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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML17355A3921999-07-27027 July 1999 Proposed Tech Specs 3.8.1.1,3.4.3 & 3.5.2,extending AOT for Inoperable EDG from 72 Hours to 7 Days on one-time Basis ML17355A3041999-04-26026 April 1999 Proposed Tech Specs Deleting Obsolete Part of License Condition 3.L & Incorporating Administrative Changes to TS Index,Ts 3/4.1.2.5 & TS 3/4.7.6 ML17355A2491999-03-0808 March 1999 Proposed Tech Specs Section 6.0,deleting Certain Requirements That Are Adequately Controlled by Existing Regulations,Other than 10CFR50.36 & TS ML17355A2411999-02-24024 February 1999 Proposed Tech Specs Page 3/4 7-15,removing Restrictions on Location at Which Temp of UHS May Be Monitored ML17354B1641998-10-27027 October 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-31 & DPR-41,to Incorporate Specific Staff Qualifications for Multi-Discipline Supervisor Position Into TS ML17354A8381998-03-12012 March 1998 Proposed Tech Specs Deleting License Conditions 3.I,3.K,3.H & 4 & Incorporating Recent Organization Change in TS 6.5.1.2 & 6.5.3.1.a ML17354A7801998-02-0202 February 1998 Proposed Tech Specs Re Diesel Fuel Storage Sys ML17354A7621998-01-0909 January 1998 Proposed Tech Specs Sections 5.3.1 & 6.9.1.7,,allowing Implementation of Zirlo Fuel Rod Cladding ML17354A7321997-12-0404 December 1997 Proposed Tech Specs Section 6.9.1.7, COLR, Clarifying References 4 & 6 by Adding Best Estimate LOCA to COLR & Documenting re-analysis Performed as Result of Revs to Large Break LOCA Methodology ML17354A6161997-08-27027 August 1997 Proposed Tech Specs Page 6.2,allowing Use of 12 Hour Shifts for Nominal 40 (36 to 48) Hour Week ML17354A4771997-04-24024 April 1997 Proposed Tech Specs Page 6-22 Re Large Break Loss of Coolant re-analysis ML17354A4221997-02-24024 February 1997 Proposed Tech Specs 6.9.1.7 Re COLR & Large Break Loss of Coolant Accident re-analysis ML17354A3741996-12-17017 December 1996 Proposed Tech Specs,Modifying TSs to Change SR for TS 4.4.10 Re Reactor Coolant Pump Flywheel Insp ML17354A3521996-11-22022 November 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Sources & 3/4.8.1 Re AC Sources Operating Limiting Condition for Operation ML17354A2871996-10-0303 October 1996 Proposed Tech Specs Revising TS to Allow Deferral for One Cycle of Reactor Coolant Pump Flywheel Ultrasonic Exams Required by Reg Guide 1.14 ML17353A7991996-07-17017 July 1996 Proposed Tech Specs,Revising TSs to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Intervals Determined by performance-based Criteria ML17353A7111996-05-28028 May 1996 Proposed Tech Specs Section 6.0, Administrative Controls. ML18008A0451996-05-10010 May 1996 Proposed Tech Specs Re Various Administrative Improvements ML17353A6781996-05-0909 May 1996 Proposed Tech Specs Re SBLOCA re-analysis ML17353A6521996-04-23023 April 1996 Proposed Tech Specs Re Accumulator Water Level & Pressure Channnel,Per NRC GL 93-05 ML17353A6581996-04-19019 April 1996 Proposed Tech Specs,Revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6171996-03-21021 March 1996 Proposed Tech Specs,Revising TS Such That Requirements for Radiological Effluent Controls Relocated to Offsite Dose Calculation Manual or Process Control Program ML17353A6091996-03-20020 March 1996 Proposed TS 3/4.5.1,reflecting Removal of SRs & Operability Requirements for ECCS SI Accumulators That Concern Water Level & Pressure Channels ML17353A6001996-03-0505 March 1996 Proposed TS Sections 4.4.3.3 & 4.5.2,reducing Frequency of Surveillances & Insps in Accordance W/Gl 93-05,Items 6.6 & 7.5 ML17353A5031995-12-18018 December 1995 Proposed Tech Specs,Increasing Allowed Rated Thermal Power from 2,200 Mwt to 2,300 Mwt ML17353A4541995-11-22022 November 1995 Proposed Tech Specs Re Administrative Controls & Reviews ML17353A4511995-11-22022 November 1995 Proposed Tech Specs Pages 3/4 8-2 & 3/4 8-3 Re Edgs,Per GLs 93-05 & 94-01 ML17353A3971995-10-0404 October 1995 Proposed Tech Specs,Modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas,Tables 4.3-1 & 4.3-2 SR for Rps/Nis/Esfas & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentations ML17353A3831995-09-28028 September 1995 Proposed Tech Specs,Implementing Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17353A3531995-09-11011 September 1995 Proposed Tech Specs Re Edgs,Change to Testing Requirements, Per GLs 93-05 & 94-01 ML17353A2831995-07-26026 July 1995 Proposed Tech Specs 4.1.3.1.2,4.6.5.1,4.4.6.2.2,4.10.1.2 & Table 4.3-3 to Reduce Frequency of Testing,Per GL 93-05 ML17353A2801995-07-26026 July 1995 Proposed Tech Specs,Modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas Instrumentation,Tables 4.3-1 & 4.3-2 SRs for Rps/Nis/Esfas Instrumentation & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentation ML17353A2761995-07-26026 July 1995 Proposed Tech Specs,Adding to Approved COLR Analysis Methodology Used for SBLOCA Analysis in Anticipation of Thermal Uprate to 2,300 Mwt for Both Units & Increasing Current Margin to Calculated PCT ML17353A2731995-07-26026 July 1995 Proposed Tech Specs,Revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl,Incorporating Administrative Clarifications & Corrections & Correcting Typos ML17353A2701995-07-26026 July 1995 Proposed Tech Specs Re Rod Misalignment Requirement for Movable Control Assemblies ML17353A2671995-07-26026 July 1995 Proposed Tech Specs for Nuclear Instrumentation Sys Adjustments Based on Calorimetric Measurements at Reduced Power Levels ML17353A2401995-06-19019 June 1995 Proposed Tech Specs Re TS SR 4.8.1.1.2.g.7 ML17352B1841995-05-23023 May 1995 Proposed Tech Specs Re Use of Changed Setpoint Presentation Format for RPS & ESFAS Instrumentation ML20083R1291995-05-0505 May 1995 Proposed Tech Specs Re Implementation of Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17352B0881995-03-30030 March 1995 Proposed Tech Specs SR 4.8.1.1.2.g.7,allowing Separation of 5-minute hot-start Test from 24-h EDG Test Run,Deleting Associated Footnote & Adding New TS SR 4.8.1.1.2.g.14 & Associated Footnote for Performance of Subj 5-minute Test ML17352B0041995-01-17017 January 1995 Proposed Tech Specs 6.9.1.7, COLR, Including Ref to Topical Rept NF-TR-95-01 Re Implementation of FPL Nuclear Physics Methodology for Calculations of COLR Parameters ML17352A8341994-10-20020 October 1994 Proposed TS 3/4.7.1.1 & Associated Bases,Addressing Max Allowable Reactor Thermal Power Operation W/Inoperable MSSVs ML17352A8281994-10-20020 October 1994 Proposed Tech Specs 4.8.1.1.2e & 4.8.1.1.2f,addressing EDG Fuel Oil Testing & TS 3.8.1.1,addressing Required Action in Event Diesel Fuel Oil Does Not Meet Diesel Fuel Oil Testing Program Limits ML17352A8311994-10-20020 October 1994 Proposed Tech Specs 3/4.4.9.1,reflecting Removal of Schedule for Withdrawal of Rv Matl Specimens ML17352A8381994-10-20020 October 1994 Proposed Tech Specs,Allowing Containment Personnel Airlock Doors to Be Opened During Core Alterations & Movement of Irradiated Fuel in Containment,Provided Certain Conditions Met ML17352A7321994-07-19019 July 1994 Proposed TS 3/4.7.1 & Associated Bases Addressing Operation at Reduced Power Levels W/Inoperable Main Steam Safety Valves ML17352A7291994-07-19019 July 1994 Proposed Tech Specs 4.8.1.1.2e & 4.8.2.2.2f Re EDG Fuel Oil Testing Program ML17352A7241994-07-19019 July 1994 Proposed Tech Specs Adding Rod Bank Insertion Limits & K(Z) Curves to COLR ML17352A5471994-04-19019 April 1994 Proposed TS 4.0.5a Re ISI & Testing Programs ML17352A5441994-04-19019 April 1994 Proposed Tech Specs Changing Containment Spray Sys Surveillance Requirements 1999-07-27
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17355A3921999-07-27027 July 1999 Proposed Tech Specs 3.8.1.1,3.4.3 & 3.5.2,extending AOT for Inoperable EDG from 72 Hours to 7 Days on one-time Basis ML17355A3581999-06-28028 June 1999 Cycle 18 Startup Rept. with 990628 Ltr ML17355A3041999-04-26026 April 1999 Proposed Tech Specs Deleting Obsolete Part of License Condition 3.L & Incorporating Administrative Changes to TS Index,Ts 3/4.1.2.5 & TS 3/4.7.6 ML17355A2491999-03-0808 March 1999 Proposed Tech Specs Section 6.0,deleting Certain Requirements That Are Adequately Controlled by Existing Regulations,Other than 10CFR50.36 & TS ML17355A2411999-02-24024 February 1999 Proposed Tech Specs Page 3/4 7-15,removing Restrictions on Location at Which Temp of UHS May Be Monitored ML17355A2011999-01-25025 January 1999 Cycle 17 Startup Rept. with 990125 Ltr ML17354B1641998-10-27027 October 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-31 & DPR-41,to Incorporate Specific Staff Qualifications for Multi-Discipline Supervisor Position Into TS ML20197C9661998-08-27027 August 1998 Rev 15 to Security Training & Qualification Plan ML17354A9471998-04-27027 April 1998 Rev 2 to Turkey Point Nuclear Plant Recovery Plan. ML17354A8381998-03-12012 March 1998 Proposed Tech Specs Deleting License Conditions 3.I,3.K,3.H & 4 & Incorporating Recent Organization Change in TS 6.5.1.2 & 6.5.3.1.a ML17354A7801998-02-0202 February 1998 Proposed Tech Specs Re Diesel Fuel Storage Sys ML17355A2711998-01-30030 January 1998 Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point Plant,Units 3 & 4. ML17354A7621998-01-0909 January 1998 Proposed Tech Specs Sections 5.3.1 & 6.9.1.7,,allowing Implementation of Zirlo Fuel Rod Cladding ML17354A7321997-12-0404 December 1997 Proposed Tech Specs Section 6.9.1.7, COLR, Clarifying References 4 & 6 by Adding Best Estimate LOCA to COLR & Documenting re-analysis Performed as Result of Revs to Large Break LOCA Methodology ML17354A6161997-08-27027 August 1997 Proposed Tech Specs Page 6.2,allowing Use of 12 Hour Shifts for Nominal 40 (36 to 48) Hour Week ML17354A4971997-05-0101 May 1997 Rev 1 to Turkey Point Nuclear Plant Recovery Plan. ML17354A4771997-04-24024 April 1997 Proposed Tech Specs Page 6-22 Re Large Break Loss of Coolant re-analysis ML17354A4221997-02-24024 February 1997 Proposed Tech Specs 6.9.1.7 Re COLR & Large Break Loss of Coolant Accident re-analysis ML17354A3741996-12-17017 December 1996 Proposed Tech Specs,Modifying TSs to Change SR for TS 4.4.10 Re Reactor Coolant Pump Flywheel Insp ML17354A3521996-11-22022 November 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Sources & 3/4.8.1 Re AC Sources Operating Limiting Condition for Operation ML17354A2871996-10-0303 October 1996 Proposed Tech Specs Revising TS to Allow Deferral for One Cycle of Reactor Coolant Pump Flywheel Ultrasonic Exams Required by Reg Guide 1.14 ML17353A7991996-07-17017 July 1996 Proposed Tech Specs,Revising TSs to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Intervals Determined by performance-based Criteria ML17353A7111996-05-28028 May 1996 Proposed Tech Specs Section 6.0, Administrative Controls. ML18008A0451996-05-10010 May 1996 Proposed Tech Specs Re Various Administrative Improvements ML17353A6781996-05-0909 May 1996 Proposed Tech Specs Re SBLOCA re-analysis ML17353A6521996-04-23023 April 1996 Proposed Tech Specs Re Accumulator Water Level & Pressure Channnel,Per NRC GL 93-05 ML17353A6581996-04-19019 April 1996 Proposed Tech Specs,Revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6171996-03-21021 March 1996 Proposed Tech Specs,Revising TS Such That Requirements for Radiological Effluent Controls Relocated to Offsite Dose Calculation Manual or Process Control Program ML17353A6091996-03-20020 March 1996 Proposed TS 3/4.5.1,reflecting Removal of SRs & Operability Requirements for ECCS SI Accumulators That Concern Water Level & Pressure Channels ML17353A6001996-03-0505 March 1996 Proposed TS Sections 4.4.3.3 & 4.5.2,reducing Frequency of Surveillances & Insps in Accordance W/Gl 93-05,Items 6.6 & 7.5 ML17353A5801996-02-29029 February 1996 Plant Procedures & Training Matl Provided for Preparation of Licensing Exams for Reactor Operator Group Xvi & Senior Reactor Operator Upgrade. ML17353A6191996-02-15015 February 1996 Offsite Dose Calculation Manual for Gaseous & Liquid Effluents from Turkey Point Plant Units 3 & 4. ML17353A7631996-02-0808 February 1996 Conduct of Operations. ML17353A5031995-12-18018 December 1995 Proposed Tech Specs,Increasing Allowed Rated Thermal Power from 2,200 Mwt to 2,300 Mwt ML17353A4541995-11-22022 November 1995 Proposed Tech Specs Re Administrative Controls & Reviews ML17353A4511995-11-22022 November 1995 Proposed Tech Specs Pages 3/4 8-2 & 3/4 8-3 Re Edgs,Per GLs 93-05 & 94-01 ML17353A3971995-10-0404 October 1995 Proposed Tech Specs,Modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas,Tables 4.3-1 & 4.3-2 SR for Rps/Nis/Esfas & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentations ML17353A3831995-09-28028 September 1995 Proposed Tech Specs,Implementing Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17353A3531995-09-11011 September 1995 Proposed Tech Specs Re Edgs,Change to Testing Requirements, Per GLs 93-05 & 94-01 ML17353A7641995-08-23023 August 1995 Emergency & Off-normal Operating Procedure Usage. ML17353A2831995-07-26026 July 1995 Proposed Tech Specs 4.1.3.1.2,4.6.5.1,4.4.6.2.2,4.10.1.2 & Table 4.3-3 to Reduce Frequency of Testing,Per GL 93-05 ML17353A2801995-07-26026 July 1995 Proposed Tech Specs,Modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas Instrumentation,Tables 4.3-1 & 4.3-2 SRs for Rps/Nis/Esfas Instrumentation & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentation ML17353A2761995-07-26026 July 1995 Proposed Tech Specs,Adding to Approved COLR Analysis Methodology Used for SBLOCA Analysis in Anticipation of Thermal Uprate to 2,300 Mwt for Both Units & Increasing Current Margin to Calculated PCT ML17353A2731995-07-26026 July 1995 Proposed Tech Specs,Revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl,Incorporating Administrative Clarifications & Corrections & Correcting Typos ML17353A2701995-07-26026 July 1995 Proposed Tech Specs Re Rod Misalignment Requirement for Movable Control Assemblies ML17353A2671995-07-26026 July 1995 Proposed Tech Specs for Nuclear Instrumentation Sys Adjustments Based on Calorimetric Measurements at Reduced Power Levels ML17353A2401995-06-19019 June 1995 Proposed Tech Specs Re TS SR 4.8.1.1.2.g.7 ML17352B1841995-05-23023 May 1995 Proposed Tech Specs Re Use of Changed Setpoint Presentation Format for RPS & ESFAS Instrumentation ML20083R1291995-05-0505 May 1995 Proposed Tech Specs Re Implementation of Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17352B0881995-03-30030 March 1995 Proposed Tech Specs SR 4.8.1.1.2.g.7,allowing Separation of 5-minute hot-start Test from 24-h EDG Test Run,Deleting Associated Footnote & Adding New TS SR 4.8.1.1.2.g.14 & Associated Footnote for Performance of Subj 5-minute Test 1999-07-27
[Table view] |
Text
ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATIONS Marked-Up Technical Specifications Pages, 3/4 7-11 3/4 7-lla (new page)
B 3/4 7-4 B 3/4 7-5 9309090232 930903 PDR ADOCK 05000250 P PDR
4 I ~ 4 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3/4. 7 PLANT SYSTEMS 3/4. 7. 1 TURBINE CYCLE Safety Valves I 3/4 7-1 TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING THREE LOOP OPERATION. 3/4 7-2 TABLE 3.7-2 STEAM LINE SAFETY VALVES PER LOOP........,...... 3/4 7-2 Auxiliary Feedwater System................. 3/4 7-3 TABLE 3.7-3 AUXILIARY FEEDWATER SYSTEM OPERABILITY.. 3/4 7-5 Condensate Storage Tank. 3/4 7-6 Specific Activity............... ..,.....~ 3/4 7-8 TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE
'AND ANALYSIS PROGRAM.........,...........,. 3/4 7-9 Main Steam Line Isolation Valves........... 3/4 7-10 tan Feedwater System. 3/4 7-11 3/4. 7. 2 COMPONENT COOLING WATER SYSTEM....,........ 3/4 7-12 3/4. 7. 3 INTAKE COOLING WATER SYSTEM... ~ ................. 3/4 7-14 3/4.7.4 ULTIMATE HEAT SINK....., .. 3/4 7-15 3/4. 7. 5 CONTROL ROOM EMERGENCY VENTILATION SYSTEM................ 3/4 7-16 3/4. 7. 6 SNUBBERS 3/4 7"18 3/4.7. 7 SEALED SOURCE CONTAMINATION............................. 3/4 7-22 S+C.a.~ G~~E.'Va.'4V TURKEY POINT " UNITS 3 8( 4 l AMENDMENT NOS.l 37 AND 32
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PLANT SYSTEMS STANDBY FEEDWATER SYSTEM
'LIMITING CONDITION FOR OPERATION 3.7. 1.6 Two standby<feedwater pumps shall be OPERABLE" and at least 60,000 gallons of water (available volume), shall be in the Demineralized Water Storage Tank"".
APPLICABILITY: MODES 1, 2 and 3 ACTION: s %caw g e~~~4 ~
- a. With one standby<feedwater pump inoperable, restore the inoperable pum to available status within 30 days or submit a SPECIAL REPORT per 3.7.1.6d.
standby feedwater pumps inoperable:
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, no RC and provide cause for inoperability and plans to restore pump(s) to tatus and,
- 2. Submit a SPECIAL REPORT er 3.7.1.6d.
- c. With less than 60,000 gallons of water in the Demineralized Water Storage Tank restore the available volume to at least 60,000 gallons within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or submit a SPECIAL REPORT per 3.7. 1,6d.
- d. If a SPECIAL REPORT is required per the above specifications submit a report describing the cause of the inoperability, action taken and a schedule for restoration within 30 days in accordance with 6.9.2.
SURVEILLANCE RE UIREMENTS 4.7. 1.6. 1 The Demineralized Water Storage tank water volume shall be deter-mined to be within limits at least once per r B~nL ~v 4.7. 1.6.2 At least monthly verify the stan p, er pumps are OPERABLE by testing in recirculation on a STAGGERED TEST BASIS.
a~ gema4r '
- 4. 7. 1. 6. n e er months verif erabi e respective standby feedwater pump by and providing feedwater t the steam genera ors.
S4 a.r 4 ~g ea.e.k y ~p "These pumps do not require plant safe y re ate emergency power sources for operability and the flowpath is normally isolated.
""The Demineralized Water Storage Tank is non-safety grade.
TURKEY POINT - UNITS 3 84 4 3/4 7-11 AMENDMENT NOS.137 AND 132
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L-93-200 Attachment 3 INSERT C
- b. With both standby steam generator feedwater pumps inoperable, restore at least one pump to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or:
1~ Notify the NRC within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, and provide cause for the inoperability and plans to restore pump(s) to OPERABLE status and, 2 ~ Submit a SPECIAL REPORT per 3.7.1.6d.
~ &
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Cont inued 4.7.1.6.4 The diesel engine for the diesel-driven standby steam generator feedwater pump shall be demonstrated OPERABLE:
- a. At least once every 31 days, by testing with the associated standby steam generator feedwater pump in recirculation.
- b. At least once pez 18 months, by subjecting the diesel to an inspection in accordance with proceduzes prepared in conjunction with its manufacturer's zecommendations for the class of service.
TURKEY POINT UNITS 3 & 4 3/4 7-11a AMENDMENT NOS. AND
0 PLANT SYSTEHS BASES 3/4. 7. 1. 6 STANOB FEEOWATER SYSTEH The purpose of this specification a the supporting surv i llance require-ments is to assure o erabi lit of the n-safety grade Standby<Feedwater System.
The Standb ee wa er ys em cons>s s of commercial grade components designed and constructed to industry and FPL standards of this ciass of equipment located in the outdoor plant environment typical of FPL facilities system wide. The system is expected to perform with high reliability, i.e., comparable to that typically achieved with this class of equipment. FPL intends to maintain the system in good operating condition with regard to appearance, structures, supports, component maintenance calibrations etc.
The function of the Stand y~ ee wa er s em or OPERABILITY determinations is that it can be used as a backup to the Auxiliary Feedwater (AFM) System in the event the AFW System does not function properly. The system would manuall started, ali ned and controlled by the o erator when needed ~e
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A supply of 60,000 gallons from the Demineralized Mater Storage Tank for Reve the Standby Feedwater Pumps is sufficient water to remove decay heat from the reactor for six (6) hours for a single unit or two (2) hours for two units.
This was th basis used for requiring 60,000 gallons of water in the non-safety grade Demine lized Mater Storage Tank and is judged to provide sufficient time for restoring Storage Tank.
Tt ments app >ca
~!t e e AFM S stem or establishing make-up to the Demineralized Mater o
dt I d uxiliary Feedwater Systems design basis events requirements.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before initiating formal notification I I These pumps and td Tg dt dltt not required to satisfy may 3e out of service for up to because of the extremely low probability of a demand for their operation.
The guidelines for NRC notification in case of both pumps being out of service for longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are provide in a licable lant rocedures, as a voluntary 4-hour notification.
Adequate demineralized water for the andby edwater system will be verified once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The Demineral zed Mater Storage Tank provides a ms and therefore, requires daily verification.
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The andb edwater mp~ill be verified OPERABLE monthly on a STAGGERED EST IA IS by startin and operating them in the recirculation mod~
- y. Also, during each unit's refuelin ou e
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TURKEY POINT - UNITS 3 8( 4 8 3/4 7"4 AHENDHENT NOS3.37 AND 132
L-93-200 XNSERT A The A pump is electric-driven and is powered from the non-safety related C bus. Zn the event of a coincident loss of offsite power, the B pump is diesel driven and can be started and operated independent of the availability of on-site or offsite power.
0 PLA'NT SYSTEMS BASES 5 Maw Qewe~Wr STANOBY FEEOMATER SYSTEM (Continued) to the nuclear unit's steam generators, e
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( i~ sea~.l d<<ve< s The OPERABILITY of the Component Cooling Mater System ensures that suf-ficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single active failure, is consistent with the assumptions used in the safety analyses. One pump and two heat exchangers provide the heat removal capability for accidents that have been analyzed.
3/4. 7. 3 INTAKE COOLING MATER SYSTEM The OPERABILITY of the Intake Cooling Mater System ensures that sufficient cooling capacity is available for continued operation of safety-related equip-ment during normal and accident conditions. The design and operation of this system, assuming a single active failure, ensures cooling capacity consistent with the assumptions used in the safety analyses.
3/4.7.4 ULTIMATE HEAT SINK The limitations on the ultimate heat sink temperature ensure that sufficient cooling capacity is available either: (1) to provide normal cooldown of the facility or (2) to mitigate the effects of accident conditions within acceptable 1 imi ts.
TURKEY PO'.NT - UNITS 3 & 4 B 3/4 7"5 AMENOMENT NOS.137 AND 132
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L-93-200 INSERT B The diesel engine driver for the B Standby Steam Generator Feedwatez Pump will be verified operable once every 31 days on a staggered test basis performed on the B Standby Steam Generator Feedwater Pump. In addition, an inspection will be performed on the diesel at'least once every 18 months in accordance with procedures prepared in conjunction with its manufacture's recommendations for the diesel's class of service. This inspection will ensure that the diesel driver is maintained in good operating condition consistent with FPL's ovezall objectives for system reliability.
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