Proposed Tech Specs 3/4.3.2 Re Removal of Decay Heat Isolation Valve & Pressurizer Heater Interlock Requirements in Modes 4 & 5ML20077E517 |
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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: |
06/04/1991 |
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From: |
CENTERIOR ENERGY |
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To: |
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Shared Package |
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ML20077E505 |
List: |
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References |
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NUDOCS 9106100433 |
Download: ML20077E517 (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 50-346 License Number NPF-3
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Page 6 of 1 1111SPAGE PROVIDED INSTRUPENTATION 3/a.3.2 ! AFETY SysitM INSTRUMENTATION SAF(TY F(ATUR(5 ACTUATION SYSTEM INSTRUMENTATION t!M1 TING CON 01T10N FOR OPERATION 3.3.2.1 The Safety Features Actuation Systen (SFAS) functional units shown in T:ble 3.3 3 thall be OPERABt.E with their trip setpoints set consistent with the values shown in the Trio Setpoint column of Table 3.3 4 ano with RESPONSE TIMES as shown in Table 3.3 5.
A p pi. !!iB ! t I TY : As shown in Table 3.3 3..
Aci!ON:
- a. Witn a SFA5 functional unit trip setpoint less conservative than the value shown in the Allowab'e Yalues column of Table 3.3 4. declare the functional unit inoperable and apply the applicable ACTION recuirement of Table 3.3-3. untti the func-tional unit is restored to OPERABLE status with the trip setcoint acjustec consistent with the Trip 5etpoint value.
- b. With a SFAS functional unit inoperable. take the action shown in Ta ble 3.3-3.
SURvtitLANet REOUIREwtNTS 4.3.2.1.1 Each 5FAS functional unit shall be demnstrated OPEP>BLE by tne performance of the CFANNEL CHECK. CHANNEL CAllBRATION and CHANNEL FUtiCTIONAL TEST during the MODES and at the frecuencies shewn in Table 4.3 2.
a.3.2.1.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCT10rtAL TEST of functional units affected by bypass operation. The total bypass function shall be demonstrated CPERABLE at least once per 18 months during CHANNEL CAtlBRATION testing of each functional unit affected by bypass operation.
4.3.2.1.3 The SAFETT FEATURES RESPONSE TIME of each 5FA3 function shall be demnstrated to be within the limit at least once per 18 months.
Each test shall include at least one functional unit per function such that all functional units are tested at least once every N times 18 months where N is the total number of redundant functional units in a specific $FAS function as shown in the " Total No. of Units
DAVIS-BESSE. UNIT 1 3/4 3-9
- Okuxom r n 001 f u w rxA /,
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sp b TABLE 3.3-3 (Continued) ezo en ESO k b$
N SAFETT FEATliRES ACT11ATIOf3 STSTEM_ IflSTRtlHENTATION E
- HINIHUM TOTAL NO. UNITS UNITS APPLICABf.E OF UNITS TO TRIP OPERABIE MODES ACT IOf 3 l d) FUNCTIONAL UNIT _
J. HANUAL ACTUATION l
- a. SFAS (except Containment
! Spray and Emer;;;ency Susp 2 2 2 1,2,3,4,6**** 12 l l Recirculation) 2 2 2 1,2,3,4 12 l
- b. Containment Spray T* 4. SEQUENCE LOGIC C11ANNELS Y Sequencer 4 2*** 3 1,2,3,4 10# l g a.
- b. Essential Bus Feeder l Breaker Trip (90Z) 2 1 2***** I,2,3,4 151 l k c. Diesel Generator Start,
$ Load Shed on Essential I,2,3,4 13I l 2 1 2 E Bus (59Z)
- 5. INTERLDCK CEANNEl_S O
j, s. Decay ticat Isolation Valve ! I I 1.2,3 M 137 l 2 2 2 aj!y. g#f r er 14$ j
- b. rressurizer sea ers d
v3 g.
C' L
3:
- - . . . - . - - - _ . - - . . . . . _ - . ~ _ . - - ..- .-. . - - - ~ . - -
Docket Number 50-346 '
License Numbet tJPF-3 Serial !Jumher 1918 !
Attachment >
Page 8 of 12 TABLE 3.3-3 (Continued)
TABLE NOTATION
(
l
- Trip function may be bypassed in this MODE vith RCS press.t. belov 1800 psig. Bypass shall be automatically removed when RCS pressure i exceeds 1800 psig.
- Trip function may be bypassed in this MODE vith RCS pressure belov 600 psig. Bypass shall be automatically removed when RCS pressure exceeds 600 psig.
- One must be in STAS Channels el or 83, the other must be in Channels 82 or #4
- This instrumentation must be OPERABLE during CORE ALTERATIONS or l movement of irradiated fuel vithin the containment to meet the requirements 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 Vater Pump.
r r r e e .t LObw elt/.er OMJHeat Ebe4t/0A OIve' n of'ehe The provisions of specification 3.0.4 are not applicable.
ACTION STATEMENTS ACTION 10 - Vith the number of OPERABLE functional units one less than the g Total Number of Units, STARTUP and/or POVER OPERATION may l \
proceed provided both of the following conditions are satisfied:
- a. The inoperable functional unit is placed in the tripped condition within one hour. For functional unit 4a the sequencer channel shall be placed in the tripped condition by physical removal of the sequencer module.
- b. The Minimum Units OPERABLE requirement is met however, one additional f unctional unit any 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 Specification 4.3.2.1.1.
ACTION 11 - Vith any componant in the Output Logic inoperable, trip the I associated components within one hour or be in at least BUT STANOSY 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 COLD SHUTDOVN vithin the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
ACTION 12 - Vith the number of OPERABLE Units one less than the Total Number I of Units, restore the inoperable functional unit to OPERABl2 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 BOT STANDBT 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 COLD SEUTDOVN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
ACTION 13 - a. Vith less than the Minicus Units OPERABLE and reactor l coolant pressure > 438 psig, both Decay Beat Isolation Valves (DH11 and 0812) shall be verified closed.
DAVIS-BESSE. UNIT 1 3/4 3-12 Amendment No. 28, 37.
- 22. 207. 135 ac
Docket Number 50-346
' License Number Ni'F-3 HMh h hlhh I HU W lph Serial Number 1918 m:t:rm FORINFORMAT.ON ONLY TABLE 3.3-3 (Continued)
ACTION STATEMENTS
- b. Vith Less than the Minimus Units OPERABLE and reactor coolant pressure < 438 psig operation may continues however, the functional unit shall be OPERABLE prior to increasing reactor coolant pressure above 438 psig.
ACTION 14 - Vith less than the Minimun Units OPERABLE and reactor coolant i pressure < 438 psig, operation may continues however, the functional 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.
ACTICN 15 - Vith the numDer of OPERABLE functional units one less than the !
Total Numoer of Units operation may proceed provided both of the follovi.sg conditions are satisfiedi
- a. The inoperable section of a functional unit is placed in the tripped condition within one hour.
- b. The Minimum Units OPERABLE requiraeant is mets however, the inoperable section of a 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 Specification 4.3.2.1.1.
DAVIS-BESSE. UNIT 1 3/4 3-12a Amenoment No. 28. 52. ,144,135
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352 y TABl.E 4.3-2 (con inued) -
g y -, . i m SAFETY FEATifRES ACTilATION SYSTEH Irl5TRIIMI!frATinti stravEII.t_Af4CE REQllIREMEtiTS
- *7Uw cn
.t'1 c
y CilAHHEL CilANNEL H0 DES IN U111C11
- e CilANNEL FIDICTIONAL FIRK~TIONAL l#4IT CHECK SIIRVEILLANCE o CALIBRATION TEST RE0llIRED
- 5. INTERIDCK CHANNELS
- a. Decay Beat Isolation Valve S R **
- b. Pressurfrer Beater S R **
1, 2. J M 3Qg ad M
e.
- See Specification 4.5.2.d.1 n
TABLE NOTATION g
g (1) Hanual actuation switchen shall be tested at least once per 18 months dur ing sleut down. At! other r
a circuitry least once associated with manual saf eguards actuation shall receive a CI8 ANNE!. FtJNCTIONAL TEST at per 31 days. I (2) The Cll ANNEL FUNCTIONAL TEST ahnll include exercising the transmit ter by applying cither vacuum or
?
i.
pressure to the appropriate side of the transmitter.
o i The surveillance requirements of Section 4.9.4 apply during core alterations or movement fut? within the cnntainment. of Irtadiated
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-t ed/ser Dcoty Mg Ischtien valve ,, cyc,,,
i ca (11
Docket thimber 50 346 Lidnse f;omber fiPF- 3
( Serial thonber 1918
=n THIS PAGE Pf!0EDED
- REACTOR COOLANT STS*EM S AFETT VALVES - SEUT'JOVN LIMITING CONDITION FOR OPERATION
'3.4.2 Decay Best Removal Systes relief valve 08-4849 shall be OPERABLE vith a l lift setting of 1330 psig* and isolation valves 08-11 and DB-12 open and
!' control pover to their valve operators removed.
'!APPLICA3ILI*T: MODES 4 and 1.
I CIIONt
. ,1
- lA. Vith DB 4849 not OPERABLE
ll l 1. Make the valve OPERABLE vitbin eight hours or ll
,l :. a. Vithin next one hour, disable the capability of both high pressure injection (HPI) pumps to inject vater into the reactor coolant l systems and I
i
- b. Vithit .1ax t eight hours:
I
- 1. Disable the automatic transfer of makeup pump suction to the borated vater storage tari on lov makeup tank levels and l 2. Reduce makeup tank level to f 73 inches and reduce reactor
- coolant system pressure and pressurizer 1 vel within the j acceptable region on Figures 3.4-2a (in n0DE 4) and 3.4-2b (in MODE 5).
l B Vith DJ-11 or 08-12 closed, open DH-21 and D8-23 vithin one hour.
!'llC. .
I Vith the control power not removed from DE-.11 and DE-12, remove the power to the valve operators at the Motor Control Canters within one hour.
{ SURVIIL'E CE REQUIREMENTS 4.4.2 Decay Heat Removal System relief valve DB-4849 shall be determined OPERABLE:
- a. per the surveillance requireaants of Specification 4.0.5.
- b. at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying either:
- 1. isolation valves DB-11 and DH-12 open with control power removed from threir valve operators: or
- 2. valves DB-21 and 08-23 open i* The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
DAVIS-BESSE, UNIT 1 3/4 a-3 Amendment No. 37,J3f 135
Docket flumber 50-346 License Number NPF-3 L l Serial Number 1918 Attachment '
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4.3 'NSTRUMENTATION FOR WORK 3N DN
!ASES
- '4. 3.1 ano 3/4. 3. ?EAC" R FROTIO"'ON SYSTEM AND S ATI-* !!!*EM lMSTRUMENTATICH The OPERARII.!TT of the EPS. STAS anc STRCS instrumentation systems ensure that
- ) the associated action ana/or trip vill be initiateo vnen the parameter tonitorea by esca c.nannel or co'scination thereof exceecs its setpoint. :) the specified coincidence logic is maintained. 3) sufficient renunaancy is
?.aintained to permit a enannel to be out of service for testing or t.aln t anance , and 4) sufficient system functional capso111ty is available for RPS. STAS and STRCS purposes tres diverse parameters.
The OPERABILI T of these systems is reautrea to provice tne overall reliacility, renuncance ano diversity assuaea available in tne f acility design
, f or tne protection ans antigation of accident and transient concitions. The l integrated operation of eacn of these systems is consistent vith tne
, assumptions used in tne accident analyses.
i
- ! The surveillance requirements specified for these systems ensure that the i overall system functional capability is maintained comparacle to the original
,I. ' ' design standards. The periodic surveillance tests perforneo at the minimum f requencies are suf ficient to demonstrate this capability.
l The measurement of response time at the specified frecuencies orovides l assurance that the RPS. ITAS, and STRCS action function associated with each enannel is completed within the time limit assumed in the safety analyses. No
- recit vas taken in tne analyses for those channels vita resconse times
- ndicates as not applicaole.
Eesoonse time may oe oesonstrated by any series of secuential. overlapping or
, total channel test mes.surements provided that such tests comonstrate the total enannel response time as definee. Sensor response time verification any be cemonstrated by either 1) in place, onsite or of fsite test measurements or 2) i utilizing replacement sensors vith certified response ti es.
l An STRCS channel consists of 1) the sensing device (s). :) associated logic and
- output relays (including Isolation of Main Feeovater Hon Essential Valves and Turbine Trip), and 3) power sources.
The STRCS response time for the tureine stop valve closure as caseo on the
,l conoined response times of =ain steam line low pressure sensors. logic cabinet
.j delay for main steam line low pressure signals and closure t1:e of the turbine
'{ stop valves. This STRCS response time ensuresthat the auxiliar/ f eeovater to ,
,; the unaf f ected steam generator vill not be isolateo due to a STRCS lov
- ! pressure trip during a atn steam line breax accident.
CAVIS-BESSE. 1: NIT 1 S 3i4 3-1 e.senoment No. 73.125
( %s t eage is B 3/4 3-la)
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