Document

Methodology for Modeling Fire Growth and Suppression for Electrical Cabinet Fires in Nuclear Power Plants

The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft NUREG entitled, "Methodology for Modeling Fire Growth and Suppression for Electrical Cabinet F...

Nuclear Regulatory Commission
  1. [NRC-2019-0119]

AGENCY:

Nuclear Regulatory Commission.

ACTION:

Draft NUREG; request for comment.

SUMMARY:

The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft NUREG entitled, “Methodology for Modeling Fire Growth and Suppression for Electrical Cabinet Fires in Nuclear Power Plants” (NUREG-2230/EPRI 3002016051). This report is a joint product of the NRC and the Electric Power Research Institute (EPRI) collaborating under a memorandum of understanding for fire research. The purpose of this report is to provide an approach that more closely models the types of fire progressions and response activities observed in operating experience. This report provides a revised set of parameters addressing both the fire growth portion and the suppression response for electrical cabinet fires.

DATES:

Submit comments by July 31, 2019. Comments received after this date will be considered if it is practical to do so, but the Commission is able to ensure consideration only for comments received before this date.

ADDRESSES:

You may submit comments by any of the following methods:

  • Federal Rulemaking Website: Go to www.regulations.gov/​ and search ( printed page 31355) for Docket ID NRC-2019-0119. Address questions about docket IDs in Regulations.gov to Jennifer Borges; telephone: 301-287-9127; email: . For technical questions, contact the individuals listed in the FOR FURTHER INFORMATION CONTACT section of this document.
  • Mail comments to: Office of Administration, Mail Stop: TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, ATTN: Program Management, Announcements and Editing Staff.

For additional direction on obtaining information and submitting comments, see “Obtaining Information and Submitting Comments” in the SUPPLEMENTARY INFORMATION section of this document.

FOR FURTHER INFORMATION CONTACT:

David W. Stroup, Office of Nuclear Regulatory Research, telephone: 301-415-1649, email: ; or Nicholas Melly, Office of Nuclear Regulatory Research, telephone: 301-415-2392, email: . Both are staff of the U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.

SUPPLEMENTARY INFORMATION:

I. Obtaining Information and Submitting Comments

A. Obtaining Information

Please refer to Docket ID NRC-2019-0119 when contacting the NRC about the availability of information for this action. You may obtain publicly-available information related to this action by any of the following methods:

B. Submitting Comments

Please include Docket ID NRC-2019-0119 in your comment submission.

The NRC cautions you not to include identifying or contact information that you do not want to be publicly disclosed in your comment submission. The NRC will post all comment submissions at www.regulations.gov/​ as well as enter the comment submissions into ADAMS. The NRC does not routinely edit comment submissions to remove identifying or contact information.

If you are requesting or aggregating comments from other persons for submission to the NRC, then you should inform those persons not to include identifying or contact information that they do not want to be publicly disclosed in their comment submission. Your request should state that the NRC does not routinely edit comment submissions to remove such information before making the comment submissions available to the public or entering the comment into ADAMS.

II. Discussion

Over the past decade, modern fire probabilistic risk assessments (PRAs) have been developed using NUREG/CR-6850 (EPRI 1011989), EPRI/NRC Fire PRA Methodology for Nuclear Power Facilities. The results show that fire can be a significant portion of the overall site risk profile, however, the methodology was never fully piloted tested before implementation. As a result, some areas of the fire PRAs have been found to be overly conservative resulting in potentially unrealistic results. Additional research is being conducted to improve the tools, methods, and data used for fire PRAs and refine the estimates of risk and close technical gaps in the methodology.

Recent research efforts focused on obtaining more detailed information regarding the fire incidents at nuclear power plants. This data collection has enabled researchers to obtain more details on the fire attributes, timeline, and plant impact. This project specifically reviewed the available electrical cabinet fire incident data in an effort to update the methodology to better reflect the observed operating experience. Insights from the data review served as the basis for amending portions of the fire modeling and suppression response to more accurately align with operating experience.

Specifically, the methodology described in this report provides:

Dated at Rockville, Maryland, this 25th day of June 2019.

For the Nuclear Regulatory Commission.

Mark H. Salley,

Branch Chief, Fire and External Hazards Analysis Branch, Division of Risk Analysis, Office of Nuclear Regulatory Research.

[FR Doc. 2019-13928 Filed 6-28-19; 8:45 am]

BILLING CODE 7590-01-P

Legal Citation

Federal Register Citation

Use this for formal legal and research references to the published document.

84 FR 31354

Web Citation

Suggested Web Citation

Use this when citing the archival web version of the document.

“Methodology for Modeling Fire Growth and Suppression for Electrical Cabinet Fires in Nuclear Power Plants,” thefederalregister.org (July 1, 2019), https://thefederalregister.org/documents/2019-13928/methodology-for-modeling-fire-growth-and-suppression-for-electrical-cabinet-fires-in-nuclear-power-plants.