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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TS License Conditions.Ts Change TS-381,consists of Administrative Revs That Delete License Conditions That Have Become Outdated,No Longer Applicable or Are Redundant ML18039A8781999-09-28028 September 1999 TS Change 399 to Licenses DPR-52 & DPR-68,increasing Allowable Leakage Rate Criteria for MSIVs &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
nn Tennessee Valley Authority. Post Office Box 2000. Decatur, Alabama 35609 April 14, 1996 TVA-BFN-TS-375 10 CFR 50.4 10 CFR 50.90 10 CFR 50.91 '
l l U.S. Nuclear Regulatory Commission l ATTN: Document Control Desk
( Washington, D.C. 20555 l
! Gentlemen:
In the Matter of ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260 50-296
, BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 1, 2, AND 3 -
l TECHNICAL SPECIFICATION (TS) 375 - CHANGE IN OPERABILITY l REQUIREMENTS FOR REACTOR VESSEL WATER LEVEL INSTRUMENTATION
{ In accordance with the provisions of 10 CFR 50.4 and 50.90, l TVA is submitting a request for an amendment (TS-375) to licenses DPR-33, DPR-52 and DPR-68 to change the TSs for l Units 1, 2, and 3. The proposed change revises the minimum l required number of operable reactor vessel water level trip systems (TS Table 3.2.B) during the period that the reactor coolant system instrument line excess flow check valve surveillance tests are being performed. This check valve surveillance testing is required by TS 4.7.D.1.d.
! Plant personnel have identified a condition that has led TVA to seek this TS change in order to resolve any potential conflict between these two TS requirements. Historically, the performance of the surveillance testing was interpreted to be acceptable because it was a requirement of the TS.
However, this testing conflicts with the literal reading of l the provisions of TS Table 3.2.B. These conflicting i requirements will prevent the resumption of power operations.
l Unit 2 is in its eighth refueling outage. The physical l characteristics of these excess flow check valves and their I
specific application at BFN require this surveillance testing
(
be performed with reactor system pressure in excess of 500 psig. This pressure is available at BFN only under hot
, conditions or in cold shutdown during hydrostatic / reactor system leak checks. For maximum personnel safety, it is desirable to perform this testing while the reactor is in cold shutdown. 4 O n n n .mr. '
9604230054 960414 #
s PDR ADOCK 05000259 L I
P PDR t
U.S. Nuclear Regulatory Commission Page 2 April 14, 1996 The Unit 2 hydrostatic testing is currently expected to occur no later that April 18, 1996. Since failure to act in a timely way would result in prevention ~of resumption of operation, TVA requests this proposed amendment be processed under the emergency provisions of 10 CFR 50.91.
TVA has determined that there are no significant hazards considerations associated with the proposed change and that the change is exempt from environmental review pursuant to the provisions of 10 CFR 51.22 (c) (9) . The BFN Plant Operations 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 significant hazards consideration, and is exempt from environmental review. Enclosure 2 contains copies of the 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 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of NRC approval. If you have any questions about this change, please contact me at (205) 729-2636.
Sinceral ,
Manager of Site Licensing Enclosures i ec:-see page 3 i Subscribed and sworn to,hefore me on his / V/h day of M8/2 1996.
AAd] . A4)fOt1 Notary Public My Commission Expires i
U.S. Nuclear Regulatory Commission Page 3 April 14, 1996 Enclosures cc (Enclosures):
Mr. W. D. Arndt 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 s
Mr. Mark S. Lesser, Branch Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 l
NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611 Mr. Joseph F. Williams, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 l Dr. Donald E. Williamson
! State Health Officer l Alabama State Department of Public Health 434 Monroe' Street Montgomery, Alabama 36130-3017 Mr. R. P. Zimmerman l U.S. Nuclear Regulatory Commission i One White Flint, North ;
11555 Rockville Pike Rockville, Maryland 20852 l
4 i
_ _ - - ._ _ m ._ . _ _ . _ _ _ _ . _ _ _ . . . . _ _ _ _ _ _ _ _ _ . - _ _ _ . _ _ - . _ . _ _ _
l l
ENCLO8URE 1 TENNESSEE VALLEY AUTHORITY BROWN 8 FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, AND 3 PROPOSED TECHNICAL 8PECIFICATION (TS) CRANGE T8-375 DE8CRIPTION AND EVALUATION OF THE PROPOSED CHANGE
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I. DESCRIPTION OF THE PROPOSED CHANGE l
l TVA is adding a note to BFN Technical Specifications for l Units 1, 2, and 3. This note clarifies the minimum number i of operable channels per trip system required to be operable l during testing of the reactor coolant system instrument line flow check valves in accordance with TS section 4.7.D.1.d.
The specific changes are described below:
- 1. Units 1, 2 and 3 TS pages 3.2/4.2-14 j Table 3.2.B, Column 1, Minimum No. Operable channel l Per Trip System for the Reactor Water Level Instrumentation LIS-3-58 A through D currently requires minimum of two operable channels per trip l
systems.
The proposed change to Column 1, Minimum No. Operable l channel Per Trip System adds a reference to Note 19, column i one item four. The reactor low water level instrumentation ,
(LIS-3-58A-D) with trip level setting greater than or equal l to 398 inches above vessel zero. l
- 2. Revised Units 1 and 2 TS page 3.2/4.2-24, Unit 3 TS page 3.2/4.2-23 to add Note 19. Note 19 reads as follows:
Only one trip system will be required to be OPERABLE l during testing of the reactor coolant system instrument l line flow check valves in accordance with TS section l l 4.7.D.1.d, provided the reactor is in COLD SHUTDOWN. I Manual and automatic initiating capability of CSS and LPCI will be available, but with a reduced number of instrument channeln.
II. REASON FOR THE PROPOSED CHANGE Plant personnel have identifj ed a condition that has led TVA to seek this TS change in order to resolve any potential l conflict between these two TS requirements. The proposed change revises the minimum required number of operable reactor vessel water level trip systems (TS Table 3.2.B) i during the period that the reactor coolant system instrument i line excess flow check valve surveillance tests are being performed. This check valve surveillance testing is required by TS 4.7.D.1.d.
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Unit 2 is in its eighth refueling outage. The physical characteristics of these excess flow check valves and their specific application at BFN require this surveillance testing be performed with reactor system pressure in excess of 500 psig. This pressure is available at BFN only under hot conditions or in cold shutdown during hydrostatic / reactor system leak checks. The safest time to perform this testing is while the reactor is in cold shutdown. The Unit 2 hydrostatic testing is currently scheduled for April 18, 1996 at 1400 CDT. Since failure to act in a timely way would result in prevention of resumption of operation, TVA requests this proposed amendment be l processed under the emergency provisions of 10 CFR 50.91.
III. BAFETY ANALYSIB Despite the fact that the minimum Technical Specification required number of reactor vessel water level trip systems will not be operable during the period that the reactor coolant system instrument line flow check valve surveillance tests are being performed, only one variable leg will be removed from service at a time. The other variable leg and its associated reactor vessel water level instrumentation will remain in service and be capable of initiating the Core Spray System, LPCI, and the multiplier relay from the Core Spray System that, in conjunction with dryw e ll hig h pressure, initiates an accident signal. However, this resulting configuration is not single failure proof.
In addition to the remaining leg (either LS-3-58A-B or LS-3-58C-D) being available for automatic initiation, the following reactor vessel water level instrumentation will not be affected by the proposed modifications and will remain in service:
INSTRUMENT RANGE Flood-Up Range O to 400" (2-LI-3-55)
While this instrumentation is not configured to substitute 4 for the automatic initiation of the reactor vessel water i level instrumentation that is being removed from service ,
(either LS-3-58A-B or LS-3-58C-D), it will provide the operators with reactor vessel water level indication. In case of a single failure in the remaining variable leg (either LS-3-58C-D or LS-3-58A-B), the operators would manually initiate the Core Spray System and LPCI, as appropriate.
During the performance of the reactor coolant system instrument line flow check valve surveillance tests, the plant will be in a cold shutdown condition with the primary system temperature at less than 212 degrees Fahrenheit.
While in a cold shutdown condition, the incidents to be El-2
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considered are an inadvertent drain down of the reactor l vessel due to a pipe break, a leak in the reactor coolant l pressure boundary due to maintenance or valve
! mispositioning, or a recirculation pump seal failure. The I BFN licensing basis does not assume a double-ended guillotine break of a recirculation discharge line during hydrostatic testing of the primary system. No unique safety actions are required with the reactor vessel head on and reactor pressure greater than 850 psig because the core is l more than one rod subcritical and could not achieve criticality with the full withdrawal of any one control rod.
Pipe breaks during hydrostatic testing are not a potential l threat. The primary piping has been analyzed to the design criteria, and with the temperature being below 212 degrees Fahrenheit, the pipe stress margins preclude critical or circumferential cracks.
Piping failures are considered to have an extremely low probability of occurrence due to the low temperature and margins inherent in reactor system piping design, the probability of a loss of reactor vessel inventory and the l need for automatic initiation of the Core Spray System and LPCI during the time period when one trip system is out of service is considered remote.
However, if a leak is assumed in the primary system piping during the performance of this test, and there is a single failure in the remaining trip system that prevents automatic initiation of the safety functions, sufficient instrumentation will be available for the operators to identify and respond to the event. The equipment required to mitigate the event will be available and the operators will be able to manually initiate the safety functions.
The operator would be initially aware of a loss of coolant inventory as a result of a lowering of reactor pressure.
Other indications would subsequently occur if the loss of inventory was not stopped (e.g., upon receipt of an abnormal water level alarm at approximately 555" above vessel zero (6" below normal water level) and an automatic depressurization system blowdown permissive alarm at approximately 546" above vessel zero). These two indications come from reactor vessel water level instrumentation, which is unaffected by the reactor coolant system instrument line flow check valve surveillance ter,ts being performed. If the reactor water level reached 39E" above vessel zero, the Emergency Operating Instructions direct the operator to manually initiate LPCI if it was not automatically initiated.
The LPCI and Core Spray Low Pressure Permissives for the injection valves are not inhibited by the isolation of a single variable leg during primary system hydrostatic testing, i
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Therefore, requiring only one trip system for the reactor low water level instrument channel (LS-3-58A-D) be operable i during the period that the reactor coolant v stem instrument I line flow check valve surveillance tests are being performed i is justified due to: ;
- 1) the low primary system temperature,
- 2) the low probability of an event that would result in l the drain down of the reactor vessel,
- 3) the automatic initiating capability of the remaining reactor vessel water level trip system, and
- 4) the other reactor vessel level instrumentation and equipment that is available for manual operator intervention in the event of a plant transient or I accident. I l
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FIGURE 1 i
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FIGURE 2 i Reactor Vessel Water Level Instrumentation Initiating Logic ORYWELL PRESS. HIGH REACTOR PRESS. LOW
-l LS-3-58A RX VESSEL Lvl LOW MOM PS (TYPIC E & 4) LS-3-588 9-3 LS- - LS-3-580 74 ISI(152)
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NOTE: The RHR automatic initiation logic is shown. The automatic initiation logic for core Spray is similar.
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IV. NO SIGNIFICANT HABARDS CONSIDERATION DETERMINATION TVA has concluded that operation of Browns Ferry Nuclear Plant (BFN) Units 1, 2, and 3 in accordance with the l
! proposed change to the technical specifications does not i involve a significant hazards consideration. TVA's l conclusion is based on its evaluation, in accordance with 10 l CFR 50.91(a) (1) , of the three standards set forth in 10 CFR l 50.92(c).
A. The cronosed amendment does not involve a sianificant increase in the probability or consecuences of an l
accident oreviousiv evah , jjuto The proposed change in the applicability of the minimum number of reactor low water level instrument channels required to be operable does not increase the frequency of the precursors to design basis events or operational transients analyzed in the Browns Ferry Final Safety Analysis Report. Therefore, the probability of an accident previously evaluated is not significantly increased.
l While in a cold shutdown condition with the reactor.
vessel below 212 degrees Fahrenheit, the incidents to be considered are an inadvertent drain down of the reactor vessel due to a pipe break, a leak in the l reactor coolant pressure boundary due to maintenance or valve mispositioning, or a recirculation pump seal i failure. The other variable leg and its associated reactor vessel water level instrumentation will remain in service and be capable of initiating the required safety functions. In addition, several other reactor vessel water level instruments will remain in service and will provide the operators with reactor vessel water level indication in case of a single failure in the remaining variable leg. Based on input from this instrumentation, the operators would manually initiate the required safety functions, as appropriate.
Therefore, the proposed changes will not significantly increase the consequences of an accident previously evaluated, i B. The cronosed amendment does not create the nossibility of a new or different kind of accident from any accident oreviousiv evaluated.
The change to the number of reactor vessel water level trip systems required to be operable does not create a new pathway for radioactive material to reach the environment. The out of service instruments are used to indicate plant parameters and to initiate systems required to mitigate accidents or plant transients.
The remaining instrumentation will still be available
- to automatically initiate the required functions. The operators will have sufficient time to manually El-7 1
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initiate the required functions if a single failure occurs in the remaining instrumentation. Therefore, j the proposed amendment does not create the possibility of a new or different kind of accident from any
- accident previously evaluated.
j C. The cronosed amendment does not involve a sianificant i reduction in a marain of safety.
i The proposed change to the number of reactor vessel i water level trip systems required to be operable does not change the licensing or design basis limits for the l initiation of protective actions. The time available for the control room operators to take manual actions will adequately compensate for the lack of single failure proof automatic initiation capability of the Core Spray and Low Pressure Coolant Injection systems during the period in which the affected systems will be out of service. Therefore, the proposed amendment does not involve a significant reduction in the margin of safety.
V. ENVIRONMENTAL IMPACT CONSIDERATION The proposed change does not involve a significant hazards consideration, a change in the types of, or increase in, the amounts of any effluents that may be released offsite, or a significant increase in individual or cumulative occupational radiation exposure. Therefore, the proposed 1 change meets the eligibility criteria for categorical I exclusion set forth in 10 CFR 51.22 (c) (9) . Therefore, l pursuant to 10 CFR 51.22(b), an environmental assessment of the proposed change is not required.
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