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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Amends to Licenses NPF-68 & NPF-81,deleting or Modifying Existing License Conditions Which Have Been Completed or Are No Longer in Effect ML20151U1931998-09-0303 September 1998 Application for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys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
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GM9 3 fDWW Cf/PP N0Y 3M PWmoN Avenue Attanta. Georg'a 30303
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Uaary Miest
- Rut Ofhce Co 4545 AMa, Gog3 2'DP R. P. Mcdonald the sa.Thern eEtr<'syseem t.eNNe Vice Pres dect Nuvear CNrat ons SL-4752 0957m X7GJ17-V600 June 1,1988 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C. 20555 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 AMENDED REQUEST TO REVISE TECHNICAL SPECIFICATIONS CORPORATE AND PLANT ORGANIZATIONS Gentlemen:
In accordance with the provisions of 10 CFR 50.90 as required by 10 CFR 50.59(c)(1), Georgia Power Company (GPC) hereby proposes to amend the Vogtle Electric Generating Plant Unit 1 Technical Specifications, Appendix A to Operating License NPF-68. This submittal revises GPC's amendment request dated May 6, 1988 (SL-4290) in order to clarify certain position titles.
The , oposed amendment replaces the organization charts in the Technical Specifications with more general organizational requirements.
These general requirements capture the essential organizational features depicted on the charts necessary for ensuring that the plant is operated safely. This change is consistent with the guidance provided in Generic Letter 88-06, "Removal of Organization Charts from Technical Specification Administrative Control Requirements", issued on March 22, 1988. GPC also proposes to revise or delete _ references to certain corporate management positions to remove unnecessary details from the Technical Specifications.
Enclosure 1 provides a detailed description of the proposed change ;
and the basis for the change request. I Enclosure ,2 details the basis for our determination that the proposed .
changes do not involve significant hazards considerations.
l Enclosure 3 provides instructions for incorporating the proposed changes into the Technical Specifications. The proposed revised pages follow Enclosure 3.
Pay'r,ent of the required filing fee was made with the May 6, 1988, j submittal.
8806130066 880601 '
'PDR ADOCK 05000424 P DCD '
... si Georgia Power 1 l l
U. S. Nuclear Regulatory Commission June 1, 1988 Page Two In .accordance with 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. R. P. Mcdonald states that he is an Executive 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 C PANY
\
By: f' 6% '
R. P. Mcdonald Sworn to and subscribed before me this 1st day of June 1988.
X$weab.0l4wa Notary Public Neeery PuhEn, Cisyten Cowey.On.
HEB/im , m a,,, gs,3m
Enclosures:
- 1. Basis for Proposed Change
- 2. 10 CFR 50.92 Evaluation
- 3. Instructions for Incorporation 1
c: Georaia Power Comp My Mr. P. D. Rice Mr. G. Bockhold, Jr.
G0-NORMS U. S. Nuclear Reaulatory Commission Dr. J. N. Grace, Regior,al Administrator Mr. J. B. Hopkins, Licensing Project Manager, NRR (2 copies)
Mr. J. F. Rogge, Senior Resident Inspector-Operations, Vogtle 1
I 0957m l
,__.m..r. .. . --
- s
'.i Georgia Power b ENCLOSURE 1 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 REQUEST TO REVISE TECHNICAL SPECIFICATIONS BASIS FOR PROPOSED CHANGE PROPOSED CHANGE 1 Delete Figures 6.2-1 and 6.2-2 of the Technical Specifications.
Revise Specification 6.2.1 to provide more general requirements for the off-site and plant organizations.
ILASl$
Inclusion of organization charts in the Technical Specifications is not specifically required by regulation. .The presence of these charts requires GPC's processing and the NRC's review of unnecessary license amendments for organization changes. Consistent with NRC and industry commitment to improve Technical Specifications, GPC proposes to replace the organization charts with more general organizational requirements.
The proposed change would eliminate a needless expenditure of resources by both GPC and the NRC. Replacement of organization charts with more general requirements was recently endorsed by the NRC in Generic Letter 88-06. The change proposed by GPC is consistent with^ the guidance '
provided in the Generic Letter.
PROPOSED CHANGL2 Change references to the Senior Vice President-Nuclear Operations to the "Vice President-Nuclear" in Specifications 6.2.3, 6.4.1, 6.4.2, 6.5.1, and 6.6.1. Change references to the General Manager - Vogtle Nuclear Operations to the "General Manager-Nuclear Plant" in specifications 6.1.1, 6.1. 2, 6.2.2, 6.4.1, 6.6.1, 6.7.1, 6.7.3, 6.12, 6.13, and 6.14. Delete references to the Manager-Nuclear Performance and Analysis in Specification 6.2.3.
ILA$1$
Consistent with the replacement of the organization charts with more general requirements, GPC proposes to incorporate more general references to the vice president and general manager positions, and to delete references to the Manager-Nuclear Performance and Analysis. These revisions would reduce the need for license amendments to reflect title changes while still maintaining the same level of management oversight to activities affecting safety.
0957m El-1 06/01/88 SL-4752
',,, .i Georgia Powerkn l ENCLOSURE 2 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE.NPF-68 REQUEST TO REVISE TECHNICAL SPECIFICATIONS 10 CFR 50.92 EVALUATION l
In accordance with 10 CFR 50.92, Georgia Power Company has evaluated the attached proposed amendment to the VEGP Unit 1 Technical Specifications and has determined that operation of the facility in accordance with the proposed amendment would not involve significant hazards considerations. The basis for this determination is as follows:
PROPOSED CHANGE 1 Delete Figures 6.2-1 and 6.2-2 of the Technical Specifications.
Revise Specification 6.2.1 to provide more general requirements for the off-site and plant organizations.
BACKGROUND The content required in the Administrative Controls section of the Technical Specifications is described in 10 CFR 50.36.c(5). This !
regulation requires that the Technical Specifications contain the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner. Organization charts are not specifically required, but have generally been included in Technical Specifications as a means of depicting the organizational and management relationships necessary to support safe plant operation. As stated in Generic Letter 88-06, the NRC staff has found the organization charts to be of little value in ensuring that the objectives of the Administrative i l
Controls are satisfied. Other Technical Specifications contain specific i operational requirements which bear more directly on operational safety.
At Plant Vogtle, for example, Administrative Technical Specifications establish the following controls:
- 1. the authority of the plant general manager for overall plant operation,
- 2. the control room command authority of the On-Shif t Operations Supervisor,
- 3. control room shift staffing and operator licensing in accordance with 10 CFR 50.54, 0957m E2-1 06/01/88 SL-4752
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- 4. review and audit by the Plant Review Board. Safety Review Board, '
and Independent Safety Engineering Group, and
- 5. procedure, recordkeeping, and reporting requirements.
The staff determined that, with certain additions, the Administrative Technical Specifications would capture those organizational features i necessary to assure safe plant operation without the need to maintain the ,
organization charts. Consistent with the guidance provided in the l Generic Letter, GPC is proposing to replace the organization charts with j the following provisions: ,
ONSITE AND OFFSITE ORGANIZATION ;
6.2.1 Onsite and offsite organizations shall be established for plant operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
- a. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization posi in s . These relationships shall be documented and updated, as appcopriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the FSAR.
- b. The General Manager-Nuclear Plant shall be responsible for overall plant safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant. >
- c. The Vice President-Nuclear shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
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REQUEST TO REVISE TECHNICAL SPECIFICATIONS 10 CFR 50.92 EVALUATION
- d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
Hith these additions, the Administrative Technical Specifications would continue to meet the objectives of 10 CFR 50.36.c(5) without the need for organiz1 tion charts. Detailed descriptions of the onsite and offsite organizations, including organization charts, are presently contained in the Vogtle FSAR. This information will be updated regularly in accordance with 10 CFR 50.71(e). The organization charts in the FSAR will be upgraded as necessary and maintained with at least the same level of detail as the charts proposed for removal from the Technical Specifications. Positions requiring a senior reactor operator license are designated in Technical Specification 6.2.2 and hence, do not need to be added.
I:s summary, the Administrative Technical Specifications, as amended, would assure that the organizational features essential to safe plant operation are maintained without the need for prior NRC approval of changes to organization charts.
ANALYSIS GPC has reviewed the proposed change with 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 is administrative in nature and involves no physical alteration of the plant or changes to setpoints or operai;ing parameters. The change does not affect operation, maintenance, or testing of the plant. For these reasons, the response of the plant to previously evaluated accidents will remain unchanged, t 0957m E2-3 06/01/88 SL-4752
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- 2. The proposed change does not create the possibility of a new or different kind of accident than any accident previously evaluated. Since no change is being made to the design, operation, maintenance, or testing of the plant, a new mode of failure ,is not created. A new or different kind of accident could therefore not result.
- 3. The proposed change does not significantly reduce a margin of safety. The general organizational requirements being added to the Technical Specifications will assure that those organizational features necessary for safe plant operation will continue to be maintained. Details of the organizational structure will be maintained in the FSAR and updated regularly.
Deletion of the organization charts frcm the Technical Specifications will eliminate the unnecessary expenditure of GPC resources currently required to process license amendment requests for organization changes. Margins of safety are therefore not reduced.
CONCLUSIQi >
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 accioent from any accident previously evaluated, or involve a significant reduction in a l margin of safety. GPC therefore concludes that the proposed change meets j the requirements of 10 CFR 50.92(c) and does not involve significant l hazards considerations.
l PROPOSE 0 CHANGE 2 Change references to the Senior Vice President-Nuclear Operations to I the "Vice President-Nuclear" in Specifications 6.2.3, 6.4.1, 6.4.2, l 6.5.1, and 6.6.1. Change references to the General Manager-Vogtle '
Nuclear Operations to the "General Manager-Nucl ear Plant" in specifications 6.1.1, 6.1.2, 6.2.2, 6.4.1, 6.6.1, 6.7.1, 6.7.3, 6.12, 6.13, and 6.14. Delete references to the Manager-Nuclear Performance and Analysis in Spe;ification 6.2.3.
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REQUEST 10 REVISE TECHNICAL SPECIFICATIONS 10 CFR 50.92 EVALUATION BACKGROUND The Administrative Technical Specifications currently contain numerous references to the Senior Vice President-Nuclear Operations, and the General Manager-Vogtle Nuclear Operations. These references assure that an appropriate level of management control is exercised over activities affecting operational safety. A change to either of these titles requires a license amendment; however, as in the case of the organization charts, these specific titles could be replaced with more general references and the objectives of the Administrative Technical Specifications would continue to be met. Changing the above references to "Vice President-Nuclear" and "General Manager-Nuclear Plant" would ,
assure the same level of management control while eliminating the need for unnecessary license amendments when title changes occur. Reference is made to the Manager-Nuclear Performance and Analysis with respect to reporting requirements of the Independent Safety Engineering Group (ISEG). Specification 6.2.3 requires that ISEG recommendations and reports be forwarded to the Senior Vice President-Nuclear Operations through the Manager-Nuclear Performance and Analysis. Since this information is required to be sent to the "Vice President-Nuclear" level,
_ an appropriate level of management attention is assured. Specification of the intermediate reporting level represents an unnecessary degree of detail. GPC therefore proposes to delete reference to the Manager-Nuclear Performance and Analysis.
ANALYSIS GPC has reviewed the above proposed change and has determined that the change does not involve significant hazards considerations. In i
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 is administrative in nature and involves no physical alteration of the plant or changes to setpoints or operating parameters. Since the change has no direct bearing on '
operation, maintenance, or testing of the plant, the response to the plant to previously evaluated accidents will not be affected.
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- 2. The proposed change does not create the possibility of a new or different kind of accident than any accident previously evaluated. Since no change is being made to the design, operation, maintenance, or testing of the plant, a new mode of failure is not created. A new or different kind of accident could therefore not result.
- 3. The proposed change does not significantly reduce a margin of safety. The previous level of management oversight will be
^ maintained over activities affecting nuclear safety. Deletion of references to the Manager-Nuclear Performance and Analysis merely removes unnecessary details from the Technical Specifications. Margins of safety are therefore not reduced.
CONCLUSION 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, l create the possibility of a new or different kind of accident from any I accident previously evaluated, or significantly reduce a margin of l 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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