ML022280431
| ML022280431 | |
| Person / Time | |
|---|---|
| Site: | National Bureau of Standards Reactor |
| Issue date: | 08/21/2002 |
| From: | Madden P NRC/NRR/DRIP/RORP |
| To: | Rowe J US Dept of Commerce, National Institute of Standards & Technology (NIST) |
| Doyle P, NRC/NRR/DRIP/RORP, 415-1058 | |
| Shared Package | |
| ML021700753 | List: |
| References | |
| 50-184/OL-02-02 50-184/OL-02-02 | |
| Download: ML022280431 (29) | |
Text
August 21, 2002 Dr. J. Michael Rowe, Director NIST Center for Neutron Research National Institute of Standards and Technology U. S. Department of Commerce Gaithersburg, MD 20899
SUBJECT:
INITIAL EXAMINATION REPORT NO. 50-184/OL-02-02, NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY
Dear Dr. Rowe:
On August 15, 2002, the NRC administered an operator licensing examination at your National Institute of Standards and Technology Reactor. The examination was conducted according to NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1.
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 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 Paul Doyle at 301-415-1058, or Internet e-mail pvd@nrc.gov.
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. 50-184
Enclosures:
- 1. Initial Examination Report No. 50-184/OL-02-02
- 2. Facility comments with NRC resolution
- 3. Examination and answer key (RO/SRO) cc w/encls:
Please see next page
August 21, 2002 Dr. J. Michael Rowe, Director NIST Center for Neutron Research National Institute of Standards and Technology U. S. Department of Commerce Gaithersburg, MD 20899
SUBJECT:
INITIAL EXAMINATION REPORT NO. 50-184/OL-02-02, NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY
Dear Dr. Rowe:
On August 15, 2002, the NRC administered an operator licensing examination at your National Institute of Standards and Technology Reactor. The examination was conducted according to NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1.
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 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 Paul Doyle at 301-415-1058, or Internet e-mail pvd@nrc.gov.
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. 50-184
Enclosures:
- 1. Initial Examination Report No. 50-184/OL-02-02
- 2. Facility comments with NRC resolution
- 3. Examination and answer key (RO/SRO) cc w/encls:
Please see next page DISTRIBUTION w/ encls.:
PUBLIC RORP/R&TR r/f PMadden MMendonca Facility File (EBarnhill) O6-D17 ADAMS ACCESSION #: ML022280431 TEMPLATE #:NRR-074 OFFICE RORP:CE IEHB:LA E RORP:SC NAME PDoyle:rdr EBarnhill PMadden DATE 08/ 20 /2002 08/ 20 /2002 08/ 21 /2002 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY
National Institute of Standards Docket No. 50-184 and Technology cc:
Montgomery County Executive County Office Building Rockville, MD 20858 Director Department of State Planning 301 West Preston Street Baltimore, MD 21201 Director Department of Natural Resources Power Plant Siting Program Energy and Coastal Zone Administration Tawes State Office Building Annapolis, MD 21401 Dr. Seymour H. Weiss, Chief Reactor Operations and Engineering National Institute of Standards and Technology U.S. Department of Commerce Gaithersburg, MD 20899 Honorable Michael L. Subin Montgomery County Council Stella B. Werner Council Office Building Rockville, MD 20850 Dr. William Vernetson Director of Nuclear Facilities Department of Nuclear Engineering Sciences University of Florida Gainesville, FL 32611-8300 Mr. Jim Torrence Reactor Radiation Division National Institute of Standards and Technology U.S. Department of Commerce Gaithersburg, MD 20899
U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-184/OL-02-02 FACILITY DOCKET NO.: 50-184 FACILITY LICENSE NO.: TR-5 FACILITY: National Institute of Standards and Technology EXAMINATION DATES: August 15, 20021 SUBMITTED BY: __________/RA/________________ 08/20/2002 Paul Doyle, Chief Examiner Date
SUMMARY
On August 15, 2002, the NRC administered an operator licensing examination to one Senior Reactor Operator (Instant) candidate for the NBSR reactor. The candidate passed all portions of the NRC administered examination.
REPORT DETAILS
- 1. Examiners:
Paul Doyle, Chief Examiner
- 2. Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 0/0 1/0 1/0 Operating Tests 0/0 1/0 1/0 Overall 0/0 1/0 1/0
- 3. Exit Meeting:
Paul Doyle, NRC, Examiner Alexander Velazquez-Lozada, NRC, Intern Seymour Weiss, NIST, Chief Tawfik Raby, NIST The examiner thanked the NIST reactor management for their support in administering the examinations. The NIST reactor management provided some minor suggestions for changes to the examination which have been incorporated.
1 Candidate passed section A of written examination administered March 1, 2002.
ENCLOSURE 1
National Institute of Standards and Technology With Answer Key OPERATOR LICENSING EXAMINATION SECTIONS B & C August 15, 2002
Section B Normal/Emergency Procedures & Radiological Controls Page 6 QUESTION B.1 [1.0 point]
Per the Emergency Plan, three (3) emergency classifications are applicable to the NIST reactor.
Notification of Unusual Event (N), Site Area Emergency (S), and Alert (A). Which ONE of the following choices correctly lists the classifications in order from least to most severe?
- a. N A S
- b. A S N
- c. S N A
- d. S A N QUESTION B.2 [1.0 point]
While working in an area marked "Caution, Radiation Area," you discover your dosimeter is off scale and leave the area. Assuming you had been working in the area for 45 minutes, what is the maximum dose you would have received?
- a. 3.8 mr
- b. 35.6 mr
- c. 75 mr
- d. 100 mr QUESTION B.3 [1.0 point]
QUARTERLY maintenance was last performed on a system on July 31, 2002. The last date quarterly maintenance may be performed on the system without being late is
- a. 3-1/2 months: November 15, 2002
- b. 4 months: November 30, 2002
- c. 4-1/2 months: December 15, 2002
- d. 5 months: December 31, 2002 QUESTION B.4 [1.0 point]
During Startup to full power, per procedure (O.P. 01) you are required to stop and take data at the 100 kilowatt, 1 megawatt, 5 megawatt and 10 megawatt levels. Which ONE by procedure requires you to hold the power level for an Hour?
- a. 100 kilowatt
- b. 1 megawatt
- c. 5 megawatt
- d. 10 megawatt
Section B Normal/Emergency Procedures & Radiological Controls Page 7 QUESTION B.5 [2.0 points, 1/2 point each]
For Research and Test reactors we primarily worry about two isotopes N16 and Ar41. Identify the approximate half-life and gamma energy for each. (Each item has only one answer.)
Isotope Radiological Parameters
- a. Ar41 half-life 1) 1.8 sec 2) 1.8 min 3) 1.8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4) 1.8 day
- b. Ar41 gamma energy 1) 10 KeV 2) 100 KeV 3) 1 MeV 4) 10 MeV
- c. N16 half-life 1) 7 sec 2) 7 min 3) 7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> 4) 7 day
- d. N16 gamma energy 1) 6 kev 2) 60 keV 3) 600 keV 4) 6 Mev QUESTION B.6 [2.0 points, 1/2 each]
Identify each of the following Technical Specification Requirements as being either a Limiting Safety System Setting (LSSS) or a Limiting Condition for Operation (LCO).
- a. Minimum Coolant Flow (outer plenum) 235 gpm/MW
- b. reactivity insertion rate for all four shim safety arms, does not exceed 5.0 x 10-4 /sec.
- c. D2 concentration in the helium sweep system of greater than 4%.
- d. Maximum Reactor power 130%
QUESTION B.7 [1.0 point]
You use a Geiger-Müller detector at the same distance from two point sources having the same curie strength. Source As gammas have an energy of 1.0 MeV, while Source Bs gammas have an energy of 2.0 MeV. Which ONE of the following would you expect for the readings due to each source?
- a. The reading from source B is four times that of source A.
- b. The reading from source B is twice that of source A.
- c. Both readings are the same.
- d. The reading from source B is half that of source A.
QUESTION B.8 [1.0 point]
Approximately how many half-lives does it take to reduce radiation from an isotope by a factor of 1000?
- a. 5
- b. 10
- c. 15
- d. 20
Section B Normal/Emergency Procedures & Radiological Controls Page 8 QUESTION B.9 [1.0 point]
Rescue personnel, are authorized to receive a pre-established radiation exposure WITHOUT Emergency Director (ED) approval in order to save someones life. What is this limit?
- a. 5 Rem
- b. 25 Rem
- c. 50 Rem
- d. 75 Rem QUESTION B.10 [1.0 point]
Which ONE of the following is the definition for Annual Limit on Intake (ALI)? A 10CFR20 derived limit based on
- a. the concentration of a radio-nuclide in air which, if inhaled by an adult worker for a year, results in a total effective dose equivalent of 100 millirem.
- b. a Committed Effective Dose Equivalent of 5 Rems whole body or 50 Rems to any individual organ, for the amount of radioactive material inhaled or ingested in a year by an adult worker.
- c. the effluent concentration of a radio-nuclide in air which, if inhaled continuously over a year, would result in a total effective dose equivalent of 50 millirem for noble gases.
- d. projected dose commitment values to individuals, that warrant protective action following a release of radioactive material.
QUESTION B.11 [1.0 point]
O.I. 6.4 NBSR Spent Fuel Cask Loading and Shipping specifies the closest a fueled section is allowed to be raised when loading a spent fuel cask as 48 inches. Given that a thumb rule for gamma attenuation is that 2 feet is equivalent to a tenth thickness, radiation from the fuel should be reduced by a factor of at least
- a. 1/10th
- b. 1/20th
- c. 1/100th
- d. 1/1000th
Section B Normal/Emergency Procedures & Radiological Controls Page 9 QUESTION B.12 [1.0 point]
While operating one of the shim arms falls to its lower stop. Per Annunciator Procedure 0.3 Stuck or Faulty Operation of Shim Arms you should
- a. continue to operate using the remaining shim arms to stay critical.
- c. maintain the reactor as is (subcritical) until Reactor Supervisor directs corrective action.
- d. shutdown the reactor.
QUESTION B.13 [1.0 point]
10CFR50.54(x) states: A licensee may take reasonable action that departs from a license condition or a technical specification (contained in a license issued under this part) in an emergency when this action is immediately needed to protect the public health and safety and no action consistent with license conditions and technical specifications that can provide adequate or equivalent protection is immediately apparent. 10CFR50.54(y) state that this may be authorized by a senior operator. Per the note in the front of the Operating Instructions, the minimum level of management who may authorize a deviation from the Operating Instructions is
- a. a licensed SRO
- b. the Reactor Supervisor
- c. the Chief of Reactor Operations
- d. the highest level of management available at the time.
QUESTION B.14 [1.0 point]
Per Annunciator Procedure 0.7, you must shutdown the reactor if emergency cooling H2O pressure drops below
- a. 45 psig
- b. 35 psig
- c. 25 psig
- d. 15 psig QUESTION B.15 [1.0 point]
Which of the following radioisotopes is considered a fission product?
- a. N16
- b. Ar41
- c. H3
- d. I135
Section B Normal/Emergency Procedures & Radiological Controls Page 10 QUESTION B.16 [1.0 point]
The reactor is considered Shutdown if it contains less than
- a. 2.2 lbm of U235
- b. 2.2 Kg of U235
- c. 10 lbm of U235
- d. 10 Kg of U235 QUESTION B.17 [1.0 point]
Which ONE of the following statements correctly defines the term "Channel Check?"
- a. The introduction of a signal into a channel and observation of the proper channel response.
- b. An arrangement of sensors, components and modules as required to provide a single trip or other output signal relating to a reactor or system operating parameter.
- c. The qualitative verification of acceptable performance by observation of channel behavior.
- d. The adjustment of a channel such that its output corresponds with acceptable accuracy to known values of the parameter which the channel measures.
QUESTION B.18 [1.0 point]
During Reactor Startup, per SOP 0.1, the minimum allowable period allowed is
- a. 10 seconds
- b. 20 seconds
- c. 30 seconds
- d. 56 seconds
Section C Facility and Radiation Monitoring Systems Page 11 QUESTION C.1 [1.0 point]
Many valves in the primary system have spark plugs associated with them. The primary purpose of these spark plugs is to
- a. recombine radiolytically separated gasses
- b. detect D2O leakage out of the primary
- c. detect H2O leakage into the primary
- d. combine H3 with O2, thus converting it to a safer composition QUESTION C.2 [1.0 point]
Which ONE of the following reactor instrumentation channels WILL NOT cause a reactor rundown, prior to activating a reactor scram?
- a. Nuclear Power Channels
- b. Nuclear intermediate channel (Log-N)
- c. Reactor Primary Outlet Flow
- d. Reactor Vessel Level QUESTION C.3 [1.0 point]
The operation mode will switch from automatic to manual if the regulating rod reaches its upper or lower limit or if the operator uses the withdraw/insert reg. rod switch or if there is a power deviation equal to or greater than
- a. 2%
- b. 5%
- c. 10%
- d. 15%
QUESTION C.4 [1.0 point]
If a Secondary cooling pump trips off due to an overload, prior to restarting you must
- a. place the control room switch to off to reset the pump electrically.
- b. place the control room switch to the on position (the pump resets itself electrically).
- c. have an auxiliary operator push a reset button on the controller locally at the pump.
- d. have an auxiliary operator take the local, auto switch to local to reset the pump, then return the switch to auto.
Section C Facility and Radiation Monitoring Systems Page 12 QUESTION C.5 [2.0 points, 1/2 point each]
Identify whether each of the listed signals will cause a Scram (S), a Major Scram (MS) or may cause either (E) type.
- a. High flux level (2 of 3 or 1 of 2 logic only)
- b. High activity effluent air exhaust
- c. Low Reactor Vessel D2O Level.
- d. Manual Pushbuttons in the control room.
QUESTION C.6 [2.0 points, 1/2 point each]
Identify the valves listed below A as either Motor Operated (MO)or Air Operated (AO).
- a. DWV-1 Inner Plenum Flow Control (D2O Main Cooling System)
- b. DWV-2 Outer Plenum Flow Control (D2O Main Cooling System)
- c. DWV-40 D2O supply to Emergency Tank (D2O Auxiliary System)
- d. DWV-19 Isolation between Core and Main Pump Piping (D2O Main Cooling System)
QUESTION C.7 [1.0 point]
You notice that when a shim arm is driven in, it stops at about two to three degrees, yet when you scram, the shim arm stops below one degree. Which ONE of the following is the reason for this?
- c. Shim drive stop lower limit switches are designed to prevent damage due to driving the shim arm in continuously.
- d. Deenergizing the scram magnet causes a change in impedance causing the readout for the shim arm to be more accurate at lower levels.
QUESTION C.8 [1.0 point]
WHICH ONE of the following correctly describes the lineup of Secondary Valves 1, 2 and 3?
- a. SCV 1 & 2 supply suction to pumps 4, 5 and 6, SCV 3 supplies suction to pumps 1, 2 and 3.
- b. SCV 2 & 3 supply suction to pumps 4, 5 and 6, SCV 1 supplies suction to pumps 1, 2 and 3.
- c. SCV 1 & 2 supply suction to pumps 1, 2 and 3, SCV 3 supplies suction to pumps 4, 5 and 6.
- d. SCV 2 & 3 supply suction to pumps 4, 5 and 6, SCV 1 supplies suction to pumps 1, 2 and 3.
Section C Facility and Radiation Monitoring Systems Page 13 QUESTION C.9 [1.0 point]
During a reactor startup, the 123 Strainer Inlet Isolation valve SCV-200 is inadvertantly left closed.
As the startup progresses, the reactor receives a rundown signal, the signal was due to
- a. low secondary flow
- b. low thermal shield flow
- c. high inlet temperature
- d. high outlet temperature QUESTION C.10 [1.0 point]
Which ONE of the following is the material used as a NEUTRON POISON in the safety-shim arms?
- a. Erbium
- b. Cadmium
- c. Aluminum
- d. Boron QUESTION C.11 [1.0 point]
Which ONE of the following correctly describes where Critical Panel 1 (CP-1) receives power from?
- a. Directly from MCCA-7
- b. Directly from the 20 kVA uninterruptible power supplies (UPS)
- c. Directly from either Scott Transformer T9 or T10.
- d. Directly from the battery QUESTION C.12 [1.0 point]
Reactor level is increasing above 168 inches. Which ONE of the following is the AUTOMATIC reactor scram which will occur?
- a. High reactor D2O level.
- b. High flux on NC-6, NC-7 or NC-8.
- c. Low reactor D2O level.
- d. High Reactor T
Section C Facility and Radiation Monitoring Systems Page 14 QUESTION C.13 [1.0 point]
Which ONE of the following is the actual method that negative building pressure is maintained following a containment building isolation and normal ventilation shutdown due to high radiation?
(Assume AC power is available and no operator actions, and the containment building pressure is being maintained by the emergency exhaust system.)
- a. automatic fan cycling on and off to maintain a pressure of -0.25".
- b. manual fan cycling on and off to maintain a pressure of -0.25".
- c. automatic fan cycling on and off to maintain a pressure of -0.1".
- d. manual fan cycling on and off to maintain a pressure of -0.1".
QUESTION C.14 [2.0 points, 1/2 each]
Match the Storage Pool cooling system components with their primary responsibiities.
- a. Suspended Solids 1. Pre and Post Filters
- b. pH 2. Ultraviolet Treatment Unit
- c. Dissolved Solids 3. Collection Basin
- d. Kill Biological Impurities 4. HOH Ion Exchanger
- e. Floating Detritus (Mosquito Larvae, dust etc.)
QUESTION C.15 [1.0 point]
What type of detector does the T3 channel use?
- a. Ion chamber
- b. Scintillation Detector
- c. Geiger Counter
- d. Proportional Counter QUESTION C.16 [1.0 point]
In order to detect neutrons the Nuclear Instrumentation ion chambers are coated with 96% enriched
- a. Be10
- b. Be11
- c. B10
- d. B11
Section C Facility and Radiation Monitoring Systems Page 15 QUESTION C.17 [1.0 point]
Which ONE of the following is the primary reason for the boral curtain in the thermal column? It absorbs
- a. thermal neutrons
- b. epi-thermal neutrons
- c. fast neutrons
- d. gamma rays
Section B Normal/Emergency Procedures & Radiological Controls Page 16 B.1 a REF: Emergency Plan B.2 c REF: Standard NRC stay time calculation question B.3 b REF: T.S. 5.0 Time period definitions.
B.4 d REF: O.P. 1.1 § III steps 12, 13, and 14.
B.5 a, 3; b, 3; c, 1; d, 4 REF: Technical Specifications § 4.0 (1) & (2), 3.3 (2)(b) and 3.4 Bases B.6 a, LSSS b, LCO c, LCO; d, LSSS REF: Technical Specifications, 2.2 1st and 4th specifications, 3.2 5th specification and 3.4 2nd specification.
B.7 c REF: Geiger-Müller detector output is independent of incident energy.
B.8 b REF: Rewrite of NBSR Requalification Examination question administered January, 2000.
B.9 b REF: Emergency Instructions Manual, E.I. 1.5, "General Information", Page 5 of 5 B.10 b REF: 10CFR20 B.11 c REF: Standard NRC question B.12 d REF: Annunciator Procedures, A.P. 0.4.
B.13 d REF: Note in the front of the Operating Instructions B.14 c REF: Annunciator Procedures, A.P. 0.7.
B.15 d REF: Standard NRC question B.16 b REF: Technical Specification 1.6 B.17 c REF: TS, § 1.1.2 B.18 b REF Standard Operating Instructions O.I.1.1, Reactor Startup: § II.C.
Section C Facility and Radiation Monitoring Systems Page 17 C.1 b REF: Rewrite of NBSR Requalification Examination question administered March, 1998 C.2 c REF: NBSR Requalification Examination question administered April, 2002 C.3 c (CAF)
REF: NBSR Reactor Operations Instruction Manual O.I 5.4.
C.4 a REF: NBSR Training Manual, § 3.2.1.
C.5 a, S; b, MS; c, S; d, E REF: T.S. § 3.4 C.6 a, MO; b, MO; c, AO; d, MO REF: NBSR Operations Training Guide, § 2.2.4 and Drawing 2.1 C.7 c REF: Rewrite of NBSR Requalification Examination Question administered March 1994.
C.8 a REF: NBSR Training Manual, Figure 3.1.
C.9 d REF: NBSR Requalification question administered March 1994.
C.10 b REF: NBSR Reactor Operations Training Guide, § 1.1.5 2nd ¶.
C.11 c REF: NBSR Reactor Operations Training Guide, § 5.0 NBSR Electrical Systems C.12 c REF: Annunicator Procedures AN.3.1 Hi Reactor D2O level C.13 a REF: NBSR Training Guide, § 4.10.3, Ventilation System Under accident conditions.
C.14 a, 1; b, 4; c, 4; d, 2; e, 3 REF: NBSR Training Guide, figure 4.10.
C.15 a REF: NBSR Training Guide, § 6.4.7.
C.16 c REF: NBSR Training Guide, § 6.2.3 and 6.2.4.
C.17 a REF: NBSR Requalification Exam Question administered Jan 2000.
U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: National Institute of Standards and Technology REACTOR TYPE: NBSR DATE ADMINISTERED: 2002/08/15 CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
Write answers on the answer sheet provided. Attach answer sheets to the examination. Points for each question are indicated in brackets. A 70% overall is required to pass the examination.
Examinations will be picked up two (2) hours after the examination starts.
%of Category % of Candidates Category Value Total Score Value Category A. Reactor Theory, Thermodynamics, and Facility 20 33.3 _____ _____ Operating Characteristics B. Normal and Emergency Operating Procedures 20 33.3 _____ _____ and Radiological Controls C. Plant and Radiation Monitoring Systems 20 33.3 _____ _____
60 _____ _____ TOTALS FINAL GRADE 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. 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 two (2) hours for completion of the examination.
- 13. When you have completed and turned in you examination, leave the examination area. If you are observed in this area while the examination is still in progress, your license may be denied or revoked.
REACTIVITY VALUES Total worth of 4 shim arms 25.6% $32 Worth of single shim arm 6.4% $8 Worth of regulating rod 0.64% $0.8 Maximum Reactivity Insertion Rate -0.04%/sec $0.05/sec Temp Coefficient (Operating temp. ~107EF) -0.016%/EF -$0.02/EF Void Coefficient (fuel region) -0.064%/liter -0.08/liter Upper Reflector Worth Rods In 4% $5 Rods Out 10% $12.5 Typical Beam Port Flooding D2O 0.2% $0.25 H2O -0.016% $0.02 Equilibrium Xenon ~3% $3.75 Equilibrium Samarium ~1% $1.25 Peak Xenon (above Samarium ~12% $15 CURRENT APPROXIMATE REACTIVITY BALANCE Temperature $5 Xenon - Samarium $5 Lifetime $4.5 Experiments Negligible Control at End-of-Life Negligible Total Excess Reactivity $10
Formulas K K&1 K &K Ct 1 1 C
' ' ' 2 1 M ' ' ' i ' 1&K K K K1 K2 Ci 1&K M Ct Ct 1 & K1 t
' R(
2 C t1 1 & K2 P ' P0 e ' $ $1 eff & eff & R(
' - ' < $1 ' (Instantaneous) > $1 R( % eff -
K ' üf p üth f ' N '
M Q0 ' m0 c P T P ' - th x N0 x f x3.2 x10&11 ' - th xV x f x 3.2x10&11 th
&X 2.3 0.693 2 2 TVL ' HVL ' I1D1 ' I2D2 I ' I0 e &µ x ' I010 TVL
µ µ X ' X0 e & t Where X can be A(activity), I(intensity), or N(number) T1/2 '
0.693 0.693 T1/2 R
6CE 0.5 C E P %
' eff eff (for large , i.e., rod drop) hr d 2(in feet) d 2(in meters) P0 %
eff C ' Curies and E ' energies gal P (watts) ' Flow x t(EF) x C (constant) min 60 x 9.2 x 1 C (D2O) ' ' 162 3.413 60 x 8.34 x 1 C (H2O) ' ' 147 3.413
CONSTANTS WATER (@STP) 1 gal (H2O) 8.34 lb 1 gal (D2O) 9.2 lb 1 ft3 7.48 gal.
Density (H2O) 62.4 lb/ft3 or 1.0 g/cm3 Density (D2O) 68.95 lb/ft3 or 1.105 g/cm3 CP (H2O and D2O) 1.0 cal/g-EC POWER AND ENERGY 1 watt 1 Joule/sec or 3.413 BTU/hr 1 calorie 4.183 joules 1 BTU 1054 joules 1 Hp 2.54 x 103 BTU/hr Thermal Power (H2O) 147 watt/gpm-EF Thermal Power (D2O) 162 watt/gpm-EF REACTOR (NBSR)
R* 7 x 10-4 sec 0.0064 eff 0.008 bar 10 sec bar 0.1 sec-1 ACTIVITY 1 curie 3.7 x 1010 disintegrations per second or 2.22 x 1012 disintegrations per minute
Section B Normal/Emergency Procedures & Rad Con Page 23 ANSWER SHEET B.1 a b c d ___ B.7 a b c d ___
B.2 a b c d ___ B.8 a b c d ___
B.3 a b c d ___ B.9 a b c d ___
B.4 a b c d ___ B.10 a b c d ___
B.5a 1 2 3 4 ___ B.11 a b c d ___
B.5b 1 2 3 4 ___ B.12 a b c d ___
B.5c 1 2 3 4 ___ B.13 a b c d ___
B.5d 1 2 3 4 ___ B.14 a b c d ___
B.6a LSSS LCO ___ B.15 a b c d ___
B.6b LSSS LCO ___ B.16 a b c d ___
B.6c LSSS LCO ___ B.17 a b c d ___
B.6d LSSS LCO ___ B.18 a b c d ___
Section C Plant and Radiation Monitoring Systems Page 24 ANSWER SHEET C.1 a b c d ___ C.8 a b c d ___
C.2 a b c d ___ C.9 a b c d ___
C.3 a b c d ___ C.10 a b c d ___
C.4 a b c d ___ C.11 a b c d ___
C.5a S MS E ___ C.12 a b c d ___
C.5b S MS E ___ C.13 a b c d ___
C.5c S MS E ___ C.14a 1 2 3 4 ___
C.5d S MS E ___ C.14b 1 2 3 4 ___
C.6a MO AO ___ C.14c 1 2 3 4 ___
C.6b MO AO ___ C.14d 1 2 3 4 ___
C.6c MO AO ___ C.14e 1 2 3 4 ___
C.6d MO AO ___ C.15 a b c d ___
C.7 a b c d ___ C.16 a b c d ___
C.17 a b c d ___
Sunday Monday Tuesday Wednesday Thursday Friday Saturday 31 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 August 18 19 20 21 22 23 24 25 26 27 28 29 30 31 1 2 3 4 5 6 7 8 9 10 11 12 13 14 September 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 1 2 3 4 5 6 7 8 9 10 11 12 October 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 November 17 18 19 20 21 22 23 24 25 26 27 28 29 30 1 2 3 4 5 6 7 8 9 10 11 12 13 14 December 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 1 2 3 4 5 6 7 8 9 10 11 January 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31