Pages that link to "PNO-II-86-002, on 851229,shutdown Initiated Due to RCS Leakage Exceeding Tech Spec Limits.Pressure Vessel Head Will Be Removed for Repair of Reactor Pressure Vessel Head Seals.Unit Will Be Out of Svc for Addl 16 Days"
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The following pages link to PNO-II-86-002, on 851229,shutdown Initiated Due to RCS Leakage Exceeding Tech Spec Limits.Pressure Vessel Head Will Be Removed for Repair of Reactor Pressure Vessel Head Seals.Unit Will Be Out of Svc for Addl 16 Days:
Displayed 15 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)
- ML20217A117 (← 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)