- d. 2.5 inches out QUESTION: 015 (1.00)
Which ONE of the following statements describes the subcritical reactor response as Keff approaches unity?
- d. A LARGER change in neutron level results from a given change in Keff and a SHORTER period of time is required to reach the equilibrium neutron level for a given change in Keff.
- b. A LARGER change in neutron level results from a given change in Keff and a LONGER period of time is required to reach the equilibrium neutron level for a given change in Keff.
c.
A SMALLER change in neutron level results from a given change in Keff and a SHORTER period of time is required to reach the equilibrium neutron level for a given change in Keff.
- d. A SMALLER change in neutron level results from a given change in Keff and a LONGER period of time is required to reach the equilibrium neutron level for a given change in Keff.
Section A Theory, Thermo & Fac. Operating Characteristics QUESTION: 016 (1.00)
An experiment to be placed in the central thimble has been wrapped in cadmium. Which one of the following types of radiation will be most effectively blocked by the cadmium wrapping?
- a. Thermal neutrons
- b. Fast neutrons
- c. Gamma rays
- d. X-rays QUESTION: 017 (1.00)
A thin foil target of 10% copper atoms and 90% atoms aluminum is in a thermal neutron beam.
Given s Al = 3.79 barns, s Cu = 0.23 barns, a Al = 7.90 barns and a Cu = 1.49 barns, which ONE of the following reactions has the highest probability of occurring? A neutron
- a. scattering reaction with aluminum.
- b. scattering reaction with copper.
- c. absorption in aluminum.
- d. absorption in copper.
QUESTION: 018 (1.00)
The reactor is operating at 500 KW in steady-state and in manual mode. Which one of the following describes the stable reactor period if a control rod drops fully into the core and no operator action is taken?
- a. -34 seconds due to the rapid decrease in prompt neutrons
- b. -34 seconds due to the rapid decay of the short lived delayed neutron precursors
- c. -80 seconds due to the slowing down length of prompt neutrons
- d. -80 seconds due to the decay half life of the long lived delayed neutron precursors QUESTION: 019 (1.00)
Which one of the following factors in the "six factor" formula is the most strongly affected by the Negative Temperature Coefficient ?
- a. The fast fission factor
- b. The thermal utilization factor
- c. The resonance escape probability
- d. The thermal non-leakage probability
Section A Theory, Thermo & Fac. Operating Characteristics ANSWER: 001 (1.00) d.
REFERENCE:
C.R. = S/(1 - Keff) C.R. = 100/(1 - 0.8) = 100/0.2 = 500 ANSWER: 002 (1.00) b.
REFERENCE:
= ( - )/
eff =.0075 -.00126 = 49.5 seconds
(.1) (.00126)
ANSWER: 003 (1.00) d.
REFERENCE:
CR1 (1-Keff1) = CR2 (1 - Keff2) or M1 (1-Keff1) = M2 (1 - Keff2)
CR2/CR1 = 32 CR1 (1-Keff1)/CR2 = 1 - Keff2) 100 (1-0.950)/3200 = 1 - Keff2 Keff2 = 1 -.0015625 =.998 ANSWER: 004 (1.00) b.
REFERENCE:
Burn, R., Introduction to Nuclear Reactor Operations, © 1982, §§ 3.2.2 3.2.3 ANSWER: 005 (1.00) a, 2; b, 1; c, 4; d, 3
REFERENCE:
Burn, R., Introduction to Nuclear Reactor Operations, © 1988, § 3.2.2 Delayed Neutrons.
ANSWER: 006 (1.00) c.
REFERENCE:
P = Poet/T 80 = 20e60 sec/T T = 43.28 sec 1.6 x 105 watts = 80et/43.28 t = 329 sec = 5.5 minutes ANSWER: 007 (1.00) b.
REFERENCE:
PSTR Training Manual, Section 2.9 24000 x 1.01 = 24240 neutrons in next generation 24240 - 24000 = 240 neutrons added 240 neutrons added - 0.7% delayed neutron fraction = 238 prompt neutrons added ANSWER: 008 (1.00) d.
REFERENCE:
Burn, R., Introduction to Nuclear Reactor Operations, © 1988, § 6.2.3, p. 6-4.
ANSWER: 009 (1.00) b.
REFERENCE:
Burn, R., Introduction to Nuclear Reactor Operations, © 1982, §§ 3.2.2 3.2.3
Section B Normal/Emergency Procedures and Radiological Controls ANSWER: 010 (1.00) d.
REFERENCE:
Burn, R., Introduction to Nuclear Reactor Operations, © 1982, § 4.9, pp. 4-23 4-26.
ANSWER: 011 (1.00) a.
REFERENCE:
Burn, R., Introduction to Nuclear Reactor Operations, © 1982, § 5.5, pp. 5-18 5-25.
ANSWER: 012 (1.00) c.
REFERENCE:
Burn, R., Introduction to Nuclear Reactor Operations, © 1988, §§ 8.1 8.4, pp. 8-3 8-14.
ANSWER: 013 (1.00) c.
REFERENCE:
Burn, R., Introduction to Nuclear Reactor Operations, © 1982, § 7.2 & 7.3, pp. 7-1 7-10.
ANSWER: 014 (1.00) d.
REFERENCE:
+20F x -0.0005 K/K/F = - 0.01 K/K. To compensate the rod must add +0.01 K/K.
+0.01 K/K ÷ +0.004 K/K/inch = +2.5 inches ANSWER: 015 (1.00) b.
REFERENCE:
Burn, R., Introduction to Nuclear Reactor Operations, © 1988, Chapt. 5, pp. 5-1 5-28.
ANSWER: 016 (1.00) a.
REFERENCE:
Glasstone, S. and Sesonske, 1991, § 10.34, pp. 639.
ANSWER: 017 (1.00) c.
REFERENCE:
Glasstone, S. and Sesonske, 1991, § 2.108 - 2.114, pp. 77 - 80.
ANSWER: 018 (1.00) d.
REFERENCE:
The amount of reactivity inserted by the blade s much larger than beta; therefore, maximum stable negative period of -80 seconds results.
ANSWER: 019 (1.00) b.
REFERENCE:
Glasstone, S. and Sesonske, 1991, § 5.98, p. 264.