Information Notice 2002-18, Effect of Adding Gas Into Water Storage Tanks on the Net Positive Suction Head for Pumps: Difference between revisions

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{{#Wiki_filter:UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, DC 20555-0001June 6, 2002NRC INFORMATION NOTICE 2002-018:EFFECT OF ADDING GAS INTO WATERSTORAGE TANKS ON THE NET POSITIVE
{{#Wiki_filter:UNITED STATES


===SUCTION HEAD FOR PUMPS===
NUCLEAR REGULATORY COMMISSION
 
OFFICE OF NUCLEAR REACTOR REGULATION
 
WASHINGTON, DC 20555-0001 June 6, 2002 NRC INFORMATION NOTICE 2002-018:                  EFFECT OF ADDING GAS INTO WATER
 
STORAGE TANKS ON THE NET POSITIVE
 
SUCTION HEAD FOR PUMPS


==Addressees==
==Addressees==
All holders of operating licenses for nuclear power reactors, except those who havepermanently ceased operations and have certified that fuel has been permanently removed
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.
from the reactor.


==Purpose==
==Purpose==
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alertaddressees to the potential impact of adding gas into water storage tanks on the available net
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alert


positive suction head (NPSH) for pumps.  The NRC anticipates that recipients will review this
addressees to the potential impact of adding gas into water storage tanks on the available net


information for applicability to their facilities and consider taking appropriate actions. However, the suggestions contained in this information notice do not constitute NRC requirements and, therefore, no specific action or written response is required.
positive suction head (NPSH) for pumps. The NRC anticipates that recipients will review this
 
information for applicability to their facilities and consider taking appropriate actions. However, the suggestions contained in this information notice do not constitute NRC requirements and, therefore, no specific action or written response is required.


==Description of Circumstances==
==Description of Circumstances==
The NRC recently performed an inspection at the Union Electric Company's Callaway nuclearpower plant in response to the identification of a degraded condensate storage tank (CST)
The NRC recently performed an inspection at the Union Electric Companys Callaway nuclear
floating diaphragm seal.  The degradation resulted in a failure of a motor-driven auxiliary


feedwater (AFW) pump. It also had the potential to induce a common-cause failure of multiple
power plant in response to the identification of a degraded condensate storage tank (CST)
floating diaphragm seal. The degradation resulted in a failure of a motor-driven auxiliary


AFW pumps. The inspection included a review of several calculations related to the available
feedwater (AFW) pump. It also had the potential to induce a common-cause failure of multiple


NPSH for AFW pumps. The NRC inspection report may be found in the NRC Agency
AFW pumps. The inspection included a review of several calculations related to the available


Document and Management System (ADAMS) under Accession Number ML 020810177.Prior to 1988, the Callaway nuclear power plant controlled the amount of dissolved oxygen inthe CST water by recirculating water to the main condenser hotwell. However, the licensee
NPSH for AFW pumps. The NRC inspection report may be found in the NRC Agency
 
Document and Management System (ADAMS) under Accession Number ML 020810177.
 
Prior to 1988, the Callaway nuclear power plant controlled the amount of dissolved oxygen in
 
the CST water by recirculating water to the main condenser hotwell. However, the licensee


determined that this method of removing oxygen from the CST caused water temperatures to
determined that this method of removing oxygen from the CST caused water temperatures to


exceed the allowable water temperature for the AFW system during the summer months. To
exceed the allowable water temperature for the AFW system during the summer months. To


prevent high water temperatures, the licensee modified the design to add a nitrogen sparging
prevent high water temperatures, the licensee modified the design to add a nitrogen sparging


system to the CST.The NRC found that the licensee's previous calculations did not appropriately address the effectof the nitrogen-saturated water on the available NPSH for the AFW pumps. The licensee's
system to the CST.
 
The NRC found that the licensees previous calculations did not appropriately address the effect
 
of the nitrogen-saturated water on the available NPSH for the AFW pumps. The licensees


recent NPSH calculation included the effect of nitrogen addition to the CST. The revised
recent NPSH calculation included the effect of nitrogen addition to the CST. The revised


calculation indicated that the available NPSH was reduced by approximately 11 feet for the
calculation indicated that the available NPSH was reduced by approximately 11 feet for the


A-train motor-driven AFW pump. ML021570158 IN 2002-018  
A-train motor-driven AFW pump.
 
ML021570158
 
IN 2002-018  


==DISCUSSION==
==DISCUSSION==
This example at the Callaway nuclear power plant shows that the available NPSH for the AFWpumps was significantly reduced when nitrogen gas is added to the CST to control dissolved
This example at the Callaway nuclear power plant shows that the available NPSH for the AFW
 
pumps was significantly reduced when nitrogen gas is added to the CST to control dissolved
 
oxygen. Criterion III, Design Control, in Appendix B to Title 10, Part 50 of the Code of Federal


oxygen.  Criterion III, "Design Control," in Appendix B to Title 10, Part 50 of the Code of FederalRegulations (10 CFR Part 50) requires, in part, that each licensee must implement designcontrol measures to verify or check the adequacy of design through the use of alternate or
Regulations (10 CFR Part 50) requires, in part, that each licensee must implement design


simplified calculational methods, or by performing a suitable testing program. In general, it is
control measures to verify or check the adequacy of design through the use of alternate or
 
simplified calculational methods, or by performing a suitable testing program. In general, it is


important to consider the effect on available NPSH for pumps when modifying the pumps
important to consider the effect on available NPSH for pumps when modifying the pumps


'suction source (e.g., CST and Refueling Water Storage Tank). Inadequate NPSH can result in
suction source (e.g., CST and Refueling Water Storage Tank). Inadequate NPSH can result in


significantly degraded pump performance or pump failure.This information notice does not require any specific action or written response.  If you haveany questions about the information in this notice, please contact  the technical contacts listed
significantly degraded pump performance or pump failure.


below or the appropriate project manager from the NRC
This information notice does not require any specific action or written response. If you have


's Office of Nuclear Reactor Regulation. /RA/William D. Beckner, Program Director
any questions about the information in this notice, please contact the technical contacts listed
 
below or the appropriate project manager from the NRCs Office of Nuclear Reactor Regulation.
 
/RA/
                                              William D. Beckner, Program Director
 
Operating Reactor Improvements Program


===Operating Reactor Improvements Program===
Division of Regulatory Improvement Programs
Division of Regulatory Improvement Programs


Office of Nuclear Reactor RegulationTechnical contact:Ian Jung, NRRTroy Pruett, Region IV(301) 415-1837(817) 860-8182 Email: ixj@nrc.govEmail: twp@nrc.govAttachment: List of Recently Issued NRC Information Notices
Office of Nuclear Reactor Regulation
 
Technical contact: Ian Jung, NRR              Troy Pruett, Region IV
 
(301) 415-1837         (817) 860-8182 Email: ixj@nrc.gov      Email: twp@nrc.gov
 
Attachment: List of Recently Issued NRC Information Notices


IN 2002-018  
IN 2002-018  


==DISCUSSION==
==DISCUSSION==
This example at the Callaway nuclear power plant shows that the available NPSH for the AFWpumps was significantly reduced when nitrogen gas is added to the CST to control dissolved
This example at the Callaway nuclear power plant shows that the available NPSH for the AFW
 
pumps was significantly reduced when nitrogen gas is added to the CST to control dissolved
 
oxygen. Criterion III, Design Control, in Appendix B to Title 10, Part 50 of the Code of Federal
 
Regulations (10 CFR Part 50) requires, in part, that each licensee must implement design


oxygen.  Criterion III, "Design Control," in Appendix B to Title 10, Part 50 of the Code of FederalRegulations (10 CFR Part 50) requires, in part, that each licensee must implement designcontrol measures to verify or check the adequacy of design through the use of alternate or
control measures to verify or check the adequacy of design through the use of alternate or


simplified calculational methods, or by performing a suitable testing program. In general, it is
simplified calculational methods, or by performing a suitable testing program. In general, it is


important to consider the effect on available NPSH for pumps when modifying the pumps
important to consider the effect on available NPSH for pumps when modifying the pumps


'suction source (e.g., CST and Refueling Water Storage Tank). Inadequate NPSH can result in
suction source (e.g., CST and Refueling Water Storage Tank). Inadequate NPSH can result in
 
significantly degraded pump performance or pump failure.
 
This information notice does not require any specific action or written response. If you have
 
any questions about the information in this notice, please contact the technical contacts listed


significantly degraded pump performance or pump failure.This information notice does not require any specific action or written response.  If you haveany questions about the information in this notice, please contact  the technical contacts listed
below or the appropriate project manager from the NRCs Office of Nuclear Reactor Regulation.


below or the appropriate project manager from the NRC
/RA/
                                                    William D. Beckner, Program Director


's Office of Nuclear Reactor Regulation. /RA/William D. Beckner, Program Director
Operating Reactor Improvements Program


===Operating Reactor Improvements Program===
Division of Regulatory Improvement Programs
Division of Regulatory Improvement Programs


Office of Nuclear Reactor RegulationTechnical contact:Ian Jung, NRRTroy Pruett, Region IV(301) 415-1837(817) 860-8182 Email: ixj@nrc.govEmail: twp@nrc.govAttachment: List of Recently Issued NRC Information NoticesDISTRIBUTION
Office of Nuclear Reactor Regulation
 
Technical contact: Ian Jung, NRR              Troy Pruett, Region IV
 
(301) 415-1837         (817) 860-8182 Email: ixj@nrc.gov      Email: twp@nrc.gov
 
Attachment: List of Recently Issued NRC Information Notices
 
DISTRIBUTION:
      PUBLIC
 
IN Reading File
 
ADAMS ACCESSION NO.:                                                          Template: NRR-052 DOCUMENT NAME: G:RORP\OES\JUNG\INCALLAWAY-NPSH.WPD*See previous concurrence
 
OFFICE  RSE:RORP:DRIP      TECH EDITOR    SC:EMEB:DE        SC:SPLB:DSSA    SC:RORP:DRIP    PD:RORP:DRIP
 
NAME    ICJung              PAGarrity*    DTerao            SWeerakkody    TReis            WDBeckner
 
DATE    05/  /2002        05/ 10 /2002  05/21/2002        05/21/2002      05/092002        06/06/2002 OFFICIAL RECORD COPY
 
Attachment 1 IN 2002-018 LIST OF RECENTLY ISSUED
 
NRC INFORMATION NOTICES


:PUBLIC
_____________________________________________________________________________________
Information                                              Date of


IN Reading FileADAMS ACCESSION NO.:Template: NRR-052DOCUMENT NAME: G:RORP\OES\JUNG\INCALLAWAY-NPSH.WPD*See previous concurrenceOFFICERSE:RORP:DRIPTECH EDITORSC:EMEB:DESC:SPLB:DSSASC:RORP:DRIPPD:RORP:DRIPNAMEICJungPAGarrity*DTeraoSWeerakkodyTReisWDBecknerDATE05/      /200205/ 10 /200205/21/200205/21/200205/09200206/06/2002OFFICIAL RECORD COPY
Notice No.               Subject                        Issuance        Issued to


______________________________________________________________________________________OL = Operating License
_____________________________________________________________________________________
2002-16          Intravascular Brachytherapy          05/01/2002      All Medical Licensees.


CP = Construction PermitAttachment 1IN 2002-018 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICES
Misadministrations


_____________________________________________________________________________________InformationDate of
2002-15          Hydrogen Combustion Events            04/12/2002      All holders of operating licenses


===Notice No.        SubjectIssuanceIssued to===
in Foreign BWR Piping                                  for light water reactors, except
_____________________________________________________________________________________2002-16Intravascular BrachytherapyMisadministrations05/01/2002All Medical Licensees.2002-15Hydrogen Combustion Eventsin Foreign BWR Piping04/12/2002All holders of operating licensesfor light water reactors, except


those who have permanently
those who have permanently
Line 124: Line 204:
permanently removed from the
permanently removed from the


reactor.2002-14Ensuring a Capability toEvacuate Individuals, Including
reactor.
 
2002-14          Ensuring a Capability to              04/08/2002      All holders of operating licenses
 
Evacuate Individuals, Including                       for nuclear power reactors, Members of the Public, From                            including those who have ceased


===Members of the Public, From===
the Owner-Controlled Area                              operations but have fuel on site.
the Owner-Controlled Area04/08/2002All holders of operating licensesfor nuclear power reactors, including those who have ceased


operations but have fuel on site.2002-13Possible Indicators of OngoingReactor Pressure Vessel Head
2002-13          Possible Indicators of Ongoing        04/04/2002      All holders of operating licenses


Degradation04/04/2002All holders of operating licensesfor pressurized water nuclear
Reactor Pressure Vessel Head                          for pressurized water nuclear


power reactors, except those who
Degradation                                            power reactors, except those who


have permanently ceased
have permanently ceased
Line 141: Line 224:
has been permanently removed
has been permanently removed


from the reactor.99-28, Supp 1Recall of Star Brand FireProtection Sprinkler Heads03/22/2002All holders of licenses for nuclearpower, research, and test
from the reactor.
 
99-28, Supp 1    Recall of Star Brand Fire            03/22/2002      All holders of licenses for nuclear
 
Protection Sprinkler Heads                            power, research, and test
 
reactors and fuel cycle facilities.
 
2002-12          Submerged Safety-Related              03/21/2002      All holders of operating licenses
 
Electrical Cables                                      or construction permits for
 
nuclear power reactors
 
Note: NRC generic communications may be received in electronic format shortly after they are issued by
 
subscribing to the NRC listserver as follows:
      To subscribe send an e-mail to <listproc@nrc.gov >, no subject, and the following command in the
 
message portion:
                                    subscribe gc-nrr firstname lastname


reactors and fuel cycle facilities.2002-12Submerged Safety-RelatedElectrical Cables03/21/2002All holders of operating licensesor construction permits for
______________________________________________________________________________________
OL = Operating License


nuclear power reactorsNote:NRC generic communications may be received in electronic format shortly after they are issued bysubscribing to the NRC listserver as follows:To subscribe send an e-mail to <listproc@nrc.gov >, no subject, and the following command in themessage portion:subscribe gc-nrr firstname lastname}}
CP = Construction Permit}}


{{Information notice-Nav}}
{{Information notice-Nav}}

Latest revision as of 04:19, 24 November 2019

Effect of Adding Gas Into Water Storage Tanks on the Net Positive Suction Head for Pumps
ML021570158
Person / Time
Issue date: 06/06/2002
From: Beckner W
NRC/NRR/DRIP/RORP
To:
Jung I, NRR/DRIP, 415-1837
References
TAC M3971 IN-02-018
Download: ML021570158 (5)
v • d • e


UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, DC 20555-0001 June 6, 2002 NRC INFORMATION NOTICE 2002-018: EFFECT OF ADDING GAS INTO WATER

STORAGE TANKS ON THE NET POSITIVE

SUCTION HEAD FOR PUMPS

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.

Purpose

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

addressees to the potential impact of adding gas into water storage tanks on the available net

positive suction head (NPSH) for pumps. The NRC anticipates that recipients will review this

information for applicability to their facilities and consider taking appropriate actions. However, the suggestions contained in this information notice do not constitute NRC requirements and, therefore, no specific action or written response is required.

Description of Circumstances

The NRC recently performed an inspection at the Union Electric Companys Callaway nuclear

power plant in response to the identification of a degraded condensate storage tank (CST)

floating diaphragm seal. The degradation resulted in a failure of a motor-driven auxiliary

feedwater (AFW) pump. It also had the potential to induce a common-cause failure of multiple

AFW pumps. The inspection included a review of several calculations related to the available

NPSH for AFW pumps. The NRC inspection report may be found in the NRC Agency

Document and Management System (ADAMS) under Accession Number ML 020810177.

Prior to 1988, the Callaway nuclear power plant controlled the amount of dissolved oxygen in

the CST water by recirculating water to the main condenser hotwell. However, the licensee

determined that this method of removing oxygen from the CST caused water temperatures to

exceed the allowable water temperature for the AFW system during the summer months. To

prevent high water temperatures, the licensee modified the design to add a nitrogen sparging

system to the CST.

The NRC found that the licensees previous calculations did not appropriately address the effect

of the nitrogen-saturated water on the available NPSH for the AFW pumps. The licensees

recent NPSH calculation included the effect of nitrogen addition to the CST. The revised

calculation indicated that the available NPSH was reduced by approximately 11 feet for the

A-train motor-driven AFW pump.

ML021570158

IN 2002-018

DISCUSSION

This example at the Callaway nuclear power plant shows that the available NPSH for the AFW

pumps was significantly reduced when nitrogen gas is added to the CST to control dissolved

oxygen. Criterion III, Design Control, in Appendix B to Title 10, Part 50 of the Code of Federal

Regulations (10 CFR Part 50) requires, in part, that each licensee must implement design

control measures to verify or check the adequacy of design through the use of alternate or

simplified calculational methods, or by performing a suitable testing program. In general, it is

important to consider the effect on available NPSH for pumps when modifying the pumps

suction source (e.g., CST and Refueling Water Storage Tank). Inadequate NPSH can result in

significantly degraded pump performance or pump failure.

This information notice does not require any specific action or written response. If you have

any questions about the information in this notice, please contact the technical contacts listed

below or the appropriate project manager from the NRCs Office of Nuclear Reactor Regulation.

/RA/

William D. Beckner, Program Director

Operating Reactor Improvements Program

Division of Regulatory Improvement Programs

Office of Nuclear Reactor Regulation

Technical contact: Ian Jung, NRR Troy Pruett, Region IV

(301) 415-1837 (817) 860-8182 Email: ixj@nrc.gov Email: twp@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

IN 2002-018

DISCUSSION

This example at the Callaway nuclear power plant shows that the available NPSH for the AFW

pumps was significantly reduced when nitrogen gas is added to the CST to control dissolved

oxygen. Criterion III, Design Control, in Appendix B to Title 10, Part 50 of the Code of Federal

Regulations (10 CFR Part 50) requires, in part, that each licensee must implement design

control measures to verify or check the adequacy of design through the use of alternate or

simplified calculational methods, or by performing a suitable testing program. In general, it is

important to consider the effect on available NPSH for pumps when modifying the pumps

suction source (e.g., CST and Refueling Water Storage Tank). Inadequate NPSH can result in

significantly degraded pump performance or pump failure.

This information notice does not require any specific action or written response. If you have

any questions about the information in this notice, please contact the technical contacts listed

below or the appropriate project manager from the NRCs Office of Nuclear Reactor Regulation.

/RA/

William D. Beckner, Program Director

Operating Reactor Improvements Program

Division of Regulatory Improvement Programs

Office of Nuclear Reactor Regulation

Technical contact: Ian Jung, NRR Troy Pruett, Region IV

(301) 415-1837 (817) 860-8182 Email: ixj@nrc.gov Email: twp@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

DISTRIBUTION:

PUBLIC

IN Reading File

ADAMS ACCESSION NO.: Template: NRR-052 DOCUMENT NAME: G:RORP\OES\JUNG\INCALLAWAY-NPSH.WPD*See previous concurrence

OFFICE RSE:RORP:DRIP TECH EDITOR SC:EMEB:DE SC:SPLB:DSSA SC:RORP:DRIP PD:RORP:DRIP

NAME ICJung PAGarrity* DTerao SWeerakkody TReis WDBeckner

DATE 05/ /2002 05/ 10 /2002 05/21/2002 05/21/2002 05/092002 06/06/2002 OFFICIAL RECORD COPY

Attachment 1 IN 2002-018 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

_____________________________________________________________________________________

Information Date of

Notice No. Subject Issuance Issued to

_____________________________________________________________________________________

2002-16 Intravascular Brachytherapy 05/01/2002 All Medical Licensees.

Misadministrations

2002-15 Hydrogen Combustion Events 04/12/2002 All holders of operating licenses

in Foreign BWR Piping for light water reactors, except

those who have permanently

ceased operations and have

certified that fuel has been

permanently removed from the

reactor.

2002-14 Ensuring a Capability to 04/08/2002 All holders of operating licenses

Evacuate Individuals, Including for nuclear power reactors, Members of the Public, From including those who have ceased

the Owner-Controlled Area operations but have fuel on site.

2002-13 Possible Indicators of Ongoing 04/04/2002 All holders of operating licenses

Reactor Pressure Vessel Head for pressurized water nuclear

Degradation power reactors, except those who

have permanently ceased

operations and certified that fuel

has been permanently removed

from the reactor.

99-28, Supp 1 Recall of Star Brand Fire 03/22/2002 All holders of licenses for nuclear

Protection Sprinkler Heads power, research, and test

reactors and fuel cycle facilities.

2002-12 Submerged Safety-Related 03/21/2002 All holders of operating licenses

Electrical Cables or construction permits for

nuclear power reactors

Note: NRC generic communications may be received in electronic format shortly after they are issued by

subscribing to the NRC listserver as follows:

To subscribe send an e-mail to <listproc@nrc.gov >, no subject, and the following command in the

message portion:

subscribe gc-nrr firstname lastname

______________________________________________________________________________________

OL = Operating License

CP = Construction Permit


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