ML051740529

Initial Examination Report No. 50-288/OL-05-02, Reed College, May 2, 2005

ML051740529
Person / Time
Site:	Reed College
Issue date:	07/13/2005
From:	Madden P NRC/NRR/DRIP/RNRP
To:	Frantz S Reed College
Doyle P, NRC/NRR/DRIP/RNRP, 415-1058
Shared Package
ML050490193	List: ML051740529 ML051740660
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50-288/OL-05-02 50-288/OL-05-02
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Text

July 13, 2005 Mr. Steven G. Frantz, Director Reed Reactor Facility 3203 SE Woodstock Blvd.

Portland, OR 97202

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-288/OL-05-02, Reed College

Dear Mr. Frantz:

During two weeks starting May 2, 2005, the NRC administered operator licensing examinations at your Reed College Reactor. The examinations were 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 2.390 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 NRC's 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/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. Paul V. Doyle Jr. at (301) 415-1058 or via internet e-mail pvd@nrc.gov.

Sincerely,

/RA/

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. 50-288

Enclosures:

1. Initial Examination Report No. 50-288/OL-05-02

2. Examination (Modified per facility comments) cc w/encls: Please see next page

July 13, 2005 Mr. Steven G. Frantz, Director Reed Reactor Facility 3203 SE Woodstock Blvd.

Portland, OR 97202

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-288/OL-05-02, Reed College

Dear Mr. Frantz:

During two weeks starting May 2, 2005, the NRC administered operator licensing examinations at your Reed College Reactor. The examinations were 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 2.390 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 NRC's 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/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. Paul V. Doyle Jr. at (301) 415-1058 or via internet e-mail pvd@nrc.gov.

Sincerely,

/RA/

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. 50-288

Enclosures:

1. Initial Examination Report No. 50-288/OL-05-02

2. Examination (Modified per facility comments) cc w/encls: Please see next page DISTRIBUTION:

PUBLIC RNRP R&TR r/f PMadden DHughes Facility File (EBarnhill) O-6 F-2 EXAMINATION PACKAGE ACCESSION NO.: ML050490193 EXAMINATION REPORT ACCESSION #: ML051740529 TEMPLATE #: NRR-074 OFFICE RNRP:CE IROB:LA RNRP:SC NAME PDoyle EBarnhill PMadden DATE 6/29/2005 7/4/2005 7/11/2005 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY

Reed College Docket No. 50-288 cc:

Mayor of the City of Portland 1220 Southwest 5th Avenue Portland, OR 97204 Reed College ATTN: Dr. Peter Steinberger Dean of Faculty 3203 S.E. Woodstock Boulevard Portland, OR 97202-8199 Reed College ATTN: Dr. Colin Diver, President 3203 S.E. Woodstock Boulevard Portland, OR 97202-8199 Oregon Department of Energy ATTN: David Stewart-Smith, Director Division of Radiation Control 625 Marion Street, N.E.

Salem, OR 97310 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-288/OL-05-02 FACILITY DOCKET NO.: 50-288 FACILITY LICENSE NO.: R-112 FACILITY: Reed College EXAMINATION DATES: May 02-12, 2005 SUBMITTED BY: ______/RA/____________________ 6/11/05__

Paul V. Doyle Jr., Chief Examiner Date

SUMMARY

The NRC administered Operator Licensing examinations to 21 Reactor Operator candidates and 11 Senior Reactor Operator candidates. One RO candidate failed Section C of the written examination. All other candidates passed their respective portions of the Examinations.

REPORT DETAILS

1. Examiners:

Paul V. Doyle Jr., Chief Examiner Warren Eresian and Patrick Isaac, Examiners

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 20/1 0/0 20/1 Operating Tests 21/0 11/0 32/0 Overall 20/1 11/0 31/1

3. Exit Meeting:

Paul V. Doyle Jr., NRC, Chief Examiner Patrick Isaac, NRC, Examiner Stephen Frantz, Reed College, Facility Director Rachel Barnett, Reed College Facility Associate Director During the exit meeting the examiners thanked the facility staff for their support in administering the examination. The facility staff presented the chief examiner with their comments on the written examination, which have been incorporated into the examination included as Enclosure 2 to this report. The examiners both noted that a few of the candidates stated that a purpose stamp was required every half hour during continuous operation, and a few candidates incorrectly stated that the fission chamber counts alpha pulses rather than pulses due to fission products.

ENCLOSURE 1

OPERATOR LICENSING EXAMINATION With Answer Key REED COLLEGE May 02, 2005 ENCLOSURE 2

Section A: L Theory, Thermodynamics & Facility Operating Characteristics Page 1 QUESTION A.1 [1.0 point]

You enter the control room and note that all nuclear instrumentation show a steady neutron level, and no rods are in motion. Which ONE of the following conditions CANNOT be true?

a. The reactor is critical.

b. The reactor is subcritical.

c. The reactor is supercritical.

d. The neutron source has been removed from the core.

QUESTION A.2 [1.0 point]

The two major fission products formed in a U235 fueled reactor, samarium and xenon, have both large absorption cross sections and a significant yield. Therefore they have a marked effect on the neutron multiplication factor by decreasing which factor in the six factor formula?

a. th or Pth the thermal non-leakage probability

b. 0, the fuel utilization factor

c. p, the resonance escape probability

d. f, the thermal utilization factor QUESTION A.3 [1.0 point]

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

a. 1 Kilowatt: from 1 kW to 2 kW

b. 1.5 Kilowatts: from 2 kW to 3.5 kW

c. 2 Kilowatts: from 3.5 kW to 5.5 kW

d. 2.5 Kilowatts: from 5.5 kW to 8 kW QUESTION A.4 [1.0 point]

After shutdown, the reactor will stabilize at a -80 second period. Which ONE of the following is the main contributor to this period?

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

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

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

d. The level of the prompt neutron population.

Section A: L Theory, Thermodynamics & Facility Operating Characteristics Page 2 QUESTION A.5 [1.0 point]

The neutron microscopic cross-section for absorption Fa generally

a. increases as neutron energy increases

b. decreases as neutron energy increases

c. increases as target nucleus mass increases

d. decreases as target nucleus mass increases QUESTION A.6 [1.0 point]

Suppose the source strength in the core is 250 neutrons per second (N/sec) and the effective multiplication factor is 0.80. Select the closest stable neutron count rate from the list below:

a. 300 N/sec

b. 750 N/sec

c. 1250 N/sec

d. 1500 N/sec QUESTION A.7 [1.0 point]

Which one of the following statements details the effect of fuel temperature on core operating characteristics? As fuel temperature

a. increases, doppler peaks will become higher.

b. decreases, resonance escape probability will increase.

c. decreases, U238 will absorb more neutrons.

d. increases, the fast non-leakage probability will decrease.

QUESTION A.8 [1.0 point]

What is the approximate amount of time that it will take the amount of Xenon being produced to reach a peak after the reactor is shut down? On the attached Xenon reactivity curve it is noted as the difference between time TSD and TPeak.

a. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />

b. 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />

c. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

d. 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br />

Section A: L Theory, Thermodynamics & Facility Operating Characteristics Page 3 QUESTION A. 9 [1.0 point]

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

a. Increases toward one

b. Decreases toward one

c. Increases toward infinity

d. Decreases toward zero QUESTION A.10 [1.0 point]

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

a. High scattering cross-section and low absorption cross-section.

b. Low scattering cross-section and high absorption cross-section.

c. Low scattering cross-section and low absorption cross-section.

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

QUESTION A.11 [1.0 point]

The reactor supervisor tells you that the Keff for the reactor is 0.955. How much reactivity must you add to the reactor to reach criticality?

a. +0.0471

b. +0.0450

c. -0.0471

d. -0.0450 QUESTION A.12 [1.0 point]

You are increasing reactor power on a steady +26 second period. How long will it take to increase power by a factor of 1000?

a. 60 seconds (1 minute)

b. 180 seconds (3 minutes)

c. 300 seconds (5 minutes)

d. 480 seconds (8 minutes)

Section A: L Theory, Thermodynamics & Facility Operating Characteristics Page 4 QUESTION A.13 [2.0 points, 0.5 each]

Match each term in column A with the correct definition in column B.

Column A Column B

a. Prompt Neutron 1. A neutron in equilibrium with its surroundings.

b. Fast Neutron 2. A neutron born directly from fission.

c. Thermal Neutron 3. A neutron born due to decay of a fission product.

d. Delayed Neutron 4. A neutron at an energy level greater than its surroundings.

QUESTION A.14 [1.0 point]

A characteristic peculiar to TRIGA fuel is that it has a relatively large (and quickly acting)

a. pressure coefficient.

b. void coefficient.

c. bath temperature coefficient.

d. fuel temperature coefficient.

QUESTION A.15 [1.0 point]

Which ONE of the following is the correct reason that delayed neutrons enhance control of the reactor?

a. There are more delayed neutrons than prompt neutrons.

b. Delayed neutrons increase the average neutron generation time.

c. Delayed neutrons are born at higher energies than prompt neutrons and therefore have a greater effect.

d. Delayed neutrons take longer to reach thermal equilibrium.

QUESTION A.16 [1.0 point]

Which ONE of the following is the DOMINANT factor in determining the differential reactivity worth of a control rod?

a. Radial and axial flux.

b. Total reactor power.

c. Control rod speed.

d. Delayed neutron fraction.

Section A: L Theory, Thermodynamics & Facility Operating Characteristics Page 5 QUESTION A.17 [1.0 point]

INELASTIC scattering is the process by which a neutron collides with a nucleus and

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

b. recoils with a lower kinetic energy than it had prior to the collision, with the nucleus emitting a gamma ray.

c. Is absorbed, with the nucleus emitting a gamma ray.

d. recoils with a higher kinetic energy than it had prior to the collision, with the nucleus emitting a gamma ray.

QUESTION A.18 [1.0 point]

Which one of the below describes why neutron sources are used in reactor cores?

a. Increase the count rate by an amount equal to the source contribution.

b. Increase the count rate by 1/M (M = Subcritical Multiplication Factor).

c. Provide the source neutrons to initiate the chain reaction when first starting-up the reactor.

d. Provide a neutron level high enough to be monitored by source range instrumentation.

QUESTION A.19 [1.0 point]

Which ONE of the following conditions will INCREASE the shutdown margin of a reactor.

a. Insertion of a positive reactivity worth experiment

b. Lowering moderator temperature (Assume negative temperature coefficient).

c. Burnout of a burnable poison.

d. Fuel depletion.

Section B Normal/Emergency Procedures & Radiological Controls Page 6 QUESTION B.1 [2.0 points, 1/2 each]

Identify whether each of the following experiments is Not Allowed (NA), must be doubly encapsulated (Double), or has no special requirements (NSR). Experiments which contain

a. explosive materials.

b. Liquid fissionable materials

c. materials corrosive to reactor components.

d. compounds highly reactive with water.

QUESTION B.2 [2.0 points, 0.5 each]

Match the type of radiation in column A with its associated Quality Factor (10CFR20) from column B.

Column A Column B

a. alpha 1

b. beta 2

c. gamma 5

d. neutron (unknown energy) 10 20 QUESTION B.3 [2.0 points, 0.5 each]

Identify whether each of the following logbook entries would be made in black ink (BLACK), green ink, (GREEN), red ink (RED) or would be black with red underline (R/U)

a. Removed fuel element ___ for inspection.

b. Removed Neutron source from core.

c. Scram due to trainee error early during a startup.

d. At power, reactor scram due to loss of electrical power to facility.

QUESTION B.4 [1.0 point]

Many research reactors use different methods to reduce the dose due to N16 at the pool top. If the method used keeps the N16 ten (10) feet below the surface of the water, and a half-thickness for the N16 gamma(s) is one foot for water, then the dose due to N16 is reduced (approximately) by a factor of (Note: Neglect any reduction in dose rate due to half-life.)

a. 20

b. 100

c. 200

d. 1000

Section B Normal/Emergency Procedures & Radiological Controls Page 7 QUESTION B.5 [1.0 point]

According to Technical Specification J.4(c) Experiments having reactivity worths greater than

_______ shall be securely located or fastened to prevent inadvertent movement during reactor operations.

a. $.25

b. $.50

c. $.75

d. $1.0 QUESTION B.6 [1.0 point]

Which ONE of the following is the definition of Emergency Action Level?

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

b. Specific instrument readings, or observations; radiation dose or dose rates; or specific contamination levels of airborne, waterborne, or surface-deposited radioactive materials that may be used as thresholds for establishing emergency classes and initiating appropriate emergency methods.

c. classes of accidents grouped by severity level for which predetermined emergency measures should be taken or considered.

d. a document that provides the basis for actions to cope with an emergency. It outlines the objectives to be met by the emergency procedures and defines the authority and responsibilities to achieve such objectives.

QUESTION B.7 [1.0 point]

The scram time for the scrammable control element were last measured on March 31, 2004. Which one of the following dates is the latest the maintenance may be performed again without exceeding a Technical Specifications requirement?

a. Six months later, September 30, 2005

b. 32 weeks later, November 10, 2005

c. 9 months later, December 31, 2005

d. 40 weeks later, January 5, 2006

Section B Normal/Emergency Procedures & Radiological Controls Page 8 QUESTION B.8 [1.0 point]

During a fire, you notice that the key for the main circuit breaker is not in the key hole. Where would you go to find the spare key?

a. the Emergency Grab Bag.

b. the Facility Director's desk in Room 102 of the chemistry building.

c. the Assistant Facility Director's desk in Room 102 of the chemistry building.

d. the desk in the control room.

QUESTION B.9 [2.0 points, 0.5 each]

Match the 10CFR55 requirements for maintaining an active operator license in column A with the corresponding time period from column B.

Column A Column B

a. Renew License 1 year

b. Medical Exam 2 years

c. Pass Requalification Written Examination 4 years

d. Pass Requalification Operating Test 6 years QUESTION B.10 [1.0 point, 1/4 each] Choice A deleted during examination due to fact that Tritium is NOT a concern at Reed College. Also Point value changed to a each Identify the PRIMARY source (irradiation of air, irradiation of water, or fission product) of EACH of the radioisotopes listed.

a. 1H3 Deleted during examination!

b. 18Ar41

c. 7N16

d. 54Xe135

Section B Normal/Emergency Procedures & Radiological Controls Page 9 QUESTION B.11 [2.0 points, 1/2 each] Question replaced during examination. See end of Section B.

Identify each of the following actions as either a channel CHECK, a channel TEST, or a channel CALibration.

a. Prior to startup you place a known radioactive source near a radiation detector, noting meter movement and alarm function operation.

b. During startup you compare all of your nuclear instrumentation channels ensuring they track together.

c. At power, you perform a heat balance (calorimetric) and determine you must adjust Nuclear Instrumentation readings.

d. During a reactor shutdown you note a -80 second period on Nuclear Instrumentation.

QUESTION B.12 [1.0 point]

Which ONE of the following conditions is a violation of Technical Specifications?

a. Core Excess Reactivity is 2.2 % )k/k with experiments in place.

b. Pool water conductivity is 2 :mhos/cm averaged over 1 month.

c. Bulk pool temperature during reactor operation is 120°F (48.9°C).

d. The RAM is inoperable (for a short period of time) during reactor operations.

QUESTION B.13 [1.0 point]

The CURIE content of a radioactive source is a measure of

a. the number of radioactive atoms in the source.

b. the amount of energy emitted per unit time by the source

c. the amount of damage to soft body tissue per unit time.

d. the number of nuclear disintegrations per unit time.

QUESTION B.14 [1.0 point]

A survey instrument with a window probe was used to measure an irradiated experiment. The results were 100 millirem/hr window open and 60 millirem/hr window closed. What was the gamma dose?

a. 100 millirem/hr

b. 60 millirem/hr

c. 40 millirem/hr

d. 140 millirem/hr

Section B Normal/Emergency Procedures & Radiological Controls Page 10 QUESTION B.15 [1.0 point]

Technical Specification 5.8 requires that All fuel elements or fueled devices outside the reactor core shall be stored in a geometry such that the calculated Keff is less than _____ under all conditions of moderation.

a. 0.80

b. 0.85

c. 0.90

d. 0.95 QUESTION B.11new [1.0 point] Question added during examination.

Which ONE of the following Emergency classifications is NOT credible at Reed College?

a. Alert.

b. General Emergency.

c. Non-L Safety Related Event.

d. Notification of Unusual Event.

QUESTION B.16 [1.0 point] Question added during examination.

When removing a control element, per SOP-41 Control Rod Inspection, you must first remove [a] fuel element[s].

Which ONE of the following correctly describes the fuel elements required to be removed?

a. 1 from A ring

b. 1 from B ring

c. 2 from B ring

d. 2 from C ring

Section C Facility and Radiation Monitoring Systems Page 11 QUESTION C.1 [1.0 point]

WHICH ONE of the following is the purpose of the diffuser on the return of the primary coolant system?

a. Increase heat transfer rate due to increased mixing within the core.

b. Decrease the activation rate of O16 to N16 due to reduced time in core.

c. Increase transport time for N16 to reach surface of pool.

d. Break up of O16 bubbles in pool, thereby decreasing production of N16.

QUESTION C.2 [1.0 point]

In order to minimize the effects of Ar41 from the pneumatic tube (rabbit) system, the

a. exhaust of the system is connected to the Ar41 purge system.

b. piping is a recirculating loop with a CO2 purge.

c. piping is a recirculating loop with an N2 purge.

d. exhaust of the system is located in the facility exhaust stack.

QUESTION C.3 [1.0 point]

Which ONE of the following is the reason that primary temperature is maintained below 49°C? Above this temperature the

a. diffusion of N16 from the pool increases dramatically.

b. bath temperature coefficient changes from negative to positive.

c. the purification system filter melts.

d. the demineralizer resin rate of depletion increases.

QUESTION C.4 [1.0 point]

Which ONE of the following is the method used to minimize mechanical shock to the standard control rods on a scram?

a. A small spring located at the bottom of the rod.

b. A piston, (part of the connecting rod) drives water out of a dashpot as the rod nears the bottom of its travel.

c. An electrical-mechanical brake energizes when the rod down limit switch is energized.

d. A piston (part of the connecting rod) drives air out of a dashpot as the rod nears the bottom of travel.

Section C Facility and Radiation Monitoring Systems Page 12 QUESTION C.5 [1.0 point]

Flow through the demineralizer loop is limited to 10 gallons per minute. This limit is to

a. prevent blowing resin out of the demineralizer thereby clogging the filter.

b. creating channels through the demineralizer reducing efficiency.

c. overpressurization of the demineralizer.

d. blowing the upstream filter into the demineralizer.

QUESTION C.6 [1.0 point]

Each fuel element contains a top and bottom reflector plugs which are made of

a. zirconium

b. zirconium hydride

c. graphite

d. polyethylene QUESTION C.7 [1.0 point]

Which ONE of the following parameters is NOT measured in the Primary Cooling/Purification System Loops?

a. Temperature

b. Flow Rate

c. Conductivity

d. pH QUESTION C.8 [1.0 point]

WHICH ONE of the following detectors is used primarily to measure N16 release to the environment?

a. NONE, N16 has too short a half-life to require environmental monitoring.

b. Stack Gas Monitor

c. Stack Particulate Monitor

d. Bridge Area Monitor

Section C Facility and Radiation Monitoring Systems Page 13 QUESTION C.9 [2.0 points, 0.4 each]

Using the figure provided, identify whether each of the dampers listed below is Open or Closed, Modulates on a ventilation system Isolation.

a. Damper 10

b. Damper 12

c. Damper 13

d. Damper 14

e. Damper 15 QUESTION C.10 [1.0 point]

Which ONE of the following facility detectors does NOT have an input signal into the Multitrend?

a. CAM

b. Log-N Channel

c. Bulk Water Temperature

d. Primary Conductivity QUESTION C.11 [1.0 point, 0.333 each]

Match the detector type in column B with its respective Nuclear Instrument Channel in column A.

Instrumentation Channel Detector Type

a. Linear 1. Fission Chamber

b. Log-N 2. Uncompensated Ion Chamber

c. Percent Power 3. Compensated Ion Chamber QUESTION C.12 [1.0 point]

Following a scram, the lights for the regulating rod are as follows RED: OFF, White ON, BLUE: ON and Yellow:

ON

a. Rod is still at top beginning to insert.

b. Rod is down but Motor is up

c. Rod and Motor are down, scram signal still present.

d. Rod and Motor are down, Scram is reset.

Section C Facility and Radiation Monitoring Systems Page 14 QUESTION C.13 [1.0 point]

Which ONE of the following is the reason for two conductivity probes in the purification system?

a. Primary and Backup indication.

b. Comparing the two readings you can measure the efficiency of the demineralizer.

c. Comparing the two readings you can calculate the pH.

d. Using two readings minimizes differences in temperature between the two probes.

QUESTION C.14 [1.0 point]

What is the purpose of the orifice in the Primary Cooling System?

a. To restrict coolant flow to 20 gpm through the demineralizers.

b. To prevent excessive coolant flow back into the core.

c. To restrict coolant flow to 100 gpm bypassing the demineralizers.

d. To prevent excessive backpressure on the heat exchanger.

QUESTION C.15 [1.0 point]

Which ONE of the following correctly describes how condensation is removed from the Lazy Susan?

a. Periodic draining of the pool, allowing the condensation to evaporate.

b. An electric heater is placed in an insulated specimen tube, which is inserted into the rack.

c. An inert gas is blown into the lazy susan to force the condensation out.

d. A water absorbent material is placed in a perforated specimen tube, which is inserted into the rack.

QUESTION C.16 [2.0 points, 0.5 each]

Match the facility radiation detector in column A with the type of radiological problem it detects in column B.

Column A Column B

a. RAM 1. Gases and Particulates

b. CAM 2. Particulates Only

c. APM 3. Radiation Level

d. GSM 4. Gases Only

Section C Facility and Radiation Monitoring Systems Page 15 QUESTION C.17 [2.0 points, 0.5 each]

Match the Input Signal from the respective Control and Instrumentation circuits in COLUMN A to the correct outputs in COLUMN B. (Items in COLUMN B may be used more than once or not at all.)

COLUMN A COLUMN B

a. Log-N Period channel 1. Indication Only

b. Log Count Rate channel 2. Indication and Scram

c. Linear Power channel 3. No Indication

d. Percent Power channel

Section A: L Theory, Thermodynamics & Facility Operating Characteristics Page 16 A.1 c REF: Reed Reactor Training Manual, § 8.1, p. 135 A.2 d REF: Reed Reactor Training Manual, § 8.2 pp. 137-140 A.3 a REF: P = P0et/T A.4 b REF: Reed Reactor Training Manual, § 9.7, Example 9.4, pp. 158-159 A.5 b REF: Reed Reactor Training Manual, § 6.3, p. 114 A.6 c REF: Reed Reactor Training Manual, § 8.4, p. 143 A.7 b REF: Reed Reactor Training Manual, § 10.6, p. 206 A.8 a REF: Reed Reactor Training Manual, § 10.4, p. 185 A.9 d REF: Reed Reactor Training Manual, § 8.4, p. 145 A.10 a REF: Reed Reactor Training Manual, § 10.5, p. 189 A.11 a REF: )D= (Keff1 - Keff2) ÷ (Keff1

• Keff2) )D = (0.9550 - 1.0000) ÷ (0.9550

• 1.0000)

)D = -0.0450 ÷ 0.9550 = -0.0471 A.12 b REF: ln (P/P0) x period = time, ln(1000) x 26 = 6.908 x 26 = 179.6 . 180 seconds A.13 a, 2; b, 4; c, 1; d, 3 REF: Reed Training Manual, §§ 7.3, 9.4 and 9.6, pp. 126, 151 and 154.

A.14 d REF: Reed Reactor Training Manual, § 10.6, p. 194 A.15 b REF: Reed Reactor Training Manual, § 9.7 p. 159 A.16 a REF: Reed Reactor Training Manual, § 10.3, p. 173 A.17 b REF: Reed Reactor Training Manual, § 3.3, p. 38 A.18 d or c 2nd answer added per facility comment.

REF: Standard NRC Question.

A.19 d REF: Reed Reactor Training Manual, § 10.1

Section B Normal/Emergency Procedures & Radiological Controls Page 17 B.1 a, NA; b Double; c, Double; d, Double REF: Technical Specification J.5, J.6 B.2 a, 20; b, 1; c, 1; d, 10 REF: 10CFR20.100x B.3 a, RED; b, R/U; c, BLACK; d, GREEN; REF:

B.4 d REF: Basic Radiological Controls knowledge: Half-Thickness and Tenth-Thickness". 210 = 1024 B.5 d REF: Technical Specification J.4(c)

B.6 b REF: Emergency Plan, § 2.0 Definitions, p. 6.

B.7 c REFERENCE T.S. §§ F.9.a (Semi-annual) and A.7 (not to exceed 32 weeks)

B.08 a REF: Emergency Implementing Procedures, p. 4.

B.9 a, 6; b, 2; c, 2; d, 1 REF: 10CFR55.

B.10 a, Water; b, Air; c, Water; d, Fission REF: Standard NRC question.

B.11 a, Check; b, Test; c, Cal; d, Check REF: Technical Specification 1.2.1-3 B.11new b REF: Emergency Plan B.12 d REF: Technical Specifications §§ D, E and G.

B.13 d REF: Standard Health Physics Definition.

B.14 b REF: Standard NRC Health Physics Question B.15 a REF: Technical Specifications § H.1 B.16 c REF: SOP-x,

Section C Facility and Radiation Monitoring Systems Page 18 C.1 c REF: Operation Support systems, § 1.2 2nd ¶.

C.2 d REF: Operation Support systems, § 3.2 1st ¶.

C.3 d REF: RRF TRIGA Mk I Mech. Maint. & Op. Manual, § 5.11.7 C.4 b REF: RRF TRIGA Mk I Mech. Maint. & Op. Manual, § 5.11.3 C.5 b REF: RRF TRIGA Mk I Mech. Maint. & Op. Manual, § 5.11.1 C.6 c REF: Reed Reactor Training Manual, § 11.3, p. 204 C.7 d REF: Reed Reactor Training Manual, § 11.6, pp. 214-215.

C.8 a REF: Standard NRC Question C.9 a, Closed; b, Open; c, Closed; d, Open e, Modulates REF: Reed Reactor Training Manual § 11.8, 2nd ¶ on page 217.

C.10 d REF: SOP-11, Multitrend Operation, § 11.7.1 1st ¶, page 2.

C.11 a, 3; b, 1; c, 2 REF: Reed Reactor Training Manual § 11.7 Instrumentation. Figure 11.3.

C.12 d REF: Reed Reactor Training Manual § 11, Table 11.1.

C.13 b REF: Reed Reactor Training Manual § 11.6, 4th ¶ on p. 214 C.14 a REF: Reed Reactor Training Manual, § 11.x C.15 d REF: RRF TRIGA Mk I Mech. Maint. & Op. Manual, § 4.3.4, p. 41.

C.16 a, 3; b, 2; c, 2; d, 4 REF: SOP-30, RAM Calibration, § 30.1; SOP-31, CAM Calibration, § 31.1; SOP-32, APM Calibration § 32.1; SOP-33, GSM Calibration

§ 33.1 C.17 a. 1; b. 3; c, 2; d, 2 REF: SAR Figure 5-7 Block diagram of Reactor Instrumentation for Steady State Operation

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: Reed Reactor Facility REACTOR TYPE: TRIGA DATE ADMINISTERED: 2005/05/02 REGION: IV CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheet provided. Attach the answer sheets to the examination. Points for each question are indicated in brackets for each question. A 70% in each section is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

% of Category % of Candidates Category Value Total Score Value Category 20.00 33.3 A. Reactor Theory, Thermodynamics and Facility Operating Characteristics 20.00 33.3 B. Normal and Emergency Operating Procedures and Radiological Controls 20.00 33.3 C. Facility and Radiation Monitoring Systems 60.00  % 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 three (3) 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.

Section A L Theory, Thermo, and Facility Characteristics Page 21 A.1 a b c d ___ A.12 a b c d ___

A.2 a b c d ___ A.13a 1 2 3 4 ___

A.3 a b c d ___ A.13b 1 2 3 4 ___

A.4 a b c d ___ A.13c 1 2 3 4 ___

A.5 a b c d ___ A.13d 1 2 3 4 ___

A.6 a b c d ___ A.14 a b c d ___

A.7 a b c d ___ A.15 a b c d ___

A.8 a b c d ___ A.16 a b c d ___

A.9 a b c d ___ A.17 a b c d ___

A.10 a b c d ___ A.18 a b c d ___

A.11 a b c d ___ A.19 a b c d ___

Section B Normal/Emerg. Procedures & Rad Con Page 22 B.1a N/A Double NSR ___ B.9a 1 2 4 6 ___

B.1b N/A Double NSR ___ B.9b 1 2 4 6 ___

B.1c N/A Double NSR ___ B.9c 1 2 4 6 ___

B.1d N/A Double NSR ___ B.9d 1 2 4 6 ___

B.2a 1 2 5 10 20 ___ B.10a Water Air Water Fission ___

B.2b 1 2 5 10 20 ___ B.10b Water Air Water Fission ___

B.2c 1 2 5 10 20 ___ B.10c Water Air Water Fission ___

B.2d 1 2 5 10 20 ___ B.10d Water Air Water Fission ___

B.3a Black Green Red R/U ___ B.11a Check Test CAL ____

B.3b Black Green Red R/U ___ B.11b Check Test CAL ____

B.3c Black Green Red R/U ___ B.11c Check Test CAL ____

B.3d Black Green Red R/U ___ B.11d Check Test CAL ____

B.4 a b c d ___ B.12 a b c d ___

B.5 a b c d ___ B.13 a b c d ___

B.6 a b c d ___ B.14 a b c d ___

B.7 a b c d ___ B.15 a b c d ___

B.8 a b c d ___

Section C Facility and Radiation Monitoring Systems Page 23 C.1 a b c d ___ C.11a 1 2 3 ___

C.2 a b c d ___ C.11b 1 2 3 ___

C.3 a b c d ___ C.11c 1 2 3 ___

C.4 a b c d ___ C.12 a b c d ___

C.5 a b c d ___ C.13 a b c d ___

C.6 a b c d ___ C.14 a b c d ___

C.7 a b c d ___ C.15 a b c d ___

C.8 a b c d ___ C.16a 1 2 3 4 ___

C.9a Open Closed Moderates ___ C.16b 1 2 3 4 ___

C.9b Open Closed Moderates ___ C.16c 1 2 3 4 ___

C.9c Open Closed Moderates ___ C.16d 1 2 3 4 ___

C.9d Open Closed Moderates ___ C.17a 1 2 3 ___

C.9e Open Closed Moderates ___ C.17b 1 2 3 ___

C.10 a b c d ___ C.17c 1 2 3 ___

C.17d 1 2 3 ___