The Nuclear Regulatory Commissionhas not accepted Subsection NH ofSection III of the ASME Code “Class1 Components in ElevatedTemperature Service.” Further, theAdvisory Committee on ReactorSafeguards (ACRS) reviewed similarelevated temperature structuraldesign criteria proposed for theClinch River Breeder Reactor(CRBR) and generated a list oftechnical issues and safety concernsthat they believed still needed to beresolved. DOE agreed to fund R & Defforts to answer their concerns tothe satisfaction of the U.S. NRC andACRS prior to requesting anOperating License for CRBR. Thestructural design criteria being usedat that time was fundamentallysimilar to the current criteria inSubsection NH of Section III of theASME Code. It is clear that thesesafety issues need to be resolvedfrom a regulatory perspective inorder to assure that the technologyneeded to support the licensing ofNGNP and Gen IV will be in place tosupport Design Efforts in a timelymanner.
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