Information Notice 1999-01, Deterioration of High-Efficiency Particulate Air Filters in a Pressurized Water Reactor Containment Fan Cooler Unit: Difference between revisions

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{{#Wiki_filter:t UNITED STATES NUCLEAR REGULATORY
{{#Wiki_filter:t


COMMISSION
UNITED STATES


===OFFICE OF NUCLEAR REACTOR REGULATION===
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D.C. 20555-0001 January 20, 1999 NRC INFORMATION


NOTICE 99-01: DETERIORATION
OFFICE OF NUCLEAR REACTOR REGULATION


OF HIGH-EFFICIENCY
WASHINGTON, D.C. 20555-0001 January 20, 1999 NRC INFORMATION NOTICE 99-01:                    DETERIORATION OF HIGH-EFFICIENCY


PARTICULATE
PARTICULATE AIR FILTERS IN A PRESSURIZED


===AIR FILTERS IN A PRESSURIZED===
WATER REACTOR CONTAINMENT FAN
WATER REACTOR CONTAINMENT


FAN COOLER UNIT
COOLER UNIT


==Addressees==
==Addressees==
All holders of licenses for nuclear power, research and test reactors;  
All holders of licenses for nuclear power, research and test reactors; and fuel cycle facilities.
and fuel cycle facilities.


==Purpose==
==Purpose==
The U.S. Nuclear Regulatory
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alert


Commission (NRC) is issuing this information
addressees to previously unknown service life and service condition limitations of high


notice to alert addressees
efficiency particulate air (HEPA) filters that are used in ventilation systems by licensees of


to previously
power, research and test reactors; and certain fuel cycle facilites. It is expected that recipients


unknown service life and service condition
will review the information for applicability to their facilities and consider actions, as appropriate.


limitations
However, suggestions contained in this information notice are not NRC requirements; therefore, no specific action or written response to this notice is required.


of high efficiency
Descriotion of Circumstances


particulate
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


air (HEPA) filters that are used in ventilation
units (FCUs). Con Edison personnel inspected the FCU's internal components and found that


systems by licensees
one of the HEPA filters in the bottom row had failed and clogged the fan intake screen. The


of power, research and test reactors;
FCU contains a bank of 64 HEPA filters, each 2 feet by 2 feet in size. Five other filters near
and certain fuel cycle facilites.


===It is expected that recipients===
the failed filter were badly damaged. To confirm the extent of the problem, Con Edison
will review the information


for applicability
subsequently inspected the other 4 FCUs. One FCU had HEPA filters in which the urethane


to their facilities
seal had pulled away from the filter frame and the filter medium had assumed an hour- glass


and consider actions, as appropriate.
shape. Con Edson concluded that the problem had a potential common-mode failure


However, suggestions
mechanism that could significantly degrade both the cooling of the FCU and the filtering by the


contained
HEPA filters.


in this information
Discussion


notice are not NRC requirements;
The HEPA filters in the two affected FCUs were Series Model 8 manufactured by Flanders
therefore, no specific action or written response to this notice is required.Descriotion


of Circumstances
Filter Corporation; they are no longer made. The Series 8 filter consists of a square stainless


On September
steel frame and a convoluted filter medium made of glass fibers held together by an acrylic


13, 1998, the operators
latex binder and coated with a silicone waterproofing agent. The filter medium is secured to all


at Consolidated
990122                                                        An                                  c


Edison's (Con Edison's)
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
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
HEPA filters were installed in 1991 and, due to being located in the normal air flow, have been


inspected
in almost continuous use since then; many other FCU designs have the filters in service only


the FCU's internal components
during testing or an accident.


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
Con Edison identified many causes contributing to the unexpected failure and degradation of


inspected
the HEPA filters, such as (1) excess water (from condensation as well as carryover from the


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
upstream de-misters, which had plugged or partially plugged drain lines) which Increased filter


that the problem had a potential
loading and distortion, (2) inadequate surveillance for detecting filter degradation or determining


common-mode
when HEPA filters should be replaced, and (3) no established service life. A technical report


failure mechanism
prepared for Con Edison following testing of samples of new and used HEPA filter media


that could significantly
provided quantitative support for this root cause determination. While inherent weaknesses in


degrade both the cooling of the FCU and the filtering
the FCU design (such as having the HEPA filters in the normal flow stream) and poor


by the HEPA filters.Discussion
preventive maintenance practices (such as not monitoring the condition of the upstream FCU


The HEPA filters in the two affected FCUs were Series Model 8 manufactured
de-mister drains) were noted, previously unknown limitations regarding HEPA filter service life


by Flanders Filter Corporation;
and the effect of service conditions were revealed.
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
HEPA filters used in the FCUs at IP-2 are required by Technical Specifications to be


agent. The filter medium is secured to all 990122 An c
surveillance tested every refueling outage. Such testing involves (1) visual inspection in


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
accordance with ANSI Standard N510-1975 for indications of filter damage (e.g., filter medium


or corrugated
tears, cracks, or bums, and damage to seating gaskets) and excessive dirt loading, (2) a check


separators
for filter bypass by a dioctylphthalate (DOP) aerosol efficiency test, and (3) measurement of air


to support the glass fibers. These HEPA filters were installed
flow and differential pressure across the filter bank. This testing does not check for evidence of


in 1991 and, due to being located in the normal air flow, have been in almost continuous
current or prior media wetting. The initial qualification testing of the HEPA filters, as specified in


use since then; many other FCU designs have the filters in service only during testing or an accident.Con Edison identified
Military Specification F-51068, did subject the filter to a continuous water spray during the


many causes contributing
resistance-to-pressure test performed at higher than accident condition flows. However, the


to the unexpected
filters were not subsequently subjected to any type of testing to demonstrate that they remain


failure and degradation
capable of performing their intended function. Consequently, loss of structural strength and


of the HEPA filters, such as (1) excess water (from condensation
deterioration can go undetected and can result in failure during design-basis conditions when


as well as carryover
the filters will be subjected to a much higher temperature, much higher differential pressure and


from the upstream de-misters, which had plugged or partially
much more entrained moisture than during normal service conditions.


plugged drain lines) which Increased
Filter media testing found a significant loss of silicone waterproofing agent from filter media


filter loading and distortion, (2) inadequate
samples that had seen a long service life - up to 7 years. This reduction allowed the filter


surveillance
medium to absorb water readily; little or no observable water absorption was observed on new


for detecting
filter media. As the water is absorbed, the medium expands and closes the medium filter


filter degradation
pores. However, since the differential pressure is typically measured across an entire bank of


or determining
filters, local water loading in one or more filters does not enable the overall differential pressure


when HEPA filters should be replaced, and (3) no established
to rise sufficiently to disclose a problem with the HEPA filters. Moreover, a damaged or failed


service life. A technical
filter could reduce the differential pressure across the filter bank. Water absorption also


report prepared for Con Edison following
increases the weight of the filter medium and can weaken it. The service life of a filter is highly


testing of samples of new and used HEPA filter media provided quantitative
dependent upon HEPA service conditions, which includes high moisture content, entrained


support for this root cause determination.
solids In the air, and elevated temperatures.


While inherent weaknesses
The Department of Energy (DOE) recently sponsored research into HEPA filter deterioration


in the FCU design (such as having the HEPA filters in the normal flow stream) and poor preventive
when several HEPA filters in a ventilation system at the Rocky Flats Environmental Technology
 
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
Site failed. Those filters had been in service for more than 15 years and had been repeatedly


subjected
subjected to wetting by an upstream fire protection deluge system test. The testing conducted


to wetting by an upstream fire protection
involved filter media from a variety of HEPA filter manufacturers, although most manufacturers


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


~1-IN 99-01 January 20, 1999 use similar filter media. This research also showed significant
HEPA filter following the wetting of used filters; it also showed that the tensile strength was not


losses in the tensile strength of HEPA filter following
recovered fully restored after drying. Further water exposures resulted in additional losses in


the wetting of used filters; it also showed that the tensile strength was not recovered
filter media tensile strength. The results of this research were publicized at the 25th DOEINRC


fully restored after drying. Further water exposures
Nuclear Air Cleaning and Treatment Conference. The DOE research data cannot be used to


resulted in additional
quantify the useful life of a HEPA filter, but the data do demonstrate that there is a finite HEPA


losses in filter media tensile strength.
filter life and that wetting of the filter medium reduces its strength.


The results of this research were publicized
In response to the research findings, Con Edison replaced the filters in the two affected FCUs


at the 25th DOEINRC Nuclear Air Cleaning and Treatment
with new Flanders Series F & W filters that incorporate internal stiffeners to help support the


Conference.
filter medium. Con Edison has limited the service cycle of the FCU HEPA filters to 6 years and


The DOE research data cannot be used to quantify the useful life of a HEPA filter, but the data do demonstrate
implemented inspections to confirm the following: (1) the integrity of the urethane seal between


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
the filter medium and filter housing, (2) proper drainage from the FCU, and (3) the extent of


internal stiffeners
water condensation and/or direct wetting of the filters.


to help support the filter medium. Con Edison has limited the service cycle of the FCU HEPA filters to 6 years and implemented
This information notice requires no specific action or written response. If you have any


inspections
questions about the information in this notice, please contact one of the technical contacts


to confirm the following:
listed below, the appropriate regional office, or the appropriate office of Nuclear Reactor
(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
Regulation (NRR) Project Manager.


and/or direct wetting of the filters.This information
Dire r                David B. Matthews, Director


notice requires no specific action or written response.
Division of Fuel Cycle Safety                    Division of Reactor Program Management


If you have any questions
and Safeguards                                  Office of Nuclear Reactor Regulation


about the information
===Office of Nuclear Material Safety===
 
and Safeguards
in this notice, please contact one of the technical
 
contacts listed below, the appropriate


regional office, or the appropriate
Technical Contacts:        Richard S. Barkley, Region I                John J. Hayes, NRR


office of Nuclear Reactor Regulation (NRR) Project Manager.Dire r Division of Fuel Cycle Safety and Safeguards
610-337-5065                                301-415-3167 E-Mail: rsbl@nrc.gov                        E-Mail: hh@nrc.gov


===Office of Nuclear Material Safety and Safeguards===
John P. Segala, NRR                          Jerry Carter, NRR
David B. Matthews, Director Division of Reactor Program Management


===Office of Nuclear Reactor Regulation===
301-415-1858                                301-415-1153 E-Mail: jpsl@nrc.gov                        E-Mail: tjc@nrc.gov
Technical


Contacts: Richard S. Barkley, Region I 610-337-5065 E-Mail: rsbl@nrc.gov
Bill Troskoski, NMSS


John J. Hayes, NRR 301-415-3167 E-Mail: hh@nrc.gov
301-415-8076 E-mail: wmt@nrc.gov


John P. Segala, NRR 301-415-1858 E-Mail: jpsl@nrc.gov
Attachments: List of Recently Issued NMSS Information Notices


Jerry Carter, NRR 301-415-1153 E-Mail: tjc@nrc.gov
List of Recently Issued NRC I foation Notices


Bill Troskoski, NMSS 301-415-8076 E-mail: wmt@nrc.gov
#Vdss                        jaflon:a-


Attachments:
A
List of Recently Issued NMSS Information


Notices List of Recently Issued NRC I foation Notices#Vdss jaflon:a- A&\1 Attachment
&\1                                     Attachment


IN 98-45 December 15, 1998 LIST OF RECENTLY ISSUED NRC INFORMATION
IN 98-45 December 15, 1998 LIST OF RECENTLY ISSUED


NOTICES Information
NRC INFORMATION NOTICES


Date of Notice No. Subject- Issuance Issued to 98-45 Cavitation
Information                                          Date of


Erosion of Letdown Line 12/15/98 All holders of operating
Notice No.            Subject-                      Issuance  Issued to


licenses Orifices Result in Fatigue Cracking of Pipe Welds for nuclear power reactors, except those that have permanently
98-45            Cavitation Erosion of Letdown Line 12/15/98  All holders of operating licenses


ceased operations
Orifices Result in Fatigue Cracking          for nuclear power reactors, except


and have certified
of Pipe Welds                                those that have permanently


that fuel has been permanently
ceased operations and have


removed from the reactor.98-44 Ten-year Inservice
certified that fuel has been


Inspection
permanently removed from the


12110/98 (ISI) Program Update for Licensees that Intend to Implement
reactor.


Risk-Informed
98-44            Ten-year Inservice Inspection        12110/98 All holder of operating licenses


ISI of Piping 98-43 98-42 Leaks in the Emergency
(ISI) Program Update for Licensees            for nuclear power reactors, except


Diesel Generator
that Intend to Implement Risk-Informed        those that have permanently


Lubricating
ISI of Piping                                ceased operations and have


Oil and Jacket Cooling Water Piping 12/04/98 All holder of operating
certified that fuel has been


licenses for nuclear power reactors, except those that have permanently
permanently removed from the


ceased operations
reactor


and have certified
98-43            Leaks in the Emergency Diesel        12/04/98 All holder of operating licenses


that fuel has been permanently
Generator Lubricating Oil and                for nuclear power reactors, except


removed from the reactor All holder of operating
Jacket Cooling Water Piping                  those licensees that have


licenses for nuclear power reactors, except those licensees
permanently ceased operations


that have permanently
and have certified that fuel has


ceased operations
been permanently removed from


and have certified
the reactor vessel


that fuel has been permanently
98-42            Implementation of 10 CFR 50.55a 12/01/98      All holders of operating licenses


removed from the reactor vessel All holders of operating
(g) Inservice Inspection Requirements        for nuclear power reactors


licenses for nuclear power reactors All holders of operating
98-41            Spurious Shutdown of Emergency      11/20/98 All holders of operating licenses


licenses for nuclear power reactors, except for those who have ceased operations
Diesel Generators from Design                for nuclear power reactors, except


and have certified
Oversight                                    for those who have ceased


that fuel has been permanently
operations and have certified that


removed from the reactor vessel Implementation
fuel has been permanently


of 10 CFR 50.55a 12/01/98 (g) Inservice
removed from the reactor vessel


Inspection
OL = Operating License


===Requirements===
CP = Construction Permit
98-41 Spurious Shutdown of Emergency


11/20/98 Diesel Generators
_    99-01 January 20, 1999 use similar filter media. This research also showed significant losses in the tensile strength of


from Design Oversight OL = Operating
HEPA filter following the wetting of used filters; it also showed that the tensile strength was not


License CP = Construction
recovered fully restored after drying. Further water exposures resulted in additional losses in


Permit
filter media tensile strength. The results of this research were publicized at the 25th DOE/NRC


_ 99-01 January 20, 1999 use similar filter media. This research also showed significant
Nuclear Air Cleaning and Treatment Conference. The DOE research data cannot be used to


losses in the tensile strength of HEPA filter following
quantify the useful life of a HEPA filter, but the data do demonstrate that there is a finite HEPA


the wetting of used filters; it also showed that the tensile strength was not recovered
filter life and that wetting of the filter medium reduces its strength.


fully restored after drying. Further water exposures
In response to the research findings, Con Edison replaced the filters in the two affected FCUs


resulted in additional
with new Flanders Series F & W filters that incorporate internal stiffeners to help support the


losses in filter media tensile strength.
filter medium. Con Edison has limited the service cycle of the FCU HEPA filters to 6 years and


The results of this research were publicized
implemented inspections to confirm the following: (1) the integrity of the urethane seal between


at the 25th DOE/NRC Nuclear Air Cleaning and Treatment
the filter medium and filter housing, (2) proper drainage from the FCU, and (3) the extent of


Conference.
water condensation and/or direct wetting of the filters.


The DOE research data cannot be used to quantify the useful life of a HEPA filter, but the data do demonstrate
This information notice requires no specific action or written response. If you have any


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
questions about the information in this notice, please contact one of the technical contacts


internal stiffeners
listed below, the appropriate regional office, or the appropriate office of Nuclear Reactor


to help support the filter medium. Con Edison has limited the service cycle of the FCU HEPA filters to 6 years and implemented
Regulation (NRR) Project Manager.


inspections
orig IsI'd by                                      orig Is! 'd by


to confirm the following:
Elizabeth 0. Ten Eyck, Director                        David B. Matthews, Director
(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
Division of Fuel Cycle Safety                          Division of Reactor Program Management


and/or direct wetting of the filters.This information
and Safeguards                                        Office of Nuclear Reactor Regulation


notice requires no specific action or written response.
Office of Nuclear Material Safety
 
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
and Safeguards


===Office of Nuclear Reactor Regulation===
Technical Contacts:        Richard S. Barkley, Region I                      John J. Hayes, NRR
Office of Nuclear Material Safety and Safeguards


Technical
610-337-5065                                      301-415-3167 E-Mail: rsbl@nrc.gov                              E-Mail: jjh@nrc.gov


Contacts:
John P. Segala, NRR                                Jerry Carter, NRR
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
301-415-1858                                      301-415-1153 E-Mail: jpslnrc.gov                                E-Mail: tjc~nrc.gov


John P. Segala, NRR Jerry Carter, NRR 301-415-1858
Bill Troskoski, NMSS
301-415-1153 E-Mail: jpslnrc.gov


E-Mail: tjc~nrc.gov
301-415-8076 E-mail: wmt@nrc.gov


Bill Troskoski, NMSS 301-415-8076 E-mail: wmt@nrc.gov
Attachments: List of Recently Issued NMSS Information Notices


Attachments:
List of Recently Issued NRC Information Notices
List of Recently Issued NMSS Information


Notices List of Recently Issued NRC Information
DOCUMENT NAME: g:\TJC\HEPA2AIN.WPD


Notices DOCUMENT NAME: g:\TJC\HEPA2AIN.WPD
To receive a coDv of this document, indicate in the box C=Coov wlo attachment/enclosure E=Copy with attachment/enclosure N = No copyr\ I  _
[OFFICE


To receive a coDv of this document, indicate in the box C=Coov wlo attachment/enclosure
NAME


E=Copy with attachment/enclosure
[ DATE


N = No copyr \ I _[OFFICE PECI I Rl1 I PERB D:NMSS PECB I lPEC Il ['NAME J Carter* _RBarkely*
PECI I
JCMiller*
_ETen Eyck* IRDennig*
JStolz* DMatthew[ DATE 1 12/23/98 l 12/24/98 1 12/28/98 1 01/11/99 I 12/24/98 1112/99 I 014/99 OFFICIAL RECORD COPY


IN 98-xx December xx, 1998 use similar filter media. This research also showed significant
J Carter*
              1 12/23/98 Rl1
                                _RBarkely*
                                l 12/24/98 I    PERB


losses in the tensile strength of HEPA filter following
JCMil er*
                                                                      D:NMSS


the wetting of used filters; it also showed that the tensile strength was not recovered
_ETen Eyck*
                                                    112/28/98 101/11/99 OFFICIAL RECORD COPY


fully after drying. Further water exposures
IRDenni


resulted in additional
PECB


losses in filter media tensile strength.
I 12/24/98 I  lPEC


The results of this research were publicized
JStolz*
                                                                                                                1112/99 Il


at the 25th DOE/NRC NuclearAir
I


Cleaning and Treatment
['
                                                                                                                                  DMatthew


Conference.
014/99


The DOE research data cannot be used to quantify the useful life of a HEPA filter, but the data do demonstrate
IN 98-xx


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
December xx, 1998 use similar filter media. This research also showed significant losses in the tensile strength of


internal stiffeners
HEPA filter following the wetting of used filters; it also showed that the tensile strength was not


to help support the filter medium. Con Edison has limited the service cycle of the FCU HEPA filters to 6 years and implemented
recovered fully after drying. Further water exposures resulted in additional losses in filter media


inspections
tensile strength. The results of this research were publicized at the 25th DOE/NRC NuclearAir


to confirm the following:
Cleaning and Treatment Conference. The DOE research data cannot be used to quantify the
(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
useful life of a HEPA filter, but the data do demonstrate that there is a finite HEPA filter life and


and/or direct wetting of the filters.Con Edison has also applied for a Technical
that wetting of the filter medium reduces its strength.


Specification
In response to the research findings, Con Edison replaced the filters in the two affected FCUs


amendment
with new Flanders Series F & W filters that incorporate internal stiffeners to help support the


that would delete the requirement
filter medium. Con Edison has limited the service cycle of the FCU HEPA filters to 6 years and


for HEPA filters and the downstream
implemented inspections to confirm the following: (1) the integrity of the urethane seal between


charcoal beds from the containment
the filter medium and filter housing, (2) proper drainage from the FCU, and (3) the extent of


FCUs.This amendment
water condensation and/or direct wetting of the filters.


is based on analyses that show the equipment
Con Edison has also applied for a Technical Specification amendment that would delete the


can be removed without significantly
requirement for HEPA filters and the downstream charcoal beds from the containment FCUs.


affecting
This amendment is based on analyses that show the equipment can be removed without


the radiological
significantly affecting the radiological consequences of a design-basis loss-of-coolant accident


consequences
at IP-2.


of a design-basis
This information notice requires no specific action or written response. If you have any


loss-of-coolant
questions about the information in this notice, please contact one of the technical contacts


accident at IP-2.This information
listed below or the appropriate office of Nuclear Reactor Regulation (NRR) Project Manager.


notice requires no specific action or written response.
Elizabeth Q. Ten Eyck, Director                      Jack W Roe, Acting Director


If you have any questions
Division of Fuel Cycle Safety                        Division of Reactor Program Management


about the information
and Safeguards                                      Office of Nuclear Reactor Regulation


in this notice, please contact one of the technical
Office of Nuclear Material Safety
 
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
and Safeguards


===Office of Nuclear Reactor Regulation===
Technical Contacts:         Richard S. Barkley, Region I                     John J. Hayes, NRR
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
610-337-5065                                      301-415-3167 E-Mail: rsbl@nrc.gov                              E-Mail: jh@nrc.gov
301-415-1153 E-Mail: jps1@nrc.gov


E-Mail: tjcenrc.gov
John P. Segala, NRR                              Jerry Carter, NRR


ta~h~merS
301-415-1858                                      301-415-1153 E-Mail: jps1@nrc.gov                              E-Mail: tjcenrc.gov


List of Recently Issued NRC Information
ta~h~merS List of Recently Issued NRC Information Notices


Notices DOCUW NT NAME: To receive a copy of this document, Indicate In the box C=Copy w/o attachment/enclosure
DOCUW       NT NAME:
To receive a copy of this document, Indicate Inthe box C=Copy w/o attachment/enclosure E=Copy with attachmentfnclosure N= No copy


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N= No copy OFFICE 1IECB I I RI, Gl IPERB I JI D:NMSjz II l E it lPECB I IADDRP NAME JlFfer I Wlarke1 I CMillerNtkkETEN
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Revision as of 03:49, 24 November 2019

Deterioration of High-Efficiency Particulate Air Filters in a Pressurized Water Reactor Containment Fan Cooler Unit
ML031040519
Person / Time
Site: Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane  Entergy icon.png
Issue date: 01/20/1999
From: Matthews D, Teneyck E
NRC/NMSS/FCSS, Office of Nuclear Reactor Regulation
To:
References
IN-99-001, NUDOCS 9901220109
Download: ML031040519 (6)


t

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555-0001 January 20, 1999 NRC INFORMATION NOTICE 99-01: 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 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: hh@nrc.gov

John P. Segala, NRR Jerry Carter, NRR

301-415-1858 301-415-1153 E-Mail: jpsl@nrc.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 I foation Notices

  1. Vdss jaflon:a-

A

&\1 Attachment

IN 98-45 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 for nuclear power reactors, except

of Pipe Welds 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 All holder of operating licenses

(ISI) Program Update for Licensees for nuclear power reactors, except

that Intend to Implement Risk-Informed those that have permanently

ISI of Piping ceased operations and have

certified that fuel has been

permanently removed from the

reactor

98-43 Leaks in the Emergency Diesel 12/04/98 All holder of operating licenses

Generator Lubricating Oil and for nuclear power reactors, except

Jacket Cooling Water Piping those licensees that have

permanently ceased operations

and have certified that fuel has

been permanently removed from

the reactor vessel

98-42 Implementation of 10 CFR 50.55a 12/01/98 All holders of operating licenses

(g) Inservice Inspection Requirements for nuclear power reactors

98-41 Spurious Shutdown of Emergency 11/20/98 All holders of operating licenses

Diesel Generators from Design for nuclear power reactors, except

Oversight for those who have ceased

operations and have certified that

fuel has been permanently

removed from the reactor vessel

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

To receive a coDv of this document, indicate in the box C=Coov wlo attachment/enclosure E=Copy with attachment/enclosure N = No copyr\ I _

[OFFICE

NAME

[ DATE

PECI I

J Carter*

1 12/23/98 Rl1

_RBarkely*

l 12/24/98 I PERB

JCMil er*

D:NMSS

_ETen Eyck*

112/28/98 101/11/99 OFFICIAL RECORD COPY

IRDenni

PECB

I 12/24/98 I lPEC

JStolz*

1112/99 Il

I

['

DMatthew

014/99

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 Inthe box C=Copy w/o attachment/enclosure E=Copy with attachmentfnclosure N= No copy

OFFICE 1IECB I I RI, Gl IPERBJII D:NMSjz II l E it lPECB I IADDRP

NAME JlFfer I Wlarke1 I CMillerNtkkETEN EfCK IF ia9' I l6t7- L e

D -- k--98- ilts I I 1..9. /

OFFICIAL RE 9 COPY