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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
[Table view] |
Text
r TOLEDO Docket No. 50-346 EDISON License No. NPF-3 Serial No. 1360 DONALD C. SHELTON March 23, 1987 pg%%*
United States Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Gentlemen:
The purpose of this letter is to request a change to the Bases of the Davis-Besse Nuclear Power Station, Unit No. 1 Operating License, Technical Specifications. The proposed changes, included as an attachment to this letter, involve Bases Section 3/4.7.1.2, Auxiliary Feedwater Systems.
The proposed changes are being submitted in accordance with Toledo Edison's commitment in its letter to the NRC, dated November 17, 1986 (Serial No.
1322), to propose a request to reduce the Auxiliary Feedwater (AFW) flow requirement in the AFW Technical Specification Bases Section 3/4.7.1.2, within 90 days after restart of Davis-Besse.
As discussed in the attached Safety Evaluation, the proposed change involves reducing the AFW flow requirement for the steam driven AFW pumps from 800 gpm to 600 gpm based on a recent analysis of AFW flow performed by the Babcock and Wilcox Company for Toledo Edison. This plant-specific analysis demonstrated that adequate cooling was achieved, for a loss of feedwater event, with a nominal AFW flow of 600 gpm at 1050 psig.
The Bases change requested herein does not require the submittal of a License Amendment Request based on the provisions of 10CFR50.36(a), which requires inclusion of Bases for Technical Specifications but indicates such Bases shall not become part of the Technical Specifications.
Toledo Edison requests that the NRC approve this change by May 18, 1987, to be effective upon NRC approval.
Enclosed is a check for $150 as required by 10CFR170.12(c) for an appli-cation fee.
Very truly y,urs, I ,
DCS:JAE: CAB:p1f dr k
Attachments tii 0 0\
GhUgD1 cc: DB-1 NRC Resident Inspector M State of Ohio g\
A. B. Davis, Acting Regional Administrator (2 copies)
A. W. DeAgazio, NRC/NRR Davis-Besse Project Manager THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652 87040;10046 870323 PDR ADOCK 05000346 P PDR
D:ck:t No. 50-346 License No. NPF-3 Serial No. 1360 Attachment 1 Page 1 SAFETY EVALUATION DESCRIPTION OF PROPOSED ACTIVITIES This Bases change request, as committed to by letter dated November 17, 1986 (Serial No. 1322) from J. Williams, Jr. (Toledo Edison) to J. F. Stolz (NRC), is to change Technical Specification Bases 3/4.7.1.2 pertaining to the Auxiliary Feedwater (AFW) System. This request proposes lowering the AFW flow requirement for each steam driven Auxiliary Feedwater Pump (AFP) from 800 gpm to 600 gpm at a pressure of 1050 psig at the entrance to the steam generators. This request is a result of recent ana!ysis performed by the Babcock and Wilcox Company (B&W) for Toledo Edison.
SYSTEMS AFFECTED The AFW System consists of two steam turbine-driven feedwater pumps, condensate storage tanks, suction and discharge water piping, steam piping, valves and associated instrumentation and controls. The pumps can take suction from the condensate storage tanks, the fire protection system, and from the Class I service water system. The condensate storage capacity is sized so that the minimum total condensate inventory available to the pumps is sufficient to remove decay heat for approx-imately thirteen hours plus a subsequent cooldown to 280*F. Following a complete loes of normal and reserve power the AFW System supplies water directly to the steam generators through the AFW nozzles to remove reactor decay heat. Reactor decay heat removal in the absence of the reactor coolant pumps is provided by the natural circulation characteristics of cl.e Reactor Coolant System (RCS). Use of the AFW System for cooldown is discontinued when the RCS temperature decreases to about 280*F; further cooldown is accomplished by the Decay Heat Removal System.
Reducing the AFW flow requirement does not alter the present configuration of the s" stem. Analysis, as described below, ensures that this change maintains an adequate AFW flow to remove core decay heat. Therefore, lowering the AFW flow does not increase the demand placed on any system.
DOCUMENTS AFFECTED
- 1. Technical Specification Bases 3/4.7.1.2
- 2. USAR Section 9.2.7
- 3. USAR Section 15.2.8 SAFETY FUNCTION OF SYSTEM AFFECTED The safety function of the AFW System is to provide feedwater to the steam generators for the removal of reactor decay heat in the absence of main feedwater and to promote natural circulation of the RCS in the event of a loss of all four reactor coolant pumps.
I Docket No. 50-346 License No. NPF-3 Serial No. 1360 Attachment 1 Page 2 EFFECTS ON SAFETY The existing Bases states that "each steam driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 800 gpm at a pressure of 1050 psig to the entrance of the steam generators". The Basis goes on to say that "this capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 280*F...". This latter quote also defines the function of the AFW System. This definition of function is unaffected by the lower flow requirement.
The performance of the AFW System is described in the USAR Chapter 15 accident analyses for the Loss of Feedwater Transient (Section 15.2.8).
This transient puts more severe design requirements on the AFW System than other transients. The USAR analysis used an AFW flowrate of 800 gpm to be delivered within 40 seconds of actuation of the AFW System.
The analysis performed by B&W in support of reducing the flow requirement, B&W document 32-1159090-01, is the Loss of Feedwater Transient analysis described in USAR Section 15.2.8. The B&W analysis includes the following assumptions:
- 1. Initial reactor power is 102% Full Power
- 2. No credit for PORV, pressurizer sprays, or make-up flows
- 3. 1.2 times ANS 5.1 (1979) decay heat curve
- 4. Full AFW flow delivered to the steam generator 40 seconds after Steam and Feedwater Rupture Control System (SFRCS) low level setpoint is reached
- 5. SFRCS low level setpoint of 10 inches actual level above lower tubesheet
- 6. Offsite power is available during event. Therefore, RCS pumps continue to operate
- 7. Turbine trip due to reactor trip Consistent with the USAR Chapter 15 acceptance criteria, the acceptance criteria for this B&W analysis are:
- 1. No fuel damage
- 2. RCS pressure does not exceed 2750 psig In this analysis, the initiating event is a failure of the main feedwater control valves with a subsequent ramp reduction to zero flow in seven seconds. During the feedwater reduction, the temperature and pressure in the RCS begins to increase and continues until the high pressure trip setpoint of 2400 psia is reached and the reactor trips at approximately 14 seconds into the event. RCS pressure is then controlled by the pressurizer safety valves. This ar.alysis initiates the turbine trip one second following the reactor trip with the turbine stop valves ramping closed during the next second for a total of two seconds from reactor trip to valve closure. At this point, the secondary side pressure is maintained by the main steam safety valves while the steam generator
~
Dockat No. 50-346 License No. NPF-3 Serial No. 1360 Attachment 1 Page 3 inventory is boiling down. When the low level setpoint of 10 inches (collapsed liquid level) in the steam generator is reached, SFRCS is initiated. This occurs at approximately 25.6 seconds into the event.
Full flow AFW reaches the steam generator 40 seconds later with AFW feeding only one steam generator due to single failure considerations.
The AFW flow curve used, based on previous analyses, provides a flow of 600 gpm at a 1050 psig steam generator pressure.
As can be seen from Figures A and B respectively, by 170 seconds into the event a sufficient water level is established in the steam generator to terminate the temperature rise in the RCS and to establish RCS cooldown.
In other words, the AFW flow is sufficient for the removal of core decay heat and subsequent cooldown to 280*F. Since the RCS remains subcooled throughout the event with no temperature or power excursions which approach the 112% full power limit, there is no fuel damage. Figure C shows the peak RCS pressure was limited to approximately 2590 psia which is below the safety limit of 110% of design pressure (2750 psig). There-fore, the USAR Chapter 15 acceptance criteria have been met. Figure D shows the maximum pressurizer level reached was approximately 350 inches as measured from a zero point 30 inches above the top of the tap. The pressurizer level did exceed the high end of the scale. However, the pressurizer maintained a steam bubble at all times during the event, (approximately four vertical feet remaining). This analysis is conserva-tive in that the modeling techniques do not consider any cooling of the RCS due to AFW impinging on the steam generator tubes.
Since the Loss of Feedwater is a bounding transient for the AFW System requirements and has been analyzed with acceptable results, the conse-quences of all other transients requiring AFW are also acceptable.
UNREVIEWED SAFETY QUESTION EVALUATION The proposed action would not increase the probability of an accident previously evaluated in the USAR because there have been no design changes (10CFR50.59(a)(2)(1)) .
The proposed action would not increase the consequences of an accident previously evaluated in the USAR because the analysis, performed for the Loss of Feedwater Transient, has shown the reduced flow capable of removing decay heat and meeting the USAR Chapter 15 acceptance criteria.
Thus, although the results are different, the consequences are acceptable (I OCFR50.59(a) (2) (1)) .
The proposed action would not increase the probability of a malfunction of equipment important to safety because there have been no design changes (10CFR50.59(a)(2)(1)).
The proposed action would not increase the consequences of a malfunction of equipment important to safety because analysis has shown, that with different but acceptable consequences, the lower flow is capable of removing decay heat and cooling the reactor core (10CFR50.59(a)(2)(i)).
- .~ ~ . .- - .. .. .- . .- .
Docket No. 50-34'6 4
- . License No.
- NPF-3 Serial No. 1360 Attachment 1 Page 4
} The proposed cetion would not create a possibility for an accident of a ,
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different type than any evaluated previously in the USAR because there:
have been no design changes and analysis has shown the lower flow capable of removing decay heat and cooling the core (10CFR50.59(a)(2)(ii)).
i The proposed action would not create a possibility for a malfunction of equipment of a different type than any evaluated previously in the USAR i because there have been no design changes (10CFR50.59(a)(2)(ii)).
i -
The proposed action would not reduce the margin of safety as defined in
< the basis for the Technical Specification. Lowering the AFW flow does 1 increase the RCS temperature and pressurizer level over.that previously analyzed for this specific event but the results meet the USAR Chapter 15 l_ acceptance criteria and are bounded by other Chapter.15 analysis (rod i withdrawal accident for pressure and LOCA for fuel temperature). There-
! . fore, lowering the AFW flow does not reduce the overall margin of safety I as analyzed for thCs plant and consequently does not impact the intent of the Bases (10CFR50.59(a)(2)(iii)).
CONCLUSION Pursuant to the above, this change to Technical Specification Bases
- 3/4.7.1.2 does not change the intent of the Bases and does not involve an.
! unreviewed safety question by Toledo Edison. In addition, the NRC has l previously reviewed the issue of a reduced AFW flow requirement for other
{ B&W reactors and granted AFW flow reductions.- Therefore, this change does not involve an unreviewed safety question.
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