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 3/4.7.7ML20203C134 |
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Davis Besse |
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Issue date: |
12/02/1997 |
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From: |
Hansen A NRC (Affiliation Not Assigned) |
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To: |
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Shared Package |
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ML20203C138 |
List: |
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References |
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NUDOCS 9712150238 |
Download: ML20203C134 (10) |
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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
.
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[
k UNITE 3 STATES 3
f' NUCLEAR REGULATORY COMMISSION WASM6NGTON D.C. SpeeH001
\\.... /'j TOLEDO EDISON COMPANY
, CENTER 10R SERVICE COMPANY atQ IHLCLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-3_%
Dayli-E iSE NUCLEAR POWER STATION. UNIT NO. 1 AENDMENT TO FACillTY OPERATING LICENSE Amendment No.217 License No. NPF-3 1.
The Nuclear Regulatory Connission (the Comission) has found that:
A.
The application for smandment by the Toledo Edison Company, Centerior Service Company, and The Cleveland Electric illuminating Company (the licensees) dated September 17, 1996, as supplemented by letters dated November 27, 1996, and October 14, 1997, complies with the standards and requirements 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; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of sne Commission; C.
There is reasonabic assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) thtt such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendnient will not be inimical to the common defense and security or to the health and safety of the pubitc; and E.
The issuance of this amendment is in wcordance with 10 CFP. Part 51 of the Commission's regulations and all aoplicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2)llows:of Facility Operating License No. NPF-3 is hereby amended to read as fo 9712150238 971202 DR ADOCK 050 y 6
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 217. ure hereby incorporated in the license.
The roledo Edison Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented no later than 120 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Allen G. Hansen, Project Manager Project Directorate 111-3 Division of Reactor Projects 111/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: December 2. 1997
ATTACHMENT TO LICENSE AMENDMENT NO. 217 FAClllTY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following anges of the Appendix "A" Technical Specifications with the attached pages. T1e revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Insert 3/4 6-28 3/4 6-28 3/4 6-29 3/4 6-29 3/4 7-17 3/4 7-17 3/4 7-18 3/4 7-18 3/4 7-23 3/4 7-23 3/4 9 12 3/4 9-12 B 3/4 7-Sa B 3/4 7-Sa
L CONTAINMENT SYSTEMS r
3/4.6.5 SHIELD BUILDING EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.5.1 Two independent emergency ventilation systems shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACIION:
With one emergency ventilation system inoperable, restore the inoperable system to OPERABLE status within 7 days 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
- hours, f
SURVEllLANCE RE0VI_REMENTS 4.6.5.1 Each emergency ventilation system shall be demonstrated OPERABLE:
At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes, b.
At least once each REFUELING INTERVAL or (1) after any structural l
maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:
DAVIS-BESSE, UNIT 1 3/4 6-28 Amendment No.1&&r217
[4NTAINMENT SYSTEMS SURVElltf,Ef RE0VIREMENTS (Continued) 1.
Verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1% and uses the test procedure guidance in Regulatory Positions C.5.a. C.5.c and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 8,000 cfm i 10%;
2.
Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a* of Regulator)
Guide 1.52, Revision 2, March 1978, for a methyliodide penetration of less than 1%; and 3.
Verifying a system flow rate of 8,000 cfm i 10% during system operation when tested in accordance with ANSI N510-1980, c.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber o>eration by verify-ing, within 31 days after removal, that a la) oratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a* of Regulatory Guide 1.52, Revision 2, March 1978, for a methyliodide penetration of less than 1%.
d.
At least once each REFUELING INTERVAL by:
l 1.
Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the system at a flow rate of 8,000 cfm i 10%;
2.
Verifying that the system starts automatically on any containment isolation test signal; 3.
Verifying that the filter cooling bypass valves can be manually opened; and
- The test is performed in accordance with ASTM D 3803-1979 with the following conditions:
- 1) equilibrate for 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> at 30'C/70% relative humidity (RH), 2) challenge for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 30*C/70% RH, 3) elution for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 30'C/70% RH.
DAVIS-BESSE, UNIT 1 3/4 6-29 Amendment No. 4h+35,155,209,217
i PLANT SYSTEMS 3/4.7.6 CONTROL RDON EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.6.1 Two independent control room emergency ventilation systems shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one control room emergency ventilation system inoperable, restore the.
inoperable system to OPERABLE status within 7 days 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 4.7.6.1 fach control room emergency ventilation system shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control room air ten.perature is less than or equal to 110'F when the control room emergency ventilation system is operating.
b.
At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes, c.
At least once each REFUELING INTERVAL or (1) after any structural l
maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicatil.g with the system by:
DAVIS-BESSE,' UNIT 1 3/4 7-17 Amendment No. 135,155,217
fibHT SYSTEMS SVRVElllANCE RE0VIREMENTS (ContinuedL
- 1. Verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1% and uses the test procedure guidance in Regulatory Positions C.S.a. C.S.c and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 3300 cfm 110%;
2.
Verifying, within 31 days after removal, that a laboratory analysis of a representative carbnn sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52 Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a* of Regulatory Guide 1.52, Revision 2, March 1978, for a methyliodide penetration of less than 1%; and 3.
Verifying a system flow rate of 3300 cfm 110% during system operation when tested in accordance with ANSI N510-1980.
d.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcotl adsorber operation by verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position,6,b of Regulatory Guide 1.52, Revision 2, r
March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a* of Regulatory Guide 1.52, Revision 2, March 1978, for a methyliodide penetration of less than 1%.
e.
At least ence each REFUELING INTERVAL by:
l 1.
Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 4.4 inches Water Gauge while operating the system at a flow rate of 3300 cfm 110%;
2.
Verifying that the control room normal ventilation system is isolated by a SFAS test signal and a Station Vent Radiation High test signal; and The test is performed in accordance with ASTM D 3803-1979 with the following conditions:
- 1) equilibrate for 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> at 30'C/70% relative humidity (RH), 2) challenge for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 30'C/70% RH, 3) elution for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 30*C/70% RH.
DAVIS-BESSE, UNIT 1 3/4 7-18 Amendment No. 444rl45,155,209,217
PLANT SYSTEMS SURVEllLANCE REOUIREMENTS (Continued)
The inspection interval for functional testing shall be each REFUELING INTERVAL.
Snubbers which are scheduled for removal for seal maintenance may be included in the test sample prior to any maintenance on the snubber.
The representative sample shall conste
' at least 10 group of(rounded off to next highest.?".ger) of each nercent snubbers in use in the Plant. The selection process shall ensure that all snubbers, regardless of their accessibility classification, are functionally tested at least once every ten inspect'on intervals.
c.
Acceptance Criteria for hydraulic snubbers (either N 1 ace testing or bench testing), the test shall verify t1at:
1.
Snubber piston w!11 allow the hydraulic fluid to
" bypass" from one side of the piston to the other to assure unrestrained action is achieved within the specified range of velocity or acceleration in both tension and compression.
2.
When the snubber is subjected to a movement which creates a laid condition thtt exceeds the specified range of velocity or acceleration, the hydraulic fluid is trapped in one end of the snubber causing suppression of that movement.
3.
Snubber release rate or bleed rate, where required, occurs in compression and tension.
For mechanical snubber in place and bench testing, the test shall verify that:
1.
The force tu.t initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force.
2.
Activation (restraining action) is achieved in both tension and compression within the specified range.
DAVIS-BESSE, UNIT 1 3/4 7-23 Amendment No. 53,^',111,217 w-
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REFUELING OPERATIONS
~ STORAGE POOL VENTILATION' LIMITING CONDITION FOR OPERATION 3.9.12 Two independent emergency ventilation systems servicing the storage pool area shall be OPERABLE.
APPLICABILITY: Whenever irradiated fuel is in the storage pool.
ACTION:.
a.
With one emergency ventilation system servicing the storage p l area.
inoperable, fuel movement within the storage pool or crane ope.. tion with loads over the storage paol may proceed provided the OPERABLE emergency ventilation system servicing the storage pool area is in operation and discharging through a' ; east one train of HEPA filters and charcoal adsorbars.
b.
With no emergency ventilation system servicing the storage pool area OPERABLE, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool until at least one system is restored to OPERABLE status, c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable, i
SURVEILLANCE RE0VIREMENTS 4.9.12.1 The above required emergency ventilation systeni servicing the storage pool area shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.6.5.1, and at least once each REFUELING INTERVAL-by verifying l
the storage pool area at a negative pressure of 21/8 inc$e pool area maintains that the emergency ventilation system servicing the storag es Water Gauge relative to the outside atmosphere during system operation.
4.9.12.2 The normal. storage caol ventilation system shall be demonstrated CPERABLE at least once each Rif0ELING INTERVAL by verifying that the system fans l
stop automatically and that dampers automatically divert flow into the emergency ventilation syster. On a fuel storage area high radiation test signal.
J DAVIS-BESSE, UNIT 1 3/4 9-12 Amendment No. 4%r217
I PLANT SYSTEMS BASES When a snubber is found inoperable through a visual or functional test, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in order to determine if any safety-related component or system has been adversely affected by the inoperability of the snubber.
The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect u* degrada-tion on the supported component or system.
To provide assurance of snubber functional reliability, e cwre',entative sample of the installed snubbers will be functionally tested each REFUELING INTERVAL.
Observed failures of these sample snubbers shall require functional testing of additional units. When a snubber is found to be inoperable due to failure to lock up or failure to move (i.e., frozen in place), the cause will be evaluated for further action or testing.
In cases where the cause of failure has been identified, additional snubbers that have a high probability for the sama type of failure or are being used in the same application that caused the failure shall be tested. This requirement increases the probability of locating inoperable snubbers without testing 100% of the snubbers.
Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.
DAVIS-BESSE, UNIT 1 B 3/4 7-Sa Amendment No. 947 217
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