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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEAR1CAN099904, Application for Amend to License DPR-51,changing TS 4.18.5.a.9 & Associated Bases for One Cycle of Operation Through End of Cycle 16,for Suppl Use of OTSG Repair Roll Technology1999-09-19019 September 1999 Application for Amend to License DPR-51,changing TS 4.18.5.a.9 & Associated Bases for One Cycle of Operation Through End of Cycle 16,for Suppl Use of OTSG Repair Roll Technology 0CAN099903, Application for Amends to Licenses DPR-51 & NPF-6,changing Heavy Load Handling Requirements & Transportation Provisions to Permit Movement of Original & Replacement SGs Through Containment Opening During SG Replacement Outage1999-09-17017 September 1999 Application for Amends to Licenses DPR-51 & NPF-6,changing Heavy Load Handling Requirements & Transportation Provisions to Permit Movement of Original & Replacement SGs Through Containment Opening During SG Replacement Outage 0CAN099901, Application for Amends to Licenses DPR-51 & NF-6,changing TS by Revising Curie Limits for Radioactive Gas Storage Tanks1999-09-17017 September 1999 Application for Amends to Licenses DPR-51 & NF-6,changing TS by Revising Curie Limits for Radioactive Gas Storage Tanks 1CAN089903, Application for Amend to License DPR-51,revising ESAS Low RCS Pressure Setpoint,To Ensure That TS Adequately Bounds Safety Analysis1999-08-18018 August 1999 Application for Amend to License DPR-51,revising ESAS Low RCS Pressure Setpoint,To Ensure That TS Adequately Bounds Safety Analysis 2CAN089905, Application for Amend to License NPF-6,revising TS to Remove Requirements for Tube Repair (Sleeving) & Clarify Requirements for Preservice & ISI of Tubes to Facilitate Replacement of Original SGs1999-08-18018 August 1999 Application for Amend to License NPF-6,revising TS to Remove Requirements for Tube Repair (Sleeving) & Clarify Requirements for Preservice & ISI of Tubes to Facilitate Replacement of Original SGs 2CAN079903, Application for Amend to License NPF-6,revising SRs Pertaining to ISI Requirements for SG Tube Circumferential Cracking at top-of-tubesheet During 2P99 Planned mid-cycle Outage1999-07-29029 July 1999 Application for Amend to License NPF-6,revising SRs Pertaining to ISI Requirements for SG Tube Circumferential Cracking at top-of-tubesheet During 2P99 Planned mid-cycle Outage 1CAN079904, Suppl to Util 990409 Proposed TS Changes to Revise Requirements Associated with Station Batteries & Dc Sources to 125 Volt Dc Switchyard Distribution Sys1999-07-29029 July 1999 Suppl to Util 990409 Proposed TS Changes to Revise Requirements Associated with Station Batteries & Dc Sources to 125 Volt Dc Switchyard Distribution Sys 0CAN079901, Application for Amends to Licenses DPR-51 & NPF-6 to Change TS & Subsequent Relief Request from Post Accident Sampling Requirements of NUREG-0737.TS Administrative Control requirements,NUREG-0737 & RG 1.97,rev 3,affected1999-07-14014 July 1999 Application for Amends to Licenses DPR-51 & NPF-6 to Change TS & Subsequent Relief Request from Post Accident Sampling Requirements of NUREG-0737.TS Administrative Control requirements,NUREG-0737 & RG 1.97,rev 3,affected 1CAN069902, Application for Amend to License DPR-51,revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks1999-06-0101 June 1999 Application for Amend to License DPR-51,revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks 1CAN059901, Application for Amend to License DPR-51,revising TS SRs & Applicable Bases Relevant to ISI Requirements for Portions of once-through SG Tubes Encompassed by Upper Tube Sheet. Proprietary Rept Encl.Rept Withheld,Per 10CFR2.790(b)(4)1999-05-14014 May 1999 Application for Amend to License DPR-51,revising TS SRs & Applicable Bases Relevant to ISI Requirements for Portions of once-through SG Tubes Encompassed by Upper Tube Sheet. Proprietary Rept Encl.Rept Withheld,Per 10CFR2.790(b)(4) 2CAN049902, Application for Amend to License NPF-6,adding TS 3.0.6 & Associated Bases to ANO-2 Ts.Proposed Specification Is Identical to Specification 3.0.5 of NUREG-1432, Improved STS CE Plants, Rev 11999-04-0909 April 1999 Application for Amend to License NPF-6,adding TS 3.0.6 & Associated Bases to ANO-2 Ts.Proposed Specification Is Identical to Specification 3.0.5 of NUREG-1432, Improved STS CE Plants, Rev 1 1CAN049901, Application for Amend to License DPR-51,revising Requirements Associated with ANO 1 Provisions for RB Testing & Insp1999-04-0909 April 1999 Application for Amend to License DPR-51,revising Requirements Associated with ANO 1 Provisions for RB Testing & Insp 1CAN049902, Application for Amend to License DPR-51,revising Requirements Associated with ANO-1 Station Batteries & DC Sources to 125 Vdc Switchyard Distribution Sys1999-04-0909 April 1999 Application for Amend to License DPR-51,revising Requirements Associated with ANO-1 Station Batteries & DC Sources to 125 Vdc Switchyard Distribution Sys 2CAN029913, Application for Amend to License NPF-6,adding Footnote to Action 2 Allowing Startup with Functional Units Associated with Channel D Excore Inoperable.Action 2 Is Associated with TS Table 3.3-1, Reactor Protective Instrumentation1999-02-25025 February 1999 Application for Amend to License NPF-6,adding Footnote to Action 2 Allowing Startup with Functional Units Associated with Channel D Excore Inoperable.Action 2 Is Associated with TS Table 3.3-1, Reactor Protective Instrumentation 0CAN119801, Application for Amends to Licenses DPR-51 & NPF-6, Implementing Consolidated EOI QA Plan Manual Submitted on 980430 & Approved by NRC in 981106 Se.Changes Also Clarify Responsibilities on STA Position on Shift1998-11-24024 November 1998 Application for Amends to Licenses DPR-51 & NPF-6, Implementing Consolidated EOI QA Plan Manual Submitted on 980430 & Approved by NRC in 981106 Se.Changes Also Clarify Responsibilities on STA Position on Shift 2CAN099805, Application for Amend to License NPF-6,modifying Notes in Table Associated with Tech Specs 2.2.1,3.3.1.1 & 3.3.2.1 Re Operating Bypass Setpoint1998-09-17017 September 1998 Application for Amend to License NPF-6,modifying Notes in Table Associated with Tech Specs 2.2.1,3.3.1.1 & 3.3.2.1 Re Operating Bypass Setpoint 1CAN089801, Application for Amend to License DPR-51,revising TS 3.3.4.B Requirements for Sodium Hydroxide Tank Concentration1998-08-0606 August 1998 Application for Amend to License DPR-51,revising TS 3.3.4.B Requirements for Sodium Hydroxide Tank Concentration 2CAN089802, Application for Amend to License NPF-6,revising TS 3.1.3.2 Action Requirements for CEA Position Indicator Channels1998-08-0606 August 1998 Application for Amend to License NPF-6,revising TS 3.1.3.2 Action Requirements for CEA Position Indicator Channels 2CAN069801, Application for Amend to License NPF-6,revising Portion of Plant Protection Sys Design to Ensure That ESFAS Meets Its Applicable Design Requirements.Rev 1 to Engineering Rept 97-R-2015-01 Encl1998-06-30030 June 1998 Application for Amend to License NPF-6,revising Portion of Plant Protection Sys Design to Ensure That ESFAS Meets Its Applicable Design Requirements.Rev 1 to Engineering Rept 97-R-2015-01 Encl 2CAN069805, Application for Amend to License NPF-6,providing Range of Acceptable Values for 4160 Volt Bus Loss of Voltage Values, to Be Consistent W/Requirements Set Forth in NUREG-1432,rev 11998-06-29029 June 1998 Application for Amend to License NPF-6,providing Range of Acceptable Values for 4160 Volt Bus Loss of Voltage Values, to Be Consistent W/Requirements Set Forth in NUREG-1432,rev 1 2CAN069807, Application for Amend to License NPF-6,revising Surveillance Testing Requirements for Unit 2 Direct Current Electrical Distribution Sys & to Reflect Installation of New Inverters During Next Scheduled Refueling Outage1998-06-29029 June 1998 Application for Amend to License NPF-6,revising Surveillance Testing Requirements for Unit 2 Direct Current Electrical Distribution Sys & to Reflect Installation of New Inverters During Next Scheduled Refueling Outage 2CAN069806, Application for Amend to License NPF-6,modifying Requirements for Pressurizer Code Safety Valve Requirements Specified by TS 3.4.2 & Safety Tank Isolation Requirements Specified in TS 3.4.121998-06-29029 June 1998 Application for Amend to License NPF-6,modifying Requirements for Pressurizer Code Safety Valve Requirements Specified by TS 3.4.2 & Safety Tank Isolation Requirements Specified in TS 3.4.12 2CAN069804, Application for Amend to License NPF-6,increasing Allowable as-found Lift Setting Tolerances on MSSVs & Pressurizer Safety Valves1998-06-29029 June 1998 Application for Amend to License NPF-6,increasing Allowable as-found Lift Setting Tolerances on MSSVs & Pressurizer Safety Valves 2CAN049802, Application for Amend to License NPF-6,revising Value of Single Largest post-accident Load Capable of Being Supplied by DGs & Relocates Value to Associated Bases1998-04-30030 April 1998 Application for Amend to License NPF-6,revising Value of Single Largest post-accident Load Capable of Being Supplied by DGs & Relocates Value to Associated Bases 1CAN049802, Application for Amend to License DPR-51,revising TS 1.6.1 Re Qpt Definition.Amend Allows Use of Either Incore Detectors or Excore Detectors for Determining Qpt1998-04-30030 April 1998 Application for Amend to License DPR-51,revising TS 1.6.1 Re Qpt Definition.Amend Allows Use of Either Incore Detectors or Excore Detectors for Determining Qpt 1CAN049806, Application for Amend to License DPR-51,changing Order of Channel Rotation During Outage for Scheduling Flexibility, While Still Requiring Rotation Schedule to Be Established for Operating Cycle1998-04-28028 April 1998 Application for Amend to License DPR-51,changing Order of Channel Rotation During Outage for Scheduling Flexibility, While Still Requiring Rotation Schedule to Be Established for Operating Cycle 1CAN049803, Application for Amend to License DPR-51,allowing Upper Tubesheet Volumetric Indications to Remain in Svc for Cycle 15,as Discussed W/Nrc on 980318 & 261998-04-0101 April 1998 Application for Amend to License DPR-51,allowing Upper Tubesheet Volumetric Indications to Remain in Svc for Cycle 15,as Discussed W/Nrc on 980318 & 26 1CAN029803, Application for Amend to License DPR-51,revising TS to Allow Use of Repair Roll Technology (Reroll) for Upper Tubesheet of Sgs.Revised TS Pages,Proprietary Rev 0 to Topical Rept BAW-10232P Included.Proprietary Encl Withheld1998-02-0909 February 1998 Application for Amend to License DPR-51,revising TS to Allow Use of Repair Roll Technology (Reroll) for Upper Tubesheet of Sgs.Revised TS Pages,Proprietary Rev 0 to Topical Rept BAW-10232P Included.Proprietary Encl Withheld 1CAN129702, Application for Amend to License DPR-51,establishing Alternate Repair Criteria for Upper Tubesheet Region of ANO-1 Sgs.Proprietary Topical Rept BAW-10226P Encl.Rept Withheld (Ref 10CFR2.790(b)(4))1997-12-12012 December 1997 Application for Amend to License DPR-51,establishing Alternate Repair Criteria for Upper Tubesheet Region of ANO-1 Sgs.Proprietary Topical Rept BAW-10226P Encl.Rept Withheld (Ref 10CFR2.790(b)(4)) 2CAN099701, Application for Amend to License NPF-6,reducing Min Required Reactor Coolant Sys Flow Rate Requirements Listed in 3.2.5 Until ANO-2 SGs Are Replaced1997-09-23023 September 1997 Application for Amend to License NPF-6,reducing Min Required Reactor Coolant Sys Flow Rate Requirements Listed in 3.2.5 Until ANO-2 SGs Are Replaced 2CAN099703, Application for Amend to License NPF-6,modifying RPS & ESFAS Trip Setpoint & Allowable Values for SG Low Pressure1997-09-23023 September 1997 Application for Amend to License NPF-6,modifying RPS & ESFAS Trip Setpoint & Allowable Values for SG Low Pressure 2CAN079702, Application for Amend to License NPF-6,modifying Actions Associated W/Ts Table 3.3-1 for Reactor Protective Instrumentation & Table 3.3-3 for Esfa Sys Instrumentation1997-07-28028 July 1997 Application for Amend to License NPF-6,modifying Actions Associated W/Ts Table 3.3-1 for Reactor Protective Instrumentation & Table 3.3-3 for Esfa Sys Instrumentation 2CAN079703, Application for Amend to License NPF-6,revising Surveillance Testing Requirements for Facility EFW Sys as Specified in TS 4.7.1.2.Requests That Effective Date for Change Be within 30 Days of Issuance1997-07-21021 July 1997 Application for Amend to License NPF-6,revising Surveillance Testing Requirements for Facility EFW Sys as Specified in TS 4.7.1.2.Requests That Effective Date for Change Be within 30 Days of Issuance 1CAN059702, Application for Amend to License DPR-51,allowing Sufficient Time for Submittal & NRC Review & Approval of Exigent TS Change Request for one-time Exception to Requirements of Section 4.18.5.b Re SG Tube Insp Surveillance Requirements1997-05-0202 May 1997 Application for Amend to License DPR-51,allowing Sufficient Time for Submittal & NRC Review & Approval of Exigent TS Change Request for one-time Exception to Requirements of Section 4.18.5.b Re SG Tube Insp Surveillance Requirements 2CAN049703, Application for Amend to License NPF-6,revising Requirements for Sample Scope Initial Size & Expansion for Inservice Insp Steam Generator Tube Sleeves1997-04-24024 April 1997 Application for Amend to License NPF-6,revising Requirements for Sample Scope Initial Size & Expansion for Inservice Insp Steam Generator Tube Sleeves 2CAN049702, Application for Amend to License NPF-6,permitting Delay of Scheduled three-yr Inspections of Flywheels on All Four RCPs Until Completion of 2R13 Refueling Outage,Scheduled for Winter of 1998-991997-04-18018 April 1997 Application for Amend to License NPF-6,permitting Delay of Scheduled three-yr Inspections of Flywheels on All Four RCPs Until Completion of 2R13 Refueling Outage,Scheduled for Winter of 1998-99 1CAN049703, Application for Amend to License DPR-51,requesting Exigent TS Change Re Steam Generator Tube Insp Surveillance Requirements1997-04-11011 April 1997 Application for Amend to License DPR-51,requesting Exigent TS Change Re Steam Generator Tube Insp Surveillance Requirements ML20133A6801996-12-23023 December 1996 Application for Amend to License NPF-6,revising TS 3/4.7.8 Which Will Enable on-line Testing of Selected Snubbers by Clarifying Intent of TS 2CAN129603, Application for Amend to License NPF-6,requesting Change to Power Calibr Requirements1996-12-19019 December 1996 Application for Amend to License NPF-6,requesting Change to Power Calibr Requirements 2CAN129604, Application for Amend to License NPF-6,requesting Deletion of Specific Value for Total Reactor Coolant Sys Volume in TS 5.4.21996-12-19019 December 1996 Application for Amend to License NPF-6,requesting Deletion of Specific Value for Total Reactor Coolant Sys Volume in TS 5.4.2 2CAN129611, Application for Amend to License NPF-6,requesting to Provide Addl NRC-approved Methodology in List of References in TS 6.9.51996-12-19019 December 1996 Application for Amend to License NPF-6,requesting to Provide Addl NRC-approved Methodology in List of References in TS 6.9.5 2CAN119609, Application for Amend to License NPF-6,revising Surveillance Requirements for Unit 2 Re SG Tubing,Ts 4.4.5.CEN-630-NP & CEN-630-P Repts encl.CEN-630-P Rept Withheld,Per 10CFR2.790(b)(4)1996-11-26026 November 1996 Application for Amend to License NPF-6,revising Surveillance Requirements for Unit 2 Re SG Tubing,Ts 4.4.5.CEN-630-NP & CEN-630-P Repts encl.CEN-630-P Rept Withheld,Per 10CFR2.790(b)(4) 2CAN119610, Application for Amend to License NPF-6,adding Suppl 1-P & Approval Ltr to Section 6.9.5.1 in Support of Increased SG Tube Plugging Limit Beyond 10% Ref to Small Break LOCA Methodology CENPD-1371996-11-24024 November 1996 Application for Amend to License NPF-6,adding Suppl 1-P & Approval Ltr to Section 6.9.5.1 in Support of Increased SG Tube Plugging Limit Beyond 10% Ref to Small Break LOCA Methodology CENPD-137 2CAN109603, Application for Amend to License NPF-6,changing Channel Functional Testing Frequency for Most of Reactor Protection Sys (RPS) & ESFAS Instrumentation from Monthly to Every Four Months1996-10-0707 October 1996 Application for Amend to License NPF-6,changing Channel Functional Testing Frequency for Most of Reactor Protection Sys (RPS) & ESFAS Instrumentation from Monthly to Every Four Months 0CAN109603, Application for Amend to Licenses DPR-51 & NPF-6 Re Relocation of RETS Per GL 89-011996-10-0202 October 1996 Application for Amend to Licenses DPR-51 & NPF-6 Re Relocation of RETS Per GL 89-01 0CAN109602, Application for Amends to Licenses DPR-51 & NPF-6,reducing Costs for Licensees by Allowing Change to Requirements W/O Necessarily Requiring License Amend,Per GL 95-101996-10-0202 October 1996 Application for Amends to Licenses DPR-51 & NPF-6,reducing Costs for Licensees by Allowing Change to Requirements W/O Necessarily Requiring License Amend,Per GL 95-10 2CAN089601, Application for Amend to License NPF-6,relocating RCS Flow Rate Limit from TS & to Colr,Iaw/Gl 88-16, Removal of Cycle-Specific Parameter Limits from Ts1996-08-23023 August 1996 Application for Amend to License NPF-6,relocating RCS Flow Rate Limit from TS & to Colr,Iaw/Gl 88-16, Removal of Cycle-Specific Parameter Limits from Ts 0CAN089606, Application for Amends to Licenses DPR-51 & NPF-6,allowing Implementation of Approved Option B to 10CFR50,App J1996-08-23023 August 1996 Application for Amends to Licenses DPR-51 & NPF-6,allowing Implementation of Approved Option B to 10CFR50,App J 2CAN089609, Application for Amend to License NPF-6,revising Section 5.0, Design Features & Would for Most Part,Adopt NUREG-1432 Rev 1,improved, Std Tech Specs for C-E Plants, for Section of TS1996-08-23023 August 1996 Application for Amend to License NPF-6,revising Section 5.0, Design Features & Would for Most Part,Adopt NUREG-1432 Rev 1,improved, Std Tech Specs for C-E Plants, for Section of TS 0CAN069601, Application for Amends to Licenses DPR-51 & NPF-6,allowing Reactor Containment Bldg Equipment Hatch Doors to Remain Open During Fuel Handling & Core Alterations1996-06-28028 June 1996 Application for Amends to Licenses DPR-51 & NPF-6,allowing Reactor Containment Bldg Equipment Hatch Doors to Remain Open During Fuel Handling & Core Alterations 1999-09-19
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEAR1CAN099904, Application for Amend to License DPR-51,changing TS 4.18.5.a.9 & Associated Bases for One Cycle of Operation Through End of Cycle 16,for Suppl Use of OTSG Repair Roll Technology1999-09-19019 September 1999 Application for Amend to License DPR-51,changing TS 4.18.5.a.9 & Associated Bases for One Cycle of Operation Through End of Cycle 16,for Suppl Use of OTSG Repair Roll Technology 0CAN099901, Application for Amends to Licenses DPR-51 & NF-6,changing TS by Revising Curie Limits for Radioactive Gas Storage Tanks1999-09-17017 September 1999 Application for Amends to Licenses DPR-51 & NF-6,changing TS by Revising Curie Limits for Radioactive Gas Storage Tanks 0CAN099903, Application for Amends to Licenses DPR-51 & NPF-6,changing Heavy Load Handling Requirements & Transportation Provisions to Permit Movement of Original & Replacement SGs Through Containment Opening During SG Replacement Outage1999-09-17017 September 1999 Application for Amends to Licenses DPR-51 & NPF-6,changing Heavy Load Handling Requirements & Transportation Provisions to Permit Movement of Original & Replacement SGs Through Containment Opening During SG Replacement Outage 2CAN089905, Application for Amend to License NPF-6,revising TS to Remove Requirements for Tube Repair (Sleeving) & Clarify Requirements for Preservice & ISI of Tubes to Facilitate Replacement of Original SGs1999-08-18018 August 1999 Application for Amend to License NPF-6,revising TS to Remove Requirements for Tube Repair (Sleeving) & Clarify Requirements for Preservice & ISI of Tubes to Facilitate Replacement of Original SGs 1CAN089903, Application for Amend to License DPR-51,revising ESAS Low RCS Pressure Setpoint,To Ensure That TS Adequately Bounds Safety Analysis1999-08-18018 August 1999 Application for Amend to License DPR-51,revising ESAS Low RCS Pressure Setpoint,To Ensure That TS Adequately Bounds Safety Analysis 1CAN079904, Suppl to Util 990409 Proposed TS Changes to Revise Requirements Associated with Station Batteries & Dc Sources to 125 Volt Dc Switchyard Distribution Sys1999-07-29029 July 1999 Suppl to Util 990409 Proposed TS Changes to Revise Requirements Associated with Station Batteries & Dc Sources to 125 Volt Dc Switchyard Distribution Sys 2CAN079903, Application for Amend to License NPF-6,revising SRs Pertaining to ISI Requirements for SG Tube Circumferential Cracking at top-of-tubesheet During 2P99 Planned mid-cycle Outage1999-07-29029 July 1999 Application for Amend to License NPF-6,revising SRs Pertaining to ISI Requirements for SG Tube Circumferential Cracking at top-of-tubesheet During 2P99 Planned mid-cycle Outage 0CAN079901, Application for Amends to Licenses DPR-51 & NPF-6 to Change TS & Subsequent Relief Request from Post Accident Sampling Requirements of NUREG-0737.TS Administrative Control requirements,NUREG-0737 & RG 1.97,rev 3,affected1999-07-14014 July 1999 Application for Amends to Licenses DPR-51 & NPF-6 to Change TS & Subsequent Relief Request from Post Accident Sampling Requirements of NUREG-0737.TS Administrative Control requirements,NUREG-0737 & RG 1.97,rev 3,affected 1CAN069902, Application for Amend to License DPR-51,revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks1999-06-0101 June 1999 Application for Amend to License DPR-51,revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks 1CAN059901, Application for Amend to License DPR-51,revising TS SRs & Applicable Bases Relevant to ISI Requirements for Portions of once-through SG Tubes Encompassed by Upper Tube Sheet. Proprietary Rept Encl.Rept Withheld,Per 10CFR2.790(b)(4)1999-05-14014 May 1999 Application for Amend to License DPR-51,revising TS SRs & Applicable Bases Relevant to ISI Requirements for Portions of once-through SG Tubes Encompassed by Upper Tube Sheet. Proprietary Rept Encl.Rept Withheld,Per 10CFR2.790(b)(4) 2CAN049902, Application for Amend to License NPF-6,adding TS 3.0.6 & Associated Bases to ANO-2 Ts.Proposed Specification Is Identical to Specification 3.0.5 of NUREG-1432, Improved STS CE Plants, Rev 11999-04-0909 April 1999 Application for Amend to License NPF-6,adding TS 3.0.6 & Associated Bases to ANO-2 Ts.Proposed Specification Is Identical to Specification 3.0.5 of NUREG-1432, Improved STS CE Plants, Rev 1 1CAN049901, Application for Amend to License DPR-51,revising Requirements Associated with ANO 1 Provisions for RB Testing & Insp1999-04-0909 April 1999 Application for Amend to License DPR-51,revising Requirements Associated with ANO 1 Provisions for RB Testing & Insp 1CAN049902, Application for Amend to License DPR-51,revising Requirements Associated with ANO-1 Station Batteries & DC Sources to 125 Vdc Switchyard Distribution Sys1999-04-0909 April 1999 Application for Amend to License DPR-51,revising Requirements Associated with ANO-1 Station Batteries & DC Sources to 125 Vdc Switchyard Distribution Sys 2CAN029913, Application for Amend to License NPF-6,adding Footnote to Action 2 Allowing Startup with Functional Units Associated with Channel D Excore Inoperable.Action 2 Is Associated with TS Table 3.3-1, Reactor Protective Instrumentation1999-02-25025 February 1999 Application for Amend to License NPF-6,adding Footnote to Action 2 Allowing Startup with Functional Units Associated with Channel D Excore Inoperable.Action 2 Is Associated with TS Table 3.3-1, Reactor Protective Instrumentation 0CAN119801, Application for Amends to Licenses DPR-51 & NPF-6, Implementing Consolidated EOI QA Plan Manual Submitted on 980430 & Approved by NRC in 981106 Se.Changes Also Clarify Responsibilities on STA Position on Shift1998-11-24024 November 1998 Application for Amends to Licenses DPR-51 & NPF-6, Implementing Consolidated EOI QA Plan Manual Submitted on 980430 & Approved by NRC in 981106 Se.Changes Also Clarify Responsibilities on STA Position on Shift 2CAN099805, Application for Amend to License NPF-6,modifying Notes in Table Associated with Tech Specs 2.2.1,3.3.1.1 & 3.3.2.1 Re Operating Bypass Setpoint1998-09-17017 September 1998 Application for Amend to License NPF-6,modifying Notes in Table Associated with Tech Specs 2.2.1,3.3.1.1 & 3.3.2.1 Re Operating Bypass Setpoint 2CAN089802, Application for Amend to License NPF-6,revising TS 3.1.3.2 Action Requirements for CEA Position Indicator Channels1998-08-0606 August 1998 Application for Amend to License NPF-6,revising TS 3.1.3.2 Action Requirements for CEA Position Indicator Channels 1CAN089801, Application for Amend to License DPR-51,revising TS 3.3.4.B Requirements for Sodium Hydroxide Tank Concentration1998-08-0606 August 1998 Application for Amend to License DPR-51,revising TS 3.3.4.B Requirements for Sodium Hydroxide Tank Concentration 2CAN069801, Application for Amend to License NPF-6,revising Portion of Plant Protection Sys Design to Ensure That ESFAS Meets Its Applicable Design Requirements.Rev 1 to Engineering Rept 97-R-2015-01 Encl1998-06-30030 June 1998 Application for Amend to License NPF-6,revising Portion of Plant Protection Sys Design to Ensure That ESFAS Meets Its Applicable Design Requirements.Rev 1 to Engineering Rept 97-R-2015-01 Encl 2CAN069804, Application for Amend to License NPF-6,increasing Allowable as-found Lift Setting Tolerances on MSSVs & Pressurizer Safety Valves1998-06-29029 June 1998 Application for Amend to License NPF-6,increasing Allowable as-found Lift Setting Tolerances on MSSVs & Pressurizer Safety Valves 2CAN069806, Application for Amend to License NPF-6,modifying Requirements for Pressurizer Code Safety Valve Requirements Specified by TS 3.4.2 & Safety Tank Isolation Requirements Specified in TS 3.4.121998-06-29029 June 1998 Application for Amend to License NPF-6,modifying Requirements for Pressurizer Code Safety Valve Requirements Specified by TS 3.4.2 & Safety Tank Isolation Requirements Specified in TS 3.4.12 2CAN069807, Application for Amend to License NPF-6,revising Surveillance Testing Requirements for Unit 2 Direct Current Electrical Distribution Sys & to Reflect Installation of New Inverters During Next Scheduled Refueling Outage1998-06-29029 June 1998 Application for Amend to License NPF-6,revising Surveillance Testing Requirements for Unit 2 Direct Current Electrical Distribution Sys & to Reflect Installation of New Inverters During Next Scheduled Refueling Outage 2CAN069805, Application for Amend to License NPF-6,providing Range of Acceptable Values for 4160 Volt Bus Loss of Voltage Values, to Be Consistent W/Requirements Set Forth in NUREG-1432,rev 11998-06-29029 June 1998 Application for Amend to License NPF-6,providing Range of Acceptable Values for 4160 Volt Bus Loss of Voltage Values, to Be Consistent W/Requirements Set Forth in NUREG-1432,rev 1 2CAN049802, Application for Amend to License NPF-6,revising Value of Single Largest post-accident Load Capable of Being Supplied by DGs & Relocates Value to Associated Bases1998-04-30030 April 1998 Application for Amend to License NPF-6,revising Value of Single Largest post-accident Load Capable of Being Supplied by DGs & Relocates Value to Associated Bases 1CAN049802, Application for Amend to License DPR-51,revising TS 1.6.1 Re Qpt Definition.Amend Allows Use of Either Incore Detectors or Excore Detectors for Determining Qpt1998-04-30030 April 1998 Application for Amend to License DPR-51,revising TS 1.6.1 Re Qpt Definition.Amend Allows Use of Either Incore Detectors or Excore Detectors for Determining Qpt 1CAN049806, Application for Amend to License DPR-51,changing Order of Channel Rotation During Outage for Scheduling Flexibility, While Still Requiring Rotation Schedule to Be Established for Operating Cycle1998-04-28028 April 1998 Application for Amend to License DPR-51,changing Order of Channel Rotation During Outage for Scheduling Flexibility, While Still Requiring Rotation Schedule to Be Established for Operating Cycle 1CAN049803, Application for Amend to License DPR-51,allowing Upper Tubesheet Volumetric Indications to Remain in Svc for Cycle 15,as Discussed W/Nrc on 980318 & 261998-04-0101 April 1998 Application for Amend to License DPR-51,allowing Upper Tubesheet Volumetric Indications to Remain in Svc for Cycle 15,as Discussed W/Nrc on 980318 & 26 1CAN029803, Application for Amend to License DPR-51,revising TS to Allow Use of Repair Roll Technology (Reroll) for Upper Tubesheet of Sgs.Revised TS Pages,Proprietary Rev 0 to Topical Rept BAW-10232P Included.Proprietary Encl Withheld1998-02-0909 February 1998 Application for Amend to License DPR-51,revising TS to Allow Use of Repair Roll Technology (Reroll) for Upper Tubesheet of Sgs.Revised TS Pages,Proprietary Rev 0 to Topical Rept BAW-10232P Included.Proprietary Encl Withheld 1CAN129702, Application for Amend to License DPR-51,establishing Alternate Repair Criteria for Upper Tubesheet Region of ANO-1 Sgs.Proprietary Topical Rept BAW-10226P Encl.Rept Withheld (Ref 10CFR2.790(b)(4))1997-12-12012 December 1997 Application for Amend to License DPR-51,establishing Alternate Repair Criteria for Upper Tubesheet Region of ANO-1 Sgs.Proprietary Topical Rept BAW-10226P Encl.Rept Withheld (Ref 10CFR2.790(b)(4)) 2CAN099703, Application for Amend to License NPF-6,modifying RPS & ESFAS Trip Setpoint & Allowable Values for SG Low Pressure1997-09-23023 September 1997 Application for Amend to License NPF-6,modifying RPS & ESFAS Trip Setpoint & Allowable Values for SG Low Pressure 2CAN099701, Application for Amend to License NPF-6,reducing Min Required Reactor Coolant Sys Flow Rate Requirements Listed in 3.2.5 Until ANO-2 SGs Are Replaced1997-09-23023 September 1997 Application for Amend to License NPF-6,reducing Min Required Reactor Coolant Sys Flow Rate Requirements Listed in 3.2.5 Until ANO-2 SGs Are Replaced 2CAN079702, Application for Amend to License NPF-6,modifying Actions Associated W/Ts Table 3.3-1 for Reactor Protective Instrumentation & Table 3.3-3 for Esfa Sys Instrumentation1997-07-28028 July 1997 Application for Amend to License NPF-6,modifying Actions Associated W/Ts Table 3.3-1 for Reactor Protective Instrumentation & Table 3.3-3 for Esfa Sys Instrumentation 2CAN079703, Application for Amend to License NPF-6,revising Surveillance Testing Requirements for Facility EFW Sys as Specified in TS 4.7.1.2.Requests That Effective Date for Change Be within 30 Days of Issuance1997-07-21021 July 1997 Application for Amend to License NPF-6,revising Surveillance Testing Requirements for Facility EFW Sys as Specified in TS 4.7.1.2.Requests That Effective Date for Change Be within 30 Days of Issuance 1CAN059702, Application for Amend to License DPR-51,allowing Sufficient Time for Submittal & NRC Review & Approval of Exigent TS Change Request for one-time Exception to Requirements of Section 4.18.5.b Re SG Tube Insp Surveillance Requirements1997-05-0202 May 1997 Application for Amend to License DPR-51,allowing Sufficient Time for Submittal & NRC Review & Approval of Exigent TS Change Request for one-time Exception to Requirements of Section 4.18.5.b Re SG Tube Insp Surveillance Requirements 2CAN049703, Application for Amend to License NPF-6,revising Requirements for Sample Scope Initial Size & Expansion for Inservice Insp Steam Generator Tube Sleeves1997-04-24024 April 1997 Application for Amend to License NPF-6,revising Requirements for Sample Scope Initial Size & Expansion for Inservice Insp Steam Generator Tube Sleeves 2CAN049702, Application for Amend to License NPF-6,permitting Delay of Scheduled three-yr Inspections of Flywheels on All Four RCPs Until Completion of 2R13 Refueling Outage,Scheduled for Winter of 1998-991997-04-18018 April 1997 Application for Amend to License NPF-6,permitting Delay of Scheduled three-yr Inspections of Flywheels on All Four RCPs Until Completion of 2R13 Refueling Outage,Scheduled for Winter of 1998-99 1CAN049703, Application for Amend to License DPR-51,requesting Exigent TS Change Re Steam Generator Tube Insp Surveillance Requirements1997-04-11011 April 1997 Application for Amend to License DPR-51,requesting Exigent TS Change Re Steam Generator Tube Insp Surveillance Requirements ML20133A6801996-12-23023 December 1996 Application for Amend to License NPF-6,revising TS 3/4.7.8 Which Will Enable on-line Testing of Selected Snubbers by Clarifying Intent of TS 2CAN129603, Application for Amend to License NPF-6,requesting Change to Power Calibr Requirements1996-12-19019 December 1996 Application for Amend to License NPF-6,requesting Change to Power Calibr Requirements 2CAN129611, Application for Amend to License NPF-6,requesting to Provide Addl NRC-approved Methodology in List of References in TS 6.9.51996-12-19019 December 1996 Application for Amend to License NPF-6,requesting to Provide Addl NRC-approved Methodology in List of References in TS 6.9.5 2CAN129604, Application for Amend to License NPF-6,requesting Deletion of Specific Value for Total Reactor Coolant Sys Volume in TS 5.4.21996-12-19019 December 1996 Application for Amend to License NPF-6,requesting Deletion of Specific Value for Total Reactor Coolant Sys Volume in TS 5.4.2 2CAN119609, Application for Amend to License NPF-6,revising Surveillance Requirements for Unit 2 Re SG Tubing,Ts 4.4.5.CEN-630-NP & CEN-630-P Repts encl.CEN-630-P Rept Withheld,Per 10CFR2.790(b)(4)1996-11-26026 November 1996 Application for Amend to License NPF-6,revising Surveillance Requirements for Unit 2 Re SG Tubing,Ts 4.4.5.CEN-630-NP & CEN-630-P Repts encl.CEN-630-P Rept Withheld,Per 10CFR2.790(b)(4) 2CAN119610, Application for Amend to License NPF-6,adding Suppl 1-P & Approval Ltr to Section 6.9.5.1 in Support of Increased SG Tube Plugging Limit Beyond 10% Ref to Small Break LOCA Methodology CENPD-1371996-11-24024 November 1996 Application for Amend to License NPF-6,adding Suppl 1-P & Approval Ltr to Section 6.9.5.1 in Support of Increased SG Tube Plugging Limit Beyond 10% Ref to Small Break LOCA Methodology CENPD-137 2CAN109603, Application for Amend to License NPF-6,changing Channel Functional Testing Frequency for Most of Reactor Protection Sys (RPS) & ESFAS Instrumentation from Monthly to Every Four Months1996-10-0707 October 1996 Application for Amend to License NPF-6,changing Channel Functional Testing Frequency for Most of Reactor Protection Sys (RPS) & ESFAS Instrumentation from Monthly to Every Four Months 0CAN109602, Application for Amends to Licenses DPR-51 & NPF-6,reducing Costs for Licensees by Allowing Change to Requirements W/O Necessarily Requiring License Amend,Per GL 95-101996-10-0202 October 1996 Application for Amends to Licenses DPR-51 & NPF-6,reducing Costs for Licensees by Allowing Change to Requirements W/O Necessarily Requiring License Amend,Per GL 95-10 0CAN109603, Application for Amend to Licenses DPR-51 & NPF-6 Re Relocation of RETS Per GL 89-011996-10-0202 October 1996 Application for Amend to Licenses DPR-51 & NPF-6 Re Relocation of RETS Per GL 89-01 0CAN089606, Application for Amends to Licenses DPR-51 & NPF-6,allowing Implementation of Approved Option B to 10CFR50,App J1996-08-23023 August 1996 Application for Amends to Licenses DPR-51 & NPF-6,allowing Implementation of Approved Option B to 10CFR50,App J 2CAN089601, Application for Amend to License NPF-6,relocating RCS Flow Rate Limit from TS & to Colr,Iaw/Gl 88-16, Removal of Cycle-Specific Parameter Limits from Ts1996-08-23023 August 1996 Application for Amend to License NPF-6,relocating RCS Flow Rate Limit from TS & to Colr,Iaw/Gl 88-16, Removal of Cycle-Specific Parameter Limits from Ts 2CAN089609, Application for Amend to License NPF-6,revising Section 5.0, Design Features & Would for Most Part,Adopt NUREG-1432 Rev 1,improved, Std Tech Specs for C-E Plants, for Section of TS1996-08-23023 August 1996 Application for Amend to License NPF-6,revising Section 5.0, Design Features & Would for Most Part,Adopt NUREG-1432 Rev 1,improved, Std Tech Specs for C-E Plants, for Section of TS 0CAN069601, Application for Amends to Licenses DPR-51 & NPF-6,allowing Reactor Containment Bldg Equipment Hatch Doors to Remain Open During Fuel Handling & Core Alterations1996-06-28028 June 1996 Application for Amends to Licenses DPR-51 & NPF-6,allowing Reactor Containment Bldg Equipment Hatch Doors to Remain Open During Fuel Handling & Core Alterations 1999-09-19
[Table view] |
Text
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ARKANSAS POWER & LIGHT COMPANY - :
CAPIT0L TOWER BUILDING /P. O. B0X 551/LITTLE ROCK, ARKANSAS 72203/(501) 377 3525 l T. GENE CAMPBELL October 28, 1987-Vice President Nuclear Operations
+
l 2CAN198705 l
U. S. Nuclear Regulatory Commission '
7920 Norfolk Avenue i Bethesda, Maryland 20814 l l
ATTN: Mr. Jose Calvo, Director i Project Directorate IV
SUBJECT:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Technical Specifications Change Request Refueling Water Tank and Safety Injection Tank Boron Concentration Increase I
Dear Mr. Calvo:
l The Arkansas Power & Light Company (AP&L) hereby requests an amendment to i l its Operating License No. NPF-6 for Arkansas Nuclear One --Unit 2 with the j enclosed submittal of proposed changes to the Technical Specifications.
l These Technical Specification changes provide safety and operational l l
enhancements specifically suited to-future extended cycle cores at l ANO-Unit 2. We wish to implement these improvements in conjunction with !
Cycle 7. Therefore, we would appreciate your review and approval of the i enclosed material so that the Operating License Amendment can-be issued prior to the start of our next. refueling outage which is scheduled to begin i- on February 12, 1988. The circumstances of this proposed. amendment,
~
1 i
however, are not of an exigent or_ emergency nature. ]
1 The proposed Technical Specification changes involve increasing the j refueling water boron concentration and the corresponding concentrations in i the refueling water tank'and-the safety injection. tanks. A~related change -j l proposed in a concurrently submitted amendment . request .will decrease the- j l boric acid concentration of the boric acid makeup tanks. These changes l offset more reactive cores which have been utilized to extend cycle length- ]
4 for the plant. The proposed changes therefore assure that adequate safety j margins are maintained. q 8711030452 871028 i- g l 1 PDR ADOCK 05000368L j P PDR; a
'l ueusea uccx.a sours urnmes sysreu ker.V WM @O* 80
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LMr. Jose Calvo - October 28, 1987-AP&L has evaluated the proposed changes'in acc'rdance o with 10CFR50.91(a)(3) l using the criteria in 10CFR50.92(c) and has determined that these changes
' involve'no significant hazards consideration. The bases for these ,
determinations are included in the enclosed submittal. ;
A copy of this amendment request and enclosure has been sent to.
Ms. Greta Dicus, Acting Director, Division of Environmental Health Protection, State Department of Health in accordance with 10CFR50.91(b)(1).
A check in the amount of $150.00 is included herewith as an appl _ication fee in'accordance with 10CFR170.12(c).
Very truly yours, AWm h 9
-U T. Gene Campbell f
TGC/sd f
Attachments / Enclosures cc: Ms. Greta Dicus, Acting Director Division of Environmental Health Protection State-Department of Health j 4815 West Markham Street 9
Little Rock, AR 72201 , .
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,u iSTATE 0'F"ARKANSASL N 'ifj
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,. -I, T.' Gene' Campbell. being duly sworns subscribe;to;and say,that-.I,am' :g-
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q Vice. President, NuclearL0perations, for. Arkansas. Power & LightLCompany;.that? <
l I have full authority to executeL.this oa'th'; that-I have~ fea'd' the document'.-
.numbereo:2CAN198705'and know the contents'thereofi aiid'that't'o thelbsst ofH s my1 knowledge, i_nformation and' belief the statements;in it are'true. .
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.T. Gene'Campbe
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SUBSCRIBED AND SWORN T0 before' me, a Notary Public in and for the 1 CountyandStateabovenamed,this2h' day.of.Oc-Koen .
1987, I
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L ENCLOSUREL ,
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~ PROPOSEDTECHNICAL SPECIFICATION ( ..
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RESPECTIVE SAFETY L _ ANALYSES:
' IN -THE MATTER OF ; AMENDING - 'i
.e ' LICENSE NO. NPF.6' ARKANSA'S POWER &LLIGHT: COMPANY ARKANSAS'NUCLEARLONE, UNIT 2 DOCKET N0,.50-368- ,
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i PROPOSED' CHANGES The proposed amendments would change ANO-2 Technical Specifications'3.1.2.7,.
3.1.2.8,.3.5.1, 3.5.4, and 3.9.1 to. increase required boron concentrations in the . refueling water tank and thel safety' injection tank and the minimum refueling water boron concentration. Corresponding changes are also <
proposed for Technical. Specifications' 3.1.1.1,.3'.1.1.2 and 3.10.1 to conform; with the proposed boron concentration changes. Bases sections 3/4.1.2, . 1 3/4.5.1, 3/4.5.4, and 3/4.6.2.2 are also revised'by;the proposed amendments-to discuss the bases.for the modified TechnicalJSpecifications. : Copies'of-the proposed revisions are included in Attachment 1. -RevisedITechnical Specifications 3.1.2.7 and 3.1.2.8 and. Bases : 3/4.1'.2 also ;contain changes from the concurrently submitted amendment request on the reduction of. boric acid makeup tank boron concentration. Attachment 2 provides further; '
description of the' prop' osed changes and. clarifies the source of each changeq ,
L DISCUSSION .I The increase in Cycle. 7 fuel reactivity and the corresponding increase in.
critical boron concentrations prompted a re evaluation 'of the boron' dilution -
event. The analysis was performed in accordance.with, and the results.of! J the re-evaluation were compared to, the. reference, analysis of' Cycle 2. ;The j reference analysis was: developed by Arkansas Power.& Light-(AP&L) and reviewed by the NRC as a part of the Cycle'2 Reload Report. .The reference analysis established conservative margins for.the-time.available to the- ;
operator to detect and terminate a boron dilution event.
To maintain the conservative margin established in'the reference' analysis
~
'I for the limiting case of a boron dilution event during refueling, the refueling boron concentration is being' increased. Corresponding increases in H the concentration of the refueling water tank (RWT) and the safety injection :i tank (SIT) assure that the refueling boron concentration is maintained' '
l The conservative margin for the other limiting case.of a boron dilution )
event during Mode 5 with the RCS partially drained..is also, maintained by-i using more realistic input assumptions. . The beginning of life-(BOL) inverse q boron worth was assumed which corresponds to the most. limiting. time of life: ~;
conditions for the event. The analysis for Modes 3, 4 and 6 used the'very ;
conservative end of life (EOL) worths. The volume of water which must be- a diluted was also increased to include the volume of one train'of shutdown-cooling which is required to be. operating-by Technica.1 Specifications in i this condition. Both of these realistic input assumptionsLare in conformance with Standard Review Plan Section 15.4.6. l i
The analysis of the boron dilution event for the less limiting cases of . .;
Modes 2-4 demonstrates that the operator will still have adequate. time to -!
detect and terminate the event.
All physics calculations for Cycle 7 at ANO-2 were performed using the increased boron concentrations for the refueling water tank and-the safety injection tank.
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-1 DETERMIN'ATION OF SIGNIFICANT HAZARDS' g Arkansas. Power & Light Company has' performed an analysis of th'e proposed change in accordance with 10 CFR 50.91(a)(1) regarding no significant i hazards consideration using the standards in.10 CFR 50.92(c). A discussion of those standards as they relate to this' amendment' request follows: 1
'/
Criterion'1 - Does.Not Involva.a Significant Increase in the Probability or ,
Consequences of an Accident Previously Evaluated l The possible impact of. increasing the minimum refueling water boron. ~l concentration and the boron concentration in the refueling waten tank and 1 the safety injection tanks was considered"fer all SAR Chapter 15 events. J Additional evaluations were performed with Mpect to:a) effect sipSAR Chapter 15 boron dilution event analysis, b) offect o'n SAR Chapter 15 steam line break analysis, c) effect on SAR Chapter 15 steam generator tube rupture analysis, d) effect on long' term boric pcid buildup calculation reported in SAR Chapter 6,'and e) effect on pos 6 LOCA containment pH value i reported in SAR Chapter 6.
The re-analysis of the boron dilution event used design. data'for ANO-2' Cycle 7 and the higher boron concentrations jn the refueling water tank as i inputs for the analysis. The assumptions lfor critical boron concentration, !
inverse boron worth and shutdown margin used in the re-analysis are compared i to the assumptions used in the Cyc h W analysis in Table 1. . The Cycle 2-analysis has been used as the refsente analysis for Cycles 3-7. Except for-the inverse boron worth and dilution volume used 'in the analysis for Mode 5, all other assumptions in completing the boron dilution event analysis are consistent with the conservative assumptions made in'the reference analysis.
s As discussed in Chapter 15 of the ANO-2 SAR, several conservative assumptions have been incorporated into the boron dilution event analysis.
The dilution flow assened in the analysis is 132 gpa which corresponds to the operation of all three charging pumps. Simultaneous injection from'all three pumps is highly unlikely. In addition, for the analysis during refueling operations (Mode 6),.it is assumed that all control element assemblies (CEAs) are withdrawn from the core. This is highly unlikely 7 since typically only those CEAs associated with fuel assemblies which are ,
being replaced or repositioned in the core would be removed.
}.j, Very conservative. values have been used for critical boron concentrad on and the inverse boron worths as shown in Table 1. These choices produce the most adverse effects by reducing the calculated time to criticality for initially subcritical.' modes. The more realistic beginning of cycle inverse boron worth was assumed for the cold shutdown1 (Mode 5) boron dilution-event analysis. >
The cold shutdown analysis conservatively assEnesthe. water volume:in the reactor vessel only up to the. lower lip of.the outlet nozzle. This .,
assumption considers the possible effects of a dilution. event during . !
maintenance activities with the RCS drained,, The Cyde 7 ecalysistincludes'- !
the volume of water of one shutdown cooling loop whit 6 sould be in service n in this condition as required by Technical Specifick(f E i
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J The results of the revised boron dilution event analyses'.are shown in Table-2. The amount of time available forithe operator to diagnose boron- 1 dilution events and initiate corrective action'.for the most limiting modes of< operation i.e., cold shutdown and refueling; is slightly greater for the Cycle 7 analysis. The decrease in timelto loss of shutdown margin for ,
Modes 2-4 is not significant since the operator.will.still have a .
substantial amount of time to diagnose the event and initiate corrective.' ,
action as is' apparent when compared to the acceptance criteria. i The results for Mode'l are not presented since the reactor is. critical- when deboration starts. Power operation will be quickly terminated by the' ;
Reactor Protection System. The results.of the Mode 2 analysis conservatively % und the event initiated in Mode 1.with respect to thel time to loss of shutdown-margin. ;
The potential effects on the steam line break analysis due to the increase. I
" .in RWT and SIT boron concentration have been evaluated. The~ steam line-break results in temperature and pressure decreases in the primary system- ,
dt.a to rapid loss of energy to the secondary system through the affected. !
, steam generator. The rapid temperature reduction results in a reactivity transient due to the moderator temperature coefficient. This transient is. I partially mitigated by the addition to:the reactor coolant system of borated water from the high pressure safety injection (HPSI) pumps and the safety injection tanks as reactor coolant system pressure drops below the HPSI injection pressure and the pressure in the safety injection tanks. The
~ increased boron concentration in the refueling water tank and'the safety 1 injection tanks will enhance the' mitigation of'this reactivity transient. a For the steam line break analyses, the proposed Technical Specification ;
changes will in fact increase the margin of safety. These conclusions l include consideration of the separately proposed decrease in HPSI i
' ' differential pressure Technical Specification requirements. 1 The potential effects on the steam generator tube rupture analysis of.the L increase in RWT and SIT boron concentration have been evaluated. The steam l
generator tube rupture results in a decrease in reactor coolant system pressure. This results in actuation of the high' pressure safety injection l pumpt to maintain reactor coolant system pressure. The high pressure i injection pumps inject borated water from the refueling water tank into the a reactor coolant system. Since the reactor will be scrammed, the borated water actually provides a slight addition in shutdown margin. The proposed
- Technical Specification changes therefore~have very little effect on this l transient other than to provide a slight increase in the margin of safety due to the minimal increases in reactor coolant system boron concentration.
- 3 The potential effects on the long term boric acid buildup calculations reported in Chapter 6 of the SAR have been evaluated. The calculation assumes the maximum inventories and concentrations of all borated water sources are available in the containment for concentration in the reactor vessel. Tr/2 proposed increase in RWT and SIT concentration would increase the total i wentory of available boron. AP&L is submitting a separate-
, request for a Technical Specification amendment to decrease.the boron concentration required in the boric acid makeup tanks (BAMT). This l
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l O Technical Specification change request woulu 1cwar the BAMT regtfked boric s
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acid concentration to 3.5% or.less. .This change will almost egacT1y offset LOCA theincreasedlhTandSITboronconcentrationinregardstocpos(echnical reactor coolan systemhoronconcentiathn. Thus the proadseG m c f
Specification d* ange for baron concentration in the. refueling yder tank ano* #
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< the safety injedion t2rA will have no significant effrdt on the long term reactor coolant systerd boron concentration since boron concentration in the ,
boric acid m ke up, tank will be decreased, i The potd$ it effects on the, post LOCA containment pH vejue calculations
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) reportef p (itapder 6 of the 9R have been evaluated. Li.ke the long term 1
boric acid buildup calc %ations bisevased above, the post LOCA containment
- x. pkwould by affected by an increas,e ja RWT . nd SIT boron concentration. The.
/ ' I'e reduction M BAMT boron concen kation also a 1 The resMt is d slight gduction in the plc,ulat spranand sump pH values.on pH.
o;se%the effect
- The maximum spray pH of 11.0 referul' erin TechMcahTprtrifications ~ basesg is-stiV1 bounding while the qinimum equil ium sump value of. 8.9 has decreased .
to 8.8. -The griginal decontaminatic, f @ actors for Jodine are jtill valid with,the reduced pH valv?s,so 4he ch sge has no signif'. b t,ispact on iodine:
/ ! rcaoval capabilities. Similarly, since the solut un is stTYL basi <, there is k no ,significant impact on containment corrosion characteristics. ,
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\, Criterwh' 2 - V.'abes Not Create the Possibility of a Nor(or Different Kfnd of f ,. / R Accidentsfrom any Accident Previously Eu luated L i
IncreMdg.the rvfuelink watUr boron coricantration and the boron conadt' ration in the refdipg water tank and the safety injection tank does
/. not deate the possibility cf a new or different kind of accident. The increas8in boron concentration in the refueling water and the corresponding '
incretises ip tank concentrations 'r epresent a belatively minor change in plai.6 parah.eters 'which ar. laiwady coNrolled by Technical Specification f requirements ST,he base.(for these regiJirsM4ts do not ide'htify any limits
[, on maximum p g issible values of boron concentyetion. These changes have no effectonplantdesignjequipmentperformance'oroperatorresponseto i
j transients oi'accidenti. Therefore, these ch!qgea do not create the 7 -
potential for any unanalyzed accidents. b ,'
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Criterion 3 - DoesNotInvolveaSignificantReductioninauMakinof Safety j CA T:
Increasing the refueijng water boron concentration and the cotAentrat4n of tt.Nrefueling water Vank and safety injectiostank will pr,t create. a '
significant reduction in a margin of safety. The retult',%f the Nnalyses supporting the inciensed boron concentrations indicate these changel msult in no significant impact on selety margin. \,
, '.\
For the boron dilution event, tN: timr available for the operator to diagnose the event and initia,te ' correct &ve act.on is slightly improved for i the limiting cases. The operator still has suhtartial time available in 3
the non-limiting cases so the decrease in time to loss of shutdown margin fnr Modes 2-4 is not significant.
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The effect'of the boron concentration. increase on both the steam line. break analysis:and on the steam generator tube rupture analysis was positive. The- .;
injection of additional. boron for both events improves the analytical l results.
- l 1
The decreased boric acid concentration of the boric acid makeup tank l proposed in the concurrently submitted amendment request offset the RWT and l SIT concentration increase'for the post LOCA. boron precipitation !
calculations. There is essentially no change in calculated containment inventory and consequently no impact on the time requirements for. initiation .
of the core flush flow. .;
The minor reduction in post LOCA containment minimum calculated pH has j insignificant impact on both iodine' removal capabilities and corrosion characteristics.
Based on these results, the prop'osed' changes do not involve any significant reduction in a margin of safety. 1 CONCLUSIONS l
The Commission has provided guidance concerning the application of the L standards for determining whether a significant hazards consideration i exists. This guidance includes examples (51 FR 7750) of types of amendments-that are considered not likely to involve significant hazards s considerations. The changes proposed in this amendment are directly 1 comparable to examples provided by the Commission.
Example (iii) relates to a change resulting from core reloading. The proposed change in the refueling water boron concentration and the corresponding concentration changes in_the refueling water and safety injection tanks are analogous to this example. These changes are being implemented partially to offset higher core reactivities used to extend cycle duration and increase fuel burnup. These changes help to assure that acceptable margins established in analyses for previous cycle are not significantly decreased.
l l The Baltimore Gas and Electric Company submitted a similar amendment request I
for Calvert Cliffs dated September 22, 1980. This Technical Specification-
. request was subsequently approved.
Based on these evaluations, AP&L has determined that these proposed changes do not involve a significant hazards consideration.
f 1
_ _-____ - - _ _--__-__ Q
i TABLE 1 KEY PARAMETERS ASSUMED IN THE B0RON DILUTION ANALYSIS ~j REFERENCE' i PARAMETER; CYCLE CYCLE 7 (Cycle 2)
Critical Boron Concentration, PPM
(All Rods Out, Zero Xenon)
Power Operation (Mode 1). 1000 '1800' Startup (Mode 2) 1300 2000 Hot Standby.'(Mode 3) :1300 1900 Hot Shutdown (Mode 4) 1300 1900 Cold Shutdown (Mode 5) 1300 1610 Refueling (Mode 6)- 1250 1650' Inverse Boron Worth, PPM /%
Power Operation 82 82 Startup 82 82 l Hot Standby 62 62 L Hot Shutdown 62 62 .
l Cold Shutdown 62 80.7#** )
Refueling 62 62 Shutdown Margin Assumed, %
Power Operation 5.4 5. 0 Startup 5.0 5.0 Hot Standby 5.0 5.0 l
Hot Shutdown 5.0 5.0 ,
Cold Shutdown 5.0 ' 5. 0 l Refueling * **
i Technical Specification minimum refueling boron concentration of 1731.
i ppm minus a 50 ppm uncertainty is assumed.
- Technical Specification minimum refueling boron concentration of 2500 ppm minus a 50 ppm uncertainty is assumed.
I *** For Mode 5, BOC physics data were used.
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