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LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 2.3, Tables 2.3-1 Through 2.3-22
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NUREG-0521, Responds to Request for Summary Data Re Releases of Radioactive Matls from Nuclear Plants.Forwards NUREG-0521, Review of 1968-78 LERs & Overview of History of Regulatory Effluent Limitations
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IR 05000336/1989003
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IR 05000157/1986001
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IR 05000409/1989002
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B16329, Forwards non-proprietary & Proprietary Versions of Nuclear Training Loit/Lout Audit Reviews. Commitments Made within Ltr,Listed.Proprietary Version Withheld
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JAFP-94-0571, Part 21 Rept Re Spare GE Molded Case Circuit Breaker.Breaker Overcurrent Trip Failed to Perform within Specified time- Current Curve.Defective Breaker Returned to GE for Evaluation
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BECO-LTR-92-036, Annual Dose Assessment to General Public from Radioactive Effluents,1991
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LER-1989-011, :on 890602,backup Manual Scram Breaker B Failed to Trip.Caused by Mechanical Binding of Parts Between Undervoltage Trip Unit & Circuit Breaker.Design Change to Remove Breaker Scheduled
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B11502, Radiological Environ Monitoring Program,Annual Environ Operating Rept for 1984
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05000374/LER-1985-035-02, :on 850723,during Special Test,Two Safety Relief Valves Opened.Caused by Excessive Pressure.Future Testing to Be Performed at Lower Reactor Pressure
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LER-1992-015-01, :on 920817,reactor Scram Occurred Following Main Generator Lock Out.Caused by Less than Adequate Generation & Approval of Substation Load Dispatcher Permit. Isolations Reset & Affected Sys Restored
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label: 05000277/LER-1992-015-01, :on 920817,reactor Scram Occurred Following Main Generator Lock Out.Caused by Less than Adequate Generation & Approval of Substation Load Dispatcher Permit. Isolations Reset & Affected Sys Restored
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wiki page sort key: 05000277/LER-1992-015-01, :on 920817,reactor Scram Occurred Following Main Generator Lock Out.Caused by Less than Adequate Generation & Approval of Substation Load Dispatcher Permit. Isolations Reset & Affected Sys Restored

LER-1992-010-01, :on 920714,discovered That EDG Fuel Oil Transfer Lines Not Missile Protected.Caused by Inadequate Initial Design of Plant.Abnormal Procedure 0-AP-41 Revised, Requiring Roving Watch of Subj Transfer Lines
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label: 05000338/LER-1992-010-01, :on 920714,discovered That EDG Fuel Oil Transfer Lines Not Missile Protected.Caused by Inadequate Initial Design of Plant.Abnormal Procedure 0-AP-41 Revised, Requiring Roving Watch of Subj Transfer Lines
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wiki page sort key: 05000338/LER-1992-010-01, :on 920714,discovered That EDG Fuel Oil Transfer Lines Not Missile Protected.Caused by Inadequate Initial Design of Plant.Abnormal Procedure 0-AP-41 Revised, Requiring Roving Watch of Subj Transfer Lines

LER-1992-007-03, :on 921004,discovered That Eight Daily Instrument Surveillance Checks Not Performed Per Ts,Due to Three Pages Inadvertently Excluded During Copying Process. Instrument Checks Performed & Acceptable
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label: 05000278/LER-1992-007-03, :on 921004,discovered That Eight Daily Instrument Surveillance Checks Not Performed Per Ts,Due to Three Pages Inadvertently Excluded During Copying Process. Instrument Checks Performed & Acceptable
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wiki page sort key: 05000278/LER-1992-007-03, :on 921004,discovered That Eight Daily Instrument Surveillance Checks Not Performed Per Ts,Due to Three Pages Inadvertently Excluded During Copying Process. Instrument Checks Performed & Acceptable

05000397/LER-1984-113, :on 841021,reactor Protection Sys (RPS) Actuation Occurred.Cause Not Stated.Reactor Level Restored, RPS Trip Signal Reset & Plant Cooldown Continued
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wiki page sort key: 05000397/LER-1984-113, :on 841021,reactor Protection Sys (RPS) Actuation Occurred.Cause Not Stated.Reactor Level Restored, RPS Trip Signal Reset & Plant Cooldown Continued

LD-92-030, Forwards Response to NRC 910926 Request for Addl Info to Enable NRC to Continue Review of SSAR - Design Certification (CESSAR-DC).Info Covers Damping Values & Groundwater Condition
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wiki page sort key: LD-92-030, Forwards Response to NRC 910926 Request for Addl Info to Enable NRC to Continue Review of SSAR - Design Certification (CESSAR-DC).Info Covers Damping Values & Groundwater Condition

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05000318/LER-1991-006, :on 910615,loss of Control Room Emergency Ventilation Occurred Causing Plant Shutdown.Caused by Lack of Adequate Procedural Guidance.Establishing Task Force to Identify Problems
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http://kanterella.com/Special:URIResolver/05000409/LER-2D1990-2D001-2C_-3Aon_900115-2Cdiscovered_That_Weekly_Battery_Tests_for_Batteries_Supplying_Dc_Buses-2CEmergency_Diesel_Generators_-26_High_Press…
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4. 4-1 & CE-NPSD-906-P & CE-NPSD-906-NP.CE-NPSD-906-P Withheld
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L-85-431, Requests Extension of 10-yr Inservice Insp Interval to 880211 as Allowed in Section XI of ASME Code & Section B of 10CFR50.55a, Codes & Stds. Extension Required Due to Outage for Core Barrel Repair
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BVY 06-047, 2005 Annual Radiological Environmental Operating Report
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AEP-NRC-2024-86, Unit 2 - Decommissioning Funding Plan for Independent Spent Fuel Storage Installation
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LER-1987-049, :on 870819,two Channel Tests Not Performed within 24 H Time Interval.Caused by Util Licensed Operator Error Due to Confusion During Shift Transition.Control Room Operator Surveillance Log Data Sheet Revised
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IR 05000321/1997006
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