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Line 29: |
Line 29: |
| TURKEY POINT - UNITS 3 8 4 3/4 7-1 AMENDMENT NOS.I37AND 132 | | TURKEY POINT - UNITS 3 8 4 3/4 7-1 AMENDMENT NOS.I37AND 132 |
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| L-94-223 Attachment 3 Insert A With (3) reactor coolant loops and associated steam generators in operation and with one or more main steam line Code safety valves inoperable, and a ~ with a positive Moderator Temperature Coefficient, operation in MODES 1 and 2 may continue provided, that within 4 hours, either= | | L-94-223 Insert A With (3) reactor coolant loops and associated steam generators in operation and with one or more main steam line Code safety valves inoperable, and a ~ with a positive Moderator Temperature Coefficient, operation in MODES 1 and 2 may continue provided, that within 4 hours, either= |
| the inoperable valve(s) is restored to OPERABLE status or reduce the Power Range Neutron Flux High Tzip Setpoint to the maximum allowable percent of RATED THERMAL POWER listed in Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 12 hours, or | | the inoperable valve(s) is restored to OPERABLE status or reduce the Power Range Neutron Flux High Tzip Setpoint to the maximum allowable percent of RATED THERMAL POWER listed in Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 12 hours, or |
| : b. with a negative or zero Moderator Temperature Coefficient, operation in MODES 1, 2, and 3 may continue provided, that within 4 hours, either the inoperable valve(s) is restored to OPERABLE status or reduce power to less than or equal to the maximum allowable percent of RATED THERMAL POWER listed in Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 12 hours. | | : b. with a negative or zero Moderator Temperature Coefficient, operation in MODES 1, 2, and 3 may continue provided, that within 4 hours, either the inoperable valve(s) is restored to OPERABLE status or reduce power to less than or equal to the maximum allowable percent of RATED THERMAL POWER listed in Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 12 hours. |
Line 56: |
Line 56: |
| p c<) | | p c<) |
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| L-94-223 Attachment 3 INSERT FOR TS BASES 3 4.7.1.1 (w h N) | | L-94-223 INSERT FOR TS BASES 3 4.7.1.1 (w h N) |
| Hi g = (100/Q) | | Hi g = (100/Q) |
| K where: | | K where: |
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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 Specification Pages:
3/4 7-1 3/4 7-2 B 3/4 7-1 Inserts A and B Insert for BASES 3/4.7.1.1 9410260330 941020 PDR ADDCK 05000250 PDR
3/4.7 PLANT SYSTEMS 3/4.7. 1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION
- 3. 7. 1. 1 All main steam line Code safety valves associated with each steam generator shall be OPERABLE with lift settings as specified in Table 3.7-2.
APPLICABILITY: MODES 1, 2, and 3.
ACTION: l<s<gT'A5- ke~
With (3) reactor coolant oops an assoc~a ed steam generators in oper with one or more main steam line Code safety valves inopera MODES 1, 2, and 3 may proceed provided, that wi operable valve is restored to OPERA
'urs, ration in either the in-s or the Power Range Neutron Flux High Trip Setpoint is re able 3.7"1; otherwise, be in at least HOT STANDBY withi ext 6 hours and in COLO SHUTDOWN within the following 30 h (O<t rwE)
SURVEILLANCE RE UIREMENTS 4.7. 1. 1 No additional requirements other than those required by Specification l~5<g~ ( 8 ke~~
TURKEY POINT - UNITS 3 8 4 3/4 7-1 AMENDMENT NOS.I37AND 132
L-94-223 Insert A With (3) reactor coolant loops and associated steam generators in operation and with one or more main steam line Code safety valves inoperable, and a ~ with a positive Moderator Temperature Coefficient, operation in MODES 1 and 2 may continue provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either=
the inoperable valve(s) is restored to OPERABLE status or reduce the Power Range Neutron Flux High Tzip Setpoint to the maximum allowable percent of RATED THERMAL POWER listed in Table 3.7-1; otherwise, 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 HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or
- b. with a negative or zero Moderator Temperature Coefficient, operation in MODES 1, 2, and 3 may continue provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve(s) is restored to OPERABLE status or reduce power to less than or equal to the maximum allowable percent of RATED THERMAL POWER listed in Table 3.7-1; otherwise, 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 HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Insert B The provisions of Specifications 4.0.4 are not applicable foz entry into MODE 3.
TABLE 3.7-1 HAXIMUM ALLOWABLE POWER WITH INOPERABLE STEAM LINE SAFETY VALVES DURING THRE L OP OPERATION HAXIHUH NUMBER OF INOPERABLE MAX UM ALLOWAB P WE {tAH&E SAFETY VALVES ON ANY OPERATING STEAM GENERATOR PE ATEO T HAL POWER TABLE 3.7-2 STEAM LINE SAFETY VALVES PER LOOP ORIFICE SIZE VALVE NUMBER LIFT SETTING 21K " S UARE INCHES
~Loo A ~Loo B ~Loo C
- 1. RV1400 RV1405 RV1410 1085 psig 16
- 2. RV1401 RV1406 RV1411 1100 psig
- 3. RV1402 RV1407 RV1412 1115 psig 16
- 4. RV 1403 RV1408 RV1413 1130 psig 16 "The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
TURKEY POINT -, UNITS 3 Ec 4 3/4 7-2 AMENDMENT NOS.137 AND 132
p 4 e r r ~ i 4n w f
'p ~ ~ NV.iJ ',
e fA e8A mtwr 4 c = 1
~ <<) (. ) q~~
~
3/4. 7 PLAHT SYSTEMS BASES 3/4. 7. 1 TURBINE CYCLE 3/4. 7. l. 1 SAFETY VALVES The OPERABILITY of the main steam line Code safety valves ensures that the Secondary System pressure will be limited to within 110K (1193. 5 psig) of its design pressure of 1085 psig during the most .severe anticipated system opera-tional transient. The maximum relieving capacity is associated with a Turbine trip from lOOX RATED THERMAL POWER coincident with an assumed loss of. condenser heat sink (i.e., no steam bypass to the condenser).
The specified valve lift settings and relieving capacities are in accordance with the requirements of Section VIII of the ASME Boiler and Pressure 'Code, 1971 Edition. The total relieving capacity for all valves on all of the steam lines is 10,670,000 lbs/h which is 111K of the total secondary steam flow of 9,600,000 lbs/h at 100K RATFD THERMAL POWER. A minimum of one OPERABLE safety valves per steam generator ensures that sufficient relieving capaci is avai lable for the allowable THERMAL POWER restriction in Table 3.7 STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in Secondary Coolant System steam flow and THEltMAL POWER required by the reduced Reactor trip settings of the Power Range Neutron Flux channels. The Reactor Trip Setpoint reductions are derived on the following bases:
SP .. x (109) FP~l C wlwH Where:
l~ sCRv'P Reduced Reac r Trip Setpoint in percent of RATED THE L POWE Maximum nu er of inoperabl safety valv per ste line, 09 = Power R ge Neutron Flux- gh Trip Set int, X Total elieving capacit of all safe valves p r steam line in lbs/hour, and M imum relieving c acity of any one safety valve in bs/hour 3/4. 7. 1. 2 AUXILIARY FEEOWATER SYSTEM The OPERABILITY of the Auxiliary Feedwater System ensures that the Reactor Coolant System can be cooled down to less than 3504F from normal operating conditions in the event of a total loss-of-offsite power. Steam can be TURKEY POINT - UNITS 3 4 4 B 3/4 7-1 AMENDMENT NOS.137 AND 132
p a~/
p c<)
L-94-223 INSERT FOR TS BASES 3 4.7.1.1 (w h N)
Hi g = (100/Q)
K where:
Hi Reduced THERMAL POWER for the most limiting steam generator expressed as a percent of RTP Q Nominal Nuclear Steam Supply System (NSSS) power rating of the plant (including reactor coolant pump heat), Mwt K ~5 Conversion factor; 947.82 (Btu/sec)/Mwt ws Minimum total steam flow rate capability of the operable MSSVs on any one steam generator at the highest MSSV opening pressure (including tolerance and accumulation) (Lbm/sec) ~ For example, if maximum number of inoperable MSSVs on any one steam the generator is one, then ws should be a summation of the capacity of the operable MSSVs at the highest operable MSSV operating pressure, excluding the highest capacity MSSV. If the maximum number of inoperable MSSVs per steam generator is three, then ws should be a summation of the capacity of the operable MSSV at the highest opezable MSSV operating pressure, excluding the three highest capacity MSSVs.
hfg Heat of vaporization for steam at the highest MSSV opening pressure (including tolezance and accumulation) (Btu/ibm)
N Number of loops in plant The values calculated from this algorithm must then be adjusted lower for use in TS 3.7.1.1 to account for instrument and channel uncertainties.
Operation with less than all four MSSVs OPERABLE for each steam generator is permissible, if THERMAL POWER is proportionally limited to the relief capacity of the remaining MSSVs. This is accomplished by restricting THERMAL POWER so that the energy transfer to the most limiting steam generator is not greater than the available relief capacity in that steam generator.
0 N r