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Rulemaking Activities to Risk-Inform Requirements in 10 CFR Part 50

[+] Author Affiliations
Eileen M. McKenna, Timothy A. Reed

U.S. Nuclear Regulatory Commission, Washington, D.C.

Paper No. ICONE10-22593, pp. 553-557; 5 pages
doi:10.1115/ICONE10-22593
From:
  • 10th International Conference on Nuclear Engineering
  • 10th International Conference on Nuclear Engineering, Volume 4
  • Arlington, Virginia, USA, April 14–18, 2002
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-3598-7 | eISBN: 0-7918-3589-8
  • Copyright © 2002 by ASME

abstract

This paper presents the status of NRC activities to revise requirements in Title 10 of the Code of Federal Regulations (10 CFR Part 50) to make them more risk-informed. The activities include proposed changes to treatment requirements (requirements such as quality assurance, testing, inspection, documentation that are imposed to add confidence in the capability of structures, systems and components (SSCs) to perform their intended functions) as well as changes to certain technical requirements. The technical requirements under consideration are those relating to combustible gas control and for emergency core cooling systems (including the evaluation models).

Copyright © 2002 by ASME

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