Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
Results
Other: ML20096C682, ML20149J903, ML20149J964, ML20151X241, ML20209H917, ML20215L839, ML20216H604, ML20235W129, ML20236H021, ML20236X859, ML20237A688
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MONTHYEARML20096C6631984-08-27027 August 1984 Application for Amend to License NPF-3,revising Tech Specs to Reflect Changes in Reactor Vessel Matls Irradiation Surveillance Schedule & Flow Verification of Auxiliary Feedwater Sys.Fee Paid Project stage: Request ML20096C6401984-08-27027 August 1984 Forwards Application to Amend License NPF-3,revising Tech Specs to Reflect Changes in Reactor Vessel Matls Irradiation Surveillance Schedule & Flow Verification of Auxiliary Feedwater Sys Project stage: Request ML20096C6821984-08-27027 August 1984 Proposed Tech Specs Reflecting Changes in Reactor Vessel Matls Irradiation Surveillance Schedule & Flow Verification of Auxiliary Feedwater Sys Project stage: Other B12414, Application for Amend to License NPF-49,extending 18-month Surveillance Testing Requirements for Diesel Generator Up to 4 Months Beyond Max Allowed by Tech Spec Section 4.0.2,on one-time Basis1987-01-30030 January 1987 Application for Amend to License NPF-49,extending 18-month Surveillance Testing Requirements for Diesel Generator Up to 4 Months Beyond Max Allowed by Tech Spec Section 4.0.2,on one-time Basis Project stage: Request ML20209H9171987-01-31031 January 1987 Proposed Tech Specs,Extending Diesel Generator 18-month Surveillance Requirements Up to 4 Months Beyond Max Allowed by Tech Spec Section 4.0.2 on one-time Basis Project stage: Other B12448, Submits Addl Info Re 870130 Application for Amend to License NPF-49,revising Tech Specs to Extend Diesel Generator 18-month Surveillance Testing Requirements,Per 870224 Telcon1987-03-0606 March 1987 Submits Addl Info Re 870130 Application for Amend to License NPF-49,revising Tech Specs to Extend Diesel Generator 18-month Surveillance Testing Requirements,Per 870224 Telcon Project stage: Request ML20215K3801987-05-0404 May 1987 Requests Reissuance of Table 3.6-2, Containment Isolation Valves of Tech Spec 3/4.6.3,correcting Typos in 840911 Application to Amend License NPF-3 Project stage: Request ML20215L8141987-05-0404 May 1987 Forwards Application for Amend to License NPF-3,deleting Portion of Tech Spec Surveillance Requirement 4.7.1.2d to Reflect Mods to Steam Line Piping to Auxiliary Feed Pump Turbine Following 850609 Loss of Feedwater Event.Fee Paid Project stage: Request ML20215L8351987-05-0404 May 1987 Application for Amend to License NPF-3,deleting Portion of Tech Spec Surveillance Requirement 4.7.1.2d Re Auxiliary Feedwater Sys as Result of 850609 Loss of Feedwater Event. Supporting Documentation Encl Project stage: Request ML20215L8391987-05-0404 May 1987 Proposed Tech Specs Re Auxiliary Feedwater Sys Surveillance Requirement 4.7.1.2d Project stage: Other ML20214K7241987-05-20020 May 1987 Forwards Application for Amend to License NPF-3,revising Tech Specs Re Fire Protection to Assist in Transfer of Fire Protection Program to Updated Sar,Per Generic Ltr 86-10.Fee Paid Project stage: Request ML20214K7551987-05-20020 May 1987 Application for Amend to License NPF-3,revising Tech Specs Re Fire Protection to Implement Guidance of Generic Ltr 86-10 & to Transfer Fire Protection Program to Updated SAR Project stage: Request ML20214K7721987-05-20020 May 1987 Proposed Changes to Tech Specs Re Fire Protection to Assist in Transfer of Fire Protection Program to Updated Sar,Per Generic Ltr 86-10.Safety Evaluation & Significant Hazards Consideration Encl Project stage: Request ML20216H6041987-06-25025 June 1987 Advises That Based on B&W Analytical Studies for Primary Sys Blowdown Using RELAP5,use of Blowdown Valves Not Practicable for Feed & Bleed,Per 851204 Commitment.Listed Proposed Mods Will Be Implemented to Enhance Makeup Sys Project stage: Other ML20235W1291987-10-0909 October 1987 Proposed Tech Specs,Allowing one-time Extension of 18 Month Emergency Diesel Generator Surveillance Interval Project stage: Other ML20235W1271987-10-0909 October 1987 Application for Amend to License NPF-3,revising Tech Specs to Allow one-time Extension of 18 Month Surveillance Interval for Insp & Operability Testing of Emergency Diesel Generators Project stage: Request ML20235W1121987-10-0909 October 1987 Forwards Application for Amend to License NPF-3.Amend Revises Tech Specs to Allow one-time Extension in 18 Month Surveillance Interval for Insp & Operability Testing of Emergency Diesel Generators.Fee Paid Project stage: Request ML20236H0211987-10-27027 October 1987 Proposed Tech Specs,Changing Section 3/4.3.2, Safety Sys Instrumentation, Table 3.3-5 & Section 3/4.6.3, Containment Isolation Valves, Table 3.6-2 to Support Enhanced Feed & Bleed Mods Project stage: Other ML20236G9801987-10-27027 October 1987 Application for Amend to License NPF-3,revising Tech Spec Section 3/4.3.2, Safety Sys Instrumentation, Table 3.3-5 & Section 3/4.6.3, Containment Isolation Valves, Table 3.6-2 to Support Enhanced Feed & Bleed Mods.Fee Paid Project stage: Request ML20236N1671987-11-0707 November 1987 Discusses 871029 & 30 Fire Protection Meetings in Bethesda, MD Re Issues Which Have Arisen in Conjunction W/Licensee App R Reappraisal Effort,Including Status of Fire Protection on Plant Mods.List of Attendees Encl Project stage: Meeting ML20236X8591987-12-0707 December 1987 Proposed Tech Specs Re Fire Protection Project stage: Other ML20236X8331987-12-0707 December 1987 Application for Amend to License NPF-3,revising Tech Specs Re Fire Protection Project stage: Request ML20236X8221987-12-0707 December 1987 Forwards Application for Amend to License NPF-3,revising Tech Specs Re Fire Protection Per Generic Ltr 86-10 Project stage: Request ML20237A6881987-12-0808 December 1987 Informs of Changes Necessary to Support Fifth Refueling Outage in Feb 1988.Key Amend Requests Placed Into 1 of 3 Listed Categories.Nrc Should Allocate Necessary Resources to Provide Timely Support for Review & Issuance of Amends Project stage: Other ML20236Y3421987-12-0808 December 1987 Forwards Application for Amend to License NPF-3,revising Tech Spec 4.6.1.2c.3,Section 3/4.6.1.2 Re Containment Sys & Containment Leakage.Fee Paid Project stage: Request ML20149J9031988-02-10010 February 1988 Forwards Environ Assessment & Finding of No Significant Impact Re Util 871207 Application for Amend to License NPF-3 to Update Tech Specs to Reflect Current Plant Design, Testing & Compensatory Measures Re Fire Protection Features Project stage: Other ML20149J9641988-02-10010 February 1988 Environ Assessment & Finding of No Significant Impact Based on Util 871207 Application for Amend to License NPF-3, Updating Tech Specs to Reflect Current Plant Design,Testing & Compensatory Measures Re Fire Protection Features Project stage: Other ML20150B0321988-03-0707 March 1988 Forwards Application for Amend to License NPF-3 Changing Tech Spec Section 4.6.1.2.a to Allow Third Type a Test & 10-yr Inservice Insps to Be Uncoupled & Performed in Separate Refueling Outages.Fee Paid Project stage: Request ML20151X2411988-04-29029 April 1988 Forwards Discussion of & Proposed Revs to Tech Specs for Resolution of NRC Comments Concerning Deletion of Auxiliary Feedwater Pump Turbine Inlet Steam Pressure Interlock Operability Requirements,Per 880406 Telcon Project stage: Other ML20154N9081988-09-23023 September 1988 Summary of 880721 Meeting/Util in Rockville,Md Re Licensee App R Reappraisal Efforts.List of Meeting Attendees & Viewgraphs Encl Project stage: Meeting 1987-12-08
[Table View] |
Proposed Tech Specs,Changing Section 3/4.3.2, Safety Sys Instrumentation, Table 3.3-5 & Section 3/4.6.3, Containment Isolation Valves, Table 3.6-2 to Support Enhanced Feed & Bleed ModsML20236H021 |
Person / Time |
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Site: |
Davis Besse ![Cleveland Electric icon.png](/w/images/7/78/Cleveland_Electric_icon.png) |
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Issue date: |
10/27/1987 |
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From: |
TOLEDO EDISON CO. |
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To: |
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Shared Package |
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ML20236G984 |
List: |
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References |
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TAC-66415, NUDOCS 8711030393 |
Download: ML20236H021 (17) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20216E6111999-09-0707 September 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210H0731999-07-28028 July 1999 Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4311999-07-27027 July 1999 Proposed Tech Specs,Changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4801999-07-26026 July 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210G9161999-07-26026 July 1999 Proposed Tech Specs 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 ML20210G5391999-07-26026 July 1999 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing ML20195F9351999-06-10010 June 1999 Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs ML20207E7941999-05-21021 May 1999 Proposed Tech Specs Allowing Use of Expanded Spent Fuel Storage Capability ML20205E5031999-03-19019 March 1999 Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application ML20204F1821999-03-0909 March 1999 Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A ML20155E3231998-10-28028 October 1998 Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155E4971998-10-28028 October 1998 Proposed Tech Specs 4.0.2 Re Applicability of 25% Surveillance Interval Extension Allowance ML20155D7791998-10-27027 October 1998 Proposed Tech Specs Relocating 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 ML20155E0721998-10-27027 October 1998 Proposed Tech Specs Revising 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation,To Provide Potential Reduction in Spurious Trip Rate for Potential Cost Savings in Excess of $50,000 ML20155D8521998-10-27027 October 1998 Proposed Tech Specs Revising 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 ML20151W2991998-09-0808 September 1998 Proposed Tech Specs Revising Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20151W3071998-09-0808 September 1998 Proposed Tech Specs Permitting Use of Framatome Cogema Fuels M5 Advanced Alloy for Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20217P8351998-04-24024 April 1998 Proposed Tech Specs Clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20217P8811998-04-24024 April 1998 Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual ML20217C4881998-03-20020 March 1998 Proposed Tech Specs SR 4.4.5.3.c.1,providing Greater Specificity as to Location of Addl Insps in Unaffected SG ML20217N4471998-02-27027 February 1998 Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431 ML20203L1111998-02-26026 February 1998 Proposed Tech Specs Pages Re Amend to License NPF-3 Involving Incorporation of New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2621997-12-23023 December 1997 Proposed Tech Specs Pages Re Changes to TS Definition 1.2, TS 3/4/9.5 & New TS 3.0.6 & Associated Bases.Ts Index Rev to Reflect Change to TS 3/4.9.5,included ML20197J5971997-12-23023 December 1997 Proposed Tech Specs Pages,Revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217R2821997-08-26026 August 1997 Proposed Tech Specs,Clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2871997-08-26026 August 1997 Proposed Tech Specs,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 ML20217G5981997-07-29029 July 1997 Proposed Tech Specs 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating ML20141F1101997-06-24024 June 1997 Proposed Tech Specs,Deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138C3261997-04-18018 April 1997 Proposed Tech Specs 3/4.7.6 Revising Limiting Condition for Operation to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20138A6891997-04-18018 April 1997 Proposed Tech Specs 3/4.5.3.2.1 & 3/4.5.2 Modifying Presently Specified 18-month Surveillance Frequencies to New Specified Frequencies of Once Each 24-months ML20138M1281997-02-14014 February 1997 Proposed Tech Specs 3.5.2 Re Emergency Core Cooling Systems & 4.5.2.f Re Surveillance Requirements ML20134L0561997-02-13013 February 1997 Proposed Tech Specs Re Changes Made Concerning Decay Heat Removal Sys Valve ML20134D7621997-01-30030 January 1997 Proposed Tech Specs 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 ML20134F1811997-01-30030 January 1997 Proposed Tech Specs Re Possession & Use of SNM as Reactor Fuel ML20134B0591997-01-20020 January 1997 Proposed Tech Specs 3/4.5.3 Re ECCS Subsystems ML20132B7031996-12-11011 December 1996 Proposed Tech Specs Revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle for License NPF-3 ML20134F1891996-10-28028 October 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20117P5311996-09-17017 September 1996 Proposed Tech Specs,Supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8531996-09-12012 September 1996 Proposed Tech Specs Re Reactivity Control Systems & Emergency Core Cooling Systems ML20117M2201996-09-0404 September 1996 Proposed Tech Specs 6.2.3,removing Specific Overtime Limits & Working Hours ML20116K2631996-08-0707 August 1996 Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle ML20117K1911996-05-28028 May 1996 Proposed Tech Specs 3/4.3.1.1 - RPS Instrumentation & TS 3/4.3.2.3 - Anticipatory RTS Instrumentation Increasing Trip Device Test Interval ML20101M1921996-03-29029 March 1996 Proposed Tech Specs 3/4.6.4.4 - HPS,3/4.6.5.1 - Shield Building Evs & 3.4.7.6.1 - CREVS Re Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability in ESF AHUs ML20101C6961996-03-0606 March 1996 Proposed Tech Specs,Allowing Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI Pump 1-2 Until 10th Refueling Outage,Scheduled to Begin 960408 ML20100E0101996-02-0505 February 1996 Proposed TS 3/4.3.2.1,Table 3.3-3,safety Features Actuation Sys Instrumentation,Reflecting Design & Actuation Logic of Plant Sequencers & Essential Bus Undervoltage Relays ML20095F5891995-12-12012 December 1995 Proposed Tech Specs Re Containment Sys ML20094D0611995-10-31031 October 1995 Proposed TS Page 6-18,deleting TS 6.9.2.d, Seismic Event Analysis ML20098C5181995-10-0202 October 1995 Proposed Tech Specs,Revising TS Section 5.0,design Features & Adopting Improved STS for B&W Plants Format & Content ML20098C4111995-09-29029 September 1995 Proposed TS 3/4.1.2.8 Re Reactivity Control Sys - Borated Water Sources - Shutdown TS 3/4.1.2.8 Re Reactivity Control Sys - Operating & TS 3/4.5.1 Re ECCS - Core Flooding Tanks ML20098C1121995-09-29029 September 1995 Proposed TS 3.4.3 & Associated Bases,Modifying Lift Setting of Pressurizer Code Safety Valves to Greater than or Equal to 2,575 Psig,Corresponding to Lift Setting Tolerance of +3% of Nominal Lift Pressure 1999-09-07
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216E6111999-09-0707 September 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210H0731999-07-28028 July 1999 Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4311999-07-27027 July 1999 Proposed Tech Specs,Changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4801999-07-26026 July 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210G9161999-07-26026 July 1999 Proposed Tech Specs 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 ML20210G5391999-07-26026 July 1999 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing ML20195F9351999-06-10010 June 1999 Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs ML20207E7941999-05-21021 May 1999 Proposed Tech Specs Allowing Use of Expanded Spent Fuel Storage Capability ML20205E5031999-03-19019 March 1999 Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application ML20204F1821999-03-0909 March 1999 Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A ML20155E4971998-10-28028 October 1998 Proposed Tech Specs 4.0.2 Re Applicability of 25% Surveillance Interval Extension Allowance ML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20155E3231998-10-28028 October 1998 Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155D7791998-10-27027 October 1998 Proposed Tech Specs Relocating 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 ML20155D8521998-10-27027 October 1998 Proposed Tech Specs Revising 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 ML20155E0721998-10-27027 October 1998 Proposed Tech Specs Revising 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation,To Provide Potential Reduction in Spurious Trip Rate for Potential Cost Savings in Excess of $50,000 ML20151W3071998-09-0808 September 1998 Proposed Tech Specs Permitting Use of Framatome Cogema Fuels M5 Advanced Alloy for Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2991998-09-0808 September 1998 Proposed Tech Specs Revising Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217P8351998-04-24024 April 1998 Proposed Tech Specs Clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20217P8811998-04-24024 April 1998 Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual ML20217C4881998-03-20020 March 1998 Proposed Tech Specs SR 4.4.5.3.c.1,providing Greater Specificity as to Location of Addl Insps in Unaffected SG ML20217N4471998-02-27027 February 1998 Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431 ML20203L1111998-02-26026 February 1998 Proposed Tech Specs Pages Re Amend to License NPF-3 Involving Incorporation of New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2621997-12-23023 December 1997 Proposed Tech Specs Pages Re Changes to TS Definition 1.2, TS 3/4/9.5 & New TS 3.0.6 & Associated Bases.Ts Index Rev to Reflect Change to TS 3/4.9.5,included ML20197J5971997-12-23023 December 1997 Proposed Tech Specs Pages,Revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20217R2821997-08-26026 August 1997 Proposed Tech Specs,Clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2871997-08-26026 August 1997 Proposed Tech Specs,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 ML20217G5981997-07-29029 July 1997 Proposed Tech Specs 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating ML20141F1101997-06-24024 June 1997 Proposed Tech Specs,Deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138C3261997-04-18018 April 1997 Proposed Tech Specs 3/4.7.6 Revising Limiting Condition for Operation to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20138A6891997-04-18018 April 1997 Proposed Tech Specs 3/4.5.3.2.1 & 3/4.5.2 Modifying Presently Specified 18-month Surveillance Frequencies to New Specified Frequencies of Once Each 24-months ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20138M1281997-02-14014 February 1997 Proposed Tech Specs 3.5.2 Re Emergency Core Cooling Systems & 4.5.2.f Re Surveillance Requirements ML20134L0561997-02-13013 February 1997 Proposed Tech Specs Re Changes Made Concerning Decay Heat Removal Sys Valve ML20134F1811997-01-30030 January 1997 Proposed Tech Specs Re Possession & Use of SNM as Reactor Fuel ML20134D7621997-01-30030 January 1997 Proposed Tech Specs 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 ML20134B0591997-01-20020 January 1997 Proposed Tech Specs 3/4.5.3 Re ECCS Subsystems ML20132B7031996-12-11011 December 1996 Proposed Tech Specs Revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle for License NPF-3 ML20134F1891996-10-28028 October 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20117P5311996-09-17017 September 1996 Proposed Tech Specs,Supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8531996-09-12012 September 1996 Proposed Tech Specs Re Reactivity Control Systems & Emergency Core Cooling Systems ML20117M2201996-09-0404 September 1996 Proposed Tech Specs 6.2.3,removing Specific Overtime Limits & Working Hours ML20116K2631996-08-0707 August 1996 Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle ML20117K1911996-05-28028 May 1996 Proposed Tech Specs 3/4.3.1.1 - RPS Instrumentation & TS 3/4.3.2.3 - Anticipatory RTS Instrumentation Increasing Trip Device Test Interval ML20101M1921996-03-29029 March 1996 Proposed Tech Specs 3/4.6.4.4 - HPS,3/4.6.5.1 - Shield Building Evs & 3.4.7.6.1 - CREVS Re Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability in ESF AHUs ML20101C6961996-03-0606 March 1996 Proposed Tech Specs,Allowing Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI Pump 1-2 Until 10th Refueling Outage,Scheduled to Begin 960408 ML20100E0101996-02-0505 February 1996 Proposed TS 3/4.3.2.1,Table 3.3-3,safety Features Actuation Sys Instrumentation,Reflecting Design & Actuation Logic of Plant Sequencers & Essential Bus Undervoltage Relays ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm 1999-09-07
[Table view] |
Text
c.
~
N?RMA"0N ONLY 1
INSTRUMENTATION
]
3/4.3.2 SAFETY SYSTEM INSTRUMENTATION -
SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION -
LIMITING CON 0! TION FOR OPERATION ,
i 3.3.2.1 The Safety Features Actuation System (STAS) functional units shown in T:ble 3.3-3 shall be OPERABLE with their trip setpoints set.
consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RE.SPONSE TIMES as shown in Table 3.3-5.
APPLICABILITY: As shown in Table 3.3-3.
I ACTION:
- a. With a SFAS functional unit trip setpoint less conservative than the value shown in the Allowable Values column of Table
. 3.3-4, declare the functional unit inoperable and apply the i applicable ACTION requirement of Table 3.3-3 until the func . i tional unit is restored to OPERABLE status with the trip i setpoint adjusted consistent with the Trip Setpoint value.
- b. With a SFAS functional unit inoperable. 'take the action-shown
. in Table 3.3-3.
SURVEILLANCE REOUTREMENTS -
l 4 . 3. 2.1.1 Each SFAS functional unit shall be demonstrated OPEP/BLE by the performance of the CFANNEL CHECX. CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST during the MODES and at the frequencies shewn in Table 4.3-2.
4.3.2.1.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of functional units affected by bypass operation. The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each functional unit affected by bypass operation.
4.3.2.1.3 The SAFETY FEATURES' RESPONSE TIME of each SFAS function shall be demonstrated to be within the limit at least once per 18 months.
Each test shall include at least one-functional unit per function such that all functional units are tested 'at least once every N times 18 months where N is the total number of redundant functional units in a-
/ specific SFAS function as shown in the " Total No. of Units" Column of Table 3.3-3. ,
DAVI'S-BESSE. UNIT 1, 3/4 3-9 -
8711030393 87102734 DR ADOCK O -.
f0fyf"0M0yy A
UBli 3.3 5
~
SAFETY FIATURES SYSTEM RESPONSE TIMES INITI ATING SIGNAL AND -FUNCTION RESPONSE TIME IN'5 ECON 05
- 1. Manual
- a. -Fans
- 1. Emergency Vent Fan NA'
- 2. Containment Cooler Fan NA
- b. HV & AC isolation Valves NA -
- 1. ECCS Room
- 2. Emergency Ventilation NA
- 3. - Containment Air Sample NA 4 Containment Purge ,
NA ,
- 5. Pentration Room Purge NA' Control Rocm HV & AC Units NA c.
- d. High Pressure Injection j
- 1. High Pressure injection' Pumps NA
- 2. High Pressure injection Valves- NA
- e. Component Cooling Water
- 1. Component Cooling Water Pumps NA
- 2. Component Cooling Aux. Equip. Inlet Valves NA '
- 3. Ccmponent Cooling to Air Compressor Valves fiA'
- f. Service Water System
- 1. Service Water Pumps MA
- 2. Service Water From Component. Cooling Heat Exchanger Isolation Valves NA
- g. Contaiment Spray isolation Yalves NA
- h. Emergency Diesel Generator. NA
- 1. Contaiment Isolation Yalves R
- 1. Vacuum Relief NA
- 2. Nonnal Sump NA
- 3. RCS Letdown Delay Coil Outlet' NA ]
4 RCS Letdown High Temperature NA ji l
i OAVIS-BESSE. UNIT 1 3/4 3 14 ._
Q_---__-__.-__-__:-_-__-__-___________
i o.
TABLE 3.3-Si(' Continued)' > I SAFETY FEATURES SYSTEM-RESPONSE-TIMES N
( INITIATING SIGNAL AND FUNCTION ,
RESPONSE TIME IN SECONDS m
- i. Containment Isolation Valves (cont'd)
- 5. Pressurizer Sample . . NA a l; 6. Service Water to Cooling Water NAL ,
7.- Vent Header. " -NA-8';
. Orain Tank: NA : .
9.- . Core F1 cod Tank = Vent NA' !
'10. Core Flood Tank Fill, NA 11.- -Steam Generator Sample. NA;
'12. Atmospheric Vent . NA.
13; Quench Tank NA-
- 14. Emergency Sump NAL
- 15. RCP Seal' Return: ,NA- H
- 16. Air Systems NA:
- 17. N,; System _ ' NA' i
- 18. Quench Tank Sample .
NA'
- 19. Main Steam Warmup.Orain- NA
- 20. "e ked NA
- 21. RCP Seal Inlet: l .
NA' ~!
- 22. Core Flood Tank _ Sample- NA
- 23. I RCP_ Standpipe'0emin Water Supply. NA-24 Containment H Dilution; Inlet.l {
NA'
- 25. Containment H ;0ilution Outlet NA 2 ,
- j. BWST Outlet Valves NA i
- k. Low Pressure Injection d i
- 1. . Decay Heat Pumps NA '
- 2. Low Pressure Injection Valves' NA
- 3. Decay Heat Pump Suction Valves - NA 1
- 4. Decay Heat Cooler' Outlet Valves NA -'
- 5. Decay Heat Cooler-Bypass Valves NA. i
- 1. Containment Spray Pump NA
. % 4
- m. Component Cooling Isolation' Valves 3 1
- 1. Inlet to Containment NA' 2.. Outlet from Containment _ NA
- 3. Inlet to CROM's NA-4 CROM Booster Pump Suction . NA-
- 5. Component. Cooling from~0ecay Heat .
Coolers NA- '
- n. Steam and Feedwater Isolation Valves
- 1. Main Steam Line '
.NA.
DAVIS'- BESSE, UNIT 1 -;
4 3/4 3 _ - _ _ _=___- _ _ _ .
~
1 RRMA"'ONLON.Y: ,
_ TABLE 3.3 (Continued)' 1 SAFETY FEATURES SYSTEM RESPONSE TIMES. ' -
INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS:
n.
' Steam and Feedwater Isolation Valves (continued)--
- 2. Main Feedwater Stop NA 4
- 3. MainStegmWarmup NA
- 2. -Containment' Pressure - High
- a. Fans
- 1. Emergency Vent Fans' . < 25*~
- 2. ' Containment Cooler Fans 7 45*
.b. HV & AC Isolation Valves -
- 1. ECCS Room
<.75*
- 2. Emergency Ventilation 3.
~ 75*-
Containment Air Sample 7'30*
I 4.
' Containment Purge 7 15*
- 5. Penetration-Room Purge
{75*-
c.
Control Room HV a. AC Units '
_< 10*
- d. High Pressure Injection
- 1. High Pressure Injection Pumps 2.
<.30*-
l High Pressure Injection Valves i30*
- e. Component Cooling Water
- 1. Component Cooling Water Pumps <L180*-
- 2. Component Cooling Aux. Equip. Inlet Valves 3.
7 180*
Component Cooling to -Air Compressor Valves
_7 180*
- f. Service Water System
- l. Service Water Pumps 2.
-< 45*
Service Water From Component Cooling Heat Exchanger Isolation Valves
._< NA*
- g. Containment Spray Isolation Valves < 80*
- h. Emergency Diesel Generator
_<:15*
DAVIS-BESSE, UNIT 1 3/4 3-16, 1
1 x ,
4+7 q
g m -- N
' TABLE 3.3 5 "(Continued)z Y
SAFETY FEATURES' SYSTEM RESPONSE tit 1ES j i
. INITIATING SIGNAlcAHO FUNCTION 1 RESPONS'E TIME'I'N SEC0HOS o
- 2. Containment Pressure - High.(Continued) ..,
, , :l
- i. Containment Isolation Valves .
R
- 1. Vacuum Relief - < 30*
- 2. . Normal Sump .
17'25*
- 3. RCS Letdown Delay Coil Outlet- i30*
- 4. RCS Letdown .High Temperature .1 30*-
- 5. . Pressurizer. Sample ' 1 48*'
- 6. Service Water.to Cooling Water
< 45* '
- 7. . Vent Header- 7 15* S -
! 8. Orain Tank 7 15*
l 9. Core F1ood; Tank" Vent- 71S*
- 10. Core Flood %r.k Fill . -
7 15*
- 11. Steam Generator Sample. 7 15* 1
- 12. Atmospheric Vent 7 17* '
- 13. Quench Tank' ^
17 15*
- 14. Emergency Sump - NA*- r
- 15. RCP Seal Return < 45*
, 16. - Air System 17 15* !
l
- 17. Np System- 7 15* l
' 18. Quench Tank' Sample E 35*4
, 19. Main Steam. Warmup Drain '7 15* --
l 20. " des 30* .[
- 21. .RCP' Seal Inlet 7 17*
l 22. Core Flood Tank Sample. 7 15*- '
L 23. RCP Standpipe Demin Water Supply. -1 15*
l
- 24. Containment H Dllution Inlet < 75*'
- 25. Containment H ( ilution Outlet ' E75*' ..
- j. BWST Outlet Valves NAt-
- k. Low Pressure Injection
- 1. < 30*-
Decay Heat Pumps
- 2. Low. Pressure Injection Valves .7 NA*
- 3. Decay Heat Pump Suction Valves 7 NA 4 Decay Heat Cooler Outlet Valves 7 NA*'
- 5. Decay. Heat Cooler Bypass Valves -[- NA*
1
- 3. Containment Pressure--High-High
- a. Containment Spray-Pump -1 80*
- b. Component Cooling Isolation Valves L 1. Inlet to Containment < 25*
- 2. Outlet from Containment 7
_ 25* i DAVIS-BESSE, UNIT'l 3/4 3-17.
. _ - _ _ _==
c
~ ^ '
TO,RMA"0NLON _Yi ,
s TABLE 3.3-5 :(Continued): _g ,
~
MFETYFEATURESSYSTEM'RESPONSETIMES-INITIATING' SIGNAL AND FUNCTION, . RESPONSE TIME IN SECONOS
~
4 b.; ComponentCooling.!solationValves(Continued)'
i
~3. ' Inlet to CROM's _.
h< ~35*
- 4. CROM Booster Pump'Suetion- .-
7 35 *.
- 5. Component Cooling from Decay Heat Cooler.: a
_7 NA*. t
- c. Steam and Feedwater Isolati^on Valves 4
1.. Main Steam'Line. < 10*
l 2.
3.
Main Feedwater Stop f30*'
Main Steam Wannup; il 15*
o
- 4. RCS Pressure-Low
- a. Fans , e-
- 1. . Emergency Vent Fans < 25*-
- 2. Containment Cooler Fans 7 45*- ^
- b. - HV & AC Isolation Valves ._t
- 1. ECCS Room .
< 75*
- 2. Emergency Ventilation- ~ 75*-
- 3. Containment Air Sample L7 30*
- 4. Containment Purge < 715'
.$: Penetration Room; Purge i75*-
- c. Control' Room HV & AC UniI!s- _< 10*'
- d. High Pressure Injection
- 1. High Pressure Injection Pumps
< 30*-
- 2. High Pressure Injection Valves
_7 30* '
- e. Component Cooling Water
- 1. Component Cooling Water Pumps < 180*
- 2. Congonent Cooling Aux. Equipment Inlet Valves .
< 180*
- 3. Component Cooling to Air Compressor Valves 7
_ 180*
- f. Service Water Syst2m -
1
- 1. Service Water Paips - .< 45* '
~
- 2. Service Water from Component Cooling He'at-I.- . Exchanger Isolation Yalves: < NA* -
- g. - Containment Spray Isolation Yalves :1 80* . 4 j h.: Emergency Diesel Generator 1 15*
j
~
DAVIS-BESSE,' UNIT 1 3/4 3-18 .
-i
n 4
TTSLE 3.3-5 (C_cntinued) 4 (t.fETY FEt.TURES SsTD4 Sts,'C:5C TIMES
~ INIT!?.T! 3 Sibt.L AND FURCTION ,
- RESPONSE T!!'E IN SECC:405
- 4. NCS Pressurc-Lou. (continued) i
- 1. Containm:nt Isolation. Valves
- 1. Vacuum Relief < 30*
- 2. Normal Sump .
7 25*
- 3. CCS Letdown. Delay Coil Cutlet 7 30* '
- 4. RCS Letdown High Temperature 7 30' ,
!- 5 .- Pnssurizer Sample -7 45C
- 6. Service Water to Cooling 1!ater 7 45*
l
- 7. Vent Header 7 15*
- 8. ' Drain Tank 7 15'
- 9. Core Flood Tank Vent "
7.15 * -
f 10. Core Flood Tank Fill 7 15*
i 11. . Steam Generator Sample- 7 15' l 12. Atmospheric Vent 7 17' l 13. -Quench Tank 7 15' j 14. Emergency Sump NA*-
l 15. Air Systems -1 15* '
- 16. N2 System 1 15' 17 Quench Tank Sample 1 3 S*
i
- 18. Main Steam Warmup'Orain ' 1 15' -
- 19. Core Flood Tank Sample - 1: 15* .
2C. RCP Standpipe Demin Water Supply 1 15' 21 . Containment Ho Oilution' Inlet 1 75* !
- 22. Containment H' Dilution Outlet 1 75
- j. BWST Outlet Yalves- NA*
- 5. RCS Pressure--Low-Low
- a. Low Pressure Injection l
- 1 1. Decay Heat Pumps < 30*
l 2'. Low Pressure Injection Valves 7 NA*
l 3. Decay Heat Pump Suction ~. Valves 7 NA'
- 4. Decay Heat Cooler Outlet Yalves 7 NA*'
- 5. Decay Heat Cooler Bypass Valves {NA*
- b. Component Cooling Isolation Valves
- 1. Auxiliary Equipment In'it < 90*
- 2. Inlet to Air Compresso.1 7 90*-
- 3. Compenent Cooiing from Decay Heat Cooler {NA*"
- c. Containment Isolation Valves I- RCP Seal Retd n ;< 45*
~
1 tidm . i OO' 'l
- 3. RCP Seal Inlet i l7*
A ,,
o
,,jn ,n o . ,. , _ _ _ _ _ _ _ _ _ _ _
N!0RMK"0N ON.Y:
TA8t.E 3.3-5 (Continued)-
SAFETY FEATURES SYSTEM RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS
- 6. Containment Radiation ' High
- a. Emergency Yent Fans < 25*
- b. HV..& AC isolation Valves
- 1. ECCS Room
< 75*
- 2. Emergency Ventilation 7 75*
- 3. Containment Air Sample 7 30*
4 Containment Purge ~ 715*
- 5. Penetration Room Purge ~ 75"
- c. Control Room HV &' AC Units' '
< 10*
1 TABLE NOTATION ,
Diesel generator starting and--sequence loading delays included when applicable. Response time limit includes movement of valves and attainment of pump or blower discharge pressure.
1 1
DAVIS-BESSE,. UNIT 1 3/4 3-20
~
l Aine'ndment No. 40f
,. ;+,
, , g i 4' ) /'$ <
~~.I
( t w'
.. \
j'
.s
)Q( n:
b
. . , Y s
CONTAINMENT SYSTEMS .
_'~
3/4.6.3oCONTAINMENTL ISOLATION VALVES '
W ,
V o3 LIMITING CONDITION-FOR OPERATION 3.6.3.1- The containment isolat' ion valves specified in Tab 1h 3 6-l2l shall be OPERABLE with isolation times as; shown ini ' Table 3.6-2.
APPLICABILITY M00ES;.1,.2, 3:and 4'.
ACTION: '
With one or more of the; isolation; valve (s) specified in' Table 3.6-2;,
inoperable, .either:
n
- a. Restore.the inoperable valve (s) to OPERABLE. status withinl4:
hours or'.
- b. Isolate each affected. penetration within 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />sLby. useHof ._
at least one deactivated automatic' valve secured inithe; isolation position, or ' '
- c. Isolate- each affe:ted > penetration withink hours iby:us' of at -
least one closed manual' valve or'. blind flange ~; ;or-d.
~ Be .in at least HOT STANDBY within' the next 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />sl and-in COLD SHUTDOWN within the;fo110 wing!30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />'s.
-i SURVEILLANCE REQUIREMENTS 4.6.3.1.1 The' isolation valves specified in: Table 3.'6-2; sha11_ be; demonstrated OPERABLE prior to returning the ~valveito service after maintenance, repair or replacement work is performed on:the1 valve-or its ' associated actuator, control or' power circuit by ' performance!
y of a cycling test and verification .of. isolation time. ,
+
l L .
1 a y.
l t,.
DAVIS-BESSE, UNIT:,1. 3/4 6-14 U q ,
EU____m_._m___
E
__._i.__I_i_m____'_._i.__________.-_______m.___ _ _ _ _ _ . _ _ _ _ ___ __ .__._.._-___m-__ -
A _ _ . _ . _ l._.__
y RRMA"!0N ON_Y d
' CONTAINMENT SYSTEMS ,
\
SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.1.2 Each isolation valve specified in Table '3.6-2 :shall be demonstrated.0PERABLE during the COLD SHUT 00WR or REFUELIN3 MODE at-least'once per 18 months by: :
j
- a. Verifying that on a containment _ isolation test signal', each -
automatic' isolation valve actuates to its . isolation.' position. ] s
- b. Verifying ;that on a -Containment Purge and: Exhaust isolation-test signal, each Purge and Exhaust automatic .' valve actuates y to its isolation position. ,
. a 1
i q
l .;
1
'l 8
3 DAVIS-BESSE, UNIT 1- 3/4 6-15 l '
L !
l l ,
~c
~
t ON'0N!Y .
.i l
y
- TABLE-3.6-2 . ly CONTAINMENT ISOLATION VALVES' .
PENETRATION VALVE f ISOLATION NUMBER i HUMBER FUNCTION- TIME 4 (seconds) i A. CONTAINMENT ISOLATION 1 RC240A Pressurizer Sample.Li.ne.
]
30 1 i
1 RC2408 Pressurizer Sample Line 30-2 # .55607 Steam Generator Secondary Water Sample.
Line 10; q
3 CC1411A Component Cooling Water Inlet LineJ 15 'l 3 CC1411B Component Cooling Water Inlet Line u
~ 15 4 CC1407A Component Cooling Water Outlet.Line 15 4 CC14078 Component Cooling Water Outlet Line 15 8A CV5070 Containment Vessel V' acuum Breaker 15.
88 CV5071
' Containment Vessel' Vacuum Breaker 15 8C CV5072 Containment Vessel Vacuum Breaker 15~ l 80 CV5073 Containment Vessel Vacuum Breaker , 15 SE CV5074 Containment Vessel Vacuum Breaker '15 8F CV5075 Containment Vessel Vacuum Breaker 15 :
8G CV5076 Containment Vessel Vacuum Breaker; 15 BH CV5077 Containment' Vessel Vacuum Breaker 15 BI CV5078 Containment Vessel Vacuum Breaker 15 8J CV5079 Containment Vessel Vacuum Breaker 15 i 12 CC1567A Control Rod Drive Cooling Supply Line 15.
12 CC1567B Control Rod 9 rive Cooling Supply.
Line -15 13 DR2012A Containment Vessel Normal Sump Drain 15 13 DR2012B Containment Vessel Normal Sump Drain 15 14 MU3 RCS Letdown Line 10:
14 MU2A RCS Letdown Line 15-DAVIS-BESSE, UNIT.1 3/4 6-16
l TABLE 3.6 .
'CONTAINMENDSOLATIONVALYES(Continued)-
PENETRATION VALVE ISOLATION:
NUMBER NUMBER -FUNCTTON' TTME (seconasT: ,
-16 RC1719A Containment Vesse1IVent Header-' 10 I 16 RC1719B Containment Vessel Vent Header 10 !
18 i S3598 -
Steam Generator Secondary Water)
Sample Line - 4 L
% "C . .,. -l C " ' ;e '.k.;
10 19 i HP2A - High Pressure Injection Line. 15:'
20'i HP2B - .High Pressure lidestion L'ine - 15 21 DW6831A Demineralized Water Supply Line J10 21- DW68318 Demineralized Water Supply Line - L10 H 22 i HP2D High Pressure Injection Line: 15.
25 CS1531 Containment Spray Line .,
26 CS1530 Containment Spray Line -
35 30 i . DHSA Containment Sump Emergency ~Recire' 71 Line l
31 i DR98 Containment Suq Emergency Recirc1 J Line- 71 32 MC1773A RCS Drain to RC Drain Tank - 10 a 32 RC17738 RCS Drain to RC. Drain Tank 10 l 37 i FW601.' Main Feedwater Line '15 l 38 i FW612- Main Feedwater Line - 15
" 39 i M5100 Main ' Steam Line - 5 l **39 i ICS11A . Main Staam Line 10 ;
39 i MS375 Main Steam Line 10 39 ,i M5100-1 Main Staas Line .10 t
i l-
) ~40 i ICS11B Main Steam Line 10 40 i MS394 Main Steam Line ,
- 10 40 i M5101-1. Main Steam Line 10:
DAVI5-BESSE, UNIT 1 3/4 6-17 AmendmentNo./,72- i
'w f
.n
-t y .,
- i n
NORMCON(ONLY TABLE 3.5-2' CONTAINMENT ISOLATION VALVES- (Continued)
NUMBER NUM3ER ,FUNCTTON- ' ISOLATION-TIME ~ - '.
itseconcs).
]
41' RC232 Press'urizer Quench Taiik> Circulating- '
Inlet Line '
10 :
42A SA2010 ' Service Mr Supply. Line : 10. n 428 CV5010! Containment Yessel Air-Sample Return 15 , l 43A .IA2011 Instrument Air Supply Line 10 4 38 - CY5011E ~ Containment Yessel Air Sample Return 15. 6 44A CF1541' i Core Flood TankJill and N2 Supply '
Line !
,10-448 NH236 Pressurizer Quench Tank ~N2 Supply Line 10 '
'47A CY1545 Core Flood Tank Sample Line 10-4 78 CY1542 Core Flood Tank Vent Line? 10 '
48 RC229A ' Pressurizer Quench Tank Circulating. '
Outlet Line
. 10 3
48 RC2298 Pressurizer Quench Tank Circulating 10 Outlet Line~
50 f HP2C High Pressure Injection Line 15 51 CV5037 ~ Hydrogen Purge System Exhaust Line 60 51 CV5038 Hydrogen Purge ~ System. Exhaust Line I 60 52 MU66A Reactor Coolant Pump Seal Supply" 12 53 MU668
! Reactor Coolant Pump Seal. Supply ; 121 54 MU66C Reactor Coolant Pump Seal Supply 12 55 MU66D Reactor Coolant Pump Seal Supply . 12 56 MU38 Reactor Coolant Pump Seal Return ~12 .;
56 MU59A Reactor Coolant Pump' Seal Return. 30 56 MU598 . Reactor Coolant Pump Seal Return '30 56 MU59C Reactor _ Coolant Pump Seal Return 30' 56- MU590 Reactor Coolant Pump Seal Return 30.
57 FG603 Steam Generator Blowdown Line 80 ;
60 M5611 Steam Generator Clowdown Line 80 DAVIS-8 ESSE, UNIT I 3/4 6 Amendment No. 79 i l I
_.____________________.m____ _ _ _ . _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ - _ _ _ _ _ . _ _ -._.m
m , .
m x i
~
x . .
+_ .
- n ; 3,; .n c , . .
l
. . i ,
j J0RMA70N{0N.Y
, ; TABLE 3.6f2 ,
,H
.CO'NTAINMENTilSOLATION VALVES:-(Continued) .
i ,
y 7 j
PENETRATION VALVE - - . flSOLATION:
NUMBER !FUNCT10N1
' NUMBER 0 <
TIME (seconds) - H 1
e67 CV5090. 4 Hydrogen DilutidntSystem Supply; :60L
~
68A- SS235A' Pressurizer Quench Tank Sample! L30)
'68AL 155235B Pressurizer Quench Tank Sample- L301 688- CV50108. Containment A1r Sample'
-688: CV5'011B' : . Containment AirjSample. :15 -
i 69 . CV5065'. l Hydrogen. Di1utio'n System Supply : 60 '
. g 71B' CV5010A = Containment Air Sample -
15' l
71 B' CV5011 A* Containment -Air Sample- 15 , !
71C. CV1544: Core Floo'd ' Tank:-N2 Fill :10 V 738 CV5010C: .ContEinmentf Air Sampis' : 15, l
73B CV5011C ' Containment Air Sample: 15 j 74B .CV50100 ' Containment' Air Sample . '15 74B CV501101 Containment l Air- Sample ,15 -
L B.- CONTAINMENT PURGE AND EXHAUST! ISOLATION-33 ## CV5005 Containment Vessel Purge Inlet Line .10 33#/.'CV5006 Containment Vessel Purge Inlet Line' 10,
~
l 34 ## CV5007 Containment Vessel; Purge .0utlet. Line- 11 0 l 34 ## CVS008 Containment Vessel' Purge Outlet Line 10 d l C. OTHER 5 #: SW1366 Containment Air Cooling' Units SW, Inlet Line 'N/A 6 # SW1368 Containment Air Cooling Units SW: '
. Inlet Line- N/A.
7 #. SW1367 . Containment Air Cooling Units SW -
Inlet Line. LN/AL ,.
9 # SW1356- Containment Air Cooling. Units SW ,
Outlet .Line N/A.
'l
- f. <
OAVIS-BESSE, UNIT 1 ; 3/4 6-19 _ Amen'dnunt n. N ek w
, , 4 .
l
1 TABLE 3. 6-2 . '
CONTAINMENT: ISOLATION VALVES (Continued).
PENETRATION VALVE .
HUMBER NUMBER FUNCTION -ISOLATION ' <
- TIFI
-It (seconos)
. Mt4 4411. Noenl RCS /4dtkp_ Line.
10 .# SW1358 N/A '
l ' Containment Air Co'oling Units SW -
Inlet Line- N/A.
11 'i '5W1357 Containment Air Cooling Units SW .
Outlet Line' 17 N/A-CY343 Containment Yessel Leak Test Inlet Linec 17 Flange 'Co'ntainment;Yessel Leak Test ln' let'.
~
---> Line (Inside Containment) N/A 19 i HPS/ Nigh Pressure Infaction Line'-
4 -N/A 20 i HPS6 . High Pressure ~ Injection Line N/A j
2? f HP49 High Pressure Injection Line N/A 2 ange Fu 1 Tr a ube -
24.f 572- Fuel Transfer Tube 24 N/A.
Fiange Fus' Transfer Tube
~N/A
-N/A 25 SAS32' Containment Spray Line
SA535 Containment Spray Line 26 N/A-SA533 Containment Spray Line
.N/A 27 i DHIA Low Pressure. Injection Line .
N/A 27 f DH76 Low Pressure Injection Line N/A
"'i DH1B Low Pressure Injection Line .
N/A 28 i DH77 Low Pressure trigection Line N/A DAVIS-BESSE, UNIT 1 3/4 6-2'O Amendment No. 3' ' .
1
_________.__m-____ ..__.__m.,m_ _s_ _ . _ _ _ . _ . _ . _ - _ _ _ -. . , - _ . _ . , _ . - _ _ . _ _ . _ . ~ _ . _
s' a > ;
i
- m u la.5'2 IFORMA~0Nf0N.Y1 /
o-n CONTAINMENT.150LAT10N[ VALVES (ConUinued) *
' e 'i 1 # ~
PENETRATION YALYE! '
ISOLATIONL NUMBER NUMBER FUNCTIONi _
TIME R 11
IDecayf Hea,t; Pump. Suction Line: 'N/A'
- 29 .DN23: Decay Neat Pump Suction.LineL '
N/A-29 i.- PSV4849: ' Decay. Heat Pump. Suction Line - 2
'It/A :
35 # AF599. ' Au' x iliary Feedwater Line. ,;N/Al ,
36:# .AF608 Auxiliary Feedwater-Line .N/A
+39 i' MS107 LMainSteamLine~' N/I : ]
+39 i'.M5107A .Hain Steam Line N/A u i'
)
- 41. RC113- Pressurizer. Quench Tank Inlet Line . N/A.
42A SA502- Service Air Supply LineL J/A'
' 428 CY124 Containment Vessel Air Sample ..
Return 'N/A 43A .IA501 Service Air SupplyLLine N/Af 438 CY125 Containment Yessel. Air Sample. . .
Return s ,
'N/A-44A CF15 Core n ood Tank Filliand Nitrogen, Supply.Line "
N/A1 44S NNS8 Pressurizer Quench Tank. Inlet.-
Line N/A'
'47A CF2A
' Core n ood Tank-Samole Line: .N/A-
'47A CF2B Core n ood Tank Sample Line N/A
- 478 CFSA . Core Flood Tank Vent' Line' 'N/A-
'47B CF5B Core n ood Tan'k Vent Line. .N/A -
49 DH87 Refueling Canal Fill Line N/A-49 DH88 Refueling Canal Fill'I.ine- N/A DAVIS-BESSE. UNIT 1 3/4.6-21' knendment' No. 3 4
T e
s wp -
i
- _ - -_- O
TABLE 3.6-2.
CONTAINMENT? ISOLATION VALVES l(Continued)-
~~
s
- : PENETRATION VALVE . .
NUMBER ' ISOLATION
' NUMBER -FUNCTION TIME?
-fo tw64i RCS Makee Line.
49 M/A
~DH87 -Refueling' Canal Fill' Line. ' ti/A
'49 DH88- Refueling Canal Fill Lines N/A, ,
Jf HP48 High Pressure Injection. N/A 52 MU242 . RCP Seal Water Supply' N/A 53 MU243 RCP ~ Seal Water Supply-
'N/A 54 MU244 RCP Seal Water Supply N/A 55 MU245 RCP Sea' Water Supply' 1
N/A Deleted Deleted Deleted Deleted 59 Flange Secend' ary Side Cleaning (Inside Containment)
N/A 59 Flange Secondary Side Cleaning- (Outside-Contairrnent)
-N/A 67 CV209 Hydrogen Dilution System Supply - 'N/A' 69 CY210 Hydrogen Dilution System Supply. N/A 71A f CV20005 Containment Pressure Sensor' N/A' l 71C CF16 Core Flood Tank Nitrogen Fill Line: -t '!
h/A
_l 72A f CV20018 Containment Pressure Sensor N/A 72C f CV6248 Containment Pressuro Differential-Transinitter '
N/A 73A f CV20028 Containment Pressure, Sensor N/A-73C f CY6458 l Containment Pressure Differential Transmitter ,
N/A' iia i CV2003B Containmen't Pressure Sensor N/A
'74C DH2735 Pressurizer Auxiliary Spray N/A
'74C DH2736 Pressurizer Auxiliary Spray N/A
'May be opened on an intermittent basis under administrative control. '
- Not subject to Type C. leakage tests.
- Surveillance testing not reguired prior to entering. MODE 4 but d shall be performed prior to entering. Mode 3. -
ffProvisions of Specification .3.0.4' are not applicable provided the .
valve is in'the closed positions and'. deactivated. .
DAVIS-BESSE, UNIT 1 3/4 6-22
~ Amendment No; Z J)',79 d
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