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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20217G6441999-10-13013 October 1999 Application for Amends to Licenses NPF-68 & NPF-81,revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2.Non-proprietary & Proprietary TS & Info Encl.Proprietary Encl Withheld ML20217B1121999-10-0404 October 1999 Application for Amends to Licenses NPF-68 & NPF-81,to Revise TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 ML20212F3521999-09-22022 September 1999 Supplemental Application for Amend to Licenses NPF-68 & NPF-81,proposing Change to SR 3.8.1.13 to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5441999-08-30030 August 1999 Application for Amends to Licenses NPF-68 & NPF-81,proposing to Raise Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7211999-08-26026 August 1999 Rev to 990413 Application for Amend to Licenses NPF-68 & NPF-81,updating Versions of LCO 3.0.4 & SR 3.0.4 to Be IAW Versions of LCO 3.0.4 & SR 3.0.4 as They Appear in Rev 1 to NUREG-1431 ML20211E9031999-08-24024 August 1999 Application for Amends to Licenses NPF-68 & NPF-81,relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3111999-05-18018 May 1999 Application for Amends to Licenses NPF-68 & NPF-81,revising SRs 3.8.1.3 & 3.8.1.13 to Reduce Loading Requirements for DGs ML20206D6831999-04-28028 April 1999 Application for Amends to Licenses NPF-68 & NPF-81,changing Licensing Basis from Present Requirement to Establish Containment Hydrogen Monitoring within 30 Minutes of Initiation of Safety Injection to within 90 Minutes of LOCA ML20205S3731999-04-19019 April 1999 Application for Amends to Licenses NPF-68 & NPF-81,revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS ML20205Q7781999-04-13013 April 1999 Application for Amends to Licenses NPF-68 & NPF-81,updating Versions of LCO 3.0.4 & SR 3.0.4 That Appear in Existing TS to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as in Rev 1 to NUREG-1431 ML20154M9911998-10-15015 October 1998 Application for Amends to Licenses NPF-68 & NPF-81,deleting or Modifying Existing License Conditions Which Have Been Completed or Are No Longer in Effect ML20151U1931998-09-0303 September 1998 Application for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Short Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys.Ts Pages Encl ML20236R4631998-07-13013 July 1998 Application for Amends to Licenses NPF-68 & NPF-81, Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protection Channels ML20236F1541998-06-26026 June 1998 Application for Amends to Licenses NPF-68 & NPF-81,revising TS LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20247K4891998-05-15015 May 1998 Suppl Application for Amend to Licenses NPF-78 & NPF-81 Ts. Amend Will Revise New Program 5.5.18 to Extent That Items B,C & D Ref to LCO Action Statement & Revises Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9371998-05-0808 May 1998 Application for Amends to Licenses NPF-68 & NPF-81,revising TS 5.5.7, RCP Flywheel Insp Program, by Specifying Alternate Flywheel Insp Once Every Ten Years ML20199A4041998-01-22022 January 1998 Application for Amends to Licenses NPF-68 & NPF-81,adding Conditions for DGs for Extended DG Completion Time of Fourteen Days ML20199G3721997-11-20020 November 1997 Application for Amends to Licenses NPF-68 & NPF-81,proposing Changes That Would Facilitate Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20199J6591997-11-20020 November 1997 Application for Amends to Licenses NPF-68 & NPF-81,revising TS to Change Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20217H8981997-08-0808 August 1997 Revised Application for Amends to Licenses NPF-68 & NPF-81, Revising TS Re Credit for Boron & Enrichment Increase for Fuel Storage ML20141A8121997-06-13013 June 1997 Application for Amends to Licenses NPF-68 & NPF-81,revising TS LCO 3.4.10, Pressurizer Safety Valves, to Reduce Nominal Set Pressure by 1% to 2460 Psig & Increase Tolerance to +2% ML20128G9881996-10-0404 October 1996 Application for Amends to Licenses NPF-68 & NPF-81, Eliminating Credit for Boraflex as Neutron Absorbing Matl in Fuel Storage Pool Criticality Analysis ML20117N6401996-06-17017 June 1996 Application for Amends to Licenses NPF-68 & NPF-81,changing TS Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20117N6311996-06-17017 June 1996 Application for Amends to Licenses NPF-68 & NPF-81, Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20101D4081996-03-0505 March 1996 Application for Amends to Licenses NPF-68 & NPF-81, Converting Existing TS to Improve for Westinghouse Plants as Represented by NUREG-1431 ML20094N3821995-11-20020 November 1995 Rev to 950501 Application for Amends to Licenses NPF-68 & NPF-81,revising TS to Convert Existing TS to Format & Content of NUREG-1431,Westinghouse Improved STS ML20093K2021995-10-16016 October 1995 Application for Amends to Licenses NPF-68 & NPF-81,adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J ML20098A4801995-09-22022 September 1995 Application for Amends to Licenses NPF-68 & NPF-81, Converting Existing VEGP TS Requirements to Format & Content of NUREG-1431 ML20083M0551995-05-12012 May 1995 Application for Amend to License NPF-68,changing TS SR 4.6.1.2 to Support one-time Exemption from Section III.D.1(a) of 10CFR50,App J,Extending Interval for Type a Test from Scheduled 36 Months to Approx 54 Months ML20082T5591995-05-0101 May 1995 Application for Amends to Licenses NPF-68 & NPF-81, Converting TSs to Improved TSs for Westinghouse Plants as Represented in NUREG-1431 ML20081J4901995-03-17017 March 1995 Application for Amends to Licenses NPF-68 & NPF-81,revising TS 3.9.4 Re Containment Bldg Penetrations,To Allow Personnel Airlock to Be Open During Core Alterations or Movement of Irradiated Fuel within Containment ML20080F7781995-01-20020 January 1995 Application for Amends to Licenses NPF-68 & NPF-81,changing TS 6.4.2 Re Plant Review Board Composition ML20079B1961994-12-29029 December 1994 Application for Amends to Licenses NPF-68 & NPF-81, Requesting to Add Automatic Load Sequencer to Plant ML20079A9411994-12-27027 December 1994 Application for Amends to Licenses NPF-68 & NPF-81,revising Ts,By Revising Leak Test Frequency for Valves W/Resilient Seals ML20077F2131994-12-0606 December 1994 Application for Amends to Licenses NPF-68 & NPF-81, Eliminating Containment Spray Additive Sys ML20073K3761994-10-0303 October 1994 Application for Amends to Licenses NPF-68 & NPF-81,revising TS Reactor Pressure Limits as Results of New Analyses That Account for Nonconservatisms Identified in NRC Info Notice 93-058 & Results of RPV Surveillance Capsule Exams ML20073B7181994-09-13013 September 1994 Application for Amends to Licenses NPF-68 & NPF-81,changing Elimination of Containment Spray Additive Sys ML20072F1981994-08-16016 August 1994 Application for Amend to License NPF-68,eliminating Article 2.C.(6) & Associated Attachment 1 of License Re Diesel Maint & Surveillance ML20072F2151994-08-16016 August 1994 Application for Amends to Licenses NPF-68 & NPF-81,revising TS 3/4.7.1.1 & Bases Re Setpoint Tolerance for Main Steam Safety Valves ML20070A9841994-06-24024 June 1994 Application for Amends to Licenses NPF-68 & NPF-81,revising Values of Z & for Pressurizer Pressure Reactor Trip Instrumentation Trip Setpoints to Allow Use of Alternate Types of Pressure Transmitters ML20069C7271994-05-20020 May 1994 Application for Amends to Licenses NPF-68 & NPF-81, Relocating Heat Flux Channel Factor,Fq(Z),Penalty of 2 Percent in Spec 4.2.2.2.f to cycle-specific COLR to Allow for burnup-dependent Values of Penalty in Excess of 2% ML20070M6711994-04-28028 April 1994 Application for Amends to Licenses NPF-68 & NPF-81,changing TS 3/3.8.1.1, AC Sources Operating, Based on GL 93-05,RG 1.9 & NUMARC 87-00,Rev 1 ML20065F8631994-03-31031 March 1994 Application for Amends to Licenses NPF-68 & NPF-81, Revising TS 3/4.7.1.1 & Bases Re Max Allowed Reactor Thermal Power Operation W/Inoperable Main Steam Safety Valves ML20064L7341994-03-18018 March 1994 Application for Amends to Licenses NPF-68 & NPF-81,proposing Changes to Ts,Incorporating Technical Substance of Corresponding Spec (LCO 3.3.3) from NUREG-1431,Rev 0 ML20064C7181994-03-0101 March 1994 Application for Amends to Licenses NPF-68 & NPF-81, Reinstating Exception 3.0.4 for TS 3.2.4, Quadrant Power Tilt Ratio, ML20063E0591994-02-0303 February 1994 Application for Amends to Licenses NPF-68 & NPF-81, Relocating Requirements of TS 3/4.7.10,area Temp Monitoring to Section 16.3 of FSAR ML20059D2381993-12-30030 December 1993 Application for Amends to Licenses NPF-68 & NPF-81,revising TS to Allow One Time Extension of AOT for RHR Pumps from 3 to 7 Days.One Time Extension Necessary to Allow Mods to RHR Sys While Plant in Mode 1 ML20058A9291993-11-19019 November 1993 Application for Amends to Licenses NPF-68 & NPF-81,proposing Revs to TS Re Dc Sources,Including Rev of SRs of Paragraphs 4.8.2.1.e & F & Table 4.8-2, Battery Srs ML20058A9451993-11-19019 November 1993 Application for Amends to Licenses NPF-68 & NPF-81,adding Footnote to Table 3.3-2,stating That ESFAS Not Required in Mode 2 When AFW Operating to Supply Sfs.Footnote Will Be Applied to Applicable Modes for Functional Unit 6.e ML20058H9971993-11-19019 November 1993 Application for Amends to Licenses NPF-68 & NPF-81, Relocating Requirements of TS 3/4.3.4, Turbine Overspeed Protection to Section 16.3 of Fsar.Ge Proprietary Rept GET-8039 Encl.Proprietary Rept Withheld,Per 10CFR2.790 1999-09-22
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217G6441999-10-13013 October 1999 Application for Amends to Licenses NPF-68 & NPF-81,revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2.Non-proprietary & Proprietary TS & Info Encl.Proprietary Encl Withheld ML20217B1121999-10-0404 October 1999 Application for Amends to Licenses NPF-68 & NPF-81,to Revise TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 ML20212F3521999-09-22022 September 1999 Supplemental Application for Amend to Licenses NPF-68 & NPF-81,proposing Change to SR 3.8.1.13 to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5441999-08-30030 August 1999 Application for Amends to Licenses NPF-68 & NPF-81,proposing to Raise Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7211999-08-26026 August 1999 Rev to 990413 Application for Amend to Licenses NPF-68 & NPF-81,updating Versions of LCO 3.0.4 & SR 3.0.4 to Be IAW Versions of LCO 3.0.4 & SR 3.0.4 as They Appear in Rev 1 to NUREG-1431 ML20211E9031999-08-24024 August 1999 Application for Amends to Licenses NPF-68 & NPF-81,relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3111999-05-18018 May 1999 Application for Amends to Licenses NPF-68 & NPF-81,revising SRs 3.8.1.3 & 3.8.1.13 to Reduce Loading Requirements for DGs ML20206D6831999-04-28028 April 1999 Application for Amends to Licenses NPF-68 & NPF-81,changing Licensing Basis from Present Requirement to Establish Containment Hydrogen Monitoring within 30 Minutes of Initiation of Safety Injection to within 90 Minutes of LOCA ML20205S3731999-04-19019 April 1999 Application for Amends to Licenses NPF-68 & NPF-81,revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS ML20205Q7781999-04-13013 April 1999 Application for Amends to Licenses NPF-68 & NPF-81,updating Versions of LCO 3.0.4 & SR 3.0.4 That Appear in Existing TS to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as in Rev 1 to NUREG-1431 ML20154M9911998-10-15015 October 1998 Application for Amends to Licenses NPF-68 & NPF-81,deleting or Modifying Existing License Conditions Which Have Been Completed or Are No Longer in Effect ML20151U1931998-09-0303 September 1998 Application for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Short Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys.Ts Pages Encl ML20236R4631998-07-13013 July 1998 Application for Amends to Licenses NPF-68 & NPF-81, Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protection Channels ML20236F1541998-06-26026 June 1998 Application for Amends to Licenses NPF-68 & NPF-81,revising TS LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20247K4891998-05-15015 May 1998 Suppl Application for Amend to Licenses NPF-78 & NPF-81 Ts. Amend Will Revise New Program 5.5.18 to Extent That Items B,C & D Ref to LCO Action Statement & Revises Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9371998-05-0808 May 1998 Application for Amends to Licenses NPF-68 & NPF-81,revising TS 5.5.7, RCP Flywheel Insp Program, by Specifying Alternate Flywheel Insp Once Every Ten Years ML20199A4041998-01-22022 January 1998 Application for Amends to Licenses NPF-68 & NPF-81,adding Conditions for DGs for Extended DG Completion Time of Fourteen Days ML20199J6591997-11-20020 November 1997 Application for Amends to Licenses NPF-68 & NPF-81,revising TS to Change Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20199G3721997-11-20020 November 1997 Application for Amends to Licenses NPF-68 & NPF-81,proposing Changes That Would Facilitate Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20217H8981997-08-0808 August 1997 Revised Application for Amends to Licenses NPF-68 & NPF-81, Revising TS Re Credit for Boron & Enrichment Increase for Fuel Storage ML20141A8121997-06-13013 June 1997 Application for Amends to Licenses NPF-68 & NPF-81,revising TS LCO 3.4.10, Pressurizer Safety Valves, to Reduce Nominal Set Pressure by 1% to 2460 Psig & Increase Tolerance to +2% ML20128G9881996-10-0404 October 1996 Application for Amends to Licenses NPF-68 & NPF-81, Eliminating Credit for Boraflex as Neutron Absorbing Matl in Fuel Storage Pool Criticality Analysis ML20117N6401996-06-17017 June 1996 Application for Amends to Licenses NPF-68 & NPF-81,changing TS Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20117N6311996-06-17017 June 1996 Application for Amends to Licenses NPF-68 & NPF-81, Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20101D4081996-03-0505 March 1996 Application for Amends to Licenses NPF-68 & NPF-81, Converting Existing TS to Improve for Westinghouse Plants as Represented by NUREG-1431 ML20094N3821995-11-20020 November 1995 Rev to 950501 Application for Amends to Licenses NPF-68 & NPF-81,revising TS to Convert Existing TS to Format & Content of NUREG-1431,Westinghouse Improved STS ML20093K2021995-10-16016 October 1995 Application for Amends to Licenses NPF-68 & NPF-81,adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J ML20098A4801995-09-22022 September 1995 Application for Amends to Licenses NPF-68 & NPF-81, Converting Existing VEGP TS Requirements to Format & Content of NUREG-1431 ML20083M0551995-05-12012 May 1995 Application for Amend to License NPF-68,changing TS SR 4.6.1.2 to Support one-time Exemption from Section III.D.1(a) of 10CFR50,App J,Extending Interval for Type a Test from Scheduled 36 Months to Approx 54 Months ML20082T5591995-05-0101 May 1995 Application for Amends to Licenses NPF-68 & NPF-81, Converting TSs to Improved TSs for Westinghouse Plants as Represented in NUREG-1431 ML20081J4901995-03-17017 March 1995 Application for Amends to Licenses NPF-68 & NPF-81,revising TS 3.9.4 Re Containment Bldg Penetrations,To Allow Personnel Airlock to Be Open During Core Alterations or Movement of Irradiated Fuel within Containment ML20080F7781995-01-20020 January 1995 Application for Amends to Licenses NPF-68 & NPF-81,changing TS 6.4.2 Re Plant Review Board Composition ML20079B1961994-12-29029 December 1994 Application for Amends to Licenses NPF-68 & NPF-81, Requesting to Add Automatic Load Sequencer to Plant ML20079A9411994-12-27027 December 1994 Application for Amends to Licenses NPF-68 & NPF-81,revising Ts,By Revising Leak Test Frequency for Valves W/Resilient Seals ML20077F2131994-12-0606 December 1994 Application for Amends to Licenses NPF-68 & NPF-81, Eliminating Containment Spray Additive Sys ML20073K3761994-10-0303 October 1994 Application for Amends to Licenses NPF-68 & NPF-81,revising TS Reactor Pressure Limits as Results of New Analyses That Account for Nonconservatisms Identified in NRC Info Notice 93-058 & Results of RPV Surveillance Capsule Exams ML20073B7181994-09-13013 September 1994 Application for Amends to Licenses NPF-68 & NPF-81,changing Elimination of Containment Spray Additive Sys ML20072F1981994-08-16016 August 1994 Application for Amend to License NPF-68,eliminating Article 2.C.(6) & Associated Attachment 1 of License Re Diesel Maint & Surveillance ML20072F2151994-08-16016 August 1994 Application for Amends to Licenses NPF-68 & NPF-81,revising TS 3/4.7.1.1 & Bases Re Setpoint Tolerance for Main Steam Safety Valves ML20070A9841994-06-24024 June 1994 Application for Amends to Licenses NPF-68 & NPF-81,revising Values of Z & for Pressurizer Pressure Reactor Trip Instrumentation Trip Setpoints to Allow Use of Alternate Types of Pressure Transmitters ML20069C7271994-05-20020 May 1994 Application for Amends to Licenses NPF-68 & NPF-81, Relocating Heat Flux Channel Factor,Fq(Z),Penalty of 2 Percent in Spec 4.2.2.2.f to cycle-specific COLR to Allow for burnup-dependent Values of Penalty in Excess of 2% ML20070M6711994-04-28028 April 1994 Application for Amends to Licenses NPF-68 & NPF-81,changing TS 3/3.8.1.1, AC Sources Operating, Based on GL 93-05,RG 1.9 & NUMARC 87-00,Rev 1 ML20065F8631994-03-31031 March 1994 Application for Amends to Licenses NPF-68 & NPF-81, Revising TS 3/4.7.1.1 & Bases Re Max Allowed Reactor Thermal Power Operation W/Inoperable Main Steam Safety Valves ML20064L7341994-03-18018 March 1994 Application for Amends to Licenses NPF-68 & NPF-81,proposing Changes to Ts,Incorporating Technical Substance of Corresponding Spec (LCO 3.3.3) from NUREG-1431,Rev 0 ML20064C7181994-03-0101 March 1994 Application for Amends to Licenses NPF-68 & NPF-81, Reinstating Exception 3.0.4 for TS 3.2.4, Quadrant Power Tilt Ratio, ML20063E0591994-02-0303 February 1994 Application for Amends to Licenses NPF-68 & NPF-81, Relocating Requirements of TS 3/4.7.10,area Temp Monitoring to Section 16.3 of FSAR ML20059D2381993-12-30030 December 1993 Application for Amends to Licenses NPF-68 & NPF-81,revising TS to Allow One Time Extension of AOT for RHR Pumps from 3 to 7 Days.One Time Extension Necessary to Allow Mods to RHR Sys While Plant in Mode 1 ML20058A9451993-11-19019 November 1993 Application for Amends to Licenses NPF-68 & NPF-81,adding Footnote to Table 3.3-2,stating That ESFAS Not Required in Mode 2 When AFW Operating to Supply Sfs.Footnote Will Be Applied to Applicable Modes for Functional Unit 6.e ML20058A9291993-11-19019 November 1993 Application for Amends to Licenses NPF-68 & NPF-81,proposing Revs to TS Re Dc Sources,Including Rev of SRs of Paragraphs 4.8.2.1.e & F & Table 4.8-2, Battery Srs ML20058H9971993-11-19019 November 1993 Application for Amends to Licenses NPF-68 & NPF-81, Relocating Requirements of TS 3/4.3.4, Turbine Overspeed Protection to Section 16.3 of Fsar.Ge Proprietary Rept GET-8039 Encl.Proprietary Rept Withheld,Per 10CFR2.790 1999-09-22
[Table view] |
Text
'
, , Georgia Fbwer Company 333 Piedmont Avenue Atlanta, Georgia 30308 Telephone 404 526 7851 Mathng Address:
. Post Office Box 4545 Atlanta, Georgia 30302 rVC re dent Nucluar Operations SL-2791 0392m X7GJ17-V600 July 7,1987 U. S. Nuclear Regulatory Commission ATTN: Docunent Control Desk Washington, D.C. 20555 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 REQUEST TO REVISE TECHNICAL SPECIFICATIONS 3/4.3.2, 3/4. 3.3.1 Gentlemen:
In accordance with the provisions of 10 CFR 50.90 and 10 CFR 50.59, Georgia Power Company (GPC) hereby proposes changes to the Vogtle Electric Generating Pl ant Unit 1 Technical Specifications, Appendix A to Operating License NPF-68.
FeaturesThe first proposed Actuation changESFAS)
System (e revises Specificationto Instrumentation, 3/4.3.2, removeEngineered references Safety to phase "A" containment isolation on a high containment area radiation signal.
This isolation signal, which is derived from high range containment area radiation monitors RE-0005 and RE-0006, is neither required by regulations nor is it necessary to mitigate the consequences of any accident or malfunction analyzed for Plant Vogtle. GPC is proposing to physically remove this feature from the containment isolation system design pending NRC approval of this proposed revision to the Technical Specifications.
The second proposed change revises Specification 3/4.3.3.1, Radiation ibnitoring for Plant Operations, to correct a reference to the ESFAS specification which would no longer be applicable as a result of the first change. This revision is proposed to achieve consistency within the Technical Specifications.
Enclosure 1 provides a detailed description of the proposed changes and the circumstances justifying the change request.
Enclosure 2 provides the basis for our determination that the proposed changes do not involve significant hazards considerations.
Enclosure 3 provides instructions for incorporating the proposed changes into the Technical Specifications. The proposed revised Technical Specification pages follow Enclosure 3.
8707150706 870707 PDR ADOCK 05000424 P pyg ggc ry g,ycgM OM f 960ScR7 lll
l V. S. - Nuclear Regulatory Commission July 7,1987 l Page-Two 1
Payment of the. required filing fee is enclosed.
We request that the proposed amendment, once approved by the NRC, be issued with an allowable implementation period of 60 days.
Pursuant to 10 CFR 50.91, Mr. J. L. Ledbetter of the Environmental Protection Division 'of the Georgia Department of Natural Resources will be sent a copy of this letter and all applicable enclosures.
Mr. James P. O'Reilly states that he is Senior Vice President of Georgia Power Company. and is. authorized to execute this . oath on behalf of Georgia Power Company, and that to the best of his knowledge and belief, the facts set forth in this letter and enclosures are true.
GEORGIA POWER COMPANY
\
By; . om L D Sc$-A dames P. O'Reilly Sworn to and subscribed before me this 7th o July 1987.
/_. Notary Public Casia. SW at Large gj ,j .
My Conmission bpires Sept.18,1987
' .Notar'y Public JH/lm
Enclosures:
- 1. Basis for Proposed Changes
- 2. 10 CFR 50.92 Evaluation 3.- Instructions for Incorporation c: (see next page) l l
1
1 x .
i i
U. S. Nuclear. Regulatory Commission July 7,1987 i Page Three i
c: ' Georgia Power Company Mr. R. E. Conway Mr. J. P. O'Reilly Mr. G. Bockhold, Jr. .
Mr. J. F. D'Amico. 1 Mr. C. W. Hayes i
GO-NORMS Southern Company Services ,
I Mr. R. A. Thomas Mr. J. A. Bailey.
Shaw, Pittman, Potts & Trowbridge Mr. B. W. Churchill . Attorney-at-Law Troutman, Sanders, Lockerman & Ashmore Mr. A. H. Domby, Attorney-at-Law U. S. Nuclear Regulatory Commission Dr. J. N. Grace, Regional Administrator Ms. M. A. Miller, Licensing Project Manager, NRR (2 copies)
Mr. J. F. Rogge, Senior Resident Inspector-Operations, Vogtle Georgians Against Nuclear Energy Mr. D. Feig Ms. C. Stangler i
I 0392m
~*
i i
1 .
I ENCLOSURE 1 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 BASIS FOR PROPOSED CHANGES PROPOSED CHANGE 1 Revise Tables 3.3-2, 3.3-3, and 4.3-2 to delete references to containment phase "A" isolation on high containment area radiation (monitors RE-0005 and RE-0006).
BASIS
Background
Four area radiation monitors are located inside the containment building to continuously indicate radiation levels at the operating deck. These monitors function as part of the Area Radiation Monitoring System (ARMS) as discussed in Section 12.3.4 of the FSAR. They are considered to be safety-related and are Class lE qualified.
In addition to their ARMS function, these monitors function as part of the Engineered Safety Features Actuation System (ESFAS). The low-range monitors, RE-0002 and RE-0003, are used to initiate containment ventilation system isolation. The high-range monitors, RE-0005 and RE-0006, are used to initiate phase "A" containment isolation. In their role of initiating containment isolation, monitors RE-0005 and RE-0006 provide redundancy to the automatic containment isolation initiated by any signal which initiates safety injection. These signals are:
- manual safety injection actuation
- high containment pressure
- low pressurizer pressure
- low steamline pressure Containment isolation may also be initiated manually.
0392m E1 -1 07/07/87 SL-2791
ENCLOSURE 1 (Continued)
BASIS FOR PROPOSED CHANGES The Technical Specifications contain limiting conditions for operation (LCO) and surveillance requirements for monitors RE-0005 and RE-0006. Specification 3/4.3.2, ESFAS Instrumentation, requires that both channels be operable in Modes 1, 2, 3, and 4. With one channel inoperable, Action 27 requires that the inoperable channel be restored to operable status within 7 days or that the plant be in at least hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, at least hot standby within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and cold shutdown within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Speci fication 3/4.3.3.1, Radiation Monitoring for Plant Operations , ,
lists monitors RE-0005 and RE-0006 and refers to the ESFAS specification for LC0 and surveillance requirements. Specification 3/4.3.3.6, Accident ;
Monitoring Instrumentation, includes monitors RE-0005 and RE-0006 and specifies LC0 and surveillance requirements consistent with an accident monitoring function.
Basis for Proposed Technical Specification Change GPC has reviewed the safety functions of high-range radiation monitors RE-0005 and RE-C006 to determine the impact of their inoperability on plant safety. l This review included a review by Westinghouse and covered all postulated accidents for which the monitors woul d be called upon to function.
Containment phase "A" isolation on high radiation is not a protective function and is not used as a basis in the FSAR Chapter 15 accident analyses. Phase "A" isolation initiation by radiation monitors RE-0005 and RE-0006 is redundant to other features that isolate containment (as discussed above).
For postulated accidents, one of these other features would initiate phase "A" isolation prior to initiation by monitors RE-0005 and RE-0006.
Indeed, phase "A" isolation by these radiation monitors is not included in the Westinghouse standard design basis, and therefore, not included in the blestinghouse Standard Technical Specifications (NUREG-0472). Inclusion of this feature in the Vogtle design, therefore, represents what we believe to be a unique application. l Based on the above, GPC believes that removal of the phase "A" containment isolation function of monitors RE-0005 and RE-0006 from the VEGP containment isolation system is justified. We are therefore proposing to physically remove this feature from the containment isolation system and remove references to this function from the Technical Specifications. We note that the accident monitoring function of monitors RE-0005 and RE-0006 is not affected by the proposed change and will be maintained in accordance with Specification 3/4.34.6. We also note that containment purge and vent valve 0392m El-2 07/07/87 SL-2791 )
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, -j ENCLOSURE 1 (Continued)
BASIS FOR PROPOSED CHANGES isolation on high containment radiation as required by NUREG-0737 Item II.E.4.2(7) is unaffected by the proposed change. This function is provided by monitors RE-0002, RE-0003, RE-2565A, RE-25658, and RE-2565C which remain in the Technical Specifications.
GPC will revise the VEGP FSAR to reflect the removal of the phase "A" isolation on high containment area radiation following NRC review and approval ;
of the change.
. PROPOSED CHANGE 2 Revise Item la of Table 3.3-4 to_ refer to Specification 3.3.3.6 for operability and action requirements for containment area high range radiation monitors RE-0005 and RE-0006. Revise Item la of Table 4.3-3 to refer to Specification 4.3.3.6 for surveillance requirements for monitors RE-0005 and RE-0006'.
BASIS This ' change - is proposed to achieve consistency within the Technical Specifications. . Specification 3/4.3.3.1, Radiation Monitoring for Plant Operations, lists containment area high range radiation monitors RE-0005 and RE-0006 in Tables 3.3-4 and 4.3-3. Reference is made in- those tables to the ESFAS specification for limiting conditions for operation (LCO). and surveillance requirements. Specification 3/4.3.3.6, Accident Monitoring Instrumentation, lists monitors RE-0005 and RE-0006 in Table 3.3-8 and specifies LC0 and surveillance requirements based on an accident monitoring function. Since proposed change 1 removes the containment isolation function of these monitors from the Technical Specifications, leaving accident monitoring as their primary function, the appropriate LC0 and . surveillance requirements are those contained in the Accident Monitoring Instrumentation specification. The references contained in Specification 3/4. 3. 3.1 are revised accordingly.
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L ENCLOSURE 2 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 10 CFR 50.92 EVALUATION Pursuant to 10 CFR 50.92, Georgia Power Company has evaluated the attached proposed amendment to the VEGP Unit 1 Technical Specifications and has determined that its implementation woul d not involve significant hazards ,
considerations. The basis for this determination is as follows:
PROPOSED CHANGE 1 Revise Tables 3.3-2, 3.3-3, and 4.3-2 to remove references to phase "A" containment isolation on a high containment area radiation signal (monitors RE-0005 and RE-0006).
BASIS This change does not involve significant hazards considerations for the following reasons:
- 1. The change does not increase the probability or consequences of an accident or malfunction previously analyzed. Phase "A" containment isolation on a high contain.nent area radiation signal is not required to mf tigate the consequences of any accident or malfunction analyzed for Plant Vogtle. No credit is taken for this isolation signal in the accident analyses described in Chapter 15 of the VEGP FSAR. Containment phase "A" isolation at VEGP is initiated by the redundant and diverse signals which initiate safety injection, i .e. , manual safety injection .
initiation, high containment p"ressure, low pressurizer pressure, and low i steam line pressure. Phase "A isolation can also be initiated manually.
In all accidents and malfunctions analyzed for VEGP, phase "A" isolation is initiated by one of these signals before the high area radiation isolation setpoint is reached. Removal of phase "A" isolation on high containment area radiation from the VEGP containment isolation system design will therefore have no significant safety consequences.
- 2. The change does not create the possibility of an accident or malfunction j different from any previously analyzed. No new system configuration or j failure mode is created by the change. The high containment area j radiation input to the VEGP containment isolation system will be physically removed such that an unanalyzed malfunction of the containment isolation system could not occur. Operation of the containment isolation system using other automatic or manual initiation signals is not affected by the change.
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l ENCLOSURE 2 (Continued) 10 CFR 50.92 EVALUATION
- 3. The margin of safety as defined in the basis of the Technical l Specifications is not reduced by the change. The basis for the ESFAS '
Instrumentation Technical Specification is not affected because phase "A" containment isolation on a high containment area radiation signal is not a protective function. It is not required and takes no part in the f mitigation of any accident or malfunction analyzed for VEGP.
Redundant and diverse signals ensure phase "A" isolation in accordance with the FSAR Chapter 15 safety analyses.
PROPOSED CHANGE 2 Revise Item la of Table 343-4 to refer to Specification 3.3.3.6 for operability and actic,n requirements for containment area high range radiation monitors RE-0005 and RE-0006. Revise Item la of Table 4.3-3 to refer to Specification 4.3.3.6 for survefilance requirements for monitors RE-0005 and RE-0006.
BASIS This change is proposed to achieve consistency within the Technical Specifications. It is therefore consistent with Item (1) of " Examples of Amendments That Are Considered Not Likely to Involve Significant Hazards Considerations", listed on page 7751 of the Federal Register, March 6,1986.
This change does not involve significant hazards considerations for the following reasons:
- 1. The proposed change does not increase the probability or consequences of an accident or malfunction previously analyzed because it is a strictly administrative change which does not affect the operation or testing of i plant equipment. The change corrects a reference to achieve internal consistency.
- 2. The proposed change does not create the possibility of an accident or malfunction of a different type than any previously analyzed because it is an administrative change which does not introduce any new system configurations or failure modes.
- 3. The proposed change does not involve a reduction in the margin of safety as defined in the basis of the Technical Specifications because it does not affect the operation or testing of plant equipment. The Technical Specification bascs are therefore not affected.
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ENCLOSURE 3 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 l OPER/; TING LICENSE NPF-68 INSTRUCTIONS FOR INCORPORATION The proposed amendment to the VEGP Unit 1 Technical Specifications (Appendix A !
to Operating License NPF-68) would be incorporated as follows:
Remove Page Insert Page i
3/4 3-18 3/4 3-18 3/4 3-27 3/4 3-27 '
3/4 3-29 3/4 3-29 3/4 3-38 3/4 3-38 3/4 3-46 3/4 3-46 ,
3/4 3-48 3/4 3-48 l
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