IR 05000269/2018010

Reissue - Oconee Nuclear Station, Units 1,2 & 3 - NRC Design Bases Assurance Inspection (Programs)Report Number 05000269/2018010 and 05000287/2018010

ML18331A376
Person / Time
Site:	Oconee
Issue date:	11/27/2018
From:	Lopez-Santiago O R NRC/RGN-II/DRS/EB2
To:	Burchfield E Duke Energy Carolinas
References
IR 2018010
Download: ML18331A376 (20)

Text

/RA/

/RA/

Code of Federal RegulationsCode of Federal Regulations, Part 50,

Viking Type J - feedthrough assemblies and cable assembliesElastimold Bushing and ConnectorNutherm International Inc. - Selector Switches and Motor Operating DeviceHowden Buffalo - Motor assemblyBoston Insulated Wire - various cable types containing Bostrad 7 insulationRotork Valve Operator (post 1978) Model NA1 ActuatorSorrento Electronics - Connectors

Code of Federal Regulations

"Aging/Qualified Life Section II, of Report 43979-1, "Environmental and Mechanical Wear Aging Test" shows the actuator being aged for 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> at 200°F. This is not equivalent to 40 years at 120°F (120°F being Duke's ambient temperature) per the Arrhenius Equation. Additional testing by Test Report TR-3030 shows justification of the 40 year qualified life of the operato Reference Rotork letter dated December 27, 1985 paragraph 1 An added justification of the 40 year life is to have one actuator pulled from containment, tested and inspected for functionability and the characteristics of the sealing material every five year Reference OM-245-0980, Section NA1 Nuclear Qualification, Paragraph 2."

The Rotork letter dated December 27, 1985, paragraph 1C, stated the following: "As you have determined, Test Report No. 43979-1 does not specifically address the life of the actuator relative to thermal aging testing. Initially, let me point out that we did age the actuators for 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> at 200°F (Reference Section 2, Page 1, Para. 1.0). Also, note that the motor was preaged as an individual component for 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> at 338°F. For your information, the basis of the aging program was an early draft of IEEE-382. The motor preaging was based on the l0°C rule. Since the time of Rotork's testing, the arrhenius equation has become accepted as the proper method of determining the life of non-metallic components. The attached Test Report No. TR3030 provides component life information based on the arrhenius equation. Included in TR3030 is a bill of material for non-metallic components, activation energies for non-metallic components, and reference to the documents used to determine the activation energies. The lowest activation energy level found is .89e Using .89ev and an ambient of 120°F (provided by Duke), a calculated qualified life equivalent to 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> of aging at 200°F is 2.2 years. The motor preaging of 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> at 338°F is equivalent to a qualified life of approximately 145 years. The thermal aging conducted in TR3030 is equivalent to 221 years at 120°F (see the attached modified version of Table 1 in TR3030).

Since the thermal aging program conducted in TR3030 was very severe (equivalent to 221 years of normal plant life) and since the actuator continued to function within acceptable parameters, results can be applied to obtain a qualification package which shows that the actuator will continue to function throughout its forty year life. Since the various non-metallic materials were not significantly degraded, the operation of the actuator under accident conditions as conducted in Test Report No's 43979-1, 43979-3 and 58364 can be assumed."

"Every year after start-up of each nuclear power plant, at least one Rotork actuator is removed from a valve, tested on a Rotork test rig, disassembled, inspected, reassembled and tested. We will make a Rotork engineer available to examine the unit and document a statement on its functionability and the characteristics of the sealing material. Although it is at the power plant's-discretion, I would suggest the selection of one actuator each year in one of the most severe ambients would be sufficient."

Code of Federal Regulations, Part 50,