Information Notice 2007-18, Operating Experience Regarding Entrainment of Gas or Debris Into Auxiliary Feedwater Systems: Difference between revisions
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{{#Wiki_filter:UNITED STATES | {{#Wiki_filter:UNITED STATES | ||
NUCLEAR REGULATORY COMMISSION | ===NUCLEAR REGULATORY COMMISSION=== | ||
OFFICE OF NUCLEAR REACTOR REGULATION | |||
WASHINGTON, DC 20555-0001 | |||
===May 13, 2007=== | |||
NRC INFORMATION NOTICE 2007-18: | |||
===OPERATING EXPERIENCE REGARDING=== | |||
ENTRAINMENT OF GAS OR DEBRIS INTO | ENTRAINMENT OF GAS OR DEBRIS INTO | ||
AUXILIARY FEEDWATER SYSTEMS | ===AUXILIARY FEEDWATER SYSTEMS=== | ||
==ADDRESSEES== | ==ADDRESSEES== | ||
| Line 38: | Line 41: | ||
addressees of operating experience regarding possible entrainment of air or debris into | addressees of operating experience regarding possible entrainment of air or debris into | ||
auxiliary feedwater (AFW) systems, potentially affecting the operability of these systems. The | auxiliary feedwater (AFW) systems, potentially affecting the operability of these systems. The | ||
NRC expects that recipients will review the information for applicability to their facilities and | NRC expects that recipients will review the information for applicability to their facilities and | ||
consider actions, as appropriate, to avoid similar problems. Suggestions contained in this IN | consider actions, as appropriate, to avoid similar problems. Suggestions contained in this IN | ||
are not NRC requirements; therefore, no specific action or written response is required. | are not NRC requirements; therefore, no specific action or written response is required. | ||
| Line 49: | Line 52: | ||
Several events have occurred at nuclear power facilities involving possible entrainment of gas | Several events have occurred at nuclear power facilities involving possible entrainment of gas | ||
or debris into AFW systems. Air or debris entrained in AFW systems can impact the capability | or debris into AFW systems. Air or debris entrained in AFW systems can impact the capability | ||
of the AFW pumps to perform their specified safety functions. Several recent events are | of the AFW pumps to perform their specified safety functions. Several recent events are | ||
discussed below: | discussed below: | ||
| Line 58: | Line 61: | ||
A design deficiency resulted in gas coming out of solution and collecting in the nuclear service | A design deficiency resulted in gas coming out of solution and collecting in the nuclear service | ||
water system where the Train A AFW assured suction was located. When this was recognized, the licensee decided to use operator manual alignments to preclude gas entrainment into the | water system where the Train A AFW assured suction was located. When this was recognized, the licensee decided to use operator manual alignments to preclude gas entrainment into the | ||
AFW pumps when alignment was to the standby nuclear service water pond. NRC inspectors | AFW pumps when alignment was to the standby nuclear service water pond. NRC inspectors | ||
identified that the licensee was crediting non-seismic pipe for no less than 30 minutes after a | identified that the licensee was crediting non-seismic pipe for no less than 30 minutes after a | ||
seismic event to allow time to perform the AFW valve lineup. Consequently, there was not | seismic event to allow time to perform the AFW valve lineup. Consequently, there was not | ||
reasonable assurance that the non-seismic pipe would be available to support supplying water | reasonable assurance that the non-seismic pipe would be available to support supplying water | ||
to the AFW pumps. (NRC Integrated Inspection Report 05000369/2004005 and | to the AFW pumps. (NRC Integrated Inspection Report 05000369/2004005 and | ||
05000370/2004005, October 8, 2004, Agencywide Documents Access and Management | 05000370/2004005, October 8, 2004, Agencywide Documents Access and Management | ||
System (ADAMS) Accession No. ML042860339) | System (ADAMS) Accession No. ML042860339) | ||
The licensee subsequently initiated a piping modification and test program to address the issue. | The licensee subsequently initiated a piping modification and test program to address the issue. | ||
| Line 82: | Line 85: | ||
NRC inspectors identified an inadequate procedure that could have resulted in sufficient air in | NRC inspectors identified an inadequate procedure that could have resulted in sufficient air in | ||
an AFW pump suction to make it inoperable. The procedure addressed the realignment of the | an AFW pump suction to make it inoperable. The procedure addressed the realignment of the | ||
AFW pumps suction from the condensate storage tank to the service water system using a | AFW pumps suction from the condensate storage tank to the service water system using a | ||
| Line 88: | Line 91: | ||
pipe that was normally voided to preclude potential leakage through a closed valve that could | pipe that was normally voided to preclude potential leakage through a closed valve that could | ||
adversely affect steam generator chemistry. The voided 6-inch diameter pipe section was | adversely affect steam generator chemistry. The voided 6-inch diameter pipe section was | ||
11-feet long. The licensee responded with a procedure change to adequately fill the affected | 11-feet long. The licensee responded with a procedure change to adequately fill the affected | ||
piping prior to transferring the suction supply. (NRC Inspection Report 05000346/2005004, June 14, 2005, ADAMS Accession No. ML051660047) | piping prior to transferring the suction supply. (NRC Inspection Report 05000346/2005004, June 14, 2005, ADAMS Accession No. ML051660047) | ||
===Watts Bar Nuclear Plant=== | ===Watts Bar Nuclear Plant=== | ||
The Watts Bar backup safety-related water supply to the AFW system is provided by the | The Watts Bar backup safety-related water supply to the AFW system is provided by the | ||
essential raw cooling water (ERCW) system. On January 13, 2006, the licensee discovered air | essential raw cooling water (ERCW) system. On January 13, 2006, the licensee discovered air | ||
in a 12-inch ERCW pipe that supplies water to a motor-driven AFW pump and a turbine-driven | in a 12-inch ERCW pipe that supplies water to a motor-driven AFW pump and a turbine-driven | ||
AFW pump and in an attached 30-inch pipe. The licensee determined that the air in the 12-inch | AFW pump and in an attached 30-inch pipe. The licensee determined that the air in the 12-inch | ||
pipe was, in part, caused by inadequate filling and venting during work performed in the Cycle 6 refueling outage. The air in the 30-inch discharge pipe and a portion of the 12-inch pipe was | pipe was, in part, caused by inadequate filling and venting during work performed in the Cycle 6 refueling outage. The air in the 30-inch discharge pipe and a portion of the 12-inch pipe was | ||
due to gas coming out of solution. Corrective actions included the establishment of continuous | due to gas coming out of solution. Corrective actions included the establishment of continuous | ||
vent paths for the 30-inch ERCW Train A and B discharge headers and the addition of | vent paths for the 30-inch ERCW Train A and B discharge headers and the addition of | ||
| Line 111: | Line 114: | ||
ultrasonic equipment for verification of the water level in the 30-inch headers and the 12-inch | ultrasonic equipment for verification of the water level in the 30-inch headers and the 12-inch | ||
header. (Licensee Event Report 2006-001-00, March 14, 2006, ADAMS Accession No. | header. (Licensee Event Report 2006-001-00, March 14, 2006, ADAMS Accession No. | ||
ML060760381) | ML060760381) | ||
| Line 118: | Line 121: | ||
The backup source of water to the emergency feedwater pumps (the licensees designation for | The backup source of water to the emergency feedwater pumps (the licensees designation for | ||
the AFW pumps) is the service water system. In its inspection report, the NRC reported that | the AFW pumps) is the service water system. In its inspection report, the NRC reported that | ||
the safety-related water supply could become unavailable due to the accumulation of tubercles | the safety-related water supply could become unavailable due to the accumulation of tubercles | ||
| Line 124: | Line 127: | ||
or other debris and that the flow control valves were not designed to handle relatively unclean | or other debris and that the flow control valves were not designed to handle relatively unclean | ||
service water. (NRC Inspection Report 05000395/2005007, March 10, 2005, ADAMS | service water. (NRC Inspection Report 05000395/2005007, March 10, 2005, ADAMS | ||
Accession No. ML050700044) | Accession No. ML050700044) | ||
| Line 133: | Line 136: | ||
condensate storage tank is designed to ensure sufficient condensate remains available if this | condensate storage tank is designed to ensure sufficient condensate remains available if this | ||
tank should fail during a design basis earthquake. An NRC inspection team found that the | tank should fail during a design basis earthquake. An NRC inspection team found that the | ||
licensee failed to follow procedural requirements and establish the necessary foreign material | licensee failed to follow procedural requirements and establish the necessary foreign material | ||
exclusion areas. As a result, foreign materials could cause AFW operational problems | exclusion areas. As a result, foreign materials could cause AFW operational problems | ||
following a seismic event. Further, the licensee failed to properly address industry operating | following a seismic event. Further, the licensee failed to properly address industry operating | ||
experience related to foreign materials in AFW water sources. (NRC Inspection Report | experience related to foreign materials in AFW water sources. (NRC Inspection Report | ||
05000361;362/2006009, December 8, 2006, ADAMS Accession No. ML063420342) Kewaunee Nuclear Power Plant | 05000361;362/2006009, December 8, 2006, ADAMS Accession No. ML063420342) Kewaunee Nuclear Power Plant | ||
| Line 147: | Line 150: | ||
The AFW pump shaft seals require a small amount of leakage to maintain adequate cooling | The AFW pump shaft seals require a small amount of leakage to maintain adequate cooling | ||
and sealing. Leakage reduction or loss can cause loss of seal cooling and lubrication with | and sealing. Leakage reduction or loss can cause loss of seal cooling and lubrication with | ||
subsequent seal degradation that may allow air flow into the pump inlet if the inlet pressure is | subsequent seal degradation that may allow air flow into the pump inlet if the inlet pressure is | ||
sub-atmospheric, a condition that may occur following a steam line break. This may cause | sub-atmospheric, a condition that may occur following a steam line break. This may cause | ||
pump damage due to air entrainment. (Licensee Event Report 2005-006-00, May 25, 2005, ADAMS Accession No. ML051530312 and NRC Inspection Report 05000305/2005010, | pump damage due to air entrainment. (Licensee Event Report 2005-006-00, May 25, 2005, ADAMS Accession No. ML051530312 and NRC Inspection Report 05000305/2005010, | ||
October 16, 2005, ADAMS Accession No. ML052290348) | October 16, 2005, ADAMS Accession No. ML052290348) | ||
| Line 168: | Line 171: | ||
Licensees rely on backup water supplies to AFW systems in response to low probability events, such as seismic and station blackout events, that render normal and preferred water sources | Licensees rely on backup water supplies to AFW systems in response to low probability events, such as seismic and station blackout events, that render normal and preferred water sources | ||
unavailable. The above events indicate that use of backup water sources or other unique and | unavailable. The above events indicate that use of backup water sources or other unique and | ||
potentially overlooked conditions may introduce air or debris that could render AFW inoperable | potentially overlooked conditions may introduce air or debris that could render AFW inoperable | ||
| Line 174: | Line 177: | ||
and illustrate the importance of having developed a complete understanding of the implications | and illustrate the importance of having developed a complete understanding of the implications | ||
of gas or debris in AFW systems. This is particularly important for operational aspects that are | of gas or debris in AFW systems. This is particularly important for operational aspects that are | ||
not tested, as illustrated by the above events where the likelihood of being in the condition was | not tested, as illustrated by the above events where the likelihood of being in the condition was | ||
| Line 183: | Line 186: | ||
==CONTACT== | ==CONTACT== | ||
This information notice requires no specific action or written response. Please direct any | This information notice requires no specific action or written response. Please direct any | ||
questions about this matter to the technical contact listed below or the appropriate Office of | questions about this matter to the technical contact listed below or the appropriate Office of | ||
| Line 190: | Line 193: | ||
/RA/ | /RA/ | ||
===Michael J. Case, Director=== | |||
Division of Policy and Rulemaking | Division of Policy and Rulemaking | ||
Office of Nuclear Reactor Regulation | ===Office of Nuclear Reactor Regulation=== | ||
===Technical Contact:=== | ===Technical Contact:=== | ||
===Warren C. Lyon, NRR=== | ===Warren C. Lyon, NRR=== | ||
301-415-2897 e-mail: wcl@nrc.gov | |||
Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections. | Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections. | ||
==CONTACT== | ==CONTACT== | ||
This information notice requires no specific action or written response. Please direct any | This information notice requires no specific action or written response. Please direct any | ||
questions about this matter to the technical contact listed below or the appropriate Office of | questions about this matter to the technical contact listed below or the appropriate Office of | ||
| Line 211: | Line 214: | ||
/RA/ | /RA/ | ||
===Michael J. Case, Director=== | |||
Division of Policy and Rulemaking | Division of Policy and Rulemaking | ||
Office of Nuclear Reactor Regulation | ===Office of Nuclear Reactor Regulation=== | ||
===Technical Contact:=== | ===Technical Contact:=== | ||
===Warren C. Lyon, NRR=== | ===Warren C. Lyon, NRR=== | ||
301-415-2897 e-mail: wcl@nrc.gov | |||
Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections. | |||
Distribution: IN Reading File | |||
ADAMS Accession Number: ML071100075 OFFICE | |||
SPWB:DSS | |||
TECH EDITOR | |||
BC:SPWB:DSS | |||
DD:DSS | |||
D:DSS | |||
NAME | |||
WLyon | |||
LCulp by e-mail | |||
GCranston | |||
JWermiel | |||
TMartin | |||
DATE | |||
04/23/07 | |||
04/27/07 | |||
04/23/07 | |||
05/10/07 | |||
05/10/07 OFFICE | |||
PGCB:DPR | |||
PGCB:DPR | |||
BC:PGCB:DPR | |||
D:DPR | |||
NAME | |||
DBeaulieu | |||
CHawes | |||
CJackson | |||
MCase | |||
DATE | |||
05/08/07 | |||
05/10/07 | |||
05/11/07 | |||
05/13/07 OFFICIAL RECORD COPY}} | |||
{{Information notice-Nav}} | {{Information notice-Nav}} | ||
Latest revision as of 01:29, 15 January 2025
| ML071100075 | |
| Person / Time | |
|---|---|
| Issue date: | 05/13/2007 |
| From: | Michael Case NRC/NRR/ADRA/DPR |
| To: | |
| References | |
| IN-07-018 | |
| Download: ML071100075 (4) | |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, DC 20555-0001
May 13, 2007
NRC INFORMATION NOTICE 2007-18:
OPERATING EXPERIENCE REGARDING
ENTRAINMENT OF GAS OR DEBRIS INTO
AUXILIARY FEEDWATER SYSTEMS
ADDRESSEES
All holders of operating licenses for nuclear power reactors, except those who have
permanently ceased operations and have certified that fuel has been permanently removed
from the reactor vessel.
PURPOSE
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice (IN) to inform
addressees of operating experience regarding possible entrainment of air or debris into
auxiliary feedwater (AFW) systems, potentially affecting the operability of these systems. The
NRC expects that recipients will review the information for applicability to their facilities and
consider actions, as appropriate, to avoid similar problems. Suggestions contained in this IN
are not NRC requirements; therefore, no specific action or written response is required.
DESCRIPTION OF CIRCUMSTANCES
Several events have occurred at nuclear power facilities involving possible entrainment of gas
or debris into AFW systems. Air or debris entrained in AFW systems can impact the capability
of the AFW pumps to perform their specified safety functions. Several recent events are
discussed below:
McGuire Nuclear Station
A design deficiency resulted in gas coming out of solution and collecting in the nuclear service
water system where the Train A AFW assured suction was located. When this was recognized, the licensee decided to use operator manual alignments to preclude gas entrainment into the
AFW pumps when alignment was to the standby nuclear service water pond. NRC inspectors
identified that the licensee was crediting non-seismic pipe for no less than 30 minutes after a
seismic event to allow time to perform the AFW valve lineup. Consequently, there was not
reasonable assurance that the non-seismic pipe would be available to support supplying water
to the AFW pumps. (NRC Integrated Inspection Report 05000369/2004005 and
05000370/2004005, October 8, 2004, Agencywide Documents Access and Management
System (ADAMS) Accession No. ML042860339)
The licensee subsequently initiated a piping modification and test program to address the issue.
(Duke Energy letters to NRC dated April 25, 2006, and September 7, 2006, ADAMS Accession
Nos. ML061230672 and ML062640070, respectively)
Davis-Besse Nuclear Power Station
NRC inspectors identified an inadequate procedure that could have resulted in sufficient air in
an AFW pump suction to make it inoperable. The procedure addressed the realignment of the
AFW pumps suction from the condensate storage tank to the service water system using a
pipe that was normally voided to preclude potential leakage through a closed valve that could
adversely affect steam generator chemistry. The voided 6-inch diameter pipe section was
11-feet long. The licensee responded with a procedure change to adequately fill the affected
piping prior to transferring the suction supply. (NRC Inspection Report 05000346/2005004, June 14, 2005, ADAMS Accession No. ML051660047)
Watts Bar Nuclear Plant
The Watts Bar backup safety-related water supply to the AFW system is provided by the
essential raw cooling water (ERCW) system. On January 13, 2006, the licensee discovered air
in a 12-inch ERCW pipe that supplies water to a motor-driven AFW pump and a turbine-driven
AFW pump and in an attached 30-inch pipe. The licensee determined that the air in the 12-inch
pipe was, in part, caused by inadequate filling and venting during work performed in the Cycle 6 refueling outage. The air in the 30-inch discharge pipe and a portion of the 12-inch pipe was
due to gas coming out of solution. Corrective actions included the establishment of continuous
vent paths for the 30-inch ERCW Train A and B discharge headers and the addition of
ultrasonic equipment for verification of the water level in the 30-inch headers and the 12-inch
header. (Licensee Event Report 2006-001-00, March 14, 2006, ADAMS Accession No.
Virgil C. Summer Nuclear Station
The backup source of water to the emergency feedwater pumps (the licensees designation for
the AFW pumps) is the service water system. In its inspection report, the NRC reported that
the safety-related water supply could become unavailable due to the accumulation of tubercles
or other debris and that the flow control valves were not designed to handle relatively unclean
service water. (NRC Inspection Report 05000395/2005007, March 10, 2005, ADAMS
Accession No. ML050700044)
San Onofre Nuclear Generating Station
The seismically qualified Enclosure Building surrounding the non-seismically qualified
condensate storage tank is designed to ensure sufficient condensate remains available if this
tank should fail during a design basis earthquake. An NRC inspection team found that the
licensee failed to follow procedural requirements and establish the necessary foreign material
exclusion areas. As a result, foreign materials could cause AFW operational problems
following a seismic event. Further, the licensee failed to properly address industry operating
experience related to foreign materials in AFW water sources. (NRC Inspection Report
05000361;362/2006009, December 8, 2006, ADAMS Accession No. ML063420342) Kewaunee Nuclear Power Plant
The AFW pump shaft seals require a small amount of leakage to maintain adequate cooling
and sealing. Leakage reduction or loss can cause loss of seal cooling and lubrication with
subsequent seal degradation that may allow air flow into the pump inlet if the inlet pressure is
sub-atmospheric, a condition that may occur following a steam line break. This may cause
pump damage due to air entrainment. (Licensee Event Report 2005-006-00, May 25, 2005, ADAMS Accession No. ML051530312 and NRC Inspection Report 05000305/2005010,
October 16, 2005, ADAMS Accession No. ML052290348)
BACKGROUND
Some of the issues of gas entrainment on AFW systems are similar to the concerns discussed
in NRC IN 2006-21, Operating Experience Regarding Entrainment of Air into Emergency Core
Cooling and Containment Spray Systems, dated September 21, 2006, ADAMS Accession No.
DISCUSSION
Licensees rely on backup water supplies to AFW systems in response to low probability events, such as seismic and station blackout events, that render normal and preferred water sources
unavailable. The above events indicate that use of backup water sources or other unique and
potentially overlooked conditions may introduce air or debris that could render AFW inoperable
and illustrate the importance of having developed a complete understanding of the implications
of gas or debris in AFW systems. This is particularly important for operational aspects that are
not tested, as illustrated by the above events where the likelihood of being in the condition was
small, but the condition impacted defense-in-depth and resulted in a failure to comply with the
plant design basis.
CONTACT
This information notice requires no specific action or written response. Please direct any
questions about this matter to the technical contact listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
/RA/
Michael J. Case, Director
Division of Policy and Rulemaking
Office of Nuclear Reactor Regulation
Technical Contact:
Warren C. Lyon, NRR
301-415-2897 e-mail: wcl@nrc.gov
Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections.
CONTACT
This information notice requires no specific action or written response. Please direct any
questions about this matter to the technical contact listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
/RA/
Michael J. Case, Director
Division of Policy and Rulemaking
Office of Nuclear Reactor Regulation
Technical Contact:
Warren C. Lyon, NRR
301-415-2897 e-mail: wcl@nrc.gov
Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections.
Distribution: IN Reading File
ADAMS Accession Number: ML071100075 OFFICE
SPWB:DSS
TECH EDITOR
BC:SPWB:DSS
DD:DSS
D:DSS
NAME
WLyon
LCulp by e-mail
GCranston
JWermiel
TMartin
DATE
04/23/07
04/27/07
04/23/07
05/10/07
05/10/07 OFFICE
PGCB:DPR
PGCB:DPR
BC:PGCB:DPR
D:DPR
NAME
DBeaulieu
CHawes
CJackson
MCase
DATE
05/08/07
05/10/07
05/11/07
05/13/07 OFFICIAL RECORD COPY