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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Amends to Licenses NPF-68 & NPF-81,deleting or Modifying Existing License Conditions Which Have Been Completed or Are No Longer in Effect ML20151U1931998-09-0303 September 1998 Application for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys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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4 e '
- J. Barnie Brastry,Jr., PE. - Southern Nuclear
,. . Vice Pesident Op: rating Company,Inc.
Vogtle Project 40 invemots Cenw Parkway PO Box 1295 Bemmgham, Alatama 35201 Tel 205932 7110 fax 205 9920403 SOUTHERN COMPANY Energy to Serve Your World*
LCV-1359 August 24, 1999 Docket Nos. 50-424 50-425 U. S. Nuclear Regulatory Commission
' ATTN: Document Control Desk Washington, D. C. 20555 Ladies and Gentlemen:
VOGTLE ELECTRIC GENERATING PLANT-REQUEST TO REVISE TECHNICAL SPECIFICATIONS SLAVE RELAY TEST FREQUENCY SURVEILLANCE REQUIREMENT 3.3.2.5 In accordance with the provisions of 10 CFR 50.90, Southern Nuclear Operating Company (SNC) proposes to revise the Vogtle Electric Generating Plant (VEGP) Unit I and Unit 2 Technical Specifications (TS} 3.3.2 " Engineered Safety Feature Actuation System (ESFAS)
Instrumentation" to relax the slave relay test frequency from quarterly to a refueling frequency.
The associated Bases to Surveillance Requirement (SR) 3.3.2.5 clarifies that slave relay test frequency is adequate based on industry operating history, considering relay reliability and operating history data. The proposed change in slave relay test frequency is based on i information contained in Westinghouse Electric Corporation (Westinghouse) report WCAP-13878 (proprietary)" Reliability Assessment of Potter & Brumfield MDR Series Relays,"
l June 1994. By letter dated May 31,1996 from . Bruce A. Boger (NRC) to Tom Greene, )
I Westinghouse Owners Group (WOG), the NRC approved WCAP-13878, WCAP-14117, and WCAP-13900.
0)0 Enclosure 1 provides the basis for the proposed change. Pursuant to 10 CFR 50.92, Enclosure 2 demonstrates that the proposed change does not involve a significant hazard consideration. Enclosure 3 is a mark-up of the affected pages from the VEGP Unit I and Unit 2 TS and the affected Bases pages. Enclosure 4 contains the clean typed pages ,
reflecting the pro' posed changes. Enclosure 5 contains a copy of the WOG letters that 1 30N20 l 9908300169 990824 L PDR ADOCK 05000424 P PDR '
l 1
k
.g
transmitt'ed WCAP-13878, Revision 1 and WCAP-14117, Revision 1. As stated above, WCAP-13878, WCAP-14117 and WCAP-13900 were reviewed and approved by the NRC as part of a generic WOG program to relax the surveillance test frequency for slave relays.
Mr. J. B. Beasley, Jr. states that he is Vice President of Southern Nuclear Operating Company and is authorized to execute this oath on behalf of Southern Nuclear Operating Company and that, to the best of his knowledge and belief, the facts set forth in this letter are true.
SOUTHERN NUCLEAR OPERATING COMPANY By: /
l['JMBfslef,/f.
Sworn to andsubscribed before me this Yfday of ,1999.
0 My commissio expires: //l0 Notary Yublic / /
JBB/JPC Enclosure 1: Basis for Proposed Change Enclosure 2: Significant Hazards Evaluation Enclosure 3: Marked-Up TS and Bases Pages Enclosure 4: Clean-Typed TS and Bases Pages Enclosure 5: Owner's Group Letter xc: Southern Nuclear Operating Company Mr. J. T. Gasser Mr. M. Sheibani SNC Document Management U. S. Nuclear Regulatorv Commission Mr. L. A. Reyes, Regional Administrator Mr. R. R.~ Assa, Senior Project Manager, NRR Mr. John Zeiler, Senior Resident Inspector, Vogtle State of Georgia L. C. Barrett, Commissioner, Department of Natural Resources -
u
1 J
ENCLOSURE 1 VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECilNICAL SPECIFICATIONS SLAVE RELAY TEST FREQUENCY SURVEILLANCE REQUIREMENT 3.3.2.5 BASIS FOR PROPOSED Cll ANGE Proposed Chance ,
i The current VEGP Technical Specifications (TS) specifically require quarterly testing of slave relays in the Engineered Safety Features Actuation System (ESFAS). This requirement involves testing the relays at power, with the attendant risk ofinadvertent actuation of the Engineered Safety Features (ESP) 1 equipment. In addition, the on-line testing of slave relays requires significant plant manipulation, j abnormal configurations, and removes from service various equipment, making it unavailable to perform )
its intended safety function. A subgroup of the Westinghouse Owners Group (WOG) sponsored a j reliability assessment of specific Potter & Brumfield (P&B) relay types to establish a slave relay surveillance test interval based on relay reliability. The study is documented in WCAP-13878,
" Reliability Assessment of P&B MDR Relays" The proposed change allows relaxing the Slave Relay Test from every 92 days to every 18 months for circuits containing P&B MDR series relays. The TS requirement for Slave Relay Testing will continue to be implemented by SR 3.3.2.5.
The associated Bases for Surveillance Requirement 3.3.2.5 will be revised to clarify that circuits containing P&B MDR series relays may be tested on an 18-month frequency. WCAP-13878, Revision 1, provides both the methodology and technical basis that justifies extending the surveillance frequency for ESFAS P&B MDR relays. The reliability assessment is relay specific and applies only to P&B MDR series relays.
l Basis for Proposed Channe in Surveillance Frequency l Generic Letter (GL) 93-05, "Line item Technical Specification Improvements to Reduce Surveillance Requirements for Testing During Power Operation," was approved in September 1993. This GL resulted from the recommendations of a 1983 NRC task group formed to investigate problems with surveillance testing required by TS. The objective of the NRC task group was: (1) to review the basis for test frequencies; (2) to ensure that the tests promote safety and do not degrade equipment; and (3) to review j surveillance tests for unnecessary burden on plant personnel. The studies found that while some testing {
at power is essential to verify equipment and system operability, safety can be improved, equipment i degradation decreased, and unnecessary personnel burden relaxed by reducing the amount of testing at l
' power. Slave relay test frequency relaxation is consistent with the objectis es of the NRC task group. )
WCAP-13878 contains the technical. basis and methodology for extending slave relay test requirements for ESFAS P&B MDR series relays. The technical basis and methodology were approved by letter dated May 31,1996 from Bruce A. Boger (NRC) to Tom Greene (WOG). The NRC safety evaluation report (SER) for WCAP-13878 requires confirmation of the following:
- 1. Verify that the genetic analysis in WCAP-13878 is applicable to their plant.
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5 ENCLOSUREI VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECIINICAL SPECIFICATIONS SLAVE RELAY TEST FREQUENCY l SURVEILLANCE REQUIREMENT 3.3.2.5 BASIS FOR PROPOSED CilANGE
- 2. Re-evaluate the adequacy of the extended surveillance interval if two or more P&B MDR ESFAS subgroup relays fail in a 12-month period.
- 3. Ensure that the procurement program for P&B MDR relays is adequate for detecting the types of failures that are discussed in References 9,10,11, and 12 of the SER.
- 4. Ensure that all pre-1992 P&B MDR relays which are used in either a nonnally energized or a 20 %
duty cycle have been removed from ESFAS applications.
- 5. Perform a contact loading analysis for P&B MDR relays to determine the acceptability of the relays.
To comply with the required actions of WCAP-13878, SNC has performed the following:
Response to item 1 SNC has compared the methodology and assumptions utilized in WCAP-13878 with the SSPS system design and application of P&B MDR relays at VEGP. Based on this review, the generic analysis
- contained in WCAP-13878 !s applicable to VEGP.
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Response to item 2 Plant procedures will be revised to specifically require monitoring for P&B MDR ESFAS subgroup relay failures. If 2 or more relays fail in a 12-month period, VEGP will re-evaluate the adequacy of the extended surveillance frequency.
Response to Item 3 References 9,10,11 and 12 of the SER for WCAP-13878 identify issues related to substandard refurbishment of P&B MDR relays, and material problems in P&B MDR relays manufactured before 1992. Appropriate plant procedures have been revised to inspect new P&B MDR relays for known substandard refurbishment issues during the material receipt process. Additionally, VEGP will revise the item description in our procurement program to specify that new P&B MDR relays are manufactured after 1992. The date codes of all P&B MDR relays currently in stock will be evaluated and any that were manufactured before 1993 will be removed from stock.
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- ENCLOSURE 1 VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECllNICAL SPECIFICATIONS SLAVE RELAY TEST FREQUENCY SURVEILLANCE REQUIREMENT 3.3.2.5 BASIS FOR PROPOSED CIIANGE Response to Item 4 SNC has performed a detailed review of Unit 1 Train "A" and Train "B" documents. Unit I and Unit 2 are similar. The review determined that there are no normally energized ESFAS Slave Relays.
Additionally, the review determined that none of these relays are energized for a 20% duty cycle.
Item 5 A review of the contact loading of all Unit 1 Train "A" and Train "B" P&B MDR Slave Relays was performed. Unit I and Unit 2 are similar. The actual contact loadings were compared with the design contact rating for P&B MDR relays. This contact loading analysis determined that all P&B MDR Slave Relay contact loadings are within acceptable limits.
Actions for items 2 & 3 will be completed upon approval, but prior to implementation of the proposed TS change.
Auxiliary Relav Reliability Since auxiliary relays can affect the ultimate function of the slave relay to start the required equipment, auxiliary relay reliability must be comparable to that of the associated slave relay. All slave relays and their actuated devices were evaluated for the presence of auxiliary relays. The majority of VEGP slave j relays directly actuate ESF equipment, although some slave relays actuate a combination of equipment j both directly and via auxiliary relays. The functions with auxiliary relays in their actuation paths may be j divided into two groups. 1
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The Erst group consists of ESF functions where the auxiliary relays are tested during the performance of other at power TS-required surveillances. The reliability of these auxiliary relays will continue to be conGrmed every quader during the performance of these surveillances even though the associated Slave Relays are being tested on an 18-month frequency.
The second group consists of ESF functions where the auxiliary relays are not tested at power during other equipment testing. The auxiliary relays used in these circuits have been very reliable, but do not always meet the criteria presented in WCAP-13878 for relaxation of the test frequency since some are not Potter & Brumfield MDR relays. Although relaxation of the surveillance interval for the associated ;
slave relays is justined by WCAP-13878, the auxiliary relays cannot be tested without testing the slave I relays. Therefore, quaderly testing of the associated slave relays will be administratively controlled until l an alternate method of testing the auxiliary relays is developed or until they are replaced with Potter & l Brumneld MDR series relays. I El-3
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.s ENCLOSURE 2 VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECHNICAL SPECIFICATIONS SLAVE RELAY TEST FREQUENCY SURVEILLANCE REQUIREMENT 3.3.2.5 SIGNIFICANT IIAZARDS EVALUATION t Evaluation VEGP has evaluated the no signincant hazards considerations involved with the proposed amendment, focusing on the three standards set forth in 10 CFR 50.92(c) as quoted below:
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The Commission may make afinal determination, pursuant to the procedures in paragraph 50.91, that aproposed amendment to an operating licensefor afacility licensed underparagraph ;
50.21(b) or paragraph 50.22 or a testingfacility involves no significant ha:ards considerations, ifoperation ofthefacility in accordwice with the proposed amendment would not:
(1) Involve a significant increase in the probability or consequences ofan accident previously evaluated; or i (2) Create thepossibility ofa new or different kind ofaccidentfrom any accident previously evaluated; or (3) Involve a sigmficant reduction in a margin ofsafety, i
The following evaluation is provided for the no significant hazards consideration standards. I
- 1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?
The results of WCAP-13878 demonstrate that slave relays are highly reliable. WCAP-13878 also provides guidance to assure that slave relays remain highly reliabte. The aging assessment concludes that the age / temperature-related degradation of all ND relays, and NE relays produced after 1992, is sufficiently slow such that a refueling frequency surveillance interval will not significantly increase the probability of slave relay failures. Finally, the evaluation of the auxiliary relays actuated during slave relay testing has concluded that based on the tests of the auxiliary relays performed during other equipment testing, reasonable assurance is provided that failures will be identified if the associated slave relays are tested on a refueling frequency.
Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
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ENCLOSURE 2 VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECHNICAL SPECIFICATIONS SLAVE RELAY TEST FREQUENCY SURVEILLANCE REQUIREMENT 3.3.2.5 SIGNIFICANT HAZARDS EVALUATION i l
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- 2. Does the change create the possibility of a new or different kind of accident from any accident j previously evaluated?
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l The proposed changes do not alter the performance of the ESFAS mitigation systems assumed l in the plant safety analysis. Changing the interval for periodically verifying ESFAS slave
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relays (assuring equipment operability) will not create any new accident initiators or scenarios. '
Therefore, the proposed changes do not create the possibility of a new or different kind of
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accident from any accident previously evaluated for VEGP.
- 3. Does the change involve a significant reduction in a margin of safety?
The proposed changes do not affect the total ESFAS response assumed in the safety analysis since the reliability of the slave relays will not be significantly affected by the decreased surveillance frequency.
Therefore, the proposed changes do not involve a significant reduction in a margin of safety.
Conclusion Based on the above safety evaluation, VEGP concludes that the changes proposed by this submittal satisfy the no significant hazards consideration standards of 10 CFR 50.92(c) and, accordingly, a no significant hazards finding isjustified.
Environmental Evaluation
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VEGP has evaluated the proposed changes and determined the changes do not involve (i) a !
significant hazards consideration,(ii) a significant change in the types or significant increase in the )
amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or j cumulative occupational radiation exposure. Accordingly, the proposed changes meet the eligibility criteria for categorical exclusion set forth in 10 CFR S t.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), an environmental assessment of the proposed changes is not required.
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