Document: NUREG-0800
Document ID: 495c2b41-2832-4900-9000-040f3ae8c835
Document Type: srp
Title: STEAM GENERATOR MATERIALS AND DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1614/ML16147A289.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.2.1
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are covered by the requirements of 10 CFR Part 50 and 10 CFR Part 52, and were approved by the Office of Management and Budget, approval number 3150-0011 and 3150-0151. PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number. 5.4.2.1-23 Revision 4 - July 2016 Standard Review Plan Section 5.4.2.1 Description of Changes Section 5.4.2.1, “Steam Generator Materials and Design” The main purpose of this update is to add regulatory review guidance, based on the recommendations from the lessons learned report that was issued following the tube degradation event at the San Onofre Nuclear Generating Station in 2012 (ADAMS Accession No. ML15015A419). The lessons learned report identified a need to clarify the appropriate scope and detail of the regulatory review guidance as it pertains to rapidly propagating degradation mechanisms, such as fluid elastic instability, that cannot be managed through the steam generator program. The title was changed (by adding “and Design”) to reflect the fact that the SRP continues to include design features in addition to materials selection. A secondary review responsibility is added for evaluating fluid elastic instability. Guidance is added for evaluating the design to determine if it precludes degradation that may propagate rapidly, such as fluid-elastic instability, which cannot be managed through the steam generator program in the plant technical specifications. Guidance for evaluating the structural and leakage integrity of the tube-to-tubesheet welds was added to ensure that these welds have been designed and analyzed appropriately. The staff described this issue in NRC Regulatory Issue Summary RIS-16-02, “Design Basis Issues Related to Tube-to-Tubesheet Joints in Pressurized-Water Reactor Steam Generators.” See ADAMS Accession