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List of results

• JPN-91-061, Responds to Generic Ltr 89-04 Re Guidance on Developing Acceptable Inservice Testing (IST) Program.Requests That NRC Review Open Relief Requests by 920101 to Enable Util to Implement Rev 4 to IST During Next Refueling Outage  + (ML20079L382)
• AECM-84-0011, RO 83-114/0:on 831215,control Room Temp Exceeded Tech Spec Limit of 77 Degrees F for Period of More than 8 H.Max Recorded Temp Was 80 Degrees F.Availability or Operability of Equipment within Area Not Affected  + (ML20079L384)
• ML20079L385  + (ML20079L385)
• 05000338/LER-1983-006, Forwards LER 83-006/03L-0  + (ML20079L386)
• ML20079L388  + (ML20079L388)
• ST-HL-AE-4001, Forwards Emergency Response Data Sys Implementation Plan, Per 10CFR50,App E,Section VI.4.a.Implementing Procedures Will Be Modified to Require That Sys Be Activated within 1 H of Declaration of Alert  + (ML20079L389)
• 05000361/LER-1991-015-01, :on 911001,containment Purge Isolation Sys Train a Actuation Occurred While Performing Radiography. Cause Not Stated.Health Physics Procedures Modified & Training Will Be Conducted  + (ML20079L390)
• ML20079L394  + (ML20079L394)
• RBG-14-374, Submits Addl Info in Response to NRC Re Util 811209 Final Response to IE Bulletin 81-03, Flow Blockage of Cooling Water to Safety Sys Components by Corbicula Sp (Asiatic Clam) & Mytilus Sp (Mussel)  + (ML20079L395)
• ML20079L396  + (ML20079L396)
• 05000338/LER-1983-006-03, /03L-0:on 830125,triaxial Peak Accelegraphs on RHR HX & Safety Injection Pipe Found Inoperable from Corrosion Damage on Internal Parts.Caused by Moisture Entering Accelegraphs.Units Replaced  + (ML20079L397)
• 05000389/LER-1983-077-03, /03L-0:on 831221,diesel Generator 2B Failed to Start within 10 & Fuel Oil Day Tank Failed to Automatically Fill Above 30% Level.Cause for Slow Start Not Determined.Tank Holding Relay Module Replaced  + (ML20079L404)
• ML20079L405  + (ML20079L405)
• ML20079L406  + (ML20079L406)
• ML20079L407  + (ML20079L407)
• ML20079L408  + (ML20079L408)
• ML20079L411  + (ML20079L411)
• 05000251/LER-1983-022-03, /03L-0:on 831219,routine Sample of Boric Acid Storage Tank Boron Concentration Revealed Three Tanks Exceeding Tech Spec Limits.Caused by Lack of Communication Between Chemistry & Operations Personnel  + (ML20079L416)
• ML20079L417  + (ML20079L417)
• ML20079L418  + (ML20079L418)
• ML20079L419  + (ML20079L419)
• ML20079L420  + (ML20079L420)
• RBG-14-367, Interim Deficiency Rept DR-92 Re Supplier & Subsupplier ASME III Documentation for Category I Stainless Steel Thermowells.Initially Reported on 830114.Investigation Not Completed.Next Rept Expected by 830418  + (ML20079L421)
• ML20079L424  + (ML20079L424)
• ML20079L426  + (ML20079L426)

• BVY-91-109, Responds to NRC Re Violations/Deviations Noted in Safety Insp Rept 50-271/91-23 on 910903-06.Corrective actions:corrected,computer-generator Manifests,Listing Fe-55 Sent to Lab & New Task Matrix Formed  + (ML20079L427)

• ML20079L428  + (ML20079L428)
• ML20079L429  + (ML20079L429)
• ML20079L431  + (ML20079L431)
• 3F1091-18, Responds to Generic Ltr 91-11, Resolution of Generic Issue 48, Limiting Condition for Operation (LCO) for Class 1E Vital Instrument Buses & 49, Interlocks & LCOs for Class 1E Tie Breakers  + (ML20079L432)
• ML20079L434  + (ML20079L434)
• ML20079L435  + (ML20079L435)
• ML20079L436  + (ML20079L436)
• ML20079L437  + (ML20079L437)
• ML20079L439  + (ML20079L439)
• ML20079L440  + (ML20079L440)
• 05000387/LER-1983-007, Forwards LER 83-007/03L-0  + (ML20079L443)
• W3P83-0519, Forwards Responses to Questions Re Proposed Installation of Insulco/Hemyc Sys as Fire Protective Envelope for Class IE Electrical Cables.Insulco/Hemyc Sys Presentation Data Encl  + (ML20079L448)
• 05000387/LER-1983-007-03, /03L-0:on 830110,during Startup Testing,Average Power Range Monitor Scram & Rod Block Setpoints Not in Tolerance.Caused by Inherent Qualities of Xenon Free Startup Causing Excessive Power Peaking.Setpoints Adjusted  + (ML20079L453)
• ML20079L455  + (ML20079L455)
• 05000259/LER-1983-074-03, /03L-0:on 831228,during Refueling,Degraded Flow Condition Discovered on Radiation Monitor 1-RM-90-250. Caused by Normal Wear & Degradation of Schwitzer Series 325 Sample Pump.Pump Replaced  + (ML20079L456)
• ML20079L457  + (ML20079L457)
• ML20079L458  + (ML20079L458)
• ML20079L459  + (ML20079L459)
• ML20079L466  + (ML20079L466)
• 3F1091-13, Forwards Emergency Response Data Sys Implementation Program Plan,Per 10CFR50,App E,Section VI.4.a & Rev 1 to NUREG-1394.Util Volunteered to Participate in Sys Per Generic Ltr 89-15  + (ML20079L468)
• ML20079L472  + (ML20079L472)
• ML20079L473  + (ML20079L473)
• ML20079L485  + (ML20079L485)
• ML20079L490  + (ML20079L490)
• ML20079L491  + (ML20079L491)