Text

Initial Examination Report No. 50-225/OL-06-01, Rensselaer Polytechnic Institute, 2/6/2006
	ML060610069
Person / Time
Site:	Rensselaer Polytechnic Institute
Issue date:	03/03/2006
From:	Bernard Thomas; NRC/NRR/ADRA/DPR/PRTA
To:	Winters G; Rensselaer Polytechnic Institute
	Eresian W, NRC/NRR/DPR/PRTB, 415-1833
Shared Package
ML053490190	List: ML053490198; ML060610069; ML060610477;
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March 3, 2006 Mr. Glenn Winters, Director Reactor Critical Facility Nuclear Engineering and Science Bldg.

Rensselaer Polytechnic Institute Troy, NY 12181

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-225/OL-06-01, RENSSELAER POLYTECHNIC INSTITUTE

Dear Mr. Winters:

During the week of February 6, 2006, the NRC administered initial examinations to employees of your facility who had applied for a license to operate your Rensselaer Polytechnic Institute 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 2.390 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 document system (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) 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. Warren Eresian at 301-415-1833 or internet e-mail wje@nrc.gov.

Sincerely,

/RA/

Brian E. Thomas, Chief Research and Test Reactors Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-225

Enclosures:

1. Initial Examination Report No. 50-225/OL-06-01

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

Rensselaer Polytechnic Institute Docket No. 50-225 cc:

Mayor of the City of Schenectady Schenectady, NY 12305 Barbara Youngberg Chief, Radiation Section NYS Dept. of Environmental Conservation 625 Broadway Albany, NY 12233-7255 Mr. Thomas McGiff, RSO 126 Humphreys Service Building Ithaca, NY 14853 Director, Bureau of Environmental Radiation Protection New York State Department of Health 547 River Street, Room 530 Troy, NY 12180-2216 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

March 3, 2006 Mr. Glenn Winters, Director Reactor Critical Facility Nuclear Engineering and Science Bldg.

Rensselaer Polytechnic Institute Troy, NY 12181

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-225/OL-06-01, RENSSELAER POLYTECHNIC INSTITUTE

Dear Mr. Winters:

During the week of February 6, 2006, the NRC administered initial examinations to employees of your facility who had applied for a license to operate your Rensselaer Polytechnic Institute 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 2.390 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 document system (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) 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. Warren Eresian at 301-415-1833 or internet e-mail wje@nrc.gov.

Sincerely,

/RA/

Brian E. Thomas, Chief Research and Test Reactors Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-225

Enclosures:

1. Initial Examination Report No. 50-225/OL-06-01

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

PUBLIC DPR/PRT r/f Facility File (EBarnhill)

DHughes, PM WEresian BThomas EXAMINATION PACKAGE ACCESSION NO.: ML053490190 EXAMINATION REPORT ACCESSION NO.: ML060610069 TEMPLATE No.: NRR-074 OFFICE PRTB:CE DIRF/IOLB:LA PRTA:BC NAME WEresian EBarnhill BThomas DATE 3/2/2006 3/2/2006 3/3/2006 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-225/OL-06-01 FACILITY DOCKET NO.: 50-225 FACILITY LICENSE NO.: CX-22 FACILITY: Rensselaer Polytechnic Institute EXAMINATION DATES: February 8-9, 2006 EXAMINERS: Warren Eresian, Chief Examiner SUBMITTED BY: 03/ /2006 Warren Eresian, Chief Examiner Date

SUMMARY

During the week of February 6, 2006, the NRC administered operator licensing examinations to three Senior Reactor Operator (Instant) candidates. All candidates passed the examination.

ENCLOSURE 1

REPORT DETAILS

1. Examiners: Warren Eresian, Chief Examiner

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written N/A 3/0 3/0 Operating Tests N/A 3/0 3/0 Overall N/A 3/0 3/0

3. Exit Meeting:

Warren Eresian, NRC Chief Examiner Glenn Winters, Facility Director Timothy Trumbull, Operations Supervisor The NRC thanked the facility staff for their cooperation during the examination. No generic concerns were noted. The facility reviewed the written examination and as a result, two questions were deleted (A20, no correct answer and C05, system no longer in use.)

U. S. NUCLEAR REGULATORY COMMISSION RESEARCH AND TEST REACTOR LICENSE EXAMINATION FACILITY: Rensselaer Polytechnic Institute REACTOR TYPE: Critical Facility DATE ADMINISTERED: 02/08/2006 REGION: 1 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 19 35 A. REACTOR THEORY, THERMODYNAMICS, AND FACILITY OPERATING CHARACTERISTICS 20 35 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 17 30 C. FACILITY AND RADIATION MONITORING SYSTEMS 56 ______ %

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)

Every fission of Uranium-235 by a thermal neutron produces an average of:

a. 2.00 neutrons

b. 2.07 neutrons

c. 2.42 neutrons

d. 2.93 neutrons QUESTION: 002 (1.00)

K-effective differs from K-infinite in that K-effective takes into account:

a. leakage from the core

b. neutrons from fast fission

c. the effect of poisons

d. delayed neutrons QUESTION: 003 (1.00)

Which ONE of the following is true concerning the differences between prompt and delayed neutrons?

a. Prompt neutrons account for less than one percent of the neutron population while delayed neutrons account for approximately ninety-nine percent of the neutron population

b. Prompt neutrons are released during fast fissions while delayed neutrons are released during thermal fissions

c. Prompt neutrons are released during the fission process while delayed neutrons are released during the decay process

d. Prompt neutrons are the dominating factor in determining the reactor period while delayed neutrons have little effect on the reactor period

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

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

The term "Prompt Critical" refers to:

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

b. a reactor which is critical using only prompt neutrons

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

d. a reactivity insertion which is less than Beta-effective QUESTION: 005 (1.00)

With the reactor critical at 10 watts, a rod withdrawal results in a power increase with a doubling time of 40 seconds. Reactor power two minutes later is:

a. 30 watts

b. 60 watts

c. 80 watts

d. 90 watts QUESTION: 006 (1.00)

Which factor in the six-factor formula is represented by the ratio:

number of neutrons that reach thermal energy number of neutrons that start to slow down

a. fast fission factor

b. resonance escape probability

c. reproduction factor

d. thermal utilization factor

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

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

Which ONE of the following statements describes the difference between Differential (DRW) and Integral (IRW) rod worth curves?

a. DRW relates the worth of the rod per increment of movement to rod position. IRW relates the total reactivity added by the rod to the rod position.

b. DRW relates the time rate of reactivity change to rod position. IRW relates the total reactivity in the core to the time rate of reactivity change.

c. IRW relates the worth of the rod per increment of movement to rod position. DRW relates the total reactivity added by the rod to the rod position.

d. IRW is the slope of the DRW at a given rod position QUESTION: 008 (1.00)

Select the statement that describes the influence of delayed neutrons on the neutron life cycle.

a. Increases average neutron lifetime.

b. Decreases probability of fissioning U-238.

c. Decreases margin to prompt criticality.

d. Increases time to thermalize.

QUESTION: 009 (1.00)

With the reactor on a constant period, which transient requires the LONGEST time to occur?

A reactor power change of:

a. 5% power - going from 1% to 6% power

b. 10% power - going from 10% to 20% power

c. 15% power - going from 20% to 35% power

d. 20% power - going from 40% to 60% power

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

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

Of the approximately 200 Mev of energy released per fission event, the largest amount appears in the form of:

a. beta and gamma radiation

b. prompt and delayed neutrons

c. fission fragments

d. alpha radiation QUESTION: 011 (1.00)

A thermal neutron is a neutron which:

a. experiences no net change in its energy after several collisions with atoms of the diffusing medium.

b. has been produced several seconds after its initiating fission occurred.

c. is produced as a result of thermal fission.

d. possesses thermal rather than kinetic energy.

QUESTION: 012 (1.00)

A reactor is subcritical with a Keff of 0.955. Seven dollars ($7.00) of positive reactivity is inserted into the core ( = 0.007). At this point, the reactor is:

a. subcritical.

b. exactly critical.

c. supercritical.

d. prompt critical.

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

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

A factor in the six-factor formula which is most affected by control rod position is:

a. Resonance escape probability

b. Fast fission factor

c. Neutron reproduction factor

d. Thermal utilization factor QUESTION: 014 (1.00)

Which ONE of the following elements will slow down fast neutrons most quickly, i.e. produces the greatest energy loss per collision?

a. Oxygen-16

b. Uranium-238

c. Hydrogen-1

d. Boron-10 QUESTION: 015 (1.00)

A 1/M curve is being generated as fuel is loaded into the core. After some fuel elements have been loaded, the count rate existing at that time is taken to be the new initial count rate, Co. Additional elements are then loaded and the inverse count rate ratio continues to decrease. As a result of changing the initial count rate:

a. criticality will occur with the same number of elements loaded as if there were no change in the initial count rate.

b. criticality will occur earlier (i.e., with fewer elements loaded.)

c. criticality will occur later (i.e., with more elements loaded.)

d. criticality will be completely unpredictable.

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

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

During the minutes following a reactor scram, reactor power decreases on a negative 80 second period, corresponding to the half-life of the longest lived delayed neutron precursor, which is approximately:

a. 20 seconds.

b. 40 seconds.

c. 55 seconds.

d. 80 seconds.

QUESTION: 017 (1.00)

Which ONE statement below describes a positive moderator temperature coefficient?

a. When moderator temperature increases, positive reactivity is added.

b. When moderator temperature decreases, positive reactivity is added.

c. When moderator temperature increases, negative reactivity is added.

d. When moderator temperature increases, reactor power decreases.

QUESTION: 018 (1.00)

A reactor with an initial population of 1x108 neutrons is operating with Keff = 1.001. Considering only the increase in neutron population, how many neutrons (of the increase) will be prompt when the neutron population changes from the current generation to the next? Assume = 0.007.

a. 700.

b. 7,000.

c. 99,300.

d. 100,000.

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

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

Inelastic scattering can be described as a process whereby a neutron collides with a nucleus and:

a. recoils with a lower kinetic energy, with the nucleus emitting a gamma ray.

b. recoils with the same kinetic energy it had prior to the collision.

c. is absorbed by the nucleus, with the nucleus emitting a gamma ray.

d. recoils with a higher kinetic energy, with the nucleus absorbing a gamma ray.

QUESTION: 020 (1.00) DELETED IAW FACILITY COMMENT The major source of heat generated in the fuel from the decay of fission products is from:

a. beta and gamma radiation.

b. prompt and delayed neutrons.

c. fission fragment kinetic energy.

d. alpha radiation.

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

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

In accordance with the Power Calibration Procedure, if the absolute power level of the log power chamber does not agree within 10% of the log power recorder:

a. The log power recorder scale must be recalibrated

b. The compensating voltage of the chamber must be adjusted to give the proper indication

c. The high voltage to the chamber must be adjusted to give the proper indication

d. The position of the chamber must be adjusted to give the proper indication QUESTION: 002 (1.00)

A radioactive sample is removed from the reactor, reading 25 R/hour. Four hours later, the sample reads 2.5 R/hour. The approximate time required for the sample to decay to 100 mR/hour from the 2.5 R/hour point is:

a. 1.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months

b. 3.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

c. 5.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

d. 7.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months QUESTION: 003 (1.00)

Two Emergency classes for the Critical Facility are:

a. Personnel Emergency and Protective Action Guide

b. Emergency Action Level and Emergency Alert

c. Protective Action Guide and Emergency Action Level

d. Personnel Emergency and Emergency Alert

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

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

In accordance with the Technical Specifications, which ONE situation below is NOT permissible?

a. A clean fuel pin with a reactivity worth of $0.20

b. A total control rod drop time (full out to full in) of 1 second

c. A water level of 10 inches above the top grid of the core

d. A moderator temperature of 50 deg. F QUESTION: 005 (1.00)

"Area for which offsite emergency planning is performed to assure that prompt and effective actions can be taken to protect the public in the event of an accident" defines a (an):

a. operations boundary

b. site boundary

c. emergency planning zone

d. emergency support center QUESTION: 006 (1.00)

Assuming that no channels are bypassed, the safety system channels which are required by the Technical Specifications to be operating in all modes of operation are:

a. log N power level, reactor period, pool water level

b. linear power level, manual scram, criticality detector

c. reactor period, water dump valve scram, manual scram

d. log N power level, reactor door scram, manual scram

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

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

A KNOWN CORE is one for which:

a. the core has been critical and the critical bank position has been measured.

b. the addition, movement or removal of fuel is limited to $0.30 of reactivity or four fuel pins, whichever is smaller.

c. the inverse multiplication method is used for fuel addition in the initial approach to criticality.

d. fuel movement may occur with only three control rods and rod drives operational.

QUESTION: 008 (1.00)

To ensure that there is adequate shutdown capability even with a stuck rod, requirements are established for the:

a. insertion time for each control rod.

b. minimum number of operable control rods.

c. maximum moderator-reflector water level.

d. actuation time for the auxiliary reactor scram.

QUESTION: 009 (1.00)

Prior to the disposal of water from the reactor tank, storage tank or sump, it must be tested to ensure that:

a. the pH is between 4.7 and 7.0.

b. the temperature is less than 70 deg. F.

c. the activity is within limits.

d. the particulate concentration is within limits.

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

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

In accordance with the Technical Specifications, which ONE situation below is NOT permissible?

a. A power level trip setting of 120 watts.

b. Operation with three operable control rods.

c. Operation with the Log N, Period channel bypassed.

d. Criticality detector system removed from service and replaced by an equivalent portable unit.

QUESTION: 011 (1.00)

In accordance with Technical Specifications, a REACTOR SHUTDOWN condition requires all control rods are fully inserted and:

a. the console key is removed.

b. the reactor is shutdown by at least $1.00.

c. no operations are in progress which involve control rod maintenance.

d. no operations are in progress which involve moving fuel pins in the reactor vessel.

QUESTION: 012 (1.00)

During performance of a power calibration, the reactor is scrammed after activation and the operator enters the high bay area to take readings. Prior to entering the high bay area the operator should verify that:

a. the neutron source has been removed to its shielded container.

b. all control rods are fully inserted and water drained from the tank.

c. the "Reactor On" key is removed and returned to the office safe.

d. 10 minutes have elapsed to allow for short lived isotopes to decay.

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

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

Which ONE of the following actions is required for a spill involving material that contains 15 microcuries of beta gamma emitters:

a. confine the spill immediately.

b. vacate and secure the affected room.

c. right the container of spilled material.

d. drop absorbent paper on the liquid spill.

QUESTION: 014 (1.00)

The limit for maximum water level at no greater than 10 inches above the top of the core is based on:

a. providing adequate neutron shielding during operation.

b. limiting moderator mass to maximize negative temperature coefficient effects during transients.

c. avoiding hydraulic restrictions to control rod insertion during a scram.

d. ensuring that negative reactivity will be added within the time assumed in the safety analysis by loss of the reflector above the core following a scram.

QUESTION: 015 (1.00)

Which ONE of the following describes the Technical Specifications limits pertaining to control rod operability?

a. All four control rods must be operable for reactor operation.

b. One control rod may be inoperable provided it is fully inserted.

c. One control rod may be inoperable provided $0.7 shutdown margin is maintained with the inoperable rod withdrawn.

d. Two control rods may be inoperable provided they are not adjacent AND the moderator dump scram is operable.

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

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

The reactor parameter which is protected by Safety Limits is:

a. steady state power level.

b. fuel pellet temperature.

c. moderator level.

d. fuel clad temperature.

QUESTION: 017 (1.00)

"The excess reactivity of the reactor core above cold, clean critical shall not be greater than $0.60." This is an example of a(n):

a. safety limit.

b. limiting safety system setting.

c. limiting condition for operation.

d. surveillance requirement.

QUESTION: 018 (1.00)

The area wherein the reactor administrator may directly initiate emergency activities is defined by the:

a. operations boundary.

b. site boundary.

c. emergency planning zone.

d. emergency support center.

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

B. NORMAL/EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS Page 16 QUESTION: 019 (2.00)

Match the 10 CFR Part 55 requirements listed in Column A for an actively licensed operator with the correct time period from Column B. Column B answers may be used once, more than once, or not at all.

Column A Column B

a. License Expiration 1. 1 year

b. Medical Examination 2. 2 years

c. Requalification Written Examination 3. 3 years

d. Requalification Operating Test 4. 6 years QUESTION: 020 (1.00)

The reactivity worth of a planned moveable experiment is determined to be $0.80. 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 is allowed in the core but must be secured.

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

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

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

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

A linear power channel (LP1 or LP2) uses a (an):

a. uncompensated ion chamber

b. compensated ion chamber

c. fission chamber

d. boron-trifluoride detector QUESTION: 002 (1.00)

If control rod sensitivity is known, withdrawal of the rods as a bank is permitted as long as:

a. reactor period is greater than 20 seconds

b. the reactivity addition does not exceed $0.05 per second

c. the reactivity addition does not exceed $0.12 per second up to 10 times source level.

d. the source level channel has increased by less than one decade QUESTION: 003 (1.00)

Which ONE of the following types of detector is utilized in the area gamma radiation monitoring system?

a. Geiger-Mueller tube

b. Scintillation detector

c. Ionization chamber

d. Proportional counter

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

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

The reactor room ventilation system:

a. operates by natural circulation, with its own vent to the outside stack

b. shares a vent with the control room ventilation system

c. exhaust fan starts up in response to high radiation alarms

d. exhaust vent closes in response to high radiation alarms QUESTION: 005 (1.00) DELETED IAW FACILITY COMMENT Which ONE of the following will result in a control rod withdrawal interlock (i.e., rod remains as is)?

a. Neutron flux = 20 CPS

b. Water level in tank = 11 inches above top grid

c. Reactor period = 20 seconds

d. Failure of 400 cycle power supply QUESTION: 006 (1.00)

The Dump Valve Bypass control:

a. allows air to be admitted to the dump valve operator regardless of the scram condition

b. bleeds air from the dump valve operator to ensure that the valve opens on a scram

c. recloses the dump valve once it has opened if no scram conditions exist

d. locks air onto the dump valve operator if an automatic scram occurs but still allows response to manual scrams

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

C. FACILITY AND RADIATION MONITORING SYSTEMS Page 19 QUESTION: 007 (1.00)

The structure within the core that forms the base of the three-tiered core-support structure is the:

a. carrier plate.

b. plastic spacer plate.

c. fuel pin lattice plate.

d. unistrut support plate.

QUESTION: 008 (1.00)

The "worst case" single instrument malfunction for a reactivity insertion accident is a(n):

a. loss of voltage to the detector for linear power channel 1(LP1).

b. open circuit on the ion chamber for log power channel 2(PP2).

c. interrupt of output current to the Water Dump Valve solenoid.

d. grounded input signal to the short period module of the Solenoid Interrupt Circuit.

QUESTION: 009 (1.00)

The area gamma monitoring system has detectors located in the control room, in the reactor room:

a. on the reactor deck and outside the reactor room window.

b. in the counting room and outside the reactor room window.

c. on the reactor deck and in the fuel storage vault.

d. in the counting room and in the fuel storage vault.

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

C. FACILITY AND RADIATION MONITORING SYSTEMS Page 20 QUESTION: 010 (1.00)

The water dump valve operation may be by-passed by:

a. locking closed the water dump valve operator locally.

b. depressing the bypass pushbutton on the main control panel.

c. placing key switch located on CP-2 to the "By-pass" position.

d. disconnecting the DC current output at the Solenoid Interrupt Circuit module.

QUESTION: 011 (1.00)

Under what condition is the moderator fill pump to be operated during startup?

a. When control rods are in motion.

b. When the dump valve is open and the scram is not bypassed.

c. When water level is less than 68 inches.

d. When the air compressor is secured.

QUESTION: 012 (1.00)

The startup channel detector provides indication of neutron flux by using:

a. current which is triggered by a neutron fission event occurring in the detector.

b. current which is proportional to the number of neutron interactions in the detector.

c. pulses which are triggered by a neutron absorption event occurring in the detector.

d. pulses which are inversely proportional to the input energy of the neutron interaction in the detector.

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

C. FACILITY AND RADIATION MONITORING SYSTEMS Page 21 QUESTION: 013 (1.00)

Which ONE of the following describes the device used for calibrating the logarithmic power channel?

a. Gold-foil neutron flux pin.

b. Boron-impregnated neutron flux pin.

c. Stochastic thermal power temperature recorder.

d. Local gamma-flux power radiation level recorder.

QUESTION: 014 (1.00)

Which ONE of the following describes the warning output of the criticality detector system (area monitor)?

a. An audible alarm is provided in the control room and a visual alarm is provided outside the facility.

b. An audible and visual alarm is provided in the control room.

c. Audible alarm is provided in the reactor room and a visual alarm is provided in the control room.

d. An audible and visual alarm is provided in the reactor room.

QUESTION: 015 (1.00)

Differentiation between gamma and neutron induced signals in the startup channels is accomplished by:

a. amplifying only neutron signals coming from the detector.

b. counting only signals at strengths greater than the gamma signals.

c. adjusting the amplifier gain.

d. adjusting the compensating voltage applied to the detector.

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

C. FACILITY AND RADIATION MONITORING SYSTEMS Page 22 QUESTION: 016 (1.00)

When there is a loss of power, the reactor tank pump:

a. suction valve fails OPEN, and the discharge valve fails CLOSED.

b. suction valve fails OPEN, and the discharge valve fails OPEN.

c. suction valve fails CLOSED, and the discharge valve fails CLOSED.

d. suction valve fails CLOSED, while the discharge valve fails OPEN.

QUESTION: 017 (1.00)

There are three scram functions that may be BYPASSED. They are:

a. high water level scram, reactor door scram, dump valve scram.

b. linear power scram, dump valve scram, period scram.

c. linear power scram, high water level scram, reactor door scram.

d. reactor door scram, period scram, dump valve scram.

QUESTION: 018 (1.00)

The temperature monitoring system monitors the temperatures of the:

a. reactor coolant and fuel.

b. reactor coolant and reactor room air.

c. fuel and reactor room air.

d. reactor coolant and control room air.

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

Lamarsh, Introduction to Nuclear Engineering, 3rd Edition, Section 3.7, Table 3.6.

ANSWER: 011 (1.00)

A.

REFERENCE:

Laboratory 5 Experiment ANSWER: 012 (1.00)

C.

REFERENCE:

Lamarsh, Introduction to Nuclear Engineering, 3rd Edition, Section 7.2, page 336.

Initial reactivity = (K-1)/K = -0.047 K/K. Reactivity added = $7.00 = 7(0.007) = +0.049 K/K.

Lamarsh, Introduction to Nuclear Engineering, 3rd Edition, Section 7.2, page 340.

1st generation = 1x108 ; 2nd generation = (1.001)1x108 = 1.001x108. Increase = 1x105.

Of the increase, 0.993 are prompt neutrons = 99,300.

ANSWER: 019 (1.00)

A.

Technical Specifications, Section 3.1.

ANSWER: 018 (1.00)

B.

REFERENCE:

Emergency Plan, Definitions.

ANSWER: 019 (1.00) a,4; b,2; c,2; d,1.

SAR page 9-1 ANSWER: 005 (1.00) DELETED IAW FACILITY COMMENT D.

REFERENCE:

SAR Figure 7.2 ANSWER: 006 (1.00)

A.

REFERENCE:

Prestart Procedures.

ANSWER: 007 (1.00)

A.

REFERENCE:

SAR page 4-14 ANSWER: 008 (1.00)

B.

REFERENCE:

SAR page 13-1 ANSWER: 009 (1.00)

A.

Emergency Procedures, page 3 ANSWER: 015 (1.00)

B.

REFERENCE:

Laboratory 1.

ANSWER: 016 (1.00)

A.

REFERENCE:

SAR Figure 5.1.

ANSWER: 017 (1.00)

D.

REFERENCE:

Technical Specifications, Section 3.2.

ANSWER: 018 (1.00)

B.

REFERENCE:

Pre-start Procedures.

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 _____ DELETED IAW FACILITY COMMENT

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

B. NORMAL/EMERGENCY OPERATING PROCEDURES AND 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 _____ DELETED IAW FACILITY COMMENT 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 _____

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

EQUATION SHEET Q = m cp T CR1 (1-Keff)1 = CR2 (1-Keff)2 SUR = 26.06/ P = P0 10SUR(t)

P = P0 e(t/) = (R*/) + [(-)/eff]

eff = 0.1 seconds-1 DR1D12 = DR2D22 DR = DRoe-t DR = 6CiE/D2

= (Keff - 1)/Keff 1 eV = 1.6x10-19 watt-sec.

1 Curie = 3.7x1010 dps 1 gallon water = 8.34 pounds 1 Btu = 778 ft-lbf EF = 9/5EC + 32 1 Mw = 3.41x106 BTU/hr EC = 5/9 (EF - 32)

ML060610069

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Dear Mr. Winters:

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