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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20140G448 | 1 May 1997 | Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages | |
| ML20135D801 | 26 November 1996 | Part 21 Rept Re Two Safety Related Valves Supplied by Velan Valve Corp Were Not in Compliance W/Originally Supplied QA Documentation.Returned Valves to Velan in May 1996 & on 961120 Velan Advised That Valves Had Been Misplaced | |
| ML20080G469 | 26 January 1995 | Record of Telcon W/Nrc & Licensees 950126 to Clarify Position Re Dispositioning of Exempt Sources Listed in Section 6.3.3 of Shoreham Termination Survey Final Rept Dtd Oct 1994 | |
| ML20069F000 | 24 January 1994 | Vols 1-4 to Shoreham Decommissioning Project Termination Survey Final Rept | Non-Destructive Examination Offsite Dose Calculation Manual Post Accident Monitoring Process Control Program Chernobyl Biofouling |
| ML20058K384 | 9 December 1993 | Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head | |
| ML20057F226 | 30 September 1993 | Safety Evaluation Supporting Exemption Request from Requirements of 10CFR50.54(q) for License NPF-82 | Exemption Request |
| ML20056C718 | 14 July 1993 | SE Supporting Amend 10 to License NPF-82 | |
| ML20045B355 | 11 June 1993 | LER 93-001-00:on 930429,refueling Jib Crane Moved in Vicinity of Spent Fuel Pool Using vendor-supplied Lifting Eye in Violation of NUREG-0612.Caused by Failure to Identify Crane as Heavy Load.Meetings held.W/930611 Ltr | Safe Shutdown Control of Heavy Loads |
| ML20045C888 | 8 June 1993 | Vols 1 & 2 to Refueling Jib Crane 1T31-CRN-008A Incident Root Cause Analysis. W/One Oversize Encl | |
| ML20128P645 | 28 February 1993 | Snps Decommissioning Project Termination Survey Final Rept for Steam Turbine Sys (N31) | Scaffolding |
| ML20044C118 | 28 February 1993 | Shoreham Nuclear Power Station Updated Decommissioning Plan. | |
| ML20128P743 | 19 February 1993 | Rev 3 to 93X027, Nuclear QA Surveillance Rept | |
| ML20127H230 | 15 January 1993 | Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites | |
| ML20126B042 | 17 December 1992 | Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed | Loctite |
| ML20125C716 | 7 December 1992 | Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl | Stroke time Anchor Darling |
| ML20127P586 | 23 November 1992 | Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl | |
| ML20128B964 | 31 October 1992 | Rev 0 to Shoreham Decommissioning Project Termination Survey Plan | |
| ML20118B439 | 11 September 1992 | Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option | |
| ML20099H578 | 31 July 1992 | Rev 4 to Shoreham Defueled Sar | Safe Shutdown Fitness for Duty High Radiation Area Ultimate heat sink Grab sample Offsite Dose Calculation Manual Fire Barrier Anticipated operational occurrence Met Tower Operating Basis Earthquake Nondestructive Examination Incorporated by reference Tornado Missile Protection Design basis earthquake Process Control Program Feedwater Controller Failure Safeguards Contingency Plan Earthquake Chernobyl Fuel cladding Fire Protection Program |
| ML20114A631 | 28 July 1992 | Shoreham Decommissioning Plan | Non-Destructive Examination Offsite Dose Calculation Manual Coatings Nondestructive Examination Condition Adverse to Quality Process Control Program Earthquake Chernobyl Fire Protection Program Scaffolding |
| ML20101K579 | 25 June 1992 | Long Island Power Authority Shoreham Decommissioning Project,Shoreham Nuclear Power Station,Technical Rept on Water Processing & Water Mgt Activities for Reactor Pressure Vessel & Wet Cutting Station | |
| ML20094L127 | 13 March 1992 | Amend 1 to Part 21 Rept 159 Re Potential Defect in Power Cylinder Liner.Initially Reported on 920115.Caused by Liner/ Block Fit & Localized Matl Microstructure.All Drawings & Specs Revised to Address Matl Design Requirements | |
| ML20082M508 | 26 August 1991 | Rev 3 to Shoreham Defueled Sar | |
| PM-91-125, Monthly Operating Rept for Jul 1991 for Shoreham Nuclear Power Station | 31 July 1991 | Monthly Operating Rept for Jul 1991 for Shoreham Nuclear Power Station | |
| PM-91-112, Monthly Operating Rept for Jun 1991 for Shoreham Nuclear Power Station | 30 June 1991 | Monthly Operating Rept for Jun 1991 for Shoreham Nuclear Power Station | |
| PM-91-075, Monthly Operating Rept for Apr 1991 for Shoreham Nuclear Power Station | 30 April 1991 | Monthly Operating Rept for Apr 1991 for Shoreham Nuclear Power Station | |
| ML20024G717 | 22 April 1991 | LER 91-001-00:on 910324,RB Normal Ventilation Sys (Rbnvs) Outboard Exhaust Valve Closed for No Apparent Reason.Cause Inconclusive.Sys Restored to Normal Lineup & Rbnvs Outboard Valve Will Be Stroked on Routine basis.W/910422 Ltr | |
| SNRC-1806, Revised Pages 2 & 6 to Encl a of 10CFR50.59 Annual Rept for 1990 | 15 April 1991 | Revised Pages 2 & 6 to Encl a of 10CFR50.59 Annual Rept for 1990 | |
| PM-91-058, Monthly Operating Rept for Mar 1991 for Shoreham Nuclear Power Station | 31 March 1991 | Monthly Operating Rept for Mar 1991 for Shoreham Nuclear Power Station | |
| PM-91-037, Monthly Operating Rept for Feb 1991 for Shoreham Nuclear Power Station | 28 February 1991 | Monthly Operating Rept for Feb 1991 for Shoreham Nuclear Power Station | |
| PM-91-016, Monthly Operating Rept for Jan 1991 for Shoreham Nuclear Power Station | 31 January 1991 | Monthly Operating Rept for Jan 1991 for Shoreham Nuclear Power Station | |
| ML20069Q390 | 31 December 1990 | Shoreham Nuclear Power Station Decommissioning Plan. (Filed in Category P) | Offsite Dose Calculation Manual Coatings Nondestructive Examination Condition Adverse to Quality Process Control Program Earthquake Fire Protection Program |
| SNRC-1797, 10CFR 50.59 Annual Rept of Facility Changes,Procedure Changes,Tests & Experiments for Jan-Dec 1990 | 31 December 1990 | 10CFR 50.59 Annual Rept of Facility Changes,Procedure Changes,Tests & Experiments for Jan-Dec 1990 | Safe Shutdown Offsite Dose Calculation Manual |
| SNRC-1794, Shoreham Nuclear Power Station Annual Operating Rept,1990 | 31 December 1990 | Shoreham Nuclear Power Station Annual Operating Rept,1990 | |
| SNRC-1799, Lilco 1990 Annual Rept | 31 December 1990 | Lilco 1990 Annual Rept | |
| ML20028H023 | 28 September 1990 | LER 90-007-00:on 900907,unplanned Actuation of ESF Sys Occurred During I&C Surveillance Test.Caused by Inadequate procedure.SP44.650.16 Revised to Require That Leads Lifted & Individually separated.W/900928 Ltr | |
| ML20056A200 | 31 July 1990 | Safety Evaluation Supporting Amend 6 to License NPF-82 | Health Physics Network Fuel cladding |
| PM-90-097, Monthly Operating Rept for June 1990 for Shoreham Nuclear Power Station | 30 June 1990 | Monthly Operating Rept for June 1990 for Shoreham Nuclear Power Station | |
| ML20055E391 | 25 June 1990 | Safety Evaluation Supporting Amend 5 to License NPF-82 | Offsite Dose Calculation Manual Process Control Program |
| PM-90-083, Monthly Operating Rept for May 1990 for Shoreham Nuclear Power Station | 31 May 1990 | Monthly Operating Rept for May 1990 for Shoreham Nuclear Power Station | |
| 05000322/LER-1987-009 | 16 May 1990 | LER 87-009-01:on 870203,full Reactor Trip Occurred Due to Perturbation in Ref Leg.Caused by Spurious Low Level Reactor Pressure Vessel Water Level Signal.Existing Level & Pressure Transmitters Replaced W/Newer Models | |
| 05000322/LER-1989-005 | 16 May 1990 | LER 89-005-01:on 890321,results of Local Leak Rate Test of Core Spray Suction Valve a Determined That Leakage,When Combined W/All Type B & C Penetration Leakages,Exceeded Tech Spec Limit.Caused by Normal Valve Degradation | Anchor Darling |
| 05000322/LER-1989-003 | 16 May 1990 | LER 89-003-01:on 890310,emergency Diesel Generator (EDG) 102 Manually Shutdown During 18-month Surveillance Test Due to Failure of EDG Output Breaker.Cause Not Determined. Replacement Breaker Installed in Cubicle 102-8 | |
| 05000322/LER-1987-022 | 16 May 1990 | LER 87-022-01:on 870604,HPCI Test Valve to Condensate Storage Tank,Globe Valve & Hpci/Rcic Test Valve to Condensate Storage Tank Failed to Close Against Sys Operating Pressure.Disc of motor-operated Valve 37 Modified | Stroke time |
| 05000322/LER-1987-012 | 16 May 1990 | LER 87-012-01:on 870504,uplanned Actuation of ESF Occurred. Caused by Technician Loosing Footing & Accidently Hitting Outside Cover of Level Switch.Permanent Ladders & Platforms Installed at Head Tank Level Switches | |
| 05000322/LER-1986-039 | 16 May 1990 | LER 86-039-01:on 861006,unplanned Initiation of Reactor Bldg Standby Ventilation Sys Occurred W/All Rods Inserted in Core.Caused by Faulty Design of Retaining Device.Warning Signs Attached to Valve Actuator & Valve Mod Initiated | |
| 05000322/LER-1988-017 | 16 May 1990 | LER 88-017-01:on 881025,discovered That Seismic Monitoring Instrumentation Returned to Svc Prior to Verifying Sys Operability & Special Rept Not Written.Caused by Personnel Error.Surveillance Engineer Reassigned | |
| 05000322/LER-1986-032 | 16 May 1990 | LER 86-032-01:on 860728,RWCU Isolated on High Differential Flow Sensed by Steam Leak Detection Sys While Placing Filter Demineralizers in Operation.Cause Not Determined. Operating Procedures Revised to Monitor RWCU Sys | |
| 05000322/LER-1986-014 | 16 May 1990 | LER 86-014-01:on 860305,full Reactor Trip Occurred Due to Momentary False Low Vessel Level Signal,Causing Hydraulic Pressure Spike in Ref Leg A.Bourton Tube Type Pressure Transmitter Replaced W/Rosemount Model 1153 | Safe Shutdown |
| 05000322/LER-1985-059 | 16 May 1990 | LER 85-059-01:on 851219,half Reactor Trip,Full NSSS Shutoff Sys Isolation & Reactor Bldg Standby Ventilation Sys Initiation Occurred Due to Loss of Power to Reactor Protection Sys Bus B.Assembly Breaker Reset | Half scram Scaffolding |