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 , 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 Issue date:
09/30/1992 From:
Rossi C Office of Nuclear Reactor Regulation To:
References IN-92-071 , NUDOCS 9209290014Download: ML031200327 (7)
Similar Documents at
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 Category:NRC Information Notice
[Table view] The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Crane]] </code>.
Contents
1 UNITED STATES 2 OFFICE OF NUCLEAR REACTOR REGULATION 3 September 30, 1992 4 PARTIAL PLUGGING OF SUPPRESSION POOL 5 Addressees 6 Purpose 7 Description of Circumstances
7.1 Reactor scram, high pressure 7.2 An estimated 220 pounds of insulating material was 7.3 The results of 7.4 The NRC concluded that the risk associated with 7.5 Division of Operational Events Assessment 7.6 List of Recently Issued NRC Information Notices 7.7 September 30, 1992 LIST OF RECENTLY ISSUED 7.8 Valve Performance Data 7.9 Plant Licensees 7.10 Area Through Conduits 7.11 Deficiencies Identified 7.12 Potentially Substandard 7.13 Deficiency in Design 7.14 Hiller Actuators Upon 7.15 Air Pressure 7.16 Inspectors at Five Star 7.17 Construction Products 7.18 Safety System Problems 7.19 That Were Not Adequately 7.20 All holders of OLs or CPs 7.21 All holders of OLs or CPs 7.22 All holders of OLs or CPs 7.23 All holders of OLs or CPs 7.24 All holders of OLs or CPs 7.25 All holders of OLs or CPs 7.26 All holders of OLs or CPs 7.27 Ring Settings 7.28 September 30, 1992 7.29 The results of 7.30 The NRC concluded that the risk associated with 7.31 Original Signed by 7.32 Charles E. Rossi, Director 7.33 Office of Nuclear Reactor Regulation 7.34 Robert L. Dennig, NRR 7.35 List of Recently Issued NRC Information Notices 7.36 However, based on the Barseback 7.37 Charles E. Rossi, Director 7.38 Events Assessment 7.39 Robert L. Dennig, NRR 7.40 List of Recently Issued Information Notices 7.41 TECH EDITORS 7.42 September 29, 1992 7.43 Charles E. Rossi, Director 7.44 Office of Nuclear Reactor Regulation 7.45 Robert L. Dennig, NRR 7.46 List of Recently Issued NRC Information Notices 7.47 Charles E. Rossi, Director 7.48 Events Assessment 7.49 Technical Contact: 7.50 Robert L. Dennig, NRR
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 hours 1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />
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 conitact:
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
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
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 09/24/92 SC:OEAB
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 contact:
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
list Information Notice 1992-01, Cable Damage Caused by Inadequate Cable Installation Procedures and Controls 3 January 1992 Information Notice 1992-02, Relap5/MOD3 Computer Code Error Associated with the Conservation of Energy Equation 3 January 1992 Topic Overspeed Information Notice 1992-02, Relap5/Mod3 Computer Code Error Associated with the Conservation of Energy Equation 3 January 1992 Information Notice 1992-03, Remote Trip Function Failures in General Electric F-Frame Molded-Case Circuit Breakers 6 January 1992 Topic Overspeed Information Notice 1992-04, Potter and Brumfield Model Mdr Rotary Relay Failures 6 January 1992 Topic Probabilistic Risk Assessment Commercial Grade Overspeed Information Notice 1992-04, Potter and Brumfield Model MDR Rotary Relay Failures 6 January 1992 Topic Probabilistic Risk Assessment Commercial Grade Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs RXMH2 Relays 8 January 1992 Topic Commercial Grade Overspeed Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs Rxmh2 Relays 8 January 1992 Topic Commercial Grade Information Notice 1992-05, Potential Coil Insulations Breakdown in ABS RXMH2 Relays 8 January 1992 Topic Commercial Grade Information Notice 1992-06, Reliability of ATWS Mitigation System and Other NRC Required Equipment Not Controlled by Plant Technical Specifications 15 January 1992 Information Notice 1992-06, Reliability of ATWS Mitigation System and Other NRC Required Equipment not Controlled by Plant Technical Specifications 15 January 1992 Information Notice 1992-07, Rapid Flow-induced Erosion/Corrosion of Feedwater Piping 9 January 1992 Information Notice 1992-08, Revised Protective Action Guidance for Nuclear Incidents 23 January 1992 Information Notice 1992-09, Overloading and Subsequent Lock Out of Electrical Buses During Accident Conditions 30 January 1992 Information Notice 1992-10, Brachytherapy Incidents Involving Iridium-192 Wire Used in Endobronchial Treatments 31 January 1992 Topic Brachytherapy Information Notice 1992-10, Brachytherapy Incidents Involving Iridium-192 Wire used in Endobronchial Treatments 31 January 1992 Topic Brachytherapy Information Notice 1992-11, Soil and Water Contamination at Fuel Cycle Facilities 5 February 1992 Information Notice 1992-12, Effects of Cable Leakage Currents on Instrument Settings and Indications 10 February 1992 Topic High Energy Line Break Information Notice 1992-13, Inadequate Control Over Vehicular Traffic at Nuclear Power Plant Sites 18 February 1992 Topic Loss of Offsite Power Information Notice 1992-14, Uranium Oxide Fires at Fuel Cycle Facilities 21 February 1992 Information Notice 1992-15, Failure of Primary Systems Compression Fitting 24 February 1992 Topic Unidentified leakage Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown 25 February 1992 Topic Reactor Vessel Water Level Temporary Modification Information Notice 1992-17, NRC Inspections of Programs Being Developed at Nuclear Power Plants in Response to Generic Letter 89-10 26 February 1992 Topic Stroke time Information Notice 1992-18, Potential for Loss of Remote Shutdown Capability During a Control Room Fire 28 February 1992 Topic Hot Short Safe Shutdown Information Notice 1992-19, Misapplication of Potter and Brumfield Mdr Rotary Relays 2 March 1992 Information Notice 1992-19, Misapplication of Potter and Brumfield MDR Rotary Relays 2 March 1992 Information Notice 1992-20, Inadequate Local Leak Rate Testing 3 March 1992 Topic Local Leak Rate Testing Information Notice 1992-21, Spent Fuel Pool Reactivity Calculations 24 March 1992 Information Notice 1992-23, Results of Validation Testing of Motor-Operated Valve Diagnostic Equipment 27 March 1992 Information Notice 1992-24, Distributor Modification to Certain Commercial-Grade Agastat Electrical Relays 30 March 1992 Information Notice 1992-25, Pressure Locking of Motor-Operated Flexible Wedge Gate Valves 2 April 1992 Topic Stroke time Hydrostatic Information Notice 1992-27, Thermally Induced Accelerated Aging and Failure of ITE/Gould A.C. Relays used in Safety-Related Applications 3 April 1992 Topic Commercial Grade Information Notice 1992-27, Thermally Induced Accelerated Aging and Failure of Ite/Gould A.C. Relays Used in Safety-Related Applications 3 April 1992 Topic Commercial Grade Information Notice 1992-28, Inadequate Fire Suppression System Testing 8 April 1992 Topic Safe Shutdown Information Notice 1992-29, Potential Breaker Miscoordination Caused by Instantaneous Trip Circuitry 17 April 1992 Information Notice 1992-30, Falsification of Plant Records 23 April 1992 Information Notice 1992-31, Electrical Connection Problem in Johnson Yokogawa Corporation YS-80 Programmable Indicating Controllers 27 April 1992 Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (Within 10 Miles) Emergency Operations Facilities and Technical Support Centers 29 April 1992 Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (within 10 Miles) Emergency Operations Facilities and Technical Support Centers 29 April 1992 Information Notice 1992-33, Increased Instrument Response Time When Pressure Dampening Devices Are Installed 30 April 1992 Information Notice 1992-33, Increased Instrument Response Time When Pressure Dampening Devices are Installed 30 April 1992 Information Notice 1992-34, New Exposure Limits for Airborne Uranium and Thorium 6 May 1992 Information Notice 1992-35, Higher than Predicted Erosion/Corrosion in Unisolable Reactor Coolant Pressure Boundary Piping Inside Containment at a Boiling Water Reactor 6 May 1992 Information Notice 1992-35, Higher than Predicted Erosion/Corrosion in Unisolable Reactor Coolant Pressure Boundary Piping inside Containment at a Boiling Water Reactor 6 May 1992 Information Notice 1992-36, Intersystem LOCA Outside Containment 7 May 1992 Information Notice 1992-37, Implementation of the Deliberate Misconduct Rule 8 May 1992 Information Notice 1992-38, Implementation Date for the Revision to the EPA Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 26 May 1992 Information Notice 1992-39, Unplanned Return to Criticality During Reactor Shutdown 13 May 1992 Topic Fuel cladding Information Notice 1992-40, Inadequate Testing of Emergency Bus Undervoltage Logic Circuitry 27 May 1992 Topic Loss of Offsite Power Information Notice 1992-41, Consideration of Stem Rejection Load In Calculation of Required Valve Thrust 29 May 1992 Topic Anchor Darling ... further results
