Information Notice 1994-28, Potential Problems with Fire-Barrier Penetration Seals
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C.
20555
April 5, 1994
NRC INFORMATION NOTICE 94-28: POTENTIAL PROBLEMS WITH FIRE-BARRIER
PENETRATION SEALS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to potential problems in installed fire-barrier
penetration seals that may have gone undetected as a result of inadequate
surveillance inspection procedures and inadequate acceptance criteria. 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 are not
NRC requirements; therefore, no specific action or written response is
required.
Description of Circumstances
Nine Mile Point Nuclear Station, Unit 1, (NMP 1)
On April 25, 1988, Niagara Mohawk Power Corporation, the licensee for NMP 1, reported (licensee event report [LER] 88-009) that on March 26, 1988, it had
determined that some existing fire barriers were inoperable because the
barriers contained potentially nonfunctional penetrations through the fire- barrier.
Initially, the licensee verified fire detection on one side of the
affected penetrations, established a fire-watch patrol, and walked down
additional potentially inoperable fire barriers. When these walkdowns
revealed additional potentially nonfunctional fire-barrier penetrations, the
licensee took additional corrective actions that included performing a
100-percent visual reinspection of the penetration seals, performing an
engineering evaluation of each penetration that did not meet accepted design
configurations, and upgrading its surveillance inspection procedure.
Supplements 1 and 2 to LER 88-009 (June 8 and August 16, 1990, respectively)
attributed the root cause of the event to personnel error due to a lack of
understanding of the fire-barrier commitments; a contributing cause was a lack
of required documentation and inadequate surveillance procedures. Additional
documentation of this event can be found in NRC Region I Inspection Reports
50-220/88-15 and 50-220/89-33 (June 2, 1988, and March 8, 1990, respectively).
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IN 94-28 April 5, 1994 James A. FitzPatrick Nuclear Power Plant (FitzPatrick)
During the performance of fire-barrier penetration surveillance inspections by
the licensee at FitzPatrick between May and November 1990, inspectors
documented numerous nonconforming conditions. One predominant condition was
the lack of adequate damming material. In August 1990, the licensee Quality
Assurance group forwarded an adverse quality condition report describing these
nonconforming conditions to the Site Engineering group for evaluation. Site
Engineering determined that the barriers were acceptable pending further
evaluation by the Corporate Engineering group. No compensatory fire watches
were established at that time. In December 1990, after additional condition
reports were submitted to Site Engineering documenting these nonconforming
conditions, an operability determination was performed and 2-hour fire patrols
were established.
In December 1990, the NRC reviewed the licensee activities
(Region I Inspection Report 50-333/90-09, March 1, 1991) and concluded that
licensee control of the fire-barrier penetration seals was inadequate because:
(1) the licensee had not documented determinations of the ability of the
nonconforming penetrations to perform as fire barriers for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />; (2) there
was no documented justification for establishing 2-hour fire patrols when the
Technical Specifications required continuous compensatory fire watches; and
(3) the inspection criteria used by the licensee were inadequate because the
criteria did not provide the information necessary to allow inspectors to
determine that the seals were not in conformance with the as-built design.
In October 1991 a NRC diagnostic evaluation team noted problems regarding the
implementation of the fire-protection program and Appendix R regulations at
FitzPatrick. As a result, a special NRC fire-protection review was conducted
at FitzPatrick in March 1992 (Region I Inspection Report 50-333/92-80,
April 8, 1992). The special NRC fire-protection review team conducted a
walkdown of fire barriers and reviewed the corrective actions initiated by the
licensee as a result of the concerns identified in Region I Inspection Report
50-333/90-09 and the findings in the licensee July 1991 triennial fire- protection audit. The team noted that some of the existing penetration seals
in fire-barrier walls were made of a combustible urethane foam and fiberglass.
In addition, several silicone foam seals were degraded or were not well
maintained. The licensee initiated a corrective action program that included:
(1) reverifying the location of the 10 CFR Part 50, Appendix R, required fire
barriers in the plant; (2) performing a baseline inspection of all fire- barrier penetration seals associated with Appendix R and the fire-protection
license condition in the plant license; and (3) evaluating the deficiencies, making operability determinations, and completing repairs as required.
Vermont Yankee Nuclear Power Station (Vermont Yankee)
On January 15, 1993, Vermont Yankee Nuclear Power Corporation, the licensee
for Vermont Yankee, reported (LER 93-001) that on December 17, 1992, an
insulated pipe-penetration seal was identified as potentially not in
IN 94-28 April 5, 1994 compliance with design requirements. The seal was only partially filled with
the expected fire-barrier material because it was partially filled with
insulation. A second similar insulated pipe penetration seal was identified
on December 22, 1992. The following day the licensee declared all similar
insulated pipe penetrations inoperable and compensatory measures were
instituted. The licensee stated that these conditions had probably existed
since the fire-barrier penetration seals were upgraded by a 1979/1980 fire- barrier modification. Supplement 1 to LER 93-001 (March 5, 1993) indicated
that certain noninsulated penetrations and the boot-seal design for lines with
large displacements were also of concern. The licensee assigned the following
root causes: (1) inadequate documentation of assumptions during the 1979 effort to scope the penetration sealing effort, (2) inadequate procedures,
(3) inattention to detail, (4) failure to follow procedures, and (5) an
inadequate surveillance procedure. Additional documentation of this event can
be found in NRC Region I Inspection Reports 50-271/92-24 and 50-271/93-05 (February 1 and April 1, 1993, respectively).
Discussion
This notice alerts addressees to the possibility that some installed fire- barrier penetration seals may contain nonconforming conditions that have not
been identified because of inadequate acceptance criteria and inadequate
surveillance inspection procedures. Additionally, nonconforming conditions
may go undetected if the surface of the seal is covered by thermal insulation
or damming material.
NRC requirements and guidelines for fire-barrier penetration seals are
contained in various documents, including 10 CFR Part 50, Appendix R, "Fire
Protection Program for Nuclear Power Facilities Operating Prior to January 1,
1979;" Branch Technical Position APCSB 9.5-1, Appendix A, "Guidelines for Fire
Protection for Nuclear Power Plants Docketed Prior to July 1, 1976;" and
NUREG-0800, "Standard Review Plan." The extent to which these requirements or
guidelines are applicable to a specific nuclear power plant depends on plant
age, commitments established by the licensee in developing the fire protection
plan, the staff safety evaluation reports and supplements, and the license
conditions pertaining to fire protection.
The goal of these requirements and guidelines is to ensure that fire-barrier
penetration seals will remain in place and retain their integrity when exposed
to a fire. By so doing, there is reasonable assurance that the effects of a
fire will be limited to discrete fire areas and that one division of safe- shutdown-related systems will remain free of fire damage.
Related Generic Communications
The NRC has issued other generic communications that have discussed
requirements, guidance, and potential problems with fire-barrier penetration
seals. For example:
I.
-:
IN 94-28 April 5, 1994 (1) On April 24, 1986, the NRC issued Generic Letter 86-10, "Implementation
of Fire Protection Requirements,* to provide information concerning the
interpretation and implementation of NRC fire-protection requirements.
(2) On February 5, 1988, the NRC issued Information Notice (IN) 88-04,
"Inadequate Qualification and Documentation of Fire Barrier Penetration
Seals,' to alert addressees that some installed fire-barrier penetration
seal designs may not be adequately qualified for the design rating of
the penetrated fire barrier.
This IN discussed an NRC staff review
which identified some instances where installed fire-barrier penetration
seal configurations were not qualified by adequate testing or were not
supported by adequate qualification documentation.
(3) On August 4, 1988, the NRC issued IN 88-56, "Potential Problems With
Silicone Foam Fire Barrier Penetration Seals," to alert addressees to
potential problems in their installed fire-barrier penetration seals
that could result in the reduction of fire-resistive capabilities for
protection of safety-related redundant equipment and electrical power
and control circuits. The IN discussed a vendor report (10 CFR Part 21,
"Reporting of Defects and Noncompliance') which identified the potential
for nonconforming conditions, such as splits, gaps, voids, and lack of
fill in the sealing material not being detected during routine
inspections because the surface of the seal material is typically
covered by damming material.
(4) On August 9, 1988, the NRC issued IN 88-04, Supplement 1, "Inadequate
Qualification and Documentation of Fire Barrier Penetration Seals," to
alert addressees to problems caused by potential misapplication of
silicone foam material used in penetration openings at nuclear power
plants.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate 0 fice of
Nuclear Reactor Regulation (NRR) project mana er.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Fred L. Bower, III, RI
(610) 337-5328
Jeff Holmes, NRR
(301) 504-2280
Attachment:
List of Recently Issued NRC Information Notices
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Attachment
April 5, 1994 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information
Date of
Notice No.
Subject
Issuance
Issued to
94-27
94-26
Facility Operating
Concerns Resulting from
Local Area Flooding
Personnel Hazards and
Other Problems from
Smoldering Fire-Retard- ant Material in the
Drywell of a Boiling-
Water Reactor
03/31/94
03/28/94
All holders of OLs or CPs
for nuclear power reactors.
All holders of OLs or CPs
for nuclear power reactors.
93-17, Rev. 1
Safety Systems Response
to Loss of Coolant and
Loss of Offsite Power
03/25/94
All holders of OLs or CPs
for nuclear power.
94-25
94-24
94-23
94-22
94-21
Failure of Containment
Spray Header Valve to
Open due to Excessive
Pressure from Inertial
Effects of Water
Inadequate Maintenance
of Uninterruptible Power
Supplies and Inverters
Guidance to Hazardous,
Radioactive and Mixed
Waste Generators on the
Elements of a Waste
Minimization Program
Fire Endurance and
Ampacity Derating Test
Results for 3-Hour Fire- Rated Thermo-Lag 330-1
Fire Barriers
Regulatory Requirements
when No Operations are
being Performed
03/25/94
03/24/94
03/25/94
03/16/94
03/18/94
All holders of OLs or CPs
for nuclear power reactors.
All holders of OLs or CPs
for nuclear power reactors.
All NRC Licensees.
All holders of OLs or CPs
for nuclear power reactors.
All fuel cycle and materials
licensees.
OL - Operating License
CP - Construction Permit
IN 94-28 April 5, 1994 (1) On April 24, 1986, the NRC issued Generic Letter 86-10, "Implementation
of Fire Protection Requirements," to provide information concerning the
interpretation and implementation of NRC fire-protection requirements.
(2) On February 5, 1988, the NRC issued Information Notice (IN) 88-04,
"Inadequate Qualification and Documentation of Fire Barrier Penetration
Seals," to alert addressees that some installed fire-barrier penetration
seal designs may not be adequately qualified for the design rating of
the penetrated fire barrier. This IN discussed an NRC staff review
which identified some instances where installed fire-barrier penetration
seal configurations were not qualified by adequate testing or were not
supported by adequate qualification documentation.
(3) On August 4, 1988, the NRC issued IN 88-56, "Potential Problems With
Silicone Foam Fire Barrier Penetration Seals," to alert addressees to
potential problems in their installed fire-barrier penetration seals
that could result in the reduction of fire-resistive capabilities for
protection of safety-related redundant equipment and electrical power
and control circuits. The IN discussed a vendor report (10 CFR Part 21,
"Reporting of Defects and Noncompliance") which identified the potential
for nonconforming conditions, such as splits, gaps, voids, and lack of
fill in the sealing material not being detected during routine
inspections because the surface of the seal material is typically
covered by damming material.
(4) On August 9, 1988, the NRC issued IN 88-04, Supplement 1, "Inadequate
Qualification and Documentation of Fire Barrier Penetration Seals," to
alert addressees to problems caused by potential misapplication of
silicone foam material used in penetration openings at nuclear power
plants.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR)
project manager.
Ogina ligned by
Brian K. Grimes, Director
It
L dme
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Fred L. Bower, III, RI
Jeff Holmes, NRR
(610) 337-5328
(301) 504-2280
Attachment: List of Recently Issued NRC Information Notices
Transmitted by TTMartin memorandum to TEMurley dated June 9. 1993
- see previous concurrence
DOC NAME: 94-28.IN
l*OGCB/DORS/NRR
- Tech Editor
- Region I
RJKiessel
RSanders
FLBower,III
2/22/94
2/22/94
3/3/94
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- Region I
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3/17/94
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IN 94-xx
March xx, 1994 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts:
Fred L. Bower, III, Region I
(215) 337-5328
Jeff Holmes, NRR
(301) 504-2280
Attachment: List of Recently Issued NRC Information Notices
Transmitted by TTMartin memorandum to TEMurley dated June 9. 1993
- see previous concurrence
- OGCB/DORS/NRR
- Tech Editor
- Region I
RJKiessel
RSanders
FLBower,III
2/22/94
2/22/94
3/ 3/94
- Region I
- Region I
- SPLB/DSSA/NRR
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ARBlough
JTWiggins
JHolmes
KSWest
3/ 3/94
3/ 3/94
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IN 94-xx
March xx, 1994 This information notice requires no specific action or written response.
If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts:
Fred L. Bower,
(215) 337-5328
III, Region I
Jeffrey Holmes, NRR
(301) 504-2280
Attachment:
List of Recently Issued NRC Information Notices
Transmitted by TTMartin memorandum to TEMurley dated June 9. 1993
- see previous concurrence
- OGCB/DORS/NRR
- Tech Editor
- Region I
RJKiessel
RSanders
FLBower,III
2/22/94
2/22/94
3/ 3/94
- Region I
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This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one-of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts:
Fred L. Bower, III, Region I
(215) 337-5328
Jeffrer Holmes, NRR
(301) 504-2280
Attachment: List of Recently Issued NRC Information Notices
- Transmitted by TTMartin memorandum to TEMurley dated June 9. 1993 OGCB/DORS/NRR
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