ML20136C997

SER Supporting CRD Matls,Reactor Internals,Reactor Coolant, Pressure Boundary Matls,Steam Generator Matls,Esf Matls & Steam & Feedwater Sys Matls

ML20136C997
Person / Time
Site:	05000000, Vogtle
Issue date:	01/03/1984
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML082840446	List: ML20136B728 ML20136B812 ML20136C125 ML20136C159 ML20136C491 ML20136C917 ML20136C922 ML20136C928 ML20136C943 ML20136C953 ML20136C968 ML20136C973 ML20136C977 ML20136C984 ML20136C992 ML20136C997 ML20136C999 ML20136D004 ML20136E610 ML20136E615 ML20136E634 ML20136E642 ML20136E653 ML20136E686 ML20136E700 ML20136E712 ML20136E781 ML20136E788 ML20136E795 ML20136E812 ML20136E883 ML20136E904 ML20136E954 ML20136E960 ML20136F014 ML20136F040 ML20136F047 ML20136F088 ML20136F103 ML20136F115 ML20136F128 ML20136F136 ML20136F140 ML20136F147 ML20136F162 ML20136F168 ML20136F176 ML20136F182 ML20136F188 ML20136F194 ... further results
References
FOIA-84-663 NUDOCS 8601040166
Download: ML20136C997 (2)

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Vogtle Electric Generating Station, Units 1 & 2 Docket Nos. 424/425 Safety Evaluation Report - Secondary Review We have reviewed FSAR Sections 3.8.1 Concrete Containment, 3.,8.2 Steel Containment and ASME Class MC Components, 4.5.1 Control Rod System Structural Materials, 4.5.2 Reactor Internals Materials, 5.2.3 Reactor Coolant Pressure Boundary Materials, 6.1.1 Engineered Safety Features Materials, 9.2.1 Station Service Water Systems, 9.2.2. Component Cooling System and 10.3.6 Steam and Feedwater System Materials, for-materials compatibility and corrosion aspects.

We are providing the following evaluation in accordance with our secondary review responsibility which includes environmental compatibility.

The materials of construction exposed to the reactor coolant, secondary coolant and containment sprays are compatible with the expected environmen,t,

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as proven by extensive testing and satisfactory performance, and conform to ASME Boiler and Pressure Vessel Code, Sections II, III and IX.

General corrosion of all materials is expected to be negligible except for carbon

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and low alloy steels.

Where~these materials are exposed to the secondary coolant, general corrosion is expected to be negligible; where these materials might.be exposed to leaking primary. coolant, their behavior.can be readily

! observed as part of the inservice visual and/or nondestructive inspection

[ program performed to ensure their integrity for subsequent service.

The external nonmetallic insulation to be used on austenitic stainless steel components. conforms with the recommendations of Regulatory Guide 1.36,-

" Nonmetallic thermal Insulation for Austenitic Stainless Steels." The onsite cleaning and cleanliness controls during fabrication and erection conform to l

the regulatory positions of Regulatory Guide 1.37, " Quality Assurance Require-ments -for Cleaning of Fluid Systems and Associated Components of Water Cooled Nuclear Power Plants." The use of materials of proven performance in service and the conformance with the recommendations of the stated regulatory guides and codes constitutes an acceptable _ basis for satisfying the requirements of NRC General Design Criterion 4, " Environmental Design," in regard to' the compatibility of materials and components with tne environmental ~ conditions asociated with normal operation, maintenance, testing, and postulated accidents.

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The selection and use of the materials further satisfies the requirements of GDC 14, " Reactor Coolant Pressure Boundary" as it relates to 't'he design having an extremely low probability of abnormal leakage, of rapidiy. propagating failure, and of gross rupture.

Based on our evaluation above, we conclude that the materials used in the above systems are acceptable from the corrosion point of view.

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