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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20216E6051999-09-0707 September 1999 Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation ML20210H0631999-07-28028 July 1999 Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, by Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4131999-07-27027 July 1999 Application for Amend to License NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G8831999-07-26026 July 1999 Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5251999-07-26026 July 1999 Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20210G4631999-07-26026 July 1999 Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumention & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20195F9121999-06-10010 June 1999 Application for Amend to License NPF-3,changing TS 3/4.6.4.4 Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20207E7861999-05-21021 May 1999 Application for Amend to License NPF-3,allowing Use of Expanded Spent Fuel Storage Capability ML20205E4961999-03-19019 March 1999 Application for Amend to License NPF-3,requesting Withdrawal of Proposed New Action B to TS 3.6.5.2,previously Submitted in 981027 Application ML20204F1691999-03-0909 March 1999 Application for Amend to License NPF-3,adopting Changes in Frequency & Scope of Volumetric Exams Justified by W TR WCAP-14535A ML20196F3791998-11-30030 November 1998 Supplemental Application for Amend to License NPF-3, Proposing Changes to License Conditions 2.C(6) & 2.E by Transferring Operating Authority for DBNPS from Toed & Centerior Svc Co to Firstenergy Nuclear Operating Co ML20155E3181998-10-28028 October 1998 Application for Amend to License NPF-3,revising Various Sections of TS 6.0, Administrative Controls, Including Relocation of Contents of 6.11 to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155E0701998-10-27027 October 1998 Application for Amend to License NPF-3,revising TSs 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation by Providing Potential Reduction in Spurious Trip Rate to Provide Cost Savings in Excess of $50,000 ML20155D7731998-10-27027 October 1998 Application for Amend to License NPF-3,relocating Existing TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8481998-10-27027 October 1998 Application for Amend to License NPF-3,revising Existing TS SRs 4.8.2.3.2.d,4.8.2.3.2.e,4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20151W2811998-09-0808 September 1998 Application for Amend to License NPF-3,permitting Use of Framatome Cogema Fuels M5 Advanced Alloy Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2851998-09-0808 September 1998 Application for Amend to License NPF-3,revising TS Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20236G6461998-06-29029 June 1998 Application for Amend to License NPF-3,transferring Operating Authority for DBNPS from TE & Centerior Svc Co to New Operating Company Called Firstenergy Nuclear Operating Co.Marked Up License,Safety & Environ Assessments Included ML20236R2301998-06-29029 June 1998 Resubmitted Application for Amend to License NPF-3, Transferring Operating Authority for DBNPS from Teco & Centerior Svc Co to New Operating Company Called Firstenergy Nuclear Operating Co.Safety Assessment & EA Included ML20217P8671998-04-24024 April 1998 Application for Amend to License NPF-3,modifying Existing TS 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases by Relocating Tables of Response Time Limits from TS to Plant USAR Technical Requirements Manual ML20217P8251998-04-24024 April 1998 Application for Amend to License NPF-3,clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20203L0861998-02-26026 February 1998 Application for Amend to License NPF-3 to Revise TS 3/4.4.5 & TS 3/4.4.6.2,incorporating New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2511997-12-23023 December 1997 Application for Amend to License NPF-3.Amend Changes TS Definitions 1.12,TS 3/4.9.5 & New TS 3.0.6 ML20197J5861997-12-23023 December 1997 Application for Amend to License NPF-3,revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217R2801997-08-26026 August 1997 Application for Amend to License NPF-3,clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2831997-08-26026 August 1997 Application for Amend to License NPF-3,modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5931997-07-29029 July 1997 Suppl 950929 to Application for Amend to License NPF-3, Change TS 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating & Associated Bases 3/4.4.2 & 3/4.4.3 ML20141F1051997-06-24024 June 1997 Application for Amend to License NPF-3,deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138A3201997-04-18018 April 1997 Application for Amend to License NPF-3,requesting Conversion to 24-month Fuel Cycle ML20138C3131997-04-18018 April 1997 Application for Amend to License NPF-3,requesting Rev to TS 3/4.7.6 to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20137M1061997-03-31031 March 1997 Application for Amend to License NPF-57,revising TS to Improve Consistency Between TS & Plant Configuration, Operation & Testing & Complete Required CA to Resolve TS Discrepancies Identified in CA Program ML20138M1251997-02-14014 February 1997 Application for Amend to License NPF-3,requesting Delay of Heat Removal Sys Valve Pit Surveillance Requirements ML20134D7461997-01-30030 January 1997 Application for Amend to License NPF-3,revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0561997-01-20020 January 1997 Application for Amend to License NPF-3,involving TS 3/4.5.3 Re ECCS Subsystems ML20132C7771996-12-13013 December 1996 Application for Amend to License NPF-3,authorizing Transfers of Control ML20132B6871996-12-11011 December 1996 Application for Amend to License NPF-3,revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle ML20134F1851996-10-28028 October 1996 Application for Amend to License NPF-3,requesting Revisions to 3/4.8.1.1,3/4.8.1.2,3/4.8.2.3,3/4.8.2.4 & 3/4.8 Re Electrical Power Systems ML20117P5301996-09-17017 September 1996 Application for Amend to License NPF-3,supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8441996-09-12012 September 1996 Application for Amend to License NPF-3,revising Reactivity Control Systems & Emergency Core Cooling Systems ML20117M1971996-09-0404 September 1996 Application for Amend to License NPF-3,App A,Modifying TS 6.2.3 by Removing Specific Overtime Limits & Working H from TS Consistent W/Nrc Recent Determination,On Generic Basis, That Limits Need Not Be Specified ML20116K2601996-08-0707 August 1996 Application for Amend to License NPF-3,changing Tech Specs 1.0, Definitions, Bases 3/4.0, Applicability & 3/4.6.2.1, Containment Sys - Depressurization & Cooling Sys - Containment Spray Sys ML20117K1871996-05-28028 May 1996 Application for Amend to License NPF-3,revising TS 3/4.3.1.1 RPS Instrumentation & TS 3/4.3.2.2 - Anticipatory RTS Instrumentation to Increase Trip Device Test Interval ML20107L3541996-04-18018 April 1996 Application for Amend to License NPF-3,requesting NRC Review & Approval to Use Alternate Electrical Lineup.Station Blackout DG as Standby Emergency Power Source to Supply Loads Normally Supplied by EDG 1,while Being Reworked ML20101M1601996-03-29029 March 1996 Application for Amend to License NPF-3,App A,Re Surveillance Requirements for Charcoal Filter Lab Testing to Revise Testing Methodology Used to Determine Operability of Charcoal Filters in ESF Air Handling Units ML20101C6911996-03-0606 March 1996 Application for Amend to License NPF-3,revising TS 3/4.5.2 to Allow Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI 1-2 Pump Until 10th Refueling Outage, Scheduled to Begin 960408 ML20100E0051996-02-0505 February 1996 LAR 93-0003 to License NPF-3,revising Table 3.3-3 of TS 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation to More Accurately Reflect Design & Actuation Logic of Plant Sequencers & Undervoltage Relays ML20095F5861995-12-12012 December 1995 Application for Amend to License NPF-3,revising TSs Re Containment Sys ML20098C5131995-10-0202 October 1995 Application for Amend to License NPF-3,revising TS Section 5.0,design Features & Adopting Improved STS for B&W Plants Format & Content ML20098C1071995-09-29029 September 1995 Application for Amend to License NPF-3,modifying TS 3.4.3 & Associated Bases for Pressurizer Code Safety Valve Lift Setpoint Tolerances ML20098C3931995-09-29029 September 1995 Application for Amend to License NPF-3,revising Tech Spec 3/4.1.2.8, Reactivity Control Sys - Borated Water Sources - Shutdown, Tech Spec 3/4.1.2.9, Reactivity Control Sys - Operating & TS 3/4.5.1, ECCS - Core Flooding Tanks 1999-09-07
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20216E6051999-09-0707 September 1999 Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation ML20210H0631999-07-28028 July 1999 Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, by Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4131999-07-27027 July 1999 Application for Amend to License NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G8831999-07-26026 July 1999 Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5251999-07-26026 July 1999 Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20210G4631999-07-26026 July 1999 Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumention & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20195F9121999-06-10010 June 1999 Application for Amend to License NPF-3,changing TS 3/4.6.4.4 Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20207E7861999-05-21021 May 1999 Application for Amend to License NPF-3,allowing Use of Expanded Spent Fuel Storage Capability ML20205E4961999-03-19019 March 1999 Application for Amend to License NPF-3,requesting Withdrawal of Proposed New Action B to TS 3.6.5.2,previously Submitted in 981027 Application ML20204F1691999-03-0909 March 1999 Application for Amend to License NPF-3,adopting Changes in Frequency & Scope of Volumetric Exams Justified by W TR WCAP-14535A ML20196F3791998-11-30030 November 1998 Supplemental Application for Amend to License NPF-3, Proposing Changes to License Conditions 2.C(6) & 2.E by Transferring Operating Authority for DBNPS from Toed & Centerior Svc Co to Firstenergy Nuclear Operating Co ML20155E3181998-10-28028 October 1998 Application for Amend to License NPF-3,revising Various Sections of TS 6.0, Administrative Controls, Including Relocation of Contents of 6.11 to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155E0701998-10-27027 October 1998 Application for Amend to License NPF-3,revising TSs 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation by Providing Potential Reduction in Spurious Trip Rate to Provide Cost Savings in Excess of $50,000 ML20155D7731998-10-27027 October 1998 Application for Amend to License NPF-3,relocating Existing TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8481998-10-27027 October 1998 Application for Amend to License NPF-3,revising Existing TS SRs 4.8.2.3.2.d,4.8.2.3.2.e,4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20151W2811998-09-0808 September 1998 Application for Amend to License NPF-3,permitting Use of Framatome Cogema Fuels M5 Advanced Alloy Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2851998-09-0808 September 1998 Application for Amend to License NPF-3,revising TS Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20236G6461998-06-29029 June 1998 Application for Amend to License NPF-3,transferring Operating Authority for DBNPS from TE & Centerior Svc Co to New Operating Company Called Firstenergy Nuclear Operating Co.Marked Up License,Safety & Environ Assessments Included ML20236R2301998-06-29029 June 1998 Resubmitted Application for Amend to License NPF-3, Transferring Operating Authority for DBNPS from Teco & Centerior Svc Co to New Operating Company Called Firstenergy Nuclear Operating Co.Safety Assessment & EA Included ML20217P8671998-04-24024 April 1998 Application for Amend to License NPF-3,modifying Existing TS 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases by Relocating Tables of Response Time Limits from TS to Plant USAR Technical Requirements Manual ML20217P8251998-04-24024 April 1998 Application for Amend to License NPF-3,clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20203L0861998-02-26026 February 1998 Application for Amend to License NPF-3 to Revise TS 3/4.4.5 & TS 3/4.4.6.2,incorporating New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2511997-12-23023 December 1997 Application for Amend to License NPF-3.Amend Changes TS Definitions 1.12,TS 3/4.9.5 & New TS 3.0.6 ML20197J5861997-12-23023 December 1997 Application for Amend to License NPF-3,revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217R2801997-08-26026 August 1997 Application for Amend to License NPF-3,clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2831997-08-26026 August 1997 Application for Amend to License NPF-3,modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5931997-07-29029 July 1997 Suppl 950929 to Application for Amend to License NPF-3, Change TS 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating & Associated Bases 3/4.4.2 & 3/4.4.3 ML20141F1051997-06-24024 June 1997 Application for Amend to License NPF-3,deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138A3201997-04-18018 April 1997 Application for Amend to License NPF-3,requesting Conversion to 24-month Fuel Cycle ML20138C3131997-04-18018 April 1997 Application for Amend to License NPF-3,requesting Rev to TS 3/4.7.6 to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20137M1061997-03-31031 March 1997 Application for Amend to License NPF-57,revising TS to Improve Consistency Between TS & Plant Configuration, Operation & Testing & Complete Required CA to Resolve TS Discrepancies Identified in CA Program ML20138M1251997-02-14014 February 1997 Application for Amend to License NPF-3,requesting Delay of Heat Removal Sys Valve Pit Surveillance Requirements ML20134D7461997-01-30030 January 1997 Application for Amend to License NPF-3,revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0561997-01-20020 January 1997 Application for Amend to License NPF-3,involving TS 3/4.5.3 Re ECCS Subsystems ML20132C7771996-12-13013 December 1996 Application for Amend to License NPF-3,authorizing Transfers of Control ML20132B6871996-12-11011 December 1996 Application for Amend to License NPF-3,revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle ML20134F1851996-10-28028 October 1996 Application for Amend to License NPF-3,requesting Revisions to 3/4.8.1.1,3/4.8.1.2,3/4.8.2.3,3/4.8.2.4 & 3/4.8 Re Electrical Power Systems ML20117P5301996-09-17017 September 1996 Application for Amend to License NPF-3,supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8441996-09-12012 September 1996 Application for Amend to License NPF-3,revising Reactivity Control Systems & Emergency Core Cooling Systems ML20117M1971996-09-0404 September 1996 Application for Amend to License NPF-3,App A,Modifying TS 6.2.3 by Removing Specific Overtime Limits & Working H from TS Consistent W/Nrc Recent Determination,On Generic Basis, That Limits Need Not Be Specified ML20116K2601996-08-0707 August 1996 Application for Amend to License NPF-3,changing Tech Specs 1.0, Definitions, Bases 3/4.0, Applicability & 3/4.6.2.1, Containment Sys - Depressurization & Cooling Sys - Containment Spray Sys ML20117K1871996-05-28028 May 1996 Application for Amend to License NPF-3,revising TS 3/4.3.1.1 RPS Instrumentation & TS 3/4.3.2.2 - Anticipatory RTS Instrumentation to Increase Trip Device Test Interval ML20107L3541996-04-18018 April 1996 Application for Amend to License NPF-3,requesting NRC Review & Approval to Use Alternate Electrical Lineup.Station Blackout DG as Standby Emergency Power Source to Supply Loads Normally Supplied by EDG 1,while Being Reworked ML20101M1601996-03-29029 March 1996 Application for Amend to License NPF-3,App A,Re Surveillance Requirements for Charcoal Filter Lab Testing to Revise Testing Methodology Used to Determine Operability of Charcoal Filters in ESF Air Handling Units ML20101C6911996-03-0606 March 1996 Application for Amend to License NPF-3,revising TS 3/4.5.2 to Allow Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI 1-2 Pump Until 10th Refueling Outage, Scheduled to Begin 960408 ML20100E0051996-02-0505 February 1996 LAR 93-0003 to License NPF-3,revising Table 3.3-3 of TS 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation to More Accurately Reflect Design & Actuation Logic of Plant Sequencers & Undervoltage Relays ML20095F5861995-12-12012 December 1995 Application for Amend to License NPF-3,revising TSs Re Containment Sys ML20098C5131995-10-0202 October 1995 Application for Amend to License NPF-3,revising TS Section 5.0,design Features & Adopting Improved STS for B&W Plants Format & Content ML20098C1071995-09-29029 September 1995 Application for Amend to License NPF-3,modifying TS 3.4.3 & Associated Bases for Pressurizer Code Safety Valve Lift Setpoint Tolerances ML20098C3931995-09-29029 September 1995 Application for Amend to License NPF-3,revising Tech Spec 3/4.1.2.8, Reactivity Control Sys - Borated Water Sources - Shutdown, Tech Spec 3/4.1.2.9, Reactivity Control Sys - Operating & TS 3/4.5.1, ECCS - Core Flooding Tanks 1999-09-07
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Devs teses (419)2 4 2300 Docket Number 50-346 License Number NPF-3 Serial Number 1898 March 1, 1991 l
United States Nuclear Regulatory Commission Document control Desk Vashington, D. C. -20555 Subj ec t : License Amendment Request to Revise Technical Specification 3/4.8.2.3, E)cetrical'Pover Systems,'D.C. Distribution -
Operating (TAC No. H79672) k Centlement, i Enclosed is an application for an amendment to the Davis-Besse Nuclear Power Station (DBNPS), Unit Number 1, Operating License NPF-3, Appendix A -
Technical Specifications-(TS). This application requests a revision to TS 3.8.2.3 and its associated Bases based on the model TS's recommended by the Nuclear Regulatory Commission (NRC) to Toledo Edison in an NRC letter dated July 16, 1981 (Toledo Edison letter Log Number 756). Specifically, this vill allow Toledo Edison to utilire an alternate method of determining battery operability following service or performance discharge surveillance testing.
Use of this alternate method of determining battery operability vill allow for a potential reduction of six to eight days in critical path duration during a refueling outage. Accordingly Toledo Edison requests that the NRC approve this amendment.by September 1, 1991, for use during the seventh ;
reiueling outage. -
If you have any questions, please contact Mr. R. V. Schrauder, Manager -
Nuclear Licensing,-at (419) 249-2366.
Very y yours, KBR/mmb m_Q ces. p. M. Byron,-DB-1 NRC Senior Resident Inspector A. B.: Davis, Regional Administrator, NRC Region III D. C. Di:Ianni, DB-1 NRC Senior Project Manager General J. Villiams, Chief of Staff, Ohio Adjutant General's Office i State of Ohio
.Vtility Radiological Safety Board operoung companies . 9103070288 9103o1 FDR
= / ' Pi i>r p clevelchd Doctuc thuminchng ADOCK 05000346 bIUUM Towo tason P PDR [lNOI lll L
. Dockst Nu2bar 50-346 Liccnse Nu:bar NPT-3 Serial Number 1898
. Enclosure Page 1 Application for Amendment to facility Operating License Number NPF-3 Davis-Besse Nuclear Power Station Unit Number 1 Attached are requested changes to the Davis-Besse Nuclear Power Station, Unit Number 1 Facility Operating License Number NPF-3. Also included is the Safety Assessaent and Significant flazards Consideration.
The proposed changes submitted under cover letter Serial Number 1898 r concerni Appendix A. Technical Specification 3/4.8.2.3, " Electrical Pover Systems, D.C. Distribution - Operating".
Appendix A, Technical Specification 3/4.8.2.4, " Electrical Power Systems, D.C. Distribution - Shutdown".
Technical Specification Bases 3/4.0, " Electrical Pover". *
)
Bya flR f'^'* %==~
D. C. Shelton, Vice President, Nuclear - Davis-Besse Svorn and Subscribed before me this 1st day of March. 1991.
$ntf b i f Ohio
~
Notary P ic, State
,A fun.nyss e p,cwggo Ul %hTau,Qay,,;,g ny
. Docket Numb 2r 50-346 Licensa Numb 3r NPF-3 Serial. Number 1898 Enclosure Page 2 The following information is provided to support issuance of the requested changes to the Davis-Besse Nuclear Power Station, Unit 1, Operating License Number NPF-3, Appendix A, Technical Specifications 3/4.8.2.3, " Electrical Power Systems, D.C. Distribution - Operating" Technien1 Specification 3/4.8.2.4, " Electrical Power Systems, D.C. Distribution - Shutdown":
Technical Specification Bases, 3/4.8, " Electrical Power Systems".
A. Time Required to Implement: This change is to be implemented within 45 days after the NRC issuance of the License Amendment.
B. Reason for change (License Amendment Request 90-0050):
This License Amendment Request (LA3) proposes revision of Davis-Besse Nuclear Pover Station (DBNPS) Operating License TS 3/4.8.2.3, TS Table 4.8-1, Battery Surveillance Requirements, to allov incorporation of the Nuclear Regulatory Commission (NRC) recomtnendations made in a letter to Toledo Edison dated July 16, 1981 (Toledo Edison letter Log Number 756).
Specifically, by adding a footnote to Table 4.8-1 this LAR vill allow the use of a battery charging current of less than 2 amps when on a float charge in lieu of specific gravities to as a means of determining battery operability following battery service or performance discharge surveillance testing. TS 3/4.8.2.4 is also affected by this proposed revision as Surveillance Requirement 4.8.2.4.2 refers back to Table 4.8-1.
Safety Assessment and Significant Hazards Consideration: See C.
attachment.
1
. Dockot husber 50-346 Licenso Nu:bar NPF-3
> Serial. Number 1898 Attachment Safety Assessment and Significant Hazards Consideration for License Amendment Request 90-0050 J
T T,1f t Revision of Technical Specification (TS) 3/4.8.2.3, " Electrical Pover l Systems, D.C. Distribution - Operating" and TS 3/4.8.2.4, " Electrical Power Systems, D.C. Distribution - Shutdovn" DESCRIPTION:
This License Amendment Request (LAR) proposes revision of Davis-Besse Nuclear Power Station (DBNPS) Operating License TS 3/4.8.2.3, TS Table 4.8-2, Battery Surveillance Requirements, to allow incorporation of the Nuclear Regulatory Commission (NRC) recommendations made in a letter to Toledo Edison (TE) dated July 16, 1981 (TE letter Log Number 756).
Specifically, by adding a footnote to TS Table 4.8-1 this LAR vill allow the use of a battery chargir g current of less than 2 amps when on a float charge in lieu of specific gravities as a means of determining station battery operability following battery service or performance discharge surveillance testing. TS 3/4.8.2.4 is also affected by this proposed revision as Surveillance Requirement (SR) 4.8.2.4.2 refers back to TS Table 4.8-1.
Presently, after charging the station battery following a battery service or performance discharge surveillance test, a several day delay is required while avalting specific gravity equelization. IEEE Standard 450-1980, "IEEE Recommended Practice for Haintenance, Testing, and Replacement of Large 1,ead Storage Batteries for Generating Stations and Substations", allovs for the use of a stabilized battery charging current as indication that a battery is charged in lieu of specific gravities. This provision vould allov a potential reduction of six to eight days critical path duration during the seventh refueling outage.
TE requested information from the station battery manufacturer on the validity of using less than two amps battery charging current as indication of sufficient charge on the station battery as discussed in the IEEE Standard. In February 1991, the manufacturer conducted testing to determine the state of charge on a battery if, following a battery service or performance discharge test, a battery is recharged until a battery charging current of less than two amps is reached. The manufacturer stated that at this point, a battery, such as the station battery, vould be approximately 95 percent fully charged.
The current station battery has a 20-year design life and is certified by the manufacturer for a nuclear service life of 16 years. The station battery was sized to include a 25 percent margin to account for aging. TE has reviewed the station battery loading calculations and has determined that even including the 95 percent factor discussed above, the station battery vill still be able to satisfy its design load requirements at the
Docket Number 50-346 License Number NPF-3 Serial Number 1898
- Attachment Page 2 end of service life. Thus, for the purpose of determining station battery operability following a battery service or performance discharge test, the utilization of a battery charging current of less than two amps when on a float charge is an acccotable alternative to the use of specific gravities.
A revision is proposed for the associated TS Bases 3/4.0, " Electrical Power Systems", to state, consistent with the proposed TS Table 4.8-1 changes, that a stabilized battery charging current may be used in lieu of specific gravities after battery service or performance discharge tests.
This LAR is similar to a revised TS approved by the NRC for the Grand Gulf Nuclear Power Station, Unit 1, Facility Operating License No. NPW29, as Amendment 29, dated October 9, 1990 (TAC No. 77294). It is also similar to the guidance provided by the NRC to Toledo Edison in their July 16, 1981 letter (TE letter Log Number 756).
SYSTEMS, COMPONENTS, AND ACTIVITIES AFFECTED:
This LAR affects the battery service and performance discharge surveillance testing for the station battery.
SAFETY FUNCTIONS OF THE AFFECTED SYSTEMS, COHp0NENTS AND ACTIVITIES:
Davis-Besse has four 125 VDC 1500 ampere-hour (based on an eight hour discharge) lead-acid batteries arranged to form two independent 250/125 VDC systems. Each battery is normally maintained in a fully charged condition and is normally float charged at approximately 132 volts from its associated battery charger. Battery discharge vill occur either when the DC requituments temporarily exceed the charger capacity or during a loss of a battery charger supply. The battery with the largest load vas used in sizing the capacity and ampere rating of all four batteries. The batteries are sized to supply the anticipated DC and instrument AC supply for a period of one hour after the loss of the battery charger supply. The one-minute rating of the batteries includes starting current requirements of the DC motors, diesel generator flashing, and current requirements for operation of the 13.8ky, 4.16ky, and 400v breakers and all continuous loads. A twenty-five percent over-capacity was designed into the sizing to account for the loss of battery capability over the 20-year design life due to battery aging.
The safety function of the battery service and performance discharge surveillance testing is to ensure that the station battery has sufficient capacity to supply the intended loads and to determine degradation when compared to the rated capacity and previous test data. The quantotiv surveillance testing is used to measure specifie parameters to enrute the station battery is fully charged following the battery service and performance discharge tests.
EFFECTS ON SAFETY:
The station battery is presently subjected to a battery service test once every 18 months and a performance discharge test once every 60 months per SR 4.8.2.3.2.d and e, respectively. Although the station battery may be
Docket Hunber 50-346
, License Number NPF-3 Seria) Number 1898 Attachment Page 3 fully charged following a battery service or performance discharge test, the present vording of Table 4.8 1 requirements for specific gravity measurements vould require several days delay vhile avatting specific gravity stabilization. The use of charging current as an indientor of the battery's state of charge is discussed in Appendix B to IEEE Standard 450-1980. TS Bases 3/4.8, " Electrical power Systems", references this IEEE Standard as providing the basis for the surveillance requirements for TS 4.8.2.3 and TS 4.8.2.4 The IEEE Standard indicates that an acceptable equivalent method for ensuring sufficient charge following a discharge test is the use of a stabilized battery charging current at float voltage.
The specific gravity of the battery drops during a discharge test, and on ,
the subsequent recharge, it is typical for the measured specific gravity to '
lag behind true specific gravity. This is caused by the generation of high specific gravity sulfuric acid during the recharging process that sinks to the bottom of the cell. This stratification phenomenon vill cause incorrect measured specific gravity readings. Several days are required for diffusion to equalize the specific gravity throughout the battery cells.
The battery charging current is a more accurate indicator of the battery's state of charge following n discharge tert. Battery charging current at the beginnisig of a recharge is typically several hundred amps. As the hattety approaches full charge, the battery voltage rises to the chcrger output voltage ar.d the charging current decreases to a stabilized value. Vhen the charger current has stabilized, the battery is charged, even though specific gravity readings vill not confirm the true state of the battery for several days. Both the Grand Gulf amendment and the July 16, 1981 NRC guidance utilize a battery charging current of less than 2 amps as indication of a stabilized battery charging current. Allowing the use of the battery l cnarging current as un indicator of the state of the battery charge vould resolve the delays in returning the battery to an operable status associated with vaiting for specific gravities to stabilize following battery service or performance discharge testing. Since the use of battery charcing current in lieu of specific gravities under these conditions is an equivalent, alternate method, margins of safety are not affected.
Accordingly, the proposed revision to Table 4.0-1 to allov the use of a stable battery charging current of less than 2 amps when on a float charge in lieu of specific gravities for determining station battery operability following a battery service or performance discharge test has no effect on safety.
SIGNIFICANT HAZARDS CONSIDERATION:
The NRC has provided standards in 10 JFR 50.92(c) for determining whethei a significant hazard exists due to a proposed amendment to an opera'ing l C
License for a facility. A proposed amendment involves no significant l hazards consideration if operation of the facility in accordance with the l proposed shenges vouldi (1) Not involve a significant increase in the ;
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- < Docket Number 50 346 l
License Number NpF-3 a
Serial Number 1898 i Attachment Page 4 probability or consequences of an accident previously evaluatedt (2) Not create the possibility of a nov or different kind of accident from any previously evaluated or (3) Not involve a significant reduction in a margin of safety. Toledo Edison has reviewed the proposed changes and determined that a significant hazards consideration does not exist because operation of the DBNpS in accordance with these changes vouldt i la. Not involve a significant increase in the probability of an
- accident previously evaluated because the use of a stable battery charging current of less than two amps when on a float charge is an acceptable, equivalent method of determining station battery operability following a battery service or performance discharge test. Batteries determined operable are capable of petforming their intended function and there is no associated nignificant increase in the probability of an accident.
Ib. Not involve a significant increase in the consequences of an i
accident previously evaluated because the use of a stable battery charging current of less than tvo amps when on a float charge is an acceptable, equivalent method of determining station battery operability following a battery service or performance discharge test. Batteries determined operable are capable of performlag their intended function and there is no associated significant increase in the consequences of an accident.
2a. Not create the possibility of a new kind of accident from any accident previously evaluated because this change proposes an alternate, equivalent method of determining station battery operability following a battery service or performance discharge test. No modifleations are being made to the butteries, the charging equipment, or the distribution system.
2b. Not create the possibility of a different kind of accident from any accident previously evaluated because this change proposes an alternate, equivalent method of determining station battery operability following a battery service or performance discharge
- test. No modifications are being made to the batteries, the charging equipment, or the distribution system.
- 3. Not involve a significant reduction in a margin of safety because the use of the station battery charging current as an indicator of the state of the battery charge following battery service or i performance discharge testing is alloved by 1EEE 450-1980 which is referenced in the TS Bases Section as the basis for the battoiv surveillance requirements. As verified by the battery manufacturer, a battery chatging current of less than two ampo indicates the battery is approximately 95 percent fully changed.
This value, when taken into consideration with the design matgins and the loading calculations for station battery capacity anfi servhc life, ensure that the station bat tery vill be capable of meetins its design load requirements throughout its servlee life.
l Therefare, t.e margin of safety is not significantly reduced.
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Docket Nu:bar 50-346
, Lietns Numb 3r NPF-3 Setial Number 1998
- Attachment Page 5
, CONCLUSION:
- On the basis of the above, Toledo Edison has determined that the License Amendment Request does not involve a significant hazards consideration. As this License Amendment Request concerns 1roposed changes to the Technical Specifications that must be reviewed by the Nuclear Regulatory Commission, this License Amendment Request does not coa 9titute an unrevieved safety question.
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ATTACHHL3:
Attached are the proposed marked-up changes to the operating License.
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