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Initial Examination Report No. 50-223/OL-05-01 University of Massachusetts - Lowell
	ML052930390
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Site:	University of Lowell
Issue date:	11/23/2005
From:	Bernard Thomas; NRC/NRR/ADRA/DPR
To:	Kegel G; Univ of Massachusetts - Lowell
	Doyle P, NRC/NRR/DPR/PRT, 415-1058
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November 23, 2005 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-05-01, UNIVERSITY OF MASSACHUSETTS - LOWELL

Dear Dr. Kegel:

During the week of September 5, 2005, the NRC administered an operator licensing examination at your University of Massachusetts - Lowell Reactor. The examination was conducted according to NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with 10 CFR 2.390 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/

Brian E. Thomas, Branch Chief Research and Test Reactors Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-223

Enclosures:

1. Initial Examination Report No. 50-223/OL-05-01

2. Examination with Facility Comments Incorporated cc w/encls: Please see next page

November 23, 2005 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-05-01, UNIVERSITY OF MASSACHUSETTS - LOWELL

Dear Dr. Kegel:

During the week of September 5, 2005, the NRC administered an operator licensing examination at your University of Massachusetts - Lowell Reactor. The examination was conducted according to NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with 10 CFR 2.390 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/

Brian E. Thomas, Branch Chief Research and Test Reactors Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-223

Enclosures:

1. Initial Examination Report No. 50-223/OL-05-01

2. Examination with Facility Comments Incorporated cc w/encls: Please see next page DISTRIBUTION w/ encls.:

PUBLIC DPR/PRT r/f BThomas MMendonca Facility File (EBarnhill) O-6 F-2 EXAMINIATION PACKAGE # : ML051810517 ADAMS ACCESSION #: ML052930390 TEMPLATE #:NRR-074 OFFICE PRT:CE IOLB:LA E PRT:SC NAME PDoyle EBarnhill BThomas DATE 11 /4/2005 11/10/2005 11/17/2005 C = COVER E = COVER & ENCLOSURE N = NO COPY 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 Office of the Attorney General Environmental Protection Division 19th Floor One Ashburton Place Boston, MA 02108 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.: 50-223/OL-05-01 FACILITY DOCKET NO.: 50-223 FACILITY LICENSE NO.: R-125 FACILITY: University of Massachusetts - Lowell EXAMINATION DATES: September 6, 2005 SUBMITTED BY: _________/RA/__________________ 10/5/2005 Paul V. Doyle Jr., Chief Examiner Date

SUMMARY

During the week of September 6, 2005, the NRC administered operator licensing examinations to two Reactor Operator candidates. One RO passed the examination, the other RO failed sections A and C of the written examination.

REPORT DETAILS

1. Examiners:

Paul V. Doyle Jr., Chief Examiner

2. Results:

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

3. Exit Meeting:

Paul V. Doyle Jr., NRC, Examiner Toungporn Angwongtrakool, Thailand, Office of Atoms for Peace Leo Bobek, Reactor Manager, University of Massachusetts-Lowell Reactor The examiner thanked Mr. Bobek for his support of the examination and for his work in allowing Ms. Angwongrakool to visit his facility. The examiner did not note any generic weaknesses on the part of the license candidates. Mr. Bobeks comments on the written examination have been incorporated into the examination attached to this report.

B2(d): Because (d) reads 520mRem as opposed to >500Rad, the correct answer would be (1).

B.11: Either (a) (see UML TS 3.6.8) or the given answer (d) are correct.

B.14: The correct answer is (d) (see UML TS 5.4)

C.1: No answer change, though I believe (b) should replace the words High Radiation with High Temperature C.5: The correct answer is (c). Answer (d) would be correct if the words

"...inner airlock door is..." were placed between the last two words of answer (d).

ENCLOSURE 1

OPERATOR LICENSING EXAMINATION With Answer Key UNIVERSITY OF MASSACHUSETTS-LOWELL September 6, 2005 ENCLOSURE 2

Section A L Theory, Thermo & Fac. Operating Characteristics Page 7 QUESTION A.01 [1.0 point]

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

a. 20th bundle Count Rate No. of Fuel nd

b. 22 bundle Bundles 842 2

c. 24th bundle 936 4

d. 26th bundle 1123 7 1684 12 2807 16 QUESTION A.02 [1.0 point]

The two figures below represent the order (number in box) and direction used in placing fuel into a reactor pool. Which of the following choices shows the preferred method for performing a 1/M plot, along with the correct reason.

Figure 1 Figure 2

a. Figure 1 because loading from the detector towards the source gives the first fuel element more emphasis resulting in a more conservative estimate of criticality.

b. Figure 2 because loading towards the detector and the source gives the first fuel element more emphasis resulting in a more conservative estimate of criticality.

c. Figure 1 because loading from the detector towards the source gives the last fuel element more emphasis resulting in a more conservative estimate of criticality.

d. Figure 2 because loading towards the detector and the source gives the last fuel element more emphasis resulting in a more conservative estimate of criticality.

QUESTION A.03 [2.0 points, 1/2 each]

Using the drawing of the Integral Rod Worth Curve provided, identify each of the following reactivity worths.

a. Total Rod Worth 1. B - A

b. Actual Shutdown Margin 2. C - A

c. Technical Specification Shutdown Margin Limit 3. C - B

d. Excess Reactivity 4. D - C

5. E - C

6. E - D

7. E - A

Section A L Theory, Thermo & Fac. Operating Characteristics Page 8 QUESTION A.04 [1.0 point]

As primary coolant (moderator) temperature increases, control rod worth

a. decreases due to lower reflector efficiency.

b. decreases due to higher neutron absorption in the moderator.

c. increases due to the increase in thermal diffusion length.

d. remains the same due to constant poison cross-section of the control rods.

QUESTION A.05 [1.0 point]

The Chief Reactor Operator tells you that the reactor is shutdown with a Shutdown Margin of 12.0%. Nuclear Instrumentation reads 100 cpm. The CRO inserts an experiment into the core and counts increase to 200 cpm. What is the resulting Keff for the core?

a. 0.920

b. 0.946

c. 0.973

d. 1.000 QUESTION A.06 [1.0 point]

Which ONE of the following is the cause of the indicated power to stabilize several hours following a reactor scram.

(Assume source inserted in core, source range instrument on and reading 3 counts/second and no reactivity changes, i.e. no temperature changes, no fuel movement, no experiments added, etc.)

a. Continuing decay of the shortest lived delayed neutron precursor.

b. Gamma saturation of the source range detector.

c. Subcritical multiplication of source neutrons.

d. Neutron activation of the Source Range Detector.

QUESTION A.07 [1.0 point]

During a startup you increase reactor power from 50 watts to 1000 watts in 100 seconds. What is reactor period?

a. 25

b. 33

c. 41

d. 50

Section A L Theory, Thermo & Fac. Operating Characteristics Page 9 QUESTION A.08 [1.0 point]

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 28EC to 20EC. Assume 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/EC. 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 QUESTION A.09 [1.0 point]

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

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

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

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

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

QUESTION A.10 [1.0 point]

An experimenter makes an error loading a rabbit sample. Injecting the sample into the core results in a 100 millisecond period. If the first scram trip setpoint (actual) is 125%, and the scram delay time is 0.1 seconds, which ONE of the following is the resulting peak reactor power before the reactor shuts down?

a. 1.4 Megawatts

b. 2.8 Megawatts

c. 3.4 Megawatts

d. 5.0 Megawatts QUESTION A.11 [1.0 point]

In a reactor the thermal neutron flux (Ø) 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

Section A L Theory, Thermo & Fac. Operating Characteristics Page 10 QUESTION A.12 [1.0 point]

Given: Primary Flow rate through heat exchanger = 1400 GPM; Secondary Flow rate through heat exchanger = 1200 GPM; TPrimary = 13EF and Secondary INLET temperature is 73EF. Which one of the following should be the secondary OUTLET temperature?

a. . 58EF

b. . 62EF

c. . 84EF

d. . 88EF QUESTION A.13 [1.0 point]

Which ONE of the following parameters is MOST significant in determining the differential worth of a control rod?

a. Rod Speed

b. Reactor Power

c. Flux Shape

d. Fuel Loading QUESTION A.14 [1.0 point]

A fissile material is one which will fission upon absorption of a THERMAL neutron. A fertile material is one which upon absorption of a neutron becomes a fissile material. Which ONE of the following isotopes is an example of a fertile material.

a. U233

b. U235

c. U238

d. Pu239 QUESTION A.15 [1.0 point]

Which one of the graphs supplied in figure A.1, most closely depicts the reactivity versus time plot for xenon for the following set of evolutions? TIME Evolution 1 Startup to 100% power, clean core 2 100% operation for four days 3 Shutdown for 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months 4 50% operation for 29 hours3.356481e-4 days 0.00806 hours 4.794974e-5 weeks 1.10345e-5 months

a. a

b. b

c. c

d. d

Section A L Theory, Thermo & Fac. Operating Characteristics Page 11 QUESTION A.16 [1.0 point]

Five minutes after shutting down the reactor, reactor 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 QUESTION A.17 [1.0 point]

Excess reactivity is the amount of reactivity

a. associated with burnable poisons

b. needed to achieve prompt criticality

c. available below that which is required to make the reactor subcritical.

d. available above that which is required to keep the reactor critical.

QUESTION A.18 [1.0 point]

Which ONE of the following describes the MAXIMUM amount of Xenon in the core?

a. 4 to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following Power Increase, 50% to 100%.

b. 4 to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following Power Decrease, 100% to 50%.

c. 8 to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months following Power startup to 100%.

d. 8 to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months following Power shutdown from 100%.

QUESTION A.19 [1.0 point]

The listed isotopes are all potential daughter products due to the radioactive decay of 35Br87. Identify the type of decay necessary (Alpha, Beta, Gamma or Neutron emission) to produce each of the isotopes.

a. 33 As83

b. 35 Br86

c. 35 Br87

d. 36 Kr87

(*** END OF SECTION A ***)

Section B Normal, Emergency and Radiological Control Procedures Page 12 QUESTION B.1 [1.0 point]

According to the Emergency plan, the Emergency Planning Zone

a. is the area enclosed within the containment vessel.

b. specifies contamination levels (airborne, radiation dose, or dose rates) that may be used as thresholds for establishing emergency classes.

c. is the geographical area beyond the site boundary, where the Reactor Director has direct authority over all activities.

d. lies within the site boundary and is bounded by a 150 meter radius from the exhaust stack.

QUESTION B.2 [2.0 points, 0.5 each]

Match the general area radiation levels listed in column A with the corresponding type of radiation area listed in column B. (Note: Only one answer for each item in column A. Items from column B may be used more than once or not at all.)

Column A Column B

a. 15 mRem/hr. 1. High Radiation Area

b. 65 mRem/hr. 2. Radiation Area

c. 203 mRem/hr. 3. Unrestricted Area

d. 520 mRem/hr. 4. Very High Radiation Area QUESTION B.3 [1.0 point]

10CFR50.54(x) states: A licensee may take reasonable action that departs from a license condition or a technical specification (contained in a license issued under this part) in an emergency when this action is immediately needed to protect the public health and safety and no action consistent with license conditions and technical specifications that can provide adequate or equivalent protection is immediately apparent. 10CFR50.54(y) 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 QUESTION B.4 [1.0 point]

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.

Section B Normal, Emergency and Radiological Control Procedures Page 13 QUESTION B.5 [1.0 point]

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.

QUESTION B.6 [1.0 point]

So far this calendar year, you have received 3.3 Rem whole body dose. You must work on a control drive mechanism where there is an average dose of 250 mR/hr. Which ONE of the following times is closest to your stay time WITHOUT going over? (Assume you are over the age of 18.)

a. 31/4 hours.

b. 61/2 hours.

c. 123/4 hours.

d. 19 hours2.199074e-4 days 0.00528 hours 3.141534e-5 weeks 7.2295e-6 months .

QUESTION B.7 [1.0 point]

An experimenter wishes to irradiate three specimens with reactivity worths of 0.15% k/k, 0.17% k/k and 0.3% k/k.

Can these specimens be placed in the reactor as SECURED experiments and why (why not).

a. Yes, the sum of the three specimens is less than 2.5% k/k.

b. No, the sum of the three specimens is greater than 0.5% k/k.

c. No, each of the experiments is greater than 0.1% k/k.

d. No, one of the specimens is greater than 0.25% k/k.

QUESTION B.8 [2.0 points, 1/2 each]

Identify the modes [Forced Convection (above 0.1 Mw) (FC), Natural Convection (NC), Cross-Pool flow pattern (CP) or Down-Comer flow pattern (DC), or all modes (ALL)] for which each of the following scrams is required to be operational.

(Modes may be used more than once or not at all.)

a. Pool level 2'3" above centerline of core.

b. Either Coolant Riser Gate or Downcomer Gate opens

c. Coolant Inlet Temperature 108EF

d. Manual Scram button

Section B Normal, Emergency and Radiological Control Procedures Page 14 QUESTION B.9 [1.0 point]

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

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

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

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

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

QUESTION B.10 [1.0 point]

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. Sample Number

b. Time In/Out

c. Exposure

d. Total Reactivity worth of all incore samples QUESTION B.11 [1.0 point]

Which ONE of the following conditions regarding experiments is not allowed under ANY condition? The experiment

a. contains cryogenic liquids.

b. contains 2.1 milligrams of explosive material

c. causes a reduction in the reading for the startup channel.

d. causes the outside temperature of a submerged material to reach 90EC (176EF)

QUESTION B.12 [1.0 point]

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

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

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.

Section B Normal, Emergency and Radiological Control Procedures Page 15 QUESTION B.13 [1.0 point]

According to the Safety Analysis Report (SAR), which ONE of the following locations has the potential of generating the greatest amount of Ar41?

a. Thermal Column Case Vent

b. Beam Port

c. Pneumatic Tube

d. Primary Coolant (Pool)

QUESTION B.14 [1.0 point]

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 QUESTION B.15 [1.0 point]

The Co60 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)

QUESTION B.16 [1.0 point]

All of the monitors checked by RO-13 are checked using a Co60 source, except one which uses a Cf 252 neutron emitting source. The channel which uses the Cf 252 source is channel

a. C (Continuous Air Monitor #1)

b. E (Fission Product Monitor)

c. I (Plenum)

d. L (Thermal Column)

Section B Normal, Emergency and Radiological Control Procedures Page 16 QUESTION B.17 [1.0 point]

When taking logs readings, you must inform the Chief Reactor Operator when you notice a discrepancy between power channels greater than

a. 2%

b. 3%

c. 4%

d. 5%

Section C Facility and Radiation Monitoring Systems Page 17 QUESTION C.1 [2.0 points, 1/2 each]

Match the purification system conditions listed in column A with their respective causes listed in column B. Each choice is used only once.

Column A Column B

a. High Radiation Level at Demineralizer. 1. Channeling in Demineralizer.

b. High Radiation Level downstream of Demineralizer. 2. Fuel element failure.

c. High flow rate through Demineralizer. 3. High temperature in Demineralizer system.

d. High pressure upstream of Demineralizer. 4. Clogged Demineralizer.

QUESTION C.2 [1.0 point]

The baffles in the holdup tank are designed to allow which two isotopes time to decay?

a. 1 H3 and 6C14

b. 1 H3 and 7N16

c. 6 C14 and 8O19

d. 7 N16 and 8O19 QUESTION C.3 [1.0 point]

Which ONE of the following is the type of startup neutron source use for your reactor?

a. Californium

b. Plutonium-Beryllium

c. Neptunium-Antimony

d. Americium-Beryllium QUESTION C.4 [1.0 point]

Which ONE of the following communications systems allows all stations to talk to each other simultaneously?

a. main intercom system

b. phone system

c. sound powered headset system

d. public address system

Section C Facility and Radiation Monitoring Systems Page 18 QUESTION C.5 [1.0 point]

Which ONE of the following conditions would cause the reactor to scram?

a. The outer airlock door lost its pneumatic seal.

b. The inner airlock door lost its pneumatic seal.

c. The truck door lost its pneumatic seal.

d. The outer airlock door lost its pneumatic seal while open.

QUESTION C.6 [1.0 point]

A severe storm causes a loss of power while you were maintaining the reactor at 1 megawatt. The emergency generator did NOT start. Select the condition of the ventilation system. The ventilation fans

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

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

c. have stopped and the ventilation valves, except valve F remain open.

d. continue to run and the ventilation valves, except valve F remain open.

QUESTION C.7 [1.0 point]

You are instructed to place the core in the #1 position, and align the primary system for minimum flow induced vibration.

Identify the position of the core and the primary flow mode.

Core Position Flow Mode

a. Bulk Pool Downcomer

b. Stall Pool Cross-Stall

c. Bulk Pool Cross-Stall

d. Stall Pool Downcomer QUESTION C.8 [1.0 point]

During shutdown, the source range indication does NOT come on-scale until AFTER the intermediate range instrumentation went off-scale low. Which ONE of the following could be the reason for the lack of overlap?

a. Source range high voltage was lost.

b. Source range high voltage was set too high.

c. Intermediate range compensating voltage was set too low.

d. Intermediate range compensating voltage was set too high.

Section C Facility and Radiation Monitoring Systems Page 19 QUESTION C.9 [2.0 points, 0.4 each]

Identify the NEAREST upstream power distribution panel (panels listed in column B), for each of hte electrical loads listed in column A. (NOTE: Responses may be used more than once or not at all.)

a. Reactor Compressors 1. ELPL-R1

b. Sump Pump 2. Motor Control Center #1

c. Emergency Exhaust Fan 3. Motor Control Center #2

d. Main Exhaust Fan 4. PPL-R1

e. Primary Pump 5. Emergency Distribution Switchboard QUESTION C.10 [1.0 point]

The purpose of the Thermal Column is to

a. enhance heat transfer characteristics of the core.

b. provide a thermal temperature rise for experiments.

c. enhance forced convection flow.

d. provide neutrons in the thermal energy range.

QUESTION C.11 [2.0 points, 0.25 each]

The liquid radwaste system divides cooling water into four sections for the purpose of performance checks/monitoring.

Match the cooling water sections in Column A with its appropriate performance checks from Column B. Note that some performance checks in Column B may be used more than once or not at all.

Column A Column B

a. Pool 1. External gamma monitor and delayed neutron detector.

b. Primary Loop 2. Continuous conductivity measurements.

c. Cleanup Loop 3. Periodic sampling for quality and presence of radionuclides.

d. Secondary Loop 4. Daily sampling for Na24.

QUESTION C.12 [1.0 point]

Which ONE of the following devices is designed to prevent the reactor pool from being completely drained by a leak in the primary coolant piping?

a. Primary Delay Tank

b. Pool Wall Liner

c. Primary Coolant Pump

d. Break Valve

Section C Facility and Radiation Monitoring Systems Page 20 QUESTION C.13 [1.0 point]

Which ONE of the following correctly describes how a compensated ion chamber detects neutrons. A neutron interacts with the

a. U235 lining of the tube.

b. B10 lining of the tube.

c. BF3 gas which fills the tube

d. N2 gas which fills the tube.

QUESTION C.14 [1.0 point]

Which ONE of the following is used when the reactor is operating to reduce the buildup of Ar41 in the reactor bay?

a. Operation of the ventilation system, which releases the Ar41 through the stack.

b. Diffuser pumps which decrease the release of Ar41 from the pool.

c. Purification system via the ion bed.

d. None required due to the relatively short half-life of Ar41 (seven seconds).

QUESTION C.15 [1.0 point]

Which ONE of the following correctly describes the manual operation of Valve A in the ventilation system? The valve is opened

a. by air acting on a piston against a spring. The valve is closed by opening a quick release valve which bleeds off air from the piston.

b. by air acting on a piston against a spring. The valve is closed by opening a quick release avle which bleeds air off of an auxiliary piston which in turn opens a port bleeding air off the main piston.

c. by spring pressure. The valve is closed by an explosive blast of high pressure air from an accumulator.

d. and closed via an air motor, using higher pressure air from an accumulator for quick closure.

QUESTION C.16 [1.0 point]

Which ONE of the following correctly describes the operation of the RTD (temperature detector used for the temperature recorder).

a. A bimetallic strip which because of differing thermal expansion coefficients causes the strip to bend proportional to temperature.

b. A bimetallic junction, which generates a potential (micro-volt range) proportional to temperature.

c. A precision wound resistor, which changes resistance proportional to temperature.

d. A precision wound inductor, which changes inductance proportional to temperature.

Section C Facility and Radiation Monitoring Systems Page 21 QUESTION C.17 [1.0 point]

Which ONE of the following describes the purpose of the filter in the reactor pool cleanup system?

a. Prevents demineralizer resin fines from entering the pool.

b. Prevents larger particles from plugging the demineralizer resin.

c. Removes CRUD from the coolant limiting the radiation levels associated with the demineralizer.

d. Removes particulates that could clog the cleanup system pump seals.

Section A L Theory, Thermo & Fac. Operating Characteristics Page 22 A.1 b (See attached sketch)

A.3 a, 7; b, 5; c, 6; d, 2 REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1988, § 6.2.1, p. 6-3 A.4 c REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1988, § 7.2, p. 7-1-7-9.

A.5 b REF: Keff(I) = 1/(1+SDM) = 1/1.120 = 0.892857 CR(I)[1 - Keff(I)] = CR(f)[1 - Keff(f)] 100(1 - 0.893) = 200 (1 - x) 1/2(1 -

0.893)= 1 - x 1 - x = 0.0535714; x = 1 - 0.0535714 = 0.94643 A.6 c REF: Burn, R. R., Introduction or Nuclear Reactor Operations, June 1984, § 5.3 A.7 b REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1988, § 4.3, p. 4-4. P = P0 et/ ln(P/P0) = t/ =

Reactivity due to temperature: -0.88 x 10-4 K/K/EC x -8EC = +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.

A.12 REF:

d Tsec = 1400/1200

13EF = 7/6

13 mpricp Tpri ' mseccp Tsec

= 15.2EF TOUT = 73 + 15.2 = 88.2 A.13 c REF: Burn, R. R., Introduction or Nuclear Reactor Operations, June 1984, § 7.2, p. 7-4.

A.16 d REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1988, § 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 A.17 d REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1988, § 6.2.2. p. 6-6.

Section A L Theory, Thermo & Fac. Operating Characteristics Page 23 A.18 d REF: Burn, R. R., Introduction or Nuclear Reactor Operations, June 1984, § 8.4, pp. 8-12 to 8-19.

A.19 a, alpha; b, neutron; c, gamma; d, Beta Ref: Standard NRC Question

Section B Normal, Emergency and Radiological Control Procedures Page 24 B.1 a REF: Emergency Plan Chapter 2.0, Definitions, § 2.11.

B.2 a, 2; b, 2; c, 1; d, 4 1 answer changed per facility comment. (Typo in question)

REF: 10 CFR20 Definitions B.3 b REF: 10CFR50.54(y).

B.4 d REF: U. Mass.-Lowell, RO-4 § 4.1.7, p. 4-2.

B.5 a REF: Standard NRC Question.

B.6 b 5.0 - 3.3 = 1.7 Rem allowable. 1.7 Rem ÷ 0.25 Rem/hr = 6.8 . 61/2 REF: 10CFR20.1201 B.7 a REF: Technical Specifications 3.1. Specification 9.

B.8 a, NC; b, DC; c, FC; ALL REF: T.S. § 3.3, table B.9 b REF: Technical Specifications 6.1.5 page 42.

B.10 c REF: NRC examination 01/27/87 and RO B.11 c REF: T.S. § 3.6, specifications 3, 5, 7 and 8.

B.12 d REF: BASIC Radiological Concept (Betas don't make it through piping.)

B.13 b REF: SAR pp. 3-18 and 7-2.

B.14 c d answer changed per facility comment (typo).

REF: Technical Specifications § 5.4, p. IV B.15 a REF: RO-13, § 13.1.b.2.

B.16 b REF: RO-13 § 13.1.a.

B.17 b REF: Standing Order #4, Sequence of Operations during Startup and at Rated Power.

Section C Facility and Radiation Monitoring Systems Page 25 C.1 a, 2; b, 3; c, 1; d, 4 REF: Standard NRC question C.2 d REF: Study Guide for Key Access and Intro. To Operator Training, § covering primary system and NRC exam administered September, 1997.

C.3 d REF: SAR § 4.1.4, page 4-6 C.4 c REF: UMLR Safety Analysis Report, § 6.3.1, Communications System C.5 d c answer changed per facility comment (typo)

REF: SAR, § 3.1.2.1, last ¶.

C.6 a REF: SAR § 3.4.2.1, System Closure and § 3.4.2.2 Response to Initiation of System Closure.

C.7 b REF: SAR § 4.1.10 Reactor Pool C.8 b REF: Standard NRC question C.9 a, 5; b, 3; c, 1; d, 3; e, 2 REF: SAR Figures 5.2 and 5.3.

C.10 d REF: SAR § 4.3.1, Thermal Column C.11 a, 3; b, 1; c, 2; d, 4 REF: SAR § 7.2.4, Page 7-5 C.12 d REF: Modified question from NRC examination bank.

C.13 b REF: Standard NRC Question C.14 a REF: SAR § C.15 b REF: SAR figure 3.7, page 3-16 C.16 c REF: SAR § 4.4.17.5 C.17 a REF: SAR § 4.2.5, page 4-29

1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0

1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 2 Bundles: 842 ÷ 842 = 1.0 4 Bundles: 842 ÷ 936 = 0.9 7 Bundles: 842 ÷ 1123 = 0.75 12 Bundles: 842 ÷ 1684 = 0.50 16 Bundles: 842 ÷ 2807 = 0.3

All work done on this examination is my own. I have neither examination.

for Answers each given INSTRUCTIONS question received Examinations arenor to are be writtenaid.

indicated TOwill CANDIDATE:

on bein the picked brackets answer up three for sheet each (3) provided.

question hours af 60.00 20.00 20.00 20.00 Category Value 33.3 33.3 33.3 Total CANDIDATE: ADMINISTERED:

DATEREACTOR FACILITY:

TYPE:

% of Candidates Score

% of NON-POWER INITIAL RE FINAL GRADE ValueCategory U. S. NUCLEAR REGU University of Massachus 2003/06/16 GE Pool

______________________________________ C. B. A. Category Candidate's Signature TOTALS Characteristics Radiological Controls FacilityNormal Reactor and Radiation Theory, Thermodynamics and Emergency Monitoring Operating SystemsProcedures and Facility and Oper

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.

EQUATION SHEET 44444444444444444444444444444444444444444444444444444444444444444444444 Q'mcp T'mH'UAT Pmax'( &)2 R('1x10 &4 seco 2(k)R eff'0.1second &1 SCR '&S.1&S Ke CR1(1&Keff 1

)'CR 2(1&Keff

)

2 CR 1(&1)'CR 2(&2)

SUR '26 .06eff M'1 &Keff0 M'1&1K 'CR 1 1&Keff1 eff CR 2 P'P0 10 SUR(t) t P'(1 &) P0 P'P0 e SDM '(1& Keff) ' R( 'R( % &

Keff &

eff

'K 2&K eff k xK eff1 T1/2'0.693 '(KK &1) eff eff 1 eff 2 eff DR 'DR 0e

&t DR '6Ci R2 E(n) DR1d1 'DR 2

2d2 2

DR - Rem, Ci - curies, E - Mev, R - feet (2&)2 '(1&)2 Peak 2 Peak 1 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lbm 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 1 BTU = 778 ft-lbf EF = 9/5 EC + 32 1 gal (H2O) . 8 lbm EC = 5/9 (EF - 32) cP = 1.0 BTU/hr/lbm/EF cp = 1 cal/sec/gm/EC

Section A.01 a b c d ___ A.10 a b c d ___

A.02 a b c d ___ A.11 a b c d ___

A.03a 1 2 3 4 5 6 7 ___ A.12 a b c d ___

A.03b 1 2 3 4 5 6 7 ___ A.13 a b c d ___

A.03c 1 2 3 4 5 6 7 ___ A.14 a b c d ___

A.03d 1 2 3 4 5 6 7 ___ A.15 a b c d ___

A.04 a b c d ___ A.16 a b c d ___

A.05 a b c d ___ A.17 a b c d ___

A.06 a b c d ___ A.18 a b c d ___

A.07 a b c d ___ A.19a n ___

A.08 a b c d ___ A.19b n ___

A.09 a b c d ___ A.19c n ___

A.19d n ___

Section B.01 a b c d ___ B.08c FC NC CP DC ALL B.02a 1 2 3 4 ___ B.08d FC NC CP DC ALL B.02b 1 2 3 4 ___ B.09 a b c d ___

B.02c 1 2 3 4 ___ B.10 a b c d ___

B.02d 1 2 3 4 ___ B.11 a b c d ___

B.03 a b c d ___ B.12 a b c d ___

B.04 a b c d ___ B.13 a b c d ___

B.05 a b c d ___ B.14 a b c d ___

B.06 a b c d ___ B.15 a b c d ___

B.07 a b c d ___ B.16 a b c d ___

B.08a FC NC CP DC ALL ___ B.17 a b c d ___

B.08b FC NC CP DC ALL ___

Section C.01a 1 2 3 4 ___ C.09d 1 2 3 4 5 ___

C.01b 1 2 3 4 ___ C.09e 1 2 3 4 5 ___

C.01c 1 2 3 4 ___ C.10 a b c d ___

C.01d 1 2 3 4 ___ C.11a 1 2 3 4 ___

C.02 a b c d ___ C.11b 1 2 3 4 ___

C.03 a b c d ___ C.11c 1 2 3 4 ___

C.04 a b c d ___ C.11d 1 2 3 4 ___

C.05 a b c d ___ C.12 a b c d ___

C.06 a b c d ___ C.13 a b c d ___

C.07 a b c d ___ C.14 a b c d ___

C.08 a b c d ___ C.15 a b c d ___

C.09a 1 2 3 4 5 ___ C.16 a b c d ___

C.09b 1 2 3 4 5 ___ C.17 a b c d ___

C.09c 1 2 3 4 5 ___

a b

c d

FIGURE A.15

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