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 SpecifiedML20117M197 |
Person / Time |
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Site: |
Davis Besse ![Cleveland Electric icon.png](/w/images/7/78/Cleveland_Electric_icon.png) |
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Issue date: |
09/04/1996 |
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From: |
Jeffery Wood CENTERIOR ENERGY |
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To: |
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Shared Package |
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ML20117M170 |
List: |
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References |
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2402, NUDOCS 9609170334 |
Download: ML20117M197 (8) |
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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
,
Docket Number 50-346 1
- License Number NPF-3 Sarial Number 2402
. Enclosure )
Page 1 l APPLICATION FOR AMENDMENT TO l
FACILITY OPERATING LICENSE NUMBER NPF-3 l DAVIS-BESSE NUCLEAR POVER STATION UNIT NUMBER 1 l
l Attached is the requested change to the Davis-Besse Nuclear Power Station, Unit Number 1 Facility Operating License Number NPF-3. Also included is l the Safety Assessment and Significant Hazards Consideration.
The proposed change (submitted under cover letter Serial Number 2402) concerns: j 1
Appendix A, Technical Specifications (TS):
TS 6.2.3 Facility Staff Overtime j By:
J. K[ Wood, Vice P're'sident - Nuclear Sworn to and subscribed before me this 4th day of September, 1996.
M pm /&
Notary Public, State of Ohio My commission expires 9/3/97.
9609170334 960904 PDR ADOCK 05000346 p PDR
. _ - . - . _ - _ . . . - . - . ~ . . - . . .
pocket Numbei 50-346 License Number NPF-3 Serial Number 2402
. Enclosure Page 2 The following information is provided to support issuance of the requested revision to the Davis-Besse Nuclear Power Station (DBNPS), Unit Number 1 Operating License NPF-3, Appendix A, Technical Specifications. The revision involves changes to TS 6.2.3, Facility Staff Overtime, and i relocation of specific overtime limits and working hours to the DBNPS l Updated Safety Analysis Report (USAR) Technical Requirements Manual (TRM). I Technical Specification 6.2.3, Facility Staff Overtime, contains the j specific controls to limit overtime hours and working hours for facility ;
staff who perform safety-related functions. <
A. Time Required to Implement: This change is to be implemented within 90 days after NRC issuance of the License Amendment. l B. Reason for Change (License Amendment Request 96-0011): Portions of TS 6.2.3 may be relocated to the DBNPS Updated Safety Analysis Report (USAR) consistent with the NRC's recent determination that specific overtime limits and working hours need not be specified within the TS.
Future proposed changes to limits and working hours may then be evaluated in accordance with 10 CFR 50.59 and implemented if an unreviewed safety question or Technical Specification change is not involved.
C. Safety Assessment and Significant Hazards Consideration. (See Attachment). 7
Docket Number 50-346 License Number NPF-3 Serial Number 2402 Attachment SAFETY ASSESSMENT AND SIGNIFICANT HAZARDS CONSIDERATION FOR LICENSE AMENDMENT REQUEST 96-0011 (6 pages follow) 1 I
l 2
i
4 f .
l LAR 96-0011
~
s Page 1 i
i e
SAFETY ASSESSMENT AND SIGNIFICANT HAZARDS CONSIDERATION l FOR LICENSE AMENDMENT REQUEST NUMBER j 96-0011 TITLE:
Proposed Revision to the Davis-Besse Nuclear Power Station (DBNPS)
Operating License NPF-3, Appendix A, Technical Specifications to Change j Technical Specification (TS) 6.2.3, Facility Staff Overtime i
DESCRIPTION:
i The purpose of this License Amendment Request is to revise the Davis-Besse j Nuclear Power Station (DBNPS) Operating License NPF-3, Appendix A,
- Technical Specifications (TS) by changing TS 6.2.3, Facility Staff Overtime, and relocating portions of it to the DBNPS Updated Safety 1 Analysis Report (USAR) Technical Requirements Manual (TRM). This revision
! will allow the DBNPS to evaluate future proposed changes to specific
! overtime limits and working hours under Section 50.59, " Changes, Tests and i Experiments," of Title 10 of the Code of Federal Regulations (10CFR), and
- implement those changes which are not an unreviewed safety question or do
{ not involve a change to a TS.
l The attached markup of TS 6.2.3 shows which requirements are being removed and the text being added to facilitate this removal. The added text is editorial, with an exception being that a new requirement has been added
} for procedures to ensure that an individual's overtime is reviewed monthly l by the Plant Manager or his designee (s) to ensure that excessive hours have i
not been worked. As discussed under " Effects on Safety' below, this requirement being proposed for inclusion in TS 6.2.3 is eensistent irith the j latest NRC guidance which also determined that specific overtime littits and j working hours need not be specified within the TS.
SYSTEMS, COMPONENTS, AND ACTIVITIES AFFECTED:
This proposed license amendment affects the TS Administrative Controls for facility staff overtime.
FUNCTIONS OF THE AFFECTED SYSTEMS, COMPONENTS, AND ACTIVITIES The overall function of the Operating License, Appendix A, TS is to impose ~
those conditions or limitations u,on reactor operation necessary to pre-serve the validity of the res'h af USAR design bases accidents. The function of the TS Section 6 Aaministration Controls, is to provide provi-sions relating to organization and management, procedures, record keeping, review, audit, and reporting necessary to assure plant operation in a safe manner.
LAR 96-0011 Page 2 The function of staff overtime limits is to prevent situations where fatigue could reduce the ability of operating personnel to maintain the plant in a safe condition. These limits apply to plant staff who perform safety-related functions, and are established to assure that personnel are not assigned to shift duties while in a fatigued condition that could significantly reduce their mental alertness or their decision-making ability.
EFFECTS ON SAFETY Facility staff overtime is described in DBNPS USAR Section 13.0, " Conduct of Operations," as controlled by administrative procedures to limit over-time hours for staff who perform safety-related functions. The USAR also states that these limits are in accordance with NUREG-0737, " Clarification of THI Action Plan Requirements," and NRC Generic Letter 82-12, " Nuclear Power Plant Staff Vorking Hours." The proposed revision to TS 6.2.3 retains control of overtime by the use of administrative procedures, that in turn, generally follow the guidance of NUREG-0737 and Generic Letter 82-12. The proposed revision is also consistent with the NRC guidance for changing and relocating TS specific overtime limits and working hours as discussed below.
10 CFR Section 50.36 establishes the regulatory requirements for licensees to include TS as part of applications for operating licenses. In addition, the Nuclear Regulatory Commission's " Final Policy Statement on Technical Specification Improvements for Nuclear Power Reactors," dated July 22, 1993, and other NRC documents provide guidance regarding the required content of TS. The fundamental purpose of the TS, as described in the j NRC's Final Policy Statement, is to impose those conditions or limitations upon reactor operation necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety. This is accomplished by identifying those features that are of controlling importance to nuclear safety and establishing on them certain TS conditions of operation which cannot be changed without prior NRC approval.
The NRC's Final Policy Statement recognized, as had previous statements related to the NRC Staff's TS Improvement Program, that implementation of the policy would result in the relocation of some existing TS requirements to licensee-controlled documents such as the USAR. Those items relocated to the USAR vould, in turn, be controlled in accordance with the requirements of 10 CFR Section 50.59. 10 CFR Section 50.59 provides criteria to determine when facility or operating changes planned by a licensee require prior NRC approval in the form of a license amendment in order to address any unreviewed safety questions or TS changes. l The proposed changes and relocation is consistent with the NRC's recent determination, on a generic basis, that specific overtime limits and working hours need not be specified within the TS. This determination was documented in the NRC's Staff's Safety Evaluation for Amendment Numbers 127 and 116 (NRC TAC Numbers M86191 and M86192) to the Operating Licenses (Numbers NPF-10 and NPF-15) for the Southern California Edison Company's
LAR 96-0011 Page 3 San Onofre Nuclear Generating Station (SONGS) Units 2 and 3, approved February 9, 1996. This generic change vill be incorporated in a future revision to the NRC's " Improved Standard Technical Specifications" by the NRC Staff.
The specific overtime limits and working hours currently contained in TS 6.2.3 vill be relocated to the USAR TRM. The new requirement being added to TS 6.2.3, that plant procedures require individual overtime be reviewed monthly by the Plant Manager or his designee (s) to ensure that excessive hours have not been worked, is currently being met by the practice of supervisors reviewing individual's overtime reports on a weekly basis. The other changes to TS 6.2.3 are editorial and do not change any requirements.
Overtime vill remain controlled by plant administrative procedures and the USAR TRH generally following the guidance of the NRC's Policy Statement on working hours contained within Generic Letter 82-12, " Nuclear Power Plant Staff Vorking Hours." Changes to these plant documents vill be evaluated, prior to implementation, in accordance with the requirements of 10 CFR Section 50.59.
In summary, the proposed TS 6.2.3 changes and relocation vill not impact the ability of plant staff who perform safety-related functions, or increase fatigue and reduce the mental alertness or decision-making ability of plant staff. These TS changes are administrative and consistent with guidance from the NRC. Any future changes to these relocated requirements vill be evaluated as required by 10 CFR 50.59. Therefore, there is no adverse effect on safety as a result of these changes and relocation.
SIGNIFICANT HAZARDS CONSIDERATION:
The Nuclear Regulatory Commission has provided standards in 10 CFR Section 50.92(c) for determining whether a significant hazard exists due to a proposed amendment to an Operating License for a facility. A proposed amendment involves no significant hazards consideration if operation of the facility in accordance with the proposed changes would: (1) Not involve a significant increase in the probability or consequences of an accident previously evaluated; (2) Not create the possibility of a new or different kind of accident from any accident 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 Davis-Besse Nuclear Power Station (DBNPS), Unit Number 1, in accordance with these changes vould:
la. Not involve a significant increase in the probability of an accident l previously evaluated because no change is being made to any accident initiator. No previously analyzed accident scenario is changed, and initiating conditions and assumptions remain as previously analyzed.
The proposed change to Technical Specification (TS) 6.2.3, " Facility Staff ;
Overtime," to relocate specific overtime limits and working hours to the !
DLNPS Updated Safety Analysis Report (USAR) is consistent with the NRC Staff's determination previously provided on a generic basis in the Safety
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. LAR 96-0011 Page 4 Evaluation to License Amendment Number 127 and 116 to the Operating Licenses (Number NPF-10 and NPF-15), for the San Onofre Generating Nuclear Station, Units 2 and 3, dated February 9, 1996. The appropriate relocation of TS requirements, such as portions of TS 6.2.3, to licensee-controlled documents is also addressed generically in the NRC's " Final Policy Statement on l Technical Specification Improvements for Nuclear Power Reactors", dated July 23, 1993.
The relocated overtime limits and working hours will be subject to reviev l
' and evaluation under Section 50.59, " Changes, Tests, and Experiments", of Title 10 of the Code of Federal Regulations (10 CFR) prior to any changes being made. The other changes to TS 6.2.3 are editorial, with an exception l being that a new requirement has been added for plant procedures to ensure that an individual's overtime is reviewed monthly by the Plant Manager or his designee (s) to ensure excessive hours have not been assigned.
Overtime vill remain controlled by plant administrative procedures and USAR requirements generally following the guidance of the NRC's Policy Statement I
on working hours contained within Generic Letter 82-12, " Nuclear Power Plant Staff Vorking Hours."
lb. Not involve a significant increase in the consequences of an accident previously evaluated because the proposed changes do not affect accident conditions or assumptions used in evaluating the radiological consequences of an accident. The proposed changes do not alter the source term, containment isolation or allovable radiological releases.
The proposed changes to TS 6.2.3 only alter the administrative location of and the regulatory controls applicable to plant staff specific overtime limits and working hours. Therefore, there is no significant increase in the consequences of an accident previously evaluated.
- 2. Not create the possibility of a new or different kind of accident from any accident previously evaluated because the proposed changes do not change the l vay the plant is operated, and no new or different failure modes have been defined for any plant system or component important to safety, nor has any limiting single failure been identified as a result of the proposed changes.
No new or different types of failures or accident initiators are introduced by the proposed changes.
The proposed changes to TS 6.2.3 only alter the administrative location of and the regulatory controls applicable to plant staff specific overtime limits and working hours. Therefore, there is no possibility created for a new or different kind of accident.
- 3. Not involve a significant reduction in a margin of safety because facility I
staff overtime is not an input in the calculation of any safety margin with l regard to Technical Specification Safety Limits, Limiting Safety System
! Settings, other Technical Specification Limiting Conditions for Operation, I
or other previously defined margins for any structure, system, or component important to safety.
. LAR #6-0011 Page 5 The proposed changes to TS 6.2.3 only alter the administrative location of and the regulatory controls applicable to plant specific overtime limits and working hours. Therefore, there is no significant reduction in a margin of safety.
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 a proposed change to the Technical Specifications that must be reviewed by the Nuclear Regalatory Commission, this License Amendment Request does not constitute an unreviewed safety question.
ATTACHMENT:
Attached are the proposed marked-up changes for the Operating License.
REFERENCES:
- 1. Technical Specification 6.2.3, Facility Staff Overtime.
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- 2. The NRC " Final Policy Statement on Technical Specifications Improvements for !
Nuclear Power Reactors", (58 FR 39132, dated July 22, 1993).
- 3. " Improved Standard Technical Specifications for Babcock and Vilcox Plants," f NUREG-1430, Revision 1, dated April 7, 1995.
- 4. USAR Section 13.0, " Conduct of Operations," through USAR Revision 19. l
- 5. 10 CFR 50.36, " Technical Specifications."
- 6. 10 CFR 50.59, " Changes, Tests, and Experiments."
- 7. NRC Generic Letter 82-12, " Nuclear Power Plant Staff Working Hours," dated June 15, 1982.
- 8. NUREG-0737, " Clarification of TMI Action Plan Requirements", dated October 31, 1980.
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