RA-17-072, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
BVY 09-014, Submittal of Revised Technical Specification Bases Pages
BVY 08-047, Technical Specification Proposed Change No. 276, Response to Request for Additional Information
BVY 06-068, Cycle 25 Startup Test Report Following Power Ascension and Testing
05000280/LER-1980-028-03, W/Unit at 100% Power, Reduction in Svc Water Pressure to Charging Pump Experienced.Caused by Missing Valve Disk for 2-SW-113.Check Valve Replaced
L-MT-05-013, Additional Technical Specification Changes for the Monticello Nuclear Generating Plant Regarding Application of Alternative Source Term (AST) Methodology to Re-Evaluate the Fuel-Handling Accident
BVY 05-032, Vermont Nuclear Power Station - Response to Request for Additional Information Regarding Intermediate Range Monitor Surveillance Test Frequencies
05000280/LER-2078-009-03, L Re Snubber Body in Contact with Structure; LER 1978-009-03L Re Trip of Boric Acid Transfer Pump; & LER 1978-010-03L Re Failure of Pressurizer Channel
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
NG-92-5179, Request for TS Change RTS-249 to License DPR-49,adding TS 3.0 & 4.0,corresponding Bases & Modifying Existing Specs Consistent W/New Requirements Denoting Applicability of LCOs & Srs,Per STS & GLs 87-09 & 89-14
BVY-96-102, Forwards Revised Pp 232 of Proposed Change 187 Re Core Shutdown Margin
L-PI-06-097, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3 Operability Requirements for Safety Injection (SI) Subsystem
05000259/LER-1989-006-01, :on 890228,loss of Secondary Containment Integrity Occurred When Ventilation Exhaust Radiation Monitor Repaired on 890225 But Not Tested Following Maint. Caused by Personnel Error.Procedures Revised
05000259/LER-1989-006, :on 890228,discovered That Secondary Containment Ventilation Exhaust Radiation Monitor Repaired on 890225 W/O Being Tested Following Maint.Caused by Personnel Error.Plant Procedures Revised
05000281/LER-1986-008, :on 860706,low Head Safety Injection Pump Discharge Isolation Valve to Cold Leg Found Energized in Open Position.Cause Undetermined.Procedural Changes Will Be Implemented
BVY 08-007, Technical Specification Proposed Change No. 276 Revision to TS Sections 3.3/4.3 for Control Rod System
05000281/LER-1986-010-02, :on 860711,pump B Discharge Pressure Dropped to Zero,Causing Inoperability of Both Charging Pumps a & B. Caused by Air Introduced in Sys During Maint on Pump A.Pump Vented.Both Pumps Returned to Svc
05000247/LER-1986-013, :on 860501,discovered That Containment Electrical Penetration H66 Not Qualified to Function During Submergence.Cause Undetermined.Control & Power Cables Rerouted to Penetration H25
05000281/LER-1986-008-03, :on 860706,low Head Safety Injection Pump Discharge Isolation Valve MOV-2890C to Cold Legs Found Energized in Open Position.Human Performance Evaluation Will Be Performed to Determine Cause
05000277/LER-1985-026, :on 851226,fully Withdrawn Control Rod 22-11 Blocked to Accommodate Repair of Leak on Hydraulic Control Unit Accumulator.Caused by Personnel Error.Crd Blocking Sequences Revised
05000277/LER-1985-026-02, :on 851226,nonconformance W/Tech Spec 3.3.A.2.f Re Control Rod Operability Discovered.Control Rod 30-15 Inserted & 22-1 Withdrawn & Blocked to Repair Leak on Hydraulic Control Unit Accumulator
05000333/LER-1996-011-01, :on 961028,both Standby Liquid Control Subsystems Determined Inoperable.Due to Inoperable Pump Discharge Pressure Relief Valves.Slc Sys Pump Discharge Pressure Relief Valve 11SV-39A Was Replaced
05000280/LER-1983-038-03, /03L-0:on 830829,at 100% Power,Svc Water Pumps 1-SW-P-10A & 1-SW-P-10B Failed to Develop Sufficient Discharge Pressure When Redundant Water Supply Header Isolated.Caused by Npsh.Pumps Vented
05000249/LER-1984-018-03, :on 841020,reactor Scram Occurred Due to Low Feedwater Level.Caused by Bad Switch in Master Controller & Broken Valve.New stem-disc Assembly Installed
05000281/LER-1976-012-03, /03L:on 760813,routine Sample of Safety Injection Accumulator C Indicated 1,893 Ppm Boron.Caused by Leaking Check Valves 2-SI-147 & 2-SI-145.During Refueling,Check Valves Will Be Inspected & Repaired
05000280/LER-1976-008-03, /03L:on 760702,safety Injection Accumulator B Indicated 1,928 Ppm Boron.Caused by Leaking Check Valves 1-SI-128 & 1-SI-130.Accumulator Recirculated in Raw Water Storage Tank to Increase Boron Concentration
05000280/LER-1983-049-03, /03L-0:on 831102,performance of Heat Tracing Periodic Test Revealed Ampere Readings for Heat Tracing Circuits 23A,24C,22A & 24D Not within Test Limits.Caused by Excessive Heat.Heat Tracing Replaced
05000247/LER-1983-038-03, /03L-0:on 831011,during Refueling Water Storage Tank Level Surveillance Test,One of Two Level Alarm Set Points Found Above Max Level.Cause by Drift of Foxboro Model 635-BROCHA Level Alarm Bistable.Bistable Reset
05000293/LER-1983-005-01, Util Operated W/O 0.25% Delta K Shutdown Margin Required Per Tech Spec 3.3.A.1. Caused by Inappropriate Cold Critical Eigenvalue Used in GE Calculations
05000247/LER-1983-008-03, /03L-0:on 830328,electric Heat Trace Circuit 51B Found W/Inoperable Primary Circuit.Caused by Primary Heating Element to Be Open Circuit.Element Replaced. Circuit Tested & Returned to Svc
05000247/LER-1983-028-03, /03L-0:on 830716,during Normal Operation,One of Three Required Boron Injection Tank Level Channels Became Inoperable.Caused by Erroneous Level Indication Due to Solidification of Boric Acid on Impulse Line
05000281/LER-1983-019-03, /03L-0:on 830415,MOV-LCV-2115D Failed to Open During Performance of PT18.6.Caused by Motor Leads Not Making Contact Due to Loose Plug in Terminal Strip in Motor Control Ctr.Terminal Strip Properly Seated
05000281/LER-1983-024-03, /03L-0:on 830517,PT-27D Revealed That Ampere Readings for Heat Tracing Panel 8,Circuit 13C Below Acceptance Criteria in PT-27D.Caused by Excessive Heat. Defective Heat Tracing Replaced
05000265/LER-1983-007-01, /01T-0:on 830509,while Reviewing out-of-svc Documentation,Discovered That Control Rod Drives (CRD) 38-07 & 46-55 on Unit 2 & 06-43 on Unit 1 Made Inoperable W/O Verifiying Shutdown Margin or Insertion
05000281/LER-1982-069-03, /03L-0:on 821104,charging Pump Svc Water Pump 2-SW-P-10B Experienced Loss of Suction Pressure.Caused by Insufficient Npsh.Pump Vented to Restore NPSH
05000247/LER-1982-042-03, /03L-0:on 820923,one of Two Level Alarm Setpoints Found Above Max Level Per Tech Specs.Caused by Level Alarm Bistable Setpoint Drift.Setpoint Reset to Required Value. Surveillance Frequency Increased
05000280/LER-1982-076-03, /03L-0:on 820803,performance of PT-27A Revealed That Amp Reading for Heat Tracing Panel 1,circuit 23A Was Below Acceptance Criteria Stipulated in Pt.Caused by Excessive Heat.Defective Heat Tracing Replaced & Tested
05000280/LER-1982-033-03, /03L-0:on 820530,w/unit at 96% Power,Charging Pump Svc Water Pump 2-SW-P-10B Failed to Develop Sufficient Discharge Pressure.Caused by Insufficient Npsh.Svc Water to Chillers Throttled
05000333/LER-1982-031-03, /03L-0:on 820715,during Routine Startup,Control Rod 02-23 Declared Inoperable in Fully Inserted Position. Caused by Directional Control Valve 123 (Insert Valve) Sticking in Open Position Resulting in Continuous Insertion
05000293/LER-1993-023, :on 930914,determined That Immediate or Timely Action Not Taken or Initiated for One two-by-two Control Rod Array.C/As Planned Includes Change in Setting of Pressure Switch That Controls Instrument Air Sys
05000280/LER-1981-063-03, /03L-0:on 811019,charging Pump Svc Water Pump 1-SW-P-10B Found to Have Zero Discharge Pressure Because of Loss of Suction to Pump.Caused by Increased Use of Svc Water by Chillers.Flow to Chillers Throttled
05000259/LER-1980-006-03, /03L-0:on 800122,during Refueling Operations, Control Rod Driveline Accumulator Level Switch LS-1-305-129 on Unit 38-11 Was Found Inoperable.Caused by Broken Reed Switch.Switch Replaced
05000280/LER-2076-012, Re Routine Sample of C Safety Injection Accumulator Indication of 1893 Ppm Boron
05000280/LER-2078-014-03, L for Surry Unit 2 Charging Pump Service Water Pump a Tripped on High Current
05000280/LER-2078-011-03, L for Surry Unit 1 Loss of Service Water Flow Through Charging Pump Intermediate Seal Cooler
05000280/LER-2075-029, For Surry Power Station, Unit 1, While in Cold Shutdown for Maintenance It Was Desired to Shut Valves MOV-1289A & B (Normal Charging Line Stop Valves) from Control Room
05000280/LER-2075-014, Re 11.4% of Boron Concentration by Weight in Boron Injection Tank Sample
05000281/LER-1991-006-02, :on 910719,safety Injection Sys Interlock Rendered Inoperable & Unit Not Placed in Shutdown within Six H Due to Personnel Error.Failed Amplifier Circuit Board & Calibr Circuit Board Replaced
05000280/LER-1992-003, :on 920214,determined That Certain ESF Sys Logic Acutation Relays Not Fully Tested Per Ts.Caused by Inadequate Testing Methodology.Surveillance Procedures for Channel Functional Test Changed
05000280/LER-1989-031, :on 890723,discharge Pressure for Control Room/ Relay Room Air Conditioning Chiller Svc Water Pump Decreased & Chillers Tripped on High Condenser Discharge Pressure.Caused by Air Binding.Pump Vented
05000280/LER-1989-030, :on 890718,charging Svc Water Pumps Became Air Bound After Air Entered Svc Water Sys.Possibly Caused by Air Trapped in Partially Drained Svc Water Supply Line.Pumps Vented to Permit Filling Supply Lines
05000280/LER-1987-033, .On 871124,charging Pump Component Cooling Water Sys (EIIS-CC) Became Inoperable.Caused by Inadequate Hydrostatic Test Procedure.Procedure Enhancement to Include Sys Depressurizing Instructions Planned
05000280/LER-1981-031-03, /03L-0:on 810508,amp Reading for Heat Tracing Panel 11,circuit 1B,found Below Acceptance Criteria.Caused by Mechanical Damage to Tape.Heat Tracing Replaced & Tested. Design Change Initiated
05000280/LER-1981-033-03, /03L-0:on 810518,amp Reading for Heat Tracing Panel 8,circuit 6A,found Below Acceptance Criteria.Caused by Excessive Heat.Tracing Replaced & Tested.Design Change Initiated
05000281/LER-1981-018-03, /03L-0:on 810318,amp Readings for Heat Tracing Panel 10,circuit 4A,were Below Acceptance Criteria Per PT-27.Caused by Excessive Heat.Defective Heat Tracing Replaced & Tested
05000281/LER-1981-010-03, /03L-0:on 810209,svc Water pump,2-SW-P-10B, Developed Low Discharge Pressure.Caused by Eel Lodged in Impeller.Eel Removed & Pump Returned to Svc
05000281/LER-1980-038-03, /03L-0:on 801105,on-svc Boric Acid Storage Tank & Boron Injection Tank Concentration Found Less That 11.5%. Caused by Improper Valve Lineup.Boric Acid Concentration Increased
05000281/LER-1981-002-03, /03L-0:on 810105,PT-27A Revealed Loss of Heat Tracing for Panel 10 Circuits 1A & 1B & Panel 11 Circuit 4A. Caused by Open Heating Elements.Defective Heat Tracing Tape Replaced
05000281/LER-1980-040-03, /03L-0:on 801114,found Charging Pump Svc Water Pump 2-SW-P10A Developed Low Discharge Pressure of 10 Psig. Caused by Matl Entrained in Water & Being Deposited on Pump Impeller.Pump Disassembled,Cleaned & Returned to Svc
05000281/LER-1980-021-03, /03L-0:on 800826,while Attempting to Pressurize Accumulator B Using Normal Nitrogen Supply,Pressure Fell Below Allowable Limits.Caused by Leak & Low Pressure in Nitrogen Fill Header.Added Pressure to Sys & Repaired Leak
05000281/LER-1980-012-03, /03L-0:on 800815,review of Unit 2 Pipe Support Showed That Seismic Support for Charging Pump 2-CH-P-1B Had Not Been Installed.Caused by Administrative Error.Support Installed
05000281/LER-1980-028-03, /03L-0:on 800926,w/unit at 100% Power,Reduction in Svc Water Pressure to Charging Pumps Experienced.Caused by Missing Valve Disk for Check Valve 2-SW-112.Valve Replaced
05000247/LER-1979-003-03, /03L-0 on 790120:during Normal Operation,Signal from One of Two Low Level Alarm Devices for Refueling Water Tank Became Erratic,Making Alarm Inoperable.Caused by Freezing of Sensing Line for Level Instrument Controller
BVY 05-094, Technical Specification Proposed Change No. 266, Revision to Control Rod Operability, Scram Time Testing and Control Rod Accumulators - Response to Request for Additional Information
BVY 05-086, Technical Specifications Proposed Change No. 263 - Supplement No. 34 Extended Power Uprate - Additional Information
05000280/LER-1982-048-03, /03L-0:on 820813,discovered That Uncollected Leakage of 2-CH-P-1C Was in Excess of Tech Spec Limit.Two Pumps Simultaneously Inoperable,Contrary to Tech Specs.Leak Caused by Loose Flange Bolt.Bolt Lubricated
05000281/LER-1983-022-03, /03L-0:on 830430,PT-27 Revealed Amp Readings for Heat Tracing Panel 8,circuits 5A & 22A,below Acceptance Criteria.Caused by Excessive Heat.Defective Heat Tracing Replaced & Tested.Design Change Prepared
05000280/LER-1982-018-03, /03L-0:on 820121,PT-27 Revealed Amp Readings for Heat Tracing Panels 8 & 9,circuit 13A,below Acceptable Criteria.Caused by Excessive Heat.Defective Heat Tracing Replaced & Tested
05000260/LER-1983-010-03, /03L-0:on 830322,CRD 10-39 Failed to Scram While Performing SI 4.3.C.Caused by Valve Stem Separating from Valve Seat in Valve 85-617