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MONTHYEARML20205R1831987-03-31031 March 1987 Proposed Tech Specs Correcting Error in Tech Spec Section 3/4.3.2, Safety Sys Instrumentation & Section 3.3.2.1, Table 3.3-3, Safety Features Actuation Sys Instrumentation Project stage: Other ML20205R1731987-03-31031 March 1987 Application for Amend to License NPF-3,correcting Error in Tech Spec Section 3/4.3.2, Safety Sys Instrumentation & Section 3.3.2.1,Table 3.3-3, Safety Features Actuation Sys Instrumentation. Fee Paid Project stage: Request ML20205R1591987-03-31031 March 1987 Forwards Application for Amend to License NPF-3.Amend Corrects Error in Section 3/4.3.2, Safety Sys Instrumentation & Spec 3.3.2.1,Table 3.3-3, Safety Feature Actuation Sys Instrumentation Project stage: Request ML20205R1341987-04-0101 April 1987 Confirms 870330 Verbal Granting of Temporary Waiver of Compliance to Change Min Number of Sequencer Channels Required to Be Operable from Four to Three,Per 870331 Application for Amend to License NPF-3 Project stage: Other 1987-03-31
[Table View] |
Proposed Tech Specs Correcting Error in Tech Spec Section 3/4.3.2, Safety Sys Instrumentation & Section 3.3.2.1, Table 3.3-3, Safety Features Actuation Sys InstrumentationML20205R183 |
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Site: |
Davis Besse |
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Issue date: |
03/31/1987 |
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From: |
TOLEDO EDISON CO. |
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Shared Package |
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ML20205R137 |
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References |
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TAC-65028, NUDOCS 8704060254 |
Download: ML20205R183 (2) |
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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
_ - .
u TABLE 3.3-3
?-
E -
T SAFETY FEATINtES ACTUATION SYSTEM INSTRtMENTATION
- g MINIPUt TOTAL NO. UNITS UNITS
.m FINETIONAL INIIT APPLICABLE Of UNITS TO TRIP OPERABLE MODES e ACTION 5
-4
- 3. MAIEAAL ACTUATION
- a. SFAS (except Containment spray and Emer 2 2 Recirculation)gency Sump 2 1,2,3,4,6**** 11
- 6. Centalament Spray 2 2 2 1, 2, 3, 4 11
- 4. SEQtENCE LOGIC CHANNELS g a. Sequencer 4 2***
a 1,2,3,4 9p g y b. Essential Cus Feeder 2 Breaker Trip (905) 1 2***** 1,2,3,4 14#
3
- c. Diesel Generator Start, 2 k 1,2,3,4 1 2 14#
Load Shed on Essential Bus (59%)
& S. IllTEllLOC,K CHAlllELS
, f A. Decay lleat Isolation Valve 1 1 1 1,2,3,4,5 12#
- b. Pressurizer fleaters 2 ~2 2 3,4,5
- h. .
13#
ee l
I 8704060254 870981 i
PDR ADOCK 05000346 p PDR 4 .
1
,No. 1369 TASM 3.3-3 (Continued)
TAOLE hGIAij0ii Trip function nay be bypassed in this MODE with RCS pressure below l 1800 psig. Bypass shall be automatically removed when RCS pressure exceeds 1800 psig, !
i Trip function may be bypassed in this MODE with ECS pressure below 600 psig. Bypass shall be automatically removed when RCS pressure exceeds 600 psig.
l One
- 2 ormust
- 4. be in SFAS Channels #1 or #3. the other must be in Channels This instrumentation must be OPERABLE during core alterations or move-ment of Irradiated fuel within the containment to meet the require-ments of Tech. Spec 3.9.4.
All functional units may be bypassed for up to one minute when starting each Reactor Coolant Pump or Circulating Water Ptap.
The provisions of Specification 3.0.4 are not applicable.
_ ACTION STATEMENTS 9 '- With the nutter'of OPERA 8LE functional units one less than the Total 'tumber of Units, startup and/or power operation may proceed provided both of the following conditions are satisfied:
- a. The inope able functional unit is.placed in the tripped condition' within one hour. FbR Fvs>M14W. uNtT4c(
nas segutpesp.cHAWEi- s4Ata GE PLMED llJ THE TRIPPUD CWM b.
The Minimum Units CPERABLE retvirement is mett how- By papcM_ -
ever, one additional functional unit may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per RN#1- eF WE
$pecification 4.3.2.1.1. SEQutum1L Mo0ULE.
0 With any component in the Output Logic inoperable, trip the associated components witnin one hour or be in at least NOT STANDSY 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
$HUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. '
I
- l. With the number of OPERA 8LE Units one less than the Total Number of Units. restore the inoperable functions) unit to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least NOT STAN0BY within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and in COLD 5HUTDOWN with.
in the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
!. a. With less than the MininJa Units OPERA 8LE and reactor coolant pressure a 438 psi , both Decay Neet Isola.
tion Yalves (DN11~and DH12 shall be verified cleted.
- b. With Less than the Minimun Units OPERABLE and reactor coolant pressure < 438 psig operation may continue, i however. the functional unct shall'be OPEAABLE prior l
to increasine reactor coolant pressure above 438 psig. '
l With less than the Ainfaus Units OPERABLE and reactor coolant - '
pressues <438 psig, operation any continuet however, the func.
tional unit shall be OPERA 8LE prior to increasing reacter coolant pressure above 438 psig, or the incoerable functione) unit shall be placed in the tripped stata.
- 11. UNIT 1 s u .i, . _ _ . . . . . . ,~. ..
? l ~- i 4 Docket No. 50-346 April - 01, 1987-4 Mr. Donald C. Shelton < 4
, Vice President, Nuclear Toledo Edison Company
[ Edison Plaza - Stop 712 i -300 Madison Avenue - <
i' Toledo,.0hio 43652
Dear Mr. Shelton:
i
SUBJECT:
EMERGENCY TECHNICAL SPECIFICATION CHANGE - SAFETY FEATURES 7
ACTUATION SYSTEM INSTRUMENTATICN j Re: Da'vis-Besse Nuclear Power Station . .
- By letter dated March 31, 1987, you requested an emergency Technical
- Specification (TS) change which would modify _the number of Safety Features-Actuation System (SFAS) logic sequencer channels for Emergency Diesel -
Generator loading which is required to be operable. LThere-are four (4) such .
logic sequencer channels as indicated in TS Section 3.3.2.1. Table 3.3-3 and the existing TS requires all four channels tolbe operable. Your March 31,
. 1987 letter proposes- to change the minimum number of sequencer channels required to be operable from four (4) to three (3).,
- y. ,
We have reviewed your evaluation and justification provided in your March 31, 1987 submittal and find them acceptable. ,This letter confirms the verbal-i granting of a temporary waiver ~of compliance,=.as discussed with you on March 30, ,
1987, to change the minimum number'of sequencer channels required to be R
, operable from 4 to 3, as indicated in the enclosediTS.page. This-temporary.
waiver of compliance will be in effect until April 3,~1987,'while we complete' '
i the processing of your _ amendment request.
Sincerely, . .
i
- /S/-- _
l i John-F..'Stolz : Director; -
PWR Project Directorate #6
, Division 'of PWR Licensing-B _
i
. H
' Enciosures:
TS pages 3/4 3-11~
and 3/4 3-12.
cc w/ enclosures:
- See next page-Distribution
- Docket File NRC &'LPDRs Branch Files- RIngram
.ADeAgazio FMi raglia ~. OGC +
ACRS .EJordan
! JPartlow BGrime NThompson
, Asn PWR.
PWRf6/w-. '
RIngram ADeAgazioteh J l 4/)/87, Y// /87
, ,, t a, a ,
g
/ - -. -
5 /y'7 7 N # 8 I ~
Mr. Donald C. Sheltor. Cavis-Besse Nuclear Power Statior Tolede Edison Company Unit Co. 1 CC*
Donald H. Hauser, Eso.
The Cleveland Electric Radiological Health Prograr Illuminating Company Chio Departrent of Health P. O. Box 5000 !??4 Kinnear Road Cleveland, Ohio 44101 Columbus, Chic 43?l?
Mr. Robert F. Peters Attorney Ge.neral Manager, Fuclear Licensing Departnent of Attorney Toledo Edison Company General Edison Plaza 30 East Broad Street 300 Madison Avenue Columbus, Ohio 43?l5 Tcledo, Ohio d365?
Mr. James W. Harris, Director Gerald Charnoff, Esq. (Addressee Only)
Shaw, Pittman, Potts Division of Power . Generation and Trowbridge _ Ohio Department of Industrial Pelations 7300 N Street N.W. ?373 West 5th Avenue Washington, D.C. 20037 P. O. Rox 825 Columbus, Ohio 43?l6 Mr. Paul P. Smart, President Ohio Environmental Protection Toledc Edison Company Agency-300 Madison Avenue 561 East Broad Street Toledo, Ohio 43652 Columbus, Ohio 43?66-0558 Mr. Robert B. Borsum President, Board of Babcock & Wilcox County Commissioners of Nuclear Power Generation Ottawa County Division Port Clinton, Ohio 43452 Suite 200, 7010 Woodmont Avenue Bethesda, Maryland 20814 State of Ohio Public Utilities Commission Resident Inspector 180 East Broad Street U.S. Nuclear Regulatory Commission Columbus, Ohio 43766-0573 5503 N. State Route ?
Oak Harbor, Ohio 43449 Reoional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Poad Glen Ellyn, Illinois 60137
. q_
~
+
TABLE 3.3-3~
E ,
,5 SAFETY' FEATURES ACTUATION SYSTEM INSTRUMENTATION j
y M MINIMUM M TOTAL NO. UNITS UNITS APPLICABLE
!" FUNCTIONAL UNIT ,0F UNITS ,TO TRIP MODES ACTION OPERAllLE_-
c 5 3. MANUAL ACTUATION y .
- a. SFAS (except Containment i -
Spray and Emergency Sump 2 2 2 1,2,3,4,6**** 11 Recirculation) a
- b. Containment Spray 2 2- 2 1,2,3,4- 11
- 4. SEQUENCE LOGIC CHANNELS .
g a. Sequencer 4 2*** 3 1,2,3,4 l-9# I a.
y
- b. Essential Dus Feeder 2 1 2***** 1,2,3,4 14#
- Breaker Trip (90%) -
'p c. Diese".' Generator. Start, - 2 1 2 1,2,3,4 14f g Load 'ihed on Essential
- . Bus' (59%)
R 5. IllTERLOCK C11AllilELS y
. d. Decay lleat Isolation Valve l~ l 1 1,2,3,4,5 12# -
- b. Pressurizer lleaters 2 2 2 3,4,5 13#
c h
e
TABLE 3.3-3 (Continued)
TABLE NOTATION Trip function may be bypassed in this MODE with RCS pressure below 1800 psig. Bypass shall be automatically removed when RCS pressure exceeds 1800 psig.
i Trip function may be bypassed in this MODE with RCS pressure below 600 psig. Bypass shall be automatically removed when RCS pressure exceeds 600 psig.
One must be in SFAS Channels #1 or #3, the other must be in Channels
- 2 or #4.
This instrumentation must be OPERABLE during core alterations or move-ment of irradiated fuel within the containment to meet the require-
.ments of Tech. Spec 3.9.4.
- All functional units may be bypassed for up to one minute when starting each Reactor Coolant Pump cr Circulating Water Pump.
- Tiw provisions of Spec'ification 3.0.4 are not applicable.
ACTION STATEMENTS ACTION 9 - Ata the nutter of OPERABLE functional units one less than M Nel Number of Units, startup and/or power operation may nroceed provided both of the following conditions are satis fied: -
- a. The inoperable functional unit is.placed in the trippec condition within one hour. For functional Unit 4a, the sequencer channel shall be placed in the tripped condition by physical
> b. The Minicum Units OPERABLE requirement is met; how- removal of the ever, one additional functional unit may be bypassed sequencer module.
for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1.
ACTION 10 - With any component in the Output logic innperable, trip the associated components within one hour or be in at least HOT STANDSY 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 SHOTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
ACTION 11 - With the number of OPERABLE Units one less than the Total Number of Units, restore the inoperable functional unit to OPERACLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-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 with-in the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
ACTION 12 - a. With less than the Mimimum Units OPERABLE. and reactor coolant pressure > 438 psig, both Decay Heat Isola-tion Valves (OHil and DH12) shall be verified closed.
- b. With Less than the Minimum Units OPERABLE and reactor coolant pressure < 438 psig operation may continue; i' however, the functional unit shall' be OPERABLE prior to increasing reactor coolant pressure above 438 psig. .
l ACTION 13 - With less than the Minimum Units OPERABLE and reactor coolan. j pressure <438 psig, operation may continue; however, the func- i tional unit shall be OPERABLE prior to increasing reactor coolant pressure above 438 psig, or the inoperable functional unit
,- shall be placed in the tripped state. '
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