ML17328A078
| ML17328A078 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/30/1987 |
| From: | Gruber T, Mirick W Battelle Memorial Institute, COLUMBUS LABORATORIES |
| To: | |
| Shared Package | |
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| References | |
| NUDOCS 8907210090 | |
| Download: ML17328A078 (92) | |
Text
PHASE I FINAL REPORT Proposal/Agreement No. 382-P-9955R on ANALYSIS OF MATERIALS:
D. C. COOK SAFETY INJECTION MOTOR MATERIALS QUALIFICATION to AMERICAN ELECTRIC POWER SERVICE CORPORATION December 30, 1987 by Tom Gruber and William Mirick BATTELLE Columbus Division 505 King Avenue Columbus, Ohio 43201-2693
ATTACHMENT 2 TO AEP:NRC:0775AP ANALYSIS OF MATERIALS: D. C. COOK SAFETY INJECTION MOTOR MATERIALS QUALIFICATION 89072&690 890714 PDR ADOCK 050003ib P PDC J
TABLE OF CONTENTS
~Pa e I NTRODUCTION o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ 1 S WARY ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 2 C ONCLUSIONS ......................................................... 3 RECOMMENDATIONS ..................................................... 4 MATERIALS ANALYSIS DETAILS .......................................... 5 L literature Survey Summary ...................................... 6 Information From IEEE Transactions ........................ 8 0 ther Reports ............................................. 18 DOE ENERGY Search Summary ............. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 33 EI ENGINEERING MEETINGS Search Summary ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 38 COMPENDEX Search Summary ....................................... 40 11
PHASE I FINAL REPORT on ANALYSIS OF MATERIALS D. C. COOK SAFETY INJECTION MOTOR MATERIALS QUALIFICATION to AMERICAN ELECTRIC POWER SERVICE CORPORATION from BATTELLE Columbus Division by Tom Gruber and William Merick
'December 30, 1987 INTRODUCTION A 400 horse power safety injection motor which was qualified for Class 1E service (equipment for nuclear power generating stations) was sent to a non-certified shop for balancing. The rotor was balanced and, as is normal practice, the stator was varnished and the end windings painted.
There is concern about the status of the Class IE qualification of this motor as a result of the use of non-certified materials used to varnish the stator.
The chemical compatibility of the newly added varnish with the original materials is unknown.
A two phase program was proposed to American Electric Power (AEP) .
by Battelle to resolve these questions. Phase I, Analysis of Materials, involves a search for information and data to demonstrate that the newly added materials and the original materials are compatible, and that the motor remains qualified for Class 1E service. Phase II, Materials qualification, involves the irradiation of a combination of the original stator materials
and the newly applied materials to demonstrate that there. is no adverse reaction to radiation.
This is the Final Report for Phase I. The following sections contain a summary of the work performed, conclusions, and recommendations for further action by American Electric Power. The final section of this report, Materials Analysis Oetails, provides permanent documentation of the informa-tion located and highlights the information that substantiates the con-clusions. The final section, Materials Analysis Oetai ls, is lengthy and is directed toward those persons with a detailed interest in the effects of radiation on organic materials.
SUMMARY
The objective of the Phase I analysis of the materials was to determine if the varnish and paint added to the motor have any adverse effect on the originally qualified materials and the qualification of the motor.
The first step was to obtain information about the materials used by the motor manufacturer, Westinghouse, and the shop which balanced and varnished the motor.
The two materials used by Westinghouse were identified as:
Item 81 8-6-665, Air Ory Insulating Enamel-Epoxy, and Item d2 8-172 Epoxy Varnish.
The information about the materials used by Westinghouse was proprietary and was obtained only after Battelle had entered a confidential information agreement with Westinghouse.
The shop that balanced the motor used material manufactured by Schenectady Chemical, Inc., with the registered trade marked name Aquanel 600, a water borne insulating varnish. This varnish is a modified alkyd solution containing dimethylaminoethanol and butyl cellosolve.
The search for pertinent data in published literature was conducted in two steps: (I) a search of published indexes of engineering and technical literature, and (2) a search of computerized databases. As it turned out, a
3 report on a significant survey was located which contained an extensive bibliography. Copies were obtained of pertinent reports and journal articles from this bibliography. The most recent information obtained was dated 1979.
The computerized database search was then conducted to obtain the most recent information available, 1986. Abstracts contained in the computer search off-line output confirmed the conclusions which had been made from the pre-1980 information. Copies of several original reports located by the computer search were ordered to obtain information on the specific materials used on the motor inquestion.
No information was found on the specific materials used on the D.
C. Cook Safety Injection Motor. However, all the information obtained from world-wide sources confirms that with few specific exceptions organic materials used for paints, varnishes, and insulating coatings may be expected to perform satisfactorily to radiation doses up to 108 rads. This informa-tion is summarized in the last section of this report and pertinent details have been highlighted by arrows in the lefthand margin ( ==> ).
CONCLUSIONS Review of the information obtained through the literature search supports the following conclusions:
(1) Radiation damage is not likely to occur until the varnishes and paints in question have received a dose of more than 108 rads.
(2) There is not likely to be any problem unless the original and over-laid varnish and paints are chemically incompatible.
(3) It is feasible to perform a relatively simple laboratory evaluation of the materials in question to determine chemical compatibility.
(4) If the materials are incompatible, there is no need to perform irradiation tests.
(5) Thermal aging of varnish and paint samples may be performed prior to irradiation of samples.
(6) If the materials are chemically compatible, and if electrical measurements after irradiation to 108 rads (gamma) show no degradation, continued use of the motor for its Class 1E application is acceptable.
RECOMMENOATIONS The following recommendations are made on the basis of the above conclusions.
(1) The chemical compatibility of the original motor insulation materials with the newly applied insulation materials be determined experimentally. These experiments may be conducted using twisted pairs of copper wire and need not use stator windings. Small sample size analysis technique should be used with a sample size of 16.
(2) If the original and the newly added materials are chemically compatible, irradiation experi-ments should be conducted to verify the effects of radiation on this material combination.
These experiments should be conducted to a total dose of 108 rads with insulation resis-tance and voltage breakdown measurements made before and after irradiation. It is not necessary to make these measurements during irradiation. The experimental samples may be twisted pairs of wire. Small sample size analysis techniques should be used with a sample size of 16.
MATERIALS ANALYSIS DETAILS Literature Search The literature search was conducted in three steps:
(1) Search of the A lied Research index to obtain specific references and also to determine which technical journals contained papers about radiation and Class 1E motors.
Search of the yearly indexes of selected publications and journals.
(3) Interrogations of computerized databases.
Thre e extensive databases were searched through the services of Dialog Informa tion Services, Inc.:
(1) DOE ENERGY, the database of the United State Department of Energy, is one the world' largest sources of literature references, on all aspects of energy and related topics. DOE ENERGY provides coverage of journal articles, report literature, conference papers, books, patents, dissertations, and translations. The following energy topics are included: nuclear, wind, fossil, geothermal, tidal, and solar.
Related topics, such as environment, energy policy, and conservation are also included.
The EI ENGINEERING MEETINGS database covers significant published proceedings of engineer-ing and technical conferences, symposia, meetings, and colloquia. The file is produced by Engineering Information, Inc. EI ENGINEER-ING database covers all disciplines of engineering including civil engineering, environmental engineering, geological
r.
engineering, bioengineering, electrical engineering, electronics, control devices and principles, applied mathematics and physics, and more.
(3) The COMPENDEX database, produced by Engineering Information, Incus provides coverage of the world's significant engineering and technologi-cal literature. The database corresponds with the printed Engineering Index. Publications from around the world are indexed, including approximately 4,500 journals, publications of engineering societies and organizations, technical reports, monographs, and publications from approximately 2,000 conferences each year.
Summaries and abstracts of pertinent articles and papers located are contained in the final section of this report, "Literature Survey Summary."
Literature Surve Summar The information contained in this section substantiates the above conclusions and recommendations. Significant information contained in the material extracted from articles and reports, and from abstracts of articles and reports, is noted with an arrow ( ==> ) in the left margin.
The initial information search was performed using the ~Alied Research index under the following topics:
1985 and later:
Nuclear Power Plants Electrical Equipment 1984 and earlier:
Atomic Power Plants Auxiliaries
Pub 1 i cati ons Located:
IEEE Trans Energy Convers EPRI J I fEE Trans Power Appar Syst Eng N Resinous Products Insulating Materials Publications Located:
Electr Horld Hire J Int IEEE Trans Power Appar Syst Insulation, electric Publications Located:
EPRI J Power J Appl Phys IEEE Trans Energy Convers IEEE Trans Power Deliv Electric Motors Maintenance and Repair Publications Located:
IEEE Trans Ind Appl Electr Constr Maint Windings Electric Motors, AC Publications Located:
Electr Constr Maint Paint Publications Located:
Chem Ind Chem Eng J Coat Technol
The journals containing information specific to the Class 1E motor problem were:
IEEE Transactions on Power Apparatus and Systems IEEE Transactions on Electrical Insulation IEEE Transactions on Nuclear Science Information from IEEE Transactions The following articles from IEEE transactions were reviewed:
IEEE Transaction on Power Apparatus and Systems, Vol. PAS-102, No. 8, August 1983 SOME CONSIDERATIONS AND METHODS MHICH MAY BE USED TO QUALIFY EQUIPMENT IN A MILD ENVIRONMENT Perry L. Kline and J. Haratyk Bechtel Power Corporation 12400 E. Imperial Highway Norwalk, CA 90650 Abstract - This paper presents a definition of a so called "mild or non-harsh env>ronment", a method to qualify (Class 1E) equipment in this environment, and the reasons behind this approach.
Extracts The mild environment area is define as any area where the environmental parameters which are present when an accident occurs (LOCA, MSLB, or HELBA) show no significant difference from the environment experienced during normal/abnormal plant operations.
Class 1E mild environment qualification program should contain the follow considerations, criteria and constraints:
Supplier's documentation must clearly show that the equipment is capable of performing its Class 1E function in the postulated environmental and service conditions...
4- A surveillance and maintenance program should be in-itiated if item number three is not satisfactory. This jointly by program should be developed and implemented the owner and supplier .
In addition to industry experience, considerable analyti-cal data has been published concerning non-metallic materials and their susceptibility to time/temperature ef fects and radi ati on damage threshol ds. A starting point in developing surveillance test intervals would be to list all non-metallic materials, their properties of interest, and identify the weak link materials that are likely to suffer loss of the important material charac-teristics due to environmental influences.
'o The first step in performing a surveillance test is conduct a thorough visual inspection... The second step is to perform the specific test to measure the physical and operational parameter selected... The last step is to examine the test results and verify that all acceptance criteria have been achieved.
Emphasis should be directed toward the correct inter-pretation of any drift or change in the operating parameters or response time, together with the process and environmental conditions... measured during surveil-lance testing.
Industry standards may be used for guidance, but should not be considered to be acceptable as a total Class 1E equipment qualification program...
Reference
- 3. EPRI no. NP-2129-81 "Radiation Effects on Organic Materials in Nuclear Plants".
IEEE Transactions on Power Apparatus and Systems Vol. PAS-100, No. 12, December 1981 IEEE 323 QUALIFICATION EXPERIENCE B. M. Schutzbank and L. B. Tiscione Ebasco Services Inc.
New York N.Y.
Abstract - The purpose of this paper is to discuss several topics of concern regarding the qualification of Class 1E equipment for use in Nuclear Power Plants and to present experience'ained in establishing methodologies and/or guide-lines to streamline the qualification process.
10 Extracts In the absence of approved specific equipment standards, numerous equipment suppliers have attempted to satisfy thermal aging criteria by utilizing the 10 degree C rule (specifically for insulating systems). The acceptance of this analysis depends on the available state of the art, activation energy factors (expressed in eV) of component materials have not progressed sufficiently to allow for accuracy. The 10 degree C rule is only an ap-proximate method. A large error may results in obtaining a test temperature and duration if the activation energy is not constant throughout the tempera-ture range. An extreme degree of conservatism may also be imposed during testing so that the results appear more pessimistic, thus projecting a reduced qualified life.
The following aging analysis, based on IEEE 323-1974 and IEEE 101-1971, offers a comparison between the 10 degree C rule and an Arrhenius calculation based on a component material's activation energy...
The qualified life of the... material using the 10 degree C rule would be 1.269 years. However, based on the Arrhenius calculation using activation energy, the qualified life is 40 years.
IEEE Transactions on Power Apparatus and Systems Vol. PAS-102, No. 6, June 1983 SPECIFICATION FOR ENVIRONMENT QUALIFICATION OF CLASS 1E EQUIPMENT Newell S. Porter Washington Public Power Supply System Richland, Washington Abstract - One of the major challenges to obtain qualified Class IE equipment
~s t e adequacy of the specification. This paper presents the minimum requirements that must be considered in the preparation of specifications for Class lE equipment.
Extract In conclusion, a specification for Class 1E equipment should be written so that a supplier can provide qualified equipment...
11 IEEE Transactions on Power Apparatus Systems Vol. PAS-102, No. 6, June 1983 R. Coupland Wyle Laboratories Huntsville, Alabama A. Marion Baltimore Gas & Electric Company Baltimore, Maryland Abstract - This paper describes the first phase in the development of a Maintenance Management System which will be used to assure that the main-tenance necessary to ensure qualification of environmentally qualified, safety related equipment is performed. A review of the qualification documentation of a selected subset of the safety-related equipment was performed, and the information obtained was summarized.
Extract Incorporation of these recommendation into the maintenance system will ensure that the maintenance required for continued equipment qualification is identified.
IEEE Transactions on Nuclear Science, Vol. NS-26, No. 4, August 1979 DESIGNER'S GUIDE TO RADIATION EFFECT ON MATERIALS FOR USE ON JUPITER FLY-BYS AND ORBITERS Frank L. Bouquet and William E. Price Jet Propulsion Laboratory Pasadena, CA 91103 Donald M. Newell Ford Aerospace Palo Alto, CA 94303 Abstract - This paper summarizes the state-of-the-art of the complex field of
~ra sat>on effects on spacecraft materials. It is intended as a guide for designers of systems exposed to damaging electrons and protons. The emphasis is on the relative damage levels for the more common materials that may be used. Information on the preliminary flux and fluence levels of the yet to be designed Jupiter orbiter, Galileo, is also presented.
12 Extracts Or anic Materials as a class are highly susceptible to radiation damage via ionization, on breakage, free radical formation, and recombination. The class includes all plastics and elastomers in all function and forms such as adhesives, encapsulants, films, coatings, foams, and fabrics. These materi-als are most effected in their physical properties, usually becoming embrit-tled at relatively low dose.
Although the name of the material is unchanged, the actual chemical formula-tion could have been changed over the years. This is a particular danger with trade names.
[Structural and mechanical properties that change usually include thermal conductivity, which is closely related to electrical conductivity.]
General radiation sensitivity of Materials: Epoxies, si licones, phenolics, polyimides, fiberglass-epoxy, carbon and alloy steels, polystyrene, polyimide
-- 109 rads (Si).
Radiation stability of plastics, preferred class:
1- Phenolics, filled or reinforces, except paper filled 2- Epoxies, curing agents may be classified in the following order of decreasing tolerance: Anhydride > aromatic amine >
aliphatic amine > diethanolamine.
Radiation stability of plastics (estimated from a graph):
Approx Appreciably Threshold Altered Epoxies Polystyrene 9.9e9 1.2e10 Diallyl Phthalate Polyimide (Kapton) 9e9 Polyurethanes 8e8 3e9 Phenolics 1.5e7 4e8 Polyimide (Vespel) le7 6e7 Aramid (Kevlar)
Melamine Formaldehyde Polyester glass laminate PVC Coatin s and Films: The phenolics, silicone alkyd enamels, the alkyd and epoxy formu ations and styrenes are preferred.
13 Radiation stability of coatings and films:
Appreciably Altered Phenolic alkyd enamels le9 - le10 Silicone alkyd enamels le9 - le10 Alkyds and epoxy formulations le9 - le10 Polyurethane 1.5e8 - le9 Styrene 1.5e8 - le9 Acrylic IEEE Transaction on Electrical Insulation, Vol . EI-15, No. 4, August 1980 THERMAL AGING PREDICTIONS FROM AN ARRHENIUS PLOT WITH ONLY ONE DATA POINT Robert R. Di xon Westinghouse Electric Corporation Research and Development Center Pittsburgh, PA 15235 Abstract - Arrhenius plots are useful in predicting long-term use tempera-tures o7 organic materials and in choosing parameters for accelerated aging.
For materi al s and components wi thout estab i shed Arrhenius curves (whi ch i s 1
also a measure of the activation energy of degradation) would allow longer-term prediction from a few short-term tests. Conversely, a required long-term temperature target can be extrapolated on the same slope to a range of short-time exposure temperatures suitable for accelerates tests. A review is made of available activation energies, from which values can be selected for conservative 'extrapolations on an Arrhenius plot.
Extracts dR/dt = A exp(-E/kT) dR/dt is reduction in property with respect to time.
.is a constant.
is the gas constant or, depending up the units, the Boltzmann constant.
is the absolute temperature.
is the activation energy of the aging reaction.
14 Integration of the rate equation followed by taking of the logarithms results in ln t = (E/k) 1/T + B is a straight line known as an Arrhenius plot.
From an examination of a typical Arrhenius plot, it can be readily seen that if the slope is steep (high activation energy), long-life extrapolations degradation mechanism with reach relatively high temperatures. An undetected a lower activation energy would reduce the effective long-term temperature, with the conclusion that the prediction was optimistic. However, if the curve has a low slope, the chances of an even lower activation energy are minimal, and the projected life is a conservative value.
In place of establishing the Arrhenius line from a number of aging experi-ments, it has been proposed that the line could be established from one test point and an assumed slope. If the slope were selected to be very conserva-tive (low activation energy), then the performance of the material or part would be expected to exceed longer life (lower temperature) predictions.
The key to these approaches is the development of a method of selecting an Arrhenius slope which can be considered to be a conservative value.
... activation energies were determined from Arrhenius curves provided in a series of Westinghouse unpublished RED reports. Properties monitored for these materials included flexural strength, impact strength, dielectric strength, etc. The actual values calculated from 667 Arrhenius slopes are listed in Table l.
The number of materials in each increment of 0. 1 eY was plotted against activation energy...; the peak occurs about the same energy value [1. 1 eY, 23000 cal), but the number of materials below 0.5 eV is only 3 percent.
this distribution on log-normal, and 95 percent of the values exceed 0.61 eV.
The conservative slope selected was 0.5 eV.
15 TABLE 1. ACTIVATION ENERGIES FROM ARRHENIUS PLOTS Activation Ener Materials Measured Property K Ca Mo e eV Melamine-Glass (G-5) Dielect Strgth 6.7 0.29 Epoxy Varnish Dielect Strgth 10.9 0.48 Ester-Glass (GPO-3) flex Strgth 13.1 0.57 RTV Silicone Elongation 13.8 0.60 Phenolic-Asbestos Dielect Strgth 13.9 0.61 Nylon, GF Tensil Strgth 16.1 0.70 Acetal Tensil Strgth 16.8 0.74 Mineral Phenolic Flex Strgth 17.0 0.74 Silicone Varnish Dielect Strgth 17.0 0.74 Polypropylene Oxidation 18.7 0.81 Phenolic-Cotton Dielect Strgth 19.4 0.84 Phenolic-Alkyd Varnish Dielect Strgth 19.6 0.85 Epoxy Weight Loss 20.3 0.88 Epoxy Adhesive Shear Strgth 20.5 0.39 Nylon Impact Strgth 20.7 0.90 Pressboard Tensil Strgth 20.9 0.93 Imide Film Dielect Strgth 21.4 0.93 Silicone Dielect Strgth 21.6 0.94 Phenolic-Asbestos (A) Flex Strgth 21.7 0.94 Cast Epoxy Flex Strgth 22.6 0.98 Urethane-Nylon wire ins Dielect Strgth 22.9 0.99 Phenolic-Glass (G-3) Dielect Strgth 23.3 1.01 Polycarbonate Tens Imp 23.3 1.01 Phenolic-Paper Flex Strgth 23.6 1.02 Epoxy Wire Insulation Dielect Strgth 24.2 1.05 Epoxy-Glass (FR-4) Dielect Strgth 24.2 1.05 Varnish Cotton Dielect Strgth 24.4 1.08 PVC Elongation 24.9 1.08 Ester-Glass (GPO-1) Flex Strgth 25.0 1.09 Phenolic-Cellulose Flex Strgth 25.4 1.10 Polyethylene, crs-lnkd Dielect Strgth 25.6 1.11 Urethane Dielect Strgth 25.8 1.12 Ester-Glass (GPO-2) Dielect Strgth 26.0 1.13 Ester + Nylon wire ins Dielect Strgth 26.1 1.14 Ester-Glass (GPO-1) Dielect Strgth 26.6 1.16 Phen-Alkyd Varnish Dielect Strgth 26.6 1.16 Yule Fiber Dielect Strgth 26.8 1.16 Phenolic-Cell + Min Impact Strgth 26.9 1.17 Polyester Film Dielect Strgth 27.1 1.18 Cast Epoxy Impact Strgth 27.2 1.18 Alkyd Varnish Dielect Strgth 27.2 1.18
16 TABLE 1. ACTIVATION ENERGIES FROM ARRHENIUS PLOTS (Continued)
Activation Ener Materials Measured Property K Ca Mo e eV Epoxy Weight Loss 27.2 1.18 Silicone Dielect Strgth 27.2 1.18 Phenolic Paper (XX) Flex Strgth 27.5 1.20 Yule Fiber Flex Strgth 27.7 1.21 Phenoli c-Ce 1 1 ul ose Impact Strgth 28.5 1.24 Phenolic-Gl ass (G-3) Flex Strgth 28.5 1.24 Phenolic-Kraft Flex Strgth 28.8 1.25 Neoprene Elongation 29.0 1.26 Amide-Imide Varnish Dielect Strgth 30.0 1.31 Ester Anaerobic Shear Strgth 31.7 1.38 Acetylated Cotton Tensil Strgth 32.0 1.39 Silicone-Asbestos Dielect Strgth 32.5 1.41 Epoxy-Glass (FR-4) Flex Strgth 34.4 1.50 Polyester Film Brittle 36.3 1.58 Nylon Paper Dielect Strgth 36.6 1.59 Ester-Amide-Imide Yarn Dielect Strgth 36.6 1.59 Epoxy-Glass (G-11) Flex Strgth 37.6 1.64 Polyester Wire Insula Dielect Strgth 37.7 1.64 Kraft Paper Burst Strgth 38.5 1.67 Polyester, TP Tensil Strgth 40.3 1.75 Varnished Kraft Dielect Strgth 42.7 1.86 Nylon Paper Elongation 43.9 1.19 Ester-Glass (GPO-3) Dielect Strgth 46.7 2.03 Phenolic-Cotton Flex Strgth 48.8 2.12 Melamine-Glass Flex Strgth 50.1 2.18
17 IEEE Transactions on Electrical Insulation, Vol. EI-16, No. 1, February 1981 THEORY OF EQUALIZATION OF THERMAL AGEING PROCESSES OF ELECTRICAL INSULATING MATERIALS IN THERMAL ENDURANCE TEST III. TEST RESULTS ON AN ENAMELLED WIRE, A POLYESTER GLASS LAMINATE AND AN EPOXY CASTING RESIN Paavo Paloniemi Oy Stromberg Ab Helsinki, Finland Paul Linstrom Technical Research Center Espoo, Finland Abstract - Comparative test results are presented on polyester-imide coated copper wires, a polyester glass mat laminate, and a heterocyclic epoxy resin.
Tests have been performed according to the application principles of the EAP theory, described in Paper II of this series. Results of test show that the ageing behavior of these materials is well predictable on the basis of EAP tests, and in every case better than the prediction based on conventional test results, whenever a reliable comparison could be made. With the exception of one insignificant deviation, all the material behaved according to the EAP principles developed in the theoretical Pape'r II of this series.
The results described here and those published earlier can be taken as the proof of reliability of the EAP method for thermal endurance testing of electrical insulating materials.
IEEE Transactions on Electrical Insulation, Vol. EI-17, No. 4, August 1982 RADIATION-INDUCED CONDUCTIVITY IN POLYMERIC INSULATING MATERIALS DEGRADED UNDER SPECIFIED CONDITIONS Yoshiaki Nakase and Isamu Kuriyama Japan Atomic .Energy Research Institute Tohru Takahashi and Setsuya Isshiki
-The Fujikura Cable Works Ltd.
Abstract - Various polympric insulating materials for cables were degraded by
~s>mo ated irradiation and environmental conditions for normal operating and under accident at a nuclear power reactor. Thermally stimulated currents
=-
were observed only in the crystalline samples, and the higher the crystal-
18 linity, the large the amounts of detrapped carriers. The change of fine structure of the degraded sample was investigated by the change of X-ray crystallinity, melting behavior, and glass transition temperature. The radiation induced conductivity was studied during irradiation and a decay curve was measured after the irradiation. Analysis of the conductivity decay curve enables us to detect at most four kinds of carriers with different time constants. Long-lived carriers were hardly observed in the non-crystalline samples, while many were seen in the crystalline samples. With the decrease of crystallinity by degradation, only short-lived carriers were observed, indicating the existence of trapping sites for the long-lived carriers in or around the polymer crystallites. Treatment of samples with high temperature steam and chemicals showed no special effect on the samples except for polyimide which dissolved in alkaline solution.
Other Re orts EPRI NP-2129 Project 1707-3 Final Reports, November 1981 RADIATION EFFECTS ON ORGANIC MATERIALS IN NUCLEAR PLANTS M.B. Bruce and M.V. Davis Georgia Institute of Technology Nuclear Engineering Department Atlanta, Georgia 30332 Pro'ect Descri tion - Equipment in nuclear plants must be qualified to per orm sa ety-re ated functions after long periods of exposure to low-level radiation during operation and after short periods of high-level radiation during accidents postulated for design... This report by the Georgia Institute of Technology presents the results of a literature search for data concerning the radiation resistance of organic materials.
Pro'ect Results - The report includes an overview of radiation effects and an extensive ist of organic materials in order of increasing resistance to radiation damage. An important finding is that a total dose of less the le5 rads produces no significant degradation of mechanical or electrical proper-ties. (Notable exceptions are equipment that contain Teflon or semiconductor devices). Also, at this level, no significant synergistic effects of radiation combined with other environmental stresses, such as elevated temperatures, were identified. The results of this work will be of interest to utility engineers, architect-engineers, equipment manufacturers, and regulatory staff involved in the qualification of equipment for radiation effects.
Abstract - A literature search was conducted to identify information useful in inetermining the lowest level at which radiation causes damage to nuclear
19 plant equipment. Information was sought concerning synergistic effects of radiation and other environmental stresses.
Organic polymers are often identified as the weak elements in equipment.
Data on radiation effects are summarized for 50 generic name plastics and 16 elastomers. Coating, lubricants, and adhesives are treated separately.
Inorganic and metallic are considered briefly. With a few noted exceptions, these are more radiation resistant than organic materials.
Some semiconductor devices and electronic assemblies are extremely sensitive to radiation. Any damage threshold including these would be too low to be of practical value. With that exception, equipment exposed to less than le4 rads should not be significantly affected. Equipment containing no Teflon should not be significantly affects by le5 rads.
Data concerning synergistic effects and radiation sensitization are dis-cussed. The authors suggest correlations between the two effects.
Extracts Specifically, little threshold information is available for complete com-ponent/equipment items. . . many equipment items function acceptably with degraded materials.
Organic polymers are most often identified as the weak element(s) in opera-ting equipment and so as a group were selected for detail study.
Inorganics and metallic are generally little affected by radiation environ-ments that cause considerable degradation in organic materials. Important exceptions are identified in Section 2 .
Reference 44 presents the following generalized statements drawn from a number of sources:
- 1. Pigmented coatings are more resistant to radiation than those containing little or no pigments. Carbon black inhibits damage, while some grades of titanium dioxide accelerate damage. Extender pigments appear to contribute to color change.
- 2. Realistic comparisons of different coating systems can be made only if the same pigment compositions are used in all vehicles.
- 3. The choice of primer is important when a costing to be subjected to radiation is applied to metal substrates.
20
- 4. The degree of cure for any specific system can influence apparent radiation resistance.
- 5. Residual solvents can influence radiation resistance.
- 6. To a point, gamma radiation (and Heat) initially improves the physical properties of many organic coatings. Exposure to radiation beyond a given point tends to excessively crosslink and/or degrade organic coatings. This leads to coating embrittlement which develops into failure. For epoxies applied to steel,
'ailure usually occurs at the metal-coating interface.
... many coating systems are not greatly affected by radiation exposures below le8 rads.
Privileged Communications (N8472N0928)
Extracts Since some confusion appears to exist in the nomenclature used in the insulation field, the following definitions are used ...
Ename1 is the coating app1ied direct1y to a bare copper wire to yieie magnet wire.
Varnish is the material used for wet-winding or dipping coils, to
~oint>e individual turns of the coil in place.
Im re nant is the compound used in conjunction with fabric tapes to orm a protective coat over the entire coil.
Cement is an adhesive compound used to hold the completed coil in proper position in the motor.
Resin is the organic polymer solid used in enamels, varnishes, f~
impregnants, and cements.
It is accepted by the insulation industry that not all varnishes are "com-patible" with any given magnet wire, or with each other. Insulation is 1 f 1 1 d 1 . b1 1 react to so ten or craze ename s.
A burn-out testin device was utilized to determine compatibility of materi-a s sn the potting compound formulation. This burn-out testing device is similar to that described by W. G. Stiffler in his paper "A Motor
21 Manufacturer Evaluation of Electrical Insulating Materials", given at the 6th Electrical Insulation Conference in 1965...
The test comprises preparing a twisted pair of 20 gage polyester-polyamide-imide round enamels wire (producing 10 twists per 5 inches as outlined in the standard test methods - ASTM-325l) while applying a 1000 gram tension load on the wire during twisting. The twisted pairs are then dip coated in the selected pottant formulation or brush coated to give a completely and evenly coated wire finish. The pairs are cured at the recommended schedule after which the coated wire ends are stripped and the pairs evaluated to failure in the burn-out apparatus... An apparatus was designed and built at Battelle that applied independently contr'oiled a-c current of 40 amperes to each wire of a twisted pair. A potential of 120 volts (a-c) is applied across the twisted pair to indicate failure. The twisted pair is enclosed in a Plexiglass cover to remove the influence of air currents and maintain temperature uniformity. Measurements of the surface temperature of the twisted pair carrying 40 amperes in each wire showed that 400 C was being obtained with this apparatus.
It is felt that the test simulates better than any other method available the conditions that might be expected from serious overloads. It also appears in light of the data being obtained on varnished and unvarnished twisted pairs, that the method is of value in determining system compatibility of insulation components.
RADIATION EFFECTS ON ORGANIC MATERIALS Edited by Robert 0. Bolt and James G. Carroll California Research Corporation Richmond, California Academic Press, 1963 CHAPTER 12 -- COATINGS AND FILMS By James G. Carroll and Robert 0. Bolt The data presented in this chapter (summarized in the following tables) indicate that significant damage occurs to materials of interest at least one order of magnitude of radiation dose above the generally accepted qualifica-tion level of Ie7 rads.
22 TABLE 12.2. RELATIVE STABILITY OF ORGANIC COATING Approx Max Gamma Coating radiation resistance Phenolic (phenol-formaldehyde) 44 x 108 Silicone-alkyd enamel 9 to 44 x 108 Alkyd enamels:
40% phthalic anhydride 9 to 44 x 108 32~ phthalic anhydride 6 to 9 x 108 Epoxy 4 to 9 x 108 Fluorinated vinyl 4 to 9 x 108 Nitrocellulose (white lacquer) 4 to 6 x 108 (page 450)
==>"After 9 x 108 rads and 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> at 500 F, the phenolic coatings retained their properties better than any of the other coatings tested. They had good abrasion resistance and adhesion and were little affected by exposure to
~
100 percent relative humidity for 28 days at 120 F. Silicone-alkyd enamel actually showed improved properties at 9 x 108 rads but became
~ ~
==> powdery and brittle at 44 x 10~ rads."~ (page 451)
"Similar paint films with and without various pigments were exposed on aluminum panels to 1.5 x 107 rads of gamma radiation... Regardless of the pigmentation the paints all behaved as expect from the stability of the bass coatings; i.e. pigments exerted little effect at this low dose." (page 451)
TABLE 12.3. THE RADIOLYSIS OF MOUNTED PROTECTIVE COATINGSa Gamma dose Polymer base Trade name Surface (air) 108 rads Appearancea Furan Alkaloy-550b Concrete 9.4 No failure Steel rod 8.4 No failure Modified Amphesive-801b Concrete 9.4 No failure phenolic Steel rod 8.7 Drastically embrittled Silicone alkyd Solar Siliconec Concrete 6.7 No failure Steel 6.7 No failure Epoxy Epon-395d Steel 6.7 No failure Vinyl chloride Amercoat-33e Aluminum 2.1 Failed, blistered Concrete 10.5 Failed, blistered Steel 8.7 Failed, blistered Styrene Prufcoatf Concrete 8.7 Failed, brittle Steel 8.7 Failed, cracked Steel (wet) 0.8 Failed, cracked Vinyl Corrosite-229 Aluminum 2.1 Failed, blistered Concrete 11.0 Borderline failure Examined for blisters, cracking, hardening, tackiness, etc. (page 452)
Atlas Mineral Products Co.
Solar Division, Gamble Skogmo, Inc.
The Glidden Co.
Amercoat Corp.
Prufcoat Laboratories, Inc.
9 Corrosite Corp.
24 RADIATION EFFECTS ON ORGANIC MATERIALS Edited by Robert 0. Bolt and James G. Carroll California Research Corporation Richmond, California Academic Press, 1963 Chapter 13 DIELECTRIC FLUIDS By Raymond S. Alger Approximate tolerance of dielectric materials to static irradiation (25 percent change). The following data were taken from Figure 13. 1, page 462.
Teflon 1 x 105 rads Lucite 9 x 105 rads Hater 9 x 106 rads Tri chl orobenzene 7 x 106 rads Silicone oil 2 x 107 rads Natural rubber 3 x 106 rads Po1yethy1 ene 2 x 107 rads Transformer oil 6 x 107 rads Polystyrene 9 x 108 rads Caster oil 1 x 108 rads Ceramics 8 x 1010 rads RADIATION EFFECTS ON ORGANIC MATERIALS James G. Carroll and Robert 0. Bolt California Research Corporation Richmond, California Nucleonics, Vol. 18, No. 9, September 1960, pp. 78-83 "Radiation does not change all properties of an organic material to the same degree. Thus, the critical property must be specified in considering useful life of a materials."
25 TABLE 2. RADIATION STABILITY OF PLASTICS Threshold dose for 25~ changea Materials (10B rads)
Polystyrene> 40 Phenol formaldehyde (asbestos filler)1 40 Polyester (mineral fi 1 1er) 1 4 Polyvinyl chloride2 1 Polyethyl ene1 0.9 Urea formaldehyde> 0.5 Monochlorotrifluorethylene2 0.2 Cellulose acetate2 0.2 Phenol formaldehyde (unfilled) 1 0.1 Methyl methacrylate2 0.01 Polyester (unfi1 led) 1 0.01 Polytetrafluoroethyl ene (Teflon) 2 0.01 Based on most 'sensitive property, usually tensile strength Crosslinks Scissions SIMULATED AND SIMULTANEOUS LOSS-OF-COOLANT ACCIDENT TESTING OF PROTECTIVE COATINGS FOR THE NUCLEAR INDUSTRY W. F. Oberbeck, Jr., K. G. Mayhan, and D. R. Edwards University of Missouri-Rolla Graduate Center for Materials Research, Rolla, Missouri 65401 J. R. Lopata, J. F. Montle, and D. R. Leritz Carboline Company 350 Hanley Industry Court St. Louis, Missouri 63144 "Results from the simultaneous exposure of coatings to high-pressure steam and radiation are compared to results obtained from the conventional simu-lated test procedures... Included zinc-based, epoxy, and phenolic primers with phenolic and modified phenolic topcoats. Coatings were exposed to 60 Co radiation dose in the range of 10B to 109 rad. The study showed that the conventional simulated LOCA conditions were more severe on the coatings than those tested under simultaneous exposure to high pressure steam and 6~ Co
26
==> radiation. It was concluded that coatings that satisfactorily passed the simulated LOCA tests will also pass the simultaneous LOCA tests."
"The following general statements, which are based on reported data and results concerning radiation resistance, can be used as reference points:
I- Pigmented coatings are more resistant to radiation than those containing little or no pigments. Carbon black inhibits damage while some grades of titanium dioxide accelerate damage. Extender pigments appear to contribute to color change.
2- Realistic comparisons of different coating systems can be made only if the same pigment compositions are used for all vehicles.
3- The choice of primer is important when a coating to be subjected to radiation is applied to metal substrates.
- 4- The degree of cure for any specific system can influence radiation resistance.
5- Residual solvents can influence radiation resistance.
6- To a point, gamma radiation (and heat) initially improves the physical properties of many organic coatings. Exposure to radiation beyond a given point tends to excessively crosslink and/or degrade organic coatings. This leads to containing embrittlement which develops into failure. For epoxies applied to steel, failure usually occurs at the metal-coating interface."
"In general, the onset of coating deterioration was noted at radiation dose of 108 to 10g rads in water."
27 TABLE I I I. APPROXIMATE RADIATION LIMITS OF POLYMER VEHICLES In Air In Water Vehicle (rad) (rad)
Phenolic 3 x 109 to 1 x,1010 2 x 109 to 8 x 109 Epoxy 3 x 109 to 1 X 1010 8 x 108 to 2 x 109 Alkyl-alkali 1010 109 silicates THE EFFECT OF NUCLEAR RADIATION ON THE ELECTRICAL PROPERTIES OF EPOXY RESINS Marcel Van de Voorde Organisation Europeane Pour La Recherche Nucleaire, CERN European Organization for Nuclear Research, CERN 68-13, Intersecting Storage Rings Division, April 17,,1968.
"The electrical properties which determine an insulator's behavior and which are studied in this paper include:
a) The dielectric stren th, which determines the maximum electric se w hach can be supported without failure; b) the electrical conductivit , which indicates the ease of charge transport; c) the dielectric constant, which shows the degree of polarszatson; d) the loss tan ent, which indicates the rate of energy lost to energy store in the dielectric.
All these properties depend on:
- 1) the chemical structure, crystallinity, crosslinks density;
28
- 2) the number of free charge carriers, their mobility and their ability to transfer energy to the surrounding molecules;
- 3) the polarizable species i.e. molecules with a permanent dipole moment and the orientation of the polar groups;
- 4) the number and energy distribution of electron-trapping sites."
"Transient phenomena can materially alter the electrical properties of a polymer during irradiation. One of the most striking transient changes is the enhancement of the electrical conductivity of the polymer. The conduc-tivity of epoxy resins, for example, increases as much as four orders of magnitude in a strong nuclear field."
"Irradiation conditions The irradiations were performed in the water reflector of the ASTRA-reactor at Seibersdorf (Austria). This radiation facility produces mainly gammas.
The dose rate corresponds to approximately 7 rad/hr with a reactor power of 5 M. Watt and an ionization chamber is used as dosimeter.
In all cases, test samples were irradiated in demineralized water at about 30 C. The absorption of water during irradiation is between 0.5 and 2.5 per cent for samples with dimensions 150 x 150 x 2 mm3. Before measuring the electrical properties the unirradiated and irradiated samples were dried under vacuum (10-2 torr) at 40 C during 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />."
"Dielectric Stren th
- 2) All the new epoxy resin systems... still give 90 percent of their initial value at 1 x 109 rad.
Surface resistivit
- 1) The surface resistivity of the epoxy resins studied is approximately 1 x 1013 ohm for hot cured and 1 x 1012 ohm for the system cured at room temperature.
- 2) Small changes are noted up to 1 x 10 9 rad for the four studied systems.
29 Volume resistivit
- 2) The volume resistivity at room temperature of unirradiated epoxy resins is of the order of 10<6 ohm cm.
- 3) ~ ~ ~
Practically no changes are noted at 1 x 109 rad and room temperature.
~ ~ ~
Dielectric constant and dissi ation factor
- 3) 'The dielectric constant and dissipation factor measured at room temperature and at 50 Hz are relatively insensitive to radiation over a wide range of doses for most of the systems studied.
General conclusions 4)'ll with resins, containing an aromatic amine a high aromatic content and cured or anhydride gave good radiation resistant materials."
RADIATION EFFECTS IN ORGANIC MATERIALS A. Charlesby Royal Military College of Science Shrivenham - Swindon, Wi ltshire C. DuPuy, Editor Noordhoff-Leyton (1975)
"~Cd During irradiation the current is approximately proportional to the applied field and varies with the radiation intensity I, usually following an IO 8 power dependence. This is difficult to explain in simple terms...
30 The post radiation current decreases approximately as (t+a)-1 (t is time after cessation of radiation). This time dependence is likewise difficult to account for on any simple theory."
HANDBOOK ON EPOXY RESINS Henry Lee and Kris Neville McGraw-Hill Book Company Radiation Resistance, pp. 6-42 to 6-44 "Tests conducted to determine the effects of the various types of irradiation indicate:
- 1. Thermal neutrons ...
- 2. Fast neutrons ...
- 3. If the environment may react with the irradiated sample, the dosage rate becomes important. For example, electron radiation may produce free radicals at a greater rate than oxygen can diffuse into sample thereby causing cross-linking reactions to predominate. In the case of gamma and pile irradiations, free-radical production is sufficiently low to allow the diffusion of oxygen to influence the degradative process, causing shortening and inhibition of cross-linking.
Because of the interdependency of dosage rate and environ-ment, aging studies in atmosphere under high dosage to obtain accelerated data may not adequately define the performance under actual service conditions.
... In general, the more heat-resistance the epoxy compound, the more irradiation-resistant it will be.
With regard to chemical resistance after radiation, it has been found that the number of decontaminations an epoxy-resin coating can withstand without degradation is not effected by doses below 107 rads. Above this dosage the useful life is reduced to two cycles.
31 RADIATION EFFECTS DESIGN HANDBOOK SECTION 3. ELECTRICAL INSULATING MATERIALS AND CAPACITORS C. L. Hanks and D. J. Hamman Radiation Effects Information Center Battelle Memorial Institute July 1971 The follow gamma doses produce incipient to mild damage with the materials.
nearly always usable (from Figure 3, page 9).
Materi al s Dose Phenolic, glass laminate 4 x 109 Phenolic, asbestos filled 1.5 x 109 Phenolic, unfilled 2 x 106 Epoxy, aromatic-type curing agent 1.2 x 109 Polyurethane 9 x 108 Polyester, glass filled 9 x 108 Olyester, mineral filled 8 x 107 Diallyl Ohthalate, mineral filled 9 x 107 Polyester, unfilled 3 x 105 Myl ar 3 x 106 Silicone, glass filled 8 x 108 Silicone, mineral filled 8 x 108 Silicone, unfilled 1 x 108 Melamine-formaldehyde 7 x 106 Urea-formaldehyde 2 x 106 Aniline-formaldehyde 6 x 105 Polystyrene 7 x 105 Acrylonitrile/butadiene/styrene (ABS) 1 x 108 Polyimde 2 x 108 Polyvinyl chloride 1.5 x 107 Po 1 yehyl ene 1.5 x 107 '
Polyvinyl formal 1 x 107 Polyvinylidene chloride x 106 Polycarbonate 2 x 106 Kel-F Polytrifluorochlorethylene 1 x 106 Polyvinyl butral 3 x 106 Cellulose acetate 1.2 x 106 Polymethyl methacrylate 8 x 105 Polyamide 7 x 105 Vinyl chloride-acetate 1 x 106 Teflon (TFE) 1 x 104 Teflon (FEP) 1 x 105 Natural rubber 1.2 x 106 Styrene-butadiene 1.2' 106 Neoprene rubber 1.2 x 106 Silicone rubber 1 x 106 Polypropylene 2 x 106 Polyvinylidene fluoride (Kynar 400) 8 x 106
32 Degradation of the electrical properties of ol eth lenetere hthalate '[at]
==>'106 to 107 rads, is insignificant (p 20).
Pol amide n ion film changes in both physical and electrical properties ...
with thresho d damage at a dose of 8.6 x 105 rads and 25 percent damage at 4.7 x 106 rads (p 21).
The permanent degradation or change in electrical properties ... [of]
1 8 d 22.8 d8.1 188 df I ff1<<l practical significance (p 22).
f~lh nificant I II I permanent changes d<
- based composites after an absorbed does of 10,000 Mrads. [1010 rads] "
34 1298318,53 EFFECTS OF ENERGETIC PROTON BOMBARDMENT ON POLYMERIC MATERIALS: EXPERIMENTAL STUDIES AND DEGRADATION MODELS D. R. Coulter, A. Gupta, M. V. Smith, R. E. Fores Jet Propulsion Laboratory report, 1986 No numeric data available in abstract.
1289765,61 STUDIES ON RADIATION RESISTANCE OF FIBER REINFORCED PLASTIC COMPOSITES FEATURE BY EASINESS OF MANUFACTURING.
- 1. DEGRADATION BEHAVIOR UNDER ELECTRON IRRADIATION AT ROOM TEMPERATURE Akir Udagawa, Miyuki Hagiwara, Shunichi Kawanishi Japan Atomic Energy Research Inst., Tokyo, 1986
- g. 7S~/~Ca'g 7S 3 mine o8'w min. Qs x-yoA.
- Job No.
- Job No.
Dear Mr. Anderson:
Enclosed please find data taken on your Westinghouse 4 KY, 60 Hz, 3 Phase, 400 HP motor 3S71. These data are heat runs and polarization index before and after irradiation.
Also please notice photos taken of damaged crate as received from Isomedix. We inspected motor and bearings and found no apparent damage. Crate is repaired and motor is ready to ship. Waiting for shipping instructions.
Note: Motor shaft shows evidence that a pipe wrench may have been used to turn the rotor. This was not done by Reliance.
Thank you.
Ed Santavlcca Lab Manager ES/Jw enclosure
4$ (4~~t-
~ () ,(,'~ I (-=S. I REL IA NCE EL EC TRIC 0 24701 Euclid Avenue, Cleveland, Ohio 44117 REPORT OF TEST For Induction Motor Purchasers Date of Test INDIANA 8( MICHIGAN ELECTRIC Order No. 03009-040-8N Serial No. 3S71 Nameplate Rating Rated Service Ratod Speed Phase Frequenoy Volts Amporos Typo Framo HP Factor r Iml n Hz 400 1. 15 3564 60 4000 52 509US Temperature Rise Conditions of Test Temperature Rise '0 Stator Rotor Wlndlngs Wlndlngs By By By Cooling Hours Line Line Alr. RES.
Run Volts Amperes c Mothod Method Method 3.5 4280 52.5 25.0 50.0 C 2-13-89 ( 1 )
3.0 4260 52.7 24.0 50.9 C 4-05-89 (2)
Characteristics No-Load Line Secondary Volts Socondary Amperes per Resistance at 25OC Rated Slip. Peroent Curront. amperos at Standstill Ring at Rated Load (between lines) ohms (1) .777 23 ~ 1 N/A N/A Pr lml (2) .777 22.7 N/A N/A N/A Tor ue and Starting Current High Potential Tests Break-Down Torque Locked-Rotor Torque Starting Current Volts a-c LB.-FT. E ~ LB.-FT. ~ ~ Amporos (locked rotor) for Soc with~ volts applied with~ volts appllod with~ volts applied Stator Rotor N/A Eff Iclencles and Power Factor Efflolency. Percent Power Faotor, Percent Rated Load 75 Peroent Load 50 Percent Load Rated Load 75 Peroent Load 50 Percent Load 96.2/96.2 79.9/80.0 Notess (1) BEFORE (2) AFTER IRRADIATION Data from test o motor.
this or duplicate)
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Page No. 11 Test Report No. 40053-02 Revision A 4.0
SUMMARY
(Continued)
This report contains two sections.Section I presents the data recorded during the Receiving/Visual Inspection, Radiation Exposure, and Post-Test Inspection.
Section II presents the Wyle Laboratories'est Procedure No. 40053-01, Revision B, used to perform the test program.
The test program was performed in the sequence indicated in the previous paragraph and as specified in the Test Procedure. During the irradiation period, the test specimen showed no indication of degradation or damage. The insulation resistance values, recorded before, during, and after the exposure period, showed no appreciable difference in levels such as to indicate degradation. The test specimen is therefore considered to have met the acceptance criteria specified for the radiation exposure.
5.0 REFERENCES
5.1 American Electric Power Service Corporation Purchase Order Number 03010-040-8N dated May 12, 1988.
5.2 'tVyle Laboratories'uality Assurance Program Manual, June 1988.
S.3 SVyle Laboratories'est Procedure No. 40053-,01, Revision B.
5.4 10 CFR 50.49, "Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants," U. S. Nuclear Regulatory Commission.
Regulatory Guide 1.89, Revision 1, June 1984, "Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants," U. S.
Nuclear Regulatory Commission.
5.6 IEEE 323-1974, "IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Stations."
6.0 EQUIPMENT DESCRIPTION The 400 Horsepower AC Motor, manufactured by westinghouse Company, was determined to have identification information as follows:
400 HP, 3-phase, 60 Hertz 4000VAC, 52 Amps, 3564 RPM Model ABDP Frame 509US Service Factor 1.15 S ¹ 70F70184 Ser. 3S-71 WYLE LABORATORIES Huntsville Fecillty
IttliEQ Ntrctaar Ertrlronrnarrtal Otratlftaattart t
Test Report REPORT NO. 40053-02 WYLE JOB NO.
CUSTOMER 03010-040-8N P. 0. NO.
PAGE i OF 21 PAGE REPORT March 20, 1989 SPEClFiCATiON <S) See References in Para raph 5.0 of this Summarv Secti n 1.0 CUSTOMER American Electric Power Service Corporation AEPSC 1 Riverside Plaza, Columbus, Ohio 43215 00 Horsepower, 3-Phase, AC Motor 3.0 MANUFACTURER 4.0
SUMMARY
The 400 Horsepower AC Motor, as described in Paragraph 6.0, was subjected to the Radiation Exposure Test as specified by AEPSC. The test specimen described herein was provided by, and is typical of, installations at Indiana Michigan Power Company.
This test program was performed to verify the ability of the. test specimen to maintain integrity during radiation exposure. The test report was prepared in accordance with the documentation requirements of IEEE 323-1974, "IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Stations."
trrrla artatl tea rto aattarttr l(tr ataltaoaa or arrr ttrrttt to rrlfaart or Ixcrrrrttr, rrcttrrartc attaclat or STATE oP ALABAMA t Alabama Professional crtrtaarttrartaat arttaeaa raatattllg ttrarrl ~'$ aliLttla aatrcaa cprtrad trr trtrt raport.
coUNTYoPM olsoN I 'ngineer Reg. No. 7948 PREPARED BY Frederick N. Sittason being duly sworn, R. T. Wa deposes and says: The information contained in this report is the result of complete and carefully conducted ts and is to the best of his k led true and correct In APPROVED BY all r pects. F. R. J I wYLaa.a. l d ~wm to b fore day of ,19 SUBSCR this G. W. Hi ht Notary Pu c in and for the State of Alabama at large My Commission expires LABORATORIES SCIENTIFIC SERVICES & SYSTEMS GROUP HUNTSVILLE. ALABAMA
Page Ão. 11-3 Test Report iNo. 40053-02 Test Procedure No. 40053-01 Page No. 2 Revision A 2.0 TEST REQUIREltIEitiTS Acceptance Criteria I
The test specimen shall demonstrate electrical intergrity during the radiation exposure test. Leakage current to ground, monitored before, during, and/or after radiation exposure, shall be addressed by thc Customer.
3.0 TEST PROGRAM'I 3.1 Receiving/Visual Inspection Upon delivery at the radiation test facility, the test specimen shall be subjected to an inspection in order to verify size, model, manul'acturer, and any other pertinent data with respect to the equipment to bc tested. All observations and recorded information shall be printed on a Test Specimen Inspection Sheet for inclusion into the test report.
3t Radiation Exposure The test specimen shall be placed in a hot cell and subjected to a total integrated dose of 10E6 rads gamma, air equivalent, at a dose rate not to exceed 1.0E6 rads/hour.
3.2.1 Insulation Resistance Test Prior to initiation of the radiation exposure test, the three-phase motor leads shall be connected together and attached to a DC insulation resistance measurement test unit. Insulation resistance measurements shall be conducted by applying 1000VDC for 1 minute prior to the reading of the resistance between the motor phases (connected together) and the frame (ground). The recorded insulation resistance measurements shall be plotted versus time and included in the test report. The insulation resistance of the specimen windings to ground shall be monitored and recorded prior to initiation of the radiation exposure period. The insulation resistance of the specimen windings shall be monitored" and recorded, during the period of radiation exposure, at approximately every four hours. Upon completion of the radiation exposure, the insulation resistance of the specimen windings shall be monitored and recorded and the test unit de-energized.
3.3 Post-Test Inspection The test specimen shall be visually inspected. The specimen shall be disassembled (i.e., removal of inspection covers) to the extent necessary to perform the inspection. The condition of the specimen shall be recorded.
Photographs shall be taken of any noticeable physical damage which may occur.
WYLE LABORATORIES Huntsville Facility
Page No. II-4 Tes t Re por t No. 40053-02 Test Procedure No. 40053-01 Page No. 3 Revision B Quality Assurance All test equipment and instrumentation to be utilized in the performance of this test program shall be calibrated in accordance with )Vyle Laboratories Quality Assurance Program Manual, which conforms to the applicable portions of ANSI N 45 2, 10 CFR 50 Appendix B, and Military Specification MIL-STD-45662A. Standards utilized in the performance of all calibrations arc B traceable to the National Bureau of Standards.
3+5 Report A let ter test report shall be issued, describing the test requirements, procedures, and results. The report shall bc prepared in accordance with IEKE Standard 323-1974.
WYLE LABORATORIES Huntsville Faclllty
Page ND. II-I Test RePort No. 40053-02 TEST PROCEDURE 4a P~ RRI SCIENTIPC 5EAYCES TEST PROCEDURE NO.
VV T Lees d SYSTEMS T
EASOAATOAIES GAOOA A 0 BOR l008, HuntSvill~, AL 55501 DATES JulY 18, 1988 TWX 1910) 9914885, Phone t2051 851 8411 REVISION A 08-08-88 REVISION B 03-20-89 RADIATION EXPOSURE TEST PROGRAM FOR A iVESTINGHOUSE 400HP iAEIOTOR FOR AIiIERICAN ELECTRIC POPOVER SERVICE 0 APPROVED RY PROJECT MANAGER'PPROVED QUALITYENGINEER:
BY ~ i I
'~/
PREPARED BY PROJECT ENGINEER: O8 Q -EIst REVISIONS FORM 1054-1 Rev. 4/74 REV. NO. DATE PAGES AFFECTED BY APP'L. DESCRIPTION OF CHANGES 8/08/88 Pae2 Revise method of monitorin and specimen degradation during
'Qf>>~ radiation exposure 3/20/89 Page 3 RTN t,iri O I
~ ~ Incoroorate revision to Nilitar Specification NIL-STD-45662 COPYRIGHT BY WYLE LABORATORIES. THE RIGHT TO REPRODUCE, COPY, EXHIBIT, OR OTHERWISE UTILIZE ANY OF THE MATERIAL CONTAINED HEREIN WITHOUT THE EXPRESS PRIOR PERMISSION OF WYLE LABORATORIES IS PROHIBITED. THE ACCEPTANCE OF A PURCHASE ORDER IN CONNECTION WITH
~ HE MATERIAL CONTAINED HEREIN SHALL BE EQUIVALENT TO EXPRESS PRIOR PERMISSION.
Page No II-~
Test Report iNo. 40053-0'est Procedure iNo. 40053-01 Page No. 1 SCOPE This document has been prepared by Wyle Laboratories 1'r testing of a =
Westinghouse motor, as further identified in Paragraph 1.3, lor use by Indiana iVIichigan Power Company.
Purpose The purpose of this document is to present the test procedure for subjecting the specimen electric motor to a radiation exposure test. The test specimen shall be provided by the Customer, upon completion of a functional test, and shall be returned to the Customer, for post-radiation exposure functional testing, upon completion of this test program.
Applicable Qualification Standards, Specifications, and Documents o 10 CFR 50.49, "Environmental Qualification of Electric Equipmcnt Important to Safety for Nuclear Power Plants," U. S. Nuclear Regulatory Commission.
o Regulatory Guide 1.89, Revision 1, Junc 1984, "Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants," U. S. Nuclear Regulatory Commission.
o IEEE 323-1974, "IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Stations."
o Wyle Laboratories Quality Assurance Program Manual, April, 1987.
Equipment Description The equipment to be tested shall be a 400HP, 3-phase, electric motor, manufactured by Westinghouse. Preliminary information of the test spccimcn is available as follows:
Motor Weight: 2450 pounds Rotor Weight: 500 pounds Rated Voltage: 4 KV Full Load Amps: 52 Amps Locked Rotor Amps: 314 Amps Approximate Motor Dimensions: 49" (L) X 25" (W) X 25" (H)
Test Sequence The test program shall be performed in the following sequence:
o Receiving/Visual Inspection Radiation Exposure Post-Test Inspection WYLE LABOAATOAIES Huntsville Facility
Page No. 1-13 Test Report No. 40053-02 APPENDIX IV INSTRUilIENTATIONEQUIPMENT SHEET WYLE LABORATORIES Huntsville Facility
Page No. I-14 Test Report No. 40053-02 INSTRUMENTATION EQUIPMENT SHEET PhGE I Oi 1 moose~ <<XW><Y vJ>
DhTE: 03/03/89 TECRHICIhH: S. SIHHONS JOR HUHBER: 40053-00 CUSTOHEB: d.E.P.S.C.
TEST hREh:
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NO. INSTRUHEHT HhNUEhCTURER HODELl SZRIhL I HYLE $ RhHGE 1 hCCURhCY 1 Chf DhTE Chl DUE 1 HEG HTE TSTR GEHEBhL RhDIO 18620 2374 097892 .5-2000KH 3X LOX KND ll/08/88 05/05/89 2 HEGORH HETER HULTI-VOLT HG-251 h2875 102977 IK-200HEG OHH v-2X , ll/ll/88 05/10/89 This is to certify that the above instruments were calibrated using state-of-the-art techniques with standards ~hose calibration is traceable to the National Institute of Standards and Technology.
INSTBUHEHTdTIOH CHECKED 4 RECEIVED BY
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O l2 l4 I8 TIME (HOURS)
Page No. I-12B Test Report No. 40053-02 Revision A THIS PAGE INTENTIONALLYLEFT BLANK WYLE LABORATORIES Huntsvilte Facility
'I Page No. I-11 Test Report iVo. 40053-02 Revision A APPEilDIX'II DATA SHEET AND DATA PLOT WYLE LABORATORIES Huntsville Facility
Page No. I-12 Test Report No. 40053-02 QATA SHEET CUstomer ~ SEc.vtc ~ Ca~. WYLE LASORATORIES Specimen Part No.
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Page No. 1-9 Test Report No. 40053-02 COttPONENT IRRADIATION CERTIFICATION CUSTOttER t WYLE LABS P, O. NO. 4-4623-P AIR EQUI V. REQUIRED DOSE (tfRADS )
RATE NOT TO EXCEED (ttRADS/HR) < 1.0 I
SP EC lfENS:
QTY PART HO. SERIAL HO. DESCR IP TIQN 7or70 184 400 Hp Motor DATA:
SOURCE TYPE: COBALT-60 I GAHHA TOTAL DELIVERED DOSE (AIR): t(IN. 10.01 ttRADS t(AX. 10.79 NRADS DOSE RATE (AIR): ttZH. 0.58 t(RADS/HR ttAX. N/A t(RADS/HR TOTAL EXPOSURE HOURS: 17 4 i
SPECIMEN ROTA TIOH: T'R(Q )(h Y X FOUR MAY N/A NONE N/A DATE IN: 3/7/89 DATE QUT: 3/8/89 DOSIttETRY:
DOSIttETER TYPE: ~11 4034 BATCH AN TOLERANCE CALIBRATION DATE: 11/21/88 READOUT INSTRUMENT: B a L Spectzonic 1001 SERIAL HO. 0715493N CALIBRATIOH DATE: 9/29/88 COMMENTS: See attached report ATTACHttEHTS-'tORKSHEETS g/~ DRAWINGS N/A NOTICE OF AHQHQLY NZA AUTHORIZED SIGNATURE: )
T I T LE: GEN1&AL MANAGER D A TE 3/8/89
page zoo, I-10 Test Report iso. 40053-02 g) /1 sf oI<cfr P-18 I I I Sbd c4< Ra.c. I s I i P3 P-1A p r0du.c f'<rriea
$g Il Ao for PRODUCT FLOW DIAGRAM IR 126
Page No. I-7 Test Report No. 40053-02 IS CIMEO IX March 9, 1989 Wyle Labs 7800 Goveners Drive P.O. Box 077777 Huntsville, AL 35807-7777 ATZN: MR. TODD %%TERS
Dear Mr. Walters,
This letter sunmarizes the parameters pertinent to the irradiation of one (1) electrical nator. Reference your Purchase Order number 4-4623-P dated August 8, 1988.
A. Descri tion of the Irradiated Material The equipnent tested consisted of one (1) 400 Horse~, 3-phase, electric gator, manufactured by Westinghouse. (S/N 70F70184)
B. Arran ements for Gamma Irradiation As per your test procedure number 40053-01 dated July 18, 1988 (Revision A 08-08-88), the motor was in a hot cell and subject to a total integrated dose of 10E6 rads gama, air equivalent, a dose rate less than 1.0 E6 rads/hour.
C. Procedure for Uniform Gamma Irradiation Prior to the initiation of the motor exposure, a gama field dose rate check was performed. This simply was to confirm that the dose rate auld not exceed 1.0 Mrad per hour.
The cardboard nrIdel was checked at three plans (front, back and middle) with five (5) dosimeters on each plan to determine the average center point dose rate.
The motor was rotated 180 degrees throughout its exposure. The rotation occurred when the center point dose reached 50% of the required mininIum dose.
The total length of time be~ rotation intervals is called a half exposure.
D. Calculation of the Dose I
The delivered dose to the motor was calculated by multiplying the dose ISOlVIEDIX (NEVI JERSEY)) INC.
9 APOLlo ORIVE. WHIPPANY. NEW JERSEY 07981 ~ 1201) 887.2754
Page iIo. I-8 Test Report iso. 40053-02 1
r-'
S O IVI F D I X rate by the time for each half ensure and adding them together. The minimum reported dose is the lowest total value from any of the three (3) plans accumulated fran the two half exposures. The 11aximum reported dose is the highest.
E. Dosime~
Do imetry was performed using Harwell 4034 Perspex dosimeters utilizing a Bausch and Lcmb Model 1001 spectrophotaneter and a Texas Instrument 59 Calcu-..=.:=
lator as the read out instrument. The Batch AW dosimeters were calibrated traceable to a recognized standards laboratory with the last calibration date being November 21, 1988. The spectrophotaneter used (S/N 0715493 N) was last calibrated by Baush and Lcmb personnel on October 29, 1988 using standards traceable to NBS. The Measuretaent tolerance for this dosimetry system is estimated to be + 8.0%.
Me dose rate values stated in this report were calculated by dividing measured dose by exposure time. Combining the estimated uncertainty of the dose measurenent (+ 8.0%) withthat of the tim measurement (+ 0.01%) yields an uncert~ty of + 8.01% for rate measurenenm.
The total dose values stated in this report are calculated by multi-plying measured dose rates by exposure tim . Ccmbining the estimated uncer-tainty of the dose rate rreasureaent (+ 8.01%) with that of the time measure-ment (+0.09%) yields an uncertainty oZ + 8.10% for total dose naasuretrIents.
G. Qualit Assurance The processing of this rotor followed the procedures outlined in the Isanedix Inc. Quality Assurance Manual for Reactor Canponent Processing, Revision I dated May 18, 1988. The program specified in'.this. manual is designed to comply with the quality assurance requirenents of 10-CFR-50, appendix B and the reporting requirements of 10-CFR-21.
ALBI~ L. DE CARM GENIAL IAGER OREST PACXAWS J MANAGER QUALITY ASSURANCE ISOlVIEDIX (NEW JERSEY), INC.
9 APOLLO DRIVE, WHIPPANY, NEW JERSEY 07981 ~ 1201I 88 2254
Page No. I-5 Test Report No. 40053-02 APPENDIX II IRRADIATIONTEST REPORT WYLE LABORATORIES Huntsville Facllliy
Page No. I-6 Test Report No. 40053-02 THIS PAGE INTENTIONALLYLEFT BLANK WYLE LABORATORIES Huntavllle Facility
Page No. I-3 Test Report No. 40053-02 APPENDIX I TEST SPECIblEN INSPECTION SHEET WYLE LABORATORIES Huntsvilte Facility
Page Xo. I-a Tps I SpECIMEiii INSPECTION Revision A Test Report No. 40053-OZ CHECK AS APPROPRIATE CUSTOMER EP I Ei-~TPic Pouter, MZ.vIQQ ~PA~
JOB NO. 4 OOSE 0~
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SPECIFICATION W L'T P K> O I av. I-I DATE 0 3 "o1-89 '0 ~~ 0~
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NOTES:
Specimen Failed Inspected By Specimen Passed Witness Date:
NOA Written Sheet No. of Approved
Page No. I-1 Test Report No. 40053-02 SECTION I RECEIVING/VISUALINSPECTION) RADIATION EXPOSURE)
AND POST-TEST INSPECTION 1.0 REQUIREb IENTS Receiving/Visual Inspection The test specimen shall be subjected to an inspection for the purpose of identification and documentation. The inspection shall be performed as specified in Paragraph 3.1, S'ection II, of this report.
1.2 Radiation Exposure The test specimen shall be subjected to the Radiation Exposure Test as specified in Paragraph 3.2,Section II, of this report. Before, during, and after the irradiation period, the test specimen shall be subjected to Insulation Resistance Tests as specified in Paragraph 3.2.1,Section II, of this report.
1.3 Post-Test Inspection Upon completion of the radiation exposure, the test specimen shall be subjected to a post-test inspection. The inspection shall be performed as specified in Paragraph 3.3,Section II, of this report.
2.0 PROCEDURES Receiving/Visual Inspection A visual inspection of the test specimen was conducted upon receipt at the radiation facility. The inspection was performed in order to document the manufacturer and model number of the specimen to be tested and any noticeable damage.
20 Radiation Exposure The test specimen was placed in the hot cell at Isomedix, Inc. Facility and subjected to a dose rate of approximately 0.58 X 10 rads/hour. At a point midway through the radiation exposure, the test specimen was rotated 180'o ensurq uniform exposure distribution. The test specimen was subjected to a minimum total integrated dose of 10.01 X 10 rads gamma, air equivalent. Upon completion of irradiation, the test specimen was removed from the hot cell.
Insulation resistance measurements were performed on the test specimen before, during, and after the period of radiation exposure. The test specimen was positioned in the hot cell during all insulation resistance measurements. Each insulation resistance measurement was conducted by applying 1000VDC to the specimen motor phases (connected together) for one minute. Insulation resistance values were recorded upon completion of the one minute interval.
WYLE LABORATORIES Huntsville Facility
Page No. I-2 Test Report No. 40053-02 Revision A 2 0 PROCEDURES (Continued) 2tw Radiation Exposure (Continued)
The resistance readings were between the motor phases and the frame (ground) for all testing. Insulation resistance measurements performed during irradiation were conducted at intervals of approximately four hours each. All measurements performed during irradiation were conducted at 1000VDC.
Additional insulation resistance measurements, performed at the Test Engineer's direction, were as follows:
The initial insulation resistance measurements (performed prior to irradiation) and the final insulation resistance measurements (performed upon completion of irradiation) were conducted at the additional test voltage of 500VDC. The insulation resistance measurements were performed at a five minute interval, in addition to the required one minute time frame. The additional insulation resistance information was recorded on a Test Data Sheet for inclusion in the test report.
~ 3 Post-Test Inspection Upon completion of the radiation exposure, the test specimen was visually inspected. The inspection was performed without disassembly of the test specimen. The condition of the test specimen was recorded and compared to the condition prior to the Radiation Exposure Test.
3.0 RESULTS The test specimen was subjected to the test of Paragraph 2.0 and met the requirements of Paragraph 1.0. The post-test inspection indicated that there was no observable damage to, or degradation of, the test specimen as a result of the radiation exposure. There was no evidence of discoloration, cracking, or flaking of the non-metallic materials composing the test specimen. There was no evidence of test specimen degradation as a result of the Irradiation Test.
The data recorded during the test program is presented in Appendices I through IV of this section as noted below:
Appendix I contains the Test Specimen Inspection Sheet.
, Appendix II contains the test report on the irradiation performed at the Radiation Test Facility.
Appendix III contains the, Data Sheet for the insulation resistance measurements and a plot of the data versus time.
Appendix IV contains the Instrumentation Equipment Sheet generated for the insulation resistance measurements.
WYLE LABORATORIES Huntsville Facility
Page No. 111 Test Report No. 40053-02 QUALITY ASSURANCE All work performed on this test program was done in accordance with Wyle Laboratories'uality, Assurance Policies and Procedures Manual, which conforms to the applicable portions of ANSI N45.2, 10 CFR 50 Appendix B, 10 CFR 21, and Military Specification MIL-STD-45662A. Standards utilized in the performance of all calibrations are traceable to the National Institute of Standards and Technology.
8.0 TEST EQUIPMENT AND INSTRUMENTATION I
All instrumentation, measuring, and test equipment used in the performance of this test program were calibrated in accordance with Wyle Laboratories'uality Assurance Program, which complies with the requirements of Military Specification MIL-STD-45662A. Standards used in performing all calibrations are traceable to the National Institute of Standards and Technology (NIST) by report number and date. When no national standards exist, the standards are traceable to international standards or the basis for calibration is otherwise documented.
WYLE LABORATORIES Huntsville Facility
N~ arnt~ aoaat tr>>tton
/
Test Report REPORT NO.
WYLE rOB NO. 40053 CUSTOMER P. O. NO. 030 1 0 040 PAGE i OF PAGE REPORT March 20, 1989 SPEClFlCATlON ($ ) See References in Para raph 5.0 of this Summary ection 1.0 CUSTOMER American Electric Power Service Corporation AEPSC ADDRESS 1 Riverside Plaza, Columbus, Ohio 432 1 5 400 Horsepower, 3-Phase, AC Moto r 0 TEST SPEClMEN 3.0 MANUFACTURER Westinghouse 4.0
SUMMARY
The 400 Horsepower AC Motor, as described in Paragraph 6.0, was subjected to the Radiation Exposure Test as specified by AEPSC. The test specimen described herein was provided by, and is typical of, installations at Indiana Michigan Power Company.
This -test program was performed to verify the ability of the test specimen to maintain integrity during radiation exposure. The test report was prepared in accordance with the documentation requirements of IEEE 323-1974, "IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Stations."
sTATE oF ALABAMA 'l alabama Professional yyrte er>>s bere no aabrety for can>>ore or any taoist to parton orfxopeny.rncturana eprc>>l or oor>>ersrent>>t carnal>>a eeerrr tc rom yrtte'e o>> eet>>oee coUNTY oF MAolsoN f f by tnra report.
Engineer Reg. No. 7948 PREPARED BY Frederick M. Sittason being duly sworn, R. T. Wa deposes and says: The Information contained In this report is the result of complete and carefully conduct sts and is to the best of his k led true and correct in APPROVED BY all reQOg~~ P. R. J sonf a
t' WYLE CL A.
SUBSCRI ED and SwOm tO b lOre thia day of G. W. Hi ht Notary Pu c in and for the State of Alabama at large My Commission expires , 19 ~+
LABORATORIES SCIENTIFIC SERVICES 5 SYSTEMS GROUP HUNTSVILLE, ALABAMA
Page iVo. ii Test Report No. 40053-02 Revision A 4.0
SUMMARY
(Continued)
This report contains two sections.Section I presents the data recorded during the Receiving/Visual Inspection, Radiation Exposure, and Post-Test Inspection.
Section II presents the Wyle Laboratories'est Procedure iVo. 40053-01, Revision B, used to perform the test program.
The test program was performed in the sequence indicated in the previous paragraph and as specified in the Test Procedure. During the irradiation period, the test specimen showed no indication of degradation or damage. The insulation resistance values, recorded before, during, and after the exposure period, showed no appreciable difference in levels such as to indicate degradation. The test specimen is therefore considered to have met the acceptance criteria specified for the radiation exposure.
5.0 REFERENCES
5.1 American Electric Power Service Corporation Purchase Order Number 03010-040-8N dated May 12, 1988.
De2 Wyle Laboratories'uality Assurance Program Manual, June 1988.
5.3 Wyle Laboratories'est Procedure No. 40053-01, Revision B.
5.4 10 CFR 50.49, "Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants," U. S. Nuclear Regulatory Commission.
5.5 Regulatory Guide 1.89, Revision 1, June 1984, "Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants," U. S.
Nuclear Regulatory Commission.
5.6 IEEE 323-1974, "IEEE Standard for Qualifying Class lE Equipment for Nuclear Power Stations."
6.0 EQUIPMEiVT DESCRIPTION The 400 Horsepower AC Motor, manufactured by Westinghouse Company, was determined to have identification information as follows:
400 HP, 3-phase, 60 Hertz 4000VAC, 52 Amps, 3564 RPM Model ABDP Frame 509US Service Factor 1.15 S 4 70F70184 Ser. 3S-71 WYLE LABORATORIES Huntsville Facility
REVISIONS REVISION.
REPORT NO DATE I~Y 30, 1989 LASOAATOR1ES SclENTIFC SEAVCES E SYSTEMS QRCUP REV.NO. DATE PAGE OR PARAGRAPH AFFECTED BY APP'L DESCRIPTION OF CHANGES a 'I- Correct tvpographical error 5/30/89 RTI'7 A 5/30/89 I-2 ost-test inspection observa-tions included A 5/30/89 I-ll, I-12Ag I-12B, I-2 s5-)a d ed plot of insulation resistance data versus time
~ I Page No. I-11 Test Report No. 40053-02 Revision A APPENDIX III DATA SHEET AND DATA PLOT WYLE LABORATORIES Huntsvilte Facility
Page )1o. I-12 Test Report Ão. 40053-02 QATA SHEET Customer ~ -,C.)C POW&Z. QE.c.utm Ca~ WYLE LABORATORlES
~.
Specimen l"lt-~
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Date:
Notice of Sheet No. 1 of 0 yH'I-I Anomaly Approved 1 Wyle Fottt) WH 6)4A. Rev. APR '84
RADIATION EXPOSURE TEST PROGRAM ON A IVESTINGHOUSE 400 HP MOTOR FOR AMERICAN ELECTRIC POPOVER SERVICE CORPORATION For American Electric Power Service Corporation 1 Riverside Plaza Columbus, Ohio 43215
7.0 6.0 IA S.Q O
(p O
X 4.0 3.0 2.0 I,O l2 T I WE ( HOUR S)
Page No. 1-128 Tes t Re p or t N o. 40053-02 Revision A THIS PAGE INTENTIONALLYLEFT BLANK WYLE LABORATORIES Huntsville Facility
Page No. I-3 Test Report iNo. 40053-02 APPENDIX I TEST SPECIAIEN INSPECTION SHEET WYLE LABORATORIES Huntsville Facility
>!> .a page ~o. I-~ TEST SPEClMEN INSPECTIOt I Revision A Test Report Lbo. 40053-02 CHECK AS APPROPRIATE CUSTOMER +Et ~Lt=cT~lc omar. Mz vicE ~pg~
JOB NO. 4CaS'5 0 0
SPECIFICATION lA LT P G%- C 'l E,v.
4 DATE 0$ -oa-8 r 0
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Specimen Passed Witness Date:
NOA Written Qo Sheet No. of Approved
Test Report REPORT NO.
VeLE SOB NO. 40>>3 CUSTOMER P. O. NO.
03010-040-8N PAGE i OF 21 PAGE REPORT March 20, 1989 SPECIFICATION <S) See References in Para ra h 5.0 of this LD CUSTOMER American Electric Power Service Cor oration AEPSC I Riverside Plaza, Columbus, Ohio 43215 400 Horsepower, 3-Phase, AC Motor 20 TEST SPECIMEN 3.0 MANUFACTURER Westinghouse 4'UMMARY The 400 Horsepower AC Motor, as described in Paragraph 6.0, was subjected to thc Radiation Exposure Test as specified by AEPSC. Thc test specimen described herein was provided by, and is typical of, installations at Indiana Michigan Power Company.
This test program was performed to verify the ability of thc test specimen to maintain integrity during radiation exposure. The test report was prepared in accordance with the documentation requircmcnts of IEEE 323-1974, "IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Stations."
STATS OS ALABAhtA Erederick dsoosee end I
M. Sittason Alabama Engineer ssyL'he Inlonnatlon contained Prof essional In th4 noott
, bslnd duly twoln.
4 the nsutt ol colno4te
~
ala ees nae ae lenny IÃeeletna PREPARED BY esaesna R. T.
cs ne leal lo ansÃl w petany. naasn uacel Wa
~ esstnea lrl~nean oS-Z~-a cv
~ ntLcsnhsly cond ~ nd Is to the best cd h4 k bue snd conect ln APPROVED BY 0 F. R. J hnson WYLEO.A. i SUSSCRI O to on th4 dey ol .10
~ ~
In snd lct the Stet ~ ol A4bsn4 et 4tgo.
.IS~<
LABGRAToRIEs scIENllFlc sERvlcEs st sYsTEMS GR0UP HUNTSVILLE, ALABAMA AEPSC/ IHDIAHA iflCHIDAH P'jHER CO/ CON HIICIEAR PIhHT THIS OOCUNENT NEETS THE QA CERTIFICATION REQUIRENEHTS OF I,O, HO, OPS-PA'-ghl! P,O. ITENS AUTH SIS, DATE~Kr cPP
. ANGERSON tSHEET t OF g L)
eg Page No. I-1 Tes t Re p or t N o. 40053-02 SECTION I RECEIVING/VISUALINSPECTION, RADIATION EXPOSURE, AND POST-TEST INSPECTION 1.0 REQUIREMEi /TS Receiving/Visual Inspection The test specimen shall be subjected to an inspection for the purpose of identification and documentation. The inspection shall be performed as specified in Paragraph 3.1,Section II, of this report.
1.2 Radiation Exposure The test specimen shall be subjected to the Radiation Exposure Test as specified in Paragraph 3.2,Section II, of this report. Before, during, and after the irradiation period, the test specimen shall be subjected to Insulation Resistance Tests as specified in Paragraph 3.2.1,Section II, of this report.
1.3 Post-Test Inspection Upon completion of the radiation exposure, the test specimen shall be subjected to a post-test inspection. The inspection shall be performed as specified in Paragraph 3.3,Section II, of this report.
2 0 PROCEDURES 2.1 Receiving/Visual Inspection A visual inspection of the test specimen was conducted upon receipt at the radiation facility. The inspection was performed in order to document the manufacturer and model number of the specimen to be tested and any noticeable damage.
Radiation Exposure The test specimen was placed in the hot cell at Isomedix, Inc. Facility and subjected to a dose rate of approximately 0.5S X 10 rads/hour. At a point midway through the radiation exposure, the test specimen was rotated 180'o ensure uniform exposure distribution. The test specimen was subjected to a minimum total integrated dose of 10.01 X 10 rads gamma, air equivalent. Upon completion of irradiation, the test specimen was removed from the hot cell.
Insulation resistance measurements were performed on the test specimen before, during, and after the period of radiation exposure. The test specimen was positioned in the hot cell during all insulation resistance measurements. Each insulation resistance measurement was conducted by applying 1000VDC to the specimen motor phases (connected together) for one minute. Insulation resistance values were recorded upon completion of the one minute interval.
WYLE LASORATORIES Huntsville Facility
Page No. I-2 Test Report No. 40053-02 Revision A 2.0 PROCEDURES (Continued) 2.2 Radiation Exposure (Continued)
The resistance readings were between the motor phases and the frame (ground) for all testing. Insulation resistance measurements performed during irradiation were conducted at intervals of approximately four hours each. All measurements performed during irradiation were conducted at 1000VDC.
Additional insulation resistance measurements, performed at the Test Engineer's direction, were as follows:
The initial insulation resistance measurements (performed prior to irradiation) and the final insulation resistance measurements (performed upon completion of irradiation) were conducted at the additional test voltage of 500VDC. The insulation resistance measurements were performed at a five minute interval, in addition to the required one minute time frame. The additional insulation resistance information was recorded on a Test Data Sheet for inclusion in the test report.
2.3 Post-Test Inspection Upon completion of the radiation exposure, the test specimen was visually inspected. The inspection was performed without disassembly of the test specimen. The condition of the test specimen was recorded and compared to the condition prior to the Radiation Exposure Test. 0:
3.0 RESULTS The test specimen was subjected to the test of Paragraph 2.0 and met the requirements of Paragraph I.O. The post-test inspection indicated that there was no observable damage to, or degradation of, the test specimen as a result of the radiation exposure. There was no evidence of discoloration, cracking, or flaking of the non-metallic materials composing the test specimen. There was no evidence of test specimen degradation as a result of the Irradiation Test.
The data recorded during the test program is presented in Appendices I through IV of this section as noted below:
Appendix I contains the Test Specimen Inspection Sheet.
Appendix II contains the test report on the irradiation performed at the Radiation Test Facility.
Appendix III contains the Data Sheet for the insulation resistance measurements and a plot of the data versus time.
Appendix generated IV contains the Instrumentation Equipment for the insulation resistance measurements.
Sheet 0
WYLE LABORATORIES Huntsville Facility
0
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