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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20217F3431999-10-15015 October 1999 Application for Amends to Licenses NPF-9,NPF-17,NPF-35 & NPF-52,to Change TS Re Requirements for Insp of RCP flywheels.Marked-up & Reprinted Ts,Encl ML20212E7711999-09-16016 September 1999 Application for Amends to Licenses NPF-35 & NPF-52 to TS Section 3.8.4,modifying Surveillance Requirements 3.8.4.8 Bases & 3.8.4.9 & 3.8.4.8 Bases to Allow Testing of DC Channel Batteries with Units on Line ML20210N3051999-08-0404 August 1999 Application for Amends to Licenses NPF-35 & NPF-52,modifying Ts,Including 3.3.2, ESFAS Instrumentation, 3.3.3, Post Accident Monitoring Instrumentation, 3.4.17, RCS Loops - Test Exceptions & 5.3, Unit Qualifications ML20196H7471999-06-24024 June 1999 Application for Amends to Licenses NPF-9,NPF-17,NPF-35 & NPF-52,revising TS 2.0, Safety Limits, TS 3.3.1, Reactor Trip Sys Instrumentation & TS 3.4.1, RCS Pressure,Temp & Flow Departure from Nucleate Boiling (DNB) Limits ML20206M9251999-05-0606 May 1999 Supplement to LARs & 1022,for Amends to Licenses NPF-9,NPF-17,NPF-52,respectively & NPF-62,revising List of Ref Documents Contained in TS 5.6.5b Re COLR Requirements ML20205C6761999-03-25025 March 1999 Application for Amends to Licenses NPF-35 & NPF-52, Facilitating Treatment of TS 3.3.1, RTS Instrumentation, TS 3.3.2, ESFAS Instrumentation, TS 3.3.5, LOP DG Start Instrumentation, TS 3.4.12, LTOP Sys & TS 3.3.6, Cp.. ML20204E5161999-03-15015 March 1999 Application for Amends to Licenses NPF-35 & NPF-52,deleting TS for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation & Adding Note to TS for Cravs Re Chlorine Protection Function ML20203A3151999-01-28028 January 1999 Application for Amends to Licenses NPF-35 & NPF-52,proposing Amend to Modify Flowrate Specified for SR 3.7.13.4 from Value Representative of One Filter Unit/Fan to Value Representative of Entire Fhves Train ML20197G8901998-12-0707 December 1998 Application for Amends to Licenses NPF-35 & NPF-32,revising ITS 3.8.3 by Modifying Inventory Requirements of DG Lube Oil Sys ML20195D6291998-11-11011 November 1998 Application for Amends to Licenses NPF-35 & NPF-52,modifying Details of SRs 3.6.11.6 & 3.6.11.7 to Be Consistent with Design of Containment Pressure Control Sys ML20237B6161998-08-14014 August 1998 Application for Amends to Licenses NPF-9,NPF-17,NPF-52 & NPF-52,revising TS Related to Ice Condenser Ice Bed ML20237A9321998-08-0606 August 1998 Application for Exigent Amends to Licenses NPF-35 & NPF-52, Deleting SR 4.8.1.1.2i.2 for Pressure Test of DG Fuel Oil Sys ML20248B5601998-05-22022 May 1998 Application for Amends to Licenses NPF-35 & NPF-52,modifying SR 4.4.3.3 for Pressurizer Heaters to Change Existing Requirement to Be Consistent W/Plant Design & W/Ts Requirement as Delineated in Improved TSs ML20217E9441998-04-20020 April 1998 Application for Amends to Licenses NPF-35 & NPF-52,revising Requirements for Automatic Actuation Logic & Actuation Relays Associated W/Cravs Operation Function,Which Is Part of ESFAS ML20216B9501998-04-0808 April 1998 Application for Amends to Licenses NPF-35 & NPF-52,amending TS 3/4.6.5 for Ice Condenser Reduction of Required Ice Weight ML20217Q3661998-03-0303 March 1998 Application for Amends to Licenses NPF-35 & NPF-52,amending TS Requirements Associated W/Composition of Catawba Safety Review Group ML20197G1551997-12-18018 December 1997 Application for Amends to Licenses NPF-35 & NPF-52,deleting Existing License Conditions Which Have Been Fulfilled by Completed Duke Actions,Changing Other Sections Which Have Been Superseded by Current Plant Status ML20197G4261997-12-17017 December 1997 Application for Amends to Licenses NPF-9,NPF-17,NPF-35 & NPF-52,respectively,ref Updated or Recently Approved Methodologies Used to Calculate cycle-specific Limits Contained in COLR ML20203H8961997-12-11011 December 1997 Application for Amends to Licenses NPF-35 & NPF-52,amending Tech Specs Requirements for ESFAS Instrumentation ML20210U6321997-09-15015 September 1997 Application for Amends to Licenses NPF-35 & NPF-52,revising Current Reactor Coolant Sys TSs for Pressure/Temp Limits, Overpressure Protection & Reactor Vessel Matl Surveillance Program ML20140A6511997-05-27027 May 1997 Application for Amends to Licenses NPF-35 & NPF-52,removing Surveillance Requirement 4.7.13.3a.2 Which Specifies 112,320 Gallon Min Volume of Borated Water Be Available to Supply Standby Makeup Pump ML20140A6141997-05-27027 May 1997 Application for Amend to License NPF-52,deleting References to Steam Generator Tube Sleeving & Repair That Will Not Be Used for Westinghouse Model D5 Steam Generators in Use at Catawba Unit 2 ML20148F2501997-05-27027 May 1997 Application for Amends to Licenses NPF-35 & NPF-52,informing of Intent to Convert Catawba CTS to Catawba Improved Ts,Per NUREG-1431 & Guidance of NEI 96-06.Vols 1-18 Encl ML20141C2221997-05-0808 May 1997 Application for Amend to License NPF-52,requesting to Allow Natural Circulation Testing in Mode 3 Following Steam Generator Replacement for Catawba Unit 1 ML20136G2241997-03-0707 March 1997 Application for Amends to Licenses NPF-35 & NPF-52, Requesting Changes to TS 3/4.7.1.6 & UFSAR Section 15.6.3 Re SGTR ML20133E6691997-01-0303 January 1997 Application for Amends to Licenses NPF-35 & NPF-52, Eliminating SI Signal on Low Steam Line Pressure.Unnecessary SI Actuation Causes Unnecessary Challenges to Plan Safety Sys,Thermal Transients & Increases Actuation Cycles ML20113G4321996-09-21021 September 1996 Application for Amends to Licenses NPF-35 & NPF-52,revising Breaker Coordination ML20113C7061996-06-21021 June 1996 Application for Amends to Licenses NPF-9,NPF-17,NPF-35, NPF-52,revising Term Lifting Loads Used in Manipulator Crane TS 3.9.6b.2 to Lifting Force. in Addition Redefining Auxiliary Hoist Min Capacities ML20101M4651996-04-0303 April 1996 Application for Amends to Licenses NPF-35 & NPF-52,changing TS 3/4.6.4.3 & Bases for Hydrogen Mitigation Sys ML20100P0381996-03-0404 March 1996 Application for Amends to Licenses NPF-35 & NPF-52 Re Rev to Implement Revised 10CFR50,App J Which Provided for Reduced Test Frequency for Qualified Containment ML20097C5261996-01-26026 January 1996 Application for Amend to License NPF-35,revising Ts,By Allowing Operation of Containment Purge Ventilation Sys During Modes 3 & 4 During Startup from SG Replacement Outage ML20096E5871996-01-12012 January 1996 Application for Amends to Licenses NPF-35 & NPF-52, Implementing performanced-based Containment Leak Rate Testing Requirement of 10CFR50 App J,Option B ML20096F2441996-01-11011 January 1996 Application for Amends to Licenses NPF-35 & NPF-52,removing Process Penetration M308 & Containment Isolation Valves RN-429A & RN-432B from TS ML20095E9261995-12-14014 December 1995 Application for Amends to Licenses NPF-9,NPF-17,NPF-35 & NPF-52,revising TS for DGs by Incorporating Guidance & Recommendations in NUREG-1366,GL 93-05,GL 94-01 & NUREG-1431 ML20094Q1621995-11-15015 November 1995 Application for Amends to Licenses NPF-35 & NPF-52,modifying TS 3/4.7.1 & Associated Bases to Increase Setpoint Tolerance of MSSV from +1% to +3% to Incorporate Requirement to Reset MSSV Lift Setting to within +1% After Surveillance Testing ML20094Q1781995-11-15015 November 1995 Application for Amends to Licenses NPF-35 & NPF-52,modifying TS LCO 3.7.5 to Raise Minimum Water Level of Standby Nuclear SW Pond from 570 Feet to 571 Feet ML20094Q2801995-11-15015 November 1995 Application for Amends to Licenses NPF-35 & NPF-52,allowing Rc Sys Gross Specific Activity Measurement Method to Be Changed from Current Degassed Method to non-degassed or Pressurized Dilution Method ML20098A4461995-09-18018 September 1995 Supplemental Application for Amend to License NPF-35, Revising Table 2.2-1, Reactor Trip Sys Instrumentation Trip Setpoints ML20092F4291995-09-13013 September 1995 Application for Amends to Licenses NPF-35 & NPF-52,modifying Notation for Overpower Delta Temp Rt Heatup Setpoint Penalty Coefficient as Delineated in Note 3 on Page 2-10 in Order to Make Nomenclature Consistent w/NUREG-0452,Rev 4 ML20092F7741995-09-0505 September 1995 Application for Amends to Licenses NPF-35 & NPF-52, Requesting That NRC Review & Approve Proposed UFSAR Change to Delete Seismic Qualification Requirement from UFSAR Per 10CFR50.90 ML20091L2971995-08-17017 August 1995 Application for Amends to Licenses NPF-35 & NPF-52,modifying TS SR 4.2.5.2 to Delete Requirement to Calibr RCS Flowrate Measurement Instrumentation within 7 Days Prior to Performance of Flow Measurement ML20087E2371995-08-0808 August 1995 Application for Amends to Licenses NPF-35 & NPF-52,proposing Ts,To Allow Reactor Coolant Sys Gross Specific Activity Measurement Method to Be Changed from Current Degassed Method to non-degassed or Pressurized Dilution,Method ML20084C1351995-05-18018 May 1995 Application for Amends to Licenses NPF-35 & NPF-52 Re Change to TS to Defer Next Scheduled Containment ILRT at Plant One Outage from EOC Seven Refueling Outage to EOC Eight ML20087H6231995-04-26026 April 1995 Application for Amends to Licenses NPF-35 & NPF-52, Increasing Allowable Enrichment Limit for Fuel Stored in Spent Fuel Pools ML20082M7921995-04-12012 April 1995 Application for Amends to Licenses NPF-35,NPF-52,NPF-9 & NPF-17,respectively to Relocate Requirements for Turbine Overspeed Protection Instrumentation from TS to Selected Licensee Commitment Manual ML20082L2781995-04-10010 April 1995 Application for Amends to Licenses NPF-35 & NPF-52,allowing Removal of H Ingnites in Incore Instrument Tunnel for Each Train of H Mitigation Sys ML20078E4731995-01-18018 January 1995 Application for Amends to Licenses NPF-9,NPF-17,NPF-35 & NPF-52,respectively.Amends Relocate Requirements for Seismic Instrumentation,Meteorological Instrumentation & loose-part Detection Sys from TS to SLC Manual for Station ML20077C5611994-11-29029 November 1994 Application for Amend to License NPF-35,requesting Permanent Renewal of Voltage Based Steam Generator Tube Interim Plugging Criteria for Unit 1 Cycle 9 ML20076M6881994-11-0202 November 1994 Application for Amends to Licenses NPF-9,NPF-17,NPF-35 & NPF-52,deleting App B,Environ Protection Plan & Modifying Portion of License Condition 2.C.(2) So as to Delete Portion Which Refers to Environ Protection Plan ML20078K0311994-10-31031 October 1994 Application for Amends to Licenses NPF-35 & NPF-52,removing Stroke Times for SG PORVs from TS Tables 3.6-2a & 3.6-2b 1999-09-16
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217F3431999-10-15015 October 1999 Application for Amends to Licenses NPF-9,NPF-17,NPF-35 & NPF-52,to Change TS Re Requirements for Insp of RCP flywheels.Marked-up & Reprinted Ts,Encl ML20212E7711999-09-16016 September 1999 Application for Amends to Licenses NPF-35 & NPF-52 to TS Section 3.8.4,modifying Surveillance Requirements 3.8.4.8 Bases & 3.8.4.9 & 3.8.4.8 Bases to Allow Testing of DC Channel Batteries with Units on Line ML20210N3051999-08-0404 August 1999 Application for Amends to Licenses NPF-35 & NPF-52,modifying Ts,Including 3.3.2, ESFAS Instrumentation, 3.3.3, Post Accident Monitoring Instrumentation, 3.4.17, RCS Loops - Test Exceptions & 5.3, Unit Qualifications ML20196H7471999-06-24024 June 1999 Application for Amends to Licenses NPF-9,NPF-17,NPF-35 & NPF-52,revising TS 2.0, Safety Limits, TS 3.3.1, Reactor Trip Sys Instrumentation & TS 3.4.1, RCS Pressure,Temp & Flow Departure from Nucleate Boiling (DNB) Limits ML20206M9251999-05-0606 May 1999 Supplement to LARs & 1022,for Amends to Licenses NPF-9,NPF-17,NPF-52,respectively & NPF-62,revising List of Ref Documents Contained in TS 5.6.5b Re COLR Requirements ML20205C6761999-03-25025 March 1999 Application for Amends to Licenses NPF-35 & NPF-52, Facilitating Treatment of TS 3.3.1, RTS Instrumentation, TS 3.3.2, ESFAS Instrumentation, TS 3.3.5, LOP DG Start Instrumentation, TS 3.4.12, LTOP Sys & TS 3.3.6, Cp.. ML20204E5161999-03-15015 March 1999 Application for Amends to Licenses NPF-35 & NPF-52,deleting TS for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation & Adding Note to TS for Cravs Re Chlorine Protection Function ML20203A3151999-01-28028 January 1999 Application for Amends to Licenses NPF-35 & NPF-52,proposing Amend to Modify Flowrate Specified for SR 3.7.13.4 from Value Representative of One Filter Unit/Fan to Value Representative of Entire Fhves Train ML20197G8901998-12-0707 December 1998 Application for Amends to Licenses NPF-35 & NPF-32,revising ITS 3.8.3 by Modifying Inventory Requirements of DG Lube Oil Sys ML20196A1981998-11-20020 November 1998 Correction to Amends 173 & 165 to Licenses NPF-35 & NPF-52, Respectively,Revising Numbering ML20195D6291998-11-11011 November 1998 Application for Amends to Licenses NPF-35 & NPF-52,modifying Details of SRs 3.6.11.6 & 3.6.11.7 to Be Consistent with Design of Containment Pressure Control Sys ML20198H9051998-09-30030 September 1998 Errata to Amends 173 & 165 to License NPF-35 & NPF-52.TS Was Inadvertently Omitted & Should Have Been Transferred to New Page 3.3.1-19 ML20237B6161998-08-14014 August 1998 Application for Amends to Licenses NPF-9,NPF-17,NPF-52 & NPF-52,revising TS Related to Ice Condenser Ice Bed ML20237A9321998-08-0606 August 1998 Application for Exigent Amends to Licenses NPF-35 & NPF-52, Deleting SR 4.8.1.1.2i.2 for Pressure Test of DG Fuel Oil Sys ML20248B5601998-05-22022 May 1998 Application for Amends to Licenses NPF-35 & NPF-52,modifying SR 4.4.3.3 for Pressurizer Heaters to Change Existing Requirement to Be Consistent W/Plant Design & W/Ts Requirement as Delineated in Improved TSs ML20217E9441998-04-20020 April 1998 Application for Amends to Licenses NPF-35 & NPF-52,revising Requirements for Automatic Actuation Logic & Actuation Relays Associated W/Cravs Operation Function,Which Is Part of ESFAS ML20216B9501998-04-0808 April 1998 Application for Amends to Licenses NPF-35 & NPF-52,amending TS 3/4.6.5 for Ice Condenser Reduction of Required Ice Weight ML20217Q3661998-03-0303 March 1998 Application for Amends to Licenses NPF-35 & NPF-52,amending TS Requirements Associated W/Composition of Catawba Safety Review Group ML20197G1551997-12-18018 December 1997 Application for Amends to Licenses NPF-35 & NPF-52,deleting Existing License Conditions Which Have Been Fulfilled by Completed Duke Actions,Changing Other Sections Which Have Been Superseded by Current Plant Status ML20197G4261997-12-17017 December 1997 Application for Amends to Licenses NPF-9,NPF-17,NPF-35 & NPF-52,respectively,ref Updated or Recently Approved Methodologies Used to Calculate cycle-specific Limits Contained in COLR ML20203H8961997-12-11011 December 1997 Application for Amends to Licenses NPF-35 & NPF-52,amending Tech Specs Requirements for ESFAS Instrumentation ML20210U6321997-09-15015 September 1997 Application for Amends to Licenses NPF-35 & NPF-52,revising Current Reactor Coolant Sys TSs for Pressure/Temp Limits, Overpressure Protection & Reactor Vessel Matl Surveillance Program ML20148F2501997-05-27027 May 1997 Application for Amends to Licenses NPF-35 & NPF-52,informing of Intent to Convert Catawba CTS to Catawba Improved Ts,Per NUREG-1431 & Guidance of NEI 96-06.Vols 1-18 Encl ML20140A6511997-05-27027 May 1997 Application for Amends to Licenses NPF-35 & NPF-52,removing Surveillance Requirement 4.7.13.3a.2 Which Specifies 112,320 Gallon Min Volume of Borated Water Be Available to Supply Standby Makeup Pump ML20140A6141997-05-27027 May 1997 Application for Amend to License NPF-52,deleting References to Steam Generator Tube Sleeving & Repair That Will Not Be Used for Westinghouse Model D5 Steam Generators in Use at Catawba Unit 2 ML20141C2221997-05-0808 May 1997 Application for Amend to License NPF-52,requesting to Allow Natural Circulation Testing in Mode 3 Following Steam Generator Replacement for Catawba Unit 1 ML20136G2241997-03-0707 March 1997 Application for Amends to Licenses NPF-35 & NPF-52, Requesting Changes to TS 3/4.7.1.6 & UFSAR Section 15.6.3 Re SGTR ML20133E6691997-01-0303 January 1997 Application for Amends to Licenses NPF-35 & NPF-52, Eliminating SI Signal on Low Steam Line Pressure.Unnecessary SI Actuation Causes Unnecessary Challenges to Plan Safety Sys,Thermal Transients & Increases Actuation Cycles ML20113G4321996-09-21021 September 1996 Application for Amends to Licenses NPF-35 & NPF-52,revising Breaker Coordination ML20113C7061996-06-21021 June 1996 Application for Amends to Licenses NPF-9,NPF-17,NPF-35, NPF-52,revising Term Lifting Loads Used in Manipulator Crane TS 3.9.6b.2 to Lifting Force. in Addition Redefining Auxiliary Hoist Min Capacities ML20101M4651996-04-0303 April 1996 Application for Amends to Licenses NPF-35 & NPF-52,changing TS 3/4.6.4.3 & Bases for Hydrogen Mitigation Sys ML20100P0381996-03-0404 March 1996 Application for Amends to Licenses NPF-35 & NPF-52 Re Rev to Implement Revised 10CFR50,App J Which Provided for Reduced Test Frequency for Qualified Containment ML20097C5261996-01-26026 January 1996 Application for Amend to License NPF-35,revising Ts,By Allowing Operation of Containment Purge Ventilation Sys During Modes 3 & 4 During Startup from SG Replacement Outage ML20096E5871996-01-12012 January 1996 Application for Amends to Licenses NPF-35 & NPF-52, Implementing performanced-based Containment Leak Rate Testing Requirement of 10CFR50 App J,Option B ML20096F2441996-01-11011 January 1996 Application for Amends to Licenses NPF-35 & NPF-52,removing Process Penetration M308 & Containment Isolation Valves RN-429A & RN-432B from TS ML20095E9261995-12-14014 December 1995 Application for Amends to Licenses NPF-9,NPF-17,NPF-35 & NPF-52,revising TS for DGs by Incorporating Guidance & Recommendations in NUREG-1366,GL 93-05,GL 94-01 & NUREG-1431 ML20094Q1621995-11-15015 November 1995 Application for Amends to Licenses NPF-35 & NPF-52,modifying TS 3/4.7.1 & Associated Bases to Increase Setpoint Tolerance of MSSV from +1% to +3% to Incorporate Requirement to Reset MSSV Lift Setting to within +1% After Surveillance Testing ML20094Q1781995-11-15015 November 1995 Application for Amends to Licenses NPF-35 & NPF-52,modifying TS LCO 3.7.5 to Raise Minimum Water Level of Standby Nuclear SW Pond from 570 Feet to 571 Feet ML20094Q2801995-11-15015 November 1995 Application for Amends to Licenses NPF-35 & NPF-52,allowing Rc Sys Gross Specific Activity Measurement Method to Be Changed from Current Degassed Method to non-degassed or Pressurized Dilution Method ML20098A4461995-09-18018 September 1995 Supplemental Application for Amend to License NPF-35, Revising Table 2.2-1, Reactor Trip Sys Instrumentation Trip Setpoints ML20092F4291995-09-13013 September 1995 Application for Amends to Licenses NPF-35 & NPF-52,modifying Notation for Overpower Delta Temp Rt Heatup Setpoint Penalty Coefficient as Delineated in Note 3 on Page 2-10 in Order to Make Nomenclature Consistent w/NUREG-0452,Rev 4 ML20092F7741995-09-0505 September 1995 Application for Amends to Licenses NPF-35 & NPF-52, Requesting That NRC Review & Approve Proposed UFSAR Change to Delete Seismic Qualification Requirement from UFSAR Per 10CFR50.90 ML20091L2971995-08-17017 August 1995 Application for Amends to Licenses NPF-35 & NPF-52,modifying TS SR 4.2.5.2 to Delete Requirement to Calibr RCS Flowrate Measurement Instrumentation within 7 Days Prior to Performance of Flow Measurement ML20087E2371995-08-0808 August 1995 Application for Amends to Licenses NPF-35 & NPF-52,proposing Ts,To Allow Reactor Coolant Sys Gross Specific Activity Measurement Method to Be Changed from Current Degassed Method to non-degassed or Pressurized Dilution,Method ML20084C1351995-05-18018 May 1995 Application for Amends to Licenses NPF-35 & NPF-52 Re Change to TS to Defer Next Scheduled Containment ILRT at Plant One Outage from EOC Seven Refueling Outage to EOC Eight ML20087H6231995-04-26026 April 1995 Application for Amends to Licenses NPF-35 & NPF-52, Increasing Allowable Enrichment Limit for Fuel Stored in Spent Fuel Pools ML20082M7921995-04-12012 April 1995 Application for Amends to Licenses NPF-35,NPF-52,NPF-9 & NPF-17,respectively to Relocate Requirements for Turbine Overspeed Protection Instrumentation from TS to Selected Licensee Commitment Manual ML20082L2781995-04-10010 April 1995 Application for Amends to Licenses NPF-35 & NPF-52,allowing Removal of H Ingnites in Incore Instrument Tunnel for Each Train of H Mitigation Sys ML20078E4731995-01-18018 January 1995 Application for Amends to Licenses NPF-9,NPF-17,NPF-35 & NPF-52,respectively.Amends Relocate Requirements for Seismic Instrumentation,Meteorological Instrumentation & loose-part Detection Sys from TS to SLC Manual for Station ML20077C5611994-11-29029 November 1994 Application for Amend to License NPF-35,requesting Permanent Renewal of Voltage Based Steam Generator Tube Interim Plugging Criteria for Unit 1 Cycle 9 1999-09-16
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Due hwerCompany M S ntxuw
' P.O.Bax1006 Senior Vicehesident Oorlone.hC28201-1006 Nuclear Generation (704)38222000flice (704)382-4360 Fax DUKEPOWER ,
May 18,1995 l U. S. Nuclear Regulatory Commission ,
Washington, D. C. 20555 i 1
Attention: Document Control Desk l I
Subject:
Catawba Nuclear Station .
Docket Numbers 50-413 and -414 1 Technical Specification Revision and Exemption to 10 CFR 50 Appendix J Attached is a request for a change to Catawba Nuclear Station's Technical Specifications to defer the next scheduled containment integrated leak rate test (ILRT) at Catawba Unit 2 for one outage, from the end-of-cycle (EOC) 7 refueling outage (scheduled for October,1995) to EOC 8 (scheduled for March, 1997).10 CFR 50, Appendix J, requires that three integrated leak rate tests (ILRTs) be performed at approximately equal intervals during each 10-year service period at a nuclear station. "Approximately equal intervals" is defined in Catawba Nuclear Station's Technical Specifications as 40 10 months. The proposed one-time change would allow Catawba to extend that interval to s 70 months.
Appendix J and Technical Specifications also require that the third ILRT of each 10-year service interval be performed during the 10-year in-service inspection (ISI) outage. While the ISI work has been staggered over several outages, the upcoming outage will occur approximately 10 years after the plant was licensed (February,1986). Therefore, an exemption to this requirement is also requested, as well as the associated Technical 1 Specification change.
it is concluded that the proposed change, a one-time extension of the interval between the second and third ILRTs at Catawba Unit 2, is justified for the following reasons:
9505310435 950518 PDR ADOCK 05000413 P PDR I
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t U. S. Nuclear Regulatory Commission May 18,1995 Page 2 Previous testine history The Catawba Unit 2 test history provides substantial justification for the proposed test interval extension. In each of the 2 previous periodic ILRTs at Catawba Unit 2, the as-found leakage was less than or equal to 48.7% of the allowable leakage, L., thereby demonstrating that Catawba Unit 2 is a low-leakage containment.
Structural Canability of Containment There are no known mechanisms which would adversely affect the structural integrity of the containment, or that would be a factor in extending the test interval by 20 months. However, as a preventative maintenance measure, a containment civil inspection will be performed during EOC-7 to verify that no structural degradation exists.
Risk Assessment Any additional risk created by the longer interval between ILRTs is considered to be negligible, in part because Type B and C testing will continue unchanged, and the probability of gross containment failure is very low.
The NRC's own analysis, published in draft NUREG-1493, concluded that increasing the ILRT interval to once every 20 years would " lead to an imperceptible increase in risk." It follows logically that increasing a test interval from 40 i 10 months to 5 70 months would ,
amount to a fraction of that already " imperceptible" increase in risk. As evidence of this j minimal risk, it is noted that for the 2 previous periodic ILRTs at Catawba Unit 2, the as-found leakage was equal to or less than 48.7% of the allowable leakage, L,.
Approval of this one-time exemption and Technical Specification change is expected to save Duke Power approximately $900,000 in avoided replacement power cost, with additional savings associated with labor and employee exposure. This is consistent with the NRC's '
initiatives to reduce sigificant cost associated with unnecessary regulatory requirements, and reduce exposure.
This proposed change is applicable to Unit 2 of Catawba Nuclear Station only.
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l 1
U. S. Nuclear Regulatory Commission May 18,1995 l Page 3 l l
l The bases for exemption from the requirements of 10 CFR 50 Appendix J, and the justification for Technical Specification change appears in Attachment I, the appropriate marked-up Technical Specification page in Attachment II, and a No Significant Hazards Analysis in Attachment III.
By copy of this letter, the State of South Carolina is being notified of this proposed Technical Specification change.
If any additional information is required, please call Scott Gewehr at (704) 382-7581.
Very truly yours,
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)x M ~ '
M. S. Tuckman t
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U. S. Nuclear Regulatory Commission May 18,1995 Page 4 cc: Mr. R. E. Martin, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 14H25, OWFN Washington, D. C. 20555 Mr. S. D. Ebneter, Regional Administrator U.S. Nuclear Regulatory Commission - Region II 101 Marietta Street, NW - Suite 2900 Atlanta, Georgia 30323 R. J. Freudenberger Senior Resident Inspector Catawba Nuclear Station Max Batavia, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29207 American Nuclear Insurers c/o Dottle Sherman, ANI Library Town Center, Suite 300A 29 South Main Street West Hartford, CT 06107-2445 INPO Records Center 1100 Circle 75 Parkway - Suite 1500 Atlanta, GA 30339 M & M Nuclear Consultants 1166 Avenue of the Americas l New York, NY 10036-2774 i
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M. S. Tuckman, being duly swom, states that he is Senior Vice President of Duke Power Company; that he is authorized on the part of said Company to sign and file with the Nuclear Regulatory Commission this revision to the Facility Operating Licenses NPF-35 and NPF-52 of the :
Catawba Nuclear Station; and that all the statements and matter set forth herein are tme and correct -
to the best of his knowledge, s ..
W ,
t M. S. Tuckman, Senior Vice President Subscribed and sworn to before me this f h dayof k dlf ,1995 v //a a 2 7 h Nota'ry l$blic My Commission Expires:
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i Attachment I Bases for Exemntion From the Reauirements of 10 CFR 50 AnpendhJ alld Justification for Technical Specification Change Drblor Exemption 10 CFR 50.12 states the NRC may grant exemptions to its regulations if: no undue risk to the health and safety of the public is created, and if special circumstances exist.
No Undue Risk to the Public In order to justify the granting of an exemption to the requirements of 10 CFR Part 50, paragraph 50.12(a)(1) requires that the licensee show that the proposed exemption will not pose an undue risk to the public. That this proposed change will not pose an undue risk is demonstrated by the analysis presented in draft NUREG-1493, which concludes that an increase in the test interval to once every 20 years would " lead to an imperceptible increase in risk." The analyses in draft NUREG-1493 are considered to be specifically applicable to Catawba because: 1) the requested exemption would result in a one-time increase in the test interval to about 5 years, not 20; 2) the population density around Catawba is less than that used in the study (329 people per square mile, vs. 340 used in the study); 3) no ILRT at Catawba has failed; 4) the core inventory used in the study was represented by a 3412 Mwt !
PWR. Catawba is a 3411 Mwt PWR, Other factors which lead to the conclusion that the proposed change will not pose an undue risk include the fact that local leak rate testing, which j identifies 97% of leakage in excess of prescribed limits, will remain in place at its current test ;
frequency; the detailed, proceduralized containment civil inspection which is normally performed in conjunction with an ILRT will be performed in place of the scheduled ILRT, to I identify potential structural deteriorations; and the historical leak-tightness of the containment l structure, as evidenced by 2 successive ILRTs in which the as-found leakage did not exceed j l
48.7% of the allowable leakage rate. A table which shows the leak test history of Catawba Unit 2 follows this Attachment.
A comparison was made between the risk analysis presented in draft NUREG-1493 and a l probabilistic risk assessment performed for Catawh Nuclear Station. While the quantitative l results of the NURPG are not directly applicable to plants not used in the study, conclusions similar to those presented in the NUREG can be made concerning Catawba. NUREG-1493 indicates that reactor accident risks are dominated by accident sequences that result in failure or bypass of the containment. This conclusion is also valid for Catawba. Considering only the Catawba accident sequences that do not result in containment failure, containment leakage contributes approximately 0.08 to 0.09 percent to off-site risk (whole-body person-rem,
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thyroid nodules, and latent fatalities). NUREG-1493 indicated that containment leakage contributed from 0.02 to 0.10 percent to latent cancer risk. The comparison between the analysis of NUREG-1493 and the Catawba PRA concludes that increases in containment leakage at Catawba are expected to produce increases in accident risk similar to the results in NUREG-1493.
Special Circumstances Present Special circumstances, as defined in 10 CFR 50.12(a)(2)(ii), are considered to exist if
" application of the regulation ...is not necessary to achieve the underlying purpose of the rule." The purposes of the rule, as stated in Section I of Appendix J, are to ensure that: a) leakage through the primary reactor containment and systems and components penetrating l containment shall not exceed allowable values, and b) periodic surveillance of reactor i containment penetrations and isolation valves is performed so that proper maintenance and repairs are made. One of the significant factors in assuring that the proposed exemption will not pose an undue risk to the public, as noted above, is the local leak rate testing (LLRT) which is performed. That the LLRT program at Catawba provides an effective mechanism for maintaining containment integrity is perbaps best demonstrated by the fact that the most recent l
ILRT at Catawba Unit 2 was performed at the front end of the refueling outage; before any repairs or adjustments were made to valves or penetrations. Nevertheless, the as-found leakage did not exceed 48.7% of the allowable leakage rate. The fact that no leakage paths were identified by an ILRT, and that the ILRT met the acceptance criteria with significant margin con 6rms the results of the Type B and C testing.
The frequency and scope of the Type B and C LLRT program are not being changed by this exemption request. The LLRT program will continue ta effectively detect containment leakage resulting from the degradation of active containment isolation components, as well as containment penetrations. Administrative limits have been established for each Type B or C component at a fraction of the allowable leak rate, such that any leakage detected in excess of the administrative limit will indicate a potential valve or penetration degradation. In instances in which a component's leakage exceeds its administrative limit, proceduralized controls in the test program require that a work order be written to repair the component.
The requirement that tests be performed during the inservice inspection outage is not necessary to achieve that purpose. In fact, the NRC staff recognized long ago that the requirement to perform the ILRT during the ISI outage is of minimal safety significance, and proposed rulemaking (Federal Register, Vol. 51, Page 39538, October 29, 1986) to eliminate the requirement. For the reasons outlined below it may be concluded that decoupling the ILRT from the ISI outage, and deferring the ILRT for one outage, will have no significant effect on achieving the underlying purpose of the rule.
Mhlitional Justification s
e Type B and C leak rate testing programs are used to determine leakage rates through systems and components that penetrate containment. These tests are currently performed at least every 2 years. This frequency will not be affected by this proposed change. Therefore, the major safety benefit achieved by performance of the Type A test is the detection of gross containment failure. This is a very low probability event. Past ILRT history shows that Catawba Unit 2 has easily passed each of its previous ILRTs.
Containment Structural Capability The Containment System consists of a free-standing cylindrical steel shell surrounded by a separate reinforced concrete reactor building. A six foot annular space is provided between the exterior surface of the steel containment vessel and the inner wall of the reactor building. The Annulus Ventilation system maintains this space at a negative pressure relative to the outside atmosphere during accident conditions. Although the Containment System incorporates the Annulus Ventilation, assurance of leak-tightness does not depend on this system at any time.
This leak rate is a property of the containment vessel alone and the effect of the Annulus Ventilation System may be considered a margin of conservatism as the system collects, delays and filters containment air leaking from the containment vessel.
Two mechanisms could adversely affect the passive structural integrity of containment. The first is deterioration of the structure itself, due to pressure, temperature, radiation, chemical, or other such effects. Secondly, modifications can be made to the structure which, if not carefully controlled, could leave the structure with reduced capavility.
Prior to the performance of the Type A test, a general visual inspection of all accessible interior and exterior surfaces of both the steel containment vessel and the reactor building shield wall is conducted. This inspection is performed in accordance with procedure. The purpose of tiie inspection is to de!ect any evidence of structural deterioration which may affect either the containment structural integrity or its leak-tightness. At the same time, the adjoining areas are inspected to ensure that there are no significant interferences with other structures which would restrict the differential movement of the steel vessel The civil inspections conducted in support of each of the two periodic Type A tests have identified no evidence of structural deterioration that would impact structural integrity or leak tightness of containment.
Absent actual accident conditions, structural deterioration is a gradual phenomenon requiring periods of time well in excess of the proposed interval extension. However, as a preventive maintenance measure, the containment civil inspection will be performed in lieu of the scheduled Type A test in October, and again during the end of the following cycle refueling outage (currently scheduled for March,1997) as part of the deferred Type A test.
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. . i Modifications that would alter the passive containment structure are infrequent and would
- receive extensive review to ensure containment capabilities are not diminished. In addition,10 CFR 50, Appendix J, Section IV.A, requires Type A testing to be performed following any major modiGcation to primary containment boundary. This requirement will be maintained.
Risk Assessment Draft NUREG-1493 includes the results of a sensitivity study performed to explore the risk '
impact of several alternate leak rate testing schedules. Alternative 4 from this study examines relaxing the ILRT frequency from 3 tests in 10 years to I test in 10 years. Using best estimat.e data, the draft NUREG concludes that the increase in population exposure risk to those in the vicinity of the five representative plants ranged from .02% to .14%. This very low impact en risk is attributable to: 1) the effectiveness of Type B and C tests in identifying potential leak paths (only about 3% of leakages that exceed current requirements are detectable only by Type A tests, and those few failures were only marginally above prescribed limits), 2) a low likelihood of ILRT-identiGed leakages in excess of 2 times allowable, and 3) the insensitivity of risk to containment leak rate (e.g., no discernable increase in population dose risk with containment leak rates 100 times greater than currently allowed). This led the authors of draft NUREG-1493 to conclude that even increasing the ILRT frequency to once in 20 years would
" lead to an imperceptible increase in risk."
Summary i
Tbt , proposed exemption to the requirements of 10 CFR 50 Appendix J, and the concurrent i
Technical Specification change, are considered to be justified based upon the minimal safety significance.
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