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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
[Table view] |
Text
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'*. - . DukeneerCompany . H'wn!R. McCou.m. Jk Catauha Nudear Generatton Drpartment . 11cehesident ;
- 00CanardRoad (8M)33 NIX $ Offwe Jhrk, SCDNS - (8M)831-35 Fax ,
I DUKEPOWER .
i November 15,'1995 -
U.S. Nuclear Regulatory Commission - v A'ITN: Document Control Desk-Washington, D.C. 20555 : f r
Subject:
Catawba Nuclear Station,'dnits 1 and 2 ' !'
Docket Nos. 50413 and 50-414 Proposed Technical Specifications (TS) Changes (TS 3.7.5)
Gentlemen: 1 Pursuant to 10CFR50.4 and 10CFR50.90, attached am license amendment requests to Appendix A, ,
Technical Specifications, of Facility Operating Licenses NPF-35 and NPF-52 for Catawba Nuclear l Station Units 1 and 2, respectively. j The proposed amendments modify TS Limiting Condition for Operation (LCO) 3.7.5 to raise the ;
minimum water level of the standby nuclear service water pond (SNSWP) from 570 feet to 571 l feet.
Attachment I contains a background and description of the enclosed amendment mquests. i Attachment 2 contains the mquired justification and safety evaluation. Pursuant to 10CFR50.91,
- Attachment 3 provides the analysis performed in accordance with the standards contained in :
10CFR50.92 which concludes that the requested amendments do not involve a significant hazards ,
consideration. Attachment 3 also contains an environmental impact analysis for the aquested l amendments. Attachment 4 contains the marked-up TS amendment pages for Catawba. Duke Power Company is forwarding a copy of this amendment request package to the appropriate South Carolina state official. Duke Power Company is mquesting a thirty-day period following NRC appmval of the proposed amendments to allow for implementation. :
Should there be any questions concermng this amendment request package or should additional ,
' information be mquired,~ please call L.J. Rudy at (803) 831-3084J
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- November 15,1995 t
i Very truly yours, . ;
W.R. McCollum <
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Attachments ;
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November 15,1995 B
xc (with attachments):
' S.D. Ebneter, Regional Administrator ;
Region II -
R.J. Freudenberger, Senior Resident Inspector R.E. Martin, Senior Project Manager .
ONRR ;
Max Batavia, Chief _t
. Bureau of Radiological Health, SC l
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. I Document Contml Desk Page 4 November 15,1995 l i
LW.R. McCollum, being duly swom, states that he is 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 these revisions to the Catawba Nuclear Station License Nos. NPF-35 and NPF-52; and ,
that all statements and matters set forth therein are tme and correct to the best of his knowledge. -
P W.R. McCollum, Vice Pre [
Subscribed and sworn to before me this 15th day of November,1995.
i l
Notary Public /
My commission expires:
Ad SS.2O I i 1
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i '- Document Control Desk
' Page 5 ..
November 15,1995 i
J lixc (with attachments)i A.V. Carr ' t Z.L Taylor 7 i i L.J. Rudy:
S.W. Brown
. D.R. Kulla i
D.W. Bradley -
. M.J. Brady W.E. Green
- M.D. Furtick R.G. Blessing !
- B.G. Addis l- NCMPA NCEMC-PMPA
- . SREC Document Control File CN-801.01 ,
Group File CN-801.01 ;
- ELL-EC050 .
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9 ATTACHMENT 1 BACKGROUND AND DESCRIIrfION OF AMENDMENT REQUESTS
4
[
, r Backstround and Description of Amendment Reauests In mid-1994, the NRC conducted a Service Water System Operational Performance Inspection (SWSOPI) of the Catawba nuclear service water (RN) system. This inspection focused on the mechanical design, operational control, maintenance, and surveillance of the RN system. One of ;
the purposes of the inspection was to verify that the RN system functional design is capable of -
meeting all thermal and hydraulic performance requirements. The results of the NRC SWSOPI are ,
documented in Inspection Report Nos. 50-413,414/94-17, dated September 9,1994.
One of the issues raised as a result of the SWSOPIinvolved available inventory of the SNSWP. In December 1994, Catawba performed a survey of the SNSWP to verify this inventory. This survey indicated that the available SNSWP inventory was less than originally believed. The survey results showed approximately a 6% decrease in inventory from what was documented in the FSAR. It was -
determined that some siltation of the SNSWP had occurred, resulting in a decrease in available inventory. In addition, part of the discrepancy was determined to be due to the fact that the survey results for underwater contours were not completely reproducible due to the field methods used in the earlier surveys and due to the interpolation and judgement that was required when constructing contour lines. It was subsequently determined that in spite of the reduced inventory, the SNSWP remained operable. In a March 27,1995 letter to the NRC, Catawba indicated that a plan was being pursued to resolve all outstanding SNSWP issues. This plan involved raising the minimum surface elevation of the SNSWP.
l Minor Modification CE-5017, completed on June 15,1995, changed the SNSWP outlet works so j that water is retained up to elevation 572 feet 0 inches instead of the previous level of 571 feet 0 ,
inches. This resulted in the minimum pond elevation being changed from 570 feet 0 inches to 571 feet 0 inches. This modification ensures that a sufficient volume of water is available for use of the SNSWP as the ultimate heat sink for postulated accidents under all meteorological conditions. The !
effect of the modification is to also increase the SNSWP surface area available for heat transfer.
This TS change modifies LCO 3.7.5 to raise the SNSWP minimum water level from 570 feet to 571 feet. No modifications to the corresponding TS Bases section are required in conjunction with ,
this change.
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i ATTACIIMENT 2 l
JUSTIFICATION AND SAFETY EVALUATION 1
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h Justification and Safety Evaluation .
This TS change.is conservative in that it will result in the specification of a greater required inventory in the SNSWP. The TS limitations on SNSWP level (the TS temperature limitations for the SNSWP are not being changed) will ensure that sufficient cooling capacity will continue to be available. using the SNSWP as the ultimate heat sink to both provide normal cooldown ,
requirements for Catawba and to mitigate the effects of postulated accident conditions as required.
Catawba has analyzed the operability of the SNSWP using the new minimum level requirement of 571 feet. The operability analysis included the following assumptions: ,
- 1) The analysis utilized a uniform (i.e., no stratification) initial SNSWP temperature of 91.5F (the existing TS limit on SNSWP temperature).
- 2) The analysis took into account the volume that was added to the SNSWP by raising the minimum level from 570 feet to 571 feet (i.e., the overflow weir is now at elevation 572 i feet).
- 3) All SNSWP heat loads, core decay and containment cooldown heat loads rejected by the-i LOCA and shutdown units, and RN inventory losses due to assured makeup to safety
. related systems have been accounted for.
Limiting case meteorological assumptions were utilized. i 4)
Utilizing the above assumptions and initial conditions, the maximum RN intake temperature realized during a simultaneous LOCA/cooldown was less than 97.6F. Equipment cooled by RN is environmentally qualified to a RN temperature of 100F. In addition, the NRC had previously imposed a 2.4F penalty as a result of concerns about the accuracy of the SNSWP model; therefore, even after taking into account the 2.4F penalty, the RN intake temperature remained below the ,
required value of 100F, Also, the analysis confirmed that there was no SNSWP intake temperature greater than 91.5F during the first 12.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of the event. (The longest period to reach peak ;
containment pressure in FSAR accident analyses is 12.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and RN intake temperature must remain below 92F during peak containment pressure transients for all design basis c.ccidents; therefore, this criterion is also satisfied.)
Based on the above technical justification, Duke Power Company concludes that it is acceptable to -
raise the SNSWP minimum required level from 570 feet to 571 feet.
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1 ATTACHMENT 3 l
4 NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AND ENVIRONMENTALIMPACT ANALYSIS a
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No Stanificant Hazards Consideration Determination As required by 10CFR50.91, this analysis is provided concerning whether the requested amendments involve significant hazards considerations, as defined by 10CFR50.92. Standards for determination that an amendment request involves no significant hazards considerations are if operation of the facility in accordance with the requested amendment would not: 1) Involve a significant increase in the probability or consequences of an 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.
Criterion 1 The requested amendments will not involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed amendments will have no impact upon any accident probabilities, since the RN system is not an accident initiating system. It is an accident mitigating system. Accident consequences will not be affected, since the proposed r amendments will require a greater surface area for heat transfer fmm the SNSWP water to the environment. It hu been determined that with the required TS minimum water level of 571 feet and with the required TS temperature limit of 91.5F, the SNSWP will be capable of fulfilling all design basis requirements pertaining to accident mitigation.
Criterion 2 The requested amendments will not create the possibility of a new or different kind of accident from any accident previously evaluated. As stated previously, the RN system is not an accident initiator. No change is being made to the plant which would cause the RN system to become an accident initiator. All relevant procedures will be changed as required, commensurate with the NRC issuance of the requested amendments. No accident causal mechanisms will be affected. The t ffect of the increased SNSWP level on the SNSWP dam was evaluated and found to be negligible.
Criterion 3 The requested amendments will not involve a significant reduction in a margin of safety. As noted above, the SNSWP was evaluated with the new TS level requirement and was determined to be operable and capable of meeting all design basis requirements. No impact on any fission product barriers is created by the proposed changes. The proposed changes will ensure that the RN system remains capable of fulfilling its required accident mitigating functions. SNSWP temperature will continue to be monitored at an elevation of 568 feet, which is considered to be the highest elevation at which the average SNSWP surface temperature is accurately represented and minimally influenced by daily temperature swings due to variations in solar heat input, air temperature, and rainfall temperature.
EnvironmentalImDact Analysis The proposed amendments have been reviewed against the criteria of 10CFR51.22 for environmental considerations. The proposed amendments do not involve a significant hazards consideration, nor increase the types and amounts of effluents that may be released offsite, nor
s increase individual or cumulative occupational radiation exposures. Therefore, the pmposed I amendments meet the criteria given in 10CFR51.22(c)(9) for a categorical exclusion from the requirement for an Environmental Impact Statement.
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ATTACHMENT 4 PROPOSED TECHNICAL SPECIFICATION AMENDMENTS FOR CATAWBA i
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Marked-up TS Pages
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