Browns Ferry: A New Milestone in Nuclear Plant Fire Protection

Barry Miller
Senior Project Manager, Fire Protection Branch

The NRC recently marked a milestone with the transition of the Browns Ferry nuclear power plant to the National Fire Protection Association’s Standard 805 (NFPA 805). The license amendment, issued October 28, is significant because it marks 23 reactors at 15 plants to have completed the transition since 2010. It is symbolically important because a fire at Browns Ferry in March of 1975 prompted the NRC and the industry to focus on fire safety at nuclear power plants.

Fire Protection infographic_r13The Browns Ferry fire started when a worker used a candle to test airflow around a temporary penetration seal in the cable spreading room. The flame ignited the temporary seal material, and the fire spread to the reactor building where it burned many of the cables in systems required to safely shut down the plant.

Although plant operators were able to shut the plant down safely, the event led the NRC to promulgate prescriptive fire safety requirements (10 CFR Part 50, Appendix R). For example, plants were to ensure there was at least 20 feet of separation between trains of redundant safety systems. However, this requirement was impractical for some plants that had already been built, so in many cases licensees had to find an alternative means of achieving an equivalent level of safety.

“The fire at Browns Ferry in 1975 was a turning point for the nuclear industry,” said Bill Dean, director of the Office of Nuclear Reactor Regulation. “It put a spotlight on the risk fires can pose to nuclear safety. Many safety improvements have been made industry-wide since that time, but the adoption of NFPA 805 represents perhaps the most significant undertaking in fire safety since the institution of Appendix R. This transition means Browns Ferry has performed a full re-analysis of the fire risk at its three reactors and identified the most efficient and effective means to protect its most fire-sensitive areas.”

The NFPA 805 is a performance-based means of using advanced fire analysis tools to assess the risk of fire at various areas of a nuclear power plant. That way, a plant’s fire protection scheme can be customized to focus on the most risk-significant areas and to protect the reactor’s safety systems.

Using the NFPA 805 standard is optional. Newer plants constructed after 1975 were typically built to the prescriptive requirements. So they may opt to remain under those requirements, contained in 10 CFR 50.48 and still be in compliance with the agency’s fire protection regulations. Although NFPA 805 offers certain advantages from a risk-informed perspective, both methods provide reasonable assurance that a plant would be able to cope with a serious fire.

The following plants have now completed the transition to the NFPA 805 fire protection standard: Shearon Harris; Oconee 1, 2 & 3; D.C. Cook 1&2; Duane Arnold; Callaway; Fort Calhoun; V.C. Summer; Cooper; Nine Mile Point 1; Turkey Point 3 & 4; Farley 1 & 2; Brunswick 1 & 2; Palisades; Arkansas Nuclear One Unit 2; and Browns Ferry 1, 2 & 3.

Preparing for Subsequent License Renewal

Albert Wong
Division of License Renewal
Office of Nuclear Reactor Regulation

The NRC’s operating licenses for commercial nuclear power reactors are valid for 40 years and may be renewed for an additional 20 years at a time.  So far the agency has renewed 78 licenses and has applications for another 16 under review. We received the first license renewal application in April 1998, and we’re expecting to receive the last application for a first renewal sometime after 2020.

Today, Dominion Virginia Power announced that it expects to submit a subsequent license renewal application in 2019 – a renewal beyond the 60 years of operation from the first license and the initial renewal — for Surry Power Station.

Subsequent renewal applications will be reviewed under the same regulations (10 CFR Part 54) as the initial renewals. That means they will get similar scrutiny for both safety (focusing on how the plant operators manage the effects of aging on certain plant components) and environmental impacts. There will also be opportunities for public input and hearings.

Of course, operating plants beyond 60 years may raise different technical issues for us to address in these reviews. So we are drawing on our experience with the initial license renewals, plant operating experience, ongoing research, and expert opinions to identify strategies for dealing with the challenges of extending operation to 80 years. Two draft guidance documents will be published in December 2015 for public comment. They are “Generic Aging Lessons Learned for Subsequent License Renewal Report” and the “Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants.”

The final guidance documents – including responses to public comments and explanations of any changes from the drafts – will be published in time to support our review of subsequent license renewal application.

Plant operators applying for subsequent license renewal will need a detailed technical basis, along with associated research and “aging management programs,” to demonstrate how they will keep their plants operating safely during the additional 20 years. The NRC staff will give these applications the same thorough reviews we give initial renewals. We expect the reviews will take about two years, though the quality of the applications could affect the schedule.

The NRC is proactively preparing for anticipated subsequent license renewal applications and stands ready to ensure the continued safety of operating plants once applications are received.

 

 

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