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| {{#Wiki_filter:_~K)UNITED STATES NUCLEAR REGULATORY | | {{#Wiki_filter:_~K) |
| | UNITED STATES |
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| |
|
| COMMISSION | | NUCLEAR REGULATORY COMMISSION |
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| |
|
| ===OFFICE OF NUCLEAR REACTOR REGULATION===
| | OFFICE OF NUCLEAR REACTOR REGULATION |
| WASHINGTON, D.C. 20555 September
| |
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| |
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| 30, 1992 NRC INFORMATION | | WASHINGTON, D.C. 20555 September 30, 1992 NRC INFORMATION NOTICE 92-71: PARTIAL PLUGGING OF SUPPRESSION POOL |
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| NOTICE 92-71: PARTIAL PLUGGING OF SUPPRESSION
| | STRAINERS AT A FOREIGN BWR |
| | |
| POOL STRAINERS
| |
| | |
| AT A FOREIGN BWR | |
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| |
|
| ==Addressees== | | ==Addressees== |
| All holders of operating | | All holders of operating licenses or construction permits for nuclear power |
| | |
| licenses or construction | |
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| |
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| permits for nuclear power reactors.
| | reactors. |
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| |
|
| ==Purpose== | | ==Purpose== |
| The U.S. Nuclear Regulatory | | The U.S. Nuclear Regulatory Commission (NRC) is issuing this information |
| | |
| Commission (NRC) is issuing this information | |
| | |
| notice to alert addressees
| |
| | |
| to the potential-for
| |
| | |
| loss of emergency
| |
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| |
|
| core cooling systems (ECCS) that was identified | | notice to alert addressees to the potential-for loss of emergency core cooling |
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| |
|
| as a result of an event at a Swedish boiling water reactor (BWR). It is expected that recipients | | systems (ECCS) that was identified as a result of an event at a Swedish |
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| |
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| will review thel information | | boiling water reactor (BWR). It is expected that recipients will review thel |
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| |
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| for applicability | | information for applicability to their facilities and consider actions, as |
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| |
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| to their facilities | | appropriate, to avoid similar problems. However, suggestions contained in |
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| |
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| and consider actions, as appropriate, to avoid similar problems.
| | this information notice are not NRC requirements; therefore, no specific |
|
| |
|
| However, suggestions
| | action or written response is required. |
|
| |
|
| contained
| | ==Description of Circumstances== |
| | | : |
| 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 | | On July 28, 1992, Sydkraft AB, the utility licensed by the Swedish regulatory |
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| |
|
| agency for the BarsebAck | | agency for the BarsebAck nuclear power plant, was restarting Unit 2 after the |
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| |
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| nuclear power plant, was restarting
| | 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. |
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| |
|
| 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
| | This valve discharges directly to the drywell. Reactor scram, high pressure |
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| |
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| directly to the drywell. Reactor scram, high pressure safety injection, core spray, and containment
| | safety injection, core spray, and containment spray systems initiated |
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| |
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| spray systems initiated automatically
| | 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 |
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| |
|
| in response to the event. Steam from the open safety valve, impinging
| | washed into the suppression pool. Two of five strainers on the suction side |
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| |
|
| on thermally-insulated
| | of the ECCS pumps were in service and became partially plugged with mineral |
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| |
|
| equipment, dislodged
| | wool. Plugging caused pressure to decrease significantly across the strainers |
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| |
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| 440 pounds of metal-jacketed, mineral wool. An estimated
| | and caused indications of cavitation in one pump in about an hour after the |
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| |
|
| 220 pounds of insulating
| | event began. The operators successfully back flushed the strainers and shut |
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| |
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| material was washed into the suppression
| | down the reactor without additional problems. |
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| |
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| pool. Two of five strainers
| | Discussion |
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| |
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| on the suction side of the ECCS pumps were in service and became partially
| | In the safety analysis for Unit 2 of the Barsebdck plant, the licensee |
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| |
|
| plugged with mineral wool. Plugging caused pressure to decrease significantly
| | concluded that the strainers would not require back flushing during the first |
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| |
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| across the strainers and caused indications
| | 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 |
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| |
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| of cavitation | | of similar design to remain shut down until this problem is resolved. |
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| |
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| in one pump in about an hour after the event began. The operators
| | 9209290014 e |
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| |
|
| successfully
| | III |
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| |
|
| back flushed the strainers
| | IN 92-71 September 30, 1992 This event at BarsebAck is directly applicable |
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| |
|
| and shut down the reactor without additional
| | by the NRC. That study evaluated the potential to an earlier study conducted |
|
| |
|
| problems.Discussion
| | insulation to form debris and to be drawn to for displaced thermal |
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| |
|
| In the safety analysis for Unit 2 of the Barsebdck
| | the study are documented in "Containment Sump the sump screen. The results of |
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| |
|
| plant, the licensee concluded
| | Revision 1, dated March 1984. The NRC concluded Performance," NUREG-0897, that the risk associated with |
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| |
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| that the strainers
| | the sump clogging concern did not warrant backfitting |
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| |
|
| would not require back flushing during the first 10 hours after a loss-of-coolant
| | However, based on the Barsebdck event, this of domestic plants. |
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| |
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| accident.
| | conclusion is being reevaluated. |
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| |
|
| Because of the event of July 28, the Swedish regulatory
| | This information notice requires no specific |
|
| |
|
| agency required Barseback
| | action or written response. If |
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| |
|
| Unit 2 and four other units of similar design to remain shut down until this problem is resolved.9209290014 e
| | you have any questions about the information |
|
| |
|
| III IN 92-71 September
| | in this notice, please contact |
|
| |
|
| 30, 1992 This event at BarsebAck
| | the technical contact listed below or the appropriate |
|
| |
|
| is directly applicable
| | Reactor Regulation (NRR) project manager. Office of Nuclear |
|
| |
|
| to an earlier study conducted by the NRC. That study evaluated
| | (arles si, Director |
|
| |
|
| the potential
| | Division of Operational Events Assessment |
|
| |
|
| for displaced
| | Office of Nuclear Reactor Regulation |
|
| |
|
| thermal insulation
| | Technical contact: Robert L. Dennig, NRR |
|
| |
|
| to form debris and to be drawn to the sump screen. The results of the study are documented
| | (301) 504-1156 Attachment: List of Recently Issued NRC Information Notices |
|
| |
|
| in "Containment
| | Attachment |
|
| |
|
| Sump Performance," NUREG-0897, Revision 1, dated March 1984. The NRC concluded
| | IN 92-71 September 30, 1992 LIST OF RECENTLY ISSUED |
|
| |
|
| that the risk associated
| | NRC INFORMATION NOTICES |
|
| |
|
| with the sump clogging concern did not warrant backfitting
| | Information Date of |
|
| |
|
| of domestic plants.However, based on the Barsebdck
| | Notice No. Subject Issuance Issued to |
|
| |
|
| event, this conclusion
| | 92-70 Westinghouse Motor-Operated 09/25/92 All holders of OLs or CPs |
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| |
|
| is being reevaluated.
| | Valve Performance Data for nuclear power reactors. |
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| |
|
| This information
| | Supplied to Nuclear Power |
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| |
|
| notice requires no specific action or written response.
| | Plant Licensees |
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| |
|
| If you have any questions
| | 92-69 Water Leakage from Yard 09/22/92 All holders of OLs or CPs |
|
| |
|
| about the information
| | Area Through Conduits for nuclear power reactors. |
|
| |
|
| in this notice, please contact the technical
| | Into Buildings |
|
| |
|
| contact listed below or the appropriate
| | 91-29, Deficiencies Identified 09/14/92 All holders of OLs or CPs |
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| |
|
| Office of Nuclear Reactor Regulation (NRR) project manager.(arles si, Director Division of Operational
| | Supp. 1 During Electrical Dis- for nuclear power reactors. |
|
| |
|
| ===Events Assessment===
| | tribution System Func- tional Inspections |
| Office of Nuclear Reactor Regulation
| |
|
| |
|
| Technical
| | 92-68 Potentially Substandard 09/10/92 All holders of OLs or CPs |
|
| |
|
| contact: Robert L. Dennig, NRR (301) 504-1156 Attachment:
| | Slip-On, Welding Neck, for nuclear power reactors. |
| List of Recently Issued NRC Information
| |
|
| |
|
| Notices
| | and Blind Flanges |
|
| |
|
| Attachment
| | 92-67 Deficiency in Design 09/10/92 All holders of OLs or CPs |
|
| |
|
| IN 92-71 September
| | Modifications to Ad- for nuclear power reactors. |
|
| |
|
| 30, 1992 LIST OF RECENTLY ISSUED NRC INFORMATION
| | dress Failures of |
|
| |
|
| NOTICES Information
| | Hiller Actuators Upon |
|
| |
|
| Date of Notice No. Subject Issuance Issued to 92-70 92-69 91-29, Supp.92-68 92-67 1 Westinghouse
| | A Gradual Loss of |
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| |
|
| Motor-Operated
| | Air Pressure |
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| |
|
| Valve Performance
| | 92-66 Access Denied to NRC 09/01/92 All holders of OLs or CPs |
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| |
|
| Data Supplied to Nuclear Power Plant Licensees Water Leakage from Yard Area Through Conduits Into Buildings Deficiencies
| | Inspectors at Five Star for nuclear power reactors |
|
| |
|
| Identified
| | Products, Inc. and and all recipients of |
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| |
|
| During Electrical
| | Construction Products NUREG-0040, "Licensee, Con- Research, Fairfield, tractor and Vendor Inspec- Connecticut tion Status Report" (White. |
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| |
|
| Dis-tribution
| | Book). |
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| |
|
| System Func-tional Inspections | | 92-65 Safety System Problems 09/03/92 All holders of OLs or CPs |
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| |
|
| Potentially
| | Caused by Modifications for nuclear power reactors. |
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| |
|
| Substandard
| | That Were Not Adequately |
|
| |
|
| Slip-On, Welding Neck, and Blind Flanges Deficiency
| | Reviewed and Tested |
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| |
|
| in Design Modifications
| | 92-64 Nozzle Ring Settings 08/28/92 All holders of-OLs or CPs |
|
| |
|
| to Ad-dress Failures of Hiller Actuators
| | on Low Pressure Water- for nuclear power reactors. |
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| |
|
| Upon A Gradual Loss of Air Pressure Access Denied to NRC Inspectors
| | Relief Valves |
|
| |
|
| at Five Star Products, Inc. and Construction
| | OL = Operating License |
|
| |
|
| ===Products Research, Fairfield, Connecticut=== | | CP = Construction Permit |
| Safety System Problems Caused by Modifications
| |
|
| |
|
| ===That Were Not Adequately===
| | K> <YIN 92-71 September 30, 1992 This event at Barseback is directly applicable to an earlier study conducted |
| 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
| | by the NRC. That study evaluated the potential for displaced thermal |
|
| |
|
| License CP = Construction
| | insulation to form debris and to be drawn to the sump screen. The results of |
|
| |
|
| Permit
| | the study are documented in "Containment Sump Performance," NUREG-0897, Revision 1, dated March 1984. The NRC concluded that the risk associated with |
|
| |
|
| K><YIN 92-71 September
| | the sump clogging concern did not warrant backfitting of domestic plants. |
|
| |
|
| 30, 1992 This event at Barseback
| | However, based on the BarsebAck event, this conclusion is being reevaluated. |
|
| |
|
| is directly applicable
| | This information notice requires no specific action or written response. If |
|
| |
|
| to an earlier study conducted by the NRC. That study evaluated
| | you have any questions about the information in this notice, please contact |
|
| |
|
| the potential | | the technical contact listed below or the appropriate Office of Nuclear |
|
| |
|
| for displaced
| | Reactor Regulation (NRR) project manager. |
|
| |
|
| thermal insulation
| | Original Signed by |
|
| |
|
| to form debris and to be drawn to the sump screen. The results of the study are documented
| | Charles E. Rossi |
|
| |
|
| in "Containment
| | Charles E. Rossi, Director |
|
| |
|
| Sump Performance," NUREG-0897, Revision 1, dated March 1984. The NRC concluded
| | Division of Operational Events Assessment |
|
| |
|
| that the risk associated
| | Office of Nuclear Reactor Regulation |
| | |
| 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
| | Technical con itact: Robert L. Dennig, NRR |
|
| |
|
| in this notice, please contact the technical
| | (301) 504-1156 Attachment: List of Recently Issued NRC Information Notices |
|
| |
|
| contact listed below or the appropriate
| | Document Name: 92-71.IN |
|
| |
|
| Office of Nuclear Reactor Regulation (NRR) project manager.Original Signed by Charles E. Rossi Charles E. Rossi, Director Division of Operational
| | *SEE PREVIOUS CONCURRENCES |
|
| |
|
| ===Events Assessment===
| | DO *C/OGCB:DOEA:NRR*RPB:ADM |
| Office of Nuclear Reactor Regulation
| |
|
| |
|
| Technical
| | C GHMarcus TechEd |
|
| |
|
| con itact: Robert L. Dennig, NRR (301) 504-1156 List of Recently Issued NRC Information
| | 09/; 92 09/28/92 09/24/24 |
| | *OEAB:DOEA:NRR*SC/OEAB:DOEA:NRR *C/OEAB:DOEA:NRR*C/SPLB:DST:NRR ICEP/OIPw |
|
| |
|
| Notices Attachment:
| | RWWoodruff RLDennig AChaffee CEMcCracken AKenqeke |
| Document Name: 92-71.IN*SEE PREVIOUS CONCURRENCES
| |
|
| |
|
| *OEAB:DOEA:NRR*SC/OEAB:DOEA:NRR
| | 09/24/92 09/24/92 09/k8/92 09/1r/92 09/dg/92 V CEp/aze |
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| |
|
| RWWoodruff
| | SC~hLAt_- Jest) |
| | o1i A e- rw W. |
|
| |
|
| RLDennig 09/24/92 09/24/92 V CEp/aze SC~hLAt_-
| | ,L .I |
| 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
| | 4.4a |
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| |
|
| ICEP/OIPw AChaffee CEMcCracken
| | -- - I |
|
| |
|
| AKenqeke 09/k8/92 09/1r/92 09/dg/92 ago,. 4 e , am ASCo-- -I rw W. 4.4a
| | 4 ago,. ?. e |
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| |
|
| NRCIN 92-XX September
| | , am ASCo |
|
| |
|
| xx, 1991 documented
| | NRCIN 92-XX |
|
| |
|
| in "Containment | | September xx, 1991 documented in "Containment Sump Performance," NUREG-0897, Revision 1, dated March |
|
| |
|
| Sump Performance," NUREG-0897, Revision 1, dated March 1984. The NRC concluded
| | 1984. The NRC concluded that the risk associated with the sump clogging concern |
|
| |
|
| that the risk associated
| | did not warrant backfitting of domestic plants. However, based on the Barseback |
|
| |
|
| with the sump clogging concern did not warrant backfitting
| | event and NUREG-0897, Revision 1, this conclusion is being reevaluated. |
|
| |
|
| of domestic plants. However, based on the Barseback event and NUREG-0897, Revision 1, this conclusion
| | This information notice requires no specific action or written response. If you |
|
| |
|
| is being reevaluated.
| | have any question about the information in this notice, please contact the |
|
| |
|
| This information
| | technical contact listed below or the appropriate Office of Nuclear Reactor |
|
| |
|
| notice requires no specific action or written response.
| | Regulation project manager.- |
| | Charles E. Rossi, Director |
|
| |
|
| If you have any question about the information
| | Division of Operational |
|
| |
|
| in this notice, please contact the technical
| | Events Assessment |
| | |
| contact listed below or the appropriate
| |
|
| |
|
| Office of Nuclear Reactor Regulation | | Office of Nuclear Reactor Regulation |
|
| |
|
| project manager.-Charles E. Rossi, Director Division of Operational
| | Technmical Contact: Robert L. Dennig, NRR |
|
| |
|
| ===Events Assessment===
| | (301) 504-1156 Attachment: |
| Office of Nuclear Reactor Regulation
| | 1. List of Recently Issued Information Notices |
|
| |
|
| Technmical
| | * See previous page for concurrence. |
|
| |
|
| Contact: Robert L. Dennig, NRR (301) 504-1156 Attachment:
| | CONCURRENCE: |
| 1. List of Recently Issued Information
| | OEAB TECH EDITORS SC:OEAB :SPLB BC:OEAB BC:OGCB |
|
| |
|
| Notices* See previous page for concurrence.
| | *RWWoodruff *JDMain *RLDennig CEMcCrcken AEChaffee GHMarcus |
|
| |
|
| CONCURRENCE:
| | 09/24/92 09/24/92 09/24/92 092/92 09/4&/92 09/ /92 D:DOEA Or? o |
| 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
| | SSC.l1er- Dues |
|
| |
|
| 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;;
| | 09 3-1 CERossi |
| 410a.in CovCO LV V% ecc eLpCAPt"XU
| |
|
| |
|
| I4 posh 4 aDSCe t.C do Lue g;Al CLL4e.?.-
| | 09/ /92 c,?/Xl/q;; |
| V- IN 92-71 September
| | nI -Kc |
|
| |
|
| 29, 1992 This event at Barseback
| | 410a.in |
|
| |
|
| is directly applicable
| | LevA^-t l40-m'- |
| | CovCO |
|
| |
|
| to an earlier study conducted by the NRC. That study evaluated
| | LV ecc |
|
| |
|
| the potential
| | V% |
| | is- DcNpu I P0u;"r t.C do Lue g; |
| | eLpCAPt"XU I4 posh 4 aDSCe Al CLL4e.?.- |
| | cz- NX,-,I- PO T-P' |
|
| |
|
| for displaced
| | V- IN 92-71 September 29, 1992 This event at Barseback is directly applicable to an earlier study conducted |
|
| |
|
| thermal insulation | | by the NRC. That study evaluated the potential for displaced thermal |
|
| |
|
| to form debris and to be drawn to the sump screen. The results of the study are documented | | insulation to form debris and to be drawn to the sump screen. The results of |
|
| |
|
| in "Containment | | the study are documented in "Containment Sump Performance," NUREG-0897, Revision 1, dated March 1984. The NRC concluded that the risk associated with |
|
| |
|
| Sump Performance," NUREG-0897, Revision 1, dated March 1984. The NRC concluded
| | the sump clogging concern did not warrant backfitting of domestic plants. |
|
| |
|
| that the risk associated
| | However, based on the Barsebdck event and NUREG-0897, Revision 1, this |
|
| |
|
| with the sump clogging concern did not warrant backfitting
| | conclusion is being reevaluated. |
|
| |
|
| of domestic plants.However, based on the Barsebdck
| | This information notice requires no specific action or written response. If |
|
| |
|
| event and NUREG-0897, Revision 1, this conclusion
| | you have any questions about the information in this notice, please contact |
|
| |
|
| is being reevaluated.
| | the technical contact listed below or the appropriate Office of Nuclear |
|
| |
|
| This information
| | Reactor Regulation (NRR) project manager. |
|
| |
|
| notice requires no specific action or written response.
| | Charles E. Rossi, Director |
|
| |
|
| If you have any questions
| | Division of Operational Events Assessment |
|
| |
|
| about the information
| | Office of Nuclear Reactor Regulation |
|
| |
|
| in this notice, please contact the technical
| | Technical con tact: Robert L. Dennig, NRR |
|
| |
|
| contact listed below or the appropriate
| | (301) 504-1156 Attachment: List of Recently Issued NRC Information Notices |
|
| |
|
| Office of Nuclear Reactor Regulation (NRR) project manager.Charles E. Rossi, Director Division of Operational
| | Document Name: 92-71.IN |
|
| |
|
| ===Events Assessment===
| | *SEE PREVIOUS CONCURRENCES |
| Office of Nuclear Reactor Regulation
| |
|
| |
|
| Technical
| | DOEA:NRR C/OGCB:DOEA:NRR*RPB:ADM |
|
| |
|
| con tact: Robert L. Dennig, NRR (301) 504-1156 List of Recently Issued NRC Information
| | CERossi GHMarcus)GLK- TechEd |
|
| |
|
| Notices Attachment:
| | 09/ /92 09/,S/92 &o 09/24/24 |
| Document Name: 92-71.IN*SEE PREVIOUS CONCURRENCES
| | *OEAB:DOEA:NRR*SC/OEAB:DOEA:NRR *C/OEAB:DOEA:NRR*C/SPLB:DST:NRR CEP/OIP |
|
| |
|
| *OEAB:DOEA:NRR*SC/OEAB:DOEA:NRR
| | RWWoodruff RLDennig AChaffee CEMcCracken AKenneke |
|
| |
|
| RWWoodruff
| | 09/24/92 09/24/92 09/ /92 09/ /92 09/ /92 |
|
| |
|
| RLDennig 09/24/92 09/24/92 DOEA:NRR C/OGCB:DOEA:NRR*RPB:ADM
| | K>- |
| | NRCIN 92-XX |
|
| |
|
| CERossi GHMarcus)GLK-
| | September xx, 1991 technical contact listed below or the appropriate Office of Nuclear Reactor |
| TechEd 09/ /92 09/,S/92 &o 09/24/24*C/OEAB:DOEA:NRR*C/SPLB:DST:NRR
| |
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| |
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| CEP/OIP AChaffee CEMcCracken
| | Regulation project manager. |
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| AKenneke 09/ /92 09/ /92 09/ /92 K>-NRCIN 92-XX September
| | Charles E. Rossi, Director |
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| xx, 1991 technical
| | Division of Operational |
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| |
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| contact listed below or the appropriate
| | Events Assessment |
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| Office of Nuclear Reactor Regulation | | Office of Nuclear Reactor Regulation |
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| |
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| project manager.Charles E. Rossi, Director Division of Operational
| | ===Technical Contact:=== |
|
| |
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| ===Events Assessment=== | | ===Robert L. Dennig, NRR=== |
| Office of Nuclear Reactor Regulation
| | (301) 504-1156 Attachment: |
| | 1. List of Recently Issued Information Notices |
|
| |
|
| Technical
| | CONCTRRENCE: |
| | OEAB W' TECH EDITOR BC: SPLU BC: OEKB BC: KCB |
|
| |
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| Contact: Robert L. Dennig, NRR (301) 504-1156 Attachment:
| | RWWoodruff irgaln Pl CEMcCracken AEChaffee GHMarcus |
| 1. List of Recently Issued Information
| |
|
| |
|
| Notices CONCTRRENCE:
| | 09 5/92 09/2,1/92 09/; f92 09/ /92 09/ /92 09/ /92 D: DOEA |
| OEAB W'RWWoodruff
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| 09 5/92 D : DOEA CERossi 09/ /92 TECH EDITOR irgaln Pl 09/2,1/92 09/; f92 BC: SPLU CEMcCracken
| | CERossi |
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| 09/ /92 BC: OEKB AEChaffee 09/ /92 BC: KCB GHMarcus 09/ /92 410.in}} | | 09/ /92 |
| | 410.in}} |
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| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Partial Plugging of Suppression Pool Strainers at a Foreign BWRML031200327 |
Person / Time |
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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](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
09/30/1992 |
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From: |
Rossi C Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-92-071, NUDOCS 9209290014 |
Download: ML031200327 (7) |
|
Similar Documents at 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 |
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Category:NRC Information Notice
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 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 [[: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 [[:Three Mile Island]] 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]] </code>.
[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 [[: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 [[:Three Mile Island]] 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]] </code>. |
_~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
by the NRC. That study evaluated the potential to an earlier study conducted
insulation to form debris and to be drawn to for displaced thermal
the study are documented in "Containment Sump the sump screen. The results of
Revision 1, dated March 1984. The NRC concluded Performance," NUREG-0897, that the risk associated with
the sump clogging concern did not warrant backfitting
However, based on the Barsebdck event, this of domestic plants.
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
Reactor Regulation (NRR) project manager. Office of Nuclear
(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 Westinghouse Motor-Operated 09/25/92 All holders of OLs or CPs
Valve Performance Data for nuclear power reactors.
Supplied to Nuclear Power
Plant Licensees
92-69 Water Leakage from Yard 09/22/92 All holders of OLs or CPs
Area Through Conduits for nuclear power reactors.
Into Buildings
91-29, Deficiencies Identified 09/14/92 All holders of OLs or CPs
Supp. 1 During Electrical Dis- for nuclear power reactors.
tribution System Func- tional Inspections
92-68 Potentially Substandard 09/10/92 All holders of OLs or CPs
Slip-On, Welding Neck, for nuclear power reactors.
and Blind Flanges
92-67 Deficiency in Design 09/10/92 All holders of OLs or CPs
Modifications to Ad- for nuclear power reactors.
dress Failures of
Hiller Actuators Upon
A Gradual Loss of
Air Pressure
92-66 Access Denied to NRC 09/01/92 All holders of OLs or CPs
Inspectors at Five Star for nuclear power reactors
Products, Inc. and and all recipients of
Construction Products NUREG-0040, "Licensee, Con- Research, Fairfield, tractor and Vendor Inspec- Connecticut tion Status Report" (White.
Book).
92-65 Safety System Problems 09/03/92 All holders of OLs or CPs
Caused by Modifications for nuclear power reactors.
That Were Not Adequately
Reviewed and Tested
92-64 Nozzle Ring Settings 08/28/92 All holders of-OLs or CPs
on Low Pressure Water- for nuclear power reactors.
Relief 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 Attachment: List of Recently Issued NRC Information Notices
Document Name: 92-71.IN
- SEE PREVIOUS CONCURRENCES
DO *C/OGCB:DOEA:NRR*RPB:ADM
C GHMarcus TechEd
09/; 92 09/28/92 09/24/24
- OEAB:DOEA:NRR*SC/OEAB:DOEA:NRR *C/OEAB:DOEA:NRR*C/SPLB:DST:NRR ICEP/OIPw
RWWoodruff RLDennig AChaffee CEMcCracken AKenqeke
09/24/92 09/24/92 09/k8/92 09/1r/92 09/dg/92 V CEp/aze
SC~hLAt_- Jest)
o1i A e- rw W.
,L .I
4.4a
-- - I
4 ago,. ?. e
, am ASCo
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 TECH EDITORS SC:OEAB :SPLB BC:OEAB BC:OGCB
- RWWoodruff *JDMain *RLDennig CEMcCrcken AEChaffee GHMarcus
09/24/92 09/24/92 09/24/92 092/92 09/4&/92 09/ /92 D:DOEA Or? o
SSC.l1er- Dues
09 3-1 CERossi
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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 Attachment: List of Recently Issued NRC Information Notices
Document Name: 92-71.IN
- SEE PREVIOUS CONCURRENCES
DOEA:NRR C/OGCB:DOEA:NRR*RPB:ADM
CERossi GHMarcus)GLK- TechEd
09/ /92 09/,S/92 &o 09/24/24
- OEAB:DOEA:NRR*SC/OEAB:DOEA:NRR *C/OEAB:DOEA:NRR*C/SPLB:DST:NRR CEP/OIP
RWWoodruff RLDennig AChaffee CEMcCracken AKenneke
09/24/92 09/24/92 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' TECH EDITOR BC: SPLU BC: OEKB BC: KCB
RWWoodruff irgaln Pl CEMcCracken AEChaffee GHMarcus
09 5/92 09/2,1/92 09/; f92 09/ /92 09/ /92 09/ /92 D: DOEA
CERossi
09/ /92
410.in
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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)
- 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)
- Information Notice 1992-04, Potter and Brumfield Model Mdr Rotary Relay Failures (6 January 1992, Topic: Probabilistic Risk Assessment)
- Information Notice 1992-04, Potter and Brumfield Model MDR Rotary Relay Failures (6 January 1992, Topic: Probabilistic Risk Assessment)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs RXMH2 Relays (8 January 1992)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs Rxmh2 Relays (8 January 1992)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in ABS RXMH2 Relays (8 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 1992-06, 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, Topic: Brachytherapy)
- Information Notice 1992-12, Effects of Cable Leakage Currents on Instrument Settings and Indications (10 February 1992, Topic: Brachytherapy)
- Information Notice 1992-13, Inadequate Control Over Vehicular Traffic at Nuclear Power Plant Sites (18 February 1992, Topic: Brachytherapy)
- Information Notice 1992-14, Uranium Oxide Fires at Fuel Cycle Facilities (21 February 1992, Topic: Brachytherapy)
- Information Notice 1992-15, Failure of Primary Systems Compression Fitting (24 February 1992)
- 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, Brachytherapy)
- 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)
- 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)
- Information Notice 1992-27, Thermally Induced Accelerated Aging and Failure of Ite/Gould A.C. Relays Used in Safety-Related Applications (3 April 1992)
- 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, Topic: Brachytherapy)
- 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)
- Information Notice 1992-41, Consideration of Stem Rejection Load In Calculation of Required Valve Thrust (29 May 1992, Topic: Anchor Darling)
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