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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
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~CCKX.Km zo DOmMKm DrSr Vnox SvsrKM REGUL RY INFORMATION 'DISTRIBUTI SYSTEM (RIDS)
ACCESSION NBR:9304160066 DOC.DATE: 93/04/13 NOTARIZED: YES DOCKET
,FACIL:50-250 Turkey.,Point .Z3.ant, Unit 3, .Florida Power and Light C 05000250 AUTH. NAME AUTHOR AFFILIATION PLUNKETT,T.F. Florida Power a Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Con'Ero Desk)y R
SUBJECT:
Application for amend to License DPR-31,revising TS re moveable incore detector thimbles .for Cycle 13.Westinghouse nonproprietary a proprietary versions of thimble deletion D evaluation encl. Proprietary version withheld.
DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution J ENCL I SIZE: + I~ +
NOTES:
RECIPIENT COPIES RECIPIENT A
COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 RAGHAVAN,L .2 2 D
INTERNAL: NRR/DE/EELB 1 1 NRR/DORS/OTSB 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SCSB 1 0 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OC/LFHB 1 0 OGC/HDS3 1 0 REC FILE Ol 1 1 EXTERNAL: NRC PDR 1 hf NSIC I Al 5 R
D D
NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 13
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P.O. Box 029100, Miami, FI33102-9100 VR <Sis%
L-93-095 10 CFR 2.790 10 CFR 50.36 10 CFR 50.90 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:
Re: Turkey Point Unit 3 Docket No. 50-250 Proposed License Amendment Unit 3 C cle 13 Moveable Incore Detector Thimbles In accordance with 10 CFR 50.90, Florida Power and Light Company (FPL) requests that Appendix A of Facility Operating Licenses DPR-31 be amended to modify Turkey Point Unit 3 Technical Specification (T.S.)
3.3.3.2, Moveable Incore Detectors; T. S. 3/4.2.2, Heat Flux Hot Channel Factor Fo(Z) and T. S. 3/4.2.3, Nuclear Enthalpy Rise Hot Channel Factor and their associated bases. The proposed amendment is a change for Turkey Point Unit 3 Cycle 13 to reduce from 38 to a minimum of 25 the number of available moveable incoze detector thimbles required foz the Moveable Incore Detection System to be operable. This change would allow continued operation of Unit 3 should the current number of operable detector thimbles decrease.
As discussed with the staff on April 1, 1993, FPL proposes a one-time only change for Turkey Point Unit 3 Cycle 13 to reduce from 38 to a minimum of 25 the required number of available moveable incore detector thimbles. At this time, it is believed that the problem with sticking detector thimbles is caused by debris (i.e., corrosion products) trapped in the incoze detector thimble tubes. In an effort to improve the performance of the Moveable Incore Detector system, FPL has replaced several flux map detectors, the dehumidifier in four of the five flux map drives and restored the nitrogen purge. Efforts are continuing to improve the performance of the moveable incore detector system. FPL is developing plans for extensive cleaning of the detector thimbles during the next scheduled refueling outage (currently scheduled to begin March 20, 1994). During the last several months more thimbles have become inoperable such that currently, fewer number of thimbles required for system operability are available. Failure to maintain the required minimum number of thimbles operable would result in a forced unit shutdown.
Accordingly, this proposed license amendment is being submitted.
Attachment. 1 provides the safety analysis for the amendment request.
Included in Attachment 1 are: (a) figures depicting measured versus predicted peaking factors (Fo and Fn,H) foz Unit 3 Cycle 13, and for (b) a table summarizing the operating conditions and peaking factors the most recent Unit 3 flux maps.
FPL has determined that the proposed license amendment does not, involve a significant hazard pursuant to 10 CFR 50.92. The no significant hazards determination in support of the proposed Technical Specification change is provided in Attachment 2.
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L-93-095 Page 2 provides the proposed revised Technical Specification changes. Note that although the changes apply only to Unit 3 and there aze no changes to the Unit 4 Technical Specifications, the Unit 4 Technical Specifications are administratively affected since they are combined into one specification applying to both Turkey Point Units 3 and 4. contains a proprietary version of the Westinghouse thimble deletion evaluation. Accordingly, FPL requests that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR 2.790 of the Commission's regulations.
In accordance with 10 CFR 50.91 (b)(1), a copy of the proposed license amendment is being forwarded to the State Designee for the State of Florida.
The proposed amendment has been reviewed by the Turkey Point Plant Nuclear Safety Committee and the FPL Company Nuclear Review Board.
FPL requests that review and approval of this proposed amendment be expedited in view of the recent history regarding availability of detector thimbles during Unit 3 Cycle 13 and the need foz the use of the Moveable Incore Detection System for Technical Specification required monitozing/calibration functions in the near future. The inability to use the incore instrumentation system for these functions would result in a forced unit shutdown. The next Technical Specification required use of the system is May 10, 1993.
Should there be any questions on this request, please contact us.
Very truly yours, T. F. Plunkett Vice President Turkey Point Nuclear Plant TFP/RJT/rt Attachments CC: S. D. Ebnetez, Regional Administrator, Region II, USNRC R. C. Butcher, Senior Resident Inspector, USNRC, Turkey Point W. A. Passetti, Florida Department of Health and Rehabilitative Services (w/o Attachment 4)
v STATE OF FLORIDA )
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COUNTY OF DADE )
T. F. Plunkett being first duly sworn, deposes and says:
That he is Vice President Turke Point Nuclear Plant, of Florida Power and Light Company, the Licensee herein; 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.
T. F. Plunkett Subscribed and sworn to before me this
~day oy c 1993 Name of Notary Public (Type or Print)
NOTARY PUBLIC, in and for t Dade, State of Florida GILLNM OALE HERBENlGK ia.: ~i- f hlY CCMMSSOM CC 220543 EXPOKS: aeoot S, >SS6 4p;,i% Soekd The Nohuy Pubic Underv4tsa My Commission expires Commission No.
T. F. Plunkett is personally known to me.
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A endix A Westinghouse Authorization Letter CAW-93-446 Affidavit Proprietary Information Letter Copyright Notice
ATTACHMENT 1 SAFETY ANALYSIS
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I,-93-095 Attachment 1 Page 1 of 5 Safet Anal sis Description of Proposed Change The Turkey Point Units 3 and 4 Movable Incore Detector System (MIDS) contains a total of 50 instrumentation thimbles in the core.
Technical Specification .3.3.3.2 requires that at least 38 detector thimbles be operable with a minimum of two detector thimbles per quadrant when used for monitoring FhH, Fq and Fxy. Due to the increase of incore detector thimble failures at Turkey Point Unit 3, Florida Power and Light Company requests a reduction in the required number of operable detector thimbles for the remainder of Cycle 13.
The proposed change will allow plant operation with the number of operable detector thimbles reduced to a minimum of 50% and will require a minimum of three detector thimbles per quadrant. To compensate for any increased uncertainty as the number of allowable operable detector thimbles is reduced, the measurement uncertainty for FhH and Fq will be increased linearly from 4% and 5% to 6% and 9%, respectively, whenever the number of operable detector thimbles is between 38 and 25. Also, the minimum number of detector-thimbles per quadrant will be increased from two to three whenever the number of operable thimbles is less than 38.
Basis for Proposed Change The main purpose of the incore detector system is to monitor the peaking factors (FhH and Fq) to verify that plant operation remains bounded by the limiting values in the Safety Analyses. Attachment 4 provides analyses of the peaking factor uncertainties with a reduced number of operable detector thimbles. The analyses show that, conservatively, measurement uncertainties on FhH of 5.0% and on Fq of 7.0% are sufficient to ensure that the peaking factors assumed in *the Safety Analyses remain bounded with 50% (25) of
-operable detector thimbles. This is compared to the uncertainties-,
on FbH of 4.0% and on Fq of 5.0% that are used in the current analyses (an increase in uncertainty of 1% and 2% for FhH and Fq, respectively). For additional conservatism, the increase uncertainty compensating factors are doubled yielding a total uncertainty of 6% and 9% for FbH and Fq, respectively, whenever the number of detector thimbles is 25. The uncertainty is linearly reduced as the number of operable detector thimbles increases from 50% (25) to 75% (38) thimbles.
The decrease in the allowable number of operable incore detectors is compensated by an increase in measurement uncertainty. This increase in measurement uncertainty ensures that peaking factor measurements using the incore detector system are consezvatively
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L-93-095 Page 2 of 5 calculated.
During Unit 3 Cycle 13, the measured peaking factors have predicted well with deviations of less than 5% between measured and predicted. Figures 1 and 2 present the measured and -predicted FhH and Fq, respectively. 'able 1 presents a summary of the full power flux maps results for the current cycle. This provides assurance that the core is following the predicted behavior. Furthermore, Cycle 13 was designed with at least 8.0% margin to the Fq and FbH limits. While Fxy is referenced in T.S. 3.3.3.2, Turkey Point Units 3 & 4 Technical Specifications do not required Fxy surveillance and as a result no increase in measurement uncertainty on Fxy is proposed.
The'ncrease in the number of thimbles per quadrant from two to three is to ensure that the deletion patterns are random. If less than three thimbles are left in any quadrant, then thimbles inoperability may not be a random process and the peaking factor uncertainties calculated previously will no longer apply.
Other Considerations Currently, FPL is in the process of developing a Proposed License Amendment (PLA) to change the Axial Flux Difference (AFD) methodology from Constant Axial Offset Control (CAOC) to Relaxed Axial Offset Control (RAOC). In the RAOC PLA, there is some Fq analytical margin that will be used. -FPL has determined that the available margin with the use of RAOC after 6,000 Megawatt-days/Metric Ton Uranium (MWD/MTU) in Unit 3 Cycle 13 is sufficient to accommodate the increase in Fq uncertainty (4%) due to the reduction of detector thimbles. As of March 26) 1993) the Unit 3 Cycle 13 exposure is approximately 3,000 MWD/MTU.
Safety Analysis Review The limiting peaking factors used in the Turkey Point Updated Final Safety Analysis Report, (UFSAR) Chapter 14,have not changed. Thus reanalysis of any of the events specified in the UFSAR is not required. A slight increase in the measurement uncertainty is needed to ensure that the actual peaking factors are conservatively bounded by the "measured" peaking factors.
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L-93-095 Page 3 of 5 TABLE 1 Turkey Point Unit 3 Cycle 13 Flux Map Data
'ap Reactor Cycle Control Maximum Maximum Minimum Minimum Axial Number Power Exposure Rod Position Fq FaH Fq Margin F~H f Of set Margin MWD MTU ste s 99.9 600 223 1.9462 1.5398 5. 37 4.95 4.211 99.9 1326 228 1.9470 1.5643 11.28 3.44 3.394 99.9 2118 228 1.9237 1.5325 17.17 5.40 1.551 99.7 2900 228 1.8491 1.5259 18.92 5.81 0.485 Note: (1) Axial Offset = P P
+ Ps where P~ is the power in the top of the core, and P~ is the power in the bottom of the core.
(2) The Minimum Fq and FaH Margin is defined as the margin to the Technical Specification limit as follows:
(1 Measured Peaking Factor/Peaking Factor Limit)
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L-93-095 Page 4 of 5 FlGURE 2.1 Unit 3 Cycle 13 F-Delta-H (including uncertainty) 1.700 1.650 1.600 1.550 o 1 500 9 1.450 g 1.400 1.350
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~ 'Predicted F-Della-H Measured F-Della-H F-Della-H T. S. Limit 1.300 1.250 1.200 6 8 10 Cycle 13 Exposure (MWD/MTU)
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L-93-095 FlGURE 2.2 Page 5 of 5 Unit 3 Cycle 13 Maximum Fq (including uncertainties) 2.100
~ Predicted Fq Measured Fq 2.000
~ 1.900 PL E
~ 1.800 1.700 1.600 6 - 8 10 12 Cych 13 Exposure (NND/MTU)
ATTACHMENT 2 DETERMZNATZON OF NO SZGNZFZCANT HAZARDS CONSZDERATZON
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L-93-095 Attachment 2
.Page 1 of 3 Determination of No Si nificant Hazards Consideration Description of Proposed License Amendment In Tecgnical Specifications 4.2.2.1 and 4.2.2.5, a change is proposed to increase the measurement uncertainty for Fq when the number of operable-incore detector thimbles are between 75% (38) and 50% (25) of the total number of detectors. The new measurement uncertainty is [5 + 4(3-T/12.5)] where T (the number of operable
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incore detector thimbles), must be greater than or equal to 50%
(25) of the total number of thimbles. This change is only applicable to Turkey Point Unit 3 Cycle 13.
In Technical Specifications 4.2.2.3 and 4.2.2.4, a change is proposed to,increase the measurement, uncertainty for .U>> and U>>
when the .number of..operable .incore detector thimbles is between 75% .
(38) and 50% (25) of the total number of detectors. The new measured uncertainty is [9' 4(3-.T/12.5)]% where T (the number of operable incore detector thimbles), must be greater than or equal to 50% (25) of the total number of thimbles. This change is only applicable to Turkey Point Unit 3 Cycle 13.
In Technical Specification 4.2.3.2, a change is proposed to increase the measurement uncertainty for FhH when the number of operable incore detector thimbles are between 75% (38) and 50% (25) of the total number of detectors. The new measurement uncertainty is [4 + 2(3-T/12.5)]% where T (the number of operable incore detector thimbles), must be greater than or equal to 50% (25) of the. total number of thimbles. This change is only applicable to Turkey Point Unit 3 Cycle 13.
In Technical Specification 3.3.3.2, a change is proposed to allow a decrease in the number of required operable detector thimbles to 50% (25) of the total number of thimbles consistent with an increase in peaking factor uncertainties, and to increase the minimum number of thimbles required per quadrant from two to three.
This change is only applicable to Turkey Point Unit 3 Cycle 13.
Introduction The Nuclear Regulatory Commission has provided standards for determining whether a significant hazards consideration exists (10 CFR 50.92(c)) . A proposed amendment to an operating license for a facility inv'olves no significant hazards considerations, 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
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L-93-095 Attachment 2
'Page 2 of 3 accident previously evaluated; or (3) involve a significant reduction in a margin of safety. Each standard is discussed below for the proposed license amendment.
Discussion Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed amendment allows operation with a fewer number of operable incore detector thimbles then currently permitted by the Technical Specifications. These detectors are used to monitor peaking factors; and the number of operable detectors
- have no-.impact, on the probability or consequences of an accident previously evaluated. An increase in the Fq
,: measurement. uncertainty to accommodate a decrease in the
-number, of operable..detector..thimbles,.reduces the, operational .
margin to the Technical Specification limit of 2.32. The 2.32 Fq limit is not affected by this proposed amendment and the results of the Loss of Coolant Accident (LOCA) analyses for Turkey Point remain valid. The increase in the F~H measurement uncertainty,to accommodate the decrease in operable detector thimbles reduces the operational margin to the Technical Specification limit of 1.62. The 1.62 FaH limit measurement is not affected by this proposed amendment and the results of the non-LOCA (DNBR) analyses remain valid.
An increase in the measured peaking factor uncertainties representing a reduction in the margin to the Technical
-.Specifications limit is applied to ensure that the reduction in the number of operable detector thimbles conservatively calculates the limiting peaking factors in the core, thus ensuring that the monitoring duty of the incore detector system is met. This proposed amendment is only applicable to the current cycle (i.e , Cycle 13) for Turkey Point Unit 3 and
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sufficient margin exists to ensure that the Technical Specifications, are.not;violated.. The.proposed amendment does..-
not involve a significant increase in'the probability of an accident previously evaluated since the proposed amendment does not change the Turkey Point Unit 3 plant design or operation of the facility as previously evaluated by the NRC.
The increase in uncertainties applied to FhH and Fq does not change the limiting peaking factors used in the UFSAR Chapter 14 safety analyses. By maintaining the Technical Specifications limits of 2.32 and 1.62 on Fq and FaH respectively, FPL can assure that the consequences to all LOCA and non-LOCA accident analyses will not change and are bound by the safety analyses for Turkey Point. Therefore, the consequence's .of,.any accident previously evaluated have not
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L-93-095 Attachment 2 Page 3 of 3 changed.
(2) Operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any accident previously evaluated.
The operation of the facility in accordance with the proposed amendment does not create the possibility of a new or different- kind of accident from any accident previously evaluated since the proposed change will not affect plant safety analysis assumptions or the physical design of the facility. No new failure mode is introduced as a result of the reduction in the minimum required number of operable incore detector thimbles.
(3) Operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety.
The operation and physical characteristic of the facility is unchanged by this proposed Technical Specification amendment.
By increasing the measurement uncertainties with increasing number of failed detector thimbles the margin of safety is .not reduced by the reduction in the number of operable detector thimbles. The increased uncertainty factors ensures that the margin of safety assumed in the Technical Specification limits of 2.32 and 1.62 on Fq and F~H is not exceeded.
Summary Based on the above, FPL has determined that the proposed amendment request does not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (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; and therefore, the
-'proposed, amendment does .not involve -a significant hazards consideration as defined in 10 CFR 50.92.