Document: NUREG-0800
Document ID: 5e3dbec9-a39f-4531-9eb9-705982190066
Document Type: srp
Title: REACTOR PRESSURE VESSEL INTERNALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1613/ML16134A059.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.5
CFR Part: 
CFR Title: 

Content:
es itemized below, editorial changes were made throughout for clarity, consistency, and applicability. Changes incorporated into Revision 4 include: I. AREAS OF REVIEW • Changes were made to clarify reactor pressure vessel internals definition, including references to SMRs and Section 3.9.5 of the DSRS for B&W mPower IPWR Design. • Appendix A: NRC Review of Potential Adverse Flow Effects was deleted as a result of consolidation of the review of potential adverse flow effects in SRP Section 3.9.2, and a pointer to Regulatory Guide 1.20 and SRP Section 3.9.2 for the determination of loading conditions caused by flow-induced vibration, acoustic resonance, acoustic- induced vibration, and mechanically-induced vibration was added as a result. • The review interface with SRP Section 3.9.6 was added. II. ACCEPTANCE CRITERIA • Added the words, “fabricated, erected, tested, and inspected” to the requirements for GDC 1 and 10 CFR 50.55a. • Updated design and construction compliance requirements for CSS with references to a Federal Register notice and ASME BPV Code cases. III. REVIEW PROCEDURES • Removed the review procedure for potential adverse flow effects in concert with the change in areas of review as mentioned above. IV. IMPLEMENTATION • No significant changes. V. REFERENCES • References were updated by adding the DSRS for Section 3.9.5 and the deletion of Appendix A: NRC Review of Potential Adverse Flow Effects in Nuclear Power Plants Systems in concert with the above changes.