NG-93-3992, Forwards Responses to Anomalies Noted in NRC 920311 TER for DAEC IST Program,Description of IST Program Development, Relief Requests PR-016 & PR-017 & Rev 12 to IST Program, in Response to GL 89-04
NSD-NRC-98-5796, Notifies NRC That Approved Process in WCAP-12488-A Being Used to Account for Design Mods for 17X17 Rfa with Ifm Grid Design as Required by Fcep SER
05000346/LER-1998-006, :on 980624,loss of Offsite Power Was Noted. Caused by Tornado Damage to Switchyard.Tested & Repaired Affected Electrical & Mechanical Equipment Necessary to Restore Two Offsite Power Sources
B17720, Forwards Mnps,Units 1,2 & 3 Decommissioning Funding Status Rept, Per 10CFR50.75(f)(1).Util Is Submitting Rept on Behalf of co-owners of Three Millstone Units Which Vary Depending on Specific Unit in Question
05000333/LER-1998-011, :on 980929,failure to Meet Drywell Continuous Atmosphere Monitoring Sys TS Surveillance Test Requirements Were Noted.Caused by Deficient Tp.Declared Both Channels of CAM Sys Inoperable.With
05000255/LER-1988-002, Forwards Corrected Semiannual Effluent Release & Waste Disposal Rept for Period Jan-June 1988,including LER 88-002 Inadvertently Omitted from Original 880831 Submittal & Supplemental Jul-Dec 1987 Rept
HNP-96-002, Forwards Inservice Inspection Summary, for Shnpp.Rept Covers Inspections Performed During Cycle 6 Operations Including Refueling Outage 6,in First Insp Interval
L-91-316, Forwards Nonproprietary WCAP-12960 & Proprietary WCAP-12959, Structural Evaluation of Turkey Point,Units 3 & 4, Pressurizer Surge Lines,Considering Effects of Thermal Stratification, Per Response to NRC Bulletin 88-011
L-91-010, Forwards Proprietary WCAP Repts,Per 901127 Meeting Re 900913 Request to Amend Tech Specs by Eliminating Resistance Temp Detector Bypass.Repts Withheld (Ref 10CFR2.790)
L-90-417, Application for Amends to Licenses DPR-31 & DPR-41,revising Tech Spec Sections 2.2, Limiting Safety Sys Settings & 3/4.3.2, ESFAS Instrumentation. Nonproprietary WCAP-12746 & Proprietary WCAP-12745 encl.WCAP-12745 Withheld
GO2-95-149, Forwards Performance Enhancement Strategy 1995. Plan Developed by Independent Mgt Team in Response to mid-cycle self-assessment
GO2-92-081, Application for Amend to License NPF-21,revising TS 4.8.2.1, Battery Load Profiles, Deleting Phrase of the Following Profile
GO2-90-075, Application for Amend to License NPF-21,supporting Cycle 6 Reload & Operation of Lead Fuel Assemblies During Feedwater Temp Reduction Anticipated & Responds to NRC Bulletin 90-002 Re Loss of Thermal Margin Caused by Channel Box Bow
GO2-90-016, Application for Amend to License NPF-21,revising Tech Spec Surveillance Requirement 4.8.1.1.2.d.2 to Add New Diesel Fuel Oil Surveillance to Ensure That Diesel Generator Operability Not Impaired by Insoluables in Fuel Oil
GO2-90-032, Application for Amend to License NPF-21,allowing Use of Cycle 6 Reload Fuel in Plant.Changes to Listed Tech Specs Requested.Supporting Reload Analysis Repts Encl.Proprietary GE & ABB Atom Repts Withheld (Ref 10CFR2.790(b)(4))
GO2-92-011, Application for Amend to License NPF-21,changing Jet Pump Surveillance 4.4.1.2.1 to Require Operability Demonstration within 12 H of Exceeding 25% Rated Thermal Power
L-87-007, Documents Implementation of Option of Substituting Accredited Training Program for Initial & Requalification Operator License Training Program,Previously Approved by Nrc,Per Generic Ltr 87-07
L-89-140, Application for Amend to License DPR-67,changing Steam Generator Tube Repair Tech Specs
L-91-096, Application for Amend to License DPR-67,deleting Tech Spec 3/4.2.2, Total Planar Radial Peaking Factor - Ftxy
L-93-127, Application for Amend to License NPF-16,requesting Approval of Improved Methodology, Extended Statistical Combination of Uncertainties (Escu). Proprietary Rept CEN-371(F)-P Encl.Rept Withheld (Ref 10CFR2.790(a)(4))
L-93-110, Application for Amends to Licenses DPR-67 & NPF-16,changing TS Section 6.0, Administrative Controls to Reflect Current FPL Organizational Titles Throughout Section 6.0 & to Modify Facility Review Group Composition
L-94-262, Forwards St Lucie Unit 2 Rept of Changes Made to Facility Under Provisions of 10CFR50.59 for Period 930326-940422. Rept Correlates W/Info Included in Rev 9 of Updated FSAR Submitted Under Separate Cover
DCL-91-313, Forwards Adequacy of Seismic Margins Assuming Increase in Amplitude of Diablo Canyon Long-Term Seismic Program, Horizontal & Vertical Ground Motions as Described in Sser 34
05000206/LER-1990-014, :on 900709,Diesel Generator 2 Automatically Started Due to Loss of Bus Signal.Caused by Inadequate Temporary Tape Insulation of Lifted Lead.Lifted Lead Restored & Training Program Will Be Enhanced
05000206/LER-1990-019, :on 901016,nuclear Overpower Low Trip Setpoint Was Determined to Be Greater than Allowed by Tech Specs Due to Inadequate Review of Design Change Documents
05000206/LER-1989-029, :on 891222,determined That Filter on Refueling Water Storage Tank Recirculation Line Could Fail During Seismic Event.Caused by Engineering Deficiencies Noted in 881003 Submittal.Filter Pump Sys Upgraded
05000206/LER-1991-005-01, :on 910321,chemistry Technician Inadvertently Discarded Weekly Continuous Release Pathway Liquid Composite Samples for Wk of 910311-17.Caused by Personnel Error.Technician Disciplined
05000206/LER-1990-004-01, Advises That Revised Tech Spec 3.1.4 Will Be Delayed Until 900930,per LER 90-004-1
05000206/LER-1989-012, :on 890525,auxiliary Feedwater Sys Train a Actuation Occurred When wide-range Steam Generator Level Signals Decreased Below Actuation Setpoint.Caused by Effects of Internal Circulation Flow
05000206/LER-1989-021, :on 890803,reactor Tripped on Low Flow Due to Instrument Cable Degradation.Caused by Polyethylene Insulation Becoming Brittle Due to Oxidation.Cable W/Loss of Insulation to Ground Replaced
05000206/LER-1989-008, :on 890303,determined That Possibility Exists That Containment Fire Suppression Sys Pneumatic Control Valve CV-92 Could Fail Open Due to Single Spurious Failure of Solenoid Valve.Training Program Initiated
L-88-011, Clarifies Bases for Facility Compliance w/10CFR50,App G Requirements Re Charpy Upper Shelf Energy Concerning Fracture Toughness
L-89-015, Advises That Util Volunteers to Participate in NRC Emergency Response Data Sys (ERDS) at Plant,In Response to Generic Ltr 89-15.Encl Provides Tabulation of Unit 1 ERDS Parameters Which Will Be Provided to NRC by 910101
L-91-011, Confirms That Guidance Provided for Resolution of Generic Issues 48 & 49 Satisfied as Documented in Generic Ltr 91-11
L-88-018, Discusses Specific Line Items Re GL 88-18, Plant Record Storage on Optical Disks
NMP1L0667, Forwards Niagara Mohawk Power Corp Annual Rept 1991, Rochester Gas & Electric Corp Annual Rept 1991, New York State Electric & Gas Corp 1991 Annual Rept, Central Hudson 1991 Annual Rept & Lilco 1991 Annual Rept
L-89-010, Informs That Util GL 89-10 Program Completed