|
|
Line 28: |
Line 28: |
| l In accordance with 10 CFR 50.90, Southem Nuclear Operating Company (Southern Nuclear) requests that Appendix A of Facility Operating Licenses NPF-68 and NPF-81 be amended to modify the Vogtle Electric Generating Plant (VEGP) Units I and 2 Technical Specifications (TS). | | l In accordance with 10 CFR 50.90, Southem Nuclear Operating Company (Southern Nuclear) requests that Appendix A of Facility Operating Licenses NPF-68 and NPF-81 be amended to modify the Vogtle Electric Generating Plant (VEGP) Units I and 2 Technical Specifications (TS). |
| The purpose of the proposed license amendments is to revise TS 5.5.7, " Reactor Coolant Pump | | The purpose of the proposed license amendments is to revise TS 5.5.7, " Reactor Coolant Pump |
| , Flywheel Inspection Program,"in accordance with the Safety Evaluation Report (SER) recommendations included in a letter dated September 12,1996 from the Nuclear Regulatory Commission (NRC) to Duquesne Light Company - Beaver Valley Power Station, " Acceptance for Referencing of Topical Report WCAP-14535, ' Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination'." | | , Flywheel Inspection Program,"in accordance with the Safety Evaluation Report (SER) recommendations included in a {{letter dated|date=September 12, 1996|text=letter dated September 12,1996}} from the Nuclear Regulatory Commission (NRC) to Duquesne Light Company - Beaver Valley Power Station, " Acceptance for Referencing of Topical Report WCAP-14535, ' Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination'." |
| The current technical specification specifies inspection of the reactor coolant pump (RCP) flywheels in accordance with Regulatory Position C.4.b of Regulatory Guide (RG) 1.14, Revision 1, August 1975. This regulatory position requires: (1) An in-place ultrasonic volumetric examination of the areas of higher stress concentration at the bore and keyway at approximately 3-year intervals and (2) A surface examination of all exposed surfaces and complete ultrasonic volumetric examination at approximately 10-year intervals. The proposed TS change specifies an alternate flywheel inspection once every 10 years which the SER states'to be acceptable relief from the requirements of RG 1.14, Regulatory Position C.4.b. | | The current technical specification specifies inspection of the reactor coolant pump (RCP) flywheels in accordance with Regulatory Position C.4.b of Regulatory Guide (RG) 1.14, Revision 1, August 1975. This regulatory position requires: (1) An in-place ultrasonic volumetric examination of the areas of higher stress concentration at the bore and keyway at approximately 3-year intervals and (2) A surface examination of all exposed surfaces and complete ultrasonic volumetric examination at approximately 10-year intervals. The proposed TS change specifies an alternate flywheel inspection once every 10 years which the SER states'to be acceptable relief from the requirements of RG 1.14, Regulatory Position C.4.b. |
| The next required RCP flywheel inspections are to be performed during the Unit I and Unit 2 | | The next required RCP flywheel inspections are to be performed during the Unit I and Unit 2 |
|
---|
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
_ - - ._ - _ - - _ _ _ - _ _ _ - _ _ - - _ _ - _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ . . _ _ _ _ - _ _ _ _ - _ _ - _ _ .
o ..
J. D.Woodard Southern Nuclear Executive Mce President Operating Company. inc.
40 invemess Center Parkway Post Office Box 1295 Birmingham. Alabama 35201 Tel 205992.5086 SOUTHERNk h COMPANY Energy to Serve YourWorld*
May 8, 1998 LCV-1180 Docket Nos.: 50-424 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington D. C. 20555-0001 Ladies and Gentlemen:
VOGTLE ELECTRIC GENERATING PLANT PROPOSED CHANGE TO TECliNICAL SPECIFICATION 5.5.7 i REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM l
l In accordance with 10 CFR 50.90, Southem Nuclear Operating Company (Southern Nuclear) requests that Appendix A of Facility Operating Licenses NPF-68 and NPF-81 be amended to modify the Vogtle Electric Generating Plant (VEGP) Units I and 2 Technical Specifications (TS).
The purpose of the proposed license amendments is to revise TS 5.5.7, " Reactor Coolant Pump
, Flywheel Inspection Program,"in accordance with the Safety Evaluation Report (SER) recommendations included in a letter dated September 12,1996 from the Nuclear Regulatory Commission (NRC) to Duquesne Light Company - Beaver Valley Power Station, " Acceptance for Referencing of Topical Report WCAP-14535, ' Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination'."
The current technical specification specifies inspection of the reactor coolant pump (RCP) flywheels in accordance with Regulatory Position C.4.b of Regulatory Guide (RG) 1.14, Revision 1, August 1975. This regulatory position requires: (1) An in-place ultrasonic volumetric examination of the areas of higher stress concentration at the bore and keyway at approximately 3-year intervals and (2) A surface examination of all exposed surfaces and complete ultrasonic volumetric examination at approximately 10-year intervals. The proposed TS change specifies an alternate flywheel inspection once every 10 years which the SER states'to be acceptable relief from the requirements of RG 1.14, Regulatory Position C.4.b.
The next required RCP flywheel inspections are to be performed during the Unit I and Unit 2
- refueling outages scheduled for February and September of 1999, respectively. Therefore, Southern Nuclear requests approval of the proposed amendments by September 1,1998.
\\ ,
l
~
9805210015 900508 l PDR ADDCK 05000424 , t\ 0 0\ i P PDR \^ l l
U. S. Nuclear Regulatory Commission Page 2 A description of the proposed technical specification change along with a supporting Safety Evaluation is provided in Enclosure 1. Southem Nuclear has determined that the proposed license amendments do not involve a significant hazards consideration pursuant to 10 CFR 50.92 (see Enclcsure 2). Enclosure 3 provides the revised technical specification pages, and the Environmental Impact Determination is included as Enclosure 4.
In accordance with 10 CFR 50.91(b)(1), a copy of these proposed license amendments is being forwarded to Mr. L. C. Barrett, the designee for the State of Georgia.
Mr. J. D. Woodard states he is executive vice president of Southem Nuclear and is authorized to execute this oath on behalf of Southern Nuclear, and to the best of his knowledge and belief, the facts set forth in this letter and enclosures are true.
Please contact this office if you have any questions.
Sincerely, N
D. oodard Sworn to and subscribed before me this FM dayof //7a4 / ,1998
[
M0A0rn" Notary Public EmmW 3,2m My Commission Expires:
1 Enclosures !
xc: Southern Nuclear Operatina Comnany Mr. J. B. Beasley Mr. M. Sheibani l SNC Document Management 1
i U. S. Nuclear Regulatory Commigii n l Mr. L. A. Reyes, Regional Administrator j l
Mr. D. H. Jaffe, Licensing Project Manager, NRR j Mr. J. Zeiler, Senior Resident inspector, Vogtle i l
State of Geornia I l Mr. L. C. Barrett, Commissioner, Department of Natural Resources l l
J l
1 c____________----------- - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - _ . _ _
j
a ENCLOSUREI VOOTLE ELECTRIC GENERATING PLANT PROPOSED CHANGE TO TECilNICAL SPECIFICATION 5.5.7 REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM DESCRIPTION OF PROPOSED LICENSE AMENDMENT AND SAFETY EVALUATION Description of Proposed Change This license amendment request proposes to revise the Vogtle Electric Generating Plant (VEGP)
Umts I and 2 Technical Specification (TS) 5.5.7, Reactor Coolant Pump Flywheel Inspection ;
Program, to provide an exception to the examination requirements of Regulatory Position C.4.b of '
Regulatory Guide (RG) 1.14, Revision 1, August 1975. The revised TS 5.5.7 would read as follows:
This program shallprovidefor the inspection ofeach reactor coolant pumpfl> wheel at least once every 10 years by conducting either:
- a. An in-place ultrasonic examination over the volumefrom the inner bore oftheflywheel to the circle ofone-halfthe outer radius; or
- b. A surface examination (magneticparticle and'or liquidpenetrant) ofexjx>sedsurfaces of the disassembledfl> wheel.
The provisions ofSR 3.0.2 andSR 3.0.3 are applicable to the Reactor Coolant Pump Flywheel inspection Program.
Safety Evaluation WCAP-14535, " Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination,"
developed by the Westinghouse Owners Group (WOG) presents the basis for relief from the RCP flywhcci inspections required by RG 1.14 Regulatory Position C.4.b. This report was submitted to the NRC for review on January 24,1996 by Duquesne Light Company for application to Beaver Valley Power Station Units I and 2. On September 12,1996, the NRC issued a Safety Evaluation Report (SER) documenting its approval of WCAP-14535. The SER states that the evaluation
- methodology described in WCAP-14535 is appropriate and the criteria are in accordance with the design criteria of RG 1.14. The naal NRC accepted version of WCAP-14535 was issued as revision A which compiles all of the relevant correspondence for this matter.
The SER requires that for those plants who plan to submit a plant-specific application of the topical report, the RCP flywheel material must be confirmed. The material used for all nine RCP motor flywheels at VEGP (including I spare pump motor)is A533 Grade B, Class 1 steel plate.
The proposed resision to TS 5.5.7 is consistent with the inspection program outlined in the SER which the NRC concludes to be acceptable relief from the requirements of RG 1.14, Regulatory Position C.4.b.
ENCLOSURE I (continued)
VOGTLE ELECTRIC GENERATING PLANT PROPOSED CHANGE TO TECHNICAL SPECIFICATION 5.5.7 REACTOR COOLANT PUMP FLYWIIEEL INSPECTION PROGRAM DESCRIPTION OF PROPOSED LICENSE AMENDMENT AND SAFETY EVALUATION As documented in WCAP-14535A, of the 729 examination results reported no indica *. ions which would affect the integrity of the flywheels were found. VEGP has performed 19 RCP flywheel inspections with no indications found.
In addition, the proposed license amendment will reduce personnel radiation exposure and minimize the possibility of damage to the RCP flywheel due to the disassembly and reassembly required to perform the currently required examination.
Summary The basis for the requested license amendments is formed by the technicaljustification presented in WCAP-14535A, VEGP's prior RCP flywheel inspection results, and the goal to minimize ;
personnel radiation exposure to as low as reasonably achievable. Therefore, Southern Nuclear has j determined that the proposed change to TS 5.5.7 for VEGP Units I and 2 does not adversely affect or endanger the health and safety of the general public.
I l
1 El-2 f i
I
f l .
l_
ENCLOSURE 2 l VOGTLE ELECTRIC GENERATING PLANT
[ PROPOSED CHA~NGE TO TECHNICAL SPECIFICATION 5.5.7 REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION l
Description of Proposed Channe This license amendment request proposes to revise the Vogtle Electric Generating Plant (VEGP)
Units 1 and 2 Technical Specification (TS) 5.5.7, Reactor Coolant Pump Flywhcci inspection Program, to provide an exception to the examination requirements of Regulatory Position C.4.b of Regulatory Guide (RG) 1.14, Revision 1, August 1975. The revised TS 5.5.7 would read as follows:
This program shallprovidefor the inspection ofeach reactor coolant pumpflywheel at least once every 10 years by conducting either:
- a. An in-place ultrasonic examination over the volumefrom the inner bore oftheflywheel to the circle ofone-halfthe outer radius; or
- b. A surface examination (magnetic particle and 'or liquidpenetrant) ofexposed surfaces of the disassembledflywheel.
The provisions ofSR 3.0.2 and SR 3.0.3 are apphcable to the Reactor Coolant Pump Rywheel Inspection Program.
Introduction The NRC has provided standards for determining whether a significant hazards consideration exists in 10 CFR 50.92. A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant increase in the probability or consequences of an l accident previously evaluated; or (2) create the possibility of a new or different kind of accident
- from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
Each standard is discussed below for the proposed amendments.
IliK9A 29.i (1) Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated.
The safety function of the RCP flywhcci is to provide suflicient rotational inenia to ensure reactor
- coolant flow through the core during coastdown following a loss of offsite power and subsequent reactor trip. FSAR Chapter 15 analysis for a complete loss of forced reactor coolant flow demonstrates that the reactor trip together with the flow sustained by the inertia of the RCP j impeller will be sufficient to prevent the most limiting fuel assembly from exceeding the DNBR !
limits. l f
_ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ . _ _ . _ _ _ _ _ _ . _ _ _ . _ _ _ _ . _ _ _ _ ._ _ .__ _ _ . _ m
l j
l ENCLOSURE 2 (continued) j VOGTLE ELECTRIC GENERATING PIANT I PROPOSED CHANGE TO TECHNICAL SPECIFICATION 5.5.7 REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM NO SIGNIFICANT HA2,ARDS CONSIDERATION DETERMINATION n.
The maximum mechanical loading on the RCP motor flywheel results from overspeed following a LOCA. The analysis presented in WCAP-14535 A demonstrates that the mised inspection program proposed by this license amendment will ensure the integrity of the RCP flywheels will be maintained.
Based upon the findings of WCAP-14535A, the ability of the RCP flywheel to perform its intended safety function will be unaffected by the license amendment and the FSAR Chapter 15 analysis will remain valid. Therefore, these proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
]
1 (2) Operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed license amendment will not change the physical plant configuration nor the modes of operation of any plant equipment. Based upon the results of WCAP-14535A, no new failure l' mechanism will be inaoduced by the revised RCP flywheel inspection program. Therefore, the proposed amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated.
(3) Operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety.
The operating limits and ftmetional capabilities of the affected systems, structures, and components will be unchanged by the proposed amendment. The results of the RCP flywheel inspections l performed throughout the industry and at VEGP have identified no indications which would affect l its integrity. As presented in WCAP-14535A, detailed stress analysis and risk assessments have been completed with the results indicating that there would be no clumge in the probability of failure for RCP flywheels if all inspections were climinated. Therefore, these changes do not involve a significant reduction in a margin of safety.
Conclusion l Based on the above discussion, it has been determined that the requested technical specification l revision does not involve a significant hazards consideration.
l l E2-2 ;
- _ _ _ . _ - _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _