|
---|
Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17355A3901999-07-27027 July 1999 Application for Amend to License DPR-31,modifying TSs 3.8.1.1,3.4.3 & 3.5.2 to Extend AOT for Inoperable EDG from 72 Hours to 7 Days on one-time Basis ML17355A3021999-04-26026 April 1999 Application for Amends to Licenses DPR-31 & DPR-41,deleting Obsolete Part of License Condition 3.L & Incorporating Administrative Changes to TS Index,Ts 3/4.1.2.5 & TS 3/4.7.6 ML17355A2471999-03-0808 March 1999 Application for Amends to Licenses DPR-31 & DPR-41,deleting Certain Requirements from TS Section 6.0 That Are Adequately Controlled by Existing Regulations Other than 10CFR50.36 & TS ML17355A2391999-02-24024 February 1999 Application for Amends to Licenses DPR-31 & DPR-41,removing Restrictions on Location at Which Temp of UHS May Be Monitored in TS 3/4.7.4 ML17354B1621998-10-27027 October 1998 Application for Amends to Licenses DPR-31 & DPR-41,to Incorporate Specific Staff Qualifications for Multi- Discipline Supervisor Position Into TS ML17354A8321998-03-12012 March 1998 Application for Amends to Licenses DPR-31 & DPR-41,deleting License Conditions 3.I,3.K,3.H & 4 & Incorporating Recent Organization Change in TS 6.5.1.2 & 6.5.3.1.a ML17354A7601998-01-0909 January 1998 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Sections 5.3.1 & 6.9.1.7 to Allow Implementation of Zirlo Fuel Rod Cladding ML17309A9111997-12-29029 December 1997 Application for Amend to License NPF-16,modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values ML17354A6141997-08-27027 August 1997 Application for Amends to Licenses DPR-31 & DPR-41,modifying Turkey Point Units 3 & 4 TS to Allow Use of 12 Hour Shifts for Nominal 40 (36 to 48) Hour Week ML17354A4201997-02-24024 February 1997 Application for Amends to Licenses DPR-31 & DPR-41,modifying Tech Specs 6.9.1.7, COLR & Adding Best Estimate Large Break Loss of Coolant Accident Analysis to COLR ML17354A3721996-12-17017 December 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS to Change SR for TS 4.4.10 Re Reactor Coolant Pump Flywheel Insp ML17354A3501996-11-22022 November 1996 Application for Amends to Licenses DPR-31 & DPR-41, Requesting Rev to Allow Unit 3 Diesel Fuel Oil Storage Tank to Be Drained,Inspected & Cleaned While Maintaining at Least One Unit 3 Diesel Operable ML17354A2851996-10-0303 October 1996 Application for Amend to Licenses DPR-31 & DPR-41 to Modify Plants Units 3 & 4 to Revise TS Allowing Deferral for One Cycle of Reactor Coolant Pump Flywheel Ultrasonic Exams Required by Reg Guide 1.14 ML17353A7971996-07-17017 July 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TSs to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Intervals Determined by performance-based Criteria ML17353A7091996-05-28028 May 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Section 6.0, Administrative Controls, IAW 10CFR50.90 to Address Licensed Qualifications of Operations Manager ML17353A6881996-05-10010 May 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6501996-04-23023 April 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS in Accordance w/Line-Item 7.4 from NRC GL 93-05, Line-Item Tech Specs Improvements to Reduce Surveillance Requirements for Testing During Power Operation. ML17353A6561996-04-19019 April 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6151996-03-21021 March 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS Such That Requirements for Radiological Effluent Controls Relocated to Offsite Dose Calculation Manual or Process Control Program ML17353A6061996-03-20020 March 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.5.1 to Remove SRs & Operability Requirements for ECCS SI Accumulators That Concern Water Level & Pressure Channels from Ts,Per Line-Item 7.4 from GL 93-05 ML17353A5981996-03-0505 March 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Sections 4.4.3.3 & 4.5.2 to Reduce Frequency of Surveillances & Insps in Accordance W/Gl 93-05 Items,6.6 & 7.5 ML17353A5011995-12-18018 December 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising Definition of RTP from 2,200 Mwt to 2,300 Mwt.Proprietary TR WCAP-13719,Rev 2 & Nonproprietary TRs WCAP-13718,Rev 2 & WCAP-14276,Rev 1 Encl.Proprietary TR WCAP-13719 Withheld ML17353A4521995-11-22022 November 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS Index to Delete Bases Re Administrative Controls & Reviews ML17353A4491995-11-22022 November 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying Tech Specs w/Line-Item 10.1 from NRC GL 93-05, Line-Item Tech Specs Improvements to Reduce Surveillance Requirements for Testing During Power Operation, Per GL 94-01 ML17353A3951995-10-0404 October 1995 Application for Amend to License DPR-31 & DPR-41,modifying Plant TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/ Esfas,Tables 4.3-1 & 4.3-2 SR for Rps/Nis/Esfas & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentations ML17353A3811995-09-28028 September 1995 Application for Amends to Licenses DPR-31 & DPR-41, Implementing Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17353A3511995-09-11011 September 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS in Accordance w/Line-Item 10.1 from GL 93-05, Line-Item TS Improvements to Reduce Surveillance Requirements for Testing During Power Operation & Guidance in GL 94-01 ML17353A2811995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Per Selected Line Items from NRC GL 93-05, Line-Item TS Improvements to Reduce SRs for Testing During Power Operation. ML17353A2771995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas Instrumentation,Tables 4.3-1 & 4.3-2 SRs for Rps/Nis/Esfas Instrumentation & Bases 3/4.3.1 & 3/4.3.2 ML17353A2741995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,adding to Approved COLR Analysis Methodology Used for SBLOCA Analysis in Anticipation of Thermal Uprate to 2,300 Mwt for Both Units & Increasing Current Margin to Calculated PCT ML17353A2711995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl,Incorporating Administrative Clarifications & Corrections & Correcting Typos ML17353A2681995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.1.3.1, Movable Control Assemblies - Group Height & 3/4.1.3.2, Position Indication Sys - Operating & Asociated Bases ML17353A2651995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Table 4.3-1 Re Nuclear Instrumentation Sys Adjustments Based on Calorimetric Measurements at Reduced Power Levels ML17352B1821995-05-23023 May 1995 Application for Amends to Licenses DPR-31 & DPR-41.Amends Would Use Changed Setpoint Presentation Format for RPS & ESFAS Instrumentation Setpoints ML17352B0851995-03-30030 March 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS SR 4.8.1.1.2.g.7,allowing Separation of 5-minute hot- Start Test from 24-h EDG Test Run,Deleting Associated Footnote & Adding New TS SR 4.8.1.1.2.g.14 ML17352B0001995-01-17017 January 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 6.9.1.7, COLR, Re Implementation of FPL Nuclear Physics Methodology for Calculations of COLR Parameters.Fpl Topical Rept NF-TR-95-01, Nuclear Physics Methodology... Encl ML17352A8361994-10-20020 October 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3.9.4 & 1.9,allowing Containment Personnel Airlock Doors to Be Opened During Core Operations & Movement of Irradiated Fuel in Containment ML17352A8291994-10-20020 October 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.4.9.1 to Remove Schedule for Withdrawal of Rv Matl Surveillance Specimens,Gl 91-01 ML17352A7221994-07-19019 July 1994 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS 3.1.3.6, Reactivity Control Sys CR Insertion Limits, 3/4.2.2, Heat Flux Hot Channel Factor - Fq(Z) & 6.9.1.7, COLR & Associated Bases,Per GL 88-16.COLRs Encl ML17352A7301994-07-19019 July 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.7.1 & Associated Bases Which Address Max Allowed Reactor Thermal Power Operation W/Inoperable Main Steam Safety Valves ML17352A7271994-07-19019 July 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 4.8.1.1.2e & 4.8.1.1.2f Re EDG Fuel Oil Testing Program ML17352A5451994-04-19019 April 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 4.0.5a, Applicability - Srs, to Reflect Intent of Revised STS (NUREG-1431) for ISI & Testing Programs,In Accordance W/Recommendations in Draft NUREG-1482 ML17352A5421994-04-19019 April 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 4.6.2.1.d, CSS Surveillance Interval for Air or Smoke Flow Test Through CS Header from at Least Once Per 5 Yrs to at Least Once Per 10 Yrs,Per GL 93-05 & NUREG-1366 ML17352A4611994-02-18018 February 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 6.5.2.8, Audits by Deleting Frequencies Performed Under Cognizance of Nuclear Review Board,Per GL 93-07 ML17352A4351993-12-28028 December 1993 Application for Amends to Licenses DPR-31 & DPR-41,proposing Addition of SG Water Level - high-high Protection to TS Tables 3.3-2,3.3-3,4.3-2 & Associated Bases,In Accordance W/ Commitment to GL 89-19 for Resolution of USI A-47 ML17352A2621993-10-0404 October 1993 Application for Amend to Licenses DPR-31 & DPR-41 Revising Surveillance Requirement 4.6.1.2a & Associated Bases to Conform w/NUREG-1431,Standard Ts,Westinghouse Plants,Rev 0 ML17352A2201993-09-0303 September 1993 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS 3/4.7.1.6, Standby FW Sys & Associated Bases to Eliminate Cranking DGs ML17352A2011993-08-17017 August 1993 Application for Amends to Licenses DPR-31 & DPR-41,revising License Conditions 3.G & 3.F Respectively,To Conform to Std Fire Protection License Proposed as Stated in GL 86-10 ML17352A1061993-07-20020 July 1993 Application for Amends to Licenses DPR-31 & DPR-41,revising TS Definitions to Ensure Consistency W/New 10CFR20 Requirements & Changing Radiological Effluent Release Rept Frequency ML17349A8771993-05-21021 May 1993 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS 5.2.2, Design Pressure & Temp & Associated Bases to Correct Ref to Max Containment Design Internal Pressure from 59 Psig to 55 Psig 1999-07-27
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17355A3901999-07-27027 July 1999 Application for Amend to License DPR-31,modifying TSs 3.8.1.1,3.4.3 & 3.5.2 to Extend AOT for Inoperable EDG from 72 Hours to 7 Days on one-time Basis ML17355A3021999-04-26026 April 1999 Application for Amends to Licenses DPR-31 & DPR-41,deleting Obsolete Part of License Condition 3.L & Incorporating Administrative Changes to TS Index,Ts 3/4.1.2.5 & TS 3/4.7.6 ML17355A2471999-03-0808 March 1999 Application for Amends to Licenses DPR-31 & DPR-41,deleting Certain Requirements from TS Section 6.0 That Are Adequately Controlled by Existing Regulations Other than 10CFR50.36 & TS ML17355A2391999-02-24024 February 1999 Application for Amends to Licenses DPR-31 & DPR-41,removing Restrictions on Location at Which Temp of UHS May Be Monitored in TS 3/4.7.4 ML17354B1621998-10-27027 October 1998 Application for Amends to Licenses DPR-31 & DPR-41,to Incorporate Specific Staff Qualifications for Multi- Discipline Supervisor Position Into TS ML17354A8321998-03-12012 March 1998 Application for Amends to Licenses DPR-31 & DPR-41,deleting License Conditions 3.I,3.K,3.H & 4 & Incorporating Recent Organization Change in TS 6.5.1.2 & 6.5.3.1.a ML17354A7601998-01-0909 January 1998 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Sections 5.3.1 & 6.9.1.7 to Allow Implementation of Zirlo Fuel Rod Cladding ML17309A9111997-12-29029 December 1997 Application for Amend to License NPF-16,modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values ML17354A6141997-08-27027 August 1997 Application for Amends to Licenses DPR-31 & DPR-41,modifying Turkey Point Units 3 & 4 TS to Allow Use of 12 Hour Shifts for Nominal 40 (36 to 48) Hour Week ML17354A4201997-02-24024 February 1997 Application for Amends to Licenses DPR-31 & DPR-41,modifying Tech Specs 6.9.1.7, COLR & Adding Best Estimate Large Break Loss of Coolant Accident Analysis to COLR ML17354A3721996-12-17017 December 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS to Change SR for TS 4.4.10 Re Reactor Coolant Pump Flywheel Insp ML17354A3501996-11-22022 November 1996 Application for Amends to Licenses DPR-31 & DPR-41, Requesting Rev to Allow Unit 3 Diesel Fuel Oil Storage Tank to Be Drained,Inspected & Cleaned While Maintaining at Least One Unit 3 Diesel Operable ML17354A2851996-10-0303 October 1996 Application for Amend to Licenses DPR-31 & DPR-41 to Modify Plants Units 3 & 4 to Revise TS Allowing Deferral for One Cycle of Reactor Coolant Pump Flywheel Ultrasonic Exams Required by Reg Guide 1.14 ML17353A7971996-07-17017 July 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TSs to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Intervals Determined by performance-based Criteria ML17353A7091996-05-28028 May 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Section 6.0, Administrative Controls, IAW 10CFR50.90 to Address Licensed Qualifications of Operations Manager ML17353A6881996-05-10010 May 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6501996-04-23023 April 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS in Accordance w/Line-Item 7.4 from NRC GL 93-05, Line-Item Tech Specs Improvements to Reduce Surveillance Requirements for Testing During Power Operation. ML17353A6561996-04-19019 April 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6151996-03-21021 March 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS Such That Requirements for Radiological Effluent Controls Relocated to Offsite Dose Calculation Manual or Process Control Program ML17353A6061996-03-20020 March 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.5.1 to Remove SRs & Operability Requirements for ECCS SI Accumulators That Concern Water Level & Pressure Channels from Ts,Per Line-Item 7.4 from GL 93-05 ML17353A5981996-03-0505 March 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Sections 4.4.3.3 & 4.5.2 to Reduce Frequency of Surveillances & Insps in Accordance W/Gl 93-05 Items,6.6 & 7.5 ML17353A5011995-12-18018 December 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising Definition of RTP from 2,200 Mwt to 2,300 Mwt.Proprietary TR WCAP-13719,Rev 2 & Nonproprietary TRs WCAP-13718,Rev 2 & WCAP-14276,Rev 1 Encl.Proprietary TR WCAP-13719 Withheld ML17353A4521995-11-22022 November 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS Index to Delete Bases Re Administrative Controls & Reviews ML17353A4491995-11-22022 November 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying Tech Specs w/Line-Item 10.1 from NRC GL 93-05, Line-Item Tech Specs Improvements to Reduce Surveillance Requirements for Testing During Power Operation, Per GL 94-01 ML17353A3951995-10-0404 October 1995 Application for Amend to License DPR-31 & DPR-41,modifying Plant TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/ Esfas,Tables 4.3-1 & 4.3-2 SR for Rps/Nis/Esfas & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentations ML17353A3811995-09-28028 September 1995 Application for Amends to Licenses DPR-31 & DPR-41, Implementing Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17353A3511995-09-11011 September 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS in Accordance w/Line-Item 10.1 from GL 93-05, Line-Item TS Improvements to Reduce Surveillance Requirements for Testing During Power Operation & Guidance in GL 94-01 ML17353A2811995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Per Selected Line Items from NRC GL 93-05, Line-Item TS Improvements to Reduce SRs for Testing During Power Operation. ML17353A2771995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas Instrumentation,Tables 4.3-1 & 4.3-2 SRs for Rps/Nis/Esfas Instrumentation & Bases 3/4.3.1 & 3/4.3.2 ML17353A2741995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,adding to Approved COLR Analysis Methodology Used for SBLOCA Analysis in Anticipation of Thermal Uprate to 2,300 Mwt for Both Units & Increasing Current Margin to Calculated PCT ML17353A2711995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl,Incorporating Administrative Clarifications & Corrections & Correcting Typos ML17353A2681995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.1.3.1, Movable Control Assemblies - Group Height & 3/4.1.3.2, Position Indication Sys - Operating & Asociated Bases ML17353A2651995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Table 4.3-1 Re Nuclear Instrumentation Sys Adjustments Based on Calorimetric Measurements at Reduced Power Levels ML17352B1821995-05-23023 May 1995 Application for Amends to Licenses DPR-31 & DPR-41.Amends Would Use Changed Setpoint Presentation Format for RPS & ESFAS Instrumentation Setpoints ML17352B0851995-03-30030 March 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS SR 4.8.1.1.2.g.7,allowing Separation of 5-minute hot- Start Test from 24-h EDG Test Run,Deleting Associated Footnote & Adding New TS SR 4.8.1.1.2.g.14 ML17352B0001995-01-17017 January 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 6.9.1.7, COLR, Re Implementation of FPL Nuclear Physics Methodology for Calculations of COLR Parameters.Fpl Topical Rept NF-TR-95-01, Nuclear Physics Methodology... Encl ML17352A8361994-10-20020 October 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3.9.4 & 1.9,allowing Containment Personnel Airlock Doors to Be Opened During Core Operations & Movement of Irradiated Fuel in Containment ML17352A8291994-10-20020 October 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.4.9.1 to Remove Schedule for Withdrawal of Rv Matl Surveillance Specimens,Gl 91-01 ML17352A7221994-07-19019 July 1994 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS 3.1.3.6, Reactivity Control Sys CR Insertion Limits, 3/4.2.2, Heat Flux Hot Channel Factor - Fq(Z) & 6.9.1.7, COLR & Associated Bases,Per GL 88-16.COLRs Encl ML17352A7301994-07-19019 July 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.7.1 & Associated Bases Which Address Max Allowed Reactor Thermal Power Operation W/Inoperable Main Steam Safety Valves ML17352A7271994-07-19019 July 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 4.8.1.1.2e & 4.8.1.1.2f Re EDG Fuel Oil Testing Program ML17352A5451994-04-19019 April 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 4.0.5a, Applicability - Srs, to Reflect Intent of Revised STS (NUREG-1431) for ISI & Testing Programs,In Accordance W/Recommendations in Draft NUREG-1482 ML17352A5421994-04-19019 April 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 4.6.2.1.d, CSS Surveillance Interval for Air or Smoke Flow Test Through CS Header from at Least Once Per 5 Yrs to at Least Once Per 10 Yrs,Per GL 93-05 & NUREG-1366 ML17352A4611994-02-18018 February 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 6.5.2.8, Audits by Deleting Frequencies Performed Under Cognizance of Nuclear Review Board,Per GL 93-07 ML17352A4351993-12-28028 December 1993 Application for Amends to Licenses DPR-31 & DPR-41,proposing Addition of SG Water Level - high-high Protection to TS Tables 3.3-2,3.3-3,4.3-2 & Associated Bases,In Accordance W/ Commitment to GL 89-19 for Resolution of USI A-47 ML17352A2621993-10-0404 October 1993 Application for Amend to Licenses DPR-31 & DPR-41 Revising Surveillance Requirement 4.6.1.2a & Associated Bases to Conform w/NUREG-1431,Standard Ts,Westinghouse Plants,Rev 0 ML17352A2201993-09-0303 September 1993 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS 3/4.7.1.6, Standby FW Sys & Associated Bases to Eliminate Cranking DGs ML17352A2011993-08-17017 August 1993 Application for Amends to Licenses DPR-31 & DPR-41,revising License Conditions 3.G & 3.F Respectively,To Conform to Std Fire Protection License Proposed as Stated in GL 86-10 ML17352A1061993-07-20020 July 1993 Application for Amends to Licenses DPR-31 & DPR-41,revising TS Definitions to Ensure Consistency W/New 10CFR20 Requirements & Changing Radiological Effluent Release Rept Frequency ML17349A8771993-05-21021 May 1993 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS 5.2.2, Design Pressure & Temp & Associated Bases to Correct Ref to Max Containment Design Internal Pressure from 59 Psig to 55 Psig 1999-07-27
[Table view] |
Text
CATEGORY 1 REGULATC INFORMATION DISTRIBUTION STEM (RIDE)'CCESSION NBR:9703040209 DOC.DATE: 97/02/24 NOTARIZED:
YES DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250.k 50-25l Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH.'NAME AUTHOR AFFILIATION HOVEY,R.J.
Florida Power 6 Light Co.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Application for amends to Licenses DPR-31 a DPR-4l,modifying Tech Specs 6.9.1.7,"COLR"&adding best estimate large break loss of coolant accident analysis to COLR.DISTRIBUTION CODE: AOOZD COPIES RECEIVED:LTR L ENCL 3 SIZE: TITLE:.OR Submittal:
General Distribution NOTES:'ECIPIENT ID CODE/NAME PD2-3 LA CROTEAU,R INTERNA FZI E CENTER 1 NRR/DE EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT EXTERNAL: NOAC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 l 1 RECIPIENT ID CODE/NAME PD2-3 PD NRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3 NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 0 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12
%PL FEB 84 1997 L-97-037 10 CFR$50.36 10 CFR$50.90 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington D.C.20555 Re: Turkey Point Units 3 and 4 Docket Nos.50-250 and 50-251 Proposed License Amendments In accordance with Title 10 Code of Federal Regulations
$50.90 (10 CFR$50.90), Florida Power and Light Company (FPL)requests that Appendix A of Facility Operating Licenses DPR-31 and DPR-41 be amended to modify Turkey Point Units 3 and 4 Technical Specifications 6.9.1.7, Core Operating Limits Report (COLR).This requested change will add Best Estimate Large Break Loss of Coolant Accident Analysis (BELOCA)to the COLR.A description of the amendments request is provided in Attachment 1.FPL has determined the proposed license amendments do not involve a significant hazard pursuant to 10 CFR$50.92.The no significant hazards determination is provided in Attachment 2.The revised Technical Specifications are provided in Attachment 3.In accordance with 10 CFR 550.91 (b)(1), a copy of these proposed license amendments are being forwarded to the State Designee for the State of Florida.The proposed amendments have been reviewed by the Turkey Point Plant Nuclear Safety Committee and the FPL Company Nuclear Review Board.'hould there be any questions on this request, please contact us.Very truly yours,'.J.Hovey Vice President Turkey Point Plant JAH Attachments 04OOOS , g0 cc: L.A.Reyes, Regional Administrator, Region II, USNRC T.P.Johnson, Senior Resident Inspector, USNRC, Turkey Point W.A.Passetti, Florida Department of Health and Rehabilitative Services 9703040209 970224 PDR ADOCK 05000250 p PDR an FPL Group company i)II@161)llllllllltlllllljlllllllll
~~~
8 P p 4 l l h'7 I 97-037 STATE OF FLORIDA))ss.COUNTY OF DADE)RJ~gz~being first duly sworn, deposes and says: That he is the Licensee herein;, of Florida Power and Light Company, That he has executed the foregoing document;that the statements made in this document are true and correct to the best of his knowledge, information and belief, and that he is authorized to execute the document on behalf of said Licensee.R.J.Hove Subscribed and sworn to before me this~/day of FWA~, 1997.Name of Notary Public (Type or Print),~~@"0"~., OLGA HANEK use MY C0MMISSIM6 CC662742 EXPIRES: Jimiti 18, 2000%z;ti~" Boehxl lhu IIahuy Piste Unstsnssttee NOTARY PUBLIC, in and for the County of Dade, State of Florida My Commission expires tu<~<<>>rrrr N.~R.J.Hovey is personally known to me.
k>6 l'h II Attachment 1 Page 1 of 4 I 97-037 Florida Power&Light Company (FPL)proposes to amend the Turkey Point Units 3 and 4 Technical Specifications (TS)Section 6.9.1.7, Core Operating Limits Report (COLR).This requested change will add Best Estimate Large Break Loss of Coolant Accident Analysis (BELOCA)to the list of approved analytical methods used in determining the Heat Flux Hot Channel Factor, F<(Z);Nuclear Enthalpy Rise Hot Channel Factor, Fz><, and the Normalized F<(Z)as a function of core height, K(Z)curve.In 1988, as a result of improved understanding of Loss of Coolant Accident (LOCA)thermal-hydraulic phenomena, the NRC amended the requirements of 10 CFR$50.46 and Appendix K"ECCS Evaluation Models." A realistic evaluation model may be used to analyze the performance of the Emergency Core Cooling System (ECCS)during a hypothetical LOCA.Under the amended rules, best estimate thermal-hydraulic models may be used in place of Appendix K models.The rule change requires an assessment of the uncertainty associated with the best estimate calculations and that this analysis uncertainty be included when comparing the results of the calculations to the prescribed acceptance limits.Guidance for the use of best estimate codes is provided in Regulatory Guide 1.157.A plant specific analysis, WCAP-14159 Revision 0,"Best Estimate Analysis of the Large Break Loss of Coolant Accident for Turkey Point Units 3&4 Nuclear Plant for Power Uprate," dated October 1996, has been performed using the Westinghouse approved methodology.
The approved methodology is documented in the following; (1)WCAP-12945-P,"Westinghouse Code Qualification Document For Best Estimate LOCA Analysis," Volumes I-V, (2)Letter from N.J.Liparulo (E)to R.C.Jones, Jr.(USNRC),"Revisions to Westinghouse Best-Estimate Uncertainty Methodology," NTD-NRC-95-4575, dated October 13, 1995, and (3)USNRC Safety Evaluation Report, Letter from R.C.Jones (USNRC)to N.J.Liparulo QQ,"Acceptance for Referencing of the Topical Report WCAP-12945(P)
'Westinghouse Code Qualification Document for Best Estimate Loss of Coolant Analysis,'
dated June 28, 1996.All plant specific parameters used in the analysis are bounded by the models and correlations contained in the generic methodology.
Therefore, the Turkey Point Units 3 and 4 specific BELOCA analyses conform to 10 CFR 50.46 and meets the intent of Regulatory Guide 1.157.
0; Attachment 1 Page 2 of 4 L-97-037 The conclusions of the analyses demonstrate there is a high level of probability that: 1)The calculated maximum fuel element cladding temperature will not exceed 2200'F.2)The calculated total oxidation of the cladding will nowhere exceed 0.17 times the total cladding thickness before oxidation.
3)The calculated total amount of hydrogen generated from the chemical reaction of the cladding with water or steam will not exceed 0.01 times the hypothetical amount that would be generated if all of the metal in the cladding tubes surrounding the fuel, excluding the cladding surrounding the plenum volume, were to react.4)The calculated changes in core geometry are such that the core remains amenable to cooling.5), After successful initial operation of the ECCS, the calculated core temperature will be maintained at an acceptable low value and decay heat will be removed for the extended period of time required by the long-lived radioactivity remaining in the core.Table 1 summarizes the results of the BELOCA analyses for Turkey Point Units 3&4.Table 2 shows the plant specific operating ranges for the main plant parameters used in the BELOCA analysis for Turkey Point Units 3&4.The range of variation of the operating parameters has been accounted for in the uncertainty evaluation.
'Attachment 1 Page 3 of 4 L-97-037 Table 1 TURKEY POINT UNITS 3&4 BEST ESTIMATE LARGE BREAK LOCA RESULTS Criteria 95th Percentile PCT ('F)*Maximum Cladding Oxidation (%)Maximum Hydrogen Generation
(%)Coolable Geometry 2067<17 Core Remains Coolable s2200 s17 Core Remains Coolable Long Term Cooling Core Remains Cool In Long Term Core Remains Cool In Long Te rill Includes a+27'F PCI'penalty for a potentially lower containment backpressure due to Qow of air and steam out of the containment prior to the closure of the purge isolation valves (2067=2040+27).
Attachment 1 Page 4of 4 Table 2 TURKEY POINT UNITS 3&4 BELOCA ANALYSIS MAJOR PLANT PARAMETER ASSUMPTIONS L-97-037 Fuel T e Parameter Allowable Ran e 15X15 OFA DRFA Steam Generator Tube Plu in Core Power MWt Fg (Z)g20 z 2346 Z 2.50 FiLH z 1.73 Peak Assembl Burnu MWD/MTU MTC Tang (F)Pressurizer Pressure (psia)z 75,000 z0 atHFP 562 7<Ta<g<585 7 2180 Z PRCS Z 2320 Loo Flow(m Accumulator Tem erature'ccumulator Pressure (psia)Accumulator Volume (gallons)>85,000 z 130 590ZP~z715 6007 z V~z 7338 Minimum ECC Boron (m SITem erature'I Delay (seconds)Offsite Power>1950 g 105~23 (with offsite power)g35 withoutoffsite ower ON or OFF
'Attachment 2 Page 1 of 2 L-97-037 The Technical Specification Administrative Controls Section 6.9.1.7, Core Operating Limits Report will be modified to reflect the use of Westinghouse BELOCA methodology for large break LOCA analysis.The following references will be added to Section 6.9.1.7 of Turkey Point Units 3 and 4 Technical Specifications.
WCAP-12945-P,"Westinghouse Code Qualification Document For Best Estimate LOCA Analysis," Volumes I-V.USNRC Safety Evaluation Report, Letter from R.C.Jones (USNRC)to N.J.Liparulo QQ,"Acceptance for Referencing of the Topical Report WCAP-12945(P)
'Westinghouse Code Qualification Document for Best Estimate Loss of Coolant Analysis,'
June 28, 1996.Consistent with the requirements of 10 CFR$50.92, the enclosed application involves no significant hazards as demonstrated by the answers to the following questions.
Qzstiz~Does the proposed license amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
The plant conditions assumed in the analysis are bounded by the design conditions for all equipment in the plant.Therefore, there will be no increase in the probability of a Loss of Coolant Accident (LOCA).The consequences of a LOCA are not being increased.
That is, it is shown that the emergency core cooling system is designed so that its calculated cooling performance conforms to the criteria contained in 10 CFR$50.46 paragraph (b).No other accident is potentially affected by this change.Therefore, neither the probability nor the consequences of an accident previously evaluated is increased due to the proposed change.QzsQg~Does the proposed license amendment create the possibility of a new or different kind of accident from.any accident previously evaluated?
No new modes of plant operation are being introduced.
The parameters assumed in the analysis are within the design limits of existing plant equipment.
All plant systems will perform as designed in response to a potential accident.Therefore, the proposed license amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated.
Attachment 2 Page2of2 L-97-037 Qzgjg~Does the proposed amendment involve a significant reduction in the margin of safety?The analysis in support of the proposed license amendment realistically models the expected response of the Turkey Point Units 3&4 nuclear core during a postulated LOCA.Uncertainties have been accounted for as required by 10 CFR 550.46.A sufficient number of loss of coolant accidents with different break sizes, different break locations and other variations in properties have been calculated to provide assurance that the most severe postulated loss of coolant accidents were analyzed.It has been shown by the analysis that there is a high level of probability the criteria contained in 10 CFR 550.46 paragraph (b)would not be exceeded.Therefore, the proposed amendment does not involve a significant reduction in the margin of safety.Based on the above, it can be concluded that the incorporation of the proposed changes;a)will not involve a significant increase in the probability or consequences of an accident previously evaluated; b)will not create the possibility of a new or different kind of accident from any accident previously'evaluated; and c)will not involve a significant reduction in a margin of safety.