RA-17-072, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
L-MT-06-069, Submittal of Revision 2 to the Cycle 23 Core Operating Limits Report
L-MT-03-033, Submittal of Core Operating Limits Report for Cycle 22
BECO-87-092, Application for Amend to License DPR-35,consisting of Proposed Change 87-10,revising Operability Requirements of Control Rod Block Actuation Instrumentation to More Closely Correspond to Logic Design
B17621, Application for Amend to License DPR-21,reflecting Permanently Defueled Condition of Unit 1,Tech Specs Administrative Controls Section as Allowed by Guidance Contained in NRC Administrative Ltr 95-06
05000271/LER-1987-002, :on 870501,primary Containment Isolation Sys Group III & Subsequent Standby Gas Treatment Sys Initiation Occurred.Caused by Technician Exposing Operating Radiation Detector.Detector Location Labeled
05000280/LER-1986-012, :on 860409,flow Path from Boric Acid Tank to Charging Pump Suction Inadvertently Isolated.Caused by Personnel Error in Isolating Boric Acid Filter.Flow Path Reestablished by Unisolating Filter
05000277/LER-1986-017-01, :on 860704,both Channels of Rod Block Monitor Bypassed.Caused by Failed Relay Associated W/Control Rod 58-43.Defective Relay Replaced to Return Rod Block Monitor to Svc
05000271/LER-1985-011, :on 851008,19 & 20,Group III Isolation Occurred.Caused by Spurious Signal Due to Unrelated Electrical Outage Activity.Equipment Bench Tested & Plant Maint Records Reviewed
05000286/LER-1985-008-01, :on 851018,boric Acid Concentrations Outside Tech Spec Limits.Caused by Difficulties Encountered by Plant Operators When Performing Precipitation Checks.Boric Acid Check Added to Plant Operator Training Program
05000280/LER-1976-013-03, /03L:on 760916,normal Boric Acid Makeup to Vol Control Tank Could Not Be Accomplished Due to Plugging of CVCS Line 1 inch-CH-56-152.Caused by Routine Use of Line. Blank Flange Installed to Clear Lines
05000280/LER-1976-003-03, /03L:on 760326,ruptured Diaphragm in Valve 1-CH-85 Caused Exccessive Leakage of Borated Water.Caused by Normal Wear.Power Rampdown Commenced,Valve Repaired & Placed Back in Svc
05000280/LER-1982-105-03, /03L-0:on 821123,amplifier Reading for Heat Tracing Panel 9,circuit 7A,fell Below Acceptance Criteria.On 821126,low Reading Detected for Panel 8.Caused by Excessive Heat.Defective Heat Tracing Replaced & Tested
05000282/LER-1991-004-01, :on 910509,failure of Redundant Heat Trace Circuits Occurred as Result of Electrical Fault.Caused by Operator Stepping on Insulated Section of piping.ET-53R Heat Trace Circuit Repaired
05000281/LER-1983-007-03, /03L-0:on 830217,operators Discovered Heat Tracing Panels 8 & 9 Circuit 2 & 13 Tagged Out & de-energized.Caused by Operator Improperly Performing Tagout Procedure.Circuits Energized & Verified Operable
05000280/LER-1982-007-03, /03L-0:on 820119,PT-27C Revealed Amp Reading for Heat Tracing Panel 9,circuit 20B Below Acceptance Criteria. Caused by Excessive Heat.Defective Heat Tracing Replaced & Tested
05000280/LER-1982-128-03, /03L-0:on 821228,at 100% power,PT-27D Revealed Amp Readings for Heat Tracing Panel 9,circuit 4B Above Test Criteria.Caused by Excessive Heat.Defective Heat Tracing Replaced & Tested.Design Change Initiated
05000280/LER-1982-103-03, /03L-0:on 820927,amp Readings for Heat Tracing Panel 2 Circuit 24D Found Below Acceptance Level.Cause Unknown.Defective Heat Tracing Replaced & Design Change Initiated
05000280/LER-1982-096-03, /03L-0:on 820916,w/unit at 99% power,PT-27C Revealed That Amp Readings for Heat Tracing Panel 9,circuit 19,was Below Acceptance Criteria.Caused by Excessive Heat. Defective Heat Tracing Replaced & Tested
05000280/LER-1982-083-03, /03L-0:on 820831,performance of PT-27E Revealed That Amp Reading for Heat Tracing Panel 9,circuit 2B,was Below Acceptance Criteria.Caused by Excessive Heat.Heat Tracing Replaced & Tested
B14673, Application for Amend to License DPR-21,incorporating Changes to TS Re Scram Discharge Vol & Controlled Block Instrumentation
05000280/LER-1982-052-03, /03L-0:on 820428,amplifier for Heat Tracing Panel B,Circuit 2B,read Below Acceptance Criteria.Caused by Excessive Heat.Defective Heat Tracing Replaced & Tested. Design Change Initiated
05000280/LER-1982-019-03, /03L-0:on 820202,PT-27 Revealed Ampere Readings for Heat Tracing Circuits 24C,25A,panel 2 & Circuit 24D, Panels 1 & 2 (Boron Injection Tank Recirculation Line) Below Acceptance Criteria.Caused by Loss of Heat Tracing
05000277/LER-1990-009-02, :on 900430,discovered That Rod Block Monitor Not Been Proven Operable Prior to Exceeding 30% Power as Required by Tech Specs.Caused by Programmatic Deficiency. General Plant Procedures Revised
05000280/LER-1981-064-03, /03L-0:on 811020,PT-27 Revealed Amp Readings for Heat Tracing Panels 8 & 9,circuit 13A Were Below Acceptance Criteria.Caused by Excessive Heat.Heat Tracing Replaced & Tested
05000281/LER-1982-051-03, /03L-0:on 820816,at 100% Power,Heat Tracing Circuit 23C on Panel 8 Found Below Criteria.Cause of Loss Unknown.Defective Heat Tracing Replaced & Tested.Design Change Implemented
05000293/LER-1990-002, :on 900228,determined That Max Fraction of Limiting Power Density Not Checked Daily During Reactor Power Operation,Per Tech Spec 4.1.B.On 900323,addl Tech Spec Issue Discovered.Tech Specs Changed
05000271/LER-1989-025, :on 891128,primary Containment Isolation Sys Group III & Standby Gas Treatment Sys Initiation Occurred. Caused by Failure of Reactor Bldg Ventilation Radiation Monitor/Sensor Converter.Converter Replaced
05000286/LER-1979-002-03, /03L-0 on 790205:at 100% Power,Increase in Gaseous Activity Was Observed.Caused by Leakage of No 32 Charging Pump Plunger.Plunger & Packing for Union Pump QX-300 Quintuplex Were Replaced & Unit Returned to Svc
05000280/LER-2077-006, No Flow of Boric Acid from the Boric Acid Transfer Pumps to the Charging Pumps
05000280/LER-1978-003, Submit Licensee Event Report No. LER-78-003/03L-0 Re Failed Heat Tracing, Panel 8 Circuit 24
05000280/LER-1988-005-01, :on 880219,heat Tracing Proper Control Setpoints Could Not Be Verified.Caused by Inadequate Surveillance & Maint Procedures.Verification of Correct Setpoints Initiated
05000331/LER-1980-036-03, During Power Ascension Following Shutdown,Rod Block Monitor B Failed.Caused by Improperly Seated Pin Connector at Rod Select Matrix Panel. Protective Panel Installed Over Pins.Pin Connectors Seated
05000247/LER-2003-002, Re Plant in a Condition Prohibited by Technical Specification Due to Unavailability of Boric Acid Storage for More than 48 Hours
05000271/LER-1987-010, :on 870820,primary Containment Isolation Sys Group III Isolation Occurred Due to High Radiation Signal from Refuel Floor Zone Radiation Detector.Caused by Defective Procedure.Isolation Reset
05000280/LER-1976-011-03, /03L:on 760823,diaphragm in Valve 1-CH-125 Failed Causing Leakage of Boric Acid.Caused by Normal Operation. Valve Repaired