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References

This page lists, in chronological order, general references for Reactor Vessel Head Penetration Leackage.

Date
Description
01-08-04 N 03-11, Supplement 1, "Leakage Found on Bottom-Mounted Instrumentation Nozzles"
08-13-03 IN 03-011, Leakage Found on Bottom-Mounted Instrumentation Nozzles
07-29-03 RIS 03-013, NRC Review of Responses to Bulletin 2002-01, "Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity"
06-23-03 MRP Letter - Recommendation for PWR Owners with Alloy 600 Bottom Mounted Reactor Vessel Instrument Nozzles
NRC Information Notice 2003-02: Recent Experience with Reactor Coolant System Leakage and Boric Acid Corrosion
NRC Bulletin 2002-02: Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs
Information Notice 2002-13: Possible Indicators of Ongoing Reactor Pressure Vessel Head Degradation
NRC Bulletin 2002-01: Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
NRC Information Notice 2002-11: Recent Experience with Degradation of Reactor Pressure Vessel Head
NRC Bulletin 2001-01: Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles, August 3, 2001
Information Notice 2001-005: Through-Wall Circumferential Cracking of Reactor Pressure Vessel Head Control Rod Drive Mechanism Penetration Nozzles at Oconee Nuclear Station, Unit 3
Generic Letter 97-001: Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations
Information Notice 96-011: Ingress of Demineralizer Resins Increases Potential for Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations
Information Notice 86-108, Supplement 3: Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion
Information Notice 94-063: Boric Acid Corrosion of Charging Pump Casing Caused by Cladding Cracks
Information Notice 90-010: Primary Water Stress Corrosion Cracking of INCONEL 600
Generic Letter 88-005: Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants
Information Notice 86-108, Supplement 2: Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion
Information Notice 86-108, Supplement 1: Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion
Bulletin 82-002: Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of PWR Plants
Information Notice 82-006: Failure of Steam Generator Primary Side Manway Closure Studs
Information Notice 80-027: Degradation of Reactor Coolant Pump Studs

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