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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Amends to Licenses NPF-68 & NPF-81,deleting or Modifying Existing License Conditions Which Have Been Completed or Are No Longer in Effect ML20151U1931998-09-0303 September 1998 Application for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys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 Power Cornpany .
333 Psedmont Avenue i
. Manta, Georgm 30308 Telephone 404 526 7851
.l Ma4ng Address:
Post Ofhce Elox 4545 Atlanta, Georgia 30302 -
James P. O'Remy tre souttern ekxtrc !.ptem
' Genior Vice President
' Nuclear Operabons ~,
I SL-2603 0327m X7GJ17-V600 August 26, 1987
.l U. S. Nuclear Regulatory Commission ]
ATTN: Document Control Desk. !
-Hashington, D.C. 20555 'l PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 REOUEST TO REVISE TECHNICAL SPECIFICATIONS 3.3.2. 3.3.3.7 -
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 Plant Unit 1 Technical Specifications, Appendix A' to Operating License NPF-68. l The first proposed change revises the action requirement for inoperable '
Fuel Handling Building Post-Accident Ventilation System actuation !'
instrumentation. The second proposed change revises the alarm / trip setpoint limit for the Chlorine Detection Systems which initiate operation . of the Control Room Emergency Filtration System in the isolation mode. l i
Enclosure 1 provides detailed descriptions of the proposed changes and the circumstances necessitating the change request. <
Enclosure 2 details the basis for our determination that the proposed changes do not involve significant hazards considerations. ;
Enclosure 3 provides instructions for incorporating the proposed changes ,
L into the Technical Specifications. The proposed changed Technical !
Specification p&ges follow Enclosure 3. ;
Payment of filh fee is enclosed.
He request that the proposed amendment, once approved by the NRC, be issued with an allowable implementation period of 60 days.
o2og 97aggg ,
WOjDocK0500o424 p
og PDR g eb h o//EC W p0
-2t /a'/fo 80 ,
U. S. Nuclear Regulatory Commission August 26, 1987 Page Two Pursuant to the requirements of 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 a 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 are true.
Sincerely, GEORGIA POWER COMPANY by: cA w n .@ 4 Jases P. O'Reilly Sen4 r Vice President '
' SHORN 0 AND SUBSCRIEED BEFORE-1E
~
THIS 26st DAY OF AUGUST 1987. J
/-
f
/ b ,
Notary Publi'c N0tsry $Uic. Georgia, Stds at Large My Commission Expires Sept.18,1987 JH/1m
Enclosures:
- 1. Bases for Proposed Changes
- 2. 10 CFR 50.92 Evaluation
- 3. Instructions for Incorporation
- 4. Check # 124680 for filing fee c: (see next page) 0327m
)
U. S. Nuclear Regulatory Commission ;
August 26, 1987 Page Three c: Georaia Power Comoany Mr. R. E. Conway Mr. J. P. O'Reilly Mr. G. Bockhold, Jr.
Mr. J. F. D'Amico .
Mr. C. H. Hayes l GO-NORMS )
Soltthern Company Services ,
Mr. R. A. Thomas 1
Mr. J. A. Bailey Shaw. Pittman. Potts & Trowbridge Mr. B. H. Churchill, Attorney-at-Law Troutman. Sanders. Lockerman & Ashmore '
Mr. A. H. Domby, Attorney-at-Law I
U. S. Nuclear Reaulatory Commission Dr. J. N. Grace, Regional Administrator Ms. M. A. Miller, Licensing Projec.t Manager, NRR (2 copies) <
Mr. J. F. Rogge, Senior Resident Inspector-0perations, Vogtle Georaians Aaqinst Nuclear Eneray Mr. D. Feig Ms. C. Stangler i
0327m
I i
ENCLOSURE 1-PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 REQUEST TO REVISE TECHNICAL SPECIFICATIONS 3.3.2, 3.3.3.7 DASES FOR PROPOSED CHANGES PROPOSED CHANGE 1 Revise the action requirement for Item 11 of Table 3.3-2 by . removing the reference to the 7 day' period and referring directly to Specification 3.9.12.
BASIS
, As currently worded, Action 26. for Item 11 of Table 3.3-2 implies that I
operation may continue for up to seven days with less than the required minimum channels of operable instrumentation before taking the action required !
by Specification 3.9.12. This proposed change removes the reference to the
- seven dey period and refers directly to Specification 3.9.12 for the action to i be taken on the basis of operability of the Fuel Handling Building Post-Accident Ventilation System.
[10 POSED CHANGE 2 Revise Specification 3.3.3.7 to raise the alarm / trip setpoint limit of the Chlorine Detection Systems from 2 ppm to 5 ppm.
BASIS Specification 3.3.3.7 currently requires an alarm / trip setpoint of less than or equal to 2 ppm. A new limit of 5 ppm is proposed. The .new limit-has been analyzed using methodology consistent with the current' plant licensing The analysis shows that the- time available for operators to don basis. i protective breathing apparatus is reduced slightly but is adequate and is well above NRC guidelines. The 5 ppm limit is proposed to reduce spurious control room isolations which have occurred as a result of erratic detector-sensitivity at a 2 ppm setpoint.
H y
0327m El-1 08/26/87 SL-2603 L.
1 1
ENCLOSURE 2 PLANT,V0GTLE'- UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE-NPF-68 REQUEST TO REVISE TECHNICAL SPECIFICATIONS 3.3.2, 3.3.3.7 )
10 CFR 50.92 EVALUATION I
Pursuant to 10 CFR 50.92, Georgia Power Company has evaluated the attached proposed amendment to the VEGP Unit 1 Technical . Specifications and has 'f determined that operation of the facility in accordance with the proposed !
amendment would not involve significant hazards considerations. The basis for I the determination is as follows: q PROPOSED CHANGE 1 Revise the action requirement for Item 11 of Table 3.3-2 by removing the i reference to the 7 day period and referring directly to Specification 3.9.12.
BACKGROUNQ Items lla, b, and c of Table 3.3-2 apply to the Fuel Handling Building j Post-Accident Ventilation Actuation Instrumentation. This table lists l operability requirements and actions to be taken in the event of inoperable instrumentation channels. In addition, the Fuel Handling Building Post-Accident Ventilation System operability requirements are given in Specification 3/4.9.12. Specification 3.9.12 includes the actions to be taken in the event one or both trains of the Fuel Handling Building Post-Accident i Ventilation System become inoperable. !
The current action statement for instrument channel inoperability states i that the action of Specification 3.9.12 shall be taken within 7 days if the !
number of operable channels is less than the minimum channels operable requirement. This implies that the actions of Specification 3.9.12 could be delayed for 7 days if the failure of instrumentation channels resulted in one or both trains of the Fuel Handling Building Post-Accident Ventilation System oming inoperable.
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The proposed change deletes the 7 day allowance and provides a - direct reference to Specification 3.9.12 for determination of the appropriate action for inoperable instrumentation channels on the basis of the effect on the operability of the system. It is noted that no ' credit is taken for this system in the safety analyses.
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4 ENCLOSURE 2 (Continued) 10 CFR 50.92 EVALUATION ANALYS15 GPC has reviewed the proposed change .to the action requirement for Fuel Handling Building Post-Accident Ventilation Actuation Instrumentation and has ;
determined that the change does _not involve significant hazards considerations. In support of this conclusion the following analysis is provided:
- 1. The proposed change does not significantly increase the probability or consequences of an accident previously evaluated.- The change has no effect on the operation of the Fuel Handling Building ' Post-Accident Ventilation System. The change achieves consistency within the Technical Specifications and ensures that no delay occurs in execution -of action requirements for inoperable instrument channels. Furthermore, operation of the Fuel Handling Building Post-Accident Ventilation System is not assumed in any accident evaluated for Plant Vogtle.
- 2. The proposed change does not create the possibility of a new or d.ifferent kind of accident than any accident previously evaluated. The change does not affect the design or operation of the Fuel Handling Building Post-Accident Ventilation System or any other plant system or structure.
No new mode of failure is introduced by the change, therefore, a new or different kind of accident could not result.
- 3. The proposed change does not significantly reduce a margin of safety. The fuel Handling Building Post-Accident Ventilation System is not ~ assumed to operate in any accident analyzed for Plant Vogtle. The system provides defense in depth to minimize the radiological consequences of a fuel handling accident. The change does not reduce the capability of the system to perform this function. The change should reduce the likelihood that a misinterpretation of the Technical Specifications will prolong an inoperable condition.
C0KCWS10E Based on the preceding analysis, GPC has determined that the proposed change to the Technical Specifications will not significantly increase the probability or consequences of an accident previously evaluated, create the possibility of a new or different kind of accident from any: accident previously evaluated, or involve a significant reduction in a margin of safety. GPC therefore concludes that the proposed change meets the requirements of 10 CFR 50.92(c) and does not involve significant hazards considerations.
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ENCLOSURE 2 (Continued) ;
10 CFR 50.92 EVALUATION i
PROPOSED CHANGE 2 Revise Specification 3.3.3.7 to raise the alarm / trip setpoint limit of the ,
Chlorine Detection Systems from 2 ppm to 5 ppm. 1 BACKGROUND The subject chlorine detection systems automatically initiate operation of the Control Room Emergency Filtration System in the isolation mode. GPC has experienced numerous control room isolations from these chlorine detectors as discussed in Licensee Event Reports 50-424/1987-019 (5/29/87) and 50-424/1987-028 (6/26/87). Manual air sampling- and analysis following the events produced no indication of chlorine gas. GPC believes that a major contributor to these isolations was erratic sensitivity of the chlorine detectors at the current 2 ppm setpoint. The vendor-recommended setpoint is i
i 50% to 70% of the full scale reading of 10 ppm. GPC is proposing a 5 ppm I setpoint to improve the reliability of the detectors and reduce unnecessary operation of the Control Room Emergency Filtration System.
The current 2 ppm setpoint is based on an analytical evaluation of con'rol room habitability in the event of a 1 ton chlorine cylinder rupture at the Nuclear Service Cooling Hater chlorine storage building. This evaluation was submitted to the NRC in References 1 and 2 and was reviewed and accepted by NRC as discussed in Reference 3.
GPC has evaluated an increase in the ch10rine detector setpoint using methodology consistent with that described in the references. This analysis utilized the Regulatory Guide 1.95 meteorological model and control room infiltration model previously used and accepted by NRC. The VEGP design basis .
wind speed of 0.9 m/s, which represents the worst fifth percentile wind i velocity, and Pasquill Class F stability were assumed. Calculations were also '
performed using a wind speed of 0.7 m/s to show the sensitivity of the l analysis to changes in wind speed.
The results of the analysis show that a setpoint of 5 ppm is acceptable.
At this setpoint, approximately 9 minutes,13 seconds are avcilable to the operator to , don protective breathing apparatus (7 minutes, 29 seconds at 0,7 m/s wind speed) after a chlorine alarm is received. This represents only a 12% reduction in available time as compared to the original analysis and is well above the 2 minutes in which VEGP operators are trained to don breathing equipment after detecting toxic gas. This is also well above the 2 minute guideline contained in Regulatory Guides 1.78 and 1.95 and is consistent with the 5 ppm guideline contained in Regulatory Guide 1.95.
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ENCLOSURE 2 (Continued) 10 CFR 50.92 EVALUATION It is noted that the original analysis did not consider ,
chlorine-contaminated air entering directly into the control room through ' the {
normal HVAC system outside air intakes. This assumption was valid since, at a '
setpoint of 2 ppm, the control room isolation dampers would be closed before any contaminated air could travel from the detector to. the downstream isolation damper. Chlorine concentrations were calculated by assuming that !
750 cfm of contaminated air entered the control room through various 1.eakage i paths specified in Reference 2.
In evaluating the effects of higher detector setpoints, where 'the time f required to close the isolation dampers exceeded the time required for contaminated air to reach the downstream damper, the analysis accounted for 3000 cfm of chlorine-contaminated air entering the control room through the 1 normal HVAC system outside air intakes until the isoittion dampers were fully i l closed. All other aspects of the original analysis, including the model, remained unchanged.
ANALYSIS l GPC has reviewed the proposed chlorine monitor setpoint change with I respect to the requirements of 10 CFR 50.92 and has determined that the change does not involve significant hazards considerations.
In support of this !
conclusion, the following analysis is provided:
- 1. The proposed change will not significantly increase the probability or consequences of an accident previously evaluated. The change affects only the chlorine concentration at which operation of the Control Room Emergency Filtration System is automatically initiated in the isolation mode. Operation of the filtration system in_ response to a safety injection, high radiation, or manuel initiation signal is not affected. i i
' Initiation of the filtration system at the revised chlorine setpoint maintains the required level of protection for control room operators during an accidental chlorine gas release. An analysis using methodology consistent with the current plant licensing basis shows that the time ,
available to operators to don protective breathing apparatus is well above trained operator response time and NRC minimum guidelines.
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ENCLOSURE 2 (Continued) 10 CFR 50.92 EVALUATION
- 2. _The proposed change does not create the. possibility of a new or different I kind of accident than any accident previously evaluated. The change does l not modify the design of the Chlorine Detection Systems, 'the Control Room i
Emergency Filtration System, or any .other plant system or structure.
Since no new system configuration or failure mode would result from the J change, a new or different kind of accident could not result.
- 3. The proposed change does not significantly reduce a margin of safety. '
Protection of control room operators in _the event of. an accidental chlorine gas release is maintained well above NRC _ minimum criteria. GPC j believes that the chlorine detectors will operate more reliably at the revised setpoint and that degradation of the Control Room Emergency Filtration System from unnecessary operation will be reduced, making a positive contribution to margins of safety.
CONCLUSION i Based on the preceding analysis, GPC has determined ' that the proposed i change to the Technical Specifications will not significantly increase the '
probability or consequences of an accident previously evaluated, create the possibility of a new or different kind of accident from any accident previously evaluated, or involve a significant reduction in a margin of safety. GPC therefore concludes that the proposed change meets the requirements of 10 CFR 50.92(c) and does not involve significant hazards j considerations. !
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ENCLOSURE 2 (Continued) 10 CFR 50.92 EVALUATION REFERENCES
- 1. GPC letter to NRC dated November 26, 1985, Log GN-750 l 2. GPC letter to NRC dated February 19, 1986, Log GN-808
- 3. -NUREG-1137 Supplement 2, " Safety Evaluation Report Related to the Operation of Vogtle Electric Generating Plant Units 1 and'2.
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1 ENCLOSURE 3 .
1 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68
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REQUEST TO REVISE TECHNICAL SPECIFICATIONS 3.3.?, 3.3.3.7 INSTRUCTIONS FOR INCORPORATION i
The proposed change to the Technical Specifications (Appendix A to 1 Operating License NPF-68) would be incorporated as follows:
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Femove Page Insert Page 3/4 3-24 3/4 3-24 3/4 3-25 3/4 3-25 3/4 3-27 3/4 3-27 3/4 3-63 3/4 3-63 l
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