Letter Sequence Other |
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MONTHYEARML20151A3321988-03-30030 March 1988 Proposed Tech Specs Revising Tech Spec 3/4.4.2,Figures 3.4-2a & 2b,Tech Spec 3/4.4.9.1,Figures 3.4-2,3.4-4,3.4-4, Table 4.4-5 & Tech Spec Bases Section 3/4.4.9,Bases Table 4-1 & Bases 4-1 & 4-2 Project stage: Other ML20151A3121988-03-30030 March 1988 Application for Amend to License NPF-3,revising License Condition 2.C.(3)(d),including Tech Spec 3/4.4.2,Figures 3.4-2a & 2b,Tech Spec 3/4.4.9.1,Figures 3.4-2,3.4-3 & 3.4-4 & Table 4.4-5 & Tech Spec Bases Section 3/4.4.9 Project stage: Request ML20151A2981988-03-30030 March 1988 Forwards Application to Amend License NPF-3,revising License Condition 2.C.(3)(d),including Tech Spec 3/4.4.2, Figures 3.4-2a-2b,Tech Spec 3/4.4.9.1,Figures 3.4-2,3.4-3 & 3.4-4,Table 4.4-5 & Tech Spec Bases Section 3/4.4.9 Project stage: Request ML20154P3381988-05-25025 May 1988 Responds to Generic Ltr 88-03 Re Resolution of Safety Issue 93, Steam Binding of Auxiliary Feedwater Pumps Project stage: Other ML20207H3811988-08-19019 August 1988 Amend 116 to License NPF-3,revising & Deleting Listed Tech Spec Sections,License Conditions,Figures & Table Project stage: Other ML20207H3941988-08-19019 August 1988 Notice of Issuance of Amend 116 to License NPF-3 Project stage: Approval ML20207H3891988-08-19019 August 1988 Safety Evaluation Supporting Amend 116 to License NPF-3 Project stage: Approval 1988-05-25
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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] |
Text
-
4 UNITED STATES
'7'n NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
%,...../
TOLED0 EDIS0N COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET N0. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.116 License No. NPF-3 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amandment by the Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated March 30, 1988, supplemented May 4, 1988 complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations;
)
D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and by amending paragraphs 2.C.(2) and 2.C.(3)(d) of Facility Operating License No. NPF-3 to read as follows:
8808260350 800819 DR ADOC;'. 0500 6
I
, 2.C.(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.116, are hereby incorporated in the license. The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.
2.C.(3)(d) Prior to operation beyond 10 Effective Full Power Years, the Toledo Edison Company shall provide to the NRC a reanalysis and proposed modifications, as necessary, to ensure continued means of protection again.ct law temperature reactor coolant system overpressure avercs.
3.
This license amendment is effectivt as of its date of issuance and shall be implemented prior to entering M(de 2 following the fifth refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION g
Kenneth E. Perkins, Director Project Directorate III-3 Division of Reactor Projects - III, IV, V, & Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: August 19, 1988
1
)
ATTACHMENT TO LICENSE AMENDMENT NO.116 FACILITY OPERATING LICENSE N0. NPF-3 DOCKET NO. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Remove Insert 3/4 4-3 3/4 4-3 3/4 4-4a 3/4 4-4a 3/4 4-4b 3/4 4-4b 3/4 4-24 3/4 4-24 3/4 4-25 3/4 4-25 3/4 4-26 3/4 4-26 3/4 4-27 3/4 4-27 3/4 4-28 3/4 4-28 8 3/4 4-7 B 3/4 4-7 B 3/4 4-8 B 3/4 4-8 B 3/4 4-9 8 3/4 4-9 B 3/4 4-10 8 3/4 4-10 B 3/4 4-11 B 3/4 4-11 B 3/4 4-12 B 3/4 4-12
REACTOR COOLANT SYSTEM SAFETY VALVES AND ELECTROMATIC RELIEF VALVE - OPERATING LIMITING CONDITION FOR OPERATION 3.4.3 All pressurizer code safety valves shall be OPERABLf. with a lift setting of < 2525 PSIG.* When not isolated, the pressurizer electromatic relief valve shall have a trip setpoint of > 2390 PSIG and an allowable value of > 2390 PSIG.**
l APPLICABILITY: MODES 1, 2 and 3.
ACTION:
With one pressurizer code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.3 For the pressurizer code safety valves, there are no additional Surveillance Requirements other than those required by Specification 4.0.5.
For the pressurizer electromatic relief valve a channel cali-bration check shall be performed every 18 months.
The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
Allowable value for channel calibration check.-
DAVIS-BESSE, UNIT 1 3/4 4-4 Amendment No. 33,60
2 REACTOR COOLANT SYSTEM SAFETY VALVES - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.2 Decay Heat Removal System relief valve DH-4849 shall be OPERABLE with a lift setting of 5 330 PSIG* and isolation valves DH-11 and DH-12 open and control power to their valve operators removed.
APPLICABILITY: MODES 4 and 5.
ACTION:
A.
With DH-4849 not OPERABLE:
1.
Make the valve OPERABLE within eight hours; or 2.
a.
Within next one hour, disable the capability of both high pressure injection (HPI) pumps to inject water into the reactor coolant system; and b.
Within next eight hours:
1.
Disable the automatic transfer of makeup pump suction to the borated water storage tank on low makeup tank level; and 2.
Reduce makeup tank level to 5 73 inches and reduce reactor coolant system pressure and pressurizer level within the acceptable region on Figures 3.4-2a (in MODE 4) and 3.4-2b (in MODE 5).
B.
With DH-11 or DH-12 closed, open DH-21 and DH-23 within one hour.
C.
With the control power not removed from DH-11 and DH-12, remove the power to the valve operators at the Motor Control Centers within one hour.
SURVEILLANCE REQUIREMENTS 4.4.2 Decay Heat Removal System relief valve DH-4849 shall be determined OPERABLE:
per the surveillance requirements of Specification 4.0.5.
a.
b.
at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying either:
1.
isolation valves DH-11 and DH-12 open with control power removed from their valve operators; or 2.
valves DH-21 and DH-23 open.
The lift seiting pressure shall correspond to ambient conditions of the valve at nominal o;srating temperature and pressure.
DAVIS-BESSE, UNIT 1 3/4 4-3 Amendment No. 57,116
\\
l Figure 3.4-2b l
Reactor Coolant System Pressure - Pressurizer Level s
Limits for inoperable Decay Heat Removal System Relief Value in MODE 5 400 I
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NOTE: NOT CORRECTED FOR INSTRUMENT ERROR 350 i
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D 300 0
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250 UNACCEPTABLE REGION a
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MODE 5 ACCEPTABLE REGION N
O 40 80 120 160 200 240 Initial Pressurizer level (Inches)
DAVIS-BESSE, UNIT 1 3/4 4-4b Amendment Fe. $1,116
l i
l Figure 3.4-2a Reactor Coolant System Pressure - Pressurizer Level Limits for inoperable Decay Heat Removal System Relief Valve in MODE 4 400 350 UNACCEPTABLE REGION
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NOT CORRECTED TOR INSTRUMENT ERROR 1 1 0
40 80 120 160 200 240 Initial Pressurizer Level (Inches) l I
l DAVIS-BESSE, UNIT 1 3/4 4-4a Amendment No. 88 116
REACTOR COOLANT SYSTEM 3/4.4.9 PRESSURE /TEMPERATLRF LIMITS REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION 3.4.9.1 The Reactor Coolant system (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figures 3.4-2, 3.4-3 and 3.4-4 during heatup, cooldown, criticality, and inservice leak and hydrostatic testing with:
A maximum heatup of 50 F in any one hour period, and l
a.
b.
A maximum cooldown of 100*F in any one hour period with cold leg temperature > 270*F and a maximum cooldown of 50*F in any one hour period with cold leg temperature <270*F.
APPLICABILITY: At all times.
ACTION:
With any of the above limits exceeded, restore the temperature and/or pressure to within the limits within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the integrity of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operation 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 be 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 4.4.9.1.1 The Reactor Coolant System temperature and pressure shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations.
4.4.9.1.2 The reactor vessel material irradiation surveillance specimens representative of the vessel materials shall be removed and examined, to determine changes in material properties, at the intervals defined in BAW 1543A.
The results of these examinations shall be used to update Figures 3.4-2, 3.4-3 and 3.4-4.
DAVIS-BESSE, UNIT 1 3/4 4-24 Amendment No. 8J, 116
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20 30 40 50 80 70 80 90 100 PERCENT OF RATED THERMAL POWER FIGURE 3.41 DOSE EQUIVALENT l-131 Primary Coolant Specific ActMty Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific ActMty > 1.0gCl/ gram Dose Equivalent 1131 l
DAVIS-BESSE, UNIT 1 3/4 4 23 1
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to Reactor Coolant System Pressure - Temperature Limits m
for Cooldown for the First 10 EFPY l-M e
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Allowable coeldeve sete ebeve 270 F de 100 F/ita (peop). Sielted by a IS F etop cheage felleeed by e 9 eteete held.
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1800
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50 100 150 200 250 300 350 400 450 Indicated Reactor Coolant Inlet Temperature. F
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Instrument error is met eccounted for in these Ilmits.
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DAVIS-BESSE, UNIT 1 3/4 4-28 Amendment No. #1,116 l
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Reactor Coolant System Pressure - Temperature lleatup and g
Cooldown Limits for Inservice Leak and Hydrostatic Tests y
for the First 10 EFPY l
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Alloweble coeldeve rate ebeve 270 F is 100 F/NR (Beep), lletted by a 13 F step change tellowed by a 9 elevte held.
3.
Allowable eeeldewe rete et er below 270 F is 30 F/ma (Resp). Ilmited by e IS F etep cheoge fellowed by se 18 eleste held.
oo; 2000
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a -.lene step t.e,neta. chose. IS r t.
11 e6te ebee re.las gg all RC pumps free operstles alth the Dora.ystee operettes. The step temperature ebenge is defleed e. the SC temp eless the Osa rotere temp to the seector reeleet systee prior to 1800 ei.pples all ac peop..
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Indicated Reactor Coolant inlet Temperature. F 1
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Bases Fiaure 4-2 Effect of Fluence and Copper Content on Shift of RT f r Reactor Vessel Steels Exposed to 550*F ET Temperature 4
DELETED i
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DAVIS-BESSE, UNIT 1 B 3/4 4-8 Amendment No.116 w-F 9
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Fast Neutron Fluence (E>1 tiev).as a Function of Full Power Service Life DELETED-i i
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l DAVIS-BESSE, UNIT 1 B 3/4 4-7 Amendment No.116 i
1 o
I REACTOR COOLANT SYSTEM BASES The closure head region is significantly stressed at 7.elatively low temperatures (due to mechanical loads resulting from bolt pre-load). This region largely controls the pressure-temperature listitations of the first several service periods. The outlet nozzles of the reactor vessel also affect the pressure-temperature limit curves of the first several service periods. This is due to the high local stresses at the inside corner of the nozzle which can be two to three times the membrane stresses of the shell. Af ter the first several years of neutron radiation exposure, the RT temperature of the beltline region materials will be high enough so th!Ethebeltlineregionofthereactorvesselwillstarttocontrolthe pressure-temperature limitations of the reactor coolant pressure boundary.
For the service period for which the limit curves are established, the maximum allowable pressure as a function of fluid temperature is obtained
)
through a point-by point comparison of the limits imposed by the closure j
head region, outlet nozzles, and beltline region. The maximum allowable pressure is taken to be the lower pressure of the three calculated pressures.
The pressure limit is adjusted for the pressure differential between the point of system pressure measurement and the limiting component for all operating reactor coolant pump combinations.
The limit curves were prepared based upon the most limiting adjusted reference temperature of all the beltline region materials at the end of the tenth effective full power year.
The actual shift in RT f the beltline region material will be estab-NDT lished periodically during operation by removing and evaluating, in accordance with Appendix H to 10 CFR 50, reactor vessel material irradiation surveillance specimens installed near the inside wall of the reactor vessel in the core area.
Since the neutron spectra at the irrriiation samples and vessel inside the radius are essentially identical, the measured transition shift for a sample can be applied with confidence to the adjacent section of the reactor vessel. The limit curres must be recalculated when the ART differen: fromthecalculkk}dARTdetermined from the surveillance capsule is NDT r the equivalent capsule radiation 1
exposure.
DAVIS-BESSE, UNIT 1 B 3/4 4-13 Amendment No.116
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I DAVIS-BESSE, UNIT 1 B 3/4 4-9 Amendment No, 116
)
REACTOR COOI. ANT SYSTEM BASES The number of reactor vessel irradiation surveillance specimens and the frequencies for removing and testing these specimens are provided in BAW 1543A. The withdrawal schedule is based on four considerations:
l (a) uncover possible technical anomalies as early in life as they can be detected (end of first fuel cycle), (b) define the material properties needed to perform the analysis required by Appendix G to 10 CFR 50, (c) reserve two capsules for evaluation of the effectiveness of thermal annealing in the event inplace annealing becomes necessary, (d) provide material property data corresponding to the reactor vessel beltline conditions at the end of service.
This withdrawal schedule is specified to assure compliance with the requirements of Appendix H to 10 CFR 50.
Appendix H references the requirements of ASTM E185 for surveillance program criteria.
l l
l DAVIS-BESSE, UNIT 1 B 3/4 4-12 Amendment No. 82 116
(
+
REACTOR COOLANT SYSTEM BASES The unirradiated transverse impact properties of the beltline regiou materials, required by Appendices G and H to 10 CFR 50, were determined for those materials for which sufficient amounts of material were available. The adjusted reference temperatures are calculated by adding i
the piedicted radiation-induced ART and the unirradiated RT The proceduresdescribedinRegulatory60Ide1.99,Rev.2,wereusggT.g,,
predicting the radiation induced ART as a function of the material's copper and nickel content and neutrogD}1uence.
Figure 3.4-2 presents the pressure-temperature limit curve for normal heatup. This figure also presents the core criticality limits as required by Appendix G to 10 CFR 50. Figure 3.4-3 presents the pressure-temper-ature limit curve for normal cooldown. Figure 3.4-4 presents the pressure-temperature limit curves for beatup and cooldown for inservice leak and hydrostatic testing.
All pressure-temperature limit curves are applicable up to the tenth
(
effective full power year. The protection against non-ductile failure is assured by maintaining the coolant pressure below the upper limits of Figures 3.4-2, 3.4-3 and 3.4-4, 1
l l
1 l
DAVIS-BESSE, UNIT 1 B 3/4 4-11 Amendment No. 116