Proposed Tech Specs Re Containment Air Lock Door Operability Requirements for Containment IntegrityML20113G818 |
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: |
05/01/1992 |
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From: |
CENTERIOR ENERGY |
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To: |
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Shared Package |
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ML20113G815 |
List: |
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References |
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NUDOCS 9205120260 |
Download: ML20113G818 (7) |
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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
. _ - - _ .
Docket Number 50-T'e6 License Nunber NPF-3 .
. Serial Number 1971 ,
Attachment Page 9
'OtttN! TION 5 i
REPORTABLE EVENT I 1 1.7 A REPORTABLE EVENT snal) be any of those conditions specified in Sect 1or '
50.73 of 1C CFR Part 50.
CONTAINMENT INTEGRITY _
1.8 CONTAllgENT INTEGRITY shall exist wnent
- a. All penetrations required to be closed during accident conditions are :
eithert
- 1. Capable of being closed by the Safety Features Actuation Systas.
or
- 2. Closed by manual valves blind flanges or deactivated automatie valves secured in their closed positions. L. cept tnose approved to be open unser assinistrative controls.
- b. All equipmen a_tches are cl_osed and__ sealed t_
aka w;6. % n.gu, M iefso Q_
- c. p. - ;mg^. t:) specification 3.6.1.3.
Each airlock ino+N'l ,
- d. The containment leakage rates are within the lini'n of 5pecification 3.5.1.2. and ,
- e. The sealing mechanism associated with each penet.*ation (e.g., welds, bellows or 0-rings) is OPERABLE.
CHANNEL CALIBRATION 1.9 A CHAluEL CALISRATION shall be the adjustment. As necessary, of the channel output such that it responds with necessary range and accuracy to kasun values of tne parameter wnich the channe) monitors. - The CHAlstEL CAL 18 TAT 10R thall encompass the entire channel including the sensor and alars and/or trip -
functtons, and shall include the CHAlfEL F151CTIORAL TEIT. CHAlelEL CAL 18AAT!0N may se performed by any series of sessential, omriapping or total channel steps suca tast the entire channel is calibrated.
CHANNEL CHECK 1.10 A CHAlpin. CHECK shall be the qualitative assessment of channe) behavior during operation by observation. This determination shall include, unere possible, comparison of the channel indication and/or status with other im:stions and/or status derived from independent in?trument channels measuring tr.'
. Same parameter.
9205120260 920501
_{DR ADOCK 05000346 DAVI5 BEEEE. Un[i% 1-2 Amenenent No. 93.135.147
Docket Nunber 50-346
'icen'se
- Number NPT-3 serial Number 1971
)
Attachment Page 10 .
2/4.6 **!!TAINMENT SYSTE*5 3/a.6.1 :ttMaRY CONTAINMENT CONTAINMENT INTEGRITY j I
- l LIMIT!!G CONDITION FOR OPERATION 1,
'!3.6.1.1 Primary CONTAINMENT INTEGRITY sna11 be maintained.
! APPt.!CABILITY: MODES 1. 2. 3 and 4 il '
ACTION:
Nithout crimary CONTAINMENT INTEGRITY. restore CONTAINMENT IMEGRITY within one nour 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 /> ano in COLD SHUTDOWN within tne 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 1 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
I j a. At least once per 31 days by verifying that:
4
- 1. All penetrations
- not capable of being closed by OPERABLE containment automatic isolation valves and reoutree to be I closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in
' their positions, except those valves that may be opened under assinistrative controls per Specification 3.6.3.1, and
- 2. All equipment hatches are closed and sealed.
_ _ ~ - ._-_ -n _ n -_ .
. p- , :y .;cifyir.; e.:: = . x:
- t. nix:: :f r S:t it er:rin: '
__ - ._ sr
__ _. _. 7
';::if S:ti::
=
3.5. ?. 3.
v MnV S e.Q A 3 0nfUf^Q fonkeinout
'Except valves, blindl langes,4deactlvated automatic valves which
, are located inside th ::Sta.and are locked. sealed. or otherwise l
secured in the closed pos ion. These penetrations shall be verified closed during each CDLD-5HUTDOWN except that verification of these penetrations being closed need not be performed more often than once per 92 days. ,
l.
l Amenament No. t47 L__ ;DAV!$-BESSE. UNIT 1--
- --3/4 6 . _ _- - - - . _ - - _ - - --
1 Docket Number 50-346 Licenas Number NPF-3 5hrial Number 1971 Attachment Page 11 CONTAINMENT SYSTEMS
, CONTAINMENT LEAXAGE D ON1 ON3 l
4 LlHITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
- a. An overall integrated leakage rate of 1 L weight of the containment air per 24 shour , O'.50 at P,, percent by 38 psig.
- b. A combined leakage rate of 1 0.60 La , for all penetrations and valves subject to Type B and C tests, when pressurized to P a*
- c. A combinM leakage rate of 1 0.03 L for all penetrations that are secondary containment bypals leakage paths, when pressurized to P,.
~
- d. A single penetration leakage rate of 1 0.15 La for the contain-f ment purge and exhaust isolacion valve special test.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTIOJ:
- a. With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L, (b) with the measured combined leakage rate for all penetrations and valves subjact to Type 8 and C tests exceeding 0.60 La, or (c) with the combined byp&ss leakage rate exceeding 0.03 La, restore the leakage rate (s) to j within the limit (s) prior to increasing the Reactor Coolant 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 l
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 l following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REOUIREMENTS
(
i 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be detennined in confonnance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4 - 1972:
I a. Three Type A tests (Overall Integrated Contairnent Leakage Rate) l shall be conducted at 40 4 10 month intervals during shutdown at P , 38 psig, during each To year service period.
3
._RMM3E. EM5L5L . . _ . . __ 3/ 4._6- 2 Amend %n% N9eE_)lJk160 _
l Docket Number 50-346 License Number NPF-3 Serial Number 1971 l Attachment ]
.Page '12 '
1:
' CONTAINMENT SYSTEMS g SURVEILLANEE REOUIREMENTS (Continued)
Il
- b. If aay periodic Type A test fails to meet 0.75 L the test schedule for subsequent Type A tests shall be reviewed an$, approved by the Cornission. If two consecutive Type A tests fail to meet 0.75 L Type A test shall be perfomed at least every 18 months until tw$, a consecutive Type A tests meet 0.75 L, 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. Confims the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 L3.
l 2. Has a duration sufficient to establish accurately the change in f' leakage between the Type A test and the supplemental test.
- 3. Requires that the rate at which gas is injected into the contair. ment or bled from the containment-during the supplemental test is ot: ween 0.75 L, and 1.25 L,.
- d. Type B and C tests shall be conducted with gas at P 38 psig, as intervalsnogreaterthan24monthsexceptfortest$ involving air locks.
, e. The combined bypass leakage rate shall be determined to be < 0.03 L a
1' by applicable Type B and C tests at least once every 24 months except for penetrations which are not individually testable; penetrations not individually testable shall be determined to have no detectable leakage when tested with soap bubbles while the contain-ment is pressurized to Pa , 38 psig, during each Type A test, w
' - h:kE :h:b be-4e+ted ind &enstrated OPEP1SLE per surUeh4M' -
%cuire ent t.S.:.3. ( pe,le,{ @
~~-
j(
% ___%~ v DAVIS-BESSE. UNIT 1 3/4 6-3 Amendment No. PD.J20,160
Docket Number 50-346
. License Number NPT-3 '
Serial Number 1971 Attac,hment Page 13 i
- NMA"0N ON Y -
CONTAINMENT SYSTEMS I SURVE1LI ANCE REQUIREMENTS (Continued)
I
- g. Each time the containment purse and exhaust isolation valves are l 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 /> af ter valve closure or prior to entering MODE 4 from MODE 5. whichever j
is later. The special test is conducted by pressurizing the piping section including one valve inside and one valve outside the containment to a pressure greater or equal to 20 psig. The leakage l
rate per penetration shall not exceed 0.15 L,.
- h. The special . test as defined in Surveillance Requirement 4.6.1.2.g <
shall be performed for the contairnent purge and isolation valves j 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 test requiredLby Surveil- .
lance Requirement 4.6.1.2.g has not been perfornied in the previous 6 months.
- i. All test leakage rates shall be calculated using observed data l converted to absolute values. Error analyses shall be performed to select a balanced integrated leakage measurement system. ,
J. The provisions of Specification 4.0.2 are not applicable.
I m i e
,.' DAVIS-BESSE. UNIT 1 1 ., , 3/16_4. _
- Amendment N@._ & 1160. _ _. _ _ __ __
~
1 Docket dumber 50-346 1.icense Number NPF-3 Serial Number 1971 Attachment.
re a N.ORMA p&0(s_Y TABLE 3.6-1 DELETED l
l DAVIS-BESSL UNIT 1 3/4 6-5 Amencnent No.160
Docket Number 50 346 Liccaos Numb 3r NPF-3 54 rial Number 1971 i Attaennent Page 15 i
l::NTAINMENTSYSTEMS ,
CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with:
8 i
- a. Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and
- b. An overall air lock leakage rate of ,< 0.002 L, at P,, 38 psig.
L APPLICABILITY: MODES 1, 2, 3 and 4. ;
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- iT COLO SHUTOOWN withir, tM f0110xing 30 h0 erb
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"RVE!LLANCE REQUIREMENTS
.5.1.3 -Each containmenLair lock shall be gmontt,~ rated OPERABLE:-
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k *Mttfhach opening e::::t Mr th: 21" !::h i bei- ~;;d .*: r QTultip!: :_ntrR:. tyt 1-Qtm; r ?? Mer+,(by 7e'FTTying either no dbfiitit$51e seal leakage when t*e voluire1etween the
- door seals is pressurized to 10 psig, or oy verifying a seal leakage rate of < 0.0015 L seals is pressurTred to P , when the volume between the door holddowns-are installed, ,,-38 psig, and the air lock door
- b. MjAt least once per 6 nonths by conducting an overall air. lock f D 1 -
leakage test at P 38 psig, and by verifying that the overall Vl L
-air lock leakage fa,te is within its limit, and
- c. At least once per 6 months hv verifying that only one door in
. eAch air lock can be ope'v6 i
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Docket Nueber 50-346 License Number MPF-3 Serial Number 1971 Attachment
. Page 16 Nov 3.6.1.3 Action
- a. Vith one air lock door inoperable in one or more containment air locks, or with the containment air lock interlock mechanism inoperable in one or more containment air locks:
- 1. Verify an OPERABLE door in each affected air lock is closed within one hour, and
- 2. Lock an OPERABLE door-closed in each affected air lock vithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and
- 3. Operation may then continue provided that an OPERABLE door in each affected air lock is maintained closed and is verified to be locked closed at least once per 31 days, and provided that the containment air lock passes each scheduled perforniance of SR 4.6.1.3b.
- 4. Otherwise, be in 110T STANDBY vithin the next 6 hoors and in COLD S!!UTDOVN vithin the folloving 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- b. Vith one or more c.-tainment air lotks inoperabic for reasons other than above:
- 1. Verify at least one door in each affected air lo:k is closed within one hour, and
- 2. Restore air lock (s) to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
- 3. U nervin.e, be in ll0T STANDBY vithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in i COLD SHUTDOVN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
I
Docktt Number 50-346 License Number SPF-3
@ rial Number 1971 A t t ac nmeqt. '
Face.17
[ 3/4.6 (,P]iAINMENT SYSTEMS l
BASES 3/4.6.1 PDIMRY CONTAINMENT .
3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive i 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 limitationTwill 3 limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions. / a
& lock door ee-
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3/4.6.1.2 CONTAINMEN1 LEAXAGE l The. limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the valt assumed in the safety analyses at the peak accident pressure of 38 psig, Pa . As an added conservatism, the measured overall integrated leakage rate is furtner limited to 1 0.75 La, during perfon.1ance of the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.
The surveillance testing for measuring leakage rates are consistent with the requirements of 10 CFR Part 50, Appenoix J with the following 2xemption. The third test of each Type A testing set need not be conducted wnen tne piant is shutcown for the 10-year plant inservice inspections.
The operational readiness of the vessel is considerec proven by the ILRT, ano in accordance with license requirements, wnen completed per the 40 t 10 months frequency.
The special test for the containment purge and exhaust isolation valves is intenced to detect gross degradation of seals on the valve seats. The special test is perfomed in addition to the Appendix J reouirements.
USAR 6.2.4 identifies all penetrations that are secondary containment bypass leakage paths.
3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the contairnent air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate. Surveillance testing 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.
IAVIS-BESSE, UNIT 1 B 3/4 6-1 Amendment No. H.H6,160