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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 ML20212H9901999-06-22022 June 1999 Amend 233 to License NPF-3,relocating TS Surveillance Requirement from TS 3/4.6.5.1, Shield Building - Emergency Ventilation Sys to TS Section 3/4.6.5.2, Shield Building Integrity 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 ML20207G6591999-06-0808 June 1999 Amend 232 to License NPF-3,revising TSs in Response to 990309 Application.Changes Increase Inservice Insp Interval & Reduce Scope of Volumetric & Surface Examinations for Reactor Coolant Pump Flywheels ML20207E7861999-05-21021 May 1999 Application for Amend to License NPF-3,allowing Use of Expanded Spent Fuel Storage Capability ML20206U7301999-05-19019 May 1999 Amend 231 to License NPF-3,revising Administrative Requirements Re TS 6.5.1.6,TS 6.8.4.d,TS 6.10,TS 6.11, TS 6.12 & TS 6.15 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 ML20206U2381999-02-0909 February 1999 Amend 229 to License NPF-3,revising TS 3/4.8.2.3 & Associated Bases & SRs for Battery Testing 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 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 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 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 ML20151W2851998-09-0808 September 1998 Application for Amend to License NPF-3,revising TS Section 3/4.7.6, Plant Systems - CREVS & Associated 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 ML20236M9321998-07-0707 July 1998 Amend 225 to License NPF-3,relocating TS Tables of Response Time Limits to Davis-Besse Technical Requirements Manual ML20236K4231998-06-30030 June 1998 Amend 224 to License NPF-03,revises TS Section 1.0, Definitions, to Clarify Meaning of Core Alteration, Relocates TS Section 3/4.9.5 & Associated Bases to Technical Requirements Manual 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 ML20249A7511998-06-11011 June 1998 Amend 223 to License NPF-3,revising TS Section 3/4.6.1.3 & Associated Bases ML20249A7611998-06-11011 June 1998 Amend 222 to License NPF-3,revising TS Section 3/4.2 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 ML20216B8291998-04-14014 April 1998 Amend 220 to License NPF-3,revising TS 3/4.4.5,TS 3/4.4.6.2 & Associated Bases to Allow Use of Repair Roll SG Tube Repair Process 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 ML20202C6011998-02-0303 February 1998 Amend 219 to License NPF-3,revising TS Sections 3/4.8.1, AC Sources, TS Section 3/4.8.2, Onsite Power Distribution Sys, TS Table 4.8.1, Battery Surveillance Requirements, & Associated Bases 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 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 ML20203C1491997-12-0202 December 1997 Amend 216 to License NPF-3,revising TS 3/4.5.2,TS 3/4.5.3 & TS 3/4.7.Several Surveillance Intervals Changed from 18 Months to Once Each Refueling Interval ML20203B1851997-12-0202 December 1997 Amend 218 to License NPF-3,extending SR Intervals from 18 to 24 Months Based on Results of Plant Instrument Drift Study ML20203C1341997-12-0202 December 1997 Amend 217 to License NPF-3,revising Surveillance Interval from 18 Months to Each Refueling Interval for TS 3/4.5.2, TS 3/4.6.5.1,TS 3/4.7.6.1,TS 3/4.7.7.2,TS 3/4.9.12 & TS Bases 3/4.7.7 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 ML20134J7741996-11-0808 November 1996 Amend 212 to License NPF-3,revising TS 6.2.3, Facility Staff Overtime. Procedural Control Requirement Added to TS That Will Ensure Monthly Review of Overtime for Personnel Who Perform Safety Related Functions 1999-09-07
[Table view] |
Text
{{#Wiki_filter:_ _ _ _ _ _ _ _ _ _ -
Docket Number 50-346 License Numbet NPF-3 3erial Number 2037 Enclosure Page 1 APPLICATION FOR AMELDMENT TO FACILITY OPERATING ICENSE NUMBER NPF-3 DAVIS-BESSE NUCLEAR POVER STATION Uh_T NUMBER 1
?
Attc%ed are requested changes to the Davis-Besse Nuclear Power Station, Unit Number 1, Facility Operating License Number NPF-3. Also included is the Safety Assessment and Significant Hazards Consideration.
The proposed changes submitted under cover letter Serial Number 2037 concern:
Appendix A, Technical Specification (TS) Figure 5.1-1, DBNPS Exclusion Area, TS Figure 5.1-2, DBNPS Lov Population Zone, TS Figure 5.1-3, DBNPS Unrestricted Area Boundary for-Liquid Effluents, TS Figure 5.1-4, DBNPS Unrestricted Area Boundary for Gaseous Effluents, TS 5.1.1, Site Exclusion Area, TS 5.1.2, Low Population Zone, and TS 5.1.3, Sita Boundary.
By:
MW7 D. C. Shelton, Vice President, Nuclear - Davis-Besse
, Svora and Subscribed before me this lith day of September, 1992.
Y U// n Notary PulyTic, State of Ohio 4 EVEYtR PMss
%CurtskaEx;its.htf 28,lis4 9209220317 900911 PDR ADOCK 05000346 P PDR
+
Docket Number 50-346 i Ulcense Number NPF-3 -!
Serial Number 2037 Enclosure
}
Page 2 1
The following information is provided to support issuance of the requested changes to the Davis-Besse Nuclear Power Station, Unit i Number 1, Operasing License Number NPF-3, Appendix A Tochnical [
Specificationst i i
A. Time Required to Implement: This change is to be implemented .
vithin 90 days after the NRC issuance of the License Imendment. j B. Reason for change (Licanse Amendment Request Number 91-0004): This license amendment request proposes deletion of TS Figure-5.1-1, i DPNPS Exclusion Area, TS Figure 5.1-2, DBNPS Lov Population Zone, -
TS Figure 5.1-3, DBNPS Unrestricted Area Boundary; for Liquid _
Effluents, and TS Figure 5.1-4, DBNPS Unrestricted Area Boundary. .
for Gaseous Effluents, on the basis that information provided by l these figures is already located in the DBNPS Updated Safety -
Analysis Report. Additionally, TS 5.1.1, Site Exclusler. Area,.TS [
5.1.2, Low Population Z(ne, and TS 5.1.3, Site Boundary, are {
proposed for revision to reflect thu_above' deletions. l C. Safety Assessment and Significant flazards Consideration: See $
attached, i
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Docket Number 50-346 E
! License Number NPF-3 l Serial Number 2037 !
Attachment l j.. Page 1 l
=
4 l Safety Assessment and Significant Harards Consideration f j' for License Amendment Request Number 91-0004 l
f- TITLE:
i-l Proposed Deletion of Technical Specification (TS) Figure 5.1-1, {
j Davis-Besse Nuclear Power Station (DBNPS) Exclusion Area, TS Figure i l 5.1-2, DBNPS Lov Population Zone, TS Figure 5.1-3, DBNPS Unrestricted 8 d Area Boundary for Liquid Effluents, and TS Figure 5.1-4. DBNPS _k l Unrestricted Area Boundary for Gaseous Effluents and Proposed Revision l l of T3 3.1.1, Site Exclusion Area, TS 5.1.2, Lov Population Zone, and TS l 5.1.3, Site Boundary i
, DESCRIPTIO_N_ : ,
i _
f This License Amendment Request (LAR) proposes deletion of TS Figure i 5.1-1, TS Figure 5.1-2, TS Figure 5.1-3, and TS Figure 5.1-4, on the basis that these figures are already maintained in the IsBNPS Updated
! Safety Analysis Report (USAR) as USAR Figure 2.1-3, DBNPS 3 te L j arrangement, and USAR Figure 2.1-7,-DBNPS Lov Population Zone. The' i
! criteria for establishing the site boundary, unrestricted area, !
j cxclusion area and low population zone continue to be defined by the TS !
l and by regulations-(10 CFR Part 100, Reactor Site. Criteria). ;
j Consequently, the proposed changes do not relax any existing-requirements, but facilitate _ administrative changes involving these [
v
- figures, including the use in the USAR of figures with greater clarity !
i e
and detail. Specifically, the following changes are proposed: i i L t
- 1. TS 5.1.1, Site Exclusion Area, currently refers to TS Figure 5.1-1. ;
l TS 5.1.1 vould be revised to delete the reterence to TS Figure j j 5.1-1 and the following sentence would be inverted:
l
'l .
\
"The Site Exclusien Area is as defined in 10 CFR Part 100." -;
- - TS Figure 5.1-1 shows the site boundary and the site exclusion l area. USAR Section 2.1.2, Site Description, states, in paru e
! "The site, site arrangement, and' location of the major statien -t l structures are shown on Figure 2.1-3. The site boundary shown on I
! this figure is also the limit of the~ exclusion area." l
-~ .-
;i This establishes that USAR Figure 2.1-3 reflects the same !
! information relative to the - houndary and exclusion area as TS. j j Figure 5.1-1. !
t
} 2. TS 5.1.2, Low Population Zone, curret.tly refers to TS Figure.5.1-2.
~
l}
} TS 5.1.2 vould be revised to delete the reference to TS Figure ~j j 5.1-2 and the following sentence vould be-insertedt ;
1 l "The Lov Population _ Zone-is as defined-in 10 CFR-Part 100." e i :
f -TS Figure 3.1-2 shows the DBNPS Lov Population Zone. USAR Section- -
[ 2.1.3.3, Lov Population-Zone, states, in part: f f
i I
!~ k w - . w n o w.- - , ,-~w-w+ w -
-ve r m i- ,rr--- -e--y - v --w - -e ve-++ , w w+ ~ vr aywwwa *-w =p-
, - . - - - - ~ _ . - . . - . - - - - - . . - . - - . . . .
1 i-Docket Number 50-346 License Number NPF-3 l
i- Serial Number 2037 I Attachment i j' Page 2 -{
g .
4 i
- "The low population zone has been established as that area outside :
i of the site boundary within a radius of two miles from the center -
j
! of the containment structure." )
- i. 1
! USAR F'qure 2.1-7 shovs_ the site boundary and a two mile radius [
{ circ 1s from a point equivalent to the center of the containment
- j. structure. TS Figure 5.1-2 shows the site laundary and a circle of
- two mile radius from a point equivalent to .nc center of the .
co.ainment structure. Therefore, USAR Figure 2.1-7 reflects thel i l
j sata information relative to the site boundary and lov population '
> zone as TS Figure 5.1-2. .i
! I l 3. TS 5.1.3, Site Boundary, currently refers to TS Figure 5.1-3 and TS -}
Figure 5.1-4. TS 5.1.3 vould be revised to delete the reference to
! TS Figure 5.1-3 and TS Figure 5.1-4 and the tollowing sentence .;
i vould be inserted: +
l 1 ?
!. "The UNRESTRICTED AREA and SITE BOUNDARY are defined in Technical i i Specification Section 1.0, Definitions." !
TS Figure 5.1-3 shows the site boundary as the unrestricted area ,
j boundary for liquid effluents. USAR Section 11.2.1, Liquid Vaste- ;
i Systems - Design'0bjectives, states, in part:
l :i
! "The systems handling liquid vastes are designed such that the
- i estimated releases in liquid effluents comply with the following ;
j requirements of 10 CFR 20 and 10 CFR-50: j
! a. The individual radionuclide concentrations in the liquid [
l effluents at the site boundary shall not exceed the limits .
i for releases to unrestricted areas given in Appendix-B of :
! 10 CFR 20." !
I i i This establishes that USAR Figure 2.1-3 reflects the-same i
! information rela:ive to the site boundary and the unrestricted area j
! boundary for liquid effluents as TS Figure 5.1-3. _i
- i
[ IS Figure 5.1-4 shows the site boundary as the unrestricted area boundary for gaseous ef fluents. USAR Section 2.1.2.2, Boundaries I
- for Establishing Effluent Release Limits, states, in part
- )
i {
j- "The site boundary es shown on USAR Figure 2.1-3 is - the boundary l 1 line which determines the-limits of gaseous' releases foripurposes
(. of TS limits to fulfill the_ requirements of 10 CFR 20 pertaining to !
radioactive releases to unrestricted areas."
{ ,
} As with TS Figure 5.1-3,-this establishes that USAR Figure 2.1-3 ,
- reflects-the same-information relative to the site boundary and the= v
[ unrestricted area boundary for gaseous effluents as1TS Figure
~
- ,i l 5.1-4. l 4
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Docket Number 50-346 License Number NPF-3 Serial Number 2037 Attachment Page 3 As described above, this LAR is an administrative change requesting deletion of TS information that is defined by TS or Nuclear Regulatory Commission regulation and is also maintained in the USAR. Presently, any changes to the facility affecting the USAR figures vould require a corresponding license amendment request per 10 CFR 50.90. Under this proposed LAR, changes to these facility as reflected in these figures vould be controlled by 10 CFR 50.59, which would require submittal of a license amendment request only if the proposed facility change involves an unreviewed safety question.
SYSTEMS, COMPONENTS, AND ACTIVITIES AFFECTFD:
This LAR affects the TS sections and figures shoving the maps of the Unrestricted Area, the Exclusion Area, and the Low Population Zone. No systems or components are affected by the proposed revision of these TS sections or deletion of these TS figures.
SAFETY FUNCTIONS OF THE AFFECTED SYSTEMS, COMPONENTS AND ACTIVI lES:
The function of TS Section 5 is to contain the facility design features including those features of the facility such as materials of constructjon and geometric arrangements which, if altered or modified, vould have a significant effect on safety, and which are not covered in the TS Limiting Conditions for Operation, Surveillance Requirements, or Safety Limits and Limiting Safety System Settings. The purpose of the TS is to maintain the validity of the Opdated Safety Analysis Report.
EFFFCTS ON SAFETY:
T'is LAR is strictly an administrative change, deleting TS figures, the content of which continue to be defined by TS and 10 CFR Part 100, and that are already maintained in the USAR. Changes-to these USAR= figures vould still be rootrolled by the 10 CFR 50.59 process. Thus, this proposed revision of the TS sections and deletion of the TS figures has no adverse effect on safety.
-SIGNIFICANT HAZARDS CONSIDERATION:
The Nuclear Regulatary Commission has provided standards in 10 CFR 50.92(c) for determining whether a significant hazard exists due to a proposed amendment to an 0perating License for a facility. A proposed amendment involves no significant hazards consideration--if operation of the faellity 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 nov
-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 reviewe6 the proposed changes and determined that a f
\
.._ __ _ _ ~ ._._ _. _ . . _ _ _ . _ _ _ _ _ , _ _ _ _ _ _ _ _ _ _
! Docket Number-50-346 License. Number.NPF-3 i' '
Serial Number 2037 '
l Attachment j j Page 4 I i
' f l significant hazards consideration does not exist because operaD ,n of l l
the Davis-Besse Nuclear Power Station, Unit Number 1, in accord ..ce j vith the proposed changes vould:
i.
f I la. Not involve a significant increase in the probability of an
! accident previously evaluated because this is strictly an '
administrative change to delete from the Davis-Besse Nuclear
'l Power Station (DBNPS) Technical Specifications (TS)
- information that is already maintained in the DBNPS Updated i
! Safety Analysis Report (USAR). There are no accident i i initiators or assumptions affected by the proposed changes. I
! lb. Not involve a significant increase in the consequences of an l
accident previously evaluated because this is strictly an ]j i' administrative change to delete from the DBNPS TS information ;
that is alvtady maintained in the DBNPS USAR. There is no j effect on the source term or containment isolation and no -
increase in radiological effluents. J i
l 2a. Not create the possibility of a new kind of accident from any l l
accident previously evaluated because this is strictly an j j administrative change to delete from the DBNPS TS information )
a that is already maintained in the DBPPS USAR. -l k k 2b. Not create the possibility of a different kind of accident !
l from any accident previously evaluated because this is !
strictly an administrative change to delete from the DBNPS TS [
information tha;. is already maintained in the DBNPS USAR. l I
} 3. Not involve a significant reduction in a margin of safety [
l because this is strictly an administrative change to delete i
! from the DBNPS TS information that is'already maintained in [
] the DBNPS USAR. !
I t
- CONCLUSION: i
, _ g i -
j On the basis of the above, Toledo Edison has determined that the -;
! License Amendment Request does not involve a significant hazards -f i- consideration. As this License Amendment Request _ concerns proposed [
l changes to the Technical Specifications that must be reviewed by the i
! Nuclear Regulatory Commission, this License Amendment Request does not _l l constitute an unreviewed safety question. }
i i I i
!. ATTACHMENT: .!.
4
- Atracheu are the proposed marked-.up changes to the Operating. License.
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