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MONTHYEARML20129D4581985-07-26026 July 1985 Package Consisting of Sequence of Events Reviews Re 850609 Event Project stage: Request ML20138R8341985-11-0404 November 1985 Requests Submittal of Revised Application for Amend to License NPF-3,changing Tech Specs to Require Nuclear Review Board Rept to & Advise Senior Vice President,Nuclear Project stage: Other ML20215L6681986-10-22022 October 1986 Revised Application for Amend to License NPF-3,changing Tech Specs to Reflect Administrative & Organizational Changes for Consistency W/B&W Rev 4 to NUREG-0103, Sts Project stage: Request ML20215L6601986-10-22022 October 1986 Forwards Revised Application for Amend to License NPF-3, Changing Tech Specs to Reflect Administrative & Organizational Changes for Consistency W/B&W Rev 4 to NUREG-0103, Sts Project stage: Request ML20213G6171986-11-13013 November 1986 Requests That Amend to License NPF-3 Re Administrative & Organizational Changes Be Issued W/Footnote Added to Tech Spec 6.2.2d Rather than Tech Spec 6.2.2b for Consistency W/B&W STS (Rev 4 to NUREG-0103) Project stage: Other ML20213H1531986-11-14014 November 1986 Requests Fee for 861022 Application Requesting Approval of Certain Administrative & Organizational Changes at Facility Project stage: Other 1986-10-22
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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
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APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE NO. NPF-3 FOR DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 Enclosed are forty-three (43) copies of the requested changes to the Davis-Besse Nuclear Power Station Unit No. 1 Facility Operating License No. NPF-3. Also included are the Safety Evaluation and Significant Hazards Consideration.
The proposed changes submitted under cover letter Serial No. 1313 include Sections 6.1.1; 6.2.2 and Figure 6.2-1; 6.2.2 and Figure 6.2-2; 6.2.2d; 6.2.2f; 6.2.3; 6.3.1; 6.4.1; 6.5.1.1; 6.5.1.2; 6.5.1.7c; 6.5.1.8; 6.5.2.9; 6.5.2.10a-c; 6.6.1b; 6.7.lb; 6.7.1d; and 6.8.
By ,
~
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enior Vice Presid , Nuclear 8610290238 861022 PDR ADOCK 05000346 p PDR Sworn to and subscribed before me this 22nd day of October, 1986.
L Illbf r . lA Notary Public, State of Ohio My Commission Expires /. /
~ - - - - - - - - -
4 Docket No. 50-346 License No. NPF-3 Serial No. 1313 October 22, 1986 Attachment The following information is provided to support issuance of the requested changes to the Davis-Besse Nuclear Power Station Unit No. 1, Operating License NPF-3, Appendix A, Technical Specifications, Sections 6.1.1; 6.2.2 and Figure 6.2-1; 6.2.2 and Figure 6.2-2; 6.2.2d; 6.2.2f; 6.2.3; 6.3.1; 6.4.1; 6.5.1.1; 6.5.1.2; 6.5.1.7c; 6.5.1.8; 6.5.2.9; 6.5.2.10a-c; 6.6.lb; 6.7.lb; 6.7.1d; and 6.8.
A. Time Required to Implement: This change is to be effective itnediately upon NRC issuance of the License Amendment.
B. Reason for change (Facility Change Request 85-0282, Revision C):
The proposed changes are to: revise the reporting and advising relationship between the Company Nuclear Review Board (CNRB) and the i
President and Chief Operating Officer and Senior Vice President, ,
Nuclear; revise specific sections to be more consistent with the Babcock and Wilcox Standard Technical Specifications, NUREG-0103, Revision 4; revise composition of the Station Review Board (SRB) to expand the range of expertise on the SRB and to reflect recent individual and/or group responsibility, organization, and title changes; and revisa organizational position titles and position responsibilities.
C. Safety Evaluation: See attached Safety Evaluation.
D. Significant Hazards Consideration: See attached Significant Hazards Consideration.
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l a
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Docket No. 50-346 License No. NPF-3 Serial No. 1313 October 22, 1986 Attachment SAFETY EVALUATION l
Section 6 to the Davis-Besse Nuclear Power Station Unit No. 1 Operating License, Appendix A, Technical Specifications, concerns administrative controls. Administrative controls are the provisions of the license relating to organization, procedures, record keeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner.
PROPOSED AMENDMENT REQUEST The proposed license amendment request revises the following sections of the Davis-Besse Nuclear Power Station Unit No. 1 Operating License, Appendix A, Technical Specifications:
6.1.1 (page 6-1) - Changes title of Plant Superintendent to Plant Manager.
This is an administrative change.
6.2.2d (page 6-1) - Applies footnote "#" for consistency with Babcock and 4 Wilcox Standard Technical Specifications, NUREG-0103, Revision 4.
Footnote "**" on page 6 Deletes footnote to 6.2.2f which has expired.
. Therefore, this is an administrative change.
Footnote "#" on page 6 Revises to include individual qualified in radiation protection procedures and revises wording to be more consistent with the Babcock and Wilcox Standard Technical Specifications, NUREG-0103, l Revision 4.
Figure 6.2 Abbreviates the offsite/onsite organization chart (entire page is revised). This change reflects title and position changes under the recent organizational change to enhance management effectiveness.
Figure 6.2.2 - Revised to show the organizational structure and lines of-responsibility for the plant operations staff, including licensed person-
}
nel (entire page is revised).
! 6.2.3 (page 6-4a) - Changes title of Superintendent to Plant Manager.
This is an administrative change.
6.3.1 (page 6-5) - Changes title of Radiation Protection Manager to Chemistry and Health Physics General Superintendent. This is an adminis-trative change.
J 6.4.1 (page 6-5) - Changes title of Nuclear Training Manager to Nuclear Training Director. This is a change reflective of increased responsibili-ty to increase management effectiveness.
- 6.5.1.1 (page 6-5) - Changes title of Station Superintendent to Plant Manager. This is an administrative change.
Dockat No. 50-346 License No. NPF-3 Serial No. 1313 October 22, 1986 Attachment 6.5.1.2 (page 6-6) - Insert "A" changes composition of the Station Review Board (SRB). This reflects changes in title of individual SRB members and changes in individual responsibility due to recent organization changes.
6.5.1.7c and 6.5.1.8 (page 6-8) - Replaces Vice President, Nuclear with Senior Vice President, Nuclear. Reflects change in title due to organiza-tional changes.
6.5.2.9 and 6.5.2.10a, b and c (page 6-12) - Replaces President and Chief Operating Officer with Senior Vice President, Nuclear. Reflects change in renponsibility due to organizational changes and is consistent with the intent of Babcock and Wilcox Standard Technical Specifications, NUREG-0103, Revision 4.
6.6.lb (page 6-12) - Replaces Vice President. Nuclear with Senior Vice President, Nuclear. Reflects change in title due to organizational changes.
6.7.lb (page 6-13) - Changes to reflect 10CFR50.72(a) requirements to notify NRC Operations Center within one hour, which is consistent with the Babcock and Wilcox Standard Technical Specifications, NUREG-0103, Revision 4.
6.7.1d (page 6-13) - Replaces Vice President, Nuclear with Senior Vice President, Nuclear. Reflects change in title due to organizational changes.
6.8 (page 6-13) - Adds "And Programs" to be consistent with Babcock and Wilcox Standard Technical Specifications, NUREG-0103, Revision 4. Accord-ingly, this is an administrative change.
PROPOSED AMENDMENT REQUEST DISCUSSION The safety function of the Station Review Board (SRB), as described in Section 6.5.1.1, is to advise the Plant Manager on all matters related to nuclear safety. The composition of the SRB ensures that the SRB can adequately perform its safety function. The proposed change in Section 6.5.1.2 will incorporate the Toledo Edison organization and managerial title changes as identified above.
The change in SRB composition replaces three members - Lead Instrument and Control Engineer, Nuclear and Performance Engineer, and Nuclear Reliabil-ity Manager. The areas of responsibility for these three SRB members are still represented by their immediate supervisor's SRB membership. Howev-er, the three members replacing those deleted expand the overall areas of expertise represented on the SRB. The addition of the Operations Quality Assurance Manager, represents an area that was not previously present in the SRB. The other two additions, Technical Support Manager and Plant Operations Engineering Supervisor, represent diverse facets of direct plant and administrative and operations responsibility.
The SRB Chairman will be designated in writing, from among the members, by the Plant Manager, adding flexibility to this position.
Docket No. 50-346 License No. NPF-3 Serial No. 1313 October 22, 1986 Attachment Therefore, the proposed changes to the SRB are either organizational in nature, designed to expand the range of expertise on the SRB, or reflect recent individual and/or group responsibility, organizational, and title changes.
The safety function of Sections 6.5.1.8, Records, 6.5.2.9, Authority, 6.5.2.10, Records and 6.7.1, Safety Limit Violation is to provide manage-ment oversight of the minutes, audits and reviews to verify that operation of the facility is performed in a safe manner and is consistent with Company policy, approved procedures and ifcense provisions; to review important proposed changes to the facility, tests and procedures; and to verify that unusual occurrences are promptly investigated and their causes are corrected in a manner that reduces the probability of recurrence.
On July 1, 1985, a management organization change occurred at Toledo Edison in which the President and Chief Operating Officer retired and a replacement was named. At that time, the position of Senior Vice Presi-dent, Nuclear was established replacing the position of Vice President, Nuclear. Sections 6.5.1.7c, 6.5.1.8, 6.6.1b and 6.7.1d reflect this change by replacing Vice President, Nuclear with Senior Vice President, Nuclear.
With the enclosed modification, the CNRB will report directly to the Senior Vice President Nuclear, who reports directly to the President and Chief Operating Officer. This changes the CNRB reporting requirements for Audits and Reviews (Section 6.5.2.9) and Records (Section 6.5.2.10) from the President and Chief Operating Officer to Senior Vice President, Nuclear.
This change is consistent with the intent of the Babcock and Wilcox Standard Technical Specifications, NUREC-0103, Revision 4.
DISCUSSION OF UNREVIEWED SAFETY QUESTION The proposed changes are administrative in nature, broaden the Station Review Board expertise or enhance management effectiveness of the Davis-Besse Nuclear Power Station, Unit No. 1. Implementation of these changes would not:
j 1. Increase the probability of occurrence or the consequences of an i
accident or malfunction of equipment important to safety previously l
evaluated in the safety analysis report (10CFR50.59 (2) (1)) .
l The proposed changes are either administrative, broaden the Station Review Board expertise or enhance management effectiveness and do not increase the probability or consequences of an accident previously I evaluated.
- 2. Create the possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report (10CFR50.59 (2) (ii)) .
The changes involve no accident or malfunction scenario. On matters related to nuclear safety, all accidents are bounded by previous analysis and no new accidents are involved.
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Docket No. 50-346 .
License No. NPF-3 Serial No. 1313
! October 22, 1986 Attachment
- 3. Reduce the margin of safety as defined in the basis for any Technical ,
Specification (10CFR50.59(2)(iii)). l The proposed changes are administrative or enhance management effec- !
tiveness and oversight and will not reduce the nargin of safety.
I Based on the above evaluation, it is determined that this revision does
- not involve an unreviewed safety question.
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Docket No. 50-346 License No. NPF-3 Serial No. 1313 t'etober 22, 1986 Attachment Significant Hazards Consideration The proposed amendment request involves the following changes:
6.1.1 (page 6-1) - Changes title of Plant Superintendent to Plant Manager. This is an administrative change.
6.2.2d (page 6-1) - Applies footnote "#" for consistency with Babcock and Wilcox Standard Technical Specifications, NUREG-0103, Revision 4.
Footnote "**" on page 6 Deletes footnote to 6.2.2f which has expired.
Therefore, this is an administrative change.
Footnote "#" on page 6 Revises to include individual qualified in radiation protection procedures and revises wording to be more consistent with the Babcock and Wilcox Standard Technical Specifications , NUREG-0103, Revision 4.
Figure 6.2 Abbreviates the offsite/onsite organization chart (entire page is revised). This change reflects title and position changes under the recent organizational change to enhance management effectiveness.
Figure 6.2.2 - Revised to show the organizational structure and lines of responsibility for the plant operatione staff, including licensed personnel (entire page is revised).
6.2.3 (page 6-4a) - Changes title of Superintendent to Plant Manager.
This is an administrative change.
6.3.1 (page 6-5) - Changes title of Radiation Protection Manager to Chemistry and Health Physics General Superintendent. This is an administrative change.
6.4.1 (page 6-5) - Changes title of Nuclear Training Manager to Nuclear Training Director. This is a change reflective of increased responsi-bility to increase management effectiveness.
6.5.1.1 (page 6-5) - Changes title of Station Superintendent to Plant Manager. This is an administrative change.
6.5.1.2 (page 6-6) - Insert "A" changes composition of the Station Review Board (SRB). This reflects changes in title of individual SRB members and changes in individual responsibility due to recent organization changes.
6.5.1.7c and 6.5.1.8 (page 6-8) - Replaces Vice President, Nuclear with Senior Vice President, Nuclear. Reflects change in title due to organiza-tional changes.
Docket No. F3 46 License No. NFF-3 Serial No. 1313 October 22, 1986 Attachment 6.5.2.9 and 6.5.2.10a, b and c (page 6-12) - Replaces President and Chief Operating Officer with Senior Vice President, Nuclear. Reflects change in responsibility due to organizational changes and is consistent with the intent of Babcock and Wilcox Standard Technical Specifications, NUREG-0103, Revision 4.
6.6.1b (page 6-12) - Replaces Vice President, Nuclear with Senior Vice President, Nuclear. Reflects change in title due to organizational i,
changes.
l 6.7.lb (page 6-13) - Changes to reflect 10 CFR 50.72(a) requirements to
< notify NRC Operations Center within one hour, which is consistent with the Babcock and Wilcox Standard Technical Specifications, NUREG-0103, Revision 4.
6.7.1d (page 6-13) - Replaces Vice President, Nuclear with Senior Vice President, Nuclear. Reflects change in title due to organizational changes.
6.8 (page 6-13) - Adds "And Programs" to be consistent with Babcock and Wilcox Standard Technical Specifications, NUREG-0103, Revision 4. Accord-i ingly, this is an administrative change.
The safety function of the Station Review Board (SRB), as described in Section 6.5.1.1, is to advise the Plant Manager on all matters related to nuclear safety. The composition of the SRB ensures that the SRB can adequately perform its safety function. The proposed change in Section
- 6.5.1.2 will incorporate the Tolede Edison organization and managerial title changes as identified above.
The change in SRB composition replaces three members - Lead Instrument i and Control Engineer, Nuclear and Performance Engineer, and Nuclear Reliability Manager. The areas of responsibility for these three SRB
> members are still represented by their immediate supervisor's SRB membership. llowever, the three members replacing those deleted expand the overall areas of expertise represented on the SRB. The addition of the Operations Quality Assurance Manager, represents an area that was not previously present in the SRB. The other two additions, Technical Support Manager and Plant Operations Engineering Supervisor, represent diverse facets of direct plant and administrative and operations responsibility.
The SRB Chairman will be designated in writing, from among the members, by the Plant Manager, adding flexibility to this position.
Therefore, the proponed changes to the SRB are either organizational in nature, designed to expand the range of expertise on the SRB, or reflect recent individual and/or group responsibility, organizational, and title changes.
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Dockat No. 50-346 License No. NPF-3 Serial No. 1313 October 22, 1986 Attachment The safety function of Sections 6.5.1.8, Records, 6.5.2.9, Authority, 6.5.2.10, Records and 6.7.1, Safety Limit Violation is to provide manage-ment oversight of the minutes, audits and reviews to verify that operation of the facility is performed in a safe manner and is consistent with Company policy, approved procedures and license provisions; to review important proposed changes to the facility, tests and procedures; and to verify that unusual occurrences are promptly investigated and their causes are corrected in a manner that reduces the probability of recurrence.
On July 1, 1985, a management organization change occurred at Toledo Edison in which the President and Chief Operating Officer retired and a replacement was named. At that time, the position of Senior Vice Presi-dent, Nuclear was established replacing the position of Vice President, Nuclear. Sections 6.5.1.7c, 6.5.1.8, 6.6.lb and 6.7.1d reflect this change by replacing Vice President, Nuclear with Senior Vice President, Nuclear.
With the enclosed modification, the CNRB will report directly to the Senior Vice President, Nuclear, who reports directly to the President and Chief Operating Officer. This changes the CNRB reporting requirements for Audits and Reviews (Section 6.5.2.9) and Records (Section 6.5.2.10) from the President and Chief Operating Officer to Senior Vice President, Nuclear. This change is consistent with the intent of the Babcock and Wilcox Standard Technical Specifications, NUREG-0103, Revision 4 The proposed change does not involve a significant hazards consideration because operation of Davis-Besse Unit No. 1 in accordance with this change would not:
- 1. Involve a significant increase in the probability or consequences of an accident previously evaluated (10CFR50.92(c)(1)).
The proposed changes are either administrative, broaden the Station Review Board expertise, or enhance management effectiveness and are in accordance with the Babcock and Wilcox Standard Technical Specifications, NUREG-0103, Revision 4. This amendment request does not increase the probability or consequencen of an accident previously evaluated.
- 2. Create the possibility of a new or different kind of accident from any previously evaluated (10CFR50.92(c)(2)).
It has been determined that a new or different kind of accident will not be possible due to these changes. All accidents are still bounded by previous analysis and no new accidents are involved.
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i Docket No. 50-346
! License No. NPF-3 i Serial No. 1313 October 22, 1986 Attachment
- 3. Involve a significant reduction in a margin of safety (10 CFR 50.92 (c) (3)) .
l The administrative changes, increase of Station Review Board e expertise, enhanced management effectiveness, and changes to make the Technical Specifications more consistent with the Babcock and Wilcox Standard Technical Specifications, NUREG-0103, Revision 4, will not reduce the margin of safety.
On the basis of the above, Toledo Edison has determined that the
- amendment request does not involve a significant hazards consideration.
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