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MONTHYEARML20096C6821984-08-27027 August 1984 Proposed Tech Specs Reflecting Changes in Reactor Vessel Matls Irradiation Surveillance Schedule & Flow Verification of Auxiliary Feedwater Sys Project stage: Other ML20096C6631984-08-27027 August 1984 Application for Amend to License NPF-3,revising Tech Specs to Reflect Changes in Reactor Vessel Matls Irradiation Surveillance Schedule & Flow Verification of Auxiliary Feedwater Sys.Fee Paid Project stage: Request ML20096C6401984-08-27027 August 1984 Forwards Application to Amend License NPF-3,revising Tech Specs to Reflect Changes in Reactor Vessel Matls Irradiation Surveillance Schedule & Flow Verification of Auxiliary Feedwater Sys Project stage: Request ML20133D7961985-08-0101 August 1985 Responds to Re NUREG-0737,Item II.E.1.1 Concerning Auxiliary Feedwater Sys Tech Specs & Request to Review SER & Submit Revised Amend Application.Revised Application Will Be Submitted by 850830 Project stage: Other ML20138C9801985-08-29029 August 1985 Proposed Tech Spec Changes,Identifying Water Source for Auxiliary Feedwater Pumps,Safety Grade Flow Indication Used for Flow Verification & Bases Project stage: Other ML20138C9731985-08-29029 August 1985 Application for Amend to License NPF-3,identifying Water Source for Auxiliary Feedwater Pumps,Safety Grade Flow Indication for Flow Verification & Bases Project stage: Request ML20138C9651985-08-29029 August 1985 Forwards Application for Amend to License NPF-3,revising Tech Specs Re Water Source for Auxiliary Feedwater Pumps, Safety Grade Flow Indication for Flow Verification & Bases Project stage: Request 1985-08-01
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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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} PLMT SYSTim BASES 3/4.7.1.7 AUX 1LI ARY FEEEEATER SYSTEMS The OPERAEILITY of the auxiliary feed.eter systems ensures that the Reactor Coolant System can be cooled down to less than 280*F frw.
nonnal operating conditions in the event of a total loss of offsite power. . .
Each steam driven auxiliary feedwater purp is capable of de[1vering a total feedwater flow of 803 spm at a pressure of 1050 psig to the -
entrance of the steam generators. This capacity is sufficient to ensure that ade:;uate feedi.ater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 2ED'T where the Decay Heat Removal Systa: may be placed into operation.
Folleu, ira en3 medihcotion s ,v irepaivr to k au xiliars (<e cl -
wate,r rp tem pipinS 4 b m % e concj,ns af e sterage <ank %roug h
- auxiGarg inct peps le -th e .stf am g e n t rede r.r 64 ceuld affect
! M 535hm'.5 ca pa bilMS te delWer water t. S sttorn generarcr$
fencWns a tended ecfd shut dec>n, a flew path verificatim test shi) be perfermed.
W i Etsi mg be conducted in rnodes A,5 or g using auxiliary steam to drive h av lay n 3 feed f amfs tubine t, demonstrate +ha+ % Clw Panu Mts 6em %e condensate stevoge tank to Oe. shom Sencrator.5 Vin aux iliard feed p w ps.
3 /4.7.1.3 CONDENSATE STORAGE FACILITIES .
The OPERAEILITY of the condensate storage tank with the en64e-mininen meter volume ensures that sufficient meter is available .to maintain the RCS at HOT STANDEY conditions for 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> with steam discharge to atresphere and to cooldown the Reactor Coolant System to less then.280'F in the event of a total loss of offsite power or of the main feedwater system. The contained water volume limit includes an allowance for
, water not usable because of tank discharge line location or other s -
physical characteristics.
, 3 /4.7.1.4 ACTIVIE The limitations on secondary system specific activity ensure that the resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 timits in the event of a steam line rupture. This dose includes the effects of a coincident 1.0 GPM primary to secondary -
tube leak .in the steam generator of the affected steam line. These values are consistent with the assur:ptions used in.the safety analyses.
3/4.7.1.5 MAIN STEM LINE ISOLATION VALVES .
The OPERABILITY of t,he tain steam line isolatiori'va'1ves ensures -
that'no more than one steam generator will blowdown in the event of a steam line rupture. Thu restriction is required to 1). minisize the (DAVI5-BESSE. UNIT 1 8 3/4 7-2 Amendment No. 58 8510230122 050029 PDR ADOCK 05000346
_ _ .P ,__ _ _ _ _
PDR. __ _ __ __ _ _ _ __
s PLANT SYSTEMS AUXILLARY FEE 0 WATER SYSTEM LIMITING CONDITION FOR OPERATION ,
3.7.1.2 Two independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE.
APPLICABILITY: MODES 1. 2 and 37 ACTION:
- a. With one auxiliary feedwater system inoperable, restore the inoperable system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.1.2 Each auxiliary feedwater system shall be demonstrated OPERABLE: .
- a. At least once per 31 days on a STAGGERED TEST BASIS by:
- 1. Verifying that each steam turbine driven pump develops a differential pressure of > 1070 psid on recirculation flow when the secondary steam supply pressure is greater than 800 psia, as measured on PI SP 12B for pump 1-1 and PI SP 12A for pump 1-2.
2.
Verifying)that automatic in the each valve flow path(=th:t nual,h power operated not 10thed. ::: or led Or Othe m he ::c r ed ' pe:it h .. is in its correct gosition. ' d '* '
'I " "
ANo ciscuAas[LwEs
- b. At least onceNi?8r'rIt'sIrfe'kvE per 18 months by: s"cM$ETYNMtUll*we"rE'T. 8N TN'8Nr's*TsE*I N"8 "*YIka P8 8 'T8 '
- l. Verifying that each automatic valve in the flow path actuates to its correct position on an auxiliary feed-water actuation test signal prior ta entering rnode 3
- 2. Verifying that each pump starts automatically upon .
receiot of an auxiliary feedwater actuation test signal frievh enItn"3 made i.
- 3. VERIF1flNs TH AT THERE IT A FLOW PATM SETwitN EACM AUrf t. lamy FKEDWATER PUMP ANO f acM l iTE AM GENE R AT0 A SY PUMPlN6 W ATER P ROM THE CoseD5MATF 818A44G TAsak TD TNL ST8 AM 6thstAT0g THE FLDW PATH TO THE STE AM 6sNER Atom SWALL st VERIPIEDest EffMER TTE AM sgusagfot '
LEVEL CHANGE OR AUKILI ARY FEEDWATE R KArfry coaAas roow Was4AT8eC WERIFIC.ATION OF THE AuslLIARY F8f DWATE A NWsTEM'A FLoint c APACITY 15 NOT AE9pf Rt0.
tr er b entering made3
- Provision *f schon 3..a 6 not oppmoWe ,
vvis -8F356. umT i 1
I
3 s
t
I SUWEILLANCE REQUIREMENTS (Continued)
- c. The Auxiliary Feed Pump Turb'ine Steam Generator Level Control ,
Syst8m shall be demonstrated OPERABLE by perforTc.ance of a CMANNEL CHECK at least cnce per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CHANNEL FUNCTIONAL TEST at least once per 31 days, and a CHANNEL CALIBRATION at least once per la months. . .
- d. The Auxiliary Feed P6r.p Suction pressure Interlocks , and Auxiliary Feed Purrp Turbine Inlet Steam Pressure Interlocks sr.all be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days, and a CHAHhEL CALIBRATION at least once per 18 sionths.
4
- 8. AFTER ANY MDDIFIC ATscN OR REPAIR To T*ir AUKILI ARy FEEDWATER SyJTE M TH AT C OUL D AFFECT THE S yJTE M'$ C APA8 8kfTJ Te DELIV ER WATER To THE STEAM GENERATom , TME AFFECTED Flow PATH ENALL SC DEMONETR ATED AVAIL AB LE As FeLLONS
cenDtys h
- I. IF TNE MGDtCIL ATIDN OR R EPAtR ff DowHSTAL AM OF ITkE TEST FLOW #
i l
LINE , THE ApriLI A R y FEED PUMP $H ALL PUMP WATER Tc THE STE AM T GENERATeR ; AND T4E F1,op PATW AVAILABILITY WILL SE VEplFAED SW l
i STEAM GENER ATAR LEVEL C HANGE DA AUXILEARY FEEDWATER SAFETf GRAtf F'LeW INDic AfterJ.
- 2. lF TNE McDiflCATlDN OR EEPAIR 15 UPJTREAM OF TNE TEET FLOW LlHE p Tut AustLIARW FEED PUMP JNALL PUMP WATER TmRoueN THE AUxlLIARY TEEDWATER SyJTEM To THE TE ST TLOW LlHE } A ND THE FLOW P.%TM AVAIL ASILIT.y .WlLL BE VERIFIED By FLOW IWDICATlaM IN TWE TEST Thew 4
uME,(ssE Norf sELow)
, THif sustvfiLLNcf TEff#dr Dw L Bf PERFostMEP 8%#8t 7b fcE**d e
' WATER 515 TEM'5 Fs ow cePAclTV is tiet Af aut AED.
< f. FALLOWlWE EACH EXTENDED COLD KWUTDOWN (> 20 DAyJ IN Most 5),3 y
- l. VE AIFJ1Ws TM AT THERE IS A FLOW PATW BETWEEN E ACM AustLIARW FEED-W ATE R PUMP AMD E ACH STE AM GEMEA ATD A s y PUMPsNS c eH DEt4 5 ATE" S roe AGE TAwk W ATER To THE E T8 A M 'a sus.R 4reR. T ng.ra o w PATM TO THE ETE AM ER NER ATo R JNALL BE VEREFlED a v EITHER ETE AM GE NER ATeR LEVE L C HANE E 01 AUXILIARY FEEDWATE R. SAFETr GRA0E Flow INDicAvson, VE RIFlC ATION OF THE AUKILEA R V F(EDWATE R s yJTEM's FLOW CAPACITF la NOT A ESulR ED, NOTE ' WNE W CONDuCTINr. TR ETA OF TME AUKILI ARY FE E DWATER S YS TEM IN MODEEIga,AND3 WHICH R E $UIR E LOC AL M A NU AL R E A Ll6MNIENT ,
OT VALVES TH AT M Ak.' THE syJTEM INDPER ABLE , A DEDIC ATED IN DIV ID U A L $ MALL BE 5 6 ATsoHED AT THE VALVE 5 (IN COMMUNICATION I WITH THE C.ONTRDL RODM) ARLd TO R E STORE THE F A LVE S TO NORM AL K y3 TE M O P E R A E L E L TAT US .
Amendment No. 41, 63 DAVIS-8E55E, UNIT 1 3/4 7-5 I
' s
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