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MONTHYEARML20137M8701986-01-22022 January 1986 Notifies That Application to Amend License NPF-3,authorizing post-transient Insp of Hydraulic & Mechanical Snubbers Will Be Submitted by 860228.Understanding That 850130 Application Will Be Approved by 860215 Confirmed Project stage: Request ML20140F9071986-03-26026 March 1986 Informs That Deletion of Footnote 6 & Addition of within Specified Range to Proposed Surveillance Requirements 4.7.7.2b & 4.7.7.2c.2,respectively,will Be Incorporated Into Apr 1986 Amend Application,Per NRC 860324 Request Project stage: Other ML20205H6191987-03-12012 March 1987 Discusses Application for Amend to License NPF-3,transmitted Under Separate Cover.Amend Revises Tech Spec 3/4.7.7 by Adding Surveillance Requirement 4.7.7.1e to Provide Insp of All safety-related Snubbers After Dynamic Event.Fee Paid Project stage: Request ML20214J1081987-03-12012 March 1987 Proposed Tech Spec 3/4.7.7,revising Requirements for Snubbers Project stage: Other ML20214J1041987-03-12012 March 1987 Application for Amend to License NPF-3,revising Tech Spec 3/4.7.7, Snubbers Project stage: Request ML20214J0981987-05-19019 May 1987 Forwards Previously Submitted Application for Amend to License NPF-3,involving Tech Spec 3/4.7.7, Snubbers, Per 870513 Request Project stage: Request 1986-03-26
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20216E6051999-09-0707 September 1999 Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation ML20210H0631999-07-28028 July 1999 Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, by Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4131999-07-27027 July 1999 Application for Amend to License NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G8831999-07-26026 July 1999 Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5251999-07-26026 July 1999 Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20210G4631999-07-26026 July 1999 Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumention & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20195F9121999-06-10010 June 1999 Application for Amend to License NPF-3,changing TS 3/4.6.4.4 Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20207E7861999-05-21021 May 1999 Application for Amend to License NPF-3,allowing Use of Expanded Spent Fuel Storage Capability ML20205E4961999-03-19019 March 1999 Application for Amend to License NPF-3,requesting Withdrawal of Proposed New Action B to TS 3.6.5.2,previously Submitted in 981027 Application ML20204F1691999-03-0909 March 1999 Application for Amend to License NPF-3,adopting Changes in Frequency & Scope of Volumetric Exams Justified by W TR WCAP-14535A ML20196F3791998-11-30030 November 1998 Supplemental Application for Amend to License NPF-3, Proposing Changes to License Conditions 2.C(6) & 2.E by Transferring Operating Authority for DBNPS from Toed & Centerior Svc Co to Firstenergy Nuclear Operating Co ML20155E3181998-10-28028 October 1998 Application for Amend to License NPF-3,revising Various Sections of TS 6.0, Administrative Controls, Including Relocation of Contents of 6.11 to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155E0701998-10-27027 October 1998 Application for Amend to License NPF-3,revising TSs 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation by Providing Potential Reduction in Spurious Trip Rate to Provide Cost Savings in Excess of $50,000 ML20155D7731998-10-27027 October 1998 Application for Amend to License NPF-3,relocating Existing TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8481998-10-27027 October 1998 Application for Amend to License NPF-3,revising Existing TS SRs 4.8.2.3.2.d,4.8.2.3.2.e,4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20151W2811998-09-0808 September 1998 Application for Amend to License NPF-3,permitting Use of Framatome Cogema Fuels M5 Advanced Alloy Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2851998-09-0808 September 1998 Application for Amend to License NPF-3,revising TS Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20236G6461998-06-29029 June 1998 Application for Amend to License NPF-3,transferring Operating Authority for DBNPS from TE & Centerior Svc Co to New Operating Company Called Firstenergy Nuclear Operating Co.Marked Up License,Safety & Environ Assessments Included ML20236R2301998-06-29029 June 1998 Resubmitted Application for Amend to License NPF-3, Transferring Operating Authority for DBNPS from Teco & Centerior Svc Co to New Operating Company Called Firstenergy Nuclear Operating Co.Safety Assessment & EA Included ML20217P8671998-04-24024 April 1998 Application for Amend to License NPF-3,modifying Existing TS 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases by Relocating Tables of Response Time Limits from TS to Plant USAR Technical Requirements Manual ML20217P8251998-04-24024 April 1998 Application for Amend to License NPF-3,clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20203L0861998-02-26026 February 1998 Application for Amend to License NPF-3 to Revise TS 3/4.4.5 & TS 3/4.4.6.2,incorporating New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2511997-12-23023 December 1997 Application for Amend to License NPF-3.Amend Changes TS Definitions 1.12,TS 3/4.9.5 & New TS 3.0.6 ML20197J5861997-12-23023 December 1997 Application for Amend to License NPF-3,revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217R2801997-08-26026 August 1997 Application for Amend to License NPF-3,clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2831997-08-26026 August 1997 Application for Amend to License NPF-3,modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5931997-07-29029 July 1997 Suppl 950929 to Application for Amend to License NPF-3, Change TS 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating & Associated Bases 3/4.4.2 & 3/4.4.3 ML20141F1051997-06-24024 June 1997 Application for Amend to License NPF-3,deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138A3201997-04-18018 April 1997 Application for Amend to License NPF-3,requesting Conversion to 24-month Fuel Cycle ML20138C3131997-04-18018 April 1997 Application for Amend to License NPF-3,requesting Rev to TS 3/4.7.6 to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20137M1061997-03-31031 March 1997 Application for Amend to License NPF-57,revising TS to Improve Consistency Between TS & Plant Configuration, Operation & Testing & Complete Required CA to Resolve TS Discrepancies Identified in CA Program ML20138M1251997-02-14014 February 1997 Application for Amend to License NPF-3,requesting Delay of Heat Removal Sys Valve Pit Surveillance Requirements ML20134D7461997-01-30030 January 1997 Application for Amend to License NPF-3,revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0561997-01-20020 January 1997 Application for Amend to License NPF-3,involving TS 3/4.5.3 Re ECCS Subsystems ML20132C7771996-12-13013 December 1996 Application for Amend to License NPF-3,authorizing Transfers of Control ML20132B6871996-12-11011 December 1996 Application for Amend to License NPF-3,revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle ML20134F1851996-10-28028 October 1996 Application for Amend to License NPF-3,requesting Revisions to 3/4.8.1.1,3/4.8.1.2,3/4.8.2.3,3/4.8.2.4 & 3/4.8 Re Electrical Power Systems ML20117P5301996-09-17017 September 1996 Application for Amend to License NPF-3,supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8441996-09-12012 September 1996 Application for Amend to License NPF-3,revising Reactivity Control Systems & Emergency Core Cooling Systems ML20117M1971996-09-0404 September 1996 Application for Amend to License NPF-3,App A,Modifying TS 6.2.3 by Removing Specific Overtime Limits & Working H from TS Consistent W/Nrc Recent Determination,On Generic Basis, That Limits Need Not Be Specified ML20116K2601996-08-0707 August 1996 Application for Amend to License NPF-3,changing Tech Specs 1.0, Definitions, Bases 3/4.0, Applicability & 3/4.6.2.1, Containment Sys - Depressurization & Cooling Sys - Containment Spray Sys ML20117K1871996-05-28028 May 1996 Application for Amend to License NPF-3,revising TS 3/4.3.1.1 RPS Instrumentation & TS 3/4.3.2.2 - Anticipatory RTS Instrumentation to Increase Trip Device Test Interval ML20107L3541996-04-18018 April 1996 Application for Amend to License NPF-3,requesting NRC Review & Approval to Use Alternate Electrical Lineup.Station Blackout DG as Standby Emergency Power Source to Supply Loads Normally Supplied by EDG 1,while Being Reworked ML20101M1601996-03-29029 March 1996 Application for Amend to License NPF-3,App A,Re Surveillance Requirements for Charcoal Filter Lab Testing to Revise Testing Methodology Used to Determine Operability of Charcoal Filters in ESF Air Handling Units ML20101C6911996-03-0606 March 1996 Application for Amend to License NPF-3,revising TS 3/4.5.2 to Allow Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI 1-2 Pump Until 10th Refueling Outage, Scheduled to Begin 960408 ML20100E0051996-02-0505 February 1996 LAR 93-0003 to License NPF-3,revising Table 3.3-3 of TS 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation to More Accurately Reflect Design & Actuation Logic of Plant Sequencers & Undervoltage Relays ML20095F5861995-12-12012 December 1995 Application for Amend to License NPF-3,revising TSs Re Containment Sys ML20098C5131995-10-0202 October 1995 Application for Amend to License NPF-3,revising TS Section 5.0,design Features & Adopting Improved STS for B&W Plants Format & Content ML20098C1071995-09-29029 September 1995 Application for Amend to License NPF-3,modifying TS 3.4.3 & Associated Bases for Pressurizer Code Safety Valve Lift Setpoint Tolerances ML20098C3931995-09-29029 September 1995 Application for Amend to License NPF-3,revising Tech Spec 3/4.1.2.8, Reactivity Control Sys - Borated Water Sources - Shutdown, Tech Spec 3/4.1.2.9, Reactivity Control Sys - Operating & TS 3/4.5.1, ECCS - Core Flooding Tanks 1999-09-07
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20216E6051999-09-0707 September 1999 Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation ML20210H0631999-07-28028 July 1999 Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, by Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4131999-07-27027 July 1999 Application for Amend to License NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G8831999-07-26026 July 1999 Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5251999-07-26026 July 1999 Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20210G4631999-07-26026 July 1999 Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumention & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20195F9121999-06-10010 June 1999 Application for Amend to License NPF-3,changing TS 3/4.6.4.4 Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20207E7861999-05-21021 May 1999 Application for Amend to License NPF-3,allowing Use of Expanded Spent Fuel Storage Capability ML20205E4961999-03-19019 March 1999 Application for Amend to License NPF-3,requesting Withdrawal of Proposed New Action B to TS 3.6.5.2,previously Submitted in 981027 Application ML20204F1691999-03-0909 March 1999 Application for Amend to License NPF-3,adopting Changes in Frequency & Scope of Volumetric Exams Justified by W TR WCAP-14535A ML20196F3791998-11-30030 November 1998 Supplemental Application for Amend to License NPF-3, Proposing Changes to License Conditions 2.C(6) & 2.E by Transferring Operating Authority for DBNPS from Toed & Centerior Svc Co to Firstenergy Nuclear Operating Co ML20155E3181998-10-28028 October 1998 Application for Amend to License NPF-3,revising Various Sections of TS 6.0, Administrative Controls, Including Relocation of Contents of 6.11 to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155E0701998-10-27027 October 1998 Application for Amend to License NPF-3,revising TSs 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation by Providing Potential Reduction in Spurious Trip Rate to Provide Cost Savings in Excess of $50,000 ML20155D7731998-10-27027 October 1998 Application for Amend to License NPF-3,relocating Existing TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8481998-10-27027 October 1998 Application for Amend to License NPF-3,revising Existing TS SRs 4.8.2.3.2.d,4.8.2.3.2.e,4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20151W2811998-09-0808 September 1998 Application for Amend to License NPF-3,permitting Use of Framatome Cogema Fuels M5 Advanced Alloy Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2851998-09-0808 September 1998 Application for Amend to License NPF-3,revising TS Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20236G6461998-06-29029 June 1998 Application for Amend to License NPF-3,transferring Operating Authority for DBNPS from TE & Centerior Svc Co to New Operating Company Called Firstenergy Nuclear Operating Co.Marked Up License,Safety & Environ Assessments Included ML20236R2301998-06-29029 June 1998 Resubmitted Application for Amend to License NPF-3, Transferring Operating Authority for DBNPS from Teco & Centerior Svc Co to New Operating Company Called Firstenergy Nuclear Operating Co.Safety Assessment & EA Included ML20217P8671998-04-24024 April 1998 Application for Amend to License NPF-3,modifying Existing TS 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases by Relocating Tables of Response Time Limits from TS to Plant USAR Technical Requirements Manual ML20217P8251998-04-24024 April 1998 Application for Amend to License NPF-3,clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20203L0861998-02-26026 February 1998 Application for Amend to License NPF-3 to Revise TS 3/4.4.5 & TS 3/4.4.6.2,incorporating New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2511997-12-23023 December 1997 Application for Amend to License NPF-3.Amend Changes TS Definitions 1.12,TS 3/4.9.5 & New TS 3.0.6 ML20197J5861997-12-23023 December 1997 Application for Amend to License NPF-3,revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217R2801997-08-26026 August 1997 Application for Amend to License NPF-3,clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2831997-08-26026 August 1997 Application for Amend to License NPF-3,modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5931997-07-29029 July 1997 Suppl 950929 to Application for Amend to License NPF-3, Change TS 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating & Associated Bases 3/4.4.2 & 3/4.4.3 ML20141F1051997-06-24024 June 1997 Application for Amend to License NPF-3,deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138A3201997-04-18018 April 1997 Application for Amend to License NPF-3,requesting Conversion to 24-month Fuel Cycle ML20138C3131997-04-18018 April 1997 Application for Amend to License NPF-3,requesting Rev to TS 3/4.7.6 to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20137M1061997-03-31031 March 1997 Application for Amend to License NPF-57,revising TS to Improve Consistency Between TS & Plant Configuration, Operation & Testing & Complete Required CA to Resolve TS Discrepancies Identified in CA Program ML20138M1251997-02-14014 February 1997 Application for Amend to License NPF-3,requesting Delay of Heat Removal Sys Valve Pit Surveillance Requirements ML20134D7461997-01-30030 January 1997 Application for Amend to License NPF-3,revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0561997-01-20020 January 1997 Application for Amend to License NPF-3,involving TS 3/4.5.3 Re ECCS Subsystems ML20132C7771996-12-13013 December 1996 Application for Amend to License NPF-3,authorizing Transfers of Control ML20132B6871996-12-11011 December 1996 Application for Amend to License NPF-3,revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle ML20134F1851996-10-28028 October 1996 Application for Amend to License NPF-3,requesting Revisions to 3/4.8.1.1,3/4.8.1.2,3/4.8.2.3,3/4.8.2.4 & 3/4.8 Re Electrical Power Systems ML20117P5301996-09-17017 September 1996 Application for Amend to License NPF-3,supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8441996-09-12012 September 1996 Application for Amend to License NPF-3,revising Reactivity Control Systems & Emergency Core Cooling Systems ML20117M1971996-09-0404 September 1996 Application for Amend to License NPF-3,App A,Modifying TS 6.2.3 by Removing Specific Overtime Limits & Working H from TS Consistent W/Nrc Recent Determination,On Generic Basis, That Limits Need Not Be Specified ML20116K2601996-08-0707 August 1996 Application for Amend to License NPF-3,changing Tech Specs 1.0, Definitions, Bases 3/4.0, Applicability & 3/4.6.2.1, Containment Sys - Depressurization & Cooling Sys - Containment Spray Sys ML20117K1871996-05-28028 May 1996 Application for Amend to License NPF-3,revising TS 3/4.3.1.1 RPS Instrumentation & TS 3/4.3.2.2 - Anticipatory RTS Instrumentation to Increase Trip Device Test Interval ML20107L3541996-04-18018 April 1996 Application for Amend to License NPF-3,requesting NRC Review & Approval to Use Alternate Electrical Lineup.Station Blackout DG as Standby Emergency Power Source to Supply Loads Normally Supplied by EDG 1,while Being Reworked ML20101M1601996-03-29029 March 1996 Application for Amend to License NPF-3,App A,Re Surveillance Requirements for Charcoal Filter Lab Testing to Revise Testing Methodology Used to Determine Operability of Charcoal Filters in ESF Air Handling Units ML20101C6911996-03-0606 March 1996 Application for Amend to License NPF-3,revising TS 3/4.5.2 to Allow Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI 1-2 Pump Until 10th Refueling Outage, Scheduled to Begin 960408 ML20100E0051996-02-0505 February 1996 LAR 93-0003 to License NPF-3,revising Table 3.3-3 of TS 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation to More Accurately Reflect Design & Actuation Logic of Plant Sequencers & Undervoltage Relays ML20095F5861995-12-12012 December 1995 Application for Amend to License NPF-3,revising TSs Re Containment Sys ML20098C5131995-10-0202 October 1995 Application for Amend to License NPF-3,revising TS Section 5.0,design Features & Adopting Improved STS for B&W Plants Format & Content ML20098C1071995-09-29029 September 1995 Application for Amend to License NPF-3,modifying TS 3.4.3 & Associated Bases for Pressurizer Code Safety Valve Lift Setpoint Tolerances ML20098C3931995-09-29029 September 1995 Application for Amend to License NPF-3,revising Tech Spec 3/4.1.2.8, Reactivity Control Sys - Borated Water Sources - Shutdown, Tech Spec 3/4.1.2.9, Reactivity Control Sys - Operating & TS 3/4.5.1, ECCS - Core Flooding Tanks 1999-09-07
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APPLICATION FOR AMENDMENT .
TO FACILITY OPERATING LICENSE NO. NPF-3 FOR DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 Enclosed are 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.1346) concern Section 3/4.7.7, Snubbers, Surveillance Requirement 4.7.7, Footnote 2 Section 3/4.7.7, Snubbers, Surveillance Requirement 4.7.7.le Section 3/4.7.7, Snubbers, Surveillance Requirement 4.7.7.2b, Footnote 63 Section 3/4.7.7, Snubbers, Surveillance Requirement 4.7.7.2c.28 Bases Section 3/4.7.7, Snubbers.
By Nd -
T.J./ypts Nuclear licensing Director For J. Williams, Jr.
Senior Vice President Nuclear Sworn to and subscribed before me this 12th day of March, 1987.
l.1&k
Notary Public, State of Ohio My cosmission expires /
8705270645 870519 DR ADOCK050g6
1 l
Docket No. 50-346 License No. NPF-3 Serial No. 1346 Attachment The following information is provided to support issuance of the requested changen to the Davis-Besse Nuclear Power Station, Unit No. 1, Operating License NPF-3. Technical Specifications Sections 4.7.7 Footnote 2, 4.7.7.le, 4.7.7.2b Footnote 6 and 4.7.7.2e.2 and Bases Section 3/4.7.7, Snubbers.
A. Time Required to Implement:
This change is to be effective 30 days af ter issuance of the l License Amendment.
B. Reason for Change (Facility Change Request 86-0044 Revision C):
On January 30, 1985, Toledo Edison submitted to the NRC a License Amendment application (Serial No. 1113) to revise Technical Specification 3/4.7.7 Snubbers, in accorde.nce with '
Generic Letter 84-13. On April 24, 1986, Amendment No. 94 (Log l No. 1977) issued the requested changes to Technical Specification '
3/4.7.7. In conjunction with approval of this Amendment, Toledo Edison committed by letters dated January 22, 1986, (Serial No.
1239) and March 26, 1986, (Serial No. 1263) to submit a separate amendment request to include the two recommendatione outlined in the Amendment No. 94 NRC Safety Evaluation. The two recommenda-tions were to add a surveillance requirement which requires the performance of a post-transient inspection of all hydraulic and mechanical snubbers attached to sections of systems that have experienced an unexpected, potentially damaging transient and to add an acceptance criterion regarding functional testing i for snubber activation.
C. Safety Evaluations i See attached Safety Evaluation.
D. Significant llazards Consideration:
See attached Significant llazards Consideration.
l
i e
Dockst No. 50-346 License No. NPF-3 Serial No. 1346 Attachment 1 Page 1 l SAFETY EVALUATION i
l This safety evaluation addresses proposed revisions to the Davis-Besse l Nuclear Power Station Unit No.1 Operating License, Appendix A, Technical Specification 3/4.7.7, Snubbers. The safety function of all nuclear safety-related snubbers is to ensure that the integrity of nuclear safety-related systems is maintained during and following dynamic loads and to ensure that the snubber support system will not degrade normal system l
operation (i.e.. prevent thereal growth). The safety function of the Davis-Besse Nuclear Power Station Unit No. 1 Operating License. Appendix A. Technical Specifications, is to provide limiting technical conditions for plant operation and provide surveillance requirements to assure that the necessary quality of systems and components is maintained and that the ifmiting conditions of operation are met.
PROPOSED AMENDMENT REQUEST Davis-Besse Nuclear Power Station, Unit No. 1, Operating License, Appendix A. Technical Specifications NRC Ceneric Letter 84-13 Technical Specifications for Snubbers (Log No. 1508)
Amendment No. 94 to Facility Operating License No. NPT-33 Snubber Requirements; Safety Evaluation (Log No. 1977)
FCR 83-080, Revision D Serial No. 1263, dated March 26, 1986 Surveillance Requirement 4.7.7.le All safety-related snubbers are required to be operable in the applicable system mode to ensure that the structural integrity of the reactor cool-ant system and all other safety-related systems is maintained during and following a dynamic event. A dynamic event is a condition resulting from either a seismic event or a system transient event such as water hammer.
The proposed addition of Surveillance Requirement 4.7.7.le, Transient Event inspection, would specifically require that an inspection be per-formed of all hydraulic and mechanical snubbers attached to sections of nuclear nafety-related systems that have experienced unexpected, l
potentially damaging transients. Operational data would be reviewed to determine the systems or sections of systems potentially affected by the event which should be inspected. This inspection would be performed within six months following the transient event.
The inspection would consist of a visual inspection of hydraulic and mechanical snubbers and verification of freedom-of-motion of mechanical snubbers, Verification of freedom-of-motion of mechanical snubbers would be accomplished through the use of one of the following (1) manually induced snobbte movement s or (2) evaluation of in-place snubber piston settings or (3) stroking the mechanical snubber through its full range of travel.
Dockot No. 50-346 License No NPF-3 Serial No. 1346 Attachment 1 Page 2 1
The identification of an inoperable snubber through this inspection would place the plant in the action statement of the Limiting Condition for Operation 3.7.7 for snubbern .and the appropriate actions would then be e implemented. This change is consistent with the recommended addition of a Transient Event Inspection surveillance requirement as outlined in the l NRC's Safety Evaluation supporting Amendment No. 94 to the Davis-Besse l Operating License No. NPF-3.
Bases 3/4.7.7 l
l The addition of the Surveillance Requirement 4.7.7.le, Transient Event Inspection, would necessitate the revision of Bases 3/4.7.7, Snubbers.
The word " seismic" would be changed to " dynamic". This change would make the bases consistent with the intent of the surveillance requirement to test the snubbers after either a seismic event or system transient event.
Surveillance Requirement 4.7.7.2b, Footnote 6 Footnote 6 to Surveillance Requirement 4.7.7.2b states:
" Permanent or other exemptions from functional testing for individual st ubbers in these categories may be granted by the commission only if a justifiable basis for exemption is presented."
As this statement only reiterates the regulatory basis established in 10 CFR Part 50.12 for obtaining specific exemptions (in this case, exempt-ing individual safety-related snubbers from functional testing), it is not i
necessary that this footnote be included within the Technical Specific-ations. Deletion of Footnote 6 is an administrative change to the Techni-cal Specifications. This change is consistent with that proposed to the NRC (Serial No. 1263) in supporting the NRC's Safety Evaluation to Amendment No. 94 to the Davis-Besse Operating License No. NPF-3.
l Surveillance Requirement 4.7.7.2.c.2 The purpose of Surveillance Requirement 4.7.7.2c.2 for mechanical snubbers is to describe the acceptance criteria for in-place and bench testing. This surveillance requirement, as presently written, describes one acceptance criterion as the achieving of activation (i.e., restraining action) in both tension and compression. Ilowever, no limits for this required restraining action are provided by the acceptance criterion.
The addition of the words "within the specified range" to Surveillance Requirement 4.7.7.2c.2 would provide a limit for the acceptance criterion. This change is consistent with the Babcock and Wilcox Standard l Technical Specifications, NUREC-0103, Revision 4. This change is also l consistent with that proposed to the NRC (Serial No.1263) and accepted l in the NRC's Safety Evaluation supporting Amendment No. 94 to the Davis-l Besse Operating License No. NPF-3.
l 1
I Dockot No. 50-346 License No. NPF-3 Serial No. 1346 Attachment 1 Page 3 Surveillance Requirement 4.7.7, Footnote 2 Footnote 2 to Su,rveillance Requirement 4.7.7 states that safety-related snubbers are listed in the latest revision of the applicabic surveillance test procedure (s). It further states that snubbers may be added to, or removed from, safety-related systems and their assigned groups "without prior Licensing Amendment". The proposed replacement of the word " prior" with the word "a" and " Licensing" with " License" clariffes that no license amendment is required either prior to, or following, such a change. This clarification is an administrative change.
DISCUSSION OF UNREVIEWED SAFETY QUESTIONS The proposed changes are administrative in nature or increase the surveillance requirements of the Davis-Besse Nuclear Power Station Unit No. 1. Implementation of these changes would not
- 1. Increase the probability of occurrence or the consequences of an accident or an1 function of equipment important to safety previously evaluated in the Safety Analysis Report (10CFR50.59(2)(i)) .
The proposed changes are either increasing the surveillance require-ments or are administrative and, therefore, do not. increase the probability or consequences of an accident previously 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 analyses and no new accidents are involved.
- 3. Reduce the margin of safety as defined in the basis for any Technical Specification (10CFR50.59(2)(iii)).
The margin of safety is not reduced by these increased surveillance requirements and administrative changen.
Based on the above evaluation, it is determined that this revision does not involve an unreviewed safety question.
1 l
Docket No. 50-346 f License No. NPF-3 ,
i Serial No. 1346
- Attachment 2 j Page 1 i
SIGNIFICANT 11AZARDS CONSIDERATION l
i The. proposed amendment request involves the following changes
! 1. Addition of a Surveillance Requirement 4.7.7.le, Transient Event
) Inspection, to require that an inspection be performed of all safety-l related hydraulic and mechanical snubbers attached to sections of l nystems that have experienced unexpected, potentially damaging trans-t lents. Revise Bases Section 3/4.7.7, Snubbers, to be consistent with
! this change.
I i
- 2. Deletion of an unnecessary footnote (Surveillance Requirement 4.7.7.2b, Footnote 6).
l 3. Addition of limits to the acceptance criteria for mechanical snubber l in-place and bench testing (Surveillance Requirement 4.7.7.2c.2).
- 4. Revision of the wording of Footnote 2 to Surveillance Requirement 4.7.7 to clarify the footnote.
The effects of these changes are detailed below Surveillance Requirement 4.7.7.le ,
j j All safety-related snubbers are required to be operable in the
] applicable system mode to ensure that the structural integrity of the i reactor coolant system and all other safety-related systems is maintained j during and following a dynamic event. A dynamic event is a condition l resulting from either a seismic event of a system transient event such as I water hammer. The proposed addition of Surveillance Requirement 4.7.7.le, t i Transient Event Inspection, would specifically require that an inspection
! be performed of all hydraulic and mechanical snubbers attached to sections
- of nuclear safety-related systems that have experienced unexpected, potentially damaging transients. Operational data would be reviewed to
- determine the systems or sections of systems potentially affected by the
) event which should be inspected. This inspection would be performed i within six months following the transient event.
l The inspection would consist of a visual inspection of hydraulic and mech-
] ancial snubbers and verification of freedom-of-motion of mechanical anubbers. Verification of freedom-of-motion of mechanical'enubbers would
, be accomplished through the use of one of the followingt (1) manually I induced snubber movement; or (2) evaluation of in-place snubber piston l settings or (3) stroking the mechanical snubber through its full range of j travel.
, The identification of an inoperable snubber through this inspection would i
place the plant in the action statement of the Limiting Condition for j operation 3.7.7 for snubbers, and the appropriate actions would then be 1
Dockot No. 50-346 License No. NPF-3 Serial No. 1346 Attachment 2 Page 2 i
implemented. This change is consistent with the recommended addition of a Transient Event Inspection surveillance requirement as outlined in the NRC's Safety Evaluation supporting Amendment No. 94 to the Davis-Besse Operating Licensing No. NPF-3.
Bases 3/4.7.7 t The addition of the Surveillance Requirement 4.7.7.le Transient Event Inspection, would necessitate the revision of Bases 3/4.7.7, Snubbers.
The word " seismic" would be changed to " dynamic". This change would make the bases consistent with the intent of the surveillance requirement to test the snubbers after either a seismic event or system transient event.
Surveillance Requirement 4.7.7.2b. Footnote 6 Footnote 6 to Surveillance Requirement 4.7.7.2b states:
" Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the commission only if a justifiable basis for exemption is presented."
As this statement only reiterates the regulatory basis established in 10 CFR 50.12 for obtaining specific exemptions (in this case, exempting individual safety-related snubbers from functional testing), it is not necessary that this footnote he included within the Technical Specifica-tions. Deletion of Footnote 6 is an administrative change to the Techni-cal Specifications. This change is consistent with that proposed to the NRC (Serial No.1263) in supporting the NRC's Safety Evaluation to Amendment No. 94 to the Davis-Besse Operating License No. NPF-3.
Surveillance Requirement 4.7.7.2c.2 The purpose of Surveillance Requirement 4.7.7.2c.2 for mechanical snubbers is to describe the acceptance criteria for in-place and bench testing. This surveillance requirement, as presently written, describes an acceptance criterion as the achieving of activation (i.e., restraining action) in both tension and compression. Ilowever, no limits for this required restraining action are provided by the acceptance criterion.
The addition of the words "within the specified range" to Surveillance Requirement 4.7.7.2c.2 would provide a limit for the acceptance criterion. This change is consistent with the Babcock and Wilcox Standard Technical Specifications, NUREG-0103, Revision 4. This change is also consistent with that proposed to the NRC (Serial No.1263) and accepted in the NRC's Safety Evaluation supporting Amendment No. 94 to the Davis-Besse Operating License No. NPF-3.
i .
i Docket No. 50-346 License No. NPF-3 l Serial No. 1346 Attachment 2 Page 3 Surveillance Requirement 4.7.7, Footnote 2 I Footnote 2 to Surveillance Requirement 4.7.7 states that safety-related j snubbers are listed in the latest revision of the applicable surveillance i test procedure (s). It further states that snubbers may be added to, or
) removed from, safety-related systems and their assigned groups "without j prior Licensing Amendment". The proposed replacement of the word " prior" 4 with the word "a" and " Licensing" with the word " License" clariffes that i no license amendment is required either prior to, or following, such a j change. This clarification is an administrative change.
BASIS FOR NO SIGNIFICANT HAZARDS CONSIDERATION i
l 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 l 1. Involve a significant increase in the probability or consequences of an accident previously evaluated (10CFR50.92(c)(1)).
- The proposed changes are either increasing the surveillance require-J ments or are administrative and, therefore, do not increase the I probability or consequences of an accident previously evaluated.
] i
- 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 this change. These changes either increase ;
l surveillance requirements or are administrative and do not create the
! possibility of a new or different kind of accident.
- 3. Involve a significant reduction in a margin of safety (10CFR50.92(c)(3)).
. The changes requested are either administrative or increase the i
surveillance requirements and, therefore, will not reduce the margin !
l of safety.
On the basis of the above Toledo Edison has determined that the amendment I l request does not involve a significant hazards consideratica.
i
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