|
---|
Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML18039A8871999-09-30030 September 1999 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, to Update TS License Conditions.Ts Change TS-381,consists of Administrative Revs That Delete License Conditions That Have Become Outdated,No Longer Applicable or Are Redundant ML18039A8781999-09-28028 September 1999 TS Change 399 to Licenses DPR-52 & DPR-68,increasing Allowable Leakage Rate Criteria for MSIVs & Requesting Exemption to Portions of 10CFR50,App J.Rev 0 to Rept 2100918-R-002 Encl ML18039A8221999-07-28028 July 1999 TS Change 398 to License DPR-58,providing TS for Operation of Oscillation PRM Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A7981999-06-0303 June 1999 Application for Amends to Licenses DPR-52 & DPR-68,reducing Allowable Value Used for Reactor Vessel Water Level - Low, Level 3 for Several Instrument Functions ML20196A9491998-11-19019 November 1998 Suppl 1 to 970602 Application for Amends to Licenses DPR-33, DPR-52 & DPR-68,allowing Continued Plant Operation with Single Recirculation Loop in Svc ML18039A5011998-09-0808 September 1998 TS Change 354 to License DPR-52,providing TS for Operation of Oscillation Power Range Monitor Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A4981998-09-0404 September 1998 Application for Amends to Licenses DPR-52 & DPR-68,amending Use of Containment Overpressure for ECCS Pump Net Positive Suction Head Analyses,Per NRC Bulletin 96-003 ML18039A4771998-08-14014 August 1998 Supplemental Application for Amends to Licenses DPR-33, DPR-52 & DPR-68 to Change TSs for Instrument Calibration Surveillance Frequencies.Proposed Changes Decrease Frequency of once-per-cycle by Substituting 24 Months for 18 Months ML18039A4071998-06-26026 June 1998 Application for Amends to Licenses DPR-52 & DPR-68,revising TS Section 3.4, Rcs. ML18039A3901998-06-12012 June 1998 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Decreasing Frequency of once-per-cycle SRs by Substituting 24 Months for 18 Months in Affected TS SRs ML20249A5641998-06-10010 June 1998 Supplemental Application for Amend to Licenses DPR-33,DPR-52 & DPR-68,revising ITS Section 5.0 Re Administrative Controls ML18039A2691998-03-16016 March 1998 Suppl 1 to TS Change 384 to Licenses DPR-52 & DPR-68, Allowing Units 2 & 3 to Operate at Uprated Power of 3458 Mwt Representing Power Level Increase of Five Percent ML18039A2591998-03-0303 March 1998 Application for Amends to Licenses DPR-52 & DPR-68,revising TS 393 Re pressure-temperature Curve Update ML18039A2201997-12-30030 December 1997 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Consisting of TS Change 395,removing non-conservatism Associated W/Lco 3.5.C, RHR Svc Water & Eecw. ML18038B9581997-10-0101 October 1997 Application for Amends to Licenses DPR-52 & DPR-68, Consisting of TS Change 384,allowing Bfn,Units 2 & 3,to Operate at Uprated Power Level of 3458 Mwt.Proprietary Rept Re Power Uprate Safety Analysis,Also Encl.Rept Withheld ML18038B9041997-06-19019 June 1997 Application for Amends to Licenses DPR-52 & DPR-68, Requesting Temporary TS Change to Provide one-time 14-day Limiting Condition for Operation for Each EDG to Accommodate Pending Vendor Recommended Maint Activities ML20137U1081997-04-11011 April 1997 Suppl 1,TS Change 353S1 to Licenses DPR-33,DPR-52 & DPR-68, Revising Existing Custom for Units to Include Changes Associated W/Implementation of Pr Neutron Monitor Upgrade & to Incorporate Changes ML18038B8321997-03-12012 March 1997 Application for Amends to Licenses DPR-52 & DPR-68, Consisting of TS Change 376,extending EDG Allowed Outage Time ML20132B7301996-12-11011 December 1996 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Consisting of TS-386,increasing TS 2.2.A Re Safety/Relief Valve Setpoint Requirements for Reactor Coolant Sys Integrity.Rev 3 to J11-02761SRLR Rept Encl ML20117P3311996-09-15015 September 1996 Application for Amend to License DPR-68 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 ML20117G7081996-08-30030 August 1996 Application for Amend to Licenses DPR-33,DPR-52 & DPR-68, Eliminating License Condition 2.C.(3) on Thermal Water Quality Stds ML20113B1851996-06-21021 June 1996 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising SLMCPR & Bases Description of RHR Removal Suppl Fuel Pool Cooling Mode ML20112G3811996-06-0606 June 1996 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising Section 6, Administrative Controls, to Be More Closely Aligned W/Requirements of Improved Std TSs ML20117H5131996-05-20020 May 1996 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Consisting of TS Change 373,revising TS to Implement Guidance of GL 87-09 & NUREG-1433,Rev 1 ML20108D8911996-05-0303 May 1996 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, 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 Only ML20107F9591996-04-14014 April 1996 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Respectively,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 ML20096C4341996-01-10010 January 1996 Suppl to TS Change Request 364 to Licenses DPR-33,DPR-52 & DPR-68,revising TS to Implement 10CFR50,App J,Option B, Performance Based Testing.Suppl Incorporates Word Door to Note in SR 4.7.A.2.g.Corrected TS Encl ML20095E4051995-12-0808 December 1995 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Consisting of Proposed TS Change TS-364,revising TS Section 4.7.A to Implement Recent Rule Change to 10CFR50,App J to Incorporate Option B for Containment Leak Rate Testing ML20093B0451995-10-0202 October 1995 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising TS-371 Bases Sections 3.5.A & 3.5.B, Core Spray Sys & Residual Heat Removal Sys & 3.5.C, RHR Svc Water & Emergency Equipment Cooling Water Sys ML20092F3191995-09-13013 September 1995 Application for Amend to License DPR-68 Changing TS Table 4.2.B & 4.2.C to Delete Requirements to Perform Daily Instrument Checks for Steam Supply Low Pressure & Turbine Exhaust Diaphragm High Pressure ML20086G6951995-07-10010 July 1995 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68 Revising TS Base Section 3.7.A/4.7.A to Clarify Method of Determining Operability of Drywell to Suppression Chamber Vacuum Breakers ML20085K4731995-06-16016 June 1995 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising TS to Allow TIP Sys to Be Considered Operable W/ Less than Five TIP Machines Operable ML20084T9631995-06-0202 June 1995 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Clarifying Definition of Operability for RHRSW Sys Standby Coolant Supply Capability & Revising Instrument Numbers in Tables 3.2.F & 4.2.F for Instruments Upgraded ML20085D5891995-06-0202 June 1995 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising TS to Be Consistent W/Planned Replacement of Current Power Range Monitoring Portion of Existing Nms,Per GL 94-02.Proprietary GE Rept NEDC-32433P Encl.Rept Withheld ML20083M0351995-05-11011 May 1995 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Reflecting Interim Addition of Scram Pilot Air Header Low Pressure Trip Function on Unit 3 ML20080J2771995-02-23023 February 1995 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising TS-348 Re Residual Heat Removal Sys Interlock Installation ML20077K2171995-01-0404 January 1995 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Proposing Changes to Ts,By Revising Applicability & SR for Irm,Aprm High Flux (15% Scram) & APRM Inoperative Trip Functions ML20077A5081994-11-15015 November 1994 Application for Amends to Licenses DPR-33,DPR-52,DPR-68, DPR-77 & DPR-79,deleting Audit Frequencies & Requirement to Perform Radiological Emergency Plan & Security Plan Audits from TSs ML20149G2391994-10-0707 October 1994 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising Surveillance Requirements for Plant Operation W/ Inoperable Diesel Generator ML18037A8741994-05-11011 May 1994 Application for Amend to License DPR-52,consisting of TS Change TS-347T to Temporarily Extend AOT of TS 3.9.B.8 While TVA Replaces Batteries & Associated Hardware That Supply 250 Volt Dc Control Power to Units 1 & 2 Shutdown Boards ML20065H2201994-04-0404 April 1994 Suppl 1 to TS-322 to Licenses DPR-33,DPR-52 & DPR-68, Eliminating Reactor Scram & Main Steam Line Isolation Functions Associated W/Msl Radiation Monitors ML20065E3651994-03-31031 March 1994 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Extending Load Line Limit & Revising Rod Block Monitor Operability Requirements & Deleting Specific Value for Rated Reactor Loop Recirculation Flow Rate ML20065F2511994-03-31031 March 1994 Request for Amend TS-319 to Licenses DPR-33 & DPR-68, Lowering Trip Level Settings for HPCI & RCIC Steam Line Space Isolation Instrument Channels ML20065E3841994-03-30030 March 1994 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising TSs Re Analog Transmitter/Trip Sys,Level 1 Reactor Water Level Setpoint & Various Calibr Frequencies ML20065D4931994-03-29029 March 1994 Request for Amend TS-340 to License DPR-68,revising TS to Add Operability & SRs to Support Unit 3 480-volt Load Shed Logic Sys Being Added by Design Change ML20059C4981993-12-23023 December 1993 TS Change 346 to Licenses DPR-33,DPR-52 & DPR-68, Incorporating Recommendations for Snubber Visual Insp Intervals Contained in GL 90-09, Alternative Requirements for Snubber Visual Insp Intervals & Corrective Actions ML20057G2511993-10-12012 October 1993 Request for Amend TS-320 to Licenses DPR-33,DPR-52 & DPR-68, Deleting Existing RWCU Sys High Temp Detection Switches from Tables 3.2.A & 4.2.A & Adding New RWCU Sys Temp Loops for Unit 3 & Clarifying Tables 3.2.A & 3.2.B for Units 1,2 & 3 ML20057E8621993-10-0707 October 1993 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Consisting of TS 313,adding High Range Primary Containment RMs & Recorders to Tables 3.2.F,4.2.F & TS Section 6.9.2 in Response to NUREG-0737,Item II.F.1.3 ML18037A4761993-09-30030 September 1993 Request for Amend TS-312 to Licenses DPR-33,DPR-52 & DPR-68, Removing SDV Air Header Pressure Trip Switches Scram Function from Unit 2 TS & Clarifying Description of SDV High Water Level Bypass in RPS for Units 1,2 & 3 ML18037A4801993-09-30030 September 1993 Requests for Amend TS-336 to Licenses DPR-33,DPR-52 & DPR-68,revising & Clarifying Spent Fuel Pool Water Level, Temp & Sampling & Analysis Srs,In Ref to Insp Repts 50-259/93-07,50-260/93-07 & 50-296/93-07 1999-09-30
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML18039A8871999-09-30030 September 1999 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, to Update TS License Conditions.Ts Change TS-381,consists of Administrative Revs That Delete License Conditions That Have Become Outdated,No Longer Applicable or Are Redundant ML18039A8781999-09-28028 September 1999 TS Change 399 to Licenses DPR-52 & DPR-68,increasing Allowable Leakage Rate Criteria for MSIVs & Requesting Exemption to Portions of 10CFR50,App J.Rev 0 to Rept 2100918-R-002 Encl ML18039A8221999-07-28028 July 1999 TS Change 398 to License DPR-58,providing TS for Operation of Oscillation PRM Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A7981999-06-0303 June 1999 Application for Amends to Licenses DPR-52 & DPR-68,reducing Allowable Value Used for Reactor Vessel Water Level - Low, Level 3 for Several Instrument Functions ML20196A9491998-11-19019 November 1998 Suppl 1 to 970602 Application for Amends to Licenses DPR-33, DPR-52 & DPR-68,allowing Continued Plant Operation with Single Recirculation Loop in Svc ML18039A5011998-09-0808 September 1998 TS Change 354 to License DPR-52,providing TS for Operation of Oscillation Power Range Monitor Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A4981998-09-0404 September 1998 Application for Amends to Licenses DPR-52 & DPR-68,amending Use of Containment Overpressure for ECCS Pump Net Positive Suction Head Analyses,Per NRC Bulletin 96-003 ML18039A4771998-08-14014 August 1998 Supplemental Application for Amends to Licenses DPR-33, DPR-52 & DPR-68 to Change TSs for Instrument Calibration Surveillance Frequencies.Proposed Changes Decrease Frequency of once-per-cycle by Substituting 24 Months for 18 Months ML18039A4071998-06-26026 June 1998 Application for Amends to Licenses DPR-52 & DPR-68,revising TS Section 3.4, Rcs. ML18039A3901998-06-12012 June 1998 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Decreasing Frequency of once-per-cycle SRs by Substituting 24 Months for 18 Months in Affected TS SRs ML20249A5641998-06-10010 June 1998 Supplemental Application for Amend to Licenses DPR-33,DPR-52 & DPR-68,revising ITS Section 5.0 Re Administrative Controls ML18039A2691998-03-16016 March 1998 Suppl 1 to TS Change 384 to Licenses DPR-52 & DPR-68, Allowing Units 2 & 3 to Operate at Uprated Power of 3458 Mwt Representing Power Level Increase of Five Percent ML18039A2591998-03-0303 March 1998 Application for Amends to Licenses DPR-52 & DPR-68,revising TS 393 Re pressure-temperature Curve Update ML18039A2201997-12-30030 December 1997 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Consisting of TS Change 395,removing non-conservatism Associated W/Lco 3.5.C, RHR Svc Water & Eecw. ML18038B9581997-10-0101 October 1997 Application for Amends to Licenses DPR-52 & DPR-68, Consisting of TS Change 384,allowing Bfn,Units 2 & 3,to Operate at Uprated Power Level of 3458 Mwt.Proprietary Rept Re Power Uprate Safety Analysis,Also Encl.Rept Withheld ML20217C2111997-09-11011 September 1997 Amend 249 to License DPR-52,providing Changes Required to Implement Improved Power Range Neutron Monitor Sys, Designated by Licensee as Group a Changes ML18038B9041997-06-19019 June 1997 Application for Amends to Licenses DPR-52 & DPR-68, Requesting Temporary TS Change to Provide one-time 14-day Limiting Condition for Operation for Each EDG to Accommodate Pending Vendor Recommended Maint Activities ML20137U1081997-04-11011 April 1997 Suppl 1,TS Change 353S1 to Licenses DPR-33,DPR-52 & DPR-68, Revising Existing Custom for Units to Include Changes Associated W/Implementation of Pr Neutron Monitor Upgrade & to Incorporate Changes ML18038B8321997-03-12012 March 1997 Application for Amends to Licenses DPR-52 & DPR-68, Consisting of TS Change 376,extending EDG Allowed Outage Time ML20132B7301996-12-11011 December 1996 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Consisting of TS-386,increasing TS 2.2.A Re Safety/Relief Valve Setpoint Requirements for Reactor Coolant Sys Integrity.Rev 3 to J11-02761SRLR Rept Encl ML20117P3311996-09-15015 September 1996 Application for Amend to License DPR-68 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 ML20117G7081996-08-30030 August 1996 Application for Amend to Licenses DPR-33,DPR-52 & DPR-68, Eliminating License Condition 2.C.(3) on Thermal Water Quality Stds ML20113B1851996-06-21021 June 1996 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising SLMCPR & Bases Description of RHR Removal Suppl Fuel Pool Cooling Mode ML20112G3811996-06-0606 June 1996 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising Section 6, Administrative Controls, to Be More Closely Aligned W/Requirements of Improved Std TSs ML20117H5131996-05-20020 May 1996 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Consisting of TS Change 373,revising TS to Implement Guidance of GL 87-09 & NUREG-1433,Rev 1 ML20108D8911996-05-0303 May 1996 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, 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 Only ML20107F9591996-04-14014 April 1996 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Respectively,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 ML20096C4341996-01-10010 January 1996 Suppl to TS Change Request 364 to Licenses DPR-33,DPR-52 & DPR-68,revising TS to Implement 10CFR50,App J,Option B, Performance Based Testing.Suppl Incorporates Word Door to Note in SR 4.7.A.2.g.Corrected TS Encl ML20095E4051995-12-0808 December 1995 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Consisting of Proposed TS Change TS-364,revising TS Section 4.7.A to Implement Recent Rule Change to 10CFR50,App J to Incorporate Option B for Containment Leak Rate Testing ML20093B0451995-10-0202 October 1995 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising TS-371 Bases Sections 3.5.A & 3.5.B, Core Spray Sys & Residual Heat Removal Sys & 3.5.C, RHR Svc Water & Emergency Equipment Cooling Water Sys ML20092F3191995-09-13013 September 1995 Application for Amend to License DPR-68 Changing TS Table 4.2.B & 4.2.C to Delete Requirements to Perform Daily Instrument Checks for Steam Supply Low Pressure & Turbine Exhaust Diaphragm High Pressure ML20086G6951995-07-10010 July 1995 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68 Revising TS Base Section 3.7.A/4.7.A to Clarify Method of Determining Operability of Drywell to Suppression Chamber Vacuum Breakers ML20085K4731995-06-16016 June 1995 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising TS to Allow TIP Sys to Be Considered Operable W/ Less than Five TIP Machines Operable ML20084T9631995-06-0202 June 1995 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Clarifying Definition of Operability for RHRSW Sys Standby Coolant Supply Capability & Revising Instrument Numbers in Tables 3.2.F & 4.2.F for Instruments Upgraded ML20085D5891995-06-0202 June 1995 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising TS to Be Consistent W/Planned Replacement of Current Power Range Monitoring Portion of Existing Nms,Per GL 94-02.Proprietary GE Rept NEDC-32433P Encl.Rept Withheld ML20083M0351995-05-11011 May 1995 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Reflecting Interim Addition of Scram Pilot Air Header Low Pressure Trip Function on Unit 3 ML20080J2771995-02-23023 February 1995 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising TS-348 Re Residual Heat Removal Sys Interlock Installation ML20077K2171995-01-0404 January 1995 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Proposing Changes to Ts,By Revising Applicability & SR for Irm,Aprm High Flux (15% Scram) & APRM Inoperative Trip Functions ML20077A5081994-11-15015 November 1994 Application for Amends to Licenses DPR-33,DPR-52,DPR-68, DPR-77 & DPR-79,deleting Audit Frequencies & Requirement to Perform Radiological Emergency Plan & Security Plan Audits from TSs ML20149G2391994-10-0707 October 1994 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising Surveillance Requirements for Plant Operation W/ Inoperable Diesel Generator ML18037A8741994-05-11011 May 1994 Application for Amend to License DPR-52,consisting of TS Change TS-347T to Temporarily Extend AOT of TS 3.9.B.8 While TVA Replaces Batteries & Associated Hardware That Supply 250 Volt Dc Control Power to Units 1 & 2 Shutdown Boards ML20065H2201994-04-0404 April 1994 Suppl 1 to TS-322 to Licenses DPR-33,DPR-52 & DPR-68, Eliminating Reactor Scram & Main Steam Line Isolation Functions Associated W/Msl Radiation Monitors ML20065E3651994-03-31031 March 1994 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Extending Load Line Limit & Revising Rod Block Monitor Operability Requirements & Deleting Specific Value for Rated Reactor Loop Recirculation Flow Rate ML20065F2511994-03-31031 March 1994 Request for Amend TS-319 to Licenses DPR-33 & DPR-68, Lowering Trip Level Settings for HPCI & RCIC Steam Line Space Isolation Instrument Channels ML20065E3841994-03-30030 March 1994 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Revising TSs Re Analog Transmitter/Trip Sys,Level 1 Reactor Water Level Setpoint & Various Calibr Frequencies ML20065D4931994-03-29029 March 1994 Request for Amend TS-340 to License DPR-68,revising TS to Add Operability & SRs to Support Unit 3 480-volt Load Shed Logic Sys Being Added by Design Change ML20059C4981993-12-23023 December 1993 TS Change 346 to Licenses DPR-33,DPR-52 & DPR-68, Incorporating Recommendations for Snubber Visual Insp Intervals Contained in GL 90-09, Alternative Requirements for Snubber Visual Insp Intervals & Corrective Actions ML20057G2511993-10-12012 October 1993 Request for Amend TS-320 to Licenses DPR-33,DPR-52 & DPR-68, Deleting Existing RWCU Sys High Temp Detection Switches from Tables 3.2.A & 4.2.A & Adding New RWCU Sys Temp Loops for Unit 3 & Clarifying Tables 3.2.A & 3.2.B for Units 1,2 & 3 ML20057E8621993-10-0707 October 1993 Application for Amends to Licenses DPR-33,DPR-52 & DPR-68, Consisting of TS 313,adding High Range Primary Containment RMs & Recorders to Tables 3.2.F,4.2.F & TS Section 6.9.2 in Response to NUREG-0737,Item II.F.1.3 ML18037A4761993-09-30030 September 1993 Request for Amend TS-312 to Licenses DPR-33,DPR-52 & DPR-68, Removing SDV Air Header Pressure Trip Switches Scram Function from Unit 2 TS & Clarifying Description of SDV High Water Level Bypass in RPS for Units 1,2 & 3 1999-09-30
[Table view] |
Text
'
1 nessee Valley Authority, Post Office Box 2000. Decatur, Alabama 35609 May 20, 1996 4
l l TVA-BFN-TS-373 10 CFR 50.90
! U.S. Nuclear Regulatory Commission 4 ATTN: Document Control Desk Washington, D.C. 20555 l
Gentlemen: 1 In the Matter of. ) Docket Nos. 50-259
. Tennessee Valley Authority ) 50-260 50-296 i;
! BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 1, 2, AND 3 -
j TECHNICAL SPECIFICATION (TS) CHANGE 373 - GENERIC LETTER (GL)
, 87-09 GUIDANCE INPLENENTATION l i 1 In accordance with the provisions of 10 CFR 50.4 and 50.90, TVA is submitting a request for an amendment (TS-373) to
- licenses DPR-33, DPR-52, and DPR-68 to change the TS for Units 1, 2,'and 3. The proposed change is a BFN TS Line Item Improvement according to the guidance provided in GL 87-09,
! Sections 3.0 And 4.0 Of The Standard Technical Specification on The Applicability Of Limiting Conditions For Operation And j Surveillance Requirements. The proposed TS wording is in
- accordance with NUREG 1433, Revision 1, " Standard Technical 2
Specifications in General Electric Boiling Water Reactors i (BWR/4)." Specifically, this change revises the BFN
- surveillance definition 1.0.LL to incorporate a 24-hour delay in implementing the action requirements due to a missed surveillance requirement when the action requirements provide a restoration time that is less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This change also clarifies that the time limit of the action requirements applies from the point in time it is identified a surveillance has not bean performed and not at the time that the allowed surveillance interval was exceeded.
i 1 O a O A #% A 9605280236 960520' n 4
PDR ADOCK 05000259 Ou P PDR-
- \\
. i i
t a
U.S. Nuclear' Regulatory Commission ,
Page 2 J May 20, 1996 l TVA has determined that there are no significant hazards
, considerations associated with the proposed change and that i
the change is exempt from environmental review pursuant to the provisions of 10 CFR 51.22(c)(9). The BFN Plant Operations i Review Committee and the BFN Nuclear Safety. Review Board have
+
reviewed this proposed change and determined that operation of BFN Units 1, 2, and 3 in accordance with the proposed change will not endanger the health and safety of the public.
Additionally, in accordance with 10 CFR 50.91(b) (1) , TVA is sending a copy of this letter and enclosures to the Alabama State Department of Public Health.
< Enclosure 1 to this letter provides the description and evaluation of the proposed change. This includes TVA's !
determination that the proposed change does not involve a i significant hazards consideration, and is exempt from i environmental review. Enclosure 2 contains copies of the l appropriate TS pages from Units 1, 2, and 3 marked-up to show the proposed change. Enclosure 3 forwards the revised TS pages for Units 1, 2, and 3 which incorporate the proposed change.
TVA requests that the revised TS be made effective within 30 days of NRC approval. If you have any questions about this change, please contact me at-(205) 729-2636.
Sincerel , - - l
\
~ ~
l A$d alas Manager of Site Licensing ,
1 Enclosures '
cc: See page 3 Subscribed and sworn ( before me
- g this 90th dag of AL 1996.
Bnd
- Notary Public RB0aA My Commission Expires 4
4 4
l;
$ l
9 U.S. Nuclear Regulatory Commission Page 3 May 20, 1996 i
Enclosures cc (Enclosures): i Mr. W. D. Arndt I General Electric Company 735 Broad Street Suite 804, James Building Chattanooga, Tennessee 37402 Mr. Johnny Black, Chairman Limestone County Commission 310 West Washington Street
. Athens, Alabama 35611 Mr. Mark S. Lesser, Section Chief l U.S. Nuclear Regulatory Commission I Region II 101 Marietta Street, NW, Suite 2900 l Atlanta, Georgia 30323
)
NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 i Athens, Alabama 35611 l 1
- Mr. Joseph F. Williams, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Dr. Donald E. Williamson State Health Officer Alabama State Department of Public Health 434 Monroe Street Montgomery, Alabama 36130-3017 i
W
ENCLOSURE 1 l TENNESSEE VALLEY AUTHORITY
- j. BROWM8 FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, AND 3 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-373 ,
DESCRIPTION AND EVALUATION OF THE PROPOSED CHANGE i
i
- I. DESCRIPTION OF THE PROPOSED CHANGE
! TVA is revising BFN Units 1, 2, and 3 TS definition 1.0.LL
.to implement the guidance of Generic Letter (GL) 87-09, i Sections 3.0 And 4.0 Of The Standard Technical 1
Specification On The Applicability of Limiting Conditions For Operation And Surveillance Requirements. The proposed change.is consistent with GL 87-09 and the proposed TS I wording is in accordance with NUREG 1433, Revision 1, 4
" Standard Technical Specifications in General Electric
- Boiling Water Reactors (BWR/4)." Specifically, this change i
revises the BFN surveillance definition 1.0.LL to i l
l incorporate a 24-hour delay in implementing the Action l
! requirements due to a missed surveillance requirement when j the Action requirements provide a restoration time that is
, less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Additionally, this change also j clarifies that the time limit of the Action requirements t applies from the point in time it is identified a surveillance has not been performed and not at the time j that the allowed surveillance interval was exceeded.
The specific changes are described below:
- 1. Units 1, 2, and 3 TS Surveillance definition 1.0.LL, TS pages 1.0-11.
Paragraph 1.0.LL currently reads:
" Surveillance - Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual limiting conditions for operation unless otherwise stated in an individual Surveillance Requirements. Each Surveillance Requirement shall be performed l within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.
It is not intended that this (extension) provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillance that are not performed during refueling outages.
Performances of a surveillance Requirement within the specified time interval shall constitute
k i .
9 compliance and OPERABILITY requirements for a limiting condition for operation and associated action statements unless otherwise required by these specifications. Surveillance Requirements do not have to be performed on inoperable equipment."
)'
The proposed change to TS definition 1.0.LL adds a
- third and Fourth paragraph to read
- " Surveillance - Surveillance Requirements shall
- be met during the OPERATIONAL CONDITIONS or other conditions specified for individual limiting i
conditions for operation unless otherwise stated in an individual Surveillance Requirements. Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.
It is not intended that this (extension) provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages.
Performance of a Surveillance Requirement within the specified time interval shall constitute compliance and OPERABILITY requirements for a limiting condition for operation and associated action statements unless otherwise required by these specifications. Surveillance Requirements do not have to be performed on inoperable equipment.
compliano l'tfed ' l' requ" irene "
~"
@jd m . lei;in filiise
~ t . I'"*
at reqpen69 i s ii!
"~"T6dfihypisiitg,it[62AC piiertormancM$g i uds1Xianch l'sW54figf55t
' elaygperT6d thogIcogaust '~16imid)ly Ste eViWiiff.NM reglsisyssBfsg$ssEMsh4fiths d
%4hlaredjnoti o pill 6Mllss$n piikt % 2esG n M PiisHTMsafiEMuiiaW3MisfCi tuitagts@iisn_sii slnotjust delayggeriddyand(iely3tseidscliF~thejsurvel'11ance Jt,t Loo 2mustf'jisisiiiidi$t t tsisetig g d impilfciWikisch4AEiMsMfaustEbehntsisdM ' 'it@is El-2
II. REASON FOR THE PROPOSED CHANGE The proposed change will make BFN's TS consistent with the l guidance provided in GL 87-09 and the proposed TS wording l in accordance with NUREG 1433, Revision 1. DFN's current i TSs do not contain provisions similar to GL 87-09. l Specifically, GL 87-09 allows the flexibility to defer declaring effected equipment inoperable or an effected variable outside the specified limits when a su:veillance has not been completed within the specified frequency.
GL 87-09 allows a delay' period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the point in time that it is discovered that the surveillance i has not been performed and not at the time that the specified frequency was not met. This delay time allows adequate time to complete surveillances that have been missed and permits completion of the surveillances before complying with required actions or other remedial measures that might preclude completion of the surveillances.
i III. SAFETY ANALYSIS In GL 87-n9, NRC stated that it is overly conservative to assume th L systems or components are inoperable when a l surveillance reqc. ement has not been performed. Because j the vast majority si surveillances demonstrate that systems or components in fact are operable. In addition, NRC j stated that the allowable outage time limits of some Action ;
requirements do not provide an appropriate time 11rit far performing a missed surveillance before chutdown requirements apply. GL 87-09 provides 6 24-hour time limit 1 for a missed surveillance. This time limit allows a delay of the required Actions to permit the performance of the missed surveillance.
The time limit is based on considerations of plant conditions, adequate planning, availability of personni,1, the time required to performed the surveillance requirement, as well as the safety significance of the delay in completing the surveillance requirement. GL 87-09 concludes that the 24-hour time limit adequately balances the risks associated with an allowance for completing the surveillance within this period against the risks associated uith the potential for a plant upset and challenge to safety systems when the alternative is a plant shutdown to comply with Action statements before t.he surveillance can be completed.
TV. NO SIGNIFICAF. HAEARDS CONSIDERATION DETERMINATION TVA has concluded that operation of BFN Units 1, 2, and 3, in accordance with the proposed change to the technical specifications.do not involve a significant hazards consideration. TVA's conclusion is barmf on its evaluation, in accorda57e with 10 CFR 50.91(a) (1) , of the three standards set forth in 10 CFR 50.92(c).
El-3
d A. The proposed amendment does not involve a sianificant increase in the erobability or conseauences of an 1 accident creviousiv evaluated.
The proposed amendment to TS definition 1.0.LL is in accordance with the guidance of GL 87-09 and NUREG i 1
. 1433, Revision 1. The proposed change will allow BFN 4
to continue operation for an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after discovery of a missed surveillance. The change being proposed does not affect the precursor for any accident or transient analyzed in Chapter 14 of the BFN Updated Final Safety Analysis Report. The proposed change does not reflect a revision to the j physical design and/or operation of the plant.
Therefore, operation of the facility in accordance with the proposed change does not affect the ;
probability or consequences of an accident previously '
evaluated.
B. The prooOsed amendment does not create the nossibility of a new or different kind of accident from any accident previous 1v evaluated.
The proposed amendment to TS definition 1.0.LL is in accordance with the guidance of GL 87-09 and NUREG 1433, Revision 1. The proposed change will allow the i plant to continue operation for an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after discovery of a missed surveillance. The change being proposed will not change the physical plant or the moaer of operation defined in the facility license. The change does not involve the addition or l moditication of equipment, nor do they alter the 1 design or operation of plant systems. Therefore, !
operation of the facility in accordance with the proposed change does not create the possibility of a new or different kind of accident from any previously I evaluated.
C. The nroposed amendment does not involve a sianificant reduction in a marain of safety.
The proposed amendment to TS definition 1.0.LL is in j accordance with the guidance of GL 87-09 and NUREG 1433, Revision 1. The proposed change does not affect plant safety analysis or change the physical design or operation of the plant. The proposed change will ;
alloa the plant up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform a missed l surveillance. The overall effect is a net gain in plant safety by avoiding unnecessary shutdowns and the associate system transients due to missed 1
El-4
l surveillance. Therefore, operation of the facility in accordance with the proposed change does not I involve a significant reduction in a margin of safety. I V. ENVIRONMENTAL IMPACT CONSIDERATION l l
I The proposed change does not involve a significant hazards consideration, a significant change in the types of or significant increase in the amounts of any effluents that l may be released,offsite, or a significant increase in )
individual or cumulative occupational radiation exposure. l Therefore, the proposed change meets the eligibility I criteria for categorical exclusion set forth in 10 CFR
- 51. 22 (c) (9) . Uterefore, pursuant to 10 CFR 51.22 (b) , an >
environmental assessment of the proposed change is not j required. I l
i 1
1 1
1 l
l i
4 i
r l
El-5