NRC-89-0226, Forwards Control Room Emergency Filtration Sys Dose Calculation Based on Test Results,Per 891025 Meeting W/Nrc
IA-87-407, Portion of Ofc of Enforcement Civil Penalties Log for Period of 860205-870630
NRC-99-0044, Forwards Rev 5 to ITS to Provide Responses to RAI Re ITS Section 3.6 (Except ITS Section 3.6.1.3) Contained in & Update in ITS Submittal to Reflect Responses
B14284, Forwards Addl Bases & Final Justification for Containment Piping Penetrations Judged to Deviate from App A,Gdc 54-57 & Seismic Criteria of GDC 2,per SEP Topic VI-4, Containment Isolation Sys
FVY-84-139, Forwards Info Supporting 790130 Application to Amend License DPR-28,consisting of Proposed Change 77 to Tech Specs to Allow Exemption from Inservice Insp Program Code (ASME Section Xi).Revised Inservice Insp Program Encl.Fee Paid
L-MT-23-030, Subsequent License Renewal Application Supplement 3
05000277/LER-1987-015-01, :on 870816,primary Containment Isolation Sys Group II Inboard & Outboard Isolation Occurred.Caused by Inadequate Tree Trimming in Transmission Corridor.Startup Source Restored & Tree Removed
05000328/LER-1997-001, :on 970117,missed Surveillance on Auxiliary Contacts of Reactor Trip Breakers Discovered.Caused by Adequate PMT for Reactor Trip Breaker Was Not Performed. Multi-disciplinary Team Formed to Perform Investigation
05000370/LER-1999-004-03, :on 990715,RT During Ssps Testing Was Noted. Caused by Switch Lever Arm Being mis-aligned During Insp or Refurbished Breaker.Made Procedure Enhancements
NOC-AE-000241, Application for Amends to Licenses NPF-76 & NPF-80,proposing Rev to TS 4.4.10 for Alternate ISI of RCP Flywheels.Se,Nshc Determination & TS Page 3/4 4-39,included
05000328/LER-1988-006-01, :on 880207,main Steam Isolation Occurred & Reactor Trip Signal Generated by ESF Actuation Sys.Caused by Improper Compliance W/Procedures & Nuance Between Operating Procedures.Procedure Changed & Recategorized
B11449, Forwards Response to 840802 SER Open Items Re Seismic & Dynamic Qualification Program
05000336/LER-1992-012-01, :on 920706,inadvertent ESAS Actuation Occurred Resulting in Partial Loss of Normal Power & Undervoltage Actuation of Facility Z1.Caused by Deenergizing ESAS Sensor Cabinet.Power Restored to Vital 4,160-volt Bus
05000482/LER-1990-027, :on 910730,discovered That STS ML-001 Had Not Been Performed within Required Time Frame During Refueling Iv.Caused by Lack of Administrative Controls.Data Base Review Conducted
LIC-95-0018, Forwards OPPD Annual Accounting for Period of Jan-Dec 1994, as Required by FCS Decommissioning Funding Plan Trust Agreement
LIC-94-0159, Requests Relief from Vibration Limits for Quarterly Min Recirculation ISI Surveillance Tests of LPSI & Containment Spray Pumps
2CAN019101, Special Rept:On 901219,fire Pumps Inoperable During Performance of Surveillance Test.Method of Performing Surveillance Procedure Will Be Revised by 910301
05000287/LER-1981-014-03, /03L-0:on 811125,channel B flux-imbalance Flow Bistable Found to Trip Outside Tech Spec Limit.Caused by non-linear Gain on Reactor Protection Sys Channel B Scaled delta-flux Amplifier.Amplifier Replaced
A01208, Responds to Suppl 3 of IE Bulletin 79-01B, Environ Qualification of Safety-Related Electrical Equipment. Forwards Revised Index,Replacement Pages for Master Listing of Electrical Components & Other Matl
L-93-230, Forwards Response to GL 89-10,Suppl 5, Inaccuracy of MOV Diagnostic Equipment. Revised Errors Associated W/Torque Switch Repeatability,As Specified in Limitorque Maint Update 92-02,incorporated in Plant MOV Diagnostic Test Procedure
GO2-93-294, Forwards Addl Info Re Issuance of Amend 119 to License NPF-21 Re TS 3/4.3.2. Isolation Actuation Instrumentation Response Time Testing
05000397/LER-1991-034, :on 911123,residual Heat Removal Sys Differential Pressure Indicating Switch Found Isolated.Cause Indeterminate.Surveillance completed.RHR-DPIS-12B Restored to Svc
NL-09-119, Proposed License Amendment Regarding Diesel Generator Air Start Receiver Pressure, Indian Point Units 2 & 3
BW050064, Eleventh Refueling Outage Steam Generator Inservice Inspection Summary Report
GO2-82-362, Forwards Study Results Re Comparison of Structural Response to Symmetric & Asymmetric Chugging & Seismic Loads.Results Show Similarity of Responses Between Load Cases
W3P87-2060, Forwards Changes to QA Program (FSAR Section 17.2) Re Significant Transition at Facility from Const to Operations Phase Which Included Major Reorganization of Nuclear Operations Dept.Fee Paid
A06401, Forwards Responses to Questions on Pumps & Valves Inservice Testing Program,Per 870602 & 03 Meetings
05000336/LER-1987-001, :on 861222,intermittent Fire Alarms Received from Heat Detectors Above Reactor Coolant Pump 5.Caused by Heat Detector Failure.Faulty Detector Will Be Replaced.W/