Technical Basis for the Containment Protection and Release Reduction Rulemaking for Boiling Water Reactors with Mark I and Mark II Containments (NUREG-2206)

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Publication Information

Manuscript Completed: December 2016
Date Published: March 2018

Prepared By:
Jonathan Barr, Sudhamay Basu,
Hossein Esmaili, and Martin Stutzke

Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

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Abstract

The work documented in this report focused on developing the technical basis for a potential rulemaking action on containment protection and release reduction (CPRR) strategies for boiling water reactors with Mark I and Mark II containments. The work covered three areas of analyses: (1) accident sequence analysis (event tree development) to identify accident sequences initiated by extended loss of ac power (ELAP) due to internal events and seismic events deemed to be the most significant risk contributors; (2) accident progression analysis of these sequences and assessment of radiological source terms; and (3) analysis of offsite consequences including individual early fatality risk and latent cancer fatality risk, land contamination, and economic consequences. The calculated offsite consequences were weighted by accident frequency to assess relative public health risk reduction associated with various CPRR strategies. Important findings and key insights from the work are delineated.