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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
_. . - _ _ _ - _ _ _ . _ _ - _ _ _
e DUKE POWER GOMI%NY P.O. IM)X W1888 CHAMLOTTE. N.G. 2H242 MALttTUCKEN TRt_Ernove ver e reemasung manean peamervoo=
(704) 373-4&ls May 5, 1986 4
Mr. Harold R. Denton, Director
- Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Coannission Washington, D.C. 20555 ATTENTION: Mr. B.J. Youngblood, Project-Director
- PWR Project Directorate No. 4 Re
- Catawba Nuclear Station, Unit 1
- Docket No. 50-413 Technical Specification Amendment for
- Extension of Surveillance Time Requirements
Dear Mr. Denton:
4' i
j This letter contains proposed amendments to the Technical Specifications for Facility Operating License No. NPF-35 for Catawba Unit 1. The attachment contains the proposed changes and a discussion of the justification and safety analysis. The analysis is included pursuant to 10 CFR 50.91 and it has been concluded that the proposed amendments do not involve significant hazards considerations.
This request involves one amendment request to Catawba's Technical
, Specifications. Accordingly, pursuant to 10 CFR 170.21 a check for $150.00 is enclosed.
Pursuant to 10 CFR 50.91 (b) (1) the appropriate South Carolina State Official is being provided a copy of this amendment request.
Very truly yours, l
g I
Hal B. Tucker 4
RWO/jgm 8605120385 860505 PDR ADOCK 05000413 h
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P Attachment PDR
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, Mr. Harold R. Denton, Director b May 5, 1986 l
Page Two xc: Dr. J. Nelson Grace, Regional Administrator U.S. Nuclear Regulatory Commission - Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. P.H. Skinner NRC Resident Inspector Catawba Nuclear Station Mr. Heyward Shealy, Chief Bureau of Radiological Health S.C. Dept. of Health & Environmental Control 2600 Bull Street Columbia, South Caolina 29201 INPO Records Center Suite 1500 1100 circle 75 Parkway Atlanta, Georgia 30339 American Nuclear Insurers c/o Dottie Sherman, ANI Library The Exchange, Suite 245 270 Farmington Avenue Farmington, CT 06032 M&M Nuclear Consultants 1221 Avenue of the Americas New York, New York 10020 J
Mr. Harold R. Denton, Director May 5. 1986
+
Page Four HAL B. TUCKER, being duly sworn, states that he is Vice President of Duke Power Company; that he is authorized on the part of said Company to sign i and file with the Nuclear Regulatory Commission this revision to the Catawba Nuclear Station Technical Specifications, Appendix A to License No.
NPF-35; and that all statements and matters set forth therein are true and
- correct to the best of his knowledge.
. d !.- %
Hal B. Tucker, Vice President s
i Subscribed and sworn to before me this 5 th day of May,1986.
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DISCUSSION OF AMENDMENT REQUEST It is requested that the time allowed to perform certain 18 month surveillance Raquirements he eurendad to the first refueling cutage for Catawba Unit 1. Unit 1 is currently scheduled to enter the first refueling outage in late August. The surveillances identified below can only be conducted while the unit is shutdown and will all come due before this time. Therefore, an extension for the time to conduct these surveillances is necessary.
Since the unit is not scheduled to be shutdown until late August, it is requested that these surveillance intervals be extended until September 28, 1986, with the exception of the Diesel Generator inspection. Due to the fact that one D/G must be operable in Modes 5 and 6, only one diesel may be taken out of service to perform surveillances. Surveillance 4.8.1.1.2g.1 involves the teardown of the diesel and normally takes up to 30 days to perform. Therefore, in order to be able to do both diesels, this surveillance interval must be extended until prior to entering Mode 4 following the first refueling. With the exception of the D/G surveillance, the most limiting extension would be on the order of 3 months.
SURVEILLANCE DUE DATE
- 1. Table 4.3-7, Items 11 and 12 7/24/86 Channel Calibration
- 2. Table 4.3-7, Item 18 8/25/86 Channel Calibration
- 3. 4.3.3.9c. Loose Part Detection 8/14/86 Channel Calibration
- 4. 4.3.4.2c. Turbine Overspeed Protection 8/19/86 Channel Calibration
- 5. 4.4.6.lb. Leakage Detection 8/9/86
- 6. 4.6.1.2d. 8/19/86 - 8/22/86 Type C Test
- 7. 4.7.13.6 SSF Level Transmitter 7/2/86 Channel Calibration
- 8. 4.8.1.1.2g.1) Diesel Generator (D/G) 7/3/86 (D/G 1A)
Manufacturer's Inspection 8/15/86 (D/G 1B)
- 9. 4.S.4a. Overcurrent Protective Devices 8/2/86 Functional Tests
ANALYSIS OF SIGNIFICANT HAZARDS CONSIDERATION 10 CFR 50.92 (c) states that s proposed amendment... involves no significant hazards considerattons. 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 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."
The change to Technical Specification Table 4.3-7 regarding the Channel Calibration for the PORV Position Indicators and the PORV Block Valve Position Indicators does not involve a significant increase in the probability or consequences of an accident previously evaluated. These indicators are highly reliable and no problems have been experienced with them. Additionally, Surveillances 4.4.4.lb. and 4.4.4.2 ensure continued operability of the associated valves. This change does not create the possibility of a new or different kind of accident from any accident previously evaluated. No design change is involved and the method and manner of plant operation is unchanged. This change does not involve a significant reduction in a margin of safety. The extension to the surveillance interval is small (approximately two months) and other required surveillances ensure that the associated valves will be operable.
The plant design bases, safety limits, limiting safety system settings and limiting conditions for operation remain unchanged.
The change to Technical Specification Table 4.3-7 regarding the Containment Area-High Range Radiation Monitor (EMF-53) Channel Calibration does not involve a significant increase in the probability or consequences of an accident previously evaluated. EMF-53 is a reliable radiation monitor intended to detect high levels of radiation which might be released during an accident. Monthly channel checks as required by the Technical Specifications will continue to be performed to ensure continued operability. This change does not create the possibility of a new or different kind of accident from any accident previously evaluated. No design change is involved and the method and manner of plant operations is unchanged. This change does not involve a significant reduction in a margin of safety. The surveillance interval extension would only be on the order of one month. Also, the plant design basis, safety limits, limiting safety system settings and limiting conditions for operation will remain unchanged.
The change to Technical Specification 4.3.3.9c. - Loose Parts Detection System, does not involve a significant increase in the probability or consequences of an accident previously evaluated. The required daily Channel Check, monthly Analog Channel Operational Test and the capability of overlap testing of the circuits will ensure continued operability of this system. This change does not create the possibility of a new or different kind of accident from any accident previously evaluated. The design and operation of the plant will be unchanged by this surveillance extension. This change does not involve a significant reduction in a margin of safety. The surveillance interval extension would be approximately 1 1/2 months. Also, the plant design basis, safety limits,
ANALYSIS OF SIGNIFICANT HAZARDR CON 9TDFRATION (Con t inued )
approximately 1 1/2 months. Also, the plant design basis, safety limits, limiting safety system setpoints and limiting conditions for operation will remain unchanged.
The change to Technical Specification 4.3.4.2c. - Turbine Overspeed Protection, does not involve a significant increase in the probability or consequences of an accident previously evaluated. Weekly cycling of the high pressure turbine stop valves, low pressure turbine intermediate stop valves and low pressure turbine intercept valves and monthly cycling of the high pressure turbine control valves will ensure continued operation of this system. This change does not create the possibility of a new or different kind of accident from any accident previously evaluated. The design and operation of the plant will be unchanged by this surveillance interval extension. This change does not involve a significant reduction in a margin of safety. The surveillance interval extension would be slightly less than 1 1/2 months. Also, the plant design basis, safety limits, limiting safety system setpoints and limiting conditions for operation will remain unchanged.
The change to Technical Specification 4.4.6.lb. concerning the Channel Calibration of the Containment Floor and Equipment Sump Level and Flow Monitoring Subsystem, does not involve a significant increase in the probability or consequences of an accident previously evaluated. Continued operability of the Containment Atmosphere Gaseous and Particulate Monitoring System and the Containment Ventilation Unit Condensate Drain Tank Level Monitoring Subsystem will assure adequate capability to monitor Reactor Coolant System Leakage. This change does not create the possibility of a new or different kind of accident from any accident previously evaluated. The design and operation of the plant will be unchanged by this surveillance interval extension. This change does not involve a significant reduction in a margin of safety. The surveillance interval extension would be less than 2 months. Also, the plant design basis, safety limits, limiting safety system setpoints and limiting conditions for operation will remain unchanged.
The change to Technical Specification 4.6.1.2d. concerning the Type C leak rate testing of the containment penetrations identified in the attached Table 3.6-la does not involve a significant increase in the probability or consequences of an accident previously evaluated. The penetrations are required to be Type C leak tested every 24 months. The last leak rate tests for these penetrations provided very good results. It is not expected that these penetrations would degrade significantly over the period of time between the first and the second Type C leak test. This change does not create the possibility of a new or dif ferent kind of accident from any accident previously evaluated. Th* design and operation of the plant will be unchanged by this surveillance interval extension.
This change does not involve a significant reduction in a margin of snfety.
The surveillance interval extension will be on the order of 1 1/2 months.
Also, the plant design basis, safety limits, limiting safety system setpoints and limiting conditions for operation will remain unchanged.
This extension request also requires a one-time exemption from the requirements of 10CFR50, Appendix J. This exemption request will be detailed in a subsequent transmittal.
ANALYSIS OF SIGNIFICANT HAZARDS CONSIDERATION (Continued)
The change to Technical Specification 4.7.13.6 would only apply to the Channel Calibration of Steam Generator level transmitter ICFLT5632. This instrument provides indication at the Standby Shutdown Facility of Steam Generator "C" wide range level. This is a non-safety related instrument which provides Control Room indication but has no actuation capability.
There are three other Steam Generator level transmitters (one per Steam Generator) which will be calibrated as required. The continued operability of the other three transmitters along with the required monthly Channel Check of all four instruments will provide adequate assurance that there will be no increase in the probability or consequences of a previously evaluated accident. This change does not create the possibility of a new or different kind of accident from any accident previously evaluated. The design and operation of the plant will be unchanged by this surveillance interval extension. This change does not involve a significant reduction in a margin of safety. The surveillance interval extension will be slightly less than 3 months. Also, the plant design basis, safety limits, limiting safety systems setpoints, and limiting conditions for operation will remain unchanged.
The change to Technical Specification 4.8.1.1.2g.1) concerning subjecting each diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations does not involve a significant increase in the probability or consequences of an accident previously evaluated. Extensive inspections were performed on each diesel prior to Unit 1 Startup (see SSER 4). All other required surveillances will continue to be performed (with the exception of those related to the ESF actuation surveillance interval extension previously granted). The performance of the other required surveillances will provide assurance of continued Diesel Generator operability. This change does not create the possibility of a new or different kind of accident from any accident previously evaluated. The design and operation of the plant will remain unchanged by this surveillance interval extension. This change does not involve a significant reduction in a margin of safety. The surveillance interval extension for the Diesel Generator inspection needs to be allowed to extend until prior to entering HOT SHUTDOWN following the refueling.
This is due to the fact that one diesel is required to be operable in Modes 5 and 6 and therefore, the diesel inspections cannot be conducted concurrently. These inspections will not be completed on both diesels prior to September 28, 1986 and thus, the surveillance interval extension needs to be extended until the unit is ready to enter Mode 4 following the outage. During this time period, one diesel will remain operable and the appropriate surveillances will be conducted to assure its operability.
Therefore, there will be no significant reduction in a margin of safety.
Also, the plant design bases, safety limits, limiting safety system setpoints and limiting conditions for operation will remain unchanged.
The change to Technical Specification 4.8.4a. concerning the functional testing of a 10% sample of the circuit breakers and fuses listed in Table 3.8-1A does not involve a significant increase in the probability or consequences of an accident previously identified. The breakers and fuses have proven to be highly reliable with no failures or actuations recorded to date. This change does not create the possibility of a new or different kind of accident from any accident previously evaluated. The design and operation of the plant will remain unchanged. This change does not involve
ANALYSIS OF SIGNIFICANT HAZARDS CONSIDERATION (Continued) a significant reduction in a margin of safety. The surveillance interval extension for the Containment Penetration Conductor Overcurrent Protective Devices would be somewhat less than 2 months. Also, the plant design basis, safety limits, limiting safety system setpoints and limiting conditions for operation will remain unchanged.
Therefore, it can be concluded that postponement of the indicated surveillances by no more than three months will not result in an unacceptable risk to plant operation or the health and safety of the public. The conduct of the other required surveillances coupled with the short duration of the exemption request plus the demonstrated reliability of the systems and components to function properly ensure that their performance will not degrade.