Letter Sequence Other |
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MONTHYEARML20076F3931983-08-18018 August 1983 Proposed Tech Specs Supporting Amend to License NPF-3 Re Leak Rate Requirement for Containment Purge & Exhaust Isolation Valves Project stage: Other ML20076F3601983-08-18018 August 1983 Application for Amend to License NPF-3 to Include Special Leakage Test Requirement for Containment Purge & Exhaust Isolation Valves.Safety Evaluation & Significant Hazards Consideration Encl Project stage: Request ML20076F3381983-08-18018 August 1983 Forwards Application for Amend to License NPF-3 to Include Special Leak Rate Requirement for Containment Purge & Exhaust Isolation Valves Project stage: Request ML20099L1511984-11-20020 November 1984 Proposed Tech Spec Changes,Revising Sections 3.6.1.2 & 4.6.1.2 Re Containment Leakage Rates Limiting Condition for Operation & Surveillance Requirements,Respectively Project stage: Other ML20099L1341984-11-20020 November 1984 Application for Amend to License NPF-3,revising Tech Spec Sections 3.6.1.2 & 4.6.1.2 Re Containment Leakage Rates Limiting Condition for Operation & Surveillance Requirements,Respectively Project stage: Request ML20099L1271984-11-20020 November 1984 Forwards Application for Amend to License NPF-3,revising Tech Spec Sections 3.6.1.2 & 4.6.1.2,in Response to NRC 821203 Request for Leak Testing to Detect Excessive Resilient Seal Deterioration.Fee Paid Project stage: Request 1983-08-18
[Table View] |
Proposed Tech Spec Changes,Revising Sections 3.6.1.2 & 4.6.1.2 Re Containment Leakage Rates Limiting Condition for Operation & Surveillance Requirements,RespectivelyML20099L151 |
Person / Time |
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Site: |
Davis Besse |
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Issue date: |
11/20/1984 |
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From: |
TOLEDO EDISON CO. |
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To: |
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Shared Package |
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ML20099L130 |
List: |
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References |
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TAC-52417, TAC-56794, NUDOCS 8412010024 |
Download: ML20099L151 (4) |
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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
. .
f n CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 4
3.6.1.2 Containment leakage rates shall be limited to:
- a. An overall integrated leakage rate of 5 L 0.50 percent by
- weightofthecontainmentairper24 houri,atP,,38psig.
4
- b. A combined leakage rate of 3 0.60 L for all penetrations and valvessubjecttoTypeBandCtestI,whenpressurizedtoP,.
- c. A combined leakage rate of 5 0.015 L for all penetrations identified in Table 3.6-1 as seconda*ry containment bypass leakage paths, when pressurized to P,.
- d. A single penetration leakage rate of 5 0.15 L for the containment purge and exhaust isolation valve.special tesf.
APPLICABILITY: MODES 1, 23 3 and 4.
ACTION:
4 a. With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L* (b) with the measured combined leakage rate for all penetrattons and valves subject to Type B and C tests leakage rate exceeding exceeding 0.015 0.60 L,L, or (c) with restore thethe combined leakage rate bypass (r) to within the limit (s) prior to iEc,reasing the Reactor Coolan' System temperature above 200*F.
- b. With a single containment purge and exhaust isolation valve penetration having leakage rate exceeding 0.15 L ; restore the leakage rate to within limits in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be In at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. i i
SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the !
l following test schedule and shall be determined in conformance with the criteria specifie( in Appendix J of 10 CFR 50 using the methods and I i
provisions of ANSI) N45.4 - 1972:
I'
- a. Three Type A tests (0verall Integrated Containment Leakage Rate) shall be conducted at 40 + 10 month intervals during shutdown at P , 38 psig, during each 10 year service period. The third test ofeachsetshallbeconductedduringtheshutdownforthe10 year plant inservice inspection. j i -
8412010024 841120 PDR ADOCK 05000346 p PDR_.
l CONTAINMENT STSTDfS
't SURVEILIANCE REQUIREMENTS (Continued)
- b. If any periodic Type A test fails to meet .75 L , the test schedule for subsequent Type A tests shall be r$ viewed and approved by the Commission. If two consecutive Type A tests fail to meet .75 L , a Type A test shall be performed at least every18monthsunfiltwoconsecutiveTypeAtestsmeet.75L*
at which time the above test schedule may be resumed.
- c. The accuracy of each Type A test shall be verified by a supplemental test which:
- 1. Confirms the accuracy of the Type A test by verifying that
- the difference between supplemental and Type A test data is within 0.25 L,.
- 2. Has a duration sufficient to establish accurately the change in leakage between the Type A test and the supplemental test.
- 3. Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage rate at P,, 38 psig.
- d. Type B and C tests shall be conducted with gas at P , 38 psig, at intervals no greater than 24 months except for testI involving:
- 1. Air locks,
- 2. Penetrations using continuous leakage monitoring systems, and
- 3. Valves pressurized with fluid from a seal system.
- e. The combined bypass leakage rate shall be determined to be
< 0.015 L, by applicable Type B and C tests at least once every l
24 months except for penetrations which are not individually testable; penetrations not individually testable shall be 1 determined to have no detectable leakage when tested with soap )
bubbles while the containment is pressurized to P,, 38 psig, during each Type A test.
l
- f. Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
,,---------n - , , , , , , - - - , - , - - - , - - - - - . _ - - - - - , , -
---,-,e . ~ , _ -c--,-
~
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 3 Leakage from isolation valves that are sealed with fluid from e seal system may be excluded, subject to the provisions of Appendix J,Section III.C.3, when determining the combined leakage rate provided the seal system and valves are pressurized to at least 1.10 P , 41.8 psig, and the seal system capacity is adequate to maintain Iystem pressure for at least 30 days.
I h. Type B tests for penetrations employing a cont'inuous leakage monitoring system shall be conducted at P,, 38 psig, at intervals no greater than once per 3 years.
- i. Each time the containment purge and exhaust isolation valves are opened, a special test shall be performed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after valve closure or prior to entering mode 4 from mode 5, whichever is later. The special test is conducted by pressurizing the piping section including one valve inside and one valve outside the con-tainment to a pressure greater or equal to 20 paig. The leakage rate per penetration shall not exceed 0.15 L,.
- j. The special test as defined in Surveillance Requirement 4.6.1.2.i shall be performed for the containment purge and isolation valves when the plant has been in any combination of modes 3, 4, 5 or 6 for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided that the tests required by Sur-veillance Requirements 4.6.1.2.1 or 4.6.1.2.d have not been performed in the previous 6 months.
- k. All test leakage rates shall be calculated using observed data converted to absolute values. Error analyses shall be performed to select a balanced integrated leakage measurement system.
- 1. The provisions of Specification 4.0.2. are not applicable.
i i
l i
. - ,-- , , , - . , , . , , , , , - - , . + - , , , --
,m- -- , , ,, ,, ,, , -- ,,._- , - , , -
- 3/4.6 CONTAINMENT SYSTEMS l
BASES l
l 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAIMENT INTEGRITY j Primary CONTAINNT INTEGRITY ensures that the release of radioactive '
materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses.
This restriction, in conjunction with the leakage rate Ifmitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.
3/4.6.1.2 CONTAINMENT LEAKAGE The limitations'on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure of 38 psig. P . As an '
added conservatism, the measured overall integrated leakage, rate is further limited to < 0.75 L .dduring performance of the periodic tests to account for possible deg,radation of the containment leakage barriers between leakage tests.
The surveillance testing for messering leakage rates are consistent with the requirements of Appendix]" of 10 CFR 50.
3/4.6.1.3 CONTAI N NT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restriotions on CONTAINNT INTEGRITY and containment leak rate. Surveillance testine of the air lock seals provide assurance that the overall air lock leakage will not become excessive due to seal damage during~the intervals between air lock leakage tests. ,
t Mt spccal kesh [or +I1e CCHbIneMed furje omd gl Q f i is.fstran mtu<s is c,+<,,bd 4o hfect y.ss dagsts, op Sal 5 en 4ka Wive seats. Tlve Spec.(d. lest .A pedr4 ik a.dA h 4o +1u.
, Appodrx J reyc<. unh.
-g l D&VIS-BESS'E. UNIT 1 8 3/4 6-1
.- . _ _ _ _ _