Text

Initial Examination Report No. 50-128/OL-04-02, Texas A&M University
	ML040720394
Person / Time
Site:	05000128
Issue date:	03/30/2004
From:	Madden P; NRC/NRR/DRIP/RNRP
To:	Bill Russell; Texas A&M Univ
	Eresian , W, NRC/NRR/DRIP/RNRP, 415-1833
Shared Package
ML040720275	List: ML040720394; ML040720609;
References
	50-128/OL-04-02 50-128/OL-04-02
	Download: ML040720394 (39)
	v • d • e

March 30, 2004 Dr. B. Don Russell, Deputy Director Texas Engineering Experiment Station Nuclear Science Center, Bldg. 1095 Texas A&M University College Station, TX 77843-3575

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-128/OL-04-02, TEXAS A&M UNIVERSITY

Dear Dr. Russell:

During the week of February 23, 2004, the NRC administered initial 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. At the conclusion of the examination, the examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report.

In accordance with 10 CFR 2.790 of the Commission's 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 Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/NRC/ADAMS/index.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. Warren Eresian at 301-415-1833 or via internet e-mail wje@nrc.gov.

Sincerely,

/RA by Marvin Mendonca Acting for/

Patrick M. Madden, Section Chief Research and Test Reactors Section New, Research and Test Reactors Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-128

Enclosures:

1. Initial Examination Report No. 50-128/OL-04-02

2. Examination and answer key cc w/encls: Please see next page

Texas A&M University Docket No. 50-59/128 cc:

Mayor, City of College Station P.O. Box Drawer 9960 College Station, TX 77840-3575 Governors Budget and Planning Office P.O. Box 13561 Austin, TX 78711 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, Texas 77843 Texas State Department of Health Radiation Control Program Director Bureau of Radiation Control Dept. of Health 1100 West 49th Street Austin, Texas 78756-3189 Test, Research and Training Reactor Newsletter 202 Nuclear Sciences Center University of Florida Gainesville, FL 32611

March 30, 2004 Dr. B. Don Russell, Deputy Director Texas Engineering Experiment Station Nuclear Science Center, Bldg. 1095 Texas A&M University College Station, TX 77843-3575

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-128/OL-04-02, TEXAS A&M UNIVERSITY

Dear Dr. Russell:

During the week of February 23, 2004, the NRC administered initial 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. At the conclusion of the examination, the examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report.

In accordance with 10 CFR 2.790 of the Commission's 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 Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/NRC/ADAMS/index.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. Warren Eresian at 301-415-1833 or via internet e-mail wje@nrc.gov.

Sincerely,

/RA by Marvin Mendonca Acting for/

Patrick M. Madden, Section Chief Research and Test Reactors Section New, Research and Test Reactors Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-128

Enclosures:

1. Initial Examination Report No. 50-128/OL-04-02

2. Examination and answer key cc w/encls: Please see next page DISTRIBUTION w/encls.: DISTRIBUTION w/o encls.:

PUBLIC RNRP/R&TR r/f MMendonca, PM WEresian Facility File (EBarnhill) (O6-F2) PMadden ADAMS ACCESSION #: ML040720394 TEMPLATE No.: NRR-074 OFFICE RNRP:CE IROB:LA RNRP:SC NAME WEresian:rdr EBarnhill PMadden DATE 03/ 15 /2004 03/ 26 /2004 03/ 26 /2004 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-128/OL-04-02 FACILITY DOCKET NO.: 50-128 FACILITY LICENSE NO.: R-83 FACILITY: Texas A&M University EXAMINATION DATES: February 25, 2004 EXAMINER: Warren Eresian, Chief Examiner SUBMITTED BY: /RA/ 03/ 15 /2004 Warren Eresian, Chief Examiner Date

SUMMARY

During the week of February 23, 2004, the NRC administered an operator licensing examination to one Reactor Operator candidate. The candidate passed the examination.

ENCLOSURE 1

REPORT DETAILS

1. Examiner: Warren Eresian, 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:

Mr. Jim Remlinger, Manager of Operations Warren Eresian, NRC Chief Examiner Kevin Witt, NRC The NRC thanked the facility staff for their cooperation during the examination. There were no comments on the written examination. No generic concerns were noted.

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: Texas A&M University REACTOR TYPE: TRIGA DATE ADMINISTERED: 02/25/2004 REGION: 4 CANDIDATE:___________________________

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the exam page itself, or the answer sheet provided. Write answers one side ONLY. Attach any answer sheets to the examination. Points for each question 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 20 33.3 A. REACTOR THEORY, THERMODYNAMICS, AND FACILITY OPERATING CHARACTERISTICS 20 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20 33.3 C. FACILITY AND RADIATION MONITORING SYSTEMS

_60__ %

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

Candidate's Signature ENCLOSURE 2

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 not received or 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.

6. Print your name in the upper right-hand corner of the answer sheets.

7. The point value for each question is indicated in parentheses after the question.

8. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK. NOTE: partial credit will NOT be given on multiple choice questions.

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

10. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets. In addition, turn in all scrap paper.

11. When you are done and have turned in your examination, leave the examination area as defined by the examiner. If you are found in this area while the examination is still in progress, your license may be denied or revoked.

A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS Page 3 QUESTION: 001 (1.00)

Approximately how many fissions occur each second in order to produce 1 MW of thermal power?

a. 3x1016

b. 1x1010

c. 7x104

d. 5x1022 QUESTION: 002 (1.00)

Which reaction below results in the formation of the N-16 produced in the reactor?

a. 5 B14 (a, n) 7N16

b. 7 N15 (n, g) 7N16

c. 9 F17 (b, p) 7N16

d. 8 O16 (n, p) 7N16 QUESTION: 003 (1.00)

Which ONE of the following is NOT a contributor to the strong negative temperature coefficient seen at the NSCR? (Assuming steady state operations)

a. Zirconium Hydride dependent disadvantage factor.

b. Doppler broadening of the U-238 resonances.

c. Density changes in the poison material in the control rods.

d. Temperature dependent moderation by the light water.

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OP. CHARACTERISTICS Page 4 QUESTION: 004 (1.00)

Reactivity may defined as a measure of the:

a. number of neutrons being produced in the core.

b. heat being produced due to neutron absorption by the fuel.

c. reactors multiplication factor.

d. fractional change in neutron population between generations.

QUESTION: 005 (1.00)

Which ONE of the following power changes would take the longest to complete, assuming the same period is maintained?

a. 1 MW to 2 MW

b. 2 MW to 3.5 MW

c. 3.5 MW to 4.5 MW

d. 4.5 MW to 5 MW QUESTION: 006 (1.00)

When the reactor is shut down from full power, what is the main contributor to the constant -80 second period that results?

a. The amount of negative reactivity introduced to the core.

b. The decay constant of the longest lived delayed neutron precursors.

c. The degree of neutron absorption by the fission products in the core.

d. The level of the prompt neutron population.

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OP. CHARACTERISTICS Page 5 QUESTION: 007 (1.00)

Which ONE of the following describes the general shape of a differential rod worth curve?

a. Parabolic shaped, with the maximums at the top and bottom of the core height.

b. S shaped, with the maximum at the top of the core height.

c. Cosine shaped, with the maximum at the middle of the core height.

d. Exponentially shaped, with the maximum at the bottom of the core height.

QUESTION: 008 (1.00)

The source strength in the NSCR core is 250 neutrons per second (N/sec) and the effective multiplication factor is 0.80. The stable neutron count rate is:

a. 300 N/sec

b. 750 N/sec

c. 1250 N/sec

d. 1500 N/sec QUESTION: 009 (1.00)

While the reactor is operating at power in the automatic mode, a void is produced in the core. The regulating rod will:

a. drive out to add positive reactivity.

b. drive in to add positive reactivity.

c. drive out to add negative reactivity.

d. drive in to add negative reactivity.

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OP. CHARACTERISTICS Page 6 QUESTION: 010 (1.00)

The speed of the prompt drop occurring just after a large amount of negative reactivity is suddenly inserted into the core is directly related to what factor?

a. Delayed neutron lifetime.

b. Prompt neutron lifetime.

c. Effective delayed neutron fraction.

d. Effective prompt neutron fraction.

QUESTION: 011 (1.00)

Erbium used in FLIP fuel in order to:

a. enhance fuel hydriding, physically strengthening the fuel matrix.

b. add negative reactivity, allowing excess fuel loading in the core.

c. permit reduced clad thickness in FLIP fuel as compared to standard fuel.

d. reduce the value of the prompt negative temperature coefficient of reactivity.

QUESTION: 012 (1.00)

What is the kinetic energy range of a thermal neutron?

a. > 1 MeV

b. 100 KeV - 1 MeV

c. 1 eV - 100 KeV

d. < 1 eV

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OP. CHARACTERISTICS Page 7 QUESTION: 013 (1.00)

What is the normal NSCR neutron startup source for a startup when the reactor has only been shut down for a few days?

a. Gammas produced from Sb124 result in a neutron from Be.

b. Spontaneous fission from Cf252.

c. Gammas produced from fuel result in a neutron from H2.

d. Betas produced from Ra result in a neutron from Li8.

QUESTION: 014 (1.00)

The term prompt critical refers to:

a. the instantaneous jump in power due to a rod withdrawal.

b. a reactor which is supercritical using only prompt neutrons.

c. a reactor which is critical using both prompt and delayed neutrons.

d. a reactivity insertion which is less then beff.

QUESTION: 015 (1.00)

The _________ of the six factor formula _________ due to the insertion of control rods in the NSCR core.

a. reproduction factor; increases

b. resonance escape probability; decreases

c. fast non-leakage probability; increases

d. thermal utilization factor; decreases

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OP. CHARACTERISTICS Page 8 QUESTION: 016 (1.00)

DK The temperature coefficient of the NSCR core is -12 . ' 10- 4 K and the average control rod worth of the o

C regulating control rod is 0.093 $ inch . If the reactor is in the automatic mode and the temperature increases by 25oC, the regulating rod will move: (assume beff = 0.007 DK K ).

a. 5.3 inches in

b. 4.6 inches out

c. 0.5 inches in

d. 7.8 inches out QUESTION: 017 (1.00)

Which ONE of the following describes the characteristics of a good moderator?

a. Low scattering cross section and high absorption cross section.

b. Low scattering cross section and low absorption cross section.

c. High scattering cross section and low absorption cross section.

d. High scattering cross section and high absorption cross section.

QUESTION: 018 (1.00)

What is the approximate amount of time that it will take the amount of Xenon in the core to reach negligible levels after the reactor is shut down from full power? The Xenon will be considered to be negligible after 7 half-lives have passed. (Xe-135 T1/2 = 9.2 hrs)

a. 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months

b. 64 hours7.407407e-4 days 0.0178 hours 1.058201e-4 weeks 2.4352e-5 months

c. 68 hours7.87037e-4 days 0.0189 hours 1.124339e-4 weeks 2.5874e-5 months

d. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OP. CHARACTERISTICS Page 9 QUESTION: 019 (1.00)

During a fuel loading of the NSCR core, as the reactor approaches criticality, the value of 1/M:

a. increases toward unity.

b. decreases toward unity.

c. increases toward infinity.

d. decreases toward zero.

QUESTION: 020 (1.00)

Which ONE of the following is the major source of energy released during fission?

a. Prompt gamma rays.

b. Fission fragments.

c. Prompt neutrons.

d. Delayed neutrons.

(***** END OF CATEGORY A *****)

B. NORMAL/EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS Page 10 QUESTION: 001 (1.00)

The SRO on duty has directed you to "secure the reactor." This is done by:

a. fully inserting all control rods and placing the rod control switches to NEUTRAL.

b. scramming the reactor.

c. removing all experiments.

d. removing the reactor key from the control console.

QUESTION: 002 (1.00)

You observe a loss of reactor pool water which can be controlled by adding makeup water. In accordance with the Emergency Plan, your first course of action is to:

a. assess the severity of the pool water loss by observing the leakage rate and reactor bridge area radiation monitor readings.

b. send a member of Reactor Operations to the west end of the pool and position the emergency cover over the 10-inch cooling exit line.

c. dispatch teams to take appropriate action to determine source of leakage and correct by valve manipulation if possible.

d. shutdown the reactor.

QUESTION: 003 (1.00)

Which ONE of the following conditions is NOT permissible when the reactor is operating, or about to be operated?

a. The reactivity worth of a single experiment = $1.00.

b. A control rod scram = 1.5 seconds.

c. An excess reactivity = $2.20.

d. The Continuous Air Radiation Monitor is inoperable due to maintenance.

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

B. NORMAL/EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS Page 11 QUESTION: 004 (1.00)

The Total Effective Dose Equivalent (TEDE) is defined as the sum of the deep-dose equivalent and the committed effective dose equivalent. The deep-dose equivalent is related to:

a. the dose to organs or tissues.

b. the external exposure to the skin or an extremity.

c. the external exposure to the lens of the eye.

d. the external whole-body exposure.

QUESTION: 005 (1.00)

An automatic scram signal which is NOT required by the Technical Specifications when operating in the steady state mode is:

a. short period.

b. high fuel temperature.

c. high power level.

d. loss of detector high voltage.

QUESTION: 006 (1.00)

In accordance with 10CFR55, a licensed operator must:

a. pass a comprehensive requalification written examination and an annual operating test during a 24-month period.

b. complete a minimum of six hours of shift functions each month.

c. have a medical examination during the six-year term of the license.

d. notify the NRC within 30 days following an arrest.

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

B. NORMAL/EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS Page 12 QUESTION: 007 (1.00)

A "Red Tag" can only be initiated by:

a. the SRO on duty.

b. any SRO.

c. any NSC staff member.

d. the Manager of Reactor Operations.

QUESTION: 008 (1.00)

In accordance with 10CFR20, the "Derived Air Concentration (DAC) refers to:

a. the amount of radioactive material taken into the body by inhalation or ingestion in one (1) year which would result in a committed effective dose equivalent of five (5) rems.

b. limits on the release of effluents to an unrestricted environment.

c. the dose equivalent to organs that will be received from an intake of radioactive material by an individual during the 50-year period following the intake.

d. the concentration of a given radionuclide in air which, if breathed for 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months , would result in a committed effective dose equivalent of five (5) rems.

QUESTION: 009 (1.00)

Information regarding the assembly and location of each fuel bundle is found in the:

a. fuel log.

b. operations log.

c. supervisor log.

d. reactor data log.

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

B. NORMAL/EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS Page 13 QUESTION: 010 (1.00)

Match each of the following actions in Column I with the correct term from the Technical Specifications in Column II: Channel Check, Channel Test, or Channel Calibration. (Only one term per action).

Column I Column II

a. Immersing a thermometer in an ice 1. Check bath, then in boiling water and noting the output. 2. Test

b. Placing a source next to a radiation 3. Calibration detector and observing meter movement.

c. Performing a determination of reactor power with a heat balance, then adjusting a power meter to correspond to the heat balance.

d. Observing the overlap between two different neutron detectors as power increases.

QUESTION: 011 (1.00)

A reactor parameter which is protected by a Safety Limit is:

a. reactor power.

b. fuel element temperature.

c. fuel cladding temperature.

d. pool water level.

QUESTION: 012 (1.00)

A person has received a serious injury which does not involve contamination. In accordance with the Emergency Plan, your first course of action is to:

a. notify the SRO on duty.

b. call for an ambulance, briefly describe the injury and explain the type of accident.

c. go to the injured person and assess the extent of the injury.

d. shutdown the reactor.

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

B. NORMAL/EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS Page 14 QUESTION: 013 (1.00)

An Emergency Action Level is:

a. a condition which calls for immediate action, beyond the scope of normal operating procedures, to avoid an accident or to mitigate the consequences of one.

b. a class of accidents for which predetermined emergency measures should be taken or considered.

c. a specific instrument reading or observation which may be used as a threshold for initiating appropriate emergency procedures.

d. a procedure that details the implementation actions and methods required to achieve the objectives of the emergency plan.

QUESTION: 014 (1.00)

The dose rate 10 feet from a point source is 25 mrem/hour. A person working for 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months at a distance of 3 feet from the source will receive a dose of:

a. 83 mrem.

b. 125 mrem.

c. 278 mrem.

d. 417 mrem.

QUESTION: 015 (1.00)

A startup checklist has been completed and a startup performed. The reactor is then shutdown (scheduled.)

During the shutdown, the bridge is moved. When the reactor is again started up on the same day:

a. another complete checklist is required.

b. the scram circuits must be checked.

c. only section A of the checklist is required.

d. only section D of the checklist is required.

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

B. NORMAL/EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS Page 15 QUESTION: 016 (1.00)

Which ONE of the statements below describes the reason the lab receivers in the pneumatic system are kept closed except when loading or unloading a sample?

a. Prolonged opening will introduce air into the system and result in high levels of radioactive Ar41.

b. Prolonged opening will cause pool leakage into the transport hoses due to the pressure differential.

c. They remain closed for neutron shielding purposes during reactor core operation.

d. They remain closed to prevent any CO2 leakage past the isolation valve from entering the labs.

QUESTION: 017 (1.00)

Which ONE of the statements below describes the reason for maintaining bulk pool water chemistry (conductivity and pH)?

a. Reduce the corrosion of the pool liner.

b. Maintain water pH in the range 8.5 and 10.5.

c. Maintain water clarity to facilitate completion of Tech. Spec. required surveillances.

d. Extend the longevity and integrity of the fuel cladding.

QUESTION: 018 (1.00)

The area radiation monitor at the pool level is out of service for maintenance. As a result:

a. the reactor cannot be operated.

b. the reactor can continue to operate.

c. the reactor can continue to operate only if the monitor is replaced with a portable gamma instrument with its own alarm.

d. the reactor can continue to operate only if the alarm setpoints of the remaining area radiation monitors are lowered.

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

B. NORMAL/EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS Page 16 QUESTION: 019 (1.00)

The reactivity worth of a particular experiment is determined to be $1.50. Which ONE of the statements below is correct concerning this experiment?

a. The experiment cannot be allowed in the core due to an excessive reactivity value.

b. The experiment can be placed in the core as a non-secured experiment.

c. The experiment is allowed in the core providing analysis indicates the worth is such that removal will not exceed the safety limit.

d. The experiment is allowed in the core but must be secured.

QUESTION: 020 (1.00)

Which ONE of the following conditions is permissible when the reactor is operating?

a. Shutdown margin = 20 cents.

b. Entry door to reactor building open to bring in equipment.

c. A vacant lattice position on the periphery of the core assembly.

d. The Continuous Air Radiation Monitor and the Exhaust Gas Radiation Monitor are inoperable due to maintenance and have been replaced with gamma sensitive instruments with alarms.

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

C. FACILITY AND RADIATION MONITORING SYSTEMS Page 17 QUESTION: 001 (1.00)

The Log Power Channel consists of a(n) ____________ and provides an input to the

a. Ion Chamber; period circuit.

b. Compensated Ion Chamber; low count rate (2 cps) interlock.

c. Fission Chamber; servo controller.

d. Fission Chamber; 1 kW pulse interlock.

QUESTION: 002 (1.00)

Which ONE of the following statements is NOT TRUE regarding the Servo Flux Control system?

a. Pressing the Gang-Up/Gang-Down switch will turn off the servo unit.

b. The regulating rod moves in response to the linear channel signal.

c. The regulating rod moves in response to the log power channel signal.

d. If power level drifts +/- 5% of the setpoint the servo unit will turn off.

QUESTION: 003 (1.00)

A three-way solenoid valve controls the air supplied to the pneumatic cylinder of the transient rod. De-energizing the solenoid causes the valve to shift to:

a. open, admitting air to the cylinder.

b. close, admitting air to the cylinder.

c. open, removing air from the cylinder.

d. close, removing air from the cylinder.

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

C. FACILITY AND RADIATION MONITORING SYSTEMS Page 18 QUESTION: 004 (1.00)

For the items labeled A through H on the attached figure, Transient Rod Drive, select the proper component from the item list in Column II. All items in Column II may not be necessarily used.

Column I (Figure label) Column II (Item list)

A._____ 1. Solenoid valve B._____ 2. Vent holes C._____ 3. Piston D._____ 4. Bottom limit

5. Piston rod

6. Shock absorber QUESTION: 005 (1.00)

For a control rod, the "CARR UP" light is OFF, the "CARR DOWN" light is OFF, and the "ENGAGED" light is ON. This indicates that:

a. the rod and drive are in contact, and are both full in.

b. the rod and drive are in contact, and are both full out.

c. the rod and drive are not in contact, and the rod and drive are somewhere between full in and full out.

d. the rod and drive are in contact, and are somewhere between full in and full out.

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

C. FACILITY AND RADIATION MONITORING SYSTEMS Page 19 QUESTION: 006 (1.00)

Under emergency conditions, the master control panel located in the reception room may be used to:

a. scram the reactor.

b. operate the air handling systems.

c. operate the emergency pool fill system.

d. operate the emergency lighting system.

QUESTION: 007 (1.00)

The FLIP fuel elements:

a. are about 20% enriched uranium with stainless steel clad and no burnable poison.

b. are about 70% enriched uranium with stainless steel clad and erbium burnable poison.

c. are about 20% enriched uranium with aluminum clad and erbium burnable poison.

d. are about 70% enriched uranium with aluminum clad and no burnable poison.

QUESTION: 008 (1.00)

Which ONE of the following controls the amount of reactivity that is inserted by the transient rod during pulse operations?

a. The preset pulse timer setting that vents the pneumatic piston.

b. The pressure of the air applied to the pneumatic piston.

c. The position of the cylinder.

d. The reactivity of the reactor prior to firing the pulse.

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

C. FACILITY AND RADIATION MONITORING SYSTEMS Page 20 QUESTION: 009 (1.00)

When the stack particulate activity alarm sounds, which ONE of the following occurs?

a. The reactor scrams.

b. The evacuation alarm sounds.

c. The air handling system shuts down.

d. There are no automatic actions.

QUESTION: 010 (1.00)

The reactor is operating at 800 kW, with power being controlled by the servo control system. An experiment is inadvertently inserted into the core, causing reactor power to drop to 600 kW. As a result:

a. the regulating rod moves out of the core in an effort to restore power to 800 kW.

b. the reactor scrams.

c. regulating rod control shifts back to manual.

d. the regulating rod moves into the core to maintain power at 600 kW.

QUESTION: 011 (1.00)

The chemical feed system controls the chemical characteristics of the:

a. secondary cooling loop.

b. pool water cooling system.

c. purification system.

d. pool water transfer system.

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

C. FACILITY AND RADIATION MONITORING SYSTEMS Page 21 QUESTION: 012 (1.00)

Which ONE of the following lists the correct locations for the air handling system dampers?

a. Air inlet to all air handlers, exhaust stack, air inlet to central exhaust fan.

b. Air inlet to all air handlers, fresh air bypass to the exhaust fan, exhaust stack.

c. Fresh air bypass to the exhaust fan, air inlet to central exhaust fan, exhaust stack.

d. Air inlet to all air handlers, fresh air bypass to the exhaust fan, air inlet to central exhaust fan.

QUESTION: 013 (1.00)

Which set of measurements are chosen by the reactor console thermocouple selector?

a. Fuel temperature, irradiation cell temperature, heat exchanger primary outlet temperature.

b. Fuel temperature, pool water temperature, heat exchanger primary outlet temperature.

c. Fuel temperature, irradiation cell temperature, pool water temperature.

d. Pool water temperature, irradiation cell temperature, heat exchanger primary outlet temperature.

QUESTION: 014 (1.00)

Which ONE of the following situations will cause the reactor to automatically SCRAM?

a. Low safety detector voltage (<150 V).

b. High Radiation level at top of pool (>100 mrem/hr).

c. Low pool water level (<90% of normal level).

d. Low air pressure applied to the transient rod (<10 psi).

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

C. FACILITY AND RADIATION MONITORING SYSTEMS Page 22 QUESTION: 015 (1.00)

What type of detector does the building particulate monitor use to measure radiation?

a. Gamma scintillator.

b. Geiger-Mueller.

c. Ionization chamber.

d. Beta scintillator.

QUESTION: 016 (1.00)

What automatic action is associated with a high radiation alarm signal from the Building Particulate Monitor?

a. The air handler fans continue to operate and all inlet dampers close.

b. The air handler fans cease operation and all inlet dampers remain open.

c. The air handler fans cease operation and all inlet dampers close.

d. The air handler fans continue to operate and all inlet dampers remain open.

QUESTION: 017 (1.00)

When the reactor is being controlled by the servo controller:

a. the period scram is bypassed.

b. the regulating rod moves in response to the linear channel signal.

c. the regulating rod moves in response to the log power channel signal.

d. the regulating rod moves out following a scram to try to maintain constant power.

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

C. FACILITY AND RADIATION MONITORING SYSTEMS Page 23 QUESTION: 018 (1.00)

The reactor is in the "PULSE" mode when the TR fire button is depressed. As a result, the solenoid valve is:

a. energized, admitting air to the cylinder.

b. de-energized, admitting air to the cylinder.

c. de-energized, removing air from the cylinder.

d. energized, removing air from the cylinder.

QUESTION: 019 (1.00)

A safety plate assembly is installed beneath the reactor grid plate. Its purpose is to:

a. stop a standard fuel element from dropping more than 2 inches out of the core if it should become detached from its mounting.

b. stop a FLIP fuel element from dropping more than 2 inches out of the core if it should become detached from its mounting.

c. stop a control rod follower from dropping more than 2 inches out of the core if it should become detached from its mounting.

d. provide a stop for the grid plate if it should become detached from the suspension frame.

QUESTION: 020 (1.00)

Match the neutron measuring channel in Column A with the type of detector in Column B. Detectors in Column B may be used once, more than once, or not at all.

Column A Column B

a. Log Power Channel 1. Compensated Ion Chamber

b. Linear Power Channel 2. Uncompensated Ion Chamber

c. Safety Power Channel 3. Fission Chamber

d. Pulse Power Channel 4. G-M Tube

(***** END OF CATEGORY C *****)

(***** END OF EXAMINATION *****)

A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS ANSWER: 001 (1.00)

A.

REFERENCE:

Standard NRC question 1 eV 1 1 MW = 1E 6 J * * = 312

. E16 fission sec s 1602

. E - 19 J 200 E 6 eV fission ANSWER: 002 (1.00)

D.

REFERENCE:

Standard NRC question 8 O16 + 0 n1 7 N 16 +1p1 ANSWER: 003 (1.00)

C.

Burn, R., Introduction to Nuclear Reactor Operations, 1988, page 3-17.

ANSWER: 016 (1.00)

B.

REF: Standard NRC Question DK 0.093 $ ' 0.007 = 6.51E - 4 K inch inch DK

-12. E -4 K

25o C = -3E - 3 DK o

TA&M Technical Specifications, Section 1.0 ANSWER: 011 (1.00)

B.

REFERENCE:

Technical Specifications, Section 2.1.

ANSWER: 012 (1.00)

A.

REFERENCE:

SOP Implementing Procedure For A Personnel Injury.

ANSWER: 013 (1.00)

C.

REFERENCE:

Emergency Plan, pg. 9.

ANSWER: 014 (1.00)

D.

REFERENCE:

DR1d12= DR2d22 ; (25)(100) = DR2(9) ; DR2 = 277 mrem/hour.

SAR, page 6-2 ANSWER: 013 (1.00)

C.

REFERENCE:

SAR, page 7-4 ANSWER: 014 (1.00)

A.

REFERENCE:

SAR, page 7-4 ANSWER: 015 (1.00)

D.

REFERENCE:

SOP VII-B-6-a ANSWER: 016 (1.00)

D.

SAR, pages 91-96.

A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS ANSWER SHEET 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 _____

020 a b c d _____

(***** END OF CATEGORY A *****)

B. NORMAL/EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS ANSWER SHEET 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 _____

020 a b c d _____

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

C. FACILITY AND RADIATION MONITORING SYSTEMS ANSWER SHEET 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 _____

020 a_____b_____c_____d _____

(***** END OF CATEGORY C *****)

EQUATION SHEET Q = m cp T CR1 (1-K1) = CR2 (1-K2)

P = P0 10SUR(t) P = P0 e(t/)

= (R*/) + [(-)/eff] eff = 0.1 seconds-1 DR1D12 = DR2D22 DR = DRoe-t DR = 6CiE/D2 = (K -1)/K 1 Curie = 3.7x1010 dps 1 gallon water = 8.34 pounds EF = 9/5EC + 32 1 Mw = 3.41x106 BTU/hr EC = 5/9 (EF - 32) 1 Mev = 1.6x10-13 watt-sec N = S/(1-K)

ML040720394

Text

SUBJECT:

Dear Dr. Russell:

Enclosures:

SUBJECT:

Dear Dr. Russell:

Enclosures:

SUMMARY

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

Navigation menu

Search