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{{#Wiki_filter:_~K)UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555September 30, 1992NRC INFORMATION NOTICE 92-71: PARTIAL PLUGGING OF SUPPRESSION POOLSTRAINERS AT A FOREIGN BWR
{{#Wiki_filter:_~K)UNITED STATES NUCLEAR REGULATORY
 
COMMISSION
 
===OFFICE OF NUCLEAR REACTOR REGULATION===
WASHINGTON, D.C. 20555 September
 
30, 1992 NRC INFORMATION
 
NOTICE 92-71: PARTIAL PLUGGING OF SUPPRESSION
 
POOL STRAINERS
 
AT A FOREIGN BWR


==Addressees==
==Addressees==
All holders of operating licenses or construction permits for nuclear powerreactors.
All holders of operating
 
licenses or construction
 
permits for nuclear power reactors.


==Purpose==
==Purpose==
The U.S. Nuclear Regulatory Commission (NRC) is issuing this informationnotice to alert addressees to the potential-for loss of emergency core coolingsystems (ECCS) that was identified as a result of an event at a Swedishboiling water reactor (BWR). It is expected that recipients will review thelinformation for applicability to their facilities and consider actions, asappropriate, to avoid similar problems. However, suggestions contained inthis information notice are not NRC requirements; therefore, no specificaction or written response is required.
The U.S. Nuclear Regulatory
 
Commission (NRC) is issuing this information
 
notice to alert addressees
 
to the potential-for
 
loss of emergency
 
core cooling systems (ECCS) that was identified
 
as a result of an event at a Swedish boiling water reactor (BWR). It is expected that recipients
 
will review thel information
 
for applicability
 
to their facilities
 
and consider actions, as appropriate, to avoid similar problems.
 
However, suggestions
 
contained
 
in this information
 
notice are not NRC requirements;  
therefore, no specific action or written response is required.Description
 
of Circumstances:
On July 28, 1992, Sydkraft AB, the utility licensed by the Swedish regulatory
 
agency for the BarsebAck
 
nuclear power plant, was restarting
 
Unit 2 after the annual outage. While the reactor was at 1 or 2 percent power and at 435 psi, a leaking pilot valve caused a safety valve for the reactor vessel to open.This valve discharges
 
directly to the drywell. Reactor scram, high pressure safety injection, core spray, and containment
 
spray systems initiated automatically
 
in response to the event. Steam from the open safety valve, impinging
 
on thermally-insulated
 
equipment, dislodged
 
440 pounds of metal-jacketed, mineral wool. An estimated
 
220 pounds of insulating
 
material was washed into the suppression
 
pool. Two of five strainers
 
on the suction side of the ECCS pumps were in service and became partially
 
plugged with mineral wool. Plugging caused pressure to decrease significantly
 
across the strainers and caused indications
 
of cavitation
 
in one pump in about an hour after the event began. The operators
 
successfully
 
back flushed the strainers
 
and shut down the reactor without additional
 
problems.Discussion
 
In the safety analysis for Unit 2 of the Barsebdck
 
plant, the licensee concluded
 
that the strainers
 
would not require back flushing during the first 10 hours after a loss-of-coolant
 
accident.
 
Because of the event of July 28, the Swedish regulatory
 
agency required Barseback
 
Unit 2 and four other units of similar design to remain shut down until this problem is resolved.9209290014 e
 
III IN 92-71 September
 
30, 1992 This event at BarsebAck
 
is directly applicable
 
to an earlier study conducted by the NRC. That study evaluated
 
the potential
 
for displaced
 
thermal insulation
 
to form debris and to be drawn to the sump screen. The results of the study are documented
 
in "Containment
 
Sump Performance," NUREG-0897, Revision 1, dated March 1984. The NRC concluded
 
that the risk associated
 
with the sump clogging concern did not warrant backfitting
 
of domestic plants.However, based on the Barsebdck
 
event, this conclusion
 
is being reevaluated.
 
This information
 
notice requires no specific action or written response.
 
If you have any questions
 
about the information
 
in this notice, please contact the technical
 
contact listed below or the appropriate
 
Office of Nuclear Reactor Regulation (NRR) project manager.(arles si, Director Division of Operational
 
===Events Assessment===
Office of Nuclear Reactor Regulation
 
Technical
 
contact: Robert L. Dennig, NRR (301) 504-1156 Attachment:
List of Recently Issued NRC Information
 
Notices
 
Attachment
 
IN 92-71 September
 
30, 1992 LIST OF RECENTLY ISSUED NRC INFORMATION
 
NOTICES Information
 
Date of Notice No. Subject Issuance Issued to 92-70 92-69 91-29, Supp.92-68 92-67 1 Westinghouse
 
Motor-Operated
 
Valve Performance
 
Data Supplied to Nuclear Power Plant Licensees Water Leakage from Yard Area Through Conduits Into Buildings Deficiencies
 
Identified
 
During Electrical
 
Dis-tribution
 
System Func-tional Inspections
 
Potentially
 
Substandard
 
Slip-On, Welding Neck, and Blind Flanges Deficiency
 
in Design Modifications
 
to Ad-dress Failures of Hiller Actuators
 
Upon A Gradual Loss of Air Pressure Access Denied to NRC Inspectors
 
at Five Star Products, Inc. and Construction
 
===Products Research, Fairfield, Connecticut===
Safety System Problems Caused by Modifications
 
===That Were Not Adequately===
Reviewed and Tested 09/25/92 09/22/92 09/14/92 09/10/92 09/10/92 09/01/92 09/03/92 08/28/92 All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors and all recipients
 
of NUREG-0040, "Licensee, Con-tractor and Vendor Inspec-tion Status Report" (White.Book).All holders of OLs or CPs for nuclear power reactors.All holders of -OLs or CPs for nuclear power reactors.92-66 92-65 92-64 Nozzle on Low Relief Ring Settings Pressure Water-Valves OL = Operating
 
License CP = Construction
 
Permit
 
K><YIN 92-71 September
 
30, 1992 This event at Barseback
 
is directly applicable
 
to an earlier study conducted by the NRC. That study evaluated
 
the potential
 
for displaced
 
thermal insulation
 
to form debris and to be drawn to the sump screen. The results of the study are documented
 
in "Containment
 
Sump Performance," NUREG-0897, Revision 1, dated March 1984. The NRC concluded
 
that the risk associated
 
with the sump clogging concern did not warrant backfitting
 
of domestic plants.However, based on the BarsebAck
 
event, this conclusion
 
is being reevaluated.
 
This information
 
notice requires no specific action or written response.
 
If you have any questions
 
about the information
 
in this notice, please contact the technical
 
contact listed below or the appropriate
 
Office of Nuclear Reactor Regulation (NRR) project manager.Original Signed by Charles E. Rossi Charles E. Rossi, Director Division of Operational
 
===Events Assessment===
Office of Nuclear Reactor Regulation
 
Technical
 
con itact: Robert L. Dennig, NRR (301) 504-1156 List of Recently Issued NRC Information
 
Notices Attachment:
Document Name: 92-71.IN*SEE PREVIOUS CONCURRENCES
 
*OEAB:DOEA:NRR*SC/OEAB:DOEA:NRR
 
RWWoodruff
 
RLDennig 09/24/92 09/24/92 V CEp/aze SC~hLAt_-
Jest)o1i A e- ,L .I DO *C/OGCB:DOEA:NRR*RPB:ADM
 
C GHMarcus TechEd 09/; 92 09/28/92 09/24/24*C/OEAB:DOEA:NRR*C/SPLB:DST:NRR
 
ICEP/OIPw AChaffee CEMcCracken
 
AKenqeke 09/k8/92 09/1r/92 09/dg/92 ago,. 4 e , am ASCo-- -I rw W. 4.4a
 
NRCIN 92-XX September
 
xx, 1991 documented
 
in "Containment
 
Sump Performance," NUREG-0897, Revision 1, dated March 1984. The NRC concluded
 
that the risk associated
 
with the sump clogging concern did not warrant backfitting
 
of domestic plants. However, based on the Barseback event and NUREG-0897, Revision 1, this conclusion
 
is being reevaluated.
 
This information
 
notice requires no specific action or written response.
 
If you have any question about the information
 
in this notice, please contact the technical
 
contact listed below or the appropriate
 
Office of Nuclear Reactor Regulation
 
project manager.-Charles E. Rossi, Director Division of Operational
 
===Events Assessment===
Office of Nuclear Reactor Regulation
 
Technmical
 
Contact: Robert L. Dennig, NRR (301) 504-1156 Attachment:
1. List of Recently Issued Information
 
Notices* See previous page for concurrence.
 
CONCURRENCE:
OEAB*RWWoodruff
 
09/24/92 D:DOEA CERossi 09/ /92 LevA^-t l40-m'-is -DcNpu P I 0 u; "r cz- NX,-,I- PO T-P'TECH EDITORS*JDMain 09/24/92 SC:OEAB*RLDennig 09/24/92:SPLB CEMcCrcken
 
092/92 09 3-1 n I -Kc BC:OEAB AEChaffee 09/4&/92 BC:OGCB GHMarcus 09/ /92 Or? o SSC.l1er- Dues c,?/Xl/q;;
410a.in CovCO LV V% ecc eLpCAPt"XU
 
I4 posh 4 aDSCe t.C do Lue g;Al CLL4e.?.-
V- IN 92-71 September
 
29, 1992 This event at Barseback
 
is directly applicable
 
to an earlier study conducted by the NRC. That study evaluated
 
the potential
 
for displaced
 
thermal insulation
 
to form debris and to be drawn to the sump screen. The results of the study are documented
 
in "Containment
 
Sump Performance," NUREG-0897, Revision 1, dated March 1984. The NRC concluded
 
that the risk associated
 
with the sump clogging concern did not warrant backfitting
 
of domestic plants.However, based on the Barsebdck
 
event and NUREG-0897, Revision 1, this conclusion
 
is being reevaluated.
 
This information
 
notice requires no specific action or written response.
 
If you have any questions
 
about the information
 
in this notice, please contact the technical
 
contact listed below or the appropriate
 
Office of Nuclear Reactor Regulation (NRR) project manager.Charles E. Rossi, Director Division of Operational
 
===Events Assessment===
Office of Nuclear Reactor Regulation
 
Technical
 
con tact: Robert L. Dennig, NRR (301) 504-1156 List of Recently Issued NRC Information
 
Notices Attachment:
Document Name: 92-71.IN*SEE PREVIOUS CONCURRENCES
 
*OEAB:DOEA:NRR*SC/OEAB:DOEA:NRR
 
RWWoodruff
 
RLDennig 09/24/92 09/24/92 DOEA:NRR C/OGCB:DOEA:NRR*RPB:ADM
 
CERossi GHMarcus)GLK-
TechEd 09/ /92 09/,S/92 &o 09/24/24*C/OEAB:DOEA:NRR*C/SPLB:DST:NRR
 
CEP/OIP AChaffee CEMcCracken
 
AKenneke 09/ /92 09/ /92 09/ /92 K>-NRCIN 92-XX September
 
xx, 1991 technical
 
contact listed below or the appropriate
 
Office of Nuclear Reactor Regulation


==Description of Circumstances==
project manager.Charles E. Rossi, Director Division of Operational
:On July 28, 1992, Sydkraft AB, the utility licensed by the Swedish regulatoryagency for the BarsebAck nuclear power plant, was restarting Unit 2 after theannual outage. While the reactor was at 1 or 2 percent power and at 435 psi,a leaking pilot valve caused a safety valve for the reactor vessel to open.This valve discharges directly to the drywell. Reactor scram, high pressuresafety injection, core spray, and containment spray systems initiatedautomatically in response to the event. Steam from the open safety valve,impinging on thermally-insulated equipment, dislodged 440 pounds of metal-jacketed, mineral wool. An estimated 220 pounds of insulating material waswashed into the suppression pool. Two of five strainers on the suction sideof the ECCS pumps were in service and became partially plugged with mineralwool. Plugging caused pressure to decrease significantly across the strainersand caused indications of cavitation in one pump in about an hour after theevent began. The operators successfully back flushed the strainers and shutdown the reactor without additional problems.DiscussionIn the safety analysis for Unit 2 of the Barsebdck plant, the licenseeconcluded that the strainers would not require back flushing during the first10 hours after a loss-of-coolant accident. Because of the event of July 28,the Swedish regulatory agency required Barseback Unit 2 and four other unitsof similar design to remain shut down until this problem is resolved.9209290014 e


IIIIN 92-71September 30, 1992 This event at BarsebAck is directly applicable to an earlier study conductedby the NRC. That study evaluated the potential for displaced thermalinsulation to form debris and to be drawn to the sump screen. The results ofthe study are documented in "Containment Sump Performance," NUREG-0897,Revision 1, dated March 1984. The NRC concluded that the risk associated withthe sump clogging concern did not warrant backfitting of domestic plants.However, based on the Barsebdck event, this conclusion is being reevaluated.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.(arles si, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical contact: Robert L. Dennig, NRR(301) 504-1156Attachment: List of Recently Issued NRC Information Notices
===Events Assessment===
Office of Nuclear Reactor Regulation


AttachmentIN 92-71September 30, 1992 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to92-7092-6991-29,Supp.92-6892-671Westinghouse Motor-OperatedValve Performance DataSupplied to Nuclear PowerPlant LicenseesWater Leakage from YardArea Through ConduitsInto BuildingsDeficiencies IdentifiedDuring Electrical Dis-tribution System Func-tional InspectionsPotentially SubstandardSlip-On, Welding Neck,and Blind FlangesDeficiency in DesignModifications to Ad-dress Failures ofHiller Actuators UponA Gradual Loss ofAir PressureAccess Denied to NRCInspectors at Five StarProducts, Inc. andConstruction ProductsResearch, Fairfield,ConnecticutSafety System ProblemsCaused by ModificationsThat Were Not AdequatelyReviewed and Tested09/25/9209/22/9209/14/9209/10/9209/10/9209/01/9209/03/9208/28/92All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactorsand all recipients ofNUREG-0040, "Licensee, Con-tractor and Vendor Inspec-tion Status Report" (White.Book).All holders of OLs or CPsfor nuclear power reactors.All holders of -OLs or CPsfor nuclear power reactors.92-6692-6592-64Nozzleon LowReliefRing SettingsPressure Water-ValvesOL = Operating LicenseCP = Construction Permit
Technical


K><YIN 92-71September 30, 992This event at Barseback is directly applicable to an earlier study conductedby the NRC. That study evaluated the potential for displaced thermalinsulation to form debris and to be drawn to the sump screen. The results ofthe study are documented in "Containment Sump Performance," NUREG-0897,Revision 1, dated March 1984. The NRC concluded that the risk associated withthe sump clogging concern did not warrant backfitting of domestic plants.However, based on the BarsebAck event, this conclusion is being reevaluated.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Original Signed byCharles E. RossiCharles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical conitact: Robert L. Dennig, NRR(301) 504-1156List of Recently Issued NRC Information NoticesAttachment:Document Name: 92-71.IN*SEE PREVIOUS CONCURRENCES*OEAB:DOEA:NRR*SC/OEAB:DOEA:NRRRWWoodruff RLDennig09/24/92 09/24/92V CEp/azeSC~hLAt_- Jest)o1i A e- ,L .IDO *C/OGCB:DOEA:NRR*RPB:ADMC GHMarcus TechEd09/; 92 09/28/92 09/24/24*C/OEAB:DOEA:NRR*C/SPLB:DST:NRR ICEP/OIPwAChaffee CEMcCracken AKenqeke09/k8/92 09/1r/92 09/dg/92ago,. 4 e, am ASCo-- -I rw W. 4.4a
Contact: Robert L. Dennig, NRR (301) 504-1156 Attachment:
1. List of Recently Issued Information


NRCIN 92-XXSeptember xx, 1991 documented in "Containment Sump Performance," NUREG-0897, Revision 1, dated March1984. The NRC concluded that the risk associated with the sump clogging concerndid not warrant backfitting of domestic plants. However, based on the Barsebackevent and NUREG-0897, Revision 1, this conclusion is being reevaluated.This information notice requires no specific action or written response. If youhave any question about the information in this notice, please contact thetechnical contact listed below or the appropriate Office of Nuclear ReactorRegulation project manager.-Charles E. Rossi, DirectorDivision of OperationalEvents AssessmentOffice of Nuclear Reactor RegulationTechnmical Contact:Robert L. Dennig, NRR(301) 504-1156Attachment:1. List of Recently Issued Information Notices* See previous page for concurrence.CONCURRENCE:OEAB*RWWoodruff09/24/92D:DOEACERossi09/ /92LevA^-t l40-m'-is -DcNpu P I 0 u; "rcz- NX,-,I- PO T-P'TECH EDITORS*JDMain09/24/92SC:OEAB*RLDennig09/24/92:SPLBCEMcCrcken092/9209 3-1n I -KcBC:OEABAEChaffee09/4&/92BC:OGCBGHMarcus09/ /92Or? oSSC.l1er- Duesc,?/Xl/q;;410a.inCovCO LV V% ecceLpCAPt"XU I4posh4aDSCet.C do Lue g;Al CLL4e.?.-
Notices CONCTRRENCE:
V- IN 92-71September 29, 992This event at Barseback is directly applicable to an earlier study conductedby the NRC. That study evaluated the potential for displaced thermalinsulation to form debris and to be drawn to the sump screen. The results ofthe study are documented in "Containment Sump Performance," NUREG-0897,Revision 1, dated March 1984. The NRC concluded that the risk associated withthe sump clogging concern did not warrant backfitting of domestic plants.However, based on the Barsebdck event and NUREG-0897, Revision 1, thisconclusion is being reevaluated.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Charles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical contact: Robert L. Dennig, NRR(301) 504-1156List of Recently Issued NRC Information NoticesAttachment:Document Name: 92-71.IN*SEE PREVIOUS CONCURRENCES*OEAB:DOEA:NRR*SC/OEAB:DOEA:NRRRWWoodruff RLDennig09/24/92 09/24/92DOEA:NRR C/OGCB:DOEA:NRR*RPB:ADMCERossi GHMarcus)GLK- TechEd09/ /92 09/,S/92 &o 09/24/24*C/OEAB:DOEA:NRR*C/SPLB:DST:NRR CEP/OIPAChaffee CEMcCracken AKenneke09/ /92 09/ /92 09/ /92 K>-NRCIN 92-XXSeptember xx, 1991 technical contact listed below or the appropriate Office of Nuclear ReactorRegulation project manager.Charles E. Rossi, DirectorDivision of OperationalEvents AssessmentOffice of Nuclear Reactor Regulation
OEAB W'RWWoodruff


===Technical Contact:===
09 5/92 D : DOEA CERossi 09/ /92 TECH EDITOR irgaln Pl 09/2,1/92 09/; f92 BC: SPLU CEMcCracken
Robert L. Dennig, NRR(301) 504-1156Attachment:1. List of Recently Issued Information NoticesCONCTRRENCE:OEAB W'RWWoodruff09 5/92D : DOEACERossi09/ /92TECH EDITORirgaln Pl09/2,1/9209/; f92BC: SPLUCEMcCracken09/ /92BC: OEKBAEChaffee09/ /92BC: KCBGHMarcus09/ /92410.in


}}
09/ /92 BC: OEKB AEChaffee 09/ /92 BC: KCB GHMarcus 09/ /92 410.in}}


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

Revision as of 13:08, 31 August 2018

Partial Plugging of Suppression Pool Strainers at a Foreign BWR
ML031200327
Person / Time
Site: Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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, Three Mile Island, 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  Entergy icon.png
Issue date: 09/30/1992
From: Rossi C E
Office of Nuclear Reactor Regulation
To:
References
IN-92-071, NUDOCS 9209290014
Download: ML031200327 (7)
v • d • e


_~K)UNITED STATES NUCLEAR REGULATORY

COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555 September

30, 1992 NRC INFORMATION

NOTICE 92-71: PARTIAL PLUGGING OF SUPPRESSION

POOL STRAINERS

AT A FOREIGN BWR

Addressees

All holders of operating

licenses or construction

permits for nuclear power reactors.

Purpose

The U.S. Nuclear Regulatory

Commission (NRC) is issuing this information

notice to alert addressees

to the potential-for

loss of emergency

core cooling systems (ECCS) that was identified

as a result of an event at a Swedish boiling water reactor (BWR). It is expected that recipients

will review thel information

for applicability

to their facilities

and consider actions, as appropriate, to avoid similar problems.

However, suggestions

contained

in this information

notice are not NRC requirements;

therefore, no specific action or written response is required.Description

of Circumstances:

On July 28, 1992, Sydkraft AB, the utility licensed by the Swedish regulatory

agency for the BarsebAck

nuclear power plant, was restarting

Unit 2 after the annual outage. While the reactor was at 1 or 2 percent power and at 435 psi, a leaking pilot valve caused a safety valve for the reactor vessel to open.This valve discharges

directly to the drywell. Reactor scram, high pressure safety injection, core spray, and containment

spray systems initiated automatically

in response to the event. Steam from the open safety valve, impinging

on thermally-insulated

equipment, dislodged

440 pounds of metal-jacketed, mineral wool. An estimated

220 pounds of insulating

material was washed into the suppression

pool. Two of five strainers

on the suction side of the ECCS pumps were in service and became partially

plugged with mineral wool. Plugging caused pressure to decrease significantly

across the strainers and caused indications

of cavitation

in one pump in about an hour after the event began. The operators

successfully

back flushed the strainers

and shut down the reactor without additional

problems.Discussion

In the safety analysis for Unit 2 of the Barsebdck

plant, the licensee concluded

that the strainers

would not require back flushing during the first 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> after a loss-of-coolant

accident.

Because of the event of July 28, the Swedish regulatory

agency required Barseback

Unit 2 and four other units of similar design to remain shut down until this problem is resolved.9209290014 e

III IN 92-71 September

30, 1992 This event at BarsebAck

is directly applicable

to an earlier study conducted by the NRC. That study evaluated

the potential

for displaced

thermal insulation

to form debris and to be drawn to the sump screen. The results of the study are documented

in "Containment

Sump Performance," NUREG-0897, Revision 1, dated March 1984. The NRC concluded

that the risk associated

with the sump clogging concern did not warrant backfitting

of domestic plants.However, based on the Barsebdck

event, this conclusion

is being reevaluated.

This information

notice requires no specific action or written response.

If you have any questions

about the information

in this notice, please contact the technical

contact listed below or the appropriate

Office of Nuclear Reactor Regulation (NRR) project manager.(arles si, Director Division of Operational

Events Assessment

Office of Nuclear Reactor Regulation

Technical

contact: Robert L. Dennig, NRR (301) 504-1156 Attachment:

List of Recently Issued NRC Information

Notices

Attachment

IN 92-71 September

30, 1992 LIST OF RECENTLY ISSUED NRC INFORMATION

NOTICES Information

Date of Notice No. Subject Issuance Issued to 92-70 92-69 91-29, Supp.92-68 92-67 1 Westinghouse

Motor-Operated

Valve Performance

Data Supplied to Nuclear Power Plant Licensees Water Leakage from Yard Area Through Conduits Into Buildings Deficiencies

Identified

During Electrical

Dis-tribution

System Func-tional Inspections

Potentially

Substandard

Slip-On, Welding Neck, and Blind Flanges Deficiency

in Design Modifications

to Ad-dress Failures of Hiller Actuators

Upon A Gradual Loss of Air Pressure Access Denied to NRC Inspectors

at Five Star Products, Inc. and Construction

Products Research, Fairfield, Connecticut

Safety System Problems Caused by Modifications

That Were Not Adequately

Reviewed and Tested 09/25/92 09/22/92 09/14/92 09/10/92 09/10/92 09/01/92 09/03/92 08/28/92 All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors and all recipients

of NUREG-0040, "Licensee, Con-tractor and Vendor Inspec-tion Status Report" (White.Book).All holders of OLs or CPs for nuclear power reactors.All holders of -OLs or CPs for nuclear power reactors.92-66 92-65 92-64 Nozzle on Low Relief Ring Settings Pressure Water-Valves OL = Operating

License CP = Construction

Permit

K><YIN 92-71 September

30, 1992 This event at Barseback

is directly applicable

to an earlier study conducted by the NRC. That study evaluated

the potential

for displaced

thermal insulation

to form debris and to be drawn to the sump screen. The results of the study are documented

in "Containment

Sump Performance," NUREG-0897, Revision 1, dated March 1984. The NRC concluded

that the risk associated

with the sump clogging concern did not warrant backfitting

of domestic plants.However, based on the BarsebAck

event, this conclusion

is being reevaluated.

This information

notice requires no specific action or written response.

If you have any questions

about the information

in this notice, please contact the technical

contact listed below or the appropriate

Office of Nuclear Reactor Regulation (NRR) project manager.Original Signed by Charles E. Rossi Charles E. Rossi, Director Division of Operational

Events Assessment

Office of Nuclear Reactor Regulation

Technical

con itact: Robert L. Dennig, NRR (301) 504-1156 List of Recently Issued NRC Information

Notices Attachment:

Document Name: 92-71.IN*SEE PREVIOUS CONCURRENCES

  • OEAB:DOEA:NRR*SC/OEAB:DOEA:NRR

RWWoodruff

RLDennig 09/24/92 09/24/92 V CEp/aze SC~hLAt_-

Jest)o1i A e- ,L .I DO *C/OGCB:DOEA:NRR*RPB:ADM

C GHMarcus TechEd 09/; 92 09/28/92 09/24/24*C/OEAB:DOEA:NRR*C/SPLB:DST:NRR

ICEP/OIPw AChaffee CEMcCracken

AKenqeke 09/k8/92 09/1r/92 09/dg/92 ago,. 4 e , am ASCo-- -I rw W. 4.4a

NRCIN 92-XX September

xx, 1991 documented

in "Containment

Sump Performance," NUREG-0897, Revision 1, dated March 1984. The NRC concluded

that the risk associated

with the sump clogging concern did not warrant backfitting

of domestic plants. However, based on the Barseback event and NUREG-0897, Revision 1, this conclusion

is being reevaluated.

This information

notice requires no specific action or written response.

If you have any question about the information

in this notice, please contact the technical

contact listed below or the appropriate

Office of Nuclear Reactor Regulation

project manager.-Charles E. Rossi, Director Division of Operational

Events Assessment

Office of Nuclear Reactor Regulation

Technmical

Contact: Robert L. Dennig, NRR (301) 504-1156 Attachment:

1. List of Recently Issued Information

Notices* See previous page for concurrence.

CONCURRENCE:

OEAB*RWWoodruff

09/24/92 D:DOEA CERossi 09/ /92 LevA^-t l40-m'-is -DcNpu P I 0 u; "r cz- NX,-,I- PO T-P'TECH EDITORS*JDMain 09/24/92 SC:OEAB*RLDennig 09/24/92:SPLB CEMcCrcken

092/92 09 3-1 n I -Kc BC:OEAB AEChaffee 09/4&/92 BC:OGCB GHMarcus 09/ /92 Or? o SSC.l1er- Dues c,?/Xl/q;;

410a.in CovCO LV V% ecc eLpCAPt"XU

I4 posh 4 aDSCe t.C do Lue g;Al CLL4e.?.-

V- IN 92-71 September

29, 1992 This event at Barseback

is directly applicable

to an earlier study conducted by the NRC. That study evaluated

the potential

for displaced

thermal insulation

to form debris and to be drawn to the sump screen. The results of the study are documented

in "Containment

Sump Performance," NUREG-0897, Revision 1, dated March 1984. The NRC concluded

that the risk associated

with the sump clogging concern did not warrant backfitting

of domestic plants.However, based on the Barsebdck

event and NUREG-0897, Revision 1, this conclusion

is being reevaluated.

This information

notice requires no specific action or written response.

If you have any questions

about the information

in this notice, please contact the technical

contact listed below or the appropriate

Office of Nuclear Reactor Regulation (NRR) project manager.Charles E. Rossi, Director Division of Operational

Events Assessment

Office of Nuclear Reactor Regulation

Technical

con tact: Robert L. Dennig, NRR (301) 504-1156 List of Recently Issued NRC Information

Notices Attachment:

Document Name: 92-71.IN*SEE PREVIOUS CONCURRENCES

  • OEAB:DOEA:NRR*SC/OEAB:DOEA:NRR

RWWoodruff

RLDennig 09/24/92 09/24/92 DOEA:NRR C/OGCB:DOEA:NRR*RPB:ADM

CERossi GHMarcus)GLK-

TechEd 09/ /92 09/,S/92 &o 09/24/24*C/OEAB:DOEA:NRR*C/SPLB:DST:NRR

CEP/OIP AChaffee CEMcCracken

AKenneke 09/ /92 09/ /92 09/ /92 K>-NRCIN 92-XX September

xx, 1991 technical

contact listed below or the appropriate

Office of Nuclear Reactor Regulation

project manager.Charles E. Rossi, Director Division of Operational

Events Assessment

Office of Nuclear Reactor Regulation

Technical

Contact: Robert L. Dennig, NRR (301) 504-1156 Attachment:

1. List of Recently Issued Information

Notices CONCTRRENCE:

OEAB W'RWWoodruff

09 5/92 D : DOEA CERossi 09/ /92 TECH EDITOR irgaln Pl 09/2,1/92 09/; f92 BC: SPLU CEMcCracken

09/ /92 BC: OEKB AEChaffee 09/ /92 BC: KCB GHMarcus 09/ /92 410.in


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