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| Issue date | Title | |
|---|---|---|
| ML102940362 | 12 November 2010 | October 2010 10 CFR 2.206 Monthly Status Report: Enclosures |
| Information Notice 1998-13, Post-Refueling Outage Reactor Pressure Vessel Leak Testing Before Core Criticality | 20 April 1998 | Post-Refueling Outage Reactor Pressure Vessel Leak Testing Before Core Criticality |
| NRC Generic Letter 1995-10 | 15 December 1995 | NRC Generic Letter 1995-010: Relocation of Selected Technical Specifications Requirements Related to Instrumentation |
| ML031140549 | 7 November 1991 | Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability |
| IR 05000029/1990016 | 6 November 1990 | Insp Rept 50-029/90-16 on 900821-1001.Violation Noted.Major Areas Inspected:Daytime & Backshifts in Areas of Plant Operations,Radiological Controls,Maint & Surveillance, Emergency Preparedness,Security |
| NRC Generic Letter 1990-06 | 25 June 1990 | NRC Generic Letter 1990-006: Resolution of Generic Issue, Power-Operated Relief Valve and Block Valve Reliability, and Generic Issue 94, Additional Low-Temp. Overpressure Protection for Light-Water Reactors, Pursuant to 10 CFR 50354 (F) |
| PNO-I-89-073, on 890825,when Tagging Removed on 5-inch Diameter Bypass Line,Pressure Boundary Leakage Discovered from Defect in Socket Weld Connection Between Vent & Bypass Lines.Plant Shutdown.Leakage Rate Less than 1 Gpm | 25 August 1989 | PNO-I-89-073:on 890825,when Tagging Removed on 5-inch Diameter Bypass Line,Pressure Boundary Leakage Discovered from Defect in Socket Weld Connection Between Vent & Bypass Lines.Plant Shutdown.Leakage Rate Less than 1 Gpm |
| ML20215B431 | 10 June 1987 | Forwards Info on Leak Tight Integrity of Reactor Coolant Pressure Boundary at Plant in Response to Generic Ltr 87-06. Util Utilizes Continuous Monitoring Techniques & Periodic Surveillance to Ensure Valve Leakage Detected Early |
| ML20135H353 | 19 June 1984 | Package of Reactor Operator & Senior Reactor Operator License Exam Questions & Answer Keys for Several Facilities, Including Yankee Rowe,Point Beach Units 1 & 2,Fort Calhoun Unit 1 & Calvert Cliffs Units 1 & 2 |
| ML20148G782 | 18 July 1977 | Submits Proposed Change 150,Suppl 1 to Tech Specs,Revising Tech Specs to Be Consistent W/Revised Model STS for Fire Protection |