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List of results

• RBG-37-110, Forwards Response to Rev 1 to Generic Ltr 92-01, Reactor Vessel Structural Integrity, Per 10CFR50.60 & 10CFR50.61 & Commitments Made in Response to Generic Ltr 88-11  + (July 2, 1992)
• ELV-03865, Comment Supporting Proposed Rule 10CFR50.63 Re Loss of All Alternating Current Power  + (July 2, 1992)
• U-602001, Responds to Rev 1 to Generic Ltr 92-01 Re Reactor Vessel Structural Integrity.All Reactor Vessel Beltline Matls Determined to Be Capable of Maintaining Charpy Upper Shelf Energy Above 50-ft Pounds  + (July 2, 1992)
• HL-2292, Forwards Response to GL 92-01,Rev 1 Re Reactor Vessel Structural Integrity  + (July 2, 1992)
• HL-2280, Suppls Containing Commitments to Comply W/Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & Surveillance,Per Findings in Insp Repts 50-321/92-04 & 50-366/92-04.Exceptions for in Situ Testing Discussed  + (July 2, 1992)
• PY-CEI-NRR-1500, Forwards Response to Rev 1 to Generic Ltr 92-01, Reactor Vessel Structural Integrity. Util Utilized Assistance of GE to Performed Technical Analysis to Predict Effects of Neutron Irradiation on Reactor Vessel Matls  + (July 2, 1992)
• ML20266F339  + (July 2, 1992)
• 05000352/LER-1992-010, :on 920605,north Stack wide-range Accident Monitor Discovered Inoperable & Unable to Perform Design Function Since 920507.Caused by Equipment Malfunction & Procedure Deficiency.Procedure Revised  + (July 2, 1992)
• 05000395/LER-1992-004, :on 920521,reactor Tripped from 9% Power on low-low SG Water Level in C Sg.Caused by Condenser Steam Dump Valves Not Fully Opening on Demand.Transducers Were Replaced W/Lower Impedance Transducers  + (July 2, 1992)
• 05000445/LER-1992-011, :on 920618,failure of thermo-lag Fire Barrier Endurance Tests Results in Some Raceways Declared Inoperable.Caused by Inadequate Vendor Installation Specs. Fire Watch Routes Adjusted  + (July 2, 1992)
• 05000445/LER-1992-013, :on 920511,loss of Cooling Water Flow to Fuel Pool Heat Exchanger Occurred After Realignment.Caused by Personnel Error.Personnel Retrained & Reevaluated & Heat Exchanger X-02 Has Restricted Use  + (July 2, 1992)
• ML20044B543  + (July 2, 1992)
• ML20101N626  + (July 2, 1992)
• ML20101N614  + (July 2, 1992)
• ML20127C693  + (July 2, 1992)
• IR 05000280/1992007  + (July 2, 1992)
• ML18096A809  + (July 2, 1992)
• ML18036A765  + (July 2, 1992)
• GO2-92-157, Requests Change in Reactor Vessel Capsule Withdrawal Schedule.Since Capsule Missed Some early-in-life Exposure, Placing Capsule in Standby Mode Rather than Being Withdrawn at 24 EFPY Appropriate  + (July 2, 1992)
• IR 05000237/1992018  + (July 2, 1992)
• ML17157B894  + (July 2, 1992)
• ML17177A520  + (July 2, 1992)
• ML17177A518  + (July 2, 1992)
• ML17177A515  + (July 2, 1992)
• ML17177A511  + (July 2, 1992)
• ML17058A987  + (July 2, 1992)
• ML17058A991  + (July 2, 1992)
• ML18010A678  + (July 2, 1992)
• ML18036A764  + (July 2, 1992)
• ML18036A767  + (July 2, 1992)
• ML20045G617  + (July 2, 1992)
• ML20101K034  + (July 2, 1992)

• ML18058A955  + (July 3, 1992)
• ML18153D056  + (July 3, 1992)
• ML20101R169  + (July 3, 1992)
• ML20101P558  + (July 3, 1992)
• ML20101N479  + (July 3, 1992)
• ML20115F614  + (July 3, 1992)
• BECO-92-071, Forwards Annual Rept of Changes to QA Program Description for Jul 1991 to June 1992  + (July 3, 1992)
• ST-HL-AE-4143, Responds to Unresolved Item Noted in Insp Repts 50-498/92-10 & 50-499/92-10.Corrective actions:off-hours Augmentation Drill Conducted on 920617 & Personnel Reported to Facility within 1 H of Notification Except for Offsite Field Team  + (July 3, 1992)
• ST-HL-AE-4133, Revises Commitment in 920311 Response to Emergency Preparedness Exercise Weaknesses Noted in Insp Repts 50-498/90-10 & 50-499/90-10.Use of Digital Dosimeters Will Not Reduce Effectiveness of Dose Monitoring  + (July 3, 1992)
• 05000338/LER-1992-014, :on 920608,noted That EDG Response Time Test Procedures Did Not Include Circuit Between 27W Relay & EDG CO2 Trouble Alarm Due to Personnel Errors.Complex Instrumentation SRs Being Reviewed  + (July 3, 1992)
• 05000302/LER-1992-011, :on 920605,failure to Install Electrical Isolation Device in Interlock Relay Branch Circuit Results in Potential Loss of Control Power to Containment Isolation Valve.Control Power Will Be Uninterrupted  + (July 3, 1992)
• 05000302/LER-1992-010, :on 920604,determined That Inadequate Level of Detail of Initial Plant Design Calculation Causes Operation Outside Design Basis.Control Transformers Replaced W/Larger Control Transformers  + (July 3, 1992)
• 05000440/LER-1992-014, :on 920603,steam Supply Pressure Low Isolation Signal & Associated RCIC Sys Isolation Were Initiated.Caused by Procedure Deficiency.Surveillance Instruction ISI-B21-T1300-1 Revised  + (July 3, 1992)
• ML13329A171  + (July 3, 1992)
• ML13329A173  + (July 3, 1992)

• ML20141M514  + (January 5, 1992)
• ML20141M512  + (July 5, 1992)
• ML17329A623  + (July 6, 1992)
• ML17289A721  + (June 30, 1992)
• ML17289A715  + (July 6, 1992)
• ML18010A672  + (July 6, 1992)
• ML20101S096  + (July 6, 1992)
• ML20101R793  + (July 6, 1992)
• ML20101R787  + (July 6, 1992)
• ML20101R621  + (July 6, 1992)
• ML20101R593  + (July 6, 1992)
• ML20101R526  + (July 6, 1992)
• ML20101R479  + (July 6, 1992)
• ML20101Q479  + (July 6, 1992)
• ML20101Q403  + (July 6, 1992)
• ML20101P487  + (July 6, 1992)
• ML20101P045  + (July 6, 1992)
• ML20101N929  + (July 6, 1992)