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Issue date | Title | Topic | |
---|---|---|---|
ML18039A881 | 28 September 1999 | Proposed Tech Specs Re Increased MSIV Leakage Rate Limits & Exemption from 10CFR50,App J | Squib Seismically rugged Earthquake |
ML18039A824 | 28 July 1999 | Proposed Tech Specs Providing TS for Operation of Oscillation PRM Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys | Abnormal operational transient Scram Discharge Volume Fuel cladding Power change |
ML18039A800 | 3 June 1999 | Proposed Tech Specs,Reducing Allowable Value Used for Reactor Vessel Water Level - Low,Level 3 for Several Instrument Functions | Reactor Vessel Water Level Scram Discharge Volume |
ML18039A699 | 22 February 1999 | Proposed Tech Specs & Bases Pages Incorporating NRC Approved TS Change 354,requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation | Abnormal operational transient Scram Discharge Volume Large early release frequency Exemption Request Earthquake Maintenance Rule Program Fuel cladding Power change Power Uprate |
ML18039A660 | 15 December 1998 | Proposed Tech Specs,Revising pressure-temp Curves to Extend Validity of Curves to 32 EFPY | |
ML18039A504 | 8 September 1998 | Proposed Tech Specs Providing TS for Operation of Oscillation Power Range Monitor Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys | Safe Shutdown Unanalyzed Condition Shutdown Margin Reactor Vessel Water Level Grab sample Anticipated operational occurrence Post Accident Monitoring Hydrostatic B.5.b Abnormal operational transient Scram Discharge Volume Feedwater Controller Failure Fuel cladding Pressure Boundary Leakage Power change Coast down Unidentified leakage Power Uprate |
ML18039A500 | 4 September 1998 | Proposed Tech Specs Re Use of Containment Overpressure for ECCS Pump Net Positive Suction Head Analyses | Earthquake |
ML18039A479 | 14 August 1998 | Proposed Tech Specs Pages Re Amends to Licenses DPR-33, DPR-52 & DPR-68 to Change Ts.Proposed Changes Decrease Frequency of once-per-cycle Instrument Calibrations by Substituting 24 Months for 18 Months | Reactor Vessel Water Level |
ML18039A461 | 31 July 1998 | Proposed Tech Specs B 3.6-2,B 3.6-7 & B 3 3.7-2 for Power Uprate Operation Omitted Pages | Safe Shutdown |
ML18039A448 | 17 July 1998 | Proposed Tech Specs,Adding LCO 3.4.10 & Accompanying TS Bases Provisions from Improved TS-362 Conversion Package as Adapted for Power Uprate Conditions | Fuel cladding |
ML18039A409 | 26 June 1998 | Proposed Tech Specs Section 3.4,allowing Units 2 & 3 to Operate at Uprated Power Level of 3458 Mwt | Fuel cladding |
ML18039A402 | 19 June 1998 | Proposed Tech Specs (TS) Converting from Existing Custom TS to Improved TS | Time of Discovery Shutdown Margin Reactor Vessel Water Level High Radiation Area Ultimate heat sink Grab sample Offsite Dose Calculation Manual Post Accident Monitoring Hydrostatic Squib Scram Discharge Volume Annual Radiological Environmental Operating Report Process Control Program Spiral reload Overtravel Deep Dose Equivalent Pressure Boundary Leakage Offsite Circuit Fire Protection Program Unidentified leakage |
ML18039A392 | 12 June 1998 | Proposed Tech Specs Change 390,decreasing Frequency of once-per-cycle SRs by Substituting 24 Months for 18 Months in Affected TS SRs | Boric Acid Squib Abnormal operational transient Excess Flow Check Valve Battery sizing |
ML20249A566 | 10 June 1998 | Proposed Tech Specs Section 5.0,revising Administrative Controls | High Radiation Area Annual Radiological Environmental Operating Report |
ML20248C515 | 27 May 1998 | Proposed Tech Specs Section 3.8.1,revising AC Sources- Operating | Safe Shutdown Offsite Circuit |
ML18039A318 | 16 April 1998 | Proposed Rev 2 to Tech Specs Section 3.6, Containment Systems, Converting from Current TS to Improved TS | High Radiation Area Stroke time Squib Power Operated Valves |
ML18039A271 | 16 March 1998 | Proposed Tech Specs Re Power Uprate Operation | |
ML18039A267 | 13 March 1998 | Proposed Tech Specs,Converting to Improved Std Ts,Per NUREG- 1433,rev 1, Std TS for GE BWRs (BWR/4). | Shutdown Margin Fuel cladding |
ML18039A264 | 12 March 1998 | Proposed Tech Specs ITS Section 3.8 Re Electrical Power Sys. | Safe Shutdown Anticipated operational occurrence Qualified Offsite Circuit Abnormal operational transient Battery sizing Offsite Circuit |
ML18039A261 | 3 March 1998 | Proposed Tech Spec Changes TS 393 Re Reactor Vessel Pressure Temperature Curves | Unanalyzed Condition Anticipated operational occurrence Hydrostatic |
ML20199E805 | 23 January 1998 | Proposed Tech Specs Section 5.0 Re Administrative Controls | |
ML18039A222 | 30 December 1997 | Proposed Tech Specs Re RHR SW Pumps Required for multi-unit Operation & Cold Shutdown | Safe Shutdown |
ML18039A215 | 23 December 1997 | Proposed Tech Specs Section 3.7 Re Plant Sys | Ultimate heat sink Abnormal operational transient Fuel cladding |
ML18039A218 | 22 December 1997 | Proposed Tech Specs Section 3.8 Re Electrical Power Sys | Safe Shutdown Anticipated operational occurrence Qualified Offsite Circuit Abnormal operational transient Battery sizing Offsite Circuit |
ML18039A210 | 4 December 1997 | Proposed Tech Specs Pages Re TS Change 362,suppl 7 Re ITS Section 3.1, Reactivity Control Sys. | Shutdown Margin Hydrostatic Squib Scram Discharge Volume |
ML18039A207 | 4 December 1997 | Proposed Tech Specs Pages Re Suppl 9 to TS Change 362, Including Rev Pages to Improved TS Section 3.5 | Reactor Vessel Water Level Stroke time |
ML18039A201 | 3 December 1997 | Proposed Tech Specs Section 3.9 Re Refueling Operations & Section 3.10, Special Operations. | Shutdown Margin Hydrostatic Scram Discharge Volume Spiral reload |
ML18039A198 | 3 December 1997 | Improved Tech Specs Pages Re Section 5, Administrative Controls. | High Radiation Area Grab sample Offsite Dose Calculation Manual Anticipated operational occurrence Post Accident Monitoring Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Deep Dose Equivalent Fire Protection Program |
ML20199D547 | 14 November 1997 | Proposed Tech Specs Section 3.0, Limiting Condition for Operation (LCO) Operability & Section 4.0, Design Changes | |
ML20199E136 | 14 November 1997 | Proposed Tech Specs Section 3.4 Re Reactor Coolant Sys | Unanalyzed Condition Grab sample Hydrostatic Abnormal operational transient Fuel cladding Pressure Boundary Leakage |
ML20198Q452 | 5 November 1997 | Proposed Tech Specs,Incorporating Improved TS (ITS) Bases Revs & Changes to Supporting Documentation Resulting from Responding to NRC Questions | Reactor Vessel Water Level Fuel cladding |
ML18038B961 | 1 October 1997 | Proposed Tech Specs,Allowing Bfn,Units 2 & 3,to Operate at Uprated Power Level of 3458 Mwt | Safe Shutdown Boric Acid Shutdown Margin Reactor Vessel Water Level Ultimate heat sink |
ML18038B936 | 15 August 1997 | Proposed Tech Specs,Extending Existing 7-day EDG Allowed Outage Time to Fourteen Days | |
ML18038B906 | 19 June 1997 | Proposed Tech Specs Supporting one-time 14-day Limiting Condition for Operation for Each EDG to Accommodate Pending Vendor Recommended Maint Activities | |
ML20138J378 | 1 May 1997 | Proposed Tech Specs,Revising TS-362 Amend for Section 3.8, Electrical Power Sys Which Addresses NRC Review Comments | Safe Shutdown Anticipated operational occurrence Qualified Offsite Circuit Abnormal operational transient Battery sizing Offsite Circuit |
ML18038B865 | 24 April 1997 | Proposed Tech Specs,Submitting Revised BFN TS Bases Section 3.5.N, References, Reflecting Updated LOCA Analyses for Units 2 & 3 | |
ML20137U169 | 11 April 1997 | Proposed Tech Specs Re Pr Neutron Monitor Upgrade W/ Implementation of Average Pr Monitor & Rod Block Monitor TS (ARTS) Improvements & Max Extended Load Line Limit Analyses | Shutdown Margin Anticipated operational occurrence Post Accident Monitoring Abnormal operational transient Scram Discharge Volume Fuel cladding Power change |
ML18038B834 | 12 March 1997 | Proposed Tech Specs Re Extended EDG Allowed Outage Time | Safe Shutdown Offsite Circuit |
ML20136F785 | 6 March 1997 | Proposed TS Supporting Planned Replacement of Current Power Range Monitoring Portion of Existing Nms W/Ge Digital Nuclear Measurement Analysis & Control Power Range Neutron Monitor Retrofit Design | Shutdown Margin Reactor Vessel Water Level Probabilistic Risk Assessment Annual Radioactive Effluent Release Report Scram Discharge Volume Annual Radiological Environmental Operating Report Fuel cladding |
ML20134G540 | 5 February 1997 | Proposed Tech Specs Revising Bases Section 3.7.A/4.7.A, Primary Containment, to Delete Wording Re Maintaining Drywell to Suppression Chamber Differential Pressure Constant for Duration of Drywell to Suppression Chamber | |
ML20132B740 | 11 December 1996 | Proposed Tech Specs 2.2.A Re Safety/Relief Valve Setpoint Requirements for Reactor Coolant Sys Integrity | Abnormal operational transient |
ML20117P334 | 15 September 1996 | Proposed Tech Specs to Change Unit 3 TS LCO 3.6.F.1 in Order to Perform Repairs & Maint Necessary to Return RCS Recirculation Loop a to Operations | |
ML18038B754 | 6 September 1996 | Proposed Conversion from Current TSs to Improved STS Consistent w/NUREG-1433,rev 1 | Safe Shutdown Boric Acid Shutdown Margin Reactor Vessel Water Level Ultimate heat sink Grab sample Offsite Dose Calculation Manual Stroke time Anticipated operational occurrence Post Accident Monitoring Hydrostatic Probabilistic Risk Assessment Squib Abnormal operational transient Scram Discharge Volume Feedwater Controller Failure Overtravel Earthquake Fuel cladding Pressure Boundary Leakage Power change Coast down |
ML20117G712 | 30 August 1996 | Proposed Tech Specs Re License Condition on Compliance W/Thermal Water Quality Stds | |
ML20113B195 | 21 June 1996 | Proposed Tech Specs,Revising Change in SLMCPR & Bases Description of RHR Suppl Fuel Pool Cooling Mode | |
ML20112G389 | 6 June 1996 | Proposed Tech Specs,Revising Section 6, Administrative Controls, to Be More Closely Aligned W/Requirements of Improved Std TSs | High Radiation Area Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Deep Dose Equivalent Fire Protection Program |
ML20117H523 | 20 May 1996 | Proposed Tech Specs Implementing Guidance of GL 87-09 & NUREG-1433,Rev 1 | Time of Discovery |
ML20108D902 | 3 May 1996 | Proposed Tech Specs,Withdrawing Amend 219,temporary TS 343T, Rv Water Level Instrumentation & Amend 228,temporary TS 347T,250 Volt DC Control Power Supply Sys AOT for Unit 2 | |
ML20107F972 | 14 April 1996 | Proposed Tech Specs,Revising Minimum Required Number of Operable Rv Water Level Trip Sys During Period That RCS Instrument Line Excess Flow Check Valve Surveillance Tests Being Performed | Reactor Vessel Water Level |
ML20096C440 | 10 January 1996 | Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B,Performance Based Testing |