Pages that link to "PNO-II-85-089, on 850911,leak in Excess of Tech Specs Discovered in Reactor Coolant Loop Bypass Valve.Cause Not Stated.Valve Backseated & Leakage Reduced.Evaluation & Repairs Performed"
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The following pages link to PNO-II-85-089, on 850911,leak in Excess of Tech Specs Discovered in Reactor Coolant Loop Bypass Valve.Cause Not Stated.Valve Backseated & Leakage Reduced.Evaluation & Repairs Performed:
Displayed 14 items.
- ML20236F414 (← links)
- ML20236E927 (← links)
- PNO-II-87-049, on 870716,augmented Insp Team Formed After Licensee Calculated Possible Leak Rate of 600 Gpm.Util Will Visually Inspect Steam Generator for More Precise Reading on Occurrence & Reconstructing Circumstances of Event (← links)
- PNO-II-87-070, on 871013,NRC Authorized Startup & Operation Limited to 50% Power for Facility,Down Since 870715 Following Steam Generator Tube Rupture.No Evidence of Steam Generator Tube Leakage Noted (← links)
- PNO-II-87-048, on 870715,cold Shutdown Reached & Util Downgraded from Alert Status to Recovery Mode.Nrc Inspectors Will Remain Onsite to Follow Up on Licensee Actions & Assess Sequence of Events.Pno Updates PNO-II-87-047 (← links)
- PNO-II-87-047, on 870715,unit Experienced Steam Generator Tube Leak.Util Reported Estimated Release of Radioactive Matl to Atmosphere Less than 1.3% of Tech Spec Release Limit.Release Path Isolated (← links)
- PNO-II-87-043, on 870702,util Shutdown Facility for Longer than 48 Hs to Repair Manual Isolation Valve.Util Plans to Bring Plant to Hot Shutdown & Repair Valve.Svc Will Resume in Several Days (← links)
- ML20216K023 (← links)
- ML20216J753 (← links)
- PNO-II-89-015A, on 890225,primary to Secondary Steam Generator Tube Leak at Plant.Caused by Mechanical Failure. Eddy Current & Boroscopic Insps of Affected Tube Will Be Conducted Following Removal of Plug (← links)
- PNO-II-89-015, on 890125,Unit 1 Tripped Due to Ruptured Air Line to Main Feedwater Regulating Valve.Subsequent to Trip, Radiation Monitor Indications & Increased Charging Flow Revealed primary-to-secondary Leak from C Steam Generator (← links)
- PNO-II-79-001C, on 791005,completed Investigation Into Cause of Overpressurization of Vol Control Tank & Release of Radioactive Gases Into Bldg.Caused by High Influx of Water from Primary Sys (← links)
- PNO-II-80-030A, on 800220,util Issued Press Release on Reactor Trip.Westinghouse & Licensee Have Completed Initial Set of Noise Measurement Tests & Will Compare Results W/Normal Operation Testing to Locate Noise (← links)
- PNO-II-80-030, on 800220,reactor Inadvertently Tripped When Input Breaker to nonsafety-related Rod Drive Motor/Generator Set 1-1 Opened.Caused by Custodial Personnel.Investigating Possible Loose Parts in Steam Generator C (← links)