Information Notice No. 91-17: Fire Safety of Temporary Installations or Services
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555
March 11, 1991
Information Notice No. 91-17: FIRE SAFETY OF TEMPORARY
INSTALLATIONS OR SERVICES
Addressees:
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose:
This information notice is intended to alert licensees to the fire hazards
that may arise because of inadequate engineering design and supervisory
control of electrical and mechanical systems temporarily installed to
support operational or maintenance activities at commercial nuclear power
reactors. It is expected that recipients will review the information for
applicability to their facilities and consider actions, as appropriate, to
avoid similar problems. However, suggestions contained in this information
notice do not constitute NRC requirements; therefore, no specific action or
written response is required.
Description of Circumstances:
On December 3, 1990, a fire occurred in the personnel access airlock between
the Unit 1 reactor building and the drywell at the Brunswick Steam Electric
Plant. Unit 1 was in a refueling outage and was defueled at the time. The
fire lasted approximately two hours. Both the inside and outside doors of
the airlock were open to accommodate the passage of numerous cables and
hoses in support of refueling outage activities in the drywell. The fire
spread along cables to just inside the drywell, but drywell damage was
limited to smoke and soot deposits. Most of the cables and hoses in the
airlock were destroyed and permanent airlock components were damaged. No
significant effects were observed in the reactor building. The fire was
caused by the overheating of electrical cables from the combined effects of
excessive current and insufficient heat dissipation. These cables were
supplying power to resistive heaters used for post-weld heat treatment
(PWHT) of recirculation system piping welds and were rated at 100 amps (free
air installation). At the time of the fire, two PWHT circuits were carrying
approximately 150 to 170 amps each. The licensee had arranged 72 cables
that supplied power to 36 PWHT circuits on a temporary fire-retardant wood
cable tray along with numerous other lines and cables, such as welding
leads, hydraulic hoses, drop cords, thermocouple lines,
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IN 91-17
March 11, 1991
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air hoses, and closed circuit television cables. All were enclosed in
individual plastic sleeves for contamination control. Also passing through
the airlock were miscellaneous other lines, cables, and ventilation ducts,
such that personnel could not gain access through the airlock. Initially,
the licensee had installed the cables and lines in an orderly manner, with
cables neatly bundled. However, the bundling and use of plastic sleeves to
control contamination significantly reduced the ability of the PWHT cables
to dissipate heat. The guidance in the Institute of Electrical and
Electronic Engineers (IEEE) Standard S-135 and the National Electric Code
(Articles 400 and 630) indicates that the cables should have been derated by
approximately 50 percent because of the spacing between them. The
combination of excessive current and inadequate spacing resulted in the
cables carrying over three times the recommended rated current. The
licensee and the NRC staff concluded that the temporary services passing
through the airlock were not properly engineered. Following the orderly
initial installation of temporary services through the airlock, additional
cables and hoses were pulled through in a haphazard manner wherever they
would fit. Services no longer needed could not be easily removed because of
the tangling and interference from other lines. These factors resulted in a
disorganized, congested, and confined space that further restricted the heat
dissipation of the PWHT cables and, once the fire started, seriously
hampered efforts to extinguish it.
Discussion:
The use of temporary services at power reactor facilities is routine,
especially in support of maintenance and other activities during outages.
In view of the magnitude and complexity of some temporary services, proper
engineering and, once installed, maintenance of the design basis become
significant.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate NRR project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact: D. J. Nelson, RII
(919) 457-9531
Attachment: List of Recently Issued NRC Information Notices
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