ASME STP-NU-072-2014 PDF

St ASME STP-NU-072-2014

Name in English:
St ASME STP-NU-072-2014

Name in Russian:
Ст ASME STP-NU-072-2014

Description in English:

Original standard ASME STP-NU-072-2014 in PDF full version. Additional info + preview on request

Description in Russian:
Оригинальный стандарт ASME STP-NU-072-2014 в PDF полная версия. Дополнительная инфо + превью по запросу
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Active

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Full title and description

STP-NU-072-2014 — "Small Modular Reactor (SMR) Roadmap". This ASME roadmap document identifies ASME Boiler & Pressure Vessel Code (BPVC) and OM Code areas that may present licensing or application challenges for small modular reactor designs and summarizes potential interpretation/application issues and strategies for addressing them.

Abstract

This roadmap describes code and standards topics (notably portions of BPVC Section III and Section XI and the ASME OM Code) that could affect NRC licensing or design deployment for near‑term SMR concepts. It identifies specific code sections included by reference in NRC regulations, highlights areas where SMR design features may create unique licensing challenges, and discusses strategies (including use of alternatives) to facilitate licensing and commercial deployment.

General information

  • Status: Active; placed on stabilized maintenance (ASME indicates the document remains in effect and will accept change requests for consideration).
  • Publication date: 2014.
  • Publisher: The American Society of Mechanical Engineers (ASME).
  • ICS / categories: ICS 27 — Energy and heat transfer engineering; specifically 27.120 (Nuclear energy engineering) with relevance to 27.120.10 (Reactor engineering) and 27.120.20 (Nuclear power plants — safety).
  • Edition / version: 2014 edition (designation STP-NU-072:2014).
  • Number of pages: 38 pages.

Scope

The roadmap surveys ASME Code and related standards topics that are relevant to licensing and deployment of small modular reactor designs. It focuses on interpretation and application issues in BPVC (notably Section III and Section XI) and the ASME Operation & Maintenance (OM) Code that may arise because of unique SMR features, and it recommends engagement strategies among vendors, regulators (NRC), ASME and other stakeholders to clarify or adapt code application where necessary.

Key topics and requirements

  • Identification of BPVC Section III (construction) and Section XI (inservice inspection) topics that may affect SMR designs.
  • Review of ASME OM Code provisions as they relate to operation and maintenance of SMRs.
  • Discussion of interpretation and application gaps between vendors and regulatory expectations that could impact NRC licensing.
  • Strategies for addressing identified issues (stakeholder dialogue, proposing alternatives to the NRC, and code/standard development priorities).
  • Roadmap recommendations to facilitate timely design development and licensing of SMR technologies.

Typical use and users

Used by SMR vendors, nuclear plant designers, code committee members, regulatory reviewers (including NRC staff), licensing engineers, and consultants to identify and prioritize ASME code interpretation, application and development activities that affect SMR licensing and deployment. It is a planning and coordination document rather than a prescriptive design rule.

Related standards

Primary related documents include ASME BPVC Section III (Rules for Construction of Nuclear Facility Components), ASME BPVC Section XI (Inservice Inspection), and the ASME Operation & Maintenance (OM) Code; the roadmap references those codes and highlights where their application may be unclear for SMR concepts. It also relates to other ASME STP-NU reports and technology roadmaps addressing nuclear code development.

Keywords

Small modular reactor, SMR, ASME, roadmap, BPVC, Section III, Section XI, OM Code, nuclear licensing, NRC, code interpretation, inservice inspection.

FAQ

Q: What is this standard?

A: STP-NU-072-2014 is an ASME "Small Modular Reactor (SMR) Roadmap" — a guidance/roadmap document that identifies code and standards topics relevant to SMR licensing and deployment (not a mandatory design standard).

Q: What does it cover?

A: It covers potential interpretation and application issues in ASME nuclear codes (particularly BPVC Section III and Section XI and the OM Code) that could affect NRC licensing of SMR designs, and it recommends strategies for stakeholders to address those issues.

Q: Who typically uses it?

A: SMR developers, nuclear code and standards committees, licensing engineers, regulatory reviewers, consultants, and other stakeholders involved in the design, licensing and deployment of SMR technologies.

Q: Is it current or superseded?

A: The document is the 2014 edition and ASME indicates it has been placed on stabilized maintenance and remains in effect; update or change requests are considered through ASME processes. Users should check ASME for any reaffirmation or maintenance notices.

Q: Is it part of a series?

A: Yes — it is one of several ASME STP-NU technology/roadmap publications addressing nuclear technology and code development topics; the STP-NU designation groups related roadmap and technical reports for nuclear topics.

Q: What are the key keywords?

A: Small Modular Reactor, SMR, roadmap, ASME, BPVC, Section III, Section XI, OM Code, licensing, NRC, code interpretation.