RA-17-072, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
BVY 12-055, Technical Specifications Proposed Change 297, Supplement 1, Response to Request for Additional Information
BVY 11-008, Technical Specifications Proposed Change No. 290 Administrative Changes - Supplement 1
BVY 10-045, Technical Specifications Proposed Change No. 289 Suppression Chamber-Drywell Vacuum Breakers and Differential Pressure
BVY 10-017, Technical Specifications Proposed Change No. 290 Administrative Changes
BVY 09-052, Technical Specifications Proposed Change No. 284 Change to Requirements for Inoperable Containment Isolation Valves
BVY 09-029, Technical Specifications Proposed Change No. 283 Change to Requirements for Performing 10 CFR 50, Appendix J, Type a Test
BVY 09-012, Submittal of Proposed License Amendment for Technical Specifications No. 282, Revision of Drywell Vacuum Breaker Surveillance Requirements
NRC-2011-0040, Sholly Report for Fr Publication on February 22, 2011
L-MT-04-003, License Amendment Request for Technical Specification Table 3.2.3 and Section 3.7/4.7
BVY 03-117, Response to a RAI Regarding Technical Specification Proposed Change No. 262, Alternative Source Term
05000219/LER-1982-056, Forwards LER 82-056/01T-0.Detailed Event Analysis Encl
05000219/LER-1982-047, Forwards LER 82-047/03L-0.Detailed Event Analysis Encl
05000277/LER-1983-006, Forwards LER 83-006/01T-0.Detailed Event Analysis Submitted
B13146, Responds to NRC Questions Re Vacuum Breakers from Torus to Reactor Bldg
B12670, Proposed Tech Specs,Revising Tech Spec 3.7.A.3, to Delete Permission to Perform Open Vessel Reactivity Tests
BECO-87-103, Forwards List of Pressure Isolation Valves Per Generic Ltr 87-06 Re Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves.List Includes Test Methods, Acceptance Criteria & Frequency
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
B16432, Provides NRC Current Position Re Unit 1 Purge/Vent Valves Resilient Seal Matl Replacement Time Interval as Discussed in TMI Action Item II.E.4.2
A04692, Responds to 850225 Request for Addl Info Re Containment Isolation Dependability & Containment Purge & Vent Valves. Schedule for Implementation of Necessary Mods Presented
BVY-97-117, Responds to NRC Re Violations Noted in Insp Rept 50-271/97-05.Corrective Actions:Troubleshooting Activities Conducted & No Significant Primary Containment Air Leaks Located
BVY-98-165, TS Proposed Change 210 to License DPR-28,resolving Emergent Concern Re Potential Operation Outside of LCO Contained in Current TS & Hence,Potential USQ with Respect to Opening of Manual PCIVs During Plant Operation.Change 209,withdrawn
BVY-98-162, TS Proposed Change 209 to License DPR-28,resolving Emergent Concern Re Potential Operation Outside of LCO Contained in Current TS & Hence,Potential USQ with Respect to Opening of Manual PCIVs During Plant Operation
BECO-85-136, Provides Info Re Means to Depressurize During Extended Period Assuming DHR Impaired,Per NUREG-0737,Item II.K.3.28. Long Term post-accident Operability of Automatic Depressurization Sys Pneumatic Supply Necessary
B11512, Application for Amend to License DPR-21,revising Tech Specs 3.7.A.2.a & 3.7.A.6 Re drywell-to-suppression Chamber Differential Pressure & Drywell Oxygen Concentration, Respectively,To Allow for Up to 48 H Nonmaint.Fee Paid
FVY-84-128, Forwards Results of Detailed Engineering Evaluation of Potential Oxygen Addition to Primary Containment Conducted to Satisfy Criteria of Generic Ltr 84-09.Hydrogen Recombiner Capability Not Necessary
NLS8400137, Application to Amend License DPR-46,consisting of Proposed Change 13,revising Tech Specs to Incorporate Mark I Containment Mods,Per NRC 840120 Request.Class III Amend Fee Encl
JPN-91-014, Forwards Response to NRC 900918 Request for Addl Info Re 900530 Application for Amend to License DPR-59,changing Tech Specs to Reflect Installation of New Reg Guide 1.97 post-accident Monitoring Instruments
BECO-90-106, Responds to 900103 Request for Confirmation That Evaluations of Compliance W/Station Blackout Rule Conducted,Per NUMARC-87-00.Util Selects Diesel Generator Target of 0.975 & Station Blackout Coping Duration of 4 H to Implement Rule
BECO-LTR-97-107, Application for Emergency Amend to License DPR-35,changing TS 3.7.A.5 as Pertains to Periodic Surveillance Testing of Check Valve 30-CK-432.Exemption from LCO Footnote Provides Would Expire When Testing Is Performed
NG-93-1842, Forwards Description of Basis for Enforcement Discretion & Temporary Request for Exemption from 10CFR50,App J Leakage Testing Requirements for Primary Containment Airlock
BVY 08-076, Revision of Technical Specification Bases Pages
05000277/LER-1982-027, Forwards LER 82-027/01T-0.Detailed Event Analysis Encl
B12478, Proposed Tech Spec 3.7.A.5.c Re Containment Sys Oxygen Concentration,Replacing Phrase Important to Safety W/ Necessary to Ensure Safe Plant Operation to Eliminate Ambiguities
05000265/LER-1995-001, Informs of Commitments Being Made by Ltr Re Suppl Info Concerning LER 95-001
JAFP-82-0543, Responds to NRC Re Violations Noted in IE Insp Rept 50-333/82-01.Corrective Actions:Valves 250C & BAS-4 Repositioned to Agree W/Lineup List & Procedures Reviewed for Control of Plant Status
05000293/LER-1989-014, :on 890412,inadvertent Overpressurization of RCIC Suction Piping Occurred During Surveillance Testing. Caused by Personnel Error.Personnel Trained Re Procedural Changes
B13304, Application for Amend to License DPR-21,adding Four Valves to Tech Spec Table 3.7.1 & Minimizing Purging Operations Needed to Maintain Required Differential Pressure Between Drywell & Torus
05000293/LER-1989-008, :on 890216,primary Containment Inadvertently Breached W/Opening of Inner & Outer Doors of Personnel Airlock for 5 S.Caused by Slack in Tie Rod Roller Chain Assembly.Security Post Order Issued
05000333/LER-1989-009-01, :on 890518,determined Containment Drywell to Suppression Chamber Differential Pressure & Suppression Chamber Level Out of Limits.Caused by Personnel Error. Personnel Involved Counseled
05000271/LER-1987-007, :on 870812,18 & 23,while Performing Type C Leak Rate Testing,Listed Valves Found to Have Seat Leakage Above Tech Spec Requirements.Util Will Perform Maint on Valves to Determine Cause of Failure
05000282/LER-1987-018, :on 871028,Bus 15 Voltage Restoring Scheme Inoperable.Caused by Relay Specialist Inadvertently Touching Lifted Wire to Stud Connection on Relay.Blown Fuse Replaced. Long-term Actions Under Consideration
05000271/LER-1989-007, :on 890216 17 & 0305 & 07,while Performimg Type C Leak Rate Testing,Several Valves Found to Have Seat Leakage Exceeding 10CFR50,App J Requirements.Cause Undetermined.Valves Will Be Repaired & Tested
05000254/LER-1987-019-04, :on 870912,containment Leakage Determined to Be in Excess of Tech Spec 3.7.A.2.b Limit.Cause Not Determined. Investigation Will Determine Corrective Actions
05000254/LER-1987-016-06, :on 870912,determined That Measured Combined Leakage Rate from All Penetrations & Valves,Excluding MSIV, Exceeded Tech Spec Limits.Cause Not Yet Determined. Investigation Underway
05000293/LER-1989-004, :on 890127,discovered Two Primary Containment Air Operated Valves Inoperable Resulting in Unit Shutdown. Caused by Pressure Drop Rate of Stored Air Supply for Valves.New Tubing Installed
05000265/LER-1986-014, :on 861012,while Performing Refuel Outage Local Leak Rate Testing,Measured Combined Leakage for Penetrations & Valves,Except Msivs,Found to Be in Excess of Tech Spec Limit.Caused by Wear or Design Deficiency
05000271/LER-1998-009, :on 980321,determined That Leakage Rates of Both Inboard & Outboard MSIV in B & C Steam Lines Exceed TS Allowable Leak Rate Limit.Cause Analysis in Progress.Rept Written to Investigate Event
05000277/LER-1986-023-01, :on 861011,improper Indication Observed on Primary Containment Valves Position Display Panel.Caused by Mechanical Interference or Binding in Ball Valve.Valve Replaced
05000298/LER-1986-013, :on 860617,during Operation at 18% Power, Primary Containment Integrity Breached When Maint Team Exited Drywell W/O Inner Airlock Door Fully Seated.Caused by Personnel Error
05000321/LER-1986-027, :on 860612,drywell Vent Valves 1T48-F319 & F320 Failed to Pressurize During Special Purpose Procedure 42SP-061286-OU-1S Re Local Leak Rate Test.Caused by Damaged T-ring.T-ring Replaced
05000254/LER-1986-039-02, :on 861117,discovered That Primary Containment Atmosphere Greater than 4% Due to Lack of Nitrogen.Caused by Nitrogen Supplier Not Delivering Nitrogen in Timely Manner. Discussions Held W/Nitrogen Suppliers
05000237/LER-1986-030-04, :on 861214,MSIV 2-203-2B Leaked in Excess of Tech Spec 3.7.A.2.b Limit.Caused by Packing Leak on 2-203-2B Valve.Valve Repacked & Local Leak Test Successfully Performed
05000271/LER-1986-007, :on 860621,while Performing Type a Containment Leak Rate Test,Leakage in Excess Permitted by Tech Spec Section 4.7.2 Measured.Leak Sources Identified & Repaired. Type a Leak Test Performed Successfully
05000254/LER-1986-002-02, :on 860107,while Performing MSIV Local Leak Rate Tests During Shutdown for Refueling & Maint,Valves AO 1-203-2A,2B & 2C Found W/Excess Leakage.Caused by Equipment Failure.Repairs Performed
05000237/LER-1986-026-02, :on 861129,primary Containment Deinerted More than 24 H Prior to Shutdown.Caused by Personnel Error.Shift Supervisors Notified & Shutdown Procedures Changed Re Deinerting Time Restriction
05000254/LER-1987-019-02, :on 870914,as Found Leakage Exceeded Tech Spec 3.7.A.2.b Limit.Cause Not Determined.Valves & Penetrations Tested as Required by Local Leak Rate Test Program.Several Valves & Penetration Repaired or Replaced
05000265/LER-1987-012-09, :on 870918,suppression Chamber to Drywell Vacuum Breaker Failed to Close After Testing.Caused by Problem W/Air Operator Portion of Vacuum Breaker.Vacuum Breakers Will Be Inspected & Repaired
05000265/LER-1987-004-10, :on 870218,suppression Chamber to Drywell Vacuum Breaker 2-1601-33A Would Not Return to Normal Closed Position After Being Tested.Caused by Either Slightly Dimpled Valve Bushing or Corroded Solenoid
05000282/LER-1988-003-01, :on 880426,during Relay Testing,Two Terminals Inadvertently Shorted,Blowing Panel Power Supplu Fuse & Making Bus 16 Voltage Restoring Scheme Inoperable.Caused by Personnel Error.Isolation Switch Installed
05000254/LER-1978-030-03, /03L-0 on 781026:dual Position Indication Was Received for Supression Chamber to Drywell Vacuum Breaker, Valve 1-1601-33E.Caused by Position Indication Problem
05000298/LER-1997-008, :on 970614,TS 3.7.A.5.d Time Limit Was Exceeded.Caused by Procedural Inadequacy.Revised Operating Procedures 2.2.60
05000298/LER-1997-003, :on 970423,primary Containment Vent & Purge Sys & Simultaneous Opening of Inlet Purge & Outlet Exhaust Lines Was Determined.Caused by Procedural Noncompliance. Procedure 2.2.6.0 Was Revised
05000254/LER-1986-002, :on 860107,during Shutdown,Discovered That Three MSIVs Leaked in Excess of 11.5 Scfh Limit.Cause Undetermined.Leaks Will Be Repaired Before Startup
05000278/LER-1985-028-01, :on 850811,12,0906 & 25,while in Refuel Outage & W/Reactor Vessel Head Removed,Primary Containment Isolation Sys Initiated Various Isolations.Caused by outage- Related Work
05000245/LER-1997-010-01, :on 970214,determined LLRT Pressure Being Used May Be Less than Accident Pressure.Caused by Weakness in Mgt Commitment to App J Program.Llrts Modified
05000254/LER-1992-020, :on 920920,determined That TS 3.7.A.2.a.2 Limit Exceeded While Performing LLRT of Atmospheric Containment,Atmospheric Dilution & SGTR Isolation Valve. Caused by Bonnet Leak.Valve Flushed
05000293/LER-1996-004, :on 960409,low Voltage Power Containment Electrical Penetrations with Degraded Electrical Protection Occurred.Caused by Unawareness of Coordination Requirements. Circuits Breakers Replaced
05000245/LER-1996-027, :on 960328,bolting Materials Used in Certain Containment Boundary Components Did Not Meet Original Design Specifications.Caused by Personnel Error.Containment Bolted Closures Will Be Removed
05000265/LER-1985-006-02, :on 850318,two MSIVs Leaked in Excess of 11.5 Std Cubic Ft Per Hour Tech Spec Limit. Caused by Valve Seating Surface Wear.Valves Repaired by Lapping Main Seats & by Replacing Main Disc & Pilot Seats
05000293/LER-1992-018, :on 921220,reactor Scram & Closing of Main Steam Isolation Valves Due to Trip Settings of Main Steam Radiation Monitors.Procedure 3.M.2-7.6 Revised to Record Alarm & Trip Settings in Scientific Notation
05000293/LER-1996-005, :on 960419,automatic Scram Occurred Due to Turbine Vibration During Planned Power Reduction.Turbine Vibration Trip Setting That Initiates Trip of Turbine Due to High Vibration Changed
05000333/LER-1991-033, :on 911219,under LOCA Conditions,Water May Accumulate in Primary Containment Pressure Suppression Chamber (Torus) Causing Instrument Error.Caused by Water Accumulation.Calculations Performed
05000254/LER-1992-020-02, :on 920921,determined That TS 3.7.A.2.a.2 Limit of 293.75 Scfh Exceeded.Cause of Excessive Leakages Cannot Be Determined Until Repairs Completed & Valves & Components Retested.Supplemental LER Will Be Issued
05000333/LER-1985-004, :on 850212,one of Two Reactor Bldg Pressure Suppression Chamber Vacuum Breaker Valves Made Inoperable & Remained Inoperable in Excess of Tech Specs.Caused by Restriction by Scaffolding
05000254/LER-1989-014, :on 890910,determined That Measured,Combined Leakage Rate from All Penetrations & Valves,Excluding Misvs, Exceeded TS Limits.On 890911,MSIV Leaked in Excess of Ts. Valve Seating Surfaces Machined & Lapped
05000293/LER-1996-001-01, :on 960312,torus-to-reactor Bldg Vacuum Relief Sys Train B Vacuum Breaker Inoperable Due to Pressure Switch.Replaced micor-switch,tested Pressure Switch Satisfactorily & Returned Vacuum to Svc
05000265/LER-1992-002, :on 920103,determined That TS 3.7.A.2.a.2 Limit of 293.75 Scfh Exceeded.Cause Not Determined.Feedwater Checkvalve 2-220-62A Repaired
05000265/LER-1992-003, :on 900205,determined That Measured Leakage Rate of 528.6 Standard Cubic Feet Per Hr Exceeded TS for All Valves.Caused by Excessive Leakage of HPCI Steam Exhaust Check Valve.Valve Replaced
05000254/LER-1984-002, :on 840307,while Performing Refueling Outage Local Leak Rate Testing,Measured Combined Leakage Rate for All Penetrations & Valves Found in Excess of Tech Specs. Valves,Hatches & Penetrations Repaired
05000293/LER-1992-003, :on 920325,RCIC Sys Declared Inoperable.Caused by Motor Operator Disconnected from Valve Yoke.Personnel Provided one-time Torque Checking Requirements
05000271/LER-1992-010, :on 920308,12 & 17,liquid Radwaste Valve, Feedwater Check Valve & CRD Valves Found W/Seat Leakage Above Ts.Caused by Equipment Wear/Age & Mfg Defect.Valves Repaired,Replaced or Successfully Retested
05000333/LER-1984-014, :on 840623,both Inner & Outer Drywell Entry Hatch Doors Open,Violating Primary Containment.Caused by Failure in Mechanical Interlock & Failure of Personnel to Recognize Integrity Violated.Doors Shut
05000249/LER-1984-013-05, :on 840830,reactor Operation Continued While Primary Containment Purge Sys Butterfly Valve 3-1601-63 Out of Svc for Air Leak Repair.Caused by Personnel Error. Outage Cleared & Valve Cycled
05000331/LER-1984-019, :on 840521,0603,05 & 06,unplanned Partial Group V Isolation Experienced.Caused by Random Noise in Circuit.Further Study to Reduce Susceptibility of Sys to Spurious Isolation Pursued
05000293/LER-1995-008, :on 950814,primary Containment Sys Isolation Valve Was Unable to Close Fully on Automatic Signal Due to Wiring Discrepancy.Trained Personnel for Maint on Specific Event
05000333/LER-1992-003, :on 920108,during Cold Shutdown Incorrect Motor Pinion Key Discovered in Core Spray Sys Injection & Primary Containment Isolation Valves.Caused by Vendor Error in Part Number.Correct Key Installed
05000293/LER-1991-024, :on 911030,loss of Preferred & Secondary Offsite Power Occurred Due to Severe Coastal Storm While Shut Down.Caused by Flashover Switchyard Insulator. Westinghouse Type Relay 62/5 Will Be Replaced
05000333/LER-1984-005-01, :on 840225,primary Containment Atmosphere Monitoring Instrumentation Analyzers a & B Out of Svc for 5 H.Caused by Zero Point Calibr & Sample Flow Vacuum Pump Problems.Sys Mods Implemented
05000333/LER-1995-012-01, :on 950526,primary Containment Makeup Nitrogen Flow Monitoring Surveillance Missed Due to Personnel Error. Applicable Surveillance Tp (ST-40D) Change to Provide Alternate Means of Monitoring Subj Flow
05000293/LER-1995-005, :on 950605,drywell-to-torus Portion of Primary Containment Vacuum Relief Sys Actuated.Caused by non- Established drywell-to-torus Atmosphere Differential Pressure.Addl Nitrogen Delivered
05000293/LER-1991-003, :on 910307,HPCI Sys Made Inoperable When Two HPCI Turbine Steam Exhaust Vacuum Breaker Containment Isolation Valves Discovered Closed.Caused by Loss of Fill Oil in Transmitter.Transmitter Replaced
05000254/LER-1984-004-06, :on 840316,five MSIV Found Leaking in Excess of Tech Spec Limits.Cause Undetermined.Repairs Will Be Completed & Leakages Brought within Tech Spec Requirements Prior to Cycle 8 Startup
05000293/LER-1995-004, :on 950324,drywell-to-torus Portion of Primary Containment Vaccuum Relief Sys Actuated While de-inerting Drywell.Caused by Deficiency in Approved Procedure Being Used.Revised Procedure to Correct Deficiency
05000237/LER-1983-072-03, /03L-0:on 831105,during Reactor Bldg to Torus Vacuum Breaker Surveillance Dis 1600-3,valve 1601-20B Failed to Open.Caused by Failed Versa Solenoid Due to Dirt Contamination.Solenoid Replaced
05000254/LER-1983-044-03, /03L-0:on 831026,pressure Switch 2 of PSI-1-1622A Actuated at 0.52 Psid,Exceeding Tech Spec Limit.Caused by Instrument Setpoint Drift.Switch Recalibr
05000271/LER-1991-015, :on 910614,containment Isolation Valve Failed to Closed Due to Erosion/Corrosion & Displacement of screw- in Seat.Valve Repaired by Welding New Seat Into Valve Body
05000254/LER-1983-037-03, /03L-0:on 830923,while Inerting Primary Containment,Containment Oxygen Not Reduced to Tech Spec Requirement.Caused by Sample Response Time & Probable Source of Air in-leakage Through Compressor
05000331/LER-1983-002-03, /03L-0:on 830124,during Normal Operation,Drywell to Torus Low Differential Pressure Alarm Received.Caused by Valve CV-4316 Not Opening Properly Due to Inadequate Calibr. Design Review Initiated
05000280/LER-1983-043-03, LER83-043/03L-0:on 830914,following Reactor Trip,Flow Control Valve (FCV) Failed to Close Upon Receipt of Feedwater Isolation Signal.Caused by Malfunctioning Solenoid Valve & FCV-1488 Restricted by Antirotation Device
05000293/LER-1994-007, :on 941228,primary Containment Pressure Boundary Degraded Due to Uninstalled Instrument Plug.Caused by Personnel Error.Isolation Valves Will Be Installed on Selected Instruments
05000293/LER-1991-004, :on 910319,RCIC Sys Made Inoperable Due to Area Temp Switch Terminal Stripped During Quarterly Functional Test & Calibr.Caused by Repeating Torquing of Screws. Terminal Replaced W/Spare
05000260/LER-1983-027-03, /03L-0:on 830520,differential Pressure Switch for Pressure Suppression chamber-reactor Bldg Vacuum Breakers Found Operating Above Tech Spec Limits.Caused by Switch Drift.Switch 2-PDIS-64-20 Recalibr
05000260/LER-1982-038-03, /03L-0:on 821124,while Performing ST 4.7.A-3 (Pressure Suppression Chamber Rx Bldg Vacuum Breakers), Pressure Switches PDIS-64-20 & 21 Had Setpoint Above Tech Spec Limit.Caused by Setpoint Drift.Switches Recalibr
05000265/LER-1991-002-01, :on 910119,HPCI Steam Exhaust Check Valve Exceeded Tech Spec Leakage Rate.Caused by Degradation of Nordel Elastomer Valve Seat.Valve Replaced W/New Valve Containing Design Improvements
05000219/LER-1982-056-01, /01T-0:on 821120,output Breaker for A2 24-volt Dc Battery Charger Tripped.Caused by Setpoint Drift of Overvoltage Relay.Breaker Checked & Closed & Relay Setpoint Adjusted
05000277/LER-1990-032, :on 901106,potential Loss of Primary Containment Occurred
05000247/LER-1982-036-03, /03L-0:on 820825,temporary Change Procedure Authorized to Permit Simultaneous Operation Under Load of Two Diesel Generators During Surveillance Test,Potentially Reducing Degree of Redundancy.Test Procedure PTM-21 Changed
05000277/LER-1990-028, :on 900801,discovered Missed Surveillance on Drywell Suppression Chamber Vacuum Breaker
05000293/LER-1990-013, :on 900902,unplanned Manual Reactor Scram Initiated W/Reactor Power at 60%.Fuse Blew in Feedwater Control Circuit Power Supply Causing Feedwater Regulating Valves to Lockup.Trip Linkage Repaired
05000271/LER-1990-012, :on 900903,App J,Type B & C Failure Occurred Due to Excessive Leakage of Seat.Seat Replaced W/Nordel Seat
05000321/LER-1982-064-03, /03L-0:on 820718,reactor Water Cleanup Sys Primary Containment Outboard Isolation Valve Opened While Sys Inoperable.Caused by Personnel Failure to Clear Outstanding Limiting Condition for Operation Prior to Opening Valve
05000321/LER-1982-063-03, /03L-0:on 820715,inboard Reactor Water Cleanup Primary Containment Isolation Valve Found Open in Presence of Isolation Signal.Caused by Loose Electrical Connection. Loose Connection Tightened
05000331/LER-1982-047-01, /01T-0:on 820729,during Testing,Pressure Differential Switches Which Control Reactor Bldg to Suppression Chamber Vacuum Breakers CV-4304 & CV-4305 Tripped Out of Spec.Caused by Instrument Drift
05000282/LER-1978-023-03, /03L-0 on 781130:during Pwr Oper & Relay Test at Refueling,Safeguards Bus 16 Inadvertently Was Locked Out of Svc for About 2 Minutes,Caused by Appl of Elec Jumper W/O Proper Review & Approval
05000277/LER-1978-020-01, /01T-0 on 781019:unit 3 Containment Oxygen Concentration Had Increased to 0.1% Above 4 Percent Limit of Tech Spec 3.7.A.5.Caused by Open Air back-up Valves in Inoperable Instru Nitrogen Compressor
05000298/LER-1993-033, :on 931011,primary Containment Declared Inoperable & Plant Placed in Lco,Per TS 3.7.A.2,loss of Containment Integrity.Caused by Design Deficiency.Design Mods & Licensing Basis Revs Evaluated
05000293/LER-1993-024, :on 930930,determined MO-2301-5 Had Inadequate Thrust to Perform Designed Closing Function.Caused by Running Efficiency Used in Valve Thrust Calculation. Modified Motor Pinion Gearing
05000293/LER-1993-022, :on 930910,simultaneous Loss of Preferred Offsite Power & Automatic Scram Resulting from Load Rejection Occurred.Caused by Load Rejection.Switchyard Walked Down for Evidence of Damage
05000333/LER-1982-006-03, /03L-0:on 820306,during Normal Startup,Pressure Suppression Pool Water Level Was Found 0.4 Inches Below Tech Spec Limit.Caused by Personnel Error.Water Level Corrected.Tech Spec Changes Considered
HL-3359, Forwards Application for Amends to Licenses DPR-57 & NPF-5, Revising TS to Allow One or More Suppression Chamber - Drywell Vacuum Breakers to Open During Surveillance Testing
05000293/LER-1990-007, :on 900507,discovered That Drywell to Suppression Chamber Vacuum Breaker Surveillance Not Performed Prior to Startup in 1988.Caused by Misunderstanding of Requirements
JPN-93-046, Proposed Tech Specs 3.7.A,changing Torus Vent Submergence Levels & Insp Intervals
05000277/LER-1982-001-03, /03L-0:on 820123,during Startup,Local Leak Rate Test of Drywell Airlock Revealed Excess Leakage.Caused by Damaged Garlock Door Gaskets.Gaskets Replaced & Leak Rate Tested
05000331/LER-1981-048-03, /03L-0:on 811223,pressure Differential Switch Which Controls Reactor Bldg to Suppression Chamber Vacuum Breaker Cv 4305 Tripped at Out of Tech Spec Value.Caused by Instrument Drift.Switch Recalibr & Functionally Tested
05000286/LER-1981-009-03, /03L-0:on 811110,battery Charger 31 Tripped.Cause Not specified.Delta-P Air Flow Sensing Switch Replaced
05000331/LER-1981-038-03, /03L-0:on 811030,following Reactor Startup,Drywell Oxygen Concentration Not Reduced to Less than 4% within 24-h of Mode Switch Being Placed in Run.Caused by Inoperable Auxiliary Boiler Feed Pumps
05000293/LER-1993-004, :on 930313,automatic Scram Occurred Resulting from Load Rejection During Severe Coastal Storm While at 100% Power.Caused by Environ Effects of Storm.Trip Settings of Main Input Circuit Breakers Increased
B14396, Proposed TS 3.7.A.2 Re Drywell to Suppression Chamber Differential Pressure
05000254/LER-1981-014-03, /03L-0:on 810723,during Suppression Chamber to Reactor Bldg Vacuum Breakers Test,Valve AO-1-1601-20 Failed to Operate.Caused by Defective Solenoid Valve SO-1-1601-50B. Solenoid Replaced
05000245/LER-1981-017-03, /03L-0:on 810620,oxygen Level in Torus Exceeded Tech Specs.Caused by Primary Containment Not Being Inerted within Required Time Period Due to Inadequate Nitrogen Supply.Inerting W/Nitrogen Brought Concentration Below 5%
05000306/LER-1982-024-03, /03L-0:on 821123,diesel Generator D1 Inoperable for Approx 4 Minutes After Lockout of Engine Shutdown Circuit Occurred.Probably Caused by Sticky Action of Speed Switch.Further Exam of Circuitry Will Be Performed
05000259/LER-1982-059-03, /03L-0:on 820818,during Calibr of Differential Pressure Switch That Initiates Pressure Suppression Chamber to Reactor Bldg Vacuum Breakers,Switch 1-PDIS-64-21 Operated Above Tech Specs.Caused by Calibr Drift.Switch Recalibr
05000237/LER-1983-055-01, /01T-0:on 830719,one 1/8 by 1/16-inch Hole Found on Bellows Seal on Torus to Drywell Vacuum Breaker Line Containing Breakers 2-1601-32A & B.Cavity Filled to Original Thickness & Surface Buffed
05000265/LER-1990-003-02, :on 900205,determined That Leakage Rate for HPCI Sys Steam Exhaust Check Valve Exceeded Tech Spec Limits.Caused by Excessive Leakage.Check Valve Replaced W/ Mission Check Valve W/Carbon Steel Springs
05000278/LER-1981-014, Forwards LER 81-014/01T-0.Detailed Event Analysis Submitted
05000321/LER-1981-087-03, /03L-0:on 810902,during Removal of Radioactive Matl from Fuel Pool,Containment Atmosphere Dilution Sys Analyzers Failed & Drywell to Torus Delta P Dropped Below Spec.Caused by High Radiation Levels
05000265/LER-1981-015-03, /03L-0:on 810823,while Performing Suppression Chamber to Drywell Vacuum Breaker Monthly Exercise,Valve 2-1601-32C Failed to Indicate Fully Closed.Caused by Misalignment of Position Indication Limit Switches
05000321/LER-1981-080-03, /03L-0:on 810724,both Primary Containment dihydrogen-dioxide Analyzers Found to Be Reading Lower than Actual Concentration of Dioxide.Caused by Component Drift. Hays Analyzers Recalibr
PNO-III-81-071, on 810812,w/reactors at Full Power,Both Diesel Generators Inadvertently Out of Svc for Approx 11 Minutes.Caused by Inadequate Test Procedure & Inadequate Operator Training.Licensee Will Take Corrective Action
05000249/LER-1986-026-03, :on 860911,drywell Oxygen Content Exceeded 4% for Greater than 24 H W/Mode Switch in Run.Caused by Personnel Error.Operating Procedures DOP-1600-5 & DOP 1600-6 Revised & Guidance Under Development
05000333/LER-1981-044-03, /03L-0:on 810601,w/oxygen Analyzer B Out of Svc, Drywell Oxygen Analyzer a Found Indicating Downscale.Caused by Instrument Drift.Calibr Restored Instrument to Svc
05000265/LER-1981-006-03, /03L-0:on 810312,differential Pressure Between Drywell & Suppression Chamber Was Lost.Caused by Isolation of Differential Pressure Sys Due to Short in Electrical Circuit Resulting in Blown Fuse.Fuse Replaced
05000293/LER-1989-037, :on 891130,discovered That Traversing in-core Probe Ball Valve,Mfg by Consolidated Controls,Inc,Closed,In Violation of Tech Specs.Caused by Damage to Valve Stem.Ball Valve & Actuator Replaced
05000331/LER-1981-020-01, /01T-0:on 810527,primary Containment Integrity Breached When Inner & Outer Airlock Doors Were Open Simultaneously While H/P Technician Exited Drywell.Cause Unknown
NG-93-5124, Revises 911211 Response to NRC Position on Operability of safety-related Dual Function Valves & Withdraws Commitment Made in .Basis for Withdrawal of 911211 Commitment to Adopt NRC Position on Operability of Subj Valves Encl
05000282/LER-1980-036-03, /03L:on 801105,battery Charger 12 Failed to Provide Normal Output.Caused by Firing Card B Not Providing Pulses to Fire B Phase Scr.Card Replaced
05000333/LER-1981-032-03, /03L-0:on 810409,torus Water Level Decreased Below Tech Spec Limit While Containment Inerting Was in Progress. Caused by Personnel Error.Water Added to Torus
05000265/LER-1980-029-03, /03L-0:on 801027,during Surveillance Procedure, Pressure Suppression Chamber & Reactor Bldg Vacuum Breaker Actuation Calibr & Functional Test Found to Actuate at 0.52 Psid.Caused by Instrument Setpoint Drift.Switch Recalibr
05000254/LER-1980-017-03, /03L-0:on 800716,alarm in Control Room Indicated Vacuum Breaker Valve A0-1601-20B Opened.Valve Position Indicating Lights Inoperable.Caused by Coil Burnup in Air Actuator Solenoid.Valve Closed & Defective Coil Replaced
05000321/LER-1981-009-03, /03L-0:on 810206,nitrogen Storage Tank Inventory Went Below 2000 Gallon Tech Spec Requirement.Caused by Supplier Delaying Shipment.Shipment Received.Supplier Instructed Not to Delay Shipments
05000306/LER-1980-030-03, /03L-0:on 801008,diesel Generator D2 Tripped on High Crankcase Pressure When Eductor Hose Failed.Caused by Burst Eductor Hose.Hose Replaced on Both Diesel Engines
B13329, Provides Util Interpretation of Important to Safety in Tech Spec 3.7.A.6.c.Phrase Encompasses More than Just safety-related Set of Equipment
05000293/LER-1997-007, :on 970401,safeguard Buses Were de-energized Due to Severe Storm.Replacement of Microprocessor Control Units Installed in Voltage Regulating Transformers
05000293/LER-1989-031, :on 891024,closing Times for Two in-series Primary Containment Isolation Valves Exceeded Acceptance Criteria During Shutdown Testing.Cause Undetermined.Closing Time Retested W/Satisfactory Results
05000265/LER-1987-012-01, :on 870918,while Performing Qos 1600-1, Vacuum Breaker 2-1601-33E Remained Open After Testing.Caused by Binding in Test Cylinder Portion of Vacuum Breaker. Nuclear Work Requests Completed
05000254/LER-1989-014-02, :on 890910,determined That Combined Leakage Rate from All Penetrations & Valves Exceeded Tech Spec Limit.Root Cause Unknown.No Corrective Action Taken. Supplemental Rept Will Be Issued
05000333/LER-1980-049-03, /03L-0:on 800507,during Plant Shutdown & Cooldown for Refueling,Torus Water Level Exceeded Tech Spec Limit. Caused by Release of Drywell to Torus Differential Pressure. Addition of Water to Torus Restored Level within Limit
05000254/LER-1979-040, Supplemental LER 79-040/03L-1:on 791213,during Instrument Check,Variations in Suppression Pool Level Noted Between Reading on Control Room Panel 901-3 & Local Sight Glass, Exceeding Tech Specs.Caused by Crud on Sensing Lines
05000254/LER-1979-040-03, /03L-0:on 791213,during Routine Instrument Checks, Variations Between Control Room Panel & Local Sight Glass Readings Caused Suppression Pool Level to Exceed Tech Spec Limit.Caused by Partially Blocked Instrument Sensing Lin
05000286/LER-1979-001-03, /03L-0 on 790211:high Dew Point & Air Leakage on Breaker 2-6 Noted.To Preclude Breaker Damage,Breaker 2-6 Was Opened.Caused by Apparent Gasket Leak in Westinghouse C-A Breaker.Feeder & Breaker Repaired
05000254/LER-1979-019-03, /03L-0 on 790524:vacuum Breaker 1-1601-32D Failed to Give Closed Indication.Caused by Binding on Valve Stem Not Allowing Disk to Shut.Defective Bushing & End Packing on Valve Stem Replaced
05000254/LER-1979-033-03, /03L-0:on 791030,suppression Pool Level Discovered Below Tech Spec Limits.Caused by Suppression Chamber Narrow Range Level Instrumentation Responding Slowly to Change in Suppression Pool Level.More Water Added to Suppression
05000265/LER-1979-015-01, /01T-0 on 790724:pressure Switches PS2-1622A & PS2-1622B Were Found to Actuate Less Conservatively than Tech Specs Required.Caused by Instrument Setpoint Drift. Instruments Recalibr
05000282/LER-1979-032-03, /03L-0:on 791221,during Surveillance Test, Diesel Generator 2 Tripped on High Crankcase Pressure. Apparently Caused by Cooling Water Leaking Into Lube Oil Sys & Accumulating During Shutdown Periods
05000271/LER-1979-030-03, /03L-0:on 791110,during Steady State Operation, Increasing Trend in Torus Water Level Observed.Caused by Leaking Bypass Valve for Torus Level Transmitters.Water Indication Restored Per Tech Specs
05000271/LER-1979-021-03, /03L-0:on 790816,transmitters LT-16-19-38A/B Underwent zero-shift & Common Ref Leg Was Not Completely Filled.Caused by Loss of Water in Common Ref Leg of Transmitters Compounded by Apparent zero-shift
05000254/LER-1979-024-03, /03L-0:on 790724,pressure Suppression Chamber Reactor Bldg Vacuum Breaker Pressure Switch Was Found to Actuate Below Limiting Condition for Operation Level.Caused by Instrument Setpoint Drift.Switch Recalibr
05000281/LER-1980-022-03, /03L-0:on 800826,w/unit Operating at Steady State, Channel III Flow Computer,For Steam Generator Steam Flow Fc 2474,failed.Caused by Loose Printed Circuit Board & Cold Solder Joint on Filter Capacitor.Board & Capacitor Repai
05000260/LER-1991-013, :on 910605,Tech Spec Violation Occurred Due to Loss of Primary Containment.Caused by Personnel Error. Specialized Training for Plant Personnel & Procedure Enhancement Initiated
05000296/LER-1979-022-03, /03L-0:on 791208,following Return to Svc After refueling,drywell-to-suppression Chamber Differential Pressure Could Not Be Maintained Per Tech Spec.Caused by Leak at Hatch Door Due to Loosened Bolts
05000237/LER-1975-051, For Dresden Unit 2 Regarding Report of Unit-2 High Torus Water Level Exceeding the Technical Specifications Limit
05000237/LER-1978-032, /03L-0 for Dresden, Unit 2 Re During Steady State Operation, Torus to Drywell Vacuum Breaker 2-1601-33E & F Were Found Inoperable During Routine Operability Surveillance
05000336/LER-1979-011-03, /03L-0 on 790514:one Electrical Penetration & Several Boundary Valves Had Leakage.Caused by Inadevertent Omission of pre-repair Leak Rate Measurement for Some Valves.Test Procedures to Be Revised
05000293/LER-2015-004-01, Regarding 480V Bus B6 Auto Transfer Function Degraded
05000293/LER-2014-001, Regarding Condition Prohibited by Technical Specifications
05000293/LER-2013-006, And LER 13-006-00 for Pilgrim Regarding Primary Containment Declared Inoperable During HPCI Testing & HPCI Controller Failure to Achieve Rated Flow While in Auto Mode
L-PI-12-007, Response to Requests for Additional Information for License Amendment Request to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8, Cooling Water System & 3.8.3, Diesel Fuel Oil
05000263/LER-1980-022-03, /03L-0:on 800529,primary Containment Oxygen Concentration Exceeded 5% by Weight Tech Spec Limit.Caused by Open Svc Air Isolation Valve to Drywell.Procedures Have Been Revised to Assure Proper Valve Positioning
05000293/LER-2011-004, For Pilgrim Nuclear Power Station, Regarding Technical Specification Required Shutdown - Drywell to Torus Dp
BVY 05-098, Technical Specification Proposed Change No. 263 - Supplement No. 38 Extended Power Uprate - Containment Overpressure Credit
BVY 04-106, Technical Specification Proposed Change No. 263 - Supplement No. 18 Extended Power Uprate - ECCS Pump Net Positive Suction Head Margin
05000293/LER-1999-003-01, Re Local Leak Rate Test Results Exceeding Allowable Technical Specification Leakage Rates
B13297, Application for Amend to License DPR-21,revising Tech Specs, Per TMI Items II.F.1.3 Re Containment high-range Radiation Monitors & II.F.1.4 Re Containment Pressure Monitors & Generic Ltr 83-36
BVY 03-102, Technical Specification Proposed Change No. 262 - Supplement No. 3, Alternative Source Term - Modified Exemption Request
BVY 07-063, Technical Specifications Proposed Change No. 275 Primary Containment Oxygen Concentration and Drywell-to-Suppression Chamber Differential Pressure Limits
B12097, Submits Addl Info on Isap Topic 1.11, Post-Accident Hydrogen Monitor, Per .Hydrogen/Oxygen Monitor & Info on Applicability of Rev 4 to BWR Owners Group Emergency Procedure Guidelines Discussed
BECO-85-063, Submits Addl Info Re Status of Containment Purging & Venting,In Response to NRC 840203 & 0411 Requests.Reduction in Risk Purported in NUREG-0737,Item II.E.4.2(7) Not Clearly Demonstrated
L-MT-03-067, Response to Request for Additional Information Related to Revised Long-Term Containment Response and Net-Positive Suction Head Analyses
05000306/LER-1980-029-03, /03L-0:on 801004,inverter 23 Failed,Leaving Panel 213 de-energized.Caused by Failure of Sola Constant Voltage Transformer.Panel Transferred & Transformer Replaced
BVY 05-023, Licensee Post Exam Comments & NRC Resolution (Folder 1)
BECO-89-178, Forwards Response to Generic Ltr 89-21, Request for Info Re Status of Implementation of USI Requirements
A05743, Advises That Automatic Purge/Vent Valve Closure on High Radiation Signal,Per NUREG-0737,Item II.E.4.2,unjustified Based on Low Probability of RCS Leak When Purge Valves Open, in Response to SER Open Item
05000277/LER-1986-020-01, :on 860817,failure to Maintain Cold Shutdown Conditions & Exceeding Torus Vol Limit Discovered.Caused by Poor Planning of Proposed Operation by Station Supervision. GP-12 Revised
05000249/LER-1985-007-05, :on 850302,during Normal Operation,Two Normally Closed Torus Water Sample Valves Discovered Open W/Water Draining to Sump.Caused by Personnel Error.Valves Locked. Procedures Revised
05000265/LER-1985-006-07, :on 850318,during Local Leak Rate Testing,Two MSIVs Leaked in Excess of Tech Specs.Cause Not Yet Determined.No Corrective Action Taken.Rept Detailing Cause Will Be Submitted Following Repair of Valves
05000260/LER-1991-013-01, :on 910605,loss of Primary Containment Integrity Occurred When Both Drywell Personnel Airlock Doors Opened Due to Personnel Error.Operating & Maint Instructions Revised
05000265/LER-1986-013, :on 861011,leakage of MSIV AO 2-203-2D in Excess of 11.5 Std Cubic Ft Per Hour Discovered.Caused by Normal Operational Wear.Valve Body Reseated.Pilot Seats Lapped.Stem & Piston Ring Replaced
05000265/LER-1986-015-08, :on 861013,leakage from Containment Exceeded 75% of La Required by Tech Spec 3.7.A.2.b.Caused by Reduced Resiliency of Silicon Rubber Mfg by J-Bar Silicon Corp. Silicon Rubber Replaced
05000254/LER-1983-043-03, /03L-0:on 831024,while Performing Suppression Chamber to Drywell Vacuum Breaker Monthly Exercise,Vacuum Breaker 1-1601-32C Showed Dual Indication While Closing. Caused by Limit Switch Out of Adjustment
05000277/LER-1994-005-02, :on 940722,actual Torus Water Level Less than That Indicated on Narrow Range Instrumentation.Initial Ref Marking Used to Support Calibr Activities Not Correct
05000265/LER-1982-020-03, /03L-0:on 821013,drywell to Suppression Pool Differential Pressure Was 0 Psid & Suppression Pool Level Fell Below Tech Spec Limits During Startup.Caused by Personnel Preoccupation W/Startup.Event to Be Discussed