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| Document | Content | RCC‑M Reference | |----------|---------|-----------------| | | All hand calculations, FE results, assumptions, safety factors. | §6.1 – “Design justification” | | Materials & Welding Procedure Files (MPF / WPQR) | Certificates, heat‑treatment records, welding qualification tests. | §5.3 – “Welding procedures” | | Manufacturing Drawing (MD) | Fully dimensioned, toleranced CAD drawing with notes on RCC‑M limits (e.g., radius ≥ X, fillet ≤ Y). | §2.4 – “Drawing conventions” | | Inspection & Test Plan (ITP) | NDT methods (ultrasonic, radiography), acceptance criteria, frequency. | §7.2 – “Quality control” | | Configuration Management Log | Revision history, change requests, traceability matrix (RSD ↔ DCR ↔ MD). | §8.1 – “Configuration control” |

The , published by AFCEN, is a comprehensive set of design and construction rules specifically for the mechanical components of Pressurized Water Reactor (PWR) nuclear islands. It serves as a critical technical standard to ensure the safety, reliability, and mechanical integrity of equipment like pressure vessels, heat exchangers, and piping systems throughout their design life. 1. Historical Development and Purpose rcc-m pdf download

The RCC-M code is and must generally be purchased for official use. Digital PDF versions and physical paper copies are available through the official AFCEN shop . | Document | Content | RCC‑M Reference |