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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20212H9901999-06-22022 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 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 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 ML20206U2381999-02-0909 February 1999 Amend 229 to License NPF-3,revising TS 3/4.8.2.3 & Associated Bases & SRs for Battery Testing 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 ML20249A7611998-06-11011 June 1998 Amend 222 to License NPF-3,revising TS Section 3/4.2 ML20249A7511998-06-11011 June 1998 Amend 223 to License NPF-3,revising TS Section 3/4.6.1.3 & Associated Bases 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 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 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 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 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 ML20198E3881992-11-23023 November 1992 Amend 175 to License NPF-3,revising TS 6.2.2,Facility Staff, by Adding Footnote to Table 6.2-1,Min Shift Crew Composition ML20248H6281989-10-0303 October 1989 Amend 139 to License NPF-3,revising Tech Spec to Reflect Administrative & Editorial Changes to Administrative Controls,Including Station Review Board Responsibilities ML20248B3541989-09-20020 September 1989 Amend 137 to License NPF-3,revising Tech Specs to Reflect Existing Operating Procedures Which Require at Least One Operator to Be in Control Panel Area When Fuel Is in Reactor ML20248E2741989-09-20020 September 1989 Amend 138 to License NPF-3,revising Tech Specs to Reflect Changes in Organization,Positions & Titles ML20245K1741989-08-15015 August 1989 Amend 136 to License NPF-3,revising Restrictions on Intervals Between Functional Testing of Snubbers by Deleting Applicability of Spec 4.0.2b to Surveillance Requirement ML20245H8841989-08-11011 August 1989 Corrected Amend 134 to License NPF-3,deleting Section 3/4.3.3.7 Re Chlorine Detection Sys from Tech Specs & Section 3/4.3.3.7 from Bases ML20245H9461989-08-0404 August 1989 Amend 135 to License NPF-3,correcting Typos & Making Minor Word Changes to Achieve Consistency Between Tech Specs & Plant Nomenclature & Deleting Unnecessary Statements Due to Elapsed Time &/Or Completion of Specified Actions ML20245F5741989-08-0404 August 1989 Amend 134 to License NPF-3,deleting Sections 3/4.3.3.7, Chlorine Detection Sys from App a & 3/4.3.3.7 from Bases ML20247J8301989-05-18018 May 1989 Amend 133 to License NPF-3,deleting from Licensee All Remaining Sections of App B ML20246K5661989-05-0303 May 1989 Errata to Amend 132 to License NPF-3,revising Tech Spec 3.7.1.1 Re Limiting Condition for Operation for Main Steam Line Safety Valves ML20245G0171989-04-25025 April 1989 Amend 131 to License NPF-3,removing Operability & Surveillance Requirements for Auxiliary Feedwater Turbine Inlet Steam Pressure Interlocks from Tech Spec Requirements for Auxiliary Feedwater Pumps ML20244D3961989-04-13013 April 1989 Amend 130 to License NPF-3,changing Tech Specs to Allow Fuel W/Max Enrichment of 3.80 Weight Percent U-235 to Be Stored in New Fuel Storage & Spent Fuel Storage Locations in Existing Fuel Storage Facilities at Plant ML20207L9381988-10-0505 October 1988 Amend 124 to License NPF-3,revising Tech Spec 3.3.2.2,Table 3.3-11, Steam & Feedwater Rupture Control Sys, to Reflect Design Mod That Simplifies Manual Initiation ML20207N8201988-10-0303 October 1988 Amend 123 to License NPF-3,revising Tech Spec to Allow Operation for Cycle 6 ML20207K0961988-09-19019 September 1988 Amend 120 to License NPF-3,revising Tech Specs 4.6.1.2 c.3 Involving Containment Sys Surveillance Requirements ML20207H9191988-08-24024 August 1988 Amend 117 to License NPF-3,revising Tech Spec Table 4.7-1 & Section 3/4.7.1.1 Re Main Steam Safety Valve Setpoints & ASME Code Requirements ML20207H3811988-08-19019 August 1988 Amend 116 to License NPF-3,revising & Deleting Listed Tech Spec Sections,License Conditions,Figures & Table ML20207D5091988-08-0404 August 1988 Amend 115 to License NPF-3,deleting Figure 6.2-1, Offsite/ Onsite Organization, & Figure 6.2-2, Station Operations Organization ML20207E3861988-08-0202 August 1988 Amend 114 to License NPF-3,changing Tech Specs to Delete Safety Features Actuation Sys Signals to Certain Valves on Secondary Side of Steam Generators & Delete Closure Time Requirements for Certain Valves ML20150C5501988-03-10010 March 1988 Omitted Tech Spec Page 3/4 8-2 to Amend 107 to License NPF-3,extending Due Date for Performing Tests & Insps Required by Surveillance Requirement 4.8.1.1.1.b to 880401 ML20150C4511988-03-0909 March 1988 Amend 109 to License NPF-3,revising Responsibilities & Authority of Station Review Board & Adding Section to Technical Review & Control ML20147H7071988-03-0202 March 1988 Amend 108 to License NPF-3,revising Tech Spec Section 3/4.3.1,Tables 3.3-1 & 4.3-1,to Address Action & Surveillance Requirements Re Reactor Trip Breaker Diverse Trip Devices ML20147C3291988-02-25025 February 1988 Amend 106 to License NPF-3,revising Tech Specs 3/4.7.10,6.4 & 6.9 & Bases 3/4.7.10 to Reflect Current Plant Design, Testing & Compensatory Measures ML20237B0271987-12-0808 December 1987 Amend 105 to License NPF-3,revising Tech Specs to Extend Due Dates for Performing Tests & Insps Required by Surveillance Requirement by Correctly Referring to Safety Features Actuation Sys Test Signal ML20235D1791987-09-21021 September 1987 Corrected Tech Spec Pages to Amends 103 & 104 to License NPF-3,changing Listed Amend Numbers ML20238E0961987-09-0808 September 1987 Amend 104 to License NPF-3,revising Tech Specs to Change Reporting Requirements for Primary Coolant Iodine Pikes from short-term Rept to Be Added in Annual Operating Rept & Delete Shutdown Requirement ML20238E0641987-09-0202 September 1987 Amend 103 to License NPF-3,revising Tech Specs to Include New Limiting Conditions for Operation & Surveillance Requirements for Moter Driven Feedwater Pump Sys ML20205C4881987-03-16016 March 1987 Amend 101 to License NPF-3,correcting Clerical Error in Tech Spec Section 3.7.9.1.a for Fire Protection ML20207S8881987-03-12012 March 1987 Amend 100 to License NPF-3,revising Tech Spec Surveillance Requirements of Dc Distribution Sys Including Batteries & Battery Chargers for Operating & Shutdown Modes ML20211G7601987-02-19019 February 1987 Amend 99 to License NPF-3,revising Tech Specs for Company Nuclear Review Board Membership by Delineating Educational & Technical Experience Required for Qualification ML20212A8411987-02-18018 February 1987 Amend 98 to License NPF-3,revising Reporting & Advising Relationship of Nuclear Review Board,Certain Sections of Tech Specs for Consistency W/B&W STS & Composition of Station Review Board ML20207S5741987-02-10010 February 1987 Corrected Amend 97 to License NPF-3,revising Tech Spec Testing Requirements for Emergency Diesel Generators to Reduce Frequency of Cold Fast Start Surveillance Tests ML20211B3021987-02-10010 February 1987 Amend 97 to License NPF-3,revising Tech Spec Testing Requirements for Emergency Diesel Generators to Reduce Frequency of Cold Fast Start Surveillance Tests ML20212C8351986-12-22022 December 1986 Amend 96 to License NPF-3,modifying Tech Spec Sections 3.7.1.2 & 4.7.1.2 & Associated Bases to Clarify Applicability of Limiting Condition for Operation & to Add New Surveillance Requirements for Auxiliary Feedwater Sys ML20212N4391986-08-20020 August 1986 Amend 95 to License NPF-3,modifying Surveillance Requirement 4.4.10.1.b to Permit one-time Extension of Surveillance Interval for Reactor Vessel Internals Vent Valves from 18 Months Until Removal of Reactor Vessel Head ML20210S0511986-04-24024 April 1986 Amend 94 to License NPF-3,changing Tech Specs to Revise Testing Requirements for Hydraulic Snubbers & Add Requirements for Mechanical Snubber Operability & Testing 1999-06-08
[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] |
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s h., t The ficien-Regu)d;oy Commissyon (the'Commissidn) has fopd that:
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$7he app'lication for amendment by the' Toledo !dison Compar4y and The
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Cleveland Electric Illuminating CompanyJthe-TicensorsJ\\tated May
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.i23, 1985, complies with the stancards a,rj rehuirements of the Atomu % 3 s and regulations set forth in 10 CFR Cha)h and the Commission's rulF
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The facility will operate in confo dity with the application, the N provisions of the Act, and the rules and regulations of the Commission;
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(Were is reasonable assurance (1) that the act'Ivities authorized by
, tgis amendment can be conducted w'1thout endangeriity the health ard E
,Safety of the public, and (ii) that suchactiv; ties will be conducted j
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f Dg de' issuance of this amendment will not tie inimhcal to the comon !
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The issuance of this amendment is in accorpance with 10 CFR Part 51.'
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Accorcingly, the license is amended by changes to the Technicr1
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1 Specif'Kations as indicated in the attachment to this license (mendment,
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and paragraph 2.C.(2) of Facility Operating License No. NPF-3"is hereby amended to t4ad as follows:
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- r.j Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 97, are hereby incorporated in the license. The Toledo Edison g'-
Cc:npany shall operate the facility in accordance with tne Technical Specifications, w
3; This license amendment is effective as of its date of issuance.
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i FOR THE NUCLEAR REGUyTORY C,0WISSION i
Jo F. Stolz, Director WRjProject Directorate #6 D vision of PWR Licensing-B i
Attachment:
- 3 Changes to the Technical Specifications Date'of Issuance
February 10, 1987
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y, ATTACPMENT TO LICENSE AMEN 0 MENT NO. 97 FACILITY OPEPATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following paces of the Appendix "A" Technical Specifications with the attached pages. The revised paces are identified by Amendment number and contain vertical lines indicatino the area of change.. The corresponding overleaf pages are also provided to maintain decueent completeness.
Pemove Insert 3/4 8-1 3/4 8-1 3/4 8-2 3/4 8-2 3/4 8-3 3/4.8-3 l
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3/4.8 ELECTRICAL POWER SYSTEMS
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3/4.8.1 A.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.1 1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
a.
Two independent circuits between the offsite transmission i
network and the onsite Class IE distribution system, each consisting of:
1.
One OPERABLE 345 KV transmission line, 2.
One OPERABLE 345-13.8 KV startup transformer, and 3.
One OPERABLE 13.8 KV bus, and b.
Two separate and independent diesel. generators each with:
1.
A separate day fuel tank containing a minimum volume of 4000 gallons of fuel, 2.
A separate fuel storage system containing a minimum volume of 32,000 gallons of fuel, and 3.
A separate fuel transfer pump.
l APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
a.
With either an offsite circuit or diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1.a within one hour and at l
least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter and by performing Surveillance Requirement 4.8.1.1.2.a.4 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Restore at least two offsite circuits and two diesel generators to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SKUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With one offsite circuit and one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing j
Surveillance Requiremeat 4.8.1.1.1.a within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter and by performing Surveillance Requirement 4.8.1.1.2.a.4 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Restore at least one of the inoperable sources to OPERABLE status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Restore at least two DAVIS-BESSE, UNIT I 3/4 8-1 Amendment No. 5,97
ELECTRICAL POWER SYSTEMS
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i ACTION (Continued) 1 offsite circuits and two diesel generators to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from the time of initial loss or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c.
With two of the above required offsite A.C. circuits inoperable, j
demonstrate the OPERABILITY of two diesel generators by performing Surveillance Requirement 4.8.1.1.2.a.4 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and at l
least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, unless the diesel generators are already opersting; restore at least one of the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. With only one offsite source restored, restore at least two offsite circuits to OPERABLE status within 72 hqurs from time of initial loss or be in at lesst HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
d.
With two of the above required diesel generators inoperable,
-demonstrate the OPERABILITY of two offsite A.C. circuits by performing Surveillance Requirement 4.8.1.1.1.a within one hour and at least once per-8 hours thereafter; restore at least one of the inoperable diesel generators to OPERABLE status within 2 i
hours or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Restore at least two. diesel generators to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from time of initial loss or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the onsite Class 1E distribution system shall be:
a.
Determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability, and b.
Demonstrated OPERABLE at least once per 18 months during shutdown by transferring (manually and automatically) unit power supply to aach of the 345 KV transmission lines.
4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:
a.
At least once per 31 days on a STAGGERED TEST BASIS, if Surveillance Requirement 4.8.1.1.2.c has not been performed within the previous 31 days, by:
DAVIS-BESSE, UNIT 1 3/4 8-2 Amendment No. 97
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1.
Verifying the fuel level in the day fuel tank.
2.
Verifying the fuel level in the fuel storage tank.
3.
Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank.
4.
Verifying the diesel starts and accelerates up to 900 rpm,
preceded by an engine prelube and/or appropriate other warmup procedures.
5.
Verifying the generator is synchronized, loaded to > 1000 kw, and operates for jt 60 minutes, and 6.
Verifying the diesel generator is aligned to provide standby power to the associated essential busses.
7.
Verifying that the automatic load sequence timer is OPERABLE with each load sequence time within 10% of its required value.
b.
At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank is within the acceptable limits specified in Table 1 of ASTM D975-68 when checked for viscosity, water and sediment.
c.
At least once per 184 days on a STAGGERED TEST,3 ASIS by:
1.
Verifying the fuel level in the day fuel tank.
2.
Verifying the fuel level in the fuel storage tank.
I 3.
Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank.
4.
Verifying the diesel starts from ambient condition and accelerates to at least 900 rpm in < 10 seconds.
l 5.
Verifying the generator is synchronized, loaded to 1 1000 kw, and operates for 1 60 minutes, and 6.
Verifying the diesel generator is aligned to provide standby power to the associated essential. busses.
7.
Verifying that the automatic load sequence timer is OPERABLE with each load sequence time uithin i 10% of its required value.
DAVIS-BESSE, UNIT 1 3/4 S-3 Amendment No. 75, 97
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.
At least once per 18 months during shutdown by:
1.
Subjecting the diesel to an inspection in accordance with procedure prepared in conjunction with its manufacturer's recommendations for this class of standby service, 2.
Verifying the generator capability to reject a load equal to the largest single emergency load supplied by the generator without tripping.
3.
Simulating a loss of offsite power in conjunction with a safety injection actuation test signal, and:
(a) Verifying de-energization of the essential busses and load shedding from the essential busses, (b) Verifying the diesel starts from ambient condition on the auto-start signal, energizes the essential busses with permanently connected 1 cads, energizes the auto-connected essential loads through the load sequencer and operates for 1 5 minutes while its generator is loaded with the essential loads.
(c) Verifying that all diesel generator trips, except-engine overspeed and generator differential, are automatically bypassed tion loss of voltage on the essential bus and/or an SFAS test signal.
4.
Verifying the diesel generator operates for 160 minutes while loaded to 1 2000 kw.
5.
Verifying that the auto-connected loads to each diesel o
generator do not exceed the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating of 2838 kw.
1 DAVIS-BESSE, UNIT 1 3/4 8-4 Amencemt No. 97
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