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Retake Examination Report No. 50-223/OL-06-01, University of Massachusetts - Lowell
	ML062910365
Person / Time
Site:	University of Lowell
Issue date:	10/20/2006
From:	Johnny Eads; NRC/NRR/ADRA/DPR/PRTB
To:	Kegel G; Univ of Massachusetts - Lowell
	Doyle P, NRC/NRR/DPR/PRT, 415-1058
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October 20, 2006 Dr. Gunter Kegel, Director Nuclear Radiation Laboratory University of Massachusetts Lowell One University Avenue Lowell, MA 01854

SUBJECT:

RETAKE EXAMINATION REPORT NO. 50-223/OL-06-01, UNIVERSITY OF MASSACHUSETTS - LOWELL

Dear Dr. Kegel:

During the week of July 03, 2006, the NRC administered an operator licensing retake 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.

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 document system (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/NRC/ADAMS/indesx.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 at or via internet E-mail at @nrc.gov.

Sincerely,

/RA/

Johnny Eads, Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-223

Enclosures:

1. Retake Examination Report No. 50-223/OL-06-01

2. Examination and answer key cc w/encls:

Please see next page

October 20, 2006 Dr. Gunter Kegel, Director Nuclear Radiation Laboratory University of Massachusetts Lowell One University Avenue Lowell, MA 01854

SUBJECT:

RETAKE EXAMINATION REPORT NO. 50-223/OL-06-01, UNIVERSITY OF MASSACHUSETTS - LOWELL

Dear Dr. Kegel:

During the week of July 03, 2006, 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.

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 document system (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/NRC/ADAMS/indesx.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 at or via internet E-mail at @nrc.gov.

Sincerely,

/RA/

Johnny Eads, Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-223

Enclosures:

1. Retake Examination Report No. 50-223/OL-06-01

2. Examination and answer key cc w/encls:

Please see next page DISTRIBUTION w/ encls.:

PUBLIC RNRP R&TR r/f JEads Facility File (EBarnhill) O-6 F-2 MMendonca ADAMS ACCESSION #: ML062910365 TEMPLATE #:NRR-074 OFFICE PRTB:CE IOLB:LA PRTB:BC NAME PDoyle:tls*

EBarnhill*

JEads:tls*

DATE 10/18/2006 10/20/2006 10/20/2006 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 RETAKE EXAMINATION REPORT REPORT NO.:

50-223/OL-03-01 FACILITY DOCKET NO.:

50-223 FACILITY LICENSE NO.:

R-125 FACILITY:

University of Massachusetts - Lowell EXAMINATION DATES:

July 07, 2006 SUBMITTED BY:

_________/RA/______________________

10/112006 Paul V. Doyle Jr., Chief Examiner Date

SUMMARY

The NRC prepared a retake written examination for a candidate who failed sections A and C of the written examination administered September 2005. The examination was mailed to the facility, and the facility management administered the examination to the candidate.

REPORT DETAILS 1.

Examiners:

Paul V. Doyle Jr., Chief Examiner 2.

Results:

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

Exit Meeting:

Due to the fact that the examination was mailed to the facility there was no exit meeting.

ENCLOSURE 1

OPERATOR LICENSING EXAMINATION With Answer Key UNIVERSITY OF MASSACHUSETTS-LOWELL Week of June 19, 2006 Retake of Sections A and C

Section A L Theory, Thermo & Fac. Operating Characteristics Page 1 QUESTION A.01 [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.02 [2.0 points, 1/2 each]

A fissile material is one which will fission upon the absorption of a THERMAL neutron. A fertile material is one which upon absorption of a neutron becomes a fissile material. Identify each of the listed isotopes as either fissile or fertile.

a. Th232

b. U235 c.

U238

d. Pu239 QUESTION A.03 [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.04 [2.0 points, 1/2 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.

Section A L Theory, Thermo & Fac. Operating Characteristics Page 2 QUESTION A.05 [1.0 point]

What is the kinetic energy range of a thermal neutron?

a. > 1 MeV

b. 100 KeV - 1 MeV c.

1 eV - 100 KeV

d. < 1 eV QUESTION A.06 [1.0 point]

When performing rod calibrations, many facilities pull the rod out a given increment, then measure the time for reactor power to double (doubling time), then calculate the reactor period. If the doubling time is 42 seconds, what is the reactor period?

a. 29 sec

b. 42 sec c.

61 sec

d. 84 sec QUESTION A.07 [1.0 point]

Shown to the right is a trace of reactor PERIOD as a function of time. Between points A and B reactor POWER is

a. continually increasing.

b. continually decreasing.

c.

increasing, the decreasing.

d. constant.

QUESTION A.08 [1.0 point]

The term reactivity may be described as a.

a measure of the cores fuel depletion.

b.

negative when Keff is greater than 1.0.

c.

a measure of the cores deviation from criticality.

d. equal to $.50 when the reactor is prompt critical.

Section A L Theory, Thermo & Fac. Operating Characteristics Page 3 QUESTION A.09 [1.0 point]

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

a. 11 minutes

b. 22 minutes c.

44 minutes

d. 51 minutes QUESTION A.10 [1.0 point]

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

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

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

c.

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

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

QUESTION A.11 [1.0 point]

The number of neutrons passing through a square centimeter per second is the definition of which ONE of the following?

a. Neutron Population (np)

b. Neutron Impact Potential (nip) c.

Neutron Flux (nv)

d. Neutron Density (nd)

QUESTION A.12 [1.0 point]

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

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

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

c.

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

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

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

Section A L Theory, Thermo & Fac. Operating Characteristics Page 4 QUESTION A.13 [1.0 point]

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

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

c.

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

d. U238 in the core becomes Pu239 (by neutron absorption), which has a higher for fission QUESTION A.14 [1.0 point]

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 QUESTION A.15 [1.0 point]

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)

QUESTION A.16 [1.0 point]

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

c.

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

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

Section A L Theory, Thermo & Fac. 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. is absorbed, with the nucleus emitting a gamma ray, and the neutron with a lower kinetic energy.

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]

The neutron microscopic cross-section for absorption a 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

Section C Facility and Radiation Monitoring Systems Page 6 QUESTION C.1

[1.0 point]

Which one of the following scrams is disabled by placing the range switch (7S5) in the 0.10 MW position?

A. Coolant Gate Open (Riser).

B. High Voltage Failure C. Pool Level D. Containment Air Leak Doors Open QUESTION C.2

[2.0 points, 0.5 each]

Match each of the electrical loads listed in column A with its electrical source listed in column B. (Each load has only one answer. Items in column may be used more than once or not at all.)

Column A Column B

a. Secondary Pump

1. Motor Control Center #l;

b. Pneumatic tube system blower

2. Motor Control Center #2; c.

Exhaust Blower EF-12

3. PPL-R1

d. Emergency Exhaust EF-14

4. ELPL-Rl QUESTION C.3

[1.0 point]

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

a. Low source count rate < 3 cps

b. High flux - 110%

c.

Short Period - 15 seconds

d. Source Range Signal/noise ratio of 2 QUESTION C.4

[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 7 QUESTION C.5

[1.0 point]

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

a. Borated Graphite

b. Boron-Aluminum Alloy (Boral) c.

Hafnium

d. Stainless Steel.

QUESTION C.6

[1.0 point]

Which one of the following ventilation valves will fail OPEN on a loss of service air?

a. G, Sanitary System Vent Isolation Valve

b. D, Emergency Exhaust Isolation Valve c.

F, Ventilation Supply Bypass Valve

d. H, Acid Vent (Basement)

QUESTION C.7

[1.0 point]

The "TEST" position of the Master Switch allows:

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

b. control power and lamp indication operability testing.

c.

control blade drive motion without energizing the scram magnets.

d. control blade drive motion with energized scram magnets QUESTION C.8

[1.0 point]

The reactor is operating at 1 Megawatt, when the SECONDARY coolant pump trips on overload. Assuming NO OPERATOR ACTION, which ONE of the following trips would most likely cause a reactor scram?

a. High Flux

b. Short Period c.

High Coolant Inlet Temperature

d. Low Secondary Flow

Section C Facility and Radiation Monitoring Systems Page 8 QUESTION C.9

[2.0 points, 0.5 each]

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 QUESTION C.10 [2.0 points, 0.33 each]

Using the drawing of the primary system provided, if the reactor is in position 1, with the coolant system in the cross-stall mode (preferred line-up). Identify the position of the valves listed (Open, Closed, Throttled).

a. P-1

b. P-2 c.

P-3

d. P-4

e. P-9 f.

P-11 QUESTION C.11 [2.0 points, 1/4 each]

Using the drawing of the ventilation system provided, give the status of the following valves (OPEN, SHUT) and fans (ON, OFF) upon receipt of a GRVS signal.

a. Valve A

b. Valve B c.

Valve C

d. Fans 3 through 6

e. Valve E f.

Valve F

g. Fan EF-12

h. Fan AC-2

Section C Facility and Radiation Monitoring Systems Page 9 QUESTION C.12 [1.0 point]

Fan EF-14 and valve D operate independently of a GRVS signal. For which of the listed conditions below, would fan EF-14 be operating? Containment Pressure =

a. +0.6 inches H2O

b. +0.3 inches H2O c.

-0.3 inches H2O

d. -0.6 inches H2O QUESTION C.13 [2.0 points, a each]

Using Figure C.13, match each of the core locations listed in column A with its correct component from column B.

Column A (Grid Position)

Column B

a. A1

1. Proportional Counter

b. A2

2. Compensated Ion Chamber c.

A5

3. Startup Source

d. B4

4. Graphite Reflector Element

e. D9

5. Fuel Element f.

G9

6. Irradiation Basket

7. Servo Control Element (Regulating rod)

QUESTION C.14 [1.0 point]

Which ONE of the following describes how the signal for regulating rod position indication is generated?

a. A series of magnetic switches which respond to lead screw position.

b. A tachometer that counts the revolutions of the lead screw.

c.

A series of limit switches that are actuated by the ball bearing screw assembly.

d. A mechanical position transmitter that is chain driven by the drive motor

Section C Facility and Radiation Monitoring Systems Page 10 QUESTION C.15 [1.0 point]

The purpose of the filter in the reactor pool cleanup system is to

a. prevent demineralizer resin fines from entering the pool.

b. prevent larger particles from plugging the demineralizer resin.

c.

remove crud from the coolant limiting the radiation levels associated with the demineralizer.

d. remove particles that could clog the cleanup system pump seals..

QUESTION C.16 [1.0 point]

Which ONE of the following is an "ELECTRONIC" scram?

a. High flux

b. High temperature primary coolant c.

Seismic

d. Low pool water level QUESTION C.17 [1.0 point]

Which ONE of the following loads is supplied from the air compressor located on the intermediate level inside the reactor building?

a. Air lock doors.

b. Thermal column door.

c.

Pneumatic tube system.

d. Containment isolation valves.

Section C Facility and Radiation Monitoring Systems Page 11 A.01 c

REF:

Standard NRC Question A.02 a, fertile; b, fissile; c, fertile; d, fissile REF:

A.03 a

REF:

= (Keff1 - Keff2) ÷ (Keff1

Keff2)

= (0.9550 - 1.0000) ÷ (0.9550

1.0000)

= -0.0450 ÷ 0.9550 = -0.0471 A.04 a, 2; b, 4; c, 1; d, 3 REF:

REF:

A.06 c

REF:

ln (2) = -time/

= time/(ln(2)) = 60.59. 61 seconds A.07 a

REF:

Standard NRC Question A.08 c

REF:

diff between moderator & reflector REF:

REF:

A.17 b

REF:

A.18 b

REF:

Section C Facility and Radiation Monitoring Systems Page 12 C.1 a

REF:

U. Mass. Lowell Reactor, RO-9 Reactor and Control System Checkout, § 9.2.2 C.2 a, 2; b, 1; c, 2; d, 4; REF:

Study Guide for Key Access and Introduction to Operator Training Electrical System, Figure 3.5.

C.3 d

REF:

U. Mass. Lowell Reactor RO-9 System Checkout Procedures C.4 a

REF:

Standard NRC Question.

C.5 b

REF:

Study Guide for Key Access and Intro to Operator Training Introduction to the UML Reactor ¶ 5 C.6 c

REF:

U. Mass. Lowell Reactor, FSAR, § 3.4.2.2 C.7 c

REF:

U. Mass Lowell, FSAR Table 4.3.

C.8 c

REF:

Modification of NRC Examination bank question administered August 1988.

C.9 a, 2; b, 2; c, 3; d, 4 REF:

NRC Examination Question administered September, 1996.

C.10 a, Open; b, Open; c, Closed; d, Closed; e, Open; f, Throttled REF:

SAR § 4.2.2, also, Training Handout section on Primary System, and drawing.

C.11 a, SHUT; b, SHUT; c, SHUT; d, OFF; e, SHUT; f, OPEN; g, OFF; h, ON REF:

C.12 b

REF:

Training Handout Section on Containment/Ventilation, last page.

C.13 a, 2; b, 4; c, 3; d, 5; e, 7; f, 1 REF:: SAR Figure 4.1, Core Arrangement C.14 d

REF:

ULR SAR, §4.1.8, p 4-11; Figures 4.6 and 4.7. C.14 C.15 a

REF:

ULR SAR, §4.2.5, p 4-29.

C.16 a

REF:

ULR SAR, §4.4.15.2, p 4-74.

C.17 a

REF:

ULR SAR, § 6.2, p 6-5.

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY:

University of Massachusetts-Lowell REACTOR TYPE:

GE Pool DATE ADMINISTERED:

2006/06/_____

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 47.6 A.

Reactor Theory, Thermodynamics and Facility Operating Characteristics 22.00 52.4 C.

Facility and Radiation Monitoring Systems 42.00 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.

EQUATION SHEET 444444444444444444444444444444444444444444444444444444444444444444444444444444 4444444444444 DR - Rem, Ci - curies, E - Mev, R - feet 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 L Theory, Thermo, and Facility Characteristics Page 16 A.01 a b c d ___

A.07 a b c d ___

A.02a fertile fissile ___

A.06 a b c d ___

A.02b fertile fissile ___

A.09 a b c d ___

A.02c fertile fissile ___

A.10 a b c d ___

A.02d fertile fissile ___

A.11 a b c d ___

A.03 a b c d ___

A.12 a b c d ___

A.04a 1 2 3 4 ___

A.13 a b c d ___

A.04b 1 2 3 4 ___

A.14 a b c d ___

A.04c 1 2 3 4 ___

A.15 a b c d ___

A.04d 1 2 3 4 ___

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 ___

Section C Facility and Radiation Monitoring Systems Page 17 C.01 a b c d ___

C.10f O C T ___

C.02a 1 2 3 4 ___

C.10a Open Shut On Off ___

C.02b 1 2 3 4 ___

C.10b Open Shut On Off ___

C.02c 1 2 3 4 ___

C.11c Open Shut On Off ___

C.02d 1 2 3 4 ___

C.11d Open Shut On Off ___

C.03 a b c d ___

C.11e Open Shut On Off ___

C.04 a b c d ___

C.11f Open Shut On Off ___

C.05 a b c d ___

C.11g Open Shut On Off ___

C.06 a b c d ___

C.11h Open Shut On Off ___

C.07 a b c d ___

C.12 a b c d ___

C.08 a b c d ___

C.13a 1 2 3 4 5 6 7 ___

C.09a 1 2 3 4 ___

C.13b 1 2 3 4 5 6 7 ___

C.09b 1 2 3 4 ___

C.13c 1 2 3 4 5 6 7 ___

C.09c 1 2 3 4 ___

C.13d 1 2 3 4 5 6 7 ___

C.09d 1 2 3 4 ___

C.13e 1 2 3 4 5 6 7 ___

C.10a O C T ___

C.13f 1 2 3 4 5 6 7 ___

C.10b O C T ___

C.14 a b c d ___

C.10c O C T ___

C.15 a b c d ___

C.10d O C T ___

C.16 a b c d ___

C.10e O C T ___

C.17 a b c d ___

Figure C.10

Figure C.11

Figure C-13

ML062910365

Contents

Text

SUBJECT:

Dear Dr. Kegel:

Enclosures:

SUBJECT:

Dear Dr. Kegel:

Enclosures:

SUMMARY

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ML062910365

Text

SUBJECT:

Dear Dr. Kegel:

Enclosures:

SUBJECT:

Dear Dr. Kegel:

Enclosures:

SUMMARY

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