Information Notice 1999-01, Deterioration of High-Efficiency Particulate Air Filters in a Pressurized Water Reactor Containment Fan Cooler Unit
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001
January 20, 1999
DETERIORATION OF HIGH-EFFICIENCY
PARTICULATE AIR FILTERS IN A PRESSURIZED
WATER REACTOR CONTAINMENT FAN
COOLER UNIT
Addressees
All holders of licenses for nuclear power, research and test reactors; and fuel cycle facilities.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alert
addressees to previously unknown service life and service condition limitations of high
efficiency particulate air (HEPA) filters that are used in ventilation systems by licensees of
power, research and test reactors; and certain fuel cycle facilites. It is expected that recipients
will review the information for applicability to their facilities and consider actions, as appropriate.
However, suggestions contained in this information notice are not NRC requirements; therefore, no specific action or written response to this notice is required.
Descriotion of Circumstances
On September 13, 1998, the operators at Consolidated Edison's (Con Edison's) Indian Point 2 (IP-2) Nuclear Power Plant received a low-flow alarm on one of the five containment fan cooler
units (FCUs). Con Edison personnel inspected the FCU's internal components and found that
one of the HEPA filters in the bottom row had failed and clogged the fan intake screen. The
FCU contains a bank of 64 HEPA filters, each 2 feet by 2 feet in size. Five other filters near
the failed filter were badly damaged. To confirm the extent of the problem, Con Edison
subsequently inspected the other 4 FCUs. One FCU had HEPA filters in which the urethane
seal had pulled away from the filter frame and the filter medium had assumed an hour- glass
shape. Con Edson concluded that the problem had a potential common-mode failure
mechanism that could significantly degrade both the cooling of the FCU and the filtering by the
HEPA filters.
Discussion
The HEPA filters in the two affected FCUs were Series Model 8 manufactured by Flanders
Filter Corporation; they are no longer made. The Series 8 filter consists of a square stainless
steel frame and a convoluted filter medium made of glass fibers held together by an acrylic
latex binder and coated with a silicone waterproofing agent. The filter medium is secured to all
990122 An
c
IN 99-01 January 20, 1999 four sides of the filter frame by a urethane coating and, unlike many other HEPA filter designs, does not have internal stiffeners or corrugated separators to support the glass fibers. These
HEPA filters were installed in 1991 and, due to being located in the normal air flow, have been
in almost continuous use since then; many other FCU designs have the filters in service only
during testing or an accident.
Con Edison identified many causes contributing to the unexpected failure and degradation of
the HEPA filters, such as (1) excess water (from condensation as well as carryover from the
upstream de-misters, which had plugged or partially plugged drain lines) which Increased filter
loading and distortion, (2) inadequate surveillance for detecting filter degradation or determining
when HEPA filters should be replaced, and (3) no established service life. A technical report
prepared for Con Edison following testing of samples of new and used HEPA filter media
provided quantitative support for this root cause determination. While inherent weaknesses in
the FCU design (such as having the HEPA filters in the normal flow stream) and poor
preventive maintenance practices (such as not monitoring the condition of the upstream FCU
de-mister drains) were noted, previously unknown limitations regarding HEPA filter service life
and the effect of service conditions were revealed.
HEPA filters used in the FCUs at IP-2 are required by Technical Specifications to be
surveillance tested every refueling outage. Such testing involves (1) visual inspection in
accordance with ANSI Standard N510-1975 for indications of filter damage (e.g., filter medium
tears, cracks, or bums, and damage to seating gaskets) and excessive dirt loading, (2) a check
for filter bypass by a dioctylphthalate (DOP) aerosol efficiency test, and (3) measurement of air
flow and differential pressure across the filter bank. This testing does not check for evidence of
current or prior media wetting. The initial qualification testing of the HEPA filters, as specified in
Military Specification F-51068, did subject the filter to a continuous water spray during the
resistance-to-pressure test performed at higher than accident condition flows. However, the
filters were not subsequently subjected to any type of testing to demonstrate that they remain
capable of performing their intended function. Consequently, loss of structural strength and
deterioration can go undetected and can result in failure during design-basis conditions when
the filters will be subjected to a much higher temperature, much higher differential pressure and
much more entrained moisture than during normal service conditions.
Filter media testing found a significant loss of silicone waterproofing agent from filter media
samples that had seen a long service life - up to 7 years. This reduction allowed the filter
medium to absorb water readily; little or no observable water absorption was observed on new
filter media. As the water is absorbed, the medium expands and closes the medium filter
pores. However, since the differential pressure is typically measured across an entire bank of
filters, local water loading in one or more filters does not enable the overall differential pressure
to rise sufficiently to disclose a problem with the HEPA filters. Moreover, a damaged or failed
filter could reduce the differential pressure across the filter bank. Water absorption also
increases the weight of the filter medium and can weaken it. The service life of a filter is highly
dependent upon HEPA service conditions, which includes high moisture content, entrained
solids In the air, and elevated temperatures.
The Department of Energy (DOE) recently sponsored research into HEPA filter deterioration
when several HEPA filters in a ventilation system at the Rocky Flats Environmental Technology
Site failed. Those filters had been in service for more than 15 years and had been repeatedly
subjected to wetting by an upstream fire protection deluge system test. The testing conducted
involved filter media from a variety of HEPA filter manufacturers, although most manufacturers
~1- IN 99-01 January 20, 1999 use similar filter media. This research also showed significant losses in the tensile strength of
HEPA filter following the wetting of used filters; it also showed that the tensile strength was not
recovered fully restored after drying. Further water exposures resulted in additional losses in
filter media tensile strength. The results of this research were publicized at the 25th DOEINRC
Nuclear Air Cleaning and Treatment Conference. The DOE research data cannot be used to
quantify the useful life of a HEPA filter, but the data do demonstrate that there is a finite HEPA
filter life and that wetting of the filter medium reduces its strength.
In response to the research findings, Con Edison replaced the filters in the two affected FCUs
with new Flanders Series F & W filters that incorporate internal stiffeners to help support the
filter medium. Con Edison has limited the service cycle of the FCU HEPA filters to 6 years and
implemented inspections to confirm the following: (1) the integrity of the urethane seal between
the filter medium and filter housing, (2) proper drainage from the FCU, and (3) the extent of
water condensation and/or direct wetting of the filters.
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, the appropriate regional office, or the appropriate office of Nuclear Reactor
Regulation (NRR) Project Manager.
Dire
r
Division of Fuel Cycle Safety
and Safeguards
Office of Nuclear Material Safety
and Safeguards
David B. Matthews, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contacts:
Richard S. Barkley, Region I
610-337-5065 E-Mail: rsbl@nrc.gov
John J. Hayes, NRR
301-415-3167 E-Mail: hh@nrc.gov
John P. Segala, NRR
301-415-1858 E-Mail: jpsl@nrc.gov
Jerry Carter, NRR
301-415-1153 E-Mail: tjc@nrc.gov
Bill Troskoski, NMSS
301-415-8076 E-mail: wmt@nrc.gov
Attachments: List of Recently Issued NMSS Information Notices
List of Recently Issued NRC I foation Notices
- Vdss
jaflon:a-
A
&\\1 Attachment
December 15, 1998 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information
Date of
Notice No.
Subject- Issuance
Issued to
98-45 Cavitation Erosion of Letdown Line 12/15/98
All holders of operating licenses
Orifices Result in Fatigue Cracking
of Pipe Welds
for nuclear power reactors, except
those that have permanently
ceased operations and have
certified that fuel has been
permanently removed from the
reactor.
98-44 Ten-year Inservice Inspection
12110/98 (ISI) Program Update for Licensees
that Intend to Implement Risk-Informed
ISI of Piping
98-43
98-42
Leaks in the Emergency Diesel
Generator Lubricating Oil and
Jacket Cooling Water Piping
12/04/98
All holder of operating licenses
for nuclear power reactors, except
those that have permanently
ceased operations and have
certified that fuel has been
permanently removed from the
reactor
All holder of operating licenses
for nuclear power reactors, except
those licensees that have
permanently ceased operations
and have certified that fuel has
been permanently removed from
the reactor vessel
All holders of operating licenses
for nuclear power reactors
All holders of operating licenses
for nuclear power reactors, except
for those who have ceased
operations and have certified that
fuel has been permanently
removed from the reactor vessel
Implementation of 10 CFR 50.55a
12/01/98 (g) Inservice Inspection Requirements
98-41 Spurious Shutdown of Emergency
11/20/98
Diesel Generators from Design
Oversight
OL = Operating License
CP = Construction Permit
_
99-01 January 20, 1999 use similar filter media. This research also showed significant losses in the tensile strength of
HEPA filter following the wetting of used filters; it also showed that the tensile strength was not
recovered fully restored after drying. Further water exposures resulted in additional losses in
filter media tensile strength. The results of this research were publicized at the 25th DOE/NRC
Nuclear Air Cleaning and Treatment Conference. The DOE research data cannot be used to
quantify the useful life of a HEPA filter, but the data do demonstrate that there is a finite HEPA
filter life and that wetting of the filter medium reduces its strength.
In response to the research findings, Con Edison replaced the filters in the two affected FCUs
with new Flanders Series F & W filters that incorporate internal stiffeners to help support the
filter medium. Con Edison has limited the service cycle of the FCU HEPA filters to 6 years and
implemented inspections to confirm the following: (1) the integrity of the urethane seal between
the filter medium and filter housing, (2) proper drainage from the FCU, and (3) the extent of
water condensation and/or direct wetting of the filters.
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, the appropriate regional office, or the appropriate office of Nuclear Reactor
Regulation (NRR) Project Manager.
orig IsI'd by
orig Is! 'd by
Elizabeth 0. Ten Eyck, Director
David B. Matthews, Director
Division of Fuel Cycle Safety
Division of Reactor Program Management
and Safeguards
Office of Nuclear Reactor Regulation
Office of Nuclear Material Safety
and Safeguards
Technical Contacts:
Richard S. Barkley, Region I
John J. Hayes, NRR
610-337-5065
301-415-3167 E-Mail: rsbl@nrc.gov
E-Mail: jjh@nrc.gov
John P. Segala, NRR
Jerry Carter, NRR
301-415-1858
301-415-1153 E-Mail: jpslnrc.gov
E-Mail: tjc~nrc.gov
Bill Troskoski, NMSS
301-415-8076 E-mail: wmt@nrc.gov
Attachments: List of Recently Issued NMSS Information Notices
List of Recently Issued NRC Information Notices
DOCUMENT NAME: g:\\TJC\\HEPA2AIN.WPD
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OFFICIAL RECORD COPY
IN 98-xx
December xx, 1998 use similar filter media. This research also showed significant losses in the tensile strength of
HEPA filter following the wetting of used filters; it also showed that the tensile strength was not
recovered fully after drying. Further water exposures resulted in additional losses in filter media
tensile strength. The results of this research were publicized at the 25th DOE/NRC NuclearAir
Cleaning and Treatment Conference. The DOE research data cannot be used to quantify the
useful life of a HEPA filter, but the data do demonstrate that there is a finite HEPA filter life and
that wetting of the filter medium reduces its strength.
In response to the research findings, Con Edison replaced the filters in the two affected FCUs
with new Flanders Series F & W filters that incorporate internal stiffeners to help support the
filter medium. Con Edison has limited the service cycle of the FCU HEPA filters to 6 years and
implemented inspections to confirm the following: (1) the integrity of the urethane seal between
the filter medium and filter housing, (2) proper drainage from the FCU, and (3) the extent of
water condensation and/or direct wetting of the filters.
Con Edison has also applied for a Technical Specification amendment that would delete the
requirement for HEPA filters and the downstream charcoal beds from the containment FCUs.
This amendment is based on analyses that show the equipment can be removed without
significantly affecting the radiological consequences of a design-basis loss-of-coolant accident
at IP-2.
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.
Elizabeth Q. Ten Eyck, Director
Jack W Roe, Acting Director
Division of Fuel Cycle Safety
Division of Reactor Program Management
and Safeguards
Office of Nuclear Reactor Regulation
Office of Nuclear Material Safety
and Safeguards
Technical Contacts:
Richard S. Barkley, Region I
John J. Hayes, NRR
610-337-5065
301-415-3167 E-Mail: rsbl@nrc.gov
E-Mail: jh@nrc.gov
John P. Segala, NRR
Jerry Carter, NRR
301-415-1858
301-415-1153 E-Mail: jps1@nrc.gov
E-Mail: tjcenrc.gov
ta~h~merS List of Recently Issued NRC Information Notices
DOCUW
NT NAME:
To receive a copy of this document, Indicate In the box C=Copy w/o attachment/enclosure E=Copy with attachmentfnclosure N= No copy
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