Text

Initial Examination Report, No. 50-223/OL-10-01, University of Massachusetts-Lowell
	ML102420012
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Site:	University of Lowell
Issue date:	10/05/2010
From:	Johnny Eads; Research and Test Reactors Branch B
To:	Kegel G; Univ of Massachusetts - Lowell
	Young P T, NRR/PROB, 415-4094
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ML101540124	List: ML102420012; ML102420059;
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	50-223/OL-10-01
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October 5, 2010 Dr. Gunter Kegel, Director Nuclear Radiation Laboratory University of Massachusetts Lowell One University Avenue Lowell, MA 01854

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-223/OL-10-01, UNIVERSITY OF MASSACHUSETTS - LOWELL.

Dear Dr. Kegel:

During the week of August 16, 2010, the NRC administered an operator licensing examination at the University of Massachusetts - Lowell Nuclear Reactor. The examination was conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. 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 Title 10 of the Code of Federal Regulations Section 2.390, 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 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 Phillip T. Young at 301-415-4094 or via internet e-mail Phillip.Young@nrc.gov.

Sincerely,

/RA/

Johnny Eads, Jr., Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-233

Enclosures:

1. Initial Examination Report No. 50-233/OL-10-01

2. Written examination with facility comments incorporated cc without enclosures: See next page

October 5, 2010 Dr. Gunter Kegel, Director Nuclear Radiation Laboratory University of Massachusetts Lowell One University Avenue Lowell, MA 01854

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-223/OL-10-01, UNIVERSITY OF MASSACHUSETTS - LOWELL.

Dear Dr. Kegel:

During the week of August 16, 2010, the NRC administered an operator licensing examination at the University of Massachusetts - Lowell Nuclear Reactor. The examination was conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. 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 Title 10 of the Code of Federal Regulations Section 2.390, 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 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 Phillip T. Young at 301-415-4094 or via internet e-mail Phillip.Young@nrc.gov.

Sincerely,

/RA/

Johnny Eads, Jr., Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-233

Enclosures:

1. Initial Examination Report No. 50-233/OL-10-01

2. Written examination with facility comments incorporated cc without enclosures: See next page DISTRIBUTION w/ encls.:

PUBLIC PROB r/f RidsNRRDPRPRLB RidsNRRDPRPROB Facility File (CRevelle) O-7 F-08 ADAMS ACCESSION #: ML102420012 TEMPLATE #:NRR-074 OFFICE PROB:CE IOLB:LA E PROB:SC NAME PYoung CRevelle JEads DATE 9/2/2010 10/5/2010 10/5/2010 OFFICIAL RECORD COPY

University of Massachusetts - Lowell Docket No. 50-223 cc:

Mayor of Lowell City Hall Lowell, MA 01852 Mr. Leo Bobek Reactor Supervisor University of Massachusetts - Lowell One University Avenue Lowell, MA 01854 Department of Environmental Protection One Winter Street Boston, MA 02108 Robert J. Walker, Director Radiation Control Program Department of Public Health Schrafft Center, Suite 1M2A 529 Main Street Charlestown, MA 02129 Nuclear Preparedness Manager Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399 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.: 50-233/OL-10-01 FACILITY DOCKET NO.: 50-233 FACILITY LICENSE NO.: R-74 FACILITY: University of Massachusetts - Lowell EXAMINATION DATES: August 17-18, 2010 SUBMITTED BY: _________________________ _8/ 24 /2010_

Philip T. Young, Chief Examiner Date

SUMMARY

During the week of August 16, 2010, the NRC administered operator licensing examinations to two Reactor Operator candidates and one Senior Operator candidate. All candidates passed all portions of the examination.

REPORT DETAILS

1. Examiners:

Phillip T. Young, NRC, Chief Examiner

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 2/0 0/0 2/0 Operating Tests 2/0 1/0 3/0 Overall 2/0 1/0 3/0

3. Exit Meeting:

Phillip T. Young, NRC, Chief Examiner Leo M. Bobek, Reactor Supervisor Thomas Regan, Chief Reactor Operator The NRC examiner thanked the facility staff for their comments on questions A.008 and A.013, (incorporated in enclosure two to this report).

UNIVERSITY OF MASSACHUSETTS, LOWELL No. 50-223 Operator License Examination OL-10-01 August 16, 2010 Examination with Answer Key

Section A - Reactor Theory, Thermo & Facility Operating Characteristics Page 6 of 28 Question A.001 [1.0 point] (1.0)

Which ONE of the following explains the response of a SUBCRITICAL reactor to equal insertions of positive reactivity as the reactor approaches criticality?

a. Each insertion causes a SMALLER increase in the neutron flux resulting in a LONGER time to stabilize.

b. Each insertion causes a LARGER increase in the neutron flux resulting in a LONGER time to stabilize.

c. Each insertion causes a SMALLER increase in the neutron flux resulting in a SHORTER time to stabilize.

d. Each insertion causes a LARGER increase in the neutron flux resulting in a SHORTER time to stabilize.

Answer: A.001 b.

Reference:

Given a source strength of 100 neutrons per second (N/sec) and a multiplication factor of 0.8, the expected neutron count rate would be:

a. 125 N/sec

b. 250 N/sec

c. 400 N/sec

d. 500 N/sec Answer: A.002 d.

Reference:

C.R. = S/(1 - Keff) C.R. = 100/(1 - 0.8) = 100/0.2 = 500 Question A.003 [1.0 point] (3.0)

The reactor is critical and increasing in power. Power has increased from 20 watts to 80 watts in 60 seconds. How long will it take at this rate for power to increase from 0.080 KW to 160 KW?

a. 0.5 minute

b. 2.5 minutes

c. 5.5 minutes

d. 10.5 minutes Answer: A.003 c.

Reference:

P = Poet/T 80 = 20e60 sec/T T = 43.28 sec 1.6 x 105 watts = 80et/43.28 t = 329 sec = 5.5 minutes

Section A - Reactor Theory, Thermo & Facility Operating Characteristics Page 7 of 28 Question A.004 [1.0 point] (4.0)

Following 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months at 1 MW, the reactor operator reduces reactor power to 50%. Rod control is placed in manual mode and all rod motion is stopped. Which one of the following describes the response of reactor power, without any further operator actions, and the PRIMARY reason for its response?

a. Power increases due to the burnout of xenon.

b. Power increases due to the burnout of samarium.

c. Power decreases due to the buildup of xenon.

d. Power decreases due to the buildup of samarium.

Answer: A.004 c.

Reference:

§§ 8.1 8.4, pp. 8-3 8-14.

Question A.005 [1.0 point] (5.0)

Several processes occur that may increase or decrease the available number of neutrons. SELECT from the following the six-factor formula term that describes an INCREASE in the number of neutrons during the cycle.

a. Reproduction factor.

b. Thermal utilization factor.

c. Resonance escape probability.

d. Thermal non-leakage probability.

Answer: A.005 a.

Reference:

By definition, an exactly critical reactor can be made prompt critical by adding positive reactivity equal to

a. the shutdown margin

b. the Kexcess margin

c. the eff value

d. 1.0 %K/K.

Answer: A.006 c.

Reference:

Section A - Reactor Theory, Thermo & Facility Operating Characteristics Page 8 of 28 Question A.007 [1.0 point] (7.0)

Reactor power doubles in 42 seconds. Based on the period associated with this transient, how long will it take for reactor power to increase by a factor of 10?

a. 80 seconds

b. 110 seconds

c. 140 seconds

d. 170 seconds Answer: A.007 c.

P = P0 et/ 1st find . = time/(ln(2)) = 42/0.693 = 60.6 sec. Time = x ln(10) = 60.6 x 139.5 sec

Reference:

Five minutes after shutting down the reactor, reactor power period is 3 x 106 counts per minute. Which ONE of the following is the count rate you would expect to three minutes later?

a. 1 x 106 cpm

b. 8 x 105 cpm

c. 5 x 105 cpm

d. 3 x 105 cpm Answer: A.008 d.

Reference:

§ 4.6, pp. 4-14 thru 4-17. For S/D reactor, = -80 seconds.

Time = 180 seconds. P = P0 et/ = 3 x 106 e-180/80 = 3.162x 105 Question A.009 [1.0 point] (9.0)

You're 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)

Answer: A.009 b.

Reference:

Section A - Reactor Theory, Thermo & Facility Operating Characteristics Page 9 of 28 Question A.010 [1.0 point] (10.0)

The reactor is operating with the Regulating Rod in Automatic mode. The Reactor Operator starts the secondary pump and both cooling tower fans. Average coolant temperature in the core decreases from 28ºC to 20ºC. Assume the Regulating Rod worth over the range of travel for this problem is 0.03%

K/K/inch, and average temperature coefficient over this temperature range is -0.88 x 10-4 K/K/ºC.

How far, and in which direction will the regulating rod move to maintain constant power?

a. 2.35 inches, inward

b. 2.35 inches, outward

c. 2.73 inches, inward

d. 2.73 inches, outward Answer: A.010 a.

Reference:

Reactivity due to temperature: -0.88 x 10-4 K/K/ºC x -8ºC = +7.04 x 10-4 K/K Movement: Rod must add -7.04 x 10-4 K/K, therefore (7.04 x 10-4 K/K) ÷ 0.0003 K/K = 2.346 inches in the negative (inward) direction.

Question A.011 [1.0 point] (11.0)

Which ONE of the following statements concerning reactor poisons is NOT true?

a. During reactor operation, Xenon concentration is dependent on reactor power level.

b. Following shutdown, Samarium concentration will increase to some value then stabilize.

c. During reactor operation, Samarium concentration is independent of reactor power level.

d. Following shutdown, Xenon concentration will initially increase to some value then decrease exponentially.

Answer: A.011 c.

Reference:

Question A.012 [1.0 point] (12.0)

In a reactor the thermal neutron flux () is 2.5 x 1012 fissions/cm2/second, and the macroscopic cross-section (f) for fission is 0.1 cm-1. The fission rate is

a. 2.5 x 1011 fissions/cm/second

b. 2.5 x 1013 fissions/cm/second

c. 2.5 x 1011 fissions/cm3/second

d. 2.5 x 1013 fissions/cm3/second Answer: A.012 c.

Reference:

Section A - Reactor Theory, Thermo & Facility Operating Characteristics Page 10 of 28 Question A.013 [1.0 point] (13.0)

From the data and the graph provided, calculate when criticality will be reached. After the loading of the

Count Rate No. of Fuel Bundles 842 2 936 4 1123 7 1684 12 2807 16

a. 20th bundle

b. 22nd bundle

c. 24th bundle

d. 26th bundle Answer: A.013 a. or b. (See attached sketch) accept either a. or b. per facility comment.

Reference:

The delayed neutron precursor () for U235 is 0.0065. However, when calculating reactor parameters you use eff with a value of ~0.0070. Why is eff larger than ?

a. The fuel also contains U238 which has a relatively large for fast fission.

b. U238 in the core becomes Pu239 (by neutron absorption), which has a higher for fission.

c. Delayed neutrons are born at higher energies than prompt neutrons resulting in a greater worth for the neutrons.

d. Delayed neutrons are born at lower energies than prompt neutrons resulting in less leakage during slowdown to thermal energies.

Answer: A.014 d.

Reference:

Section A - Reactor Theory, Thermo & Facility Operating Characteristics Page 11 of 28 Question A.015 [1.0 point] (15.0)

The Fast Fission Factor () is defined as The ratio of the number of neutrons produced by

a. fast fission to the number produced by thermal fission.

b. thermal fission to the number produced by fast fission.

c. fast and thermal fission to the number produced by thermal fission.

d. fast fission to the number produced by fast and thermal fission Answer: A.015 c.

Reference:

Which ONE of the following atoms will cause a neutron to lose the most energy in an elastic collision?

a. Uranium (U238)

b. Carbon (C12)

c. Deuterium (H2)

d. Hydrogen (H1)

Answer: A.016 d.

Reference:

Which one of the following is the primary reason a neutron source is installed in the core?

a. To allow for testing and irradiation of experiments when the reactor is shutdown.

b. To provide a neutron level high enough to be monitored for a controlled reactor startup.

c. To increase the excess reactivity of the reactor which reduces the frequency for refueling.

d. To supply the neutrons required to start the chain reaction for subsequent reactor startups.

Answer: A.017 b.

Reference:

Section A - Reactor Theory, Thermo & Facility Operating Characteristics Page 12 of 28 Question A.018 [1.0 point] (18.0)

Given the data in the table to the right, which ONE of the following is the closest to the half-life of the material?

TIME ACTIVITY 0 minutes 2400 cps 10 minutes 1757 cps 20 minutes 1286 cps 30 minutes 941 cps 60 minutes 369 cps

a. 11 minutes

b. 22 minutes

c. 44 minutes

d. 51 minutes Answer: A.018 b.

Reference:

Which ONE of the following is the definition of the term Cross-Section?

a. The area of the nucleus including the electron cloud.

b. The probability that a neutron will be captured by a nucleus.

c. The most likely energy at which a charge particle will be captured.

d. The length a charged particle travels past the nucleus before being captured.

Answer: A.19 b.

Reference:

The difference between a moderator and a reflector is that a reflector

a. increases the neutron production factor and a moderator increase the fast fission factor.

b. increases the fast non-leakage factor and a moderator increases the thermal utilization factor.

c. decreases the fast non-leakage factor, and a moderator increases the thermal utilization factor.

d. increases the neutron production factor, and a moderator decreases the thermal utilization factor.

Answer: A.020 b.

Reference:

Section B Normal, Emergency and Radiological Control Procedures Page 13 of 28 Question B.001 [1.00 point] (1.0)

You are operating the reactor in natural convection mode at 250 Kilowatts when you note pool temperature is 100ºF. Select the required operator action for the above condition.

a. Continue operations.

b. Shutdown the reactor.

c. Increase secondary cooling flow.

d. Reduce reactor power to 1.33 Kilowatts.

Answer: B.001 b.

Reference:

Tech. Specs 2.1.2 Question B.002 [1.00 point, 0.25 each] (2.0)

Identify each of the following as either a Safety Limit (SL), a Limiting Safety System Setting (LSSS) or as a Limiting Condition for Operations (LCO).

a. 1170 gpm Primary Flow

b. 24 feet of water above core centerline.

c. 110ºF Reactor Inlet Temperature (TP)

d. 1.25 Megawatts Answer: B.002 a. = LSSS; b. = SL; c. = SL; d. = LSSS;

Reference:

Technical Specifications §§ 2.1 and 2.2 Question B.003 [1.00 point] (3.0)

The containment ventilation system is not operating. The reactor may continue to operate if

a. Each ventilation valve is in its Technical Specification required position and the RSO approves.

b. Each ventilation valve is closed or has failed in the closed position.

c. The ventilation system is not required due to weather conditions.

d. No experiments are in progress.

Answer: B.003 a.

Reference:

R0-5, 8.0 Actions for Ventilation Shutdown

Section B Normal, Emergency and Radiological Control Procedures Page 14 of 28 Question B.004 [1.0 point, 0.25 each] (4.0)

Identify the correct number which correctly defines the maximum period between testing intervals per the Technical Specifications definitions.

a. Weekly: ___ days

b. Monthly: ___ weeks

c. Quarterly: ___ months

d. Annually: ___ months Answer: B.004 a. = 10; b. = 6; c. = 4; d. = 15

Reference:

TS 1.26 Question B.005 [1.00 point] (5.0)

What is the maximum Keff allowed (per Technical Specifications) for reactor fuel element storage under quiescent flooding with water.

a. 0.7

b. 0.75

c. 0.8

d. 0.85 Answer: B.005 d.

Reference:

Technical Specifications § 5.4, p. IV Question B.006 [1.00 point] (6.0) 60 The Co source is in use. RO-13, Radiation Monitoring Equipment Checkout, states that you shall not perform checks on channel Q (Gamma Cave) and channel

a. F (Facilities Filter)

b. G (Rabbit Filter)

c. H (Hot Cell)

d. O (Stairwell)

Answer: B.006 a.

Reference:

RO-13, § 13.1.b.2.

Section B Normal, Emergency and Radiological Control Procedures Page 15 of 28 Question B.007 [2.0 points, 0.4 each] (8.0)

As a licensed reactor operator you will be responsible for ensuring the correctness of Irradiation Request Forms (IRFs). To do this you must know your technical specification reactivity limits. Match the terms listed in column A with the respective reactivity limit from column B. (Note: There is only one answer for each item in column A. Items in column B may be used more than once or not at all.)

Column A Column B

a. reactivity insertion rates of the control rods < 1. 0.02% K/K

b. Single Moveable 2. 0.025%K/K

c. Total Moveable 3. 0.05%K/K

d. Single Secured 4. 0.1%K/K

e. Total Experiment Worth 5. 0.2%K/K

6. 0.25%K/K

7. 0.5%K/K

8. 2.0%K/K

9. 2.5%K/K Answer: B.007 a. = 2; b. = 4; c. = 7; d. = 7; e. = 9

Reference:

U. Mass-Lowell Technical Specifications § 3.1 Question B.008 [1.0 point] (9.0)

According to Technical Specifications an individual meets the definition of ON CALL if

a. is within the confines of the Pinanski building while the reactor is in operation.

b. keeps the operator posted of his/her whereabouts and telephone number.

c. is capable of arriving at the reactor facility within 30 minutes.

d. calls in to the operator at the controls every half hour.

Answer: B.008 a.

Reference:

AP-0, REACTOR OPERATIONS AUTHORITY #2 and Tech Spec 6.1.5

Section B Normal, Emergency and Radiological Control Procedures Page 16 of 28 Question B.009 [1.0 point] (10.0)

You are the console operator during insertion of a sample into and later removal of a sample from the core. Which ONE of the following items are you NOT required to log in the console operator's log?

a. Exposure

b. Time In/Out

c. Sample Number

d. Reactivity worth of sample Answer: B.009 a.

Reference:

U. Mass.-Lowell, RO-4 § 2.1.9 Question B.010 [1.0 point] (11.0)

You bring a radiation monitor into the pump room during reactor operation. If you were to open the window on the detector you would expect the meter reading to (Assume no piping leaks.)

a. remain the same, because the Quality Factors for gamma and beta radiation are the same.

b. increase, because you would now be receiving signal due to H3 and O16 betas.

c. increase, because the Quality Factor for betas is greater than for gammas.

d. remain the same, because you still would not be detecting beta radiation.

Answer: B.010 d.

Reference:

BASIC Radiological Concept (Betas don't make it through piping.)

Question B.011 [1.0 point] (12.0) 10CFR50.54(x) states: A licensee may take reasonable action that departs from a license condition or a technical specification (contained in a license issued under this part) in an emergency when this action is immediately needed to protect the public health and safety and no action consistent with license conditions and technical specifications that can provide adequate or equivalent protection is immediately apparent. 10CFR50.54(y) states that the minimum level of management which may authorize this action is

a. any Reactor Operator licensed at the facility.

b. any Senior Reactor Operator licensed at the facility.

c. Facility Manager (or equivalent at facility).

d. NRC Project Manager Answer: B.011 b.

Reference:

10CFR50.54(y).

Section B Normal, Emergency and Radiological Control Procedures Page 17 of 28 Question B.012 [1.0 point] (13.0)

Which ONE of the following correctly describes a Safety Limit?

a. Limits on important process variables which are found to be necessary to reasonably protect the integrity of certain physical barriers which guard against the uncontrolled release of radioactivity.

b. The Lowest functional capability of performance levels of equipment required for safe operation of the facility.

c. Settings for automatic protective devices related to those variables having significant safety functions.

d. A measuring or protective channel in the reactor safety system.

Answer: B.012 a.

Reference:

Standard NRC Question.

Question B.013 [1.0 point] (14.0)

During a normal reactor startup, the neutron source is normally removed at

a. 500 milliwatts

b. 5 watts

c. 50 watts

d. 500 watts Answer: B.013 d.

Reference:

RO-5 Routine Startup, § 4.1.4 Question B.014 [1.0 point] (15.0)

During a reactor start-up the console operator is withdrawing a control blade and notices that the position indicator for the control blade is not changing. Select the operator action for these conditions.

a. Attempt to insert the control blade whose position indicator was not changing during blade withdrawal.

b. Continue the reactor start-up. Level power at 1 watt and investigate the cause.

c. Run the other unstuck blades and the Regulating Rod fully in.

d. Verify that source range counts are not changing.

Answer: B.014 c.

Reference:

EO-7, "Stuck Rod or Safety Blade," step 1

Section B Normal, Emergency and Radiological Control Procedures Page 18 of 28 Question B.015 [1.0 point] (16.0)

When removing a sample from the pneumatic tube receiver, Health Physics coverage is required if the sample reads greater than

a. 0.001 Rem/hr.

b. 0.01 Rem/hr.

c. 0.1 Rem/hr.

d. 1 Rem/hr.

Answer: B.015 d.

Reference:

U. Mass.-Lowell, RO-4 § 1.4 Question B.016 [1.0 point] (17.0)

While working in a radiation area, you note that your pocket dosimeter reads off-scale and immediately leave the area. You had been working for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months at 8 feet from a source reading 2400 mr/hr at a foot.

Which one of the following is the estimated dose you received?

a. 600 mr

b. 300 mr

c. 75 mr

d. 371/2 mr Answer: B.016 c.

Reference:

D1d12 = D2d22 (D is Dose rate, d is distance) D1 (82) = 2400 (12)

D1 = 2400/64 = 371/2 mr/hr DOSE = Dose Rate x time 371/2 mr/hr x 2 hr = 75 mr Question B.017 [1.0 point] (18.0)

During an emergency responsibility for authorizing re-entry into the reactor building or portions thereof belongs to the

a. Console Operator

b. Senior Reactor Operator

c. Emergency Director

d. Radiation Safety Officer Answer: B.017 c.

Reference:

Emergency Plan § 3.4

Section B Normal, Emergency and Radiological Control Procedures Page 19 of 28 Question B.018 [1.0 point] (19.0)

Following work in a drained pool, whose permission (minimum) is required to use the primary system for refill?

a. None, this is the normal method for refill.

b. The Chief Reactor Operator.

c. The Reactor Supervisor.

d. The Reactor Director.

Answer: B.018 c.

Reference:

AP-0, GENERAL AUTHORITY, #4 Question B.019 [1.0 point, 0.25 each] (20.0)

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 Answer: B.019 a. = 6; b. = 2; c. = 2; d. = 1

Reference:

10CFR55.

Section B Normal, Emergency and Radiological Control Procedures Page 20 of 28 Question B.020 [2.0 point, 0.5 each] (22.0)

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.

Answer: B.020 a. = Test; b. = Check; c. = Cal; d. = Check

Reference:

Technical Specification 1.2.3-5.

Section C - Facility and Radiation Monitoring Systems Page 21 of 28 Question C.001 [1.0 point] (1.0)

You are operating the reactor power at 1 Megawatt. A severe storm warning has been announced by the National Weather Service. A loss of electrical power has occurred (the emergency generator has NOT started). Select the condition of the ventilation system.

a. The ventilation fans have stopped and the ventilation valves, except valve F, have closed.

b. The ventilation fans continue to run and the ventilation valves, except valve F, have closed.

c. The ventilation fans have stopped and valve F has closed, the other ventilation valves remain open.

d. The ventilation fans continue to run and valve F has closed, the other ventilation valves remain open.

Answer: C.001 a.

Reference:

SAR, Section 3.4.2.1, "System Closure," and 3.4.2.2, "Response to Initiation of System Closure."

Question C.002 [1.0 points, 0.25 each] (2.0)

Match the Radiation Detection Systems in Column A with its corresponding detector type from Column B.

Column A Column B

a. Continuous Air Monitors 1. Proportional Counter

b. Stack Effluent Monitor (Gaseous) 2. Geiger-Müeller

c. Stack Effluent Monitor (Particulate) 3. Scintillation

d. Bridge Area Radiation Monitor 4. Ion Chamber Answer: C.002 a. = 2; b. = 2; c. = 3; d. = 4

Reference:

NRC Exam OL-06-01 Retake Question administered September, 1996.

Question C.003 [1.0 point] (3.0)

The "TEST" position of the Master Switch allows:

a. control power and lamp indication operability testing.

b. control blade drive motion with energized scram magnets.

c. control blade drive motion without energizing the scram magnets.

d. insertion of scram signals without deenergizing the scram magnets.

Answer: C.003 c.

Reference:

U. Mass Lowell, FSAR Table 4.3.

Section C - Facility and Radiation Monitoring Systems Page 22 of 28 Question C.004 [1.0 point] (4.0)

Which ONE of the following poisons is used in all of the control elements?

a. Hafnium.

b. Stainless Steel.

c. Borated Graphite.

d. Boron-Aluminum Alloy (Boral)

Answer: C.004 d.

Reference:

FSAR Table 1-1 Question C.005 [1.0 point] (5.0)

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 Particulate Monitor.

c. Bridge Area Monitor.

d. Stack Gas Monitor.

Answer: C.005 a.

Reference:

Standard NRC Question.

Question C.006 [1.0 point] (6.0)

Which ONE of the following is NOT a Rod Withdrawal Interlock?

a. High flux - 110%

b. Short Period - 15 seconds

c. Low source count rate < 3 cps

d. Source Range Signal/noise ratio of 2 Answer: C.006 d.

Reference:

FSAR, 4.4 - CONTROL AND INSTRUMENTATION

Section C - Facility and Radiation Monitoring Systems Page 23 of 28 Question C.007 [1.0 point] (7.0)

Which ONE of the following safety system protective functions (Scrams) is NOT bypassed when the Power Level Selector Switch is in the 0.1 mW position?

a. High temperature Primary Coolant leaving core

b. Primary coolant low flow rate

c. Bridge Low Power Position

d. Low Pool Water Level Answer: C.007 d.

Reference:

U. Mass Lowell Technical Specifications § 3.3.

Question C.008 [1.0 point] (8.0)

Which ONE of the following methods is used to determine if there is a leak in the heat exchanger?

a. Routine checks of the secondary coolant for O19.

b. Routine checks of the secondary coolant for Na24.

c. Pool level will decrease due to leakage into the secondary.

d. Decrease in secondary makeup, due to water from primary.

Answer: C.008 b.

Reference:

{Study Guide for Key Access and Introduction to Operator Training Secondary Cooling System ¶ 8.???}

Question C.009 [1.0 point] (9.0)

Which ONE of the following is the actual design feature which prevents siphoning of pool water on a failure of the primary/purification system?

a. All primary system pipes end three feet below the water surface.

b. The suction and return line each contain a siphon break valve and stand-pipe.

c. 1/2 inch holes are located in each water pipe about a foot below the water surface.

d. The suction and return line each contain a valve which will inject service air into the loop.

Answer: C.009 b.

Reference:

SAR § 4.2.2 Primary Coolant System, 5th ¶.

Section C - Facility and Radiation Monitoring Systems Page 24 of 28 Question C.010 [1.0 point] (10.0)

Which ONE of the following contaminants is the Demineralizer most efficient at removing from pool water?

a. oil

b. Ar41

c. I135

d. mosquito larvae Answer: C.010 c.

Reference:

SAR § 4.2.5 Question C.011 [1.0 point] (11.0)

Reactor power is 300 Kilowatts when the console operator selects "Rundown" on the console.

Reactor power will:

a. decrease because the regulating blade is inserted into the core.

b. decrease because all four control blades are inserted into the core.

c. decrease because the regulating blade is inserted to the 50% withdrawn position.

d. decrease because all four control blades are inserted to the 50% withdrawn position.

Answer: C.011 b.

Reference:

FSAR, Table 4.2 Question C.012 [1.0 point] (12.0)

Which of the following describes how the cleanup system functions to minimize corrosion of the reactor components? The cleanup system:

a. maintains the coolant pH at a basic value.

b. maintains the coolant pH at a acidic value.

c. filters suspended particles from the coolant.

d. maintains primary coolant at a low conductivity.

Answer: C.012 d.

Reference:

Technical Specifications, 3.8, Coolant System, and SAR, ¶ 4.2.5, Cleanup System.

Section C - Facility and Radiation Monitoring Systems Page 25 of 28 Question C.013 [1.0 point] (13.0)

Given the following conditions:

- Reactor power is 250 Kilowatts.

- Stack ventilation radiation monitor (gaseous/particulate) has indicated increasing counts over the past hour.

- A small leak has developed in the pneumatic tube.

Select a method to determine the LOCATION of the problem.

a. Operate the ventilation system in the manual mode.

b. Shutdown the reactor and take a pool area air sample.

c. Use a portable air monitor taking suction from the stack.

d. Place a portable monitor in the area of the ventilation monitor.

Answer: C.013 a.

Reference:

FSAR, ¶ 3.3.2, Facilities Exhaust, & 3.4.1, Normal Operation.

Question C.014 [1.0 point] (14.0)

During reactor operation, the console operator has noticed the pool temperature channel failed low (on the low end scale peg). Select the cause for this reading.

a. The thermocouple has shorted.

b. The thermocouple has opened.

c. The RTD has shorted.

d. The RTD has opened.

Answer: C.014 c.

Reference:

FSAR, Paragraph 4.4.17.5

Section C - Facility and Radiation Monitoring Systems Page 26 of 28 Question C.015 [1.0 point] (15.0)

Given the following conditions:

- Reactor power is 250 Kilowatts and increasing.

- Core inlet temperature is 104ºF.

- Coolant flow is 1400 gpm.

- Reactor period is 15 seconds.

The Reactor scrams. Select the cause for the reactor scram.

a. High reactor flux

b. High core inlet temperature

c. Low coolant flow

d. Short period Answer: C.015 b.

Reference:

FSAR Table 4.4 Question C.016 [1.0 point] (16.0)

Given the following conditions:

- There is NO blade position indication.

- NO annunciators are in alarm.

- The picoammeters are in the tripped state.

- The scram magnets are de-energized.

Select the cause for the above conditions. A loss of the:

a. emergency generator

b. high voltage dc power supplies

c. unregulated control power supply

d. regulated instrumentation power supply Answer: C.016 c.

Reference:

FSAR, Paragraphs 4.4.5, 4.4.6, and 4.4.7, (Power Supplies)

Section C - Facility and Radiation Monitoring Systems Page 27 of 28 Question C.017 [1.0 point] (17.0)

The "Rabbit" is inserted and withdrawn from the core using:

a. two exhausters.

b. a length of cable wire.

c. a blower and exhauster.

d. an exhauster and a wind gate cabinet.

Answer: C.017 d.

Reference:

FSAR, Paragraph 4.3.3.2 & 4.3.3.3, "Pneumatic Tube System." ¶ Question C.018 [1.0 point] (18.0)

The reactor is operating at 100 kilowatts steady state power, when one of the beam tubes develops a small leak. Select the indication which alerts the console operator to the beam tube leak.

a. The stack monitor

b. Bubbling in the pool

c. The water line in the beam tube

d. The conduit lines connected to the beam tube Answer: C.018 a.

Reference:

FSAR, Paragraph 4.3.2, "Beam Ports."

Question C.019 [1.0 point] (19.0)

You are operating the reactor at 1 Megawatt. Personnel are performing maintenance on the airlock doors and the truck door when a reactor scram occurs. Select the cause for the reactor scram.

a. The outer airlock door was opened and the inner airlock door was shut.

b. The outer airlock door was shut and the inner airlock door was open.

c. The outer airlock door has lost its pneumatic seal.

d. The truck door has lost its pneumatic seal.

Answer: C.019 d.

Reference:

FSAR, Section 3.1.2.1, last paragraph.

Section C - Facility and Radiation Monitoring Systems Page 28 of 28 Question C.020 [1.0 point] (20.0)

Which ONE of the following conditions will result in a control blade withdrawal inhibit?

a. Positive 20 second Log N period.

b. Movement of the startup detector.

c. Startup detector indication of 5 CPS.

d. Picoammeter range switch in the most sensitive position.

Answer: C.020 b.

Reference:

ML102420012

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