|
Education -->
Nuclear Facts
SAFETY
Fire protection
| n |
The Nuclear Regulatory Commission's (NRC) fire
protection rules, 10 CFR 50.48 and 10 CFR 50 Appendix R, establish
detailed requirements for "defense-in-depth" fire
protection programs at commercial nuclear power plants. These
programs include measures related to fire prevention, detection
and response, and the protection of vital safety equipment in the
event of a fire.
|
| n |
Nuclear power plants have multiple fire protection
systems to ensure high levels of safety. When a system is out of
service—during maintenance, for example—utilities must take
compensatory measures that have been approved by the NRC.
|
| n |
Prevention is the first line of defense against
fire at a nuclear power plant. Utilities have numerous
programs—including administrative controls, inspections and
employee training—related to control of combustible materials
and ignition sources. But if a fire were to occur, fire detection
and suppression systems and trained personnel would quickly
control and extinguish it.
|
| n |
The NRC and the industry agree that, in general,
nuclear plant fire protection should be more risk-informed and
performance-based. Industry and NRC goals in this area can be
achieved within the context of the existing regulation.
|
Evolution of nuclear plant fire protection
Nuclear power plants are built mainly of concrete and steel,
which are relatively impervious to fire damage. Yet fire is an
important safety concern at nuclear plants because, depending on its
severity and where it occurs, a fire could threaten systems and
components that are needed to shut down the plant and provide coolant
for the fuel. The ultimate goal of fire protection programs at nuclear
power plants is to protect public health and safety by ensuring that
plants can be shut down and maintained in a safe condition.
Plant design and regulation have always considered
fire safety to some extent, but in the early years of commercial
nuclear energy in the United States—the 1960s and early 1970s—the
requirements and standards related to fire protection at nuclear power
plants were not well developed. Nuclear plants had to meet applicable
building codes-the same codes used for office complexes and other
types of industrial facilities. In addition, the NRC's general design
criteria for nuclear power plants, issued in the 1970s, included
general requirements for fire prevention, detection and response. It
was not until 1981 that the NRC issued detailed requirements and
guidance on how to meet those requirements.
A serious fire at a nuclear power plant in the
mid-1970s revealed shortcomings in fire protection requirements. The
plant's fuel was not affected and no one was seriously hurt, but the
incident prompted a detailed examination of fire protection practices
and led to sweeping changes in the NRC's fire protection regulations.
Lessons learned from Browns Ferry fire
On March 22, 1975, workers at the Browns Ferry nuclear plant
in northern Alabama were using a candle to check for air leaks at
openings in a wall where trays of electrical cables pass from one room
to another. As a worker held a candle near one of the openings, the
flow of air through it drew the flame toward the polyurethane foam
that had recently been installed to seal the openings. The foam
ignited and fire spread along the cables, shorting out backup safety
systems as the cable insulation burned off.
Workers immediately tried to extinguish the fire,
without success, and also notified the control room. Shortly
afterward, a municipal fire department was called to the scene.
Operators manually shut down both units and were able to keep the fuel
covered with water and the plant adequately cooled throughout the
incident. However, fire fighting efforts were hampered by the limited
availability of breathing apparatus and reluctance to use water in
electrical equipment areas. The fire was officially declared
"out" more than seven hours after it started.
Four days later, the NRC appointed a special review
group to study the lessons learned and make recommendations. The
review group issued a report in February 1976 that identified a number
of needed improvements in fire protection requirements and programs.
The report noted that public health and safety were
protected during the incident at Browns Ferry despite significant
shortcomings in fire protection:
"The question naturally arises: How can a
serious fire that involved inoperability of so many important
systems result in no adverse effect on the public health and safety?
The answer is to be found in the defense-in-depth used to provide
safety in nuclear power plants today."
The same principle should be applied to fire
protection, suggested the review group:
"This defense-in-depth principle would be aimed
at achieving safety through an adequate balance in:
|
1. |
Preventing fires from getting
started. |
|
2. |
Detecting and extinguishing quickly such
fires as do get started and limiting their damage. |
|
3. |
Designing the plant to minimize the effect
of fires on essential functions." |
Designing the plant to minimize the effect of
fires on essential functions."
NRC issues fire protection rule
The NRC issued fire protection guidance to utilities shortly
after the Browns Ferry fire and, over the next several years,
developed a rule that sets detailed requirements related to fire
prevention and detection, fire brigade training, and other areas of
fire protection. The requirements were codified in 1981 in 10 CFR
50.48 and Appendix R to 10 CFR 50.
Among other things, the rule requires fire protection
equipment to limit damage done to structures and equipment that are
"important to safe shutdown." Nuclear plant operating
companies use various means—fire detectors, heat sensors, remote
cameras, automatic sprinklers and so on—depending on which area of
the plant is involved. These help ensure that a fire will be quickly
detected and extinguished. The inaccessibility of some plant areas
posed problems for firefighters battling the Browns Ferry fire. Some
burning cable trays, for example, were as much as 30 feet above the
floor and difficult to reach with fire hoses. Built-in fire
suppression systems are intended to solve this type of problem.
But the rule's requirement for "automatic"
suppression systems creates a different problem: If something triggers
the system falsely, there is a potential for electrical equipment to
be damaged by the suppression system—when no fire threat exists. So
some companies have asked the NRC's permission to use manually
activated suppression in areas where electrical equipment is located.
The NRC has granted a number of such requests, which require an
exemption from the rule's requirements.
The rule also requires that one set of systems needed
to safely shut down the plant be kept free of fire damage—one of the
major lessons from the Browns Ferry fire. The NRC changed its
regulations to require that designs for new plants—those that
started operating after Jan. 1, 1979—provide at least 20 feet of
separation between certain systems and components. But for plants
already built, the difficulty was how to provide the necessary
separation between systems.
In some cases, electrical circuits needed for safe
shutdown can be rerouted to separate them from a backup system. Where
this is not feasible or desirable, the rule provides another option:
fire barriers. A utility can meet the requirement with either a fire
barrier rated to survive a standard fire for one hour, plus automatic
suppression and detection equipment, or with a three-hour rated
barrier.
These fire rating requirements are somewhat arbitrary.
They apply equally to all areas where fire barriers are used,
regardless of the actual fire hazard in a given area. In practice,
however, the NRC has granted limited exemptions for plant areas where
the fire hazard is low and where features of the plant would make it
extremely difficult to install a fire barrier.
The rule also includes detailed requirements
pertaining to fire brigades—their formation, equipment and
training—as well as administrative controls governing the use and
storage of combustible materials, the use of ignition sources (welding
or grinding, for example), and periodic "housekeeping"
inspections to ensure that employees comply with these controls. If a
company wants to take a different approach to accomplish the same
objective-for example, make changes in the way it trains fire
brigades—it must apply to the NRC for an exemption to the rule.
The NRC has granted more than 1,200 exemptions to
specific requirements of the fire protection rule since it was issued
in 1981. Each exemption request involves a case-by-case safety review
by NRC staff.
Fire protection: Applying defense-in-depth
Nuclear power plant fire protection programs integrate plant
design features, management resources, training, equipment and
procedures to provide defense-in-depth protection of public health and
safety. Fire protection programs include:
Administrative controls—The introduction of
combustible materials into safety-related areas of the plant is
limited, and their handling, storage and use are strictly controlled.
For example, some inside walls are painted with easy-to-clean epoxy
paints that are combustible when they are being applied. To minimize
the possibility of fueling an accidental fire, bulk quantities of the
paint are stored outside the building and used only as needed. Other
administrative controls minimize ignition sources. Permits are
required, for example, before any "hot work" such as welding
can be performed. In addition, fire-watch guards are posted during the
performance of such welding operations.
Training—Utilities typically provide five
types of fire protection training for nuclear plant employees,
depending on their responsibilities: general, fire watch, fire
department and brigade, maintenance, and operations. All employees
receive training about the importance of fire prevention, how to
report a fire and any administrative controls that govern their work
activities.
Fire watches—Fire watches are used when
normal fire protection equipment (including barriers) is not
functional—while it is being serviced, for example. Employees who
participate in fire watches receive special training that includes the
location and use of fire extinguishers and other plant fire protection
equipment. Either fixed or roving fire watches are used, depending on
the situation.
Maintenance—All fire protection equipment
used in nuclear power plants is subject to regularly scheduled
preventive maintenance and testing.
Sharing industry experience—The nuclear
industry places great emphasis on sharing lessons learned from
experience. The Institute of Nuclear Power Operations regularly
collects, analyzes and distributes information on numerous aspects of
plant operation, including fire protection. Plants routinely receive
the latest data on potential fire hazards and take necessary actions
where appropriate.
Fire protection regulations: A need for update
and enhancement
The NRC and the industry agree that, in general, regulations
should become more risk-informed and performance-based. A
performance-based approach to fire safety in a nuclear power plant
would include an assessment of the actual risks in various areas-the
amount of combustible material, potential ignition sources, whether
fire suppression systems have been installed and so on. It also would
consider the relative importance of the systems and components in that
area to achieving and maintaining safe shutdown of the plant. Fire
protection measures would then be based on a more realistic assessment
of the actual fire hazard than is assumed in existing requirements.
Since 1995, the NRC and the industry have attempted to
transition fire protection to a more risk-informed, performance-based
structure. One of the industry's key objectives is to ensure that
plant fire protection programs are not affected adversely by any new
rule. Industry and NRC goals for risk-informed, performance-based fire
protection regulation can be achieved within the existing regulations.
In June 1998, the commission directed the NRC staff to
work with the National Fire Protection Association committee that is
developing NFPA Standard 805, a risk-informed, performance-based fire
protection standard for nuclear power plants. The NRC has initiated
rulemaking to allow nuclear plant operating companies to adopt this
standard as an alternative to existing regulations, if they choose,
when the standard is complete in late 2000. Companies also will be
able to use risk techniques from NFPA 805 if they choose to maintain
their current licensing bases. This achieves the industry goal of
risk-informing fire protection programs without making this approach
mandatory.
NRC is also risk-informing the inspection process. NRC
has developed baseline inspection guidance that involves routine
resident inspections of fire protection programs and triennial
regional team inspections of safe shutdown programs. Safety insights
from probabilistic safety studies are used on the front end of these
inspections to focus the inspection on safety-significant areas and at
the end of the inspection to assess the safety significance of the
findings.
The NRC is developing a comprehensive regulatory guide
to consolidate existing regulatory guidance for plants choosing to
maintain compliance with current regulations. This guidance is
intended by NRC to provide best practices for future plant fire
protection program changes.
|