ML20205J754
| ML20205J754 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 02/24/1986 |
| From: | Kitchens J, Mayer M, Nau P, Quasny H BECHTEL GROUP, INC., GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20205J720 | List: |
| References | |
| OL, NUDOCS 8602260391 | |
| Download: ML20205J754 (26) | |
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DOLMETED February if,NR1986 16 R8 25 P2 :32 UNITED STATES OF AMERICA QFFICE OF A u.u An' t NUCLEAR REGULATORY COMMISSION u0CMETinc r. SEPvlu.
BRANCH BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
GEORGIA POWER COMPANY, et al.
)
Docket Nos. 50-424 (OL)
)
50-425 (OL)
(Vogtle Electric Generating Plant, )
Units 1 and 2)
)
i APPLICANTS' TESTIMONY OF JOEL KITCHENS, MARK L. MAYER, PATRICK R. NAU, AND HAROLD J. QUASNY ON CONTENTION 10.1 (DOSE-RATE EFFECTS)
Ql.
Please state your namen, employer, and address.
A1.
(JK, MLM, HJQ) Our names are Joel Kitchens, Mark L.
Mayer, and Harold J. Quasny.
We are employed by Bechtel Power Corporation, Western Power Division.
Our business address is Bechtel Power Corporation, 12440 East Imperial Highway, Norwalk, California 90650.
(PRN) My name is Patrick R. Nau.
I am employed by Bechtel National Inc., Research and Development Division, Mate-rial and Quality Services Department. My business address is 9602260391 860224 ADOCK 0 % 4y4 PDR 1
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Bechtel National Inc., P. O. Box.3965,. San Francisco, California 94119.
Q2.
Please state your occupation and describe your educa-tion and professional experience.
(JK) I mn Assistant to the Chief Electrical Engineer, Bechtel Power Corporation, Western Power-Division.
I am an electrical engineer with thirty-seven years of design, supervi-sory, and management experience in power engineering fields.
I received a Bachelor of Science degree in electrical engineering.
from the University of California, Berkeley in 1948.
A summary of my professional qualifications and experience is attached i
hereto as Exhibit A, which I incorporate herein by reference.
(MLM) I hold the position of Engineer, Bechtel Power Corporation, Western Power Division.
I am-a nuclear engineer.
I received a Bachelor of Science degree in Nuclear Engineering from the Massachusetts Institute of Technology in 1981.
Since then, I have been a part of the Vogtle Electric Generating-Plant-(VEGP) nuclear engineering group and have worked on, among other things, project radiation shielding and equipment radiation dose calculations.
A summary of my professional 1
qualifications and experience is attached hereto as Exhibit B, i
which I incorporate herein by reference.
(PRN) I am a Coatings Engineer in the Coatings and Nonmetallic Materials Section of the Material and Corrosion 4
I l i
O' Group, Materials and Quality Services Department, Bechtel Na-tional.
My. job. responsibilities include nonmetallic materials of construction as well as coatings.
As such I have been in-volved in the evaluation and selection of plastics and elastomers in radiation environments for a number of Bechtel projects.
I hold a Bachelor of Science degree in. Polymer Sci-t ence from the University of Southern Mississippi.
A summary of my professional qualifications and experience is attached
. hereto as Exhibit C, which I incorporate herein by reference.
(HJQ) I am an Equipment Qualification Supervisor with the Equipment Qualification Group, Bechtel Power Corporation, Western Power Division.
I am an electrical engineer and hold a Bachelor of Science degree from Chicago Technical. College.
A summary of my professional qualifications and experience is attached hereto as Exhibit D, which I incorporate herein by reference.
Q3.
Please state the purpose of your testimony.
A3.
The purpose of our testimony is to respond to the first three issues that the Atomic Safoty and Licensing Board designated for hearing in its Ja5v)/, 23, 1986 Memorandum and Order (Ruling on Motion.for Sums.ary jtsposition of Contention 10.1 re Dose Rate Effects).1/
These issues relate to the 1/
The fourth issue designated for hearing was subsequently deleted by the, Licensing Board's February 13, 1986 Memorandum (Continued Next Page) l 4
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Affidavit of Joel Kitchens, Victor L. Gonzales, and Mark L.
Mayer (July 30, 1985) (hereinafter " Affidavit of Kitchens et al."), which was submitted in support of Applicants' Motion for Summary Disposition of Joint Intervenors' Contention 10.1 (Dose Rate Effects).
The three issues are:
The Board is unaware, from the in-formation submitted, whether XLPO is the only polymer whose electrical in-sulation property was evaluated subse-quent to radiation exposure.
Applicants have not stated what sig-nificance is to be derived from re-sults of the Duke Power Company's cable surveillance program, vis-a-vis a 40 year service life in VEGP.
The scope and results of the mechani-cal stress tests on prototype VEGP ca-bles are not explained.
Q4.
Please define what is meant by the term " dose-rate effect."
A4.
The term dose-rate effect means that the amount of degradation experienced in an irradiated material is dependent not only on the total integrated dose, but also on the applica-tion rate of the radiation.
In other words, a dose-rate effect (Continued) and Order (Ruling on Applicants' Motion For Partial Reconsider-ation of Board Ruling re contention 10.1).
The fifth and sixth issues designated for hearing by the Licensing Board concern maintenance and surveillance, which is addressed by "Appli-cants' Testimony of George B. Bockhold, Jr.,
and Harold J.
Quasny on Contention 10.1 (Dose-Rate Effects)." '
a exists if the degradation observed in samples of a material receiving equal total integrated doses varies with the rate at which each sample is irradiated.
QS.
How do dose-rate effects pertain to the environmental qualification of equipment?
AS.
To qualify equipment important to safety to withstand accident conditions, it is necessary to take into account equipment degradation that could occur before an accident.
Thus, for environmental qualification, the preconditioning (aging) of equipment to its end-of-normal life condition is considered.
The normal life of equipment, however, is long; most equipment has a service life equal to that of the plant -- ap-proximately forty years.
It is therefore generally impractical to age equipment naturally.
Recognizing this limitation, the Commission specifically permits accelerated aging.
See 10 C.F.R. 5 50.49(e)(5).
Radiation exposure during normal operation of the plant is one contributor to aging.
Accordingly, the acceler-ated aging used in environmental qualification tests must simu-late the degradation attributable to the low dose-rate radia-tion environment to which equipment would be exposed over its normal life.
To simulate the effects of this environment, equipment is exposed to radiation at a high dose rate for a 4
relatively short period of time.
The generally accepted.indus-
~
c try practice has been to use dose rates on the order of 0.01 to:
1 1.0 megarads/hr for this purpose.
.When a high dose rate is used;to simulate aging attributable to radiation, the possibility of dose-rate effects arises.
Dose-rate effects are not a concern for the portion of environmental qualification testing that simulates accident l
conditions, since the dose rates used in testing are comparable to the actual dose rate that would be. experienced during the most severe design basis accident.
Therefore,-the only issue I
is whether the use of a high dose rate to precondition equip-i ment simulates normal aging.
Q6.
Please summarize Contention 10.1.
4 A6.
In 1981, K. T. Gillen and R. L. Clough of.Sandia Na-tional Laboratories conducted a study addressing dose-rate ef-fects in ethylene propylene rubber (EPR), cross-linked polyolefin (XLPO), chloroprene (Neoprene), and chlorosulfonated polyethylene (Hypalon).
This study is entitled NUREG/CR-2157,
" Occurrence and Implications of Radiation Dose-Rate Effects for Material Aging Studies" (June 1981).
Contention 10.1 asserts 4
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that VEGP safety-related equipment containing any of the four i
j polymers addressed in NUREG/CR-2157 has not been properly qual-ified because high dose rates customarily used in accelerated 4
i aging produce less degradation in these polymers than low dose i
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rates.
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Q7.
Please describe the four polymers which Gillen and Clough addressed in NUREG/CR-2157.
A7.
Chlorosulfonated polyethylene, also known as Hypalon, is a polymer produced by reacting chlorine and sulfur with 1
polyethylene.
Some of the hydrogen atoms along the polyethylene chain are replaced with chlorine and sulfur.
The resultant modified polyethylene-based polymer exhibits rubber-like properties and is classified as an elastomer.
Chloroprene, also called Neoprene, is a homopolymer formed entirely from the chloroprene monomer.
Chloroprene is also an elastomer.
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Ethylene Propylene Rubber is typically a copolymer of j
ethylene and propylene monomer units or a terpolymer of ethyl-ene, propylene, and diene monomer (EPDM) units.
EPR is an elastomer.
The term cross-linked polyolefin does not refer to a specific polymer.
The polyolefins are a group of polymers based on aliphatic alkene monomers.
Polyolefins may be homopolymers based on a single repeating olefin monomer or a copolymer based on two alternating olefin monomers.
Examples of polyolefin homopolymers are polyethylene, polypropylene, and polybutylene.
Examples of polyolefin copolymers are i
ethylene-vinyl acetate, polyallomers, and polymethyl pentene.
These polymers are thermoplastics.
Cross-linked polyolefins i
are olefin polymers linked together with short. chains or i
branches at various points.
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e Cross-linked' polyethylene (XLPE).is the polymer most often referred to generically as XLPO.
Sandia has informed us, how-ever, that the polymer that was designated as XLPO in the Sandia study (NUREG/CR-2157) was a copolymer of ethylene and.
vinyl acetate (EVA).
Q8.
How does radiation affect such polymers?
A8.
When polymers absorb radiation, the energy of their atoms is increased.
As a consecuence, free electrons are pro-duced rupturing the chemical bonds and fragmenting the polymer molecules.
The process of irradiation changes the chemical structure of the polymer molecules by breaking them into smaller molecules (scission) or by forming the molecules into a more non-linear network (cross-linking).
The molecules may also reform in their original network, leaving no net structur-al change (recombination).
The competition between the rates of these chemical processes determines the changes in polymer properties due to irradiation.
Q9.
Please describe the Sandia study (NUREG/CR-2157) and its results.
A9.
Gillen and Clough tested EPR and XLPO (EVA) cable in-sulation, and Hypalon and Neoprene cable jacketing.
These ma-terials were stripped from the cables and irradiated in air and nitrogen at radiation dose rates ranging from approximately 0.001 to 1.0 megarads/hr.
Material degradation was followed i t
using ultimate tensile properties (elongation and tensile strength), swelling measurements, and infrared spectroscopy.
Radiation dose-rate effects were found in air envi-ronments at high total integrated doses for all of the materi-als tested.
The mechanism for these effects appears to be the result of competition between cross-linking and scission.
As i
the dose-rate is lowered, there is more time for oxygen diffu-sion into the material and chemical reactions to occur, and scission therefore becomes more important.
The results of the study are shown in Figures 1 through 4.
Q10.
What is the significance of these results?
A10.
The dose-rate effects observed in these four polymers are minor.
Moreover, the differences in the rate of degradation caused by the various dose-rates decrease as the total integrated dose decreases.
In other words, dose-rate ef-fects are more pronounced for higher doses.
At and below total doses equal to the maximum normal 40-year total dose determined for safety-related equipment at VEGP (and expected doses are less) dose-rate effects are insignificant.
In the case of ethylene-propylene rubber and Hypalon, the reduction of tensile properties is virtually the same for all dose rates up to a total integrated dose of 20 megarads.
In the case of Neoprene, the reduction is virtually the same for all dose rates up to a total integrated dose of 10
_9
megarads.
At VEGP, no safety-related equipment will receive a total integrated dose for 40 years normal operation greater than 10 megarads; and most such equipment will receive less than two megarads.
Thus, for EPR, Neoprene, and Hypalon, the dose-rate effects observed by Gillen and Clough are insignifi-cant irrespective of polymer application.
Of the four polymers addressed in NUREG/CR-2157, only EVA (the sample designated as XLPO) exhibited 6 se-rate effects that were discernible at total doses below 10 megarads.
- EVA, however, is not uced at VEGP in any safety-related equipment subject to a harsh environment.
Nor can the results for EVA be used to predict similar effects in other cross-linked polyolefins.
A new study by Sandia, released after Applicants' motion for summary disposition was filed, has evaluated dose-rate effects in cross-linked polyethylene.
K. T. Gillen, R.
L.
Clough, and N. J. Dhogge, NUREG/CR-4358, " Applications of Den-sity Profiling to Equipment Qualification Issues" (Sept. 1985).
Sandia evaluated among other things the degradation of tensile properties of XLPE insulation at various dose-rates.
The re-sults are shown in Figure 5 and demonstrate that dose-rate ef-l fects in XLPE are not significant below 20 megarads.
Thus, the dose-rate effects observed by Gillen and Clough in XLPO, EPR, Hypalon, and Neoprene are insignificant with respect to safety-related equipment at VEGP.
- Moreover, one should also recognize that the dose-rate effects observed - - -
by Gillen and Clough.are probably exaggerated.
In their study, pieces of cable insulation were stripped from the wire for the tests.
The insulation material was thus completely exposed to oxygen in the ambient environment.
In actual application, in-sultion is covered with a jacket material.
Although the jacket is primarily for mechanical protection (protection from abra-sion, cuts, etc.), this covering significantly reduces the oxy-gen available for radiation-induced oxidation of the cable in-sulation. Since oxygen diffusion into the materials is postulated to be a major contribution to the degradation mecha-nism, the applicability of the Sandia test results to cable in-stalled at VEGP is questionable.
Q11.
The Licensing Board stated that it is unaware, from the information submitted, whether XLPO is the only polymer whose electrical insulation property was evaluated subsequent to radiation exposure.
Were any other polymers so evaluated?
All.
In the Affidavit of Kitchens et al.,
the affiants assumed for the purpose of their analysis that the dose-rate effects observed in the polymer designated as XLPO in NUREG/
CR-2157 (which was EVA) were applicable to XLPE.
The only safety-related application of XLPE, or of any other type of XLPO, subject to a harsh radiation environment at VEGP is cable insulation.
To demonstrate that the dose-rate effects observed in XLPO did not compromise safety-related cable, affiants - -
described the results of another Sandia study which demon-strated that degradation of the mechanical properties of XLPO insulation does not prevent the cable from performing its re-quired electrical function.
This particular.Sandia study is NUREG/CR-2932, E. E. Minor and D. T. Furgal, Sandia National Laboratories, " Equipment Qualification Research Test of Elec-tric Cable With Factory Splices and Insulation Rework Test 2
No. 2" (Sept. 1982).
In Minor and Furgal's study (NUREG/CR-2932), the XLPO materials that were tested consisted of XLPE.
Electrical cable insulated with these materials was exposed to a relatively low dose rate (0.062 megarads/hr) for a total integrated normal op-erational dose of 50 megarads.
Then, after elevated tempera-ture aging, the cable was exposed to an accident dose of 150 megarads at a rate of 0.77 megarads/hr.
Despite severe degra-dation of mechanical properties, the cable was able to perform its electrical function at all times.
This series of tests was conducted according to industry standards (IEEE 323-1974 and IEEE 383-1974) and NRC guidelines (NUREG-0588).
Minor and Furgal concluded that the methodology employed by the nuclear industry to qualify electrical equipment (which includes accel-erated aging), is adequate despite the dose-rate effect on me-chanical properties studied by Gillen and Clough.
We are not aware of studies that evaluated dose-rate effects in the electrical properties of polymers other than.
XLPE after radiation exposure.
The electrical properties XLPE and EPR after radiation exposure were evaluated in two addi-tional Sandia studies, but these studies did not assess dose-rate effects.
The two studies are NUREG/CR-3538, L. D.
Bustard, "The Effect of LOCA Simulation Procedures on Ethylene Propylene Rubber's Mechanical and Electrical Properties" (Oct.
1983), and NUREG/CR-3588, L. D. Bustard, "The Effect of LOCA Simulation Procedures on Cross-Linked Polyolefin Cable's Per-formance" (April 1984).
Of course, during environmental quali-fication testing, all safety-related cables undergo an insula-tion test after LOCA simulation.
Q12.
The Licensing Board stated that Applicants have not stated what significance is to be derived from results of the Duke Power Company's cable surveillance program, vis-a-vis a 40 year service life in VEGP.
Please discuss the significance of the Duke study.
A12.
In the prior affidavit, we noted that additional in-formation regarding dose-rate effects may be obtained from a Duke Power Company Study.
Duke Power established an informal cable life evaluation program at its Oconee Nuclear Generating Unit 1, which became commercially operational in 1973.
For this program, representative specimens of con-trol, instrumentation and power cable were placed in selected locations within the reactor building so that they would be subjected to a normal in-containment environment.
The cables were for the most part insulated with EPR and had Neoprene jackets.
Some samples were insulated with cross-linked polyethylene and covered with Neoprene j ackets.
~
For all cable samples, the average radiation exposure rate was 0.65 rads /hr during operation and 0.12 rads /hr when the unit was shut down.
The actual exposure level that each sample received is considered to have varied considerably over the length of the cable dependent upon the exact location of the cable within the reactor building.
These dose rates are quite low in comparison to rates used in the Sandia investiga-tions, but are representative of the dose rates expected to occur at VIGP.
Samples of these cables were removed after 5 years and again after 10 years of exposure.
Physical and electrical tests were conducted to determine the degree of degradation of the cable components.
In all cases, the cables were in good condition with no more deterioration observed than would be ex-pected over a similar period in a non-nuclear environment.
In fact, in one instance, the physical properties of the cable 1
sample actually improved during the ten year period.
The significance of the Duke Power Company s cable
~
surveillance program is that 10 year exposure to the low dose-rate radiation actually encountered in operating nuclear power plants has not done detectable harm thus far to cables of the I
f.
same general type that are used at VEGP.
While this experience cannot yet be extrapolated out to forty-years, it is at least an indication that dose-rate effects are insignificant.
Fur-thermore, the results demonstrate that there will be plenty of time to benefit from operating experience gained from other plants and to take any necessary corrective action if signifi-cant dose-rate effects are identified.
Q13.
With respect to the Affidavit of Kitchens et al.,
the Board stated that the scope and results of mechanical stress tests on prototype VEGP cables have not been explained.
Please provide this explanation.
A13.
In the prior affidavit, we noted that with respect to electrical insulation, Gillen and Clough have suggested that mechanical properties are of interest primarily when consid-ering the effect of catastrophic failure under the influence of some applied stress.
Cable qualification tests at VEGP, how-ever, currently include a mechanical durability test for cable applied following the simulated normal and accidental environ-mental conditions.
This stress test is applied to test samples of all VEGP safety-related cables.
The test complies with IEEE-383-74, section 2.4, which states:
Upon completion of the LOCA simulation, the specimens should be straightened and re-coiled around a metal mandrel with a diame-ter of approximately 40 times the overall cable diameter and immersed in tap water at e
room temperature.
(Caile still immersed, these specimens should again pass a voltage withstand test for 5 minutes at a potential of 80 V/ mil ac or 240 V/ mil dc.
NOTE:
The post LOCA simulation test demonstrates an adequate margin of safety by requiring mechanical durability (Mandrel bend) fol-lowing the environmental simulation and is more severe than exposure to two cycles of the environment.
Id.
The samples used to qualify each type of VEGP safety-related cable passed this test.
Q14.
What is your conclusion regarding Contention 10.l?
A14.
It is our conclusion and professional opinion that the dose-rate effects observed in NUREG/CR-2157 are insignifi-cant with respect to safety-related equipment at VEGP, and that the dose-rates used in artificial aging of VEGP safety-related equipment are appropriate.
-VEGP NORMA 1. 40 YEAR TOTAL INTEGRATED DOSES
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The tensile strength af ter aging divided by the tensile strength before aging (T/T ) and the tensile elongation after j
aging divided by the tensi,le elongation before aging (e/a ) are L
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EXHIBIT A JOEL KITCHENS Assistant to the Chief Electrical Engineer Sechtel Power Corporation. Western Power Division PROFESSIONAL QUALIFICATIONS EDUCATION BSEE - University of California, Berkeley - 1948 4
Business Management Certificate Program. University of California, Berkeley - 1973 EXPERIENCE
SUMMARY
37 years design, supervisory and management positions in power engineering fields.
~
EMPLOYMENT HISTORY 1966 to present:
Bechtel Group - various locations 1956 to 1966:
Anaconda Company - Wire and Cable Division New York and San Francisco 1948 to 1956:
Pacific Gas and Electric Company San Francisco PROFESSIONAL AFFILIATIONS:
Fellow, Institute for the Advancement of Engineering Senior Member. Institute of Electrical and Electronic Engineers Member, IEEE Insulated Conductors Committee Member, Project Management Institute Registered Professional Engineer, Arizona and California SPECIFIC OVALIFICATIONS IN THE INSULATED CABLE FIELD Ten years with the Anaconda Company, Wire and Cable Division. These years 4
included the following positions held and duties performed:
o 31/2 years as a cable Engineer doing cable design, specification writing, 1
inspection and manufacturing engineering.
o 2 years as a Regional Engineer doing application engineering and providing technical assistance for sale personnel and clients.
o 2 1/2 years a Chief Cable Engineer with full responsibility for design, specifications and quality for the company',5 insulated products in the low voltage and medium voltage field, o
2 years as General Manager of the Cable Accessories Division in charge of design, manufacture and marketing of the accessories product line.
During 19 years with the Bechtel Group of Companies, have been a Cable Specialis'. with responsibility for insulated cable master specifications i
for all voltages and applications. Have been a member of the IEEE Power Engineering Society Insulated Conductors Committee and havu represented Bechtel on this committee for this full time. Have actively participated on subcommittees and working groups responsible for maintaining and revising, as necessary, cable industry qualification standards such as IEEE Standard 383.
n
n EXIIIBIT B MARK L. MAYER ENGINEER Bechtel Power Corporation, Western Power Division l
PROFESSIONAL QUALIFICATIONS EDUCATION BS, Nuclear Engineering, Massachusetts Institute of Technology-1981 EXPERIENCE
SUMMARY
4 years as a nuclear engineer EMPLOYMENT HISTORi 1981 to present:
Bechtel Power Corporation, Western Power Division PROFESSIONAL AFFILIATIONS:
Registered Professional Engineer, California SPECIFIC QUALIFICATIONS IN THE RADIATION ANALYSIS FIELD Four years with the VEGP nuclear engineering group.
Responsibilities and duties have included:
Input to, and review of, project radiation shielding o
calculations. These duties required the review and understanding of the plant layout, operation and radiation sources.
Input to, generation of, and review of, project o
equipment radiation dose calculations. These duties required a review of radiation sources and accident scenarios to identify qualification doses, s
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EXHIBIT C PATRICX g. NAU EDUCATION:
B.S., Polymer Science, 1981 University of Southern Mississippi
SUMMARY
4-1/2 YEARS: Corrosion Engineer, specializing in coating formulation and application, plastic materials, and elastomers.
EXPERIENCE:
1982 - Present: Bechtel National, Inc., Research and Development / Materials and Quality Services Department, Materials and Corrosion Group. Mr. Nau's activities are in the areas of coatings and nonnetallic materials of construction and include material selection, preparation and review of specifications, review of suppliers procedures, probles analysis and inspection and monitoring of applications. Mr. Neu has completed extensive studies on temporary preservatives, composite materials, geooembranes and gasket materials and has done a considerable amount of work in the areas of elastomers and thermoplastics. His experience includes the use of most instruments used to analyse and inspect coatings both before and after application. In addition he has experience in laboratory work using scanning electron microscopy and infrared spectroscopy.
Mr. Neu has completed the Materials and Quality Services Inspector training program. He spent six months inspecting extensive coating and lining work on the scrubber outlet ducts, stacks and a number of assorted tanks for Colstrip Units 3 & 4 in Colstrip, Montana. He has also been involved in inspection and monitoring of the lining of a large water tank for the Limerick Generating Station in Pennsylvania and a variety of coatings for the Hope Creek Generating Station in New Jersey. Most recently, Mr. Nau has completed a six month assignment in South Korea where he functioned as the client coating inspector for Chevron's off shore platform, ' Esther.
Ne has also performed coatings work on Chevron's Hidalgo offshore platform, Occidental's San Miguel platform and the Harriet offshore platform in Australia.
1981 - 1982: Mr. Neu was an associate chemist in the Thermark Corporation laboratory developing coatings formulations.
PROFESSIONAL DATA:
Member: Steel Structures Painting Council (SSPC)
February 1986 - R&D/ Materials and Qua1Lty Services l
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EXHIBIT D
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HAROLD J. QUASNY Education:
BS. Electrical Engineering, Chicago Technical College Business Management certificate. University of California Berkeley Summary:
39 Years:
Electrical engineering supervision in power plants and industrial and i
government facilities Experience:
Mr. Quasny is presently the Supervisor of the Equipment Environmental Qualification Group providing technical support for all of the domestic and overseas nuclear power plants.
Prior to this, he was a coordinator for the Chief Electrical Engineer for three nuclear and two fossil power plants and modifications to two existing power plants.
Responsibilities included the technical and administrative coordination of the project and review of the discipline operations.
Mr. Quasny was the Assistant Project Engineer and Electrical Engineering Supervisor on the 80-MW Hawaiian Wind Farm Project.
Prior to this, he was on the electrical technical staff as senior l
technical representative of the Chief Electrical Engineer for various power plant projects.
His responsibilities included solution of key technical areas on projects requiring multi-project overviews, including four nuclear and one fossil fuel projects.
Previously, Mr. Quasny was an Administrative Assistant to the Chief Electrical Engineer responsible for personnel and salary administration and alto manager of the reliability engineering group.
He had the project engineering responsibilities for the conceptual studies, master planning. final engineering design, and client assistance during the construction of a gas turbine assembly and facilities of over 260,000 square feet.
As test Engineering Group Supervisor, Mr. Quaany was responsible for the engineering and design of
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more than 10 types of facilities. including the I
i Mead Converter Station to convert high voltage AC to 750-v de for power transmission.
He has been responsible for the engineering design of high reliability power systems for airports and prepared a handbook on the engineering design of airport high reliability power systems.
l 3299W l
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RAROLD J. QUASNY (continued) l Prior to joining Bechtel, Mr. Quasny was associated with Aerojet-General, where he was Project Engineer on a high thrust nuclear rocket test facilities complex and high powered radar l
facilities. including a diesel power plant in the Pacific and various facilities at Vandenberg Air Force Base.
In addition, Mr. Quasny was a Lead Engineer responsible for various industrial and government projects, including additions and modification at the Idaho Falls Complex.
Mr. Quasny was an Electrical Engineer for C. F.
Braun active in the design of the multi-million dollar flying "A"
refinery complex.
At Harza Engineering, Mr. Quasny was an Assistant Project Engineer on an underground hydroelectric power plant for El Salvador.
He also had engineering design responsibilities on hydroelectric power plants, transmission systems, and substations.
Professional Affiliations:
Member, Institute of Electrical and Electronics Engineers v
Member Electrical Maintenance Engineers Association Member, Society of Military Engineers Member, Institute for the Advancement of Engineering 3299W