Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements for Containment Isolation ValvesML20245A294 |
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Davis Besse ![Cleveland Electric icon.png](/w/images/7/78/Cleveland_Electric_icon.png) |
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Issue date: |
06/13/1989 |
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From: |
TOLEDO EDISON CO. |
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To: |
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Shared Package |
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ML20245A227 |
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References |
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NUDOCS 8906210192 |
Download: ML20245A294 (5) |
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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
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- , . Docket Number:50-346' License Number NPF-3 Serial Number 1667 j Attachment I ~l FORINFORMAT10N ONLY CONTAINMENT SYSTEMS 1
3/4.6.3 CONTAINMENT ISOLATION VALVES l
LIMITING CONDITION FOR'0PERATION l
3.6.3.1 The containment isolation valves specified.in Table 3.6 ,
- i. shall be OPERABLE with isolation times as shown in Table 3.6-2. :
4 APPLICABILITY: MODES 1, 2, 3 and 4.~
ACTION:
With one or more of the isolation valve (s) specified in Table 3.6-2 inoperable, either: ;
L a. Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or
- b. Isolate each affected penetration'within.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of -
at least one deactivated automatic valve secured in the isolation.
position, or
- c. Isolate each affected penetration within 4-hours 'by use of at -
least one closed manual valve or blind flange; or
- d. 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 SURVEILLANCE REQUIREMENTS
- 4. 6. 3.1.1 The isolation valves specified in Table 3.'6-2 shall be I demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed ~ on the valve ;
or its associated actuator, control or power circuit by performance af a cycling test and verification of isolation time. .
DAVIS-BESSE, UNIT.1 3/4 6-14 8906210192 890613 PDR ADOCK 05000346 P FDC .,
- , Docket Number 50-346 License Number NPF-3 Serial Number 1667 y j t E2 p ' eat (jp Attachment 1 Page 6 gg jg gzigg ,g g h.{,gy CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.1.2 Each isolation valve specified in Table 3.6-2 shall be I demonstrated GTERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by: l
- a. Verifying that on a containment isolation test signal, each i automatic isolation valve actuates to its isolation position.
- b. Verifying that on a Containment Purge and Exhaust isolation <
test signal, each Purge and Exhaust automatic valve actuates I to its isolation position. l l
l
\
i i
DAVIS-BESSE, UNIT 1 3/4 6-15
. Docket Number 50-346
.
- License Number NPF-3 Serial Number 1667 Attachment 1 Page 7 TABLE 3.6-2 CONTAINMENT ISOLATION VALVES (Continued)
PENETRATION VALVE ISOLATION NUMBER NUMBER FUNCTION TIME (seconds)
- 29 DH11 Decay Heat Pump Suction Line N/A 3*-
- 2 DH23 Decay Heat Pump Suction Line N/A l l 29 # PSV4849 Decay Heat Pump Suction Line N/A ;
35 # AF599 Auxiliary Feedvater Line N/A i 36 # AF608 Auxiliary Feedvater Line N/A 37 # FV601 Main Feedvater Line N/A 38 # FV612 Main Feedvater Line N/A
- 40 # ICS11B Main Steam Line N/A 40 # MS394 Main Steam Line N/A 40 # MS101-1 Main Steam Line N/A 41 RC113 Pressurizer Quench Tank Inlet Line N/A 42A . SA502 Service Air Supply Line N/A 42B CV124 Containment Vessel Air Sample Return N/A 43A IA501 Service Air Supply Line N/A l 43B CV125 Containment Vessel Air Sample I Return N/A i 44A CF15 Core Flood Tank Fill and Nitrogen Supply Line N/A 44B NN58 Pressurizer Quench Tank Inlet Line N/A
- 47A CF2A Core Flood Tank Sample Line N/A l *47A CF2B Core Flood Tank Sample Line N/A i *47B CF5A Core Flood Tank Vent Line N/A l *47B CF5B Core Flood Tank Vent Line N/A l
j DAVIS-BESSE, UNIT 1 3/4 6-21 Amendment No. 3,114, 127
, Docket Number 50-346 i
."L'icense Number NPF-3 ,
Serial Number 1667 I
. aciment 1 ' TABLE 3.6-2 CONTAINMENT ISOLATION VALVES (dontinuec )
PENETRATION VALVE ISOLATION' NUMBER NUMBER FUNCTION TIME '
(seconds) J 49 DHB7 Refueling Canal Fill Line N/A 49 DH88 Refueling Canal Fill Line N/A 50 # HP48 High Pressure Injection Line N/A i 50 # HP2C High Pressure Injection Line N/A i 50 MU6421 RCS Makeup Line N/A 52 MU242 RCP Seal Vater Supply N/A }
53 HU243 RCP Seal Vater Supply N/A 54 MU244 RCP Seal Vater Supply N/A 55 MU245 RCP Seal Water Supply N/A 59 Flange Secondary Side Cleaning (Inside !
Containment) N/A- j 59 Flange- Secondary Side Cleaning (Outside i Containment) N/A l
57 # MS603 Steam Generator Blovdown Line N/A 60 # MS611 Steam Generator Blovdown Line N/A l ]
I 67 CV209 Hydrogen Dilution System Supply N/A !
69 CV210 Hydrogen Dilution System Supply N/A 71A # CV2000B Containment Fressure Sensor N/A I 71C CFl6 Core Flood Tank Nitrogen Fill Line N/A ,
72A # CV2001B Containment Pressure Sensor N/A 72C # CV624B Containment Pressure Differential Transmitter- N/A 73A # CV2002B Containment Pressure Sensor N/A 73C # CV645B Containment Pressure Differential Transmitter N/A 74A # CV2003B Containment Pressure Sensor N/A
- 74C DB2735 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 required prior to entering MODE 4 but shall be performed prior to entering Mode 3.
- Provisions 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. 3,31,79,112,114, 127-1
l
. Docket Number.50-346 License Number NPF-3 Serial Number 1667 Attachment 2 i Page 1 SIGNIFICANT HAZARDS CONSIDERATION Description of Proposed Technical Specification Change The purpose of this significant hazards consideration is to review a proposed change to the Davis-Besse Nuclear Power Station Technical Specification (TS).
3/4.6.3.1, containment Isolation Valves, Table 3.6-2. This request proposes to' apply an existing Table 3.6-2 footnote'to decay heat removal valve DH23 j vhich vill clarify that the valve is not subject to 10CFR50, Appendix A,. Type C testing. Valve DH23 is a normally locked closed, manually operated- .
j containment isolation valve, located inside the containment vessel in series j with valve DH21 (also normally closed) in the bypass line around valves DH11 and DH12, decay heat pump suction isolation valves. Type C testing of valve DH23 is not required since the valve does not meet the criteria which requires ',
Type C testing. The Technical Description (Attachment 1) discusses this change in detail.
Significant Hazards Consideration The Nuclear Regulatory Commission has provided standards in 10CFR50.92(c) for determining whether a significant hazard exists. A proposed amendment to an Operating License for a facility involves no significant hazards if operation of the facility in accordance with the proposed changes vould not: . 1) Involve a significant increase in the probability or consequences of an accident previously evaluated; 2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or 3) Involve a significant reduction in a margin of safety.
The proposed change does not involve a significant hazards consideration because the operation of the Davis-Besse Nuclear Power Station, Unit Number 1, in accordance with this change vould:
- 1. Not involve a significant increase in the probability or consequences of an accident previously evaluated because no operating requirement of valve DH23 is changed. As a containment integrity boundary, any potential leakage past valve DH23 vould be contained in the closed loop system.
[10CFR50.92(c)(1)]
1
- 2. Not create the possibility of a new or different kind of accident from any accident previously evaluated because no operating requirement of valve DH23 is changed. On matters related to nuclear safety, all accidents are bounded by previous analysis and no new malfunctions are involved.
[10CFR50.92(c)(2)]
- 3. Not involve a significant reduction in a 'argin of safety because the assumptions in the USAR remain unchanged .1d the containment integrity function of valve DH23 is not changed. [10CFR50.92(c)(3)]
Conclusion Based on the discussion above, it is concluded that the proposed change not involve a significant hazards consideration.
1 i
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