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Regulatory Guide 1.36 - Nonmetallic Thermal Insulation for Austenitic Stainless Steel(Task SC 807-4) A. IntroductionGeneral Design Criterion 1, "Quality Standards and Records," of Appendix A to 10 CFR Part 50, ''General Design Criteria for Nuclear Power Plants," requires that structures, systems, and components important to safely be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety function to be performed. In addition, General Design Criteria 14 and 31 require assurance that the reactor coolant pressure boundary will have an extremely low probability of gross rupture or rapidly propagating fracture. Stress-corrosion cracking, which is promoted by certain contaminants, is one mechanism whereby such failures may be postulated. This guide describes an acceptable method for implementing these criteria with regard to the selection and use of nonmetallic thermal insulation to minimize any contamination that could promote stress-corrosion cracking in the stainless steel portions of the reactor coolant pressure boundary and other systems important to safety. This guide applies to light-water-cooled reactors. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position. B. DiscussionWhether sensitized or not, austenitic stainless steel is subject to stress corrosion and should be protected from certain contaminants that can promote cracking. Chloride and fluoride ions are the most serious contaminants, so it is necessary to minimize the levels of these ions (and others that have the potential to cause stress-corrosion cracking) in all material that may come in contact with austenitic stainless steel. Thermal insulation is often employed adjacent to, or in direct contact with, stainless steel piping and components. Accidental spillages and leakages of fluids through pipe fittings, valves, and equipment cannot be entirely prevented, and contaminants present in the thermal insulation may be leached by these liquids and deposited on the stainless steel surfaces. Extensive test programs by Dana(1) and Karnes(2) have demonstrated that stress-corrosion cracking of both unsensitized and sensitized austenitic stainless steel can be induced by chloride or fluoride ions leached from many representative thermal insulation materials. Karnes has further shown that leachable sodium and silicate ions at least partially inhibit the adverse effects of the chloride and fluoride ions. Controls should be exercised to assure that nonmetallic thermal insulations employed in nuclear power plants do not contribute significantly to stress corrosion of stainless steel. A quality assurance program should be implemented at all steps from manufacturing through installation to minimize pickup of contaminants from external sources. Each type(3) of insulation should pass an appropriate qualification test (such as those identified in C.2.a. below) to demonstrate that under conditions conservatively representing those encountered in reactor operation, the insulation does not induce excessive cracking in stressed stainless steel specimens. A further qualification test should consist of a chemical analysis to demonstrate that the leachable chloride and fluoride ion concentrations are within acceptable levels and that sufficient quantities of the corrosion inhibiting ions (sodium and silicate) are present in the insulation. The following procedures may be used in the chemical analyses(4) for chlorides and fluorides:
Silicates may be analyzed using ASTM E60 "Photometric Methods for Chemical Analysis of Metals," by either of the following methods:
Sodium ion concentrations may be obtained by either spectrographic or flame photometric methods. Further, each lot(5) of insulation should be analyzed to demonstrate that chlorides and fluorides are being maintained at acceptable levels and that the composition is representative of the material employed in the qualification test. The production lot is considered representative if the levels of the principal leachable promoters (chloride and fluoride ions) and inhibitors (sodium and silicate ions) of stress-corrosion cracking are within fifty percent of the corresponding values determined for the qualification sample. C. Regulatory PositionThe levels of leachable contaminants in nonmetallic insulation materials(6) that come in contact with austenitic stainless steels of the American Iron and Steel Institute (AISI) type 3XX series used in fluid systems important to safety should be carefully controlled so that stress-corrosion cracking is not promoted. In particular, the leachable chlorides and fluorides should be held to the lowest practicable levels. Insulation for the above application should meet the following conditions:
1. A. W. Dana, Jr., "Stress Corrosion Cracking of Insulated Austenitic Stainless Steel," ASTM Bulletin October 1957. 2. H. F. Karnes, "Corrosion Potential of Wetted Thermal Insulation," presented at American Institute of Chemical Engineers 57th National Meeting, September 1965 (Conf-650905-2). 3. Type means material of similar composition, form, and class and of consistent quality, formulation, and manufacturing process. 4. Samples for chemical analysis may be prepared by the procedure described in Reactor Development & Technology (RDT) M12-IT, Para. 6.1-6.3. Copies may be obtained from RDT Standards Office, Oak Ridge National Laboratory, Building 1000, P.O. Box X, Oak Ridge, Tennessee 37830. 5. A lot is defined as the thermal insulation material of the same composition, form, type, grade, and class produced at one plant under the same conditions over a limited time span and designated by the producer as a production lot. 6. Thermal insulating materials include block insulation, pipe insulation, board and blanket and the cements and adhesives employed in their application. 7. A representative sample should be fully representative of the cross section of the material; that is, it should include proportionate amounts of all components including facing fabrics and finishing layers. |
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