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| {{#Wiki_filter:ATTACHMENT 3 Proposed Technical Specifications Marked-up Technical Specification Pages 3/4 6-2 S 3/4 6-X f 9310120275 9>MO+-PDR ADQCK 05000250',,;PDR v,4@Lb,.AW-a*I't~ | | {{#Wiki_filter:ATTACHMENT 3 Proposed Technical Specifications Marked-up Technical Specification Pages 3/4 6-2 S 3/4 6-X 9310120275 9>MO+- |
| CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to: a.An overall integrated leakage rate of less than or-equal to L , a'.25K by weight of the containment air per 24 hours at P, 49.9 psig.a'.A combined leakage rate of less than 0.60 L for all penetrations and valves subject to Type B and C tests, when pressurized to APPLICABILITY: | | f PDR ADQCK v,4 @Lb, 05000250',,;PDR |
| MODES 1, 2, 3, and 4.ACTION: With either the measured overall integrated containment leakage rate exceeding 0.75 L or the measured combined leakage rate for all penetrations and valves subject to Types 8 and C tests exceeding 0.60 L , restore the overall integrated leakage rate to less than 0.75 L and the combined leakage rate for all penetrations subject to Type B and C tests to less than 0.60 L prior to increasing the Reactor Coolant System temperature above 200'F.SURVEILLANCE RE UIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR Part 50 using the methods and provisions of ANSI N45.4-1972: | | .AW |
| DBLE~B AhlD gGP~crE.a~e A tests (Overall Integrated Containment Leak shall be con t 40+10 month intervals'hutdown at a pressure not less than ,.9 , r>ng each 10-year service period.The third each set sha nducted during the shutdow e 10-year plant inservice inspection, TYPE A+est ahall be PeaA>r mac>te AccaaDAu(c mn-H tO CFR.SO hPPEVQlX D, hS&OQivt5&8w APPcoV Ec7 C'kL MPT70AJZ, TURKEY POINT-UNITS 3 8(4'/4 6-2 AMENDMENT NOS.137AND 132 Fg~II 1'II'II~(~h 3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses.This restric-tion, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the dose guideline values of 10 CFR Part 100 during accident conditions. | | |
| 3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure, P.'s an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L during performance of the periodic test to account for possible degradation of the containment leakage barriers between leakage tests.The surveillance testing for measuring leakage rat s is consi nt w't the requirements of Appendix J of 10 CFR Part 50.ao rnooinlmDBY nponoumm Rsetnpfsons i add 3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.In order to meet the ACTION requirement to lock the OPERABLE air lock door closed, the air lock door inter-lock may provide the required locking.In addition, the outer air lock door is secured under administrative controls.3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that: (1)the containment structure is prevented from exceeding its design negative pressure differential of 2.5 psig with respect to the outside atmosphere, and (2)the containment peak pressure does not exceed the design pressure of 59 psig during LOCA conditions. | | a*I't ~ |
| The maximum peak pressure expected to be obtained from a LOCA event is 49.9 psig assuming an initial containment pressure of 0.3 psig.An initial positive pressure of as much as 5 psi would result in a maximum containment pressure that is less than design pressure and is consistent with the safety analyses.TURKEY POINT" UNITS 3 8t 4 B 3/4 6-1 AMENDMENT NOS.I37AND 132 | | CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION |
| ~W~t" g'@i>t~" 4 i(d t s j}} | | : 3. 6. 1. 2 Containment leakage rates shall be limited to: |
| | : a. An overall integrated leakage rate of less than or-equal to L , |
| | by weight of the containment air per 24 hours at P, 49.9 psig. |
| | a'.25K a'. |
| | A combined leakage rate of less than 0.60 L for all penetrations and valves subject to Type B and C tests, when pressurized to APPLICABILITY: MODES 1, 2, 3, and 4. |
| | ACTION: |
| | With either the measured overall integrated containment leakage rate exceeding 0.75 L or the measured combined leakage rate for all penetrations and valves subject to Types 8 and C tests exceeding 0. 60 L , restore the overall integrated leakage rate to less than 0.75 L and the combined leakage rate for all penetrations subject to Type B and C tests to less than 0.60 L prior to increasing the Reactor Coolant System temperature above 200'F. |
| | SURVEILLANCE RE UIREMENTS 4.6. 1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR Part 50 using the methods and provisions of ANSI N45.4-1972: |
| | DBLE~B AhlD gGP~crE. |
| | a e A tests (Overall Integrated Containment Leak t |
| | ~ |
| | shall be con 40 + 10 month intervals 'hutdown at a pressure not less than , .9 , r>ng each 10-year service period. The third each set sha nducted during the shutdow e 10-year plant inservice inspection, TYPE A +est ahall be PeaA>r mac> te AccaaDAu(c mn-H tO CFR. SO hPPEVQlX D, hS &OQivt5& 8w APPcoV Ec7 C'kL MPT70AJZ, TURKEY POINT - UNITS 3 8( 4'/4 6-2 AMENDMENT NOS.137AND 132 |
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| | 3/4.6 CONTAINMENT SYSTEMS BASES 3/4. 6. 1 PRIMARY CONTAINMENT 3/4. 6. 1. 1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses. This restric-tion, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the dose guideline values of 10 CFR Part 100 during accident conditions. |
| | 3/4. 6. 1. 2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure, P .'s an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L during performance of the periodic test to account for possible degradation of the containment leakage barriers between leakage tests. |
| | The surveillance testing for measuring leakage rat s is consi nt w't the requirements of Appendix J of 10 CFR Part 50. ao rnooinlmDBY nponoumm Rsetnpfsons i 3/4. 6. 1. 3 CONTAINMENT AIR LOCKS add The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate. Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests. In order to meet the ACTION requirement to lock the OPERABLE air lock door closed, the air lock door inter-lock may provide the required locking. In addition, the outer air lock door is secured under administrative controls. |
| | 3/4.6. 1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that: (1) the containment structure is prevented from exceeding its design negative pressure differential of 2.5 psig with respect to the outside atmosphere, and (2) the containment peak pressure does not exceed the design pressure of 59 psig during LOCA conditions. |
| | The maximum peak pressure expected to be obtained from a LOCA event is 49.9 psig assuming an initial containment pressure of 0.3 psig. An initial positive pressure of as much as 5 psi would result in a maximum containment pressure that is less than design pressure and is consistent with the safety analyses. |
| | TURKEY POINT " UNITS 3 8t 4 B 3/4 6-1 AMENDMENT NOS. I37AND 132 |
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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 6-2 S 3/4 6-X 9310120275 9>MO+-
f PDR ADQCK v,4 @Lb, 05000250',,;PDR
.AW
a*I't ~
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION
- 3. 6. 1. 2 Containment leakage rates shall be limited to:
- a. An overall integrated leakage rate of less than or-equal to L ,
by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P, 49.9 psig.
a'.25K a'.
A combined leakage rate of less than 0.60 L for all penetrations and valves subject to Type B and C tests, when pressurized to APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With either the measured overall integrated containment leakage rate exceeding 0.75 L or the measured combined leakage rate for all penetrations and valves subject to Types 8 and C tests exceeding 0. 60 L , restore the overall integrated leakage rate to less than 0.75 L and the combined leakage rate for all penetrations subject to Type B and C tests to less than 0.60 L prior to increasing the Reactor Coolant System temperature above 200'F.
SURVEILLANCE RE UIREMENTS 4.6. 1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR Part 50 using the methods and provisions of ANSI N45.4-1972:
DBLE~B AhlD gGP~crE.
a e A tests (Overall Integrated Containment Leak t
~
shall be con 40 + 10 month intervals 'hutdown at a pressure not less than , .9 , r>ng each 10-year service period. The third each set sha nducted during the shutdow e 10-year plant inservice inspection, TYPE A +est ahall be PeaA>r mac> te AccaaDAu(c mn-H tO CFR. SO hPPEVQlX D, hS &OQivt5& 8w APPcoV Ec7 C'kL MPT70AJZ, TURKEY POINT - UNITS 3 8( 4'/4 6-2 AMENDMENT NOS.137AND 132
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3/4.6 CONTAINMENT SYSTEMS BASES 3/4. 6. 1 PRIMARY CONTAINMENT 3/4. 6. 1. 1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses. This restric-tion, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the dose guideline values of 10 CFR Part 100 during accident conditions.
3/4. 6. 1. 2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure, P .'s an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L during performance of the periodic test to account for possible degradation of the containment leakage barriers between leakage tests.
The surveillance testing for measuring leakage rat s is consi nt w't the requirements of Appendix J of 10 CFR Part 50. ao rnooinlmDBY nponoumm Rsetnpfsons i 3/4. 6. 1. 3 CONTAINMENT AIR LOCKS add The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate. Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests. In order to meet the ACTION requirement to lock the OPERABLE air lock door closed, the air lock door inter-lock may provide the required locking. In addition, the outer air lock door is secured under administrative controls.
3/4.6. 1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that: (1) the containment structure is prevented from exceeding its design negative pressure differential of 2.5 psig with respect to the outside atmosphere, and (2) the containment peak pressure does not exceed the design pressure of 59 psig during LOCA conditions.
The maximum peak pressure expected to be obtained from a LOCA event is 49.9 psig assuming an initial containment pressure of 0.3 psig. An initial positive pressure of as much as 5 psi would result in a maximum containment pressure that is less than design pressure and is consistent with the safety analyses.
TURKEY POINT " UNITS 3 8t 4 B 3/4 6-1 AMENDMENT NOS. I37AND 132
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