ML033040019
| ML033040019 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Calvert Cliffs, Dresden, Davis Besse, Nine Mile Point, Diablo Canyon, South Texas  |
| Issue date: | 10/29/2003 |
| From: | Beckner W NRC/NRR/DIPM |
| To: | Delattre D International Atomic Energy Agency (IAEA) |
| Dozier J, NRR/IROB 415-1014 | |
| References | |
| BN-03-001, BN-03-002, IN-03-011, IN-03-013, IN-03-014, IN-03-015, IN-03-017, IN-03-018, IN-03-019 | |
| Download: ML033040019 (22) | |
Text
October 29, 2003 Mr. Dominique Delattre Head, Regulatory Activities Unit IAEA INES/NEWS Coordinator International Atomic Energy Agency Wagramer Strasse 5, P.O. Box 100 A-1400 Wien AUTRICHE
Dear Mr. Delattre:
The following operating experience reports from United States reactors are enclosed for your consideration for including in the AIRS database:
NRC Information Notice 2003-11: Leakage Found on Bottom-Mounted Instrumentation Nozzles NRC Information Notice 2003-13: Steam Generator Tube Degradation at Diablo Canyon NRC Information Notice 2003-14: Potential Vulnerability of Plant Computer Network to Worm Infection NRC Information Notice 2003-15: Importance of Follow-up Activities in Resolving Maintenance Issues NRC Information Notice 2003-17: Reduced Service Life of Automatic Switch Company (ASCO)
Solenoid Valves with Buna-N Material NRC Information Notice 2003-18: General Electric Type SBM Control Switches with Defective CAM Followers NRC Information Notice 2003-19: Unanalyzed Condition of Reactor Coolant Pump Seal Leak-off Line During Postulated Fire Scenarios or Station Blackout NRC Bulletin 2003-01: Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors NRC Bulletin 2003-02: Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity Each report is being submitted in the following two media: (1) a hard copy of the input file for the AIRS database; and (2) a 3.5-inch HD diskette containing the input file for the AIRS database in WordPerfect format.
Mr. Dominique Delattre October 29, 2003 If you have any questions regarding these reports, please call Jerry Dozier of my staff. He can be reached at 301-415-1014.
Sincerely,
/RA/
William D. Beckner, Chief Reactor Operations Branch Division of Inspection Program Management Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/enclosures:
Dr. Pekka T. Pyy Administrator, Operating Experience & Human Factors Nuclear Safety Division Nuclear Energy Agency OECD Le Seine St. Germain, Batiment B 12, Boulevard des Iles 92130 - Issy-les-Moulineaux FRANCE
ML033040019 DOCUMENT NAME:
C:\\ORPCheckout\\FileNET\\ML033040019.wpd OFFICE RSE:OES:IROB:DIPM IMA:OES:IROB:DIPM SC:OES:IROB:DIPM D:IROB:DIPM NAME IJDozier KAGray TReis WDBeckner DATE 10/28/2003 10/28/2003 10/28/2003 10/28/2003
INCIDENT REPORTING SYSTEM IRS NO.
EVENT DATE 04/12/2003 DATE RECEIVED EVENT TITLE NRC Information Notice 2003-11: Leakage Found on Bottom-Mounted Instrumentation Nozzles COUNTRY PLANT AND UNIT REACTOR TYPE USA South Texas Project Unit 1 PWR INITIAL STATUS RATED POWER (MWe NET)
N/A DESIGNER 1st COMMERCIAL OPERATION Westinghouse 4lp 03/22/1988 ABSTRACT The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice (IN) to alert addressees to indications of leakage in the form of boron deposits discovered on bottom-mounted instrumentation (BMI) nozzles at South Texas Project Unit 1 (STP Unit 1).
NRC INFORMATION NOTICE 2003-11 Please refer to the dictionary of codes corresponding to each of the sections below and to the coding guidelines manual.
1.
Reporting Categories:
1.4 1.2.2 2.
Plant Status Prior to the Event:
2.3.2 3.
Failed/Affected Systems:
3.AC 4.
Failed/Affected Components:
4.2.5 5.
Cause of the Event:
5.1.1.7 5.1.1.3 6.
Effects on Operation:
6.9 7.
Characteristics of the Incident:
- 7. 2 8.
Nature of Failure or Error:
8.1 9.
Nature of Recovery Actions:
9.0
INCIDENT REPORTING SYSTEM IRS NO.
EVENT DATE 08/28/2003 DATE RECEIVED EVENT TITLE NRC Information Notice 2003-13: Steam Generator Tube Degradation at Diablo Canyon COUNTRY PLANT AND UNIT REACTOR TYPE USA Diablo Canyon Unit 2 PWR INITIAL STATUS RATED POWER (MWe NET)
N/A DESIGNER 1st COMMERCIAL OPERATION Westinghouse 4lp 08/26/1985 ABSTRACT The U.S. Nuclear Regulatory Commission is issuing this information notice to inform addressees about findings from a recent steam generator tube inspection at the Diablo Canyon Power Plant, Unit 2.
NRC INFORMATION NOTICE 2003-13 Please refer to the dictionary of codes corresponding to each of the sections below and to the coding guidelines manual.
1.
Reporting Categories:
1.3 1.4 2.
Plant Status Prior to the Event:
2.3.2 3.
Failed/Affected Systems:
3.AH 4.
Failed/Affected Components:
4.2.4 5.
Cause of the Event:
5.1.1.7 5.3.1 6.
Effects on Operation:
6.9 7.
Characteristics of the Incident:
7.2 8.
Nature of Failure or Error:
8.2 9.
Nature of Recovery Actions:
9.0
INCIDENT REPORTING SYSTEM IRS NO.
EVENT DATE 01/25/2003 DATE RECEIVED EVENT TITLE NRC INFORMATION NOTICE 2003-14: Potential Vulnerability of Plant Computer Network to Worm Infection COUNTRY PLANT AND UNIT REACTOR TYPE USA Nine Mile Point Unit 1 BWR INITIAL STATUS RATED POWER (MWe NET)
N/A DESIGNER 1st COMMERCIAL OPERATION GEC 12/01/1969 ABSTRACT The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alert addressees to the recent identification of a potential vulnerability of the plant computer network server to infection by the Microsoft (MS) SQL Server worm.
NRC INFORMATION NOTICE 2003-14 Please refer to the dictionary of codes corresponding to each of the sections below and to the coding guidelines manual.
1.
Reporting Categories:
1.4 2.
Plant Status Prior to the Event:
2.3.2.1 3.
Failed/Affected Systems:
3.1A 4.
Failed/Affected Components:
4.4.2 5.
Cause of the Event:
5.1.5.6 5.3.3 6.
Effects on Operation:
6.0 7.
Characteristics of the Incident:
7.16 8.
Nature of Failure or Error:
8.4 9.
Nature of Recovery Actions:
9.1
INCIDENT REPORTING SYSTEM IRS NO.
EVENT DATE 01/25/2003 DATE RECEIVED EVENT TITLE NRC INFORMATION NOTICE 2003-15: Importance of Follow-up Activities in Resolving Maintenance Issues COUNTRY PLANT AND UNIT REACTOR TYPE USA South Texas Unit 2 PWR INITIAL STATUS RATED POWER (MWe NET)
N/A DESIGNER 1st COMMERCIAL OPERATION Westinghouse 4lp 03/28/1989 ABSTRACT The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alert addressees to recent experience that emphasizes the importance of followup activities in resolving maintenance issues in nuclear power plants.
NRC INFORMATION NOTICE 2003-15 Please refer to the dictionary of codes corresponding to each of the sections below and to the coding guidelines manual.
1.
Reporting Categories:
1.2.5 1.4 2.
Plant Status Prior to the Event: 2.3.2.1 3.
Failed/Affected Systems:
3.BE 4.
Failed/Affected Components:
4.2.3 5.
Cause of the Event:
5.3.1 5.4.7 6.
Effects on Operation:
6.9 7.
Characteristics of the Incident: 7.8 8.
Nature of Failure or Error:
8.3 9.
Nature of Recovery Actions:
9.1
INCIDENT REPORTING SYSTEM IRS NO.
EVENT DATE 9/1/2002 DATE RECEIVED EVENT TITLE NRC INFORMATION NOTICE 2003-17: Reduced Service Life of Automatic Switch Company (ASCO) Solenoid Valves with Buna-N Material COUNTRY PLANT AND UNIT REACTOR TYPE USA Dresden, Unit 2 BWR INITIAL STATUS RATED POWER (MWe NET)
N/A DESIGNER 1st COMMERCIAL OPERATION GE-3MK1 02/20/1991 ABSTRACT The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alert addressees to potential problems caused by the hardening of Buna-N material used in fabricating solenoid valves manufactured by Automatic Switch Company (ASCO).
NRC INFORMATION NOTICE 2003-17 Please refer to the dictionary of codes corresponding to each of the sections below and to the coding guidelines manual.
1.
Reporting Categories:
1.2.4 1.4 2.
Plant Status Prior to the Event: 2.3.2.1 3.
Failed/Affected Systems:
3.AB 4.
Failed/Affected Components:
4.2.3 5.
Cause of the Event:
5.1.1.9 6.
Effects on Operation:
6.9 7.
Characteristics of the Incident: 7.13 8.
Nature of Failure or Error:
8.3 9.
Nature of Recovery Actions:
9.1
INCIDENT REPORTING SYSTEM IRS NO.
EVENT DATE 01/5/2003 DATE RECEIVED EVENT TITLE NRC INFORMATION NOTICE 2003-18: General Electric Type SBM Control Switches with Defective CAM Followers COUNTRY PLANT AND UNIT REACTOR TYPE USA Calvert Cliffs Unit 1 PWR INITIAL STATUS RATED POWER (MWe NET)
N/A DESIGNER 1st COMMERCIAL OPERATION CE 07/31/1974 ABSTRACT The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to inform addressees of recent and long-term operational experience with control switches and relays incorporating a polycarbonate plastic material manufactured by General Electric known as Lexan.
NRC INFORMATION NOTICE 2003-18 Please refer to the dictionary of codes corresponding to each of the sections below and to the coding guidelines manual.
1.
Reporting Categories:
1.2.5 1.4
- 2. Plant Status Prior to the Event:
2.3.2.1 3.
Failed/Affected Systems:
3.EF 3.EB 3.CB 4.
Failed/Affected Components:
4.3.2 5.
Cause of the Event:
5.7.2 5.4.5 6.
Effects on Operation:
6.9 7.
Characteristics of the Incident: 7.4 8.
Nature of Failure or Error:
8.3 9.
Nature of Recovery Actions:
9.1
INCIDENT REPORTING SYSTEM IRS NO.
EVENT DATE 01/13/2003 DATE RECEIVED EVENT TITLE NRC INFORMATION NOTICE 2003-19: Unanalyzed Condition of Reactor Coolant Pump Seal Leak-off Line During Postulated Fire Scenarios or Station Blackout COUNTRY PLANT AND UNIT REACTOR TYPE USA Millstone Unit 3 PWR INITIAL STATUS RATED POWER (MWe NET)
N/A DESIGNER 1st COMMERCIAL OPERATION Westinghouse 4lp 01/31/1986 ABSTRACT The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice (IN) to alert addressees to the recent identification of an unanalyzed condition involving the design of the reactor coolant pump (RCP) seal leakoff line.
NRC INFORMATION NOTICE 2003-19 Please refer to the dictionary of codes corresponding to each of the sections below and to the coding guidelines manual.
1.
Reporting Categories:
1.3.1 1.4
- 2. Plant Status Prior to the Event:
2.0 3.
Failed/Affected Systems:
3.AE 4.
Failed/Affected Components:
4.2.6 5.
Cause of the Event:
5.7.1 6.
Effects on Operation:
6.0 7.
Characteristics of the Incident: 7.5 8.
Nature of Failure or Error:
8.1 9.
Nature of Recovery Actions:
9.0
INCIDENT REPORTING SYSTEM IRS NO.
EVENT DATE 12/11/2002 DATE RECEIVED EVENT TITLE NRC Bulletin 2003-01: Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors COUNTRY PLANT AND UNIT REACTOR TYPE USA Davis Besse PWR INITIAL STATUS RATED POWER (MWe NET)
N/A DESIGNER 1st COMMERCIAL OPERATION B&W 04/22/1977 ABSTRACT The U.S. Nuclear Regulatory Commission (NRC) is issuing this bulletin to: (1) inform addressees of the results of NRC-sponsored research identifying the potential susceptibility of pressurized-water reactor (PWR) recirculation sump screens to debris blockage in the event of a high-energy line break (HELB) requiring recirculation operation of the emergency core cooling system (ECCS) or containment spray system (CSS); (2) inform addressees of the potential for additional adverse effects due to debris blockage of flowpaths necessary for ECCS and CSS recirculation and containment drainage.
NRC BULLETIN 2003-01 Please refer to the dictionary of codes corresponding to each of the sections below and to the coding guidelines manual.
1.
Reporting Categories:
1.2 1.4 1.2.5 2.
Plant Status Prior to the Event:
2.3.2 3.
Failed/Affected Systems:
3.BG 4.
Failed/Affected Components:
4.2.1 5.
Cause of the Event:
5.1.1.8 6.
Effects on Operation:
6.10 7.
Characteristics of the Incident:
7.4 8.
Nature of Failure or Error:
8.3 9.
Nature of Recovery Actions:
9.0
INCIDENT REPORTING SYSTEM IRS NO.
EVENT DATE 04/12/2003 DATE RECEIVED EVENT TITLE NRC Bulletin 2003-02: Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity COUNTRY PLANT AND UNIT REACTOR TYPE USA South Texas Project Unit 1 PWR INITIAL STATUS RATED POWER (MWe NET)
N/A DESIGNER 1st COMMERCIAL OPERATION Westinghouse 4lp 03/22/1988 ABSTRACT The U.S. Nuclear Regulatory Commission (NRC) is issuing this bulletin to advise PWR addressees that current methods of inspecting the reactor pressure vessel lower heads may need to be supplemented with additional measures (e.g., bare-metal visual inspections) to detect reactor coolant pressure boundary (RCPB) leakage.
NRC BULLETIN 2003-02 Please refer to the dictionary of codes corresponding to each of the sections below and to the coding guidelines manual.
1.
Reporting Categories:
1.4 1.2.2 2.
Plant Status Prior to the Event:
2.3.2 3.
Failed/Affected Systems:
3.AC 4.
Failed/Affected Components:
4.2.5 5.
Cause of the Event:
5.1.1.7 5.1.1.3 6.
Effects on Operation:
6.9 7.
Characteristics of the Incident:
- 7. 2 8.
Nature of Failure or Error:
8.1 9.
Nature of Recovery Actions:
9.0