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| {{#Wiki_filter:ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)Units 2 and 3 PROPOSED IMPROVED TECHNICAL SPECI FICATION CHANGE TS 393 I SUPPLEMENT 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION MARKED PAGE S I.AFFECTED PAGE LIST Unit 2-Page 3.4-29 Unit 3-Page 3.4-29 II.REVISED PAGES See attached.98i2240i64 98i2i5~I PDR ADOCK 05000260 P PDR j RCS P/T Limits 3.4.9 I=/a~]l-/K/-0/MMMM@PAg~1600 1500 BROWNS FERRY U Curve No 1 Minimum temperature for pressure tests such as required by Section XI.1300 c3 1200 1100 1000~wsoo 500 O I-700 800 500 3OO 200 100 0 0 312 PSIG CURVES 1,2, 8 3 ARE VAUD FOR FPY OF OPERATION 50 100 150 200 250 300 350 400 MIQMUM REACTORVESSEL MEfAL TEMPERATURE('F) | | {{#Wiki_filter:ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN) |
| Curve No 2 Minimum temperature for mechanical heatup or cooldowh following nuclear shutdown.Curve No.3 Minimum temperature for core operation'(criticality). | | Units 2 and 3 PROPOSED IMPROVED TECHNICAL SPECI FICATION CHANGE TS 393 I SUPPLEMENT 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION MARKED PAGE S I. AFFECTED PAGE LIST Unit 2 Page 3.4-29 Unit 3 Page 3.4-29 II. REVISED PAGES See attached. |
| Notes These curves include sufficient margin to provide protection against feedwater nozzle degradation. | | 98i2240i64 98i2i5 ~I PDR ADOCK 05000260 P PDR j |
| The curves allow for shifts in RTNOT of the Reactor vessel beltline materials, in accordance with Reg.Guide 1.99 Rev.2 to compensate for radiation embrittlement for FPY.Figure 3.4.9-1 Pressure/Temperature Limits BFN-UNIT 2 3.4-29 Amendment No.253 | | |
| *I{II l 1 1 1600 1500 BROWNS FERRY UNIT 2 1400 1300 1200 o 1100 O~1000 I g coo 0 CC g 800 z 7oo 600 C D N 600 400 300 200 100 0 60 100 160 200 250 300 360 400 MINIMUM REACTOR VESSEL METAL TEMPERATURE | | RCS P/T Limits 3.4.9 I=/a~ |
| ('F) | | ] l-/K /-0/MMMM@ PAg~ |
| RCS P/T Limits 3.4.9/~~~7-~lc H Q~RP~S HEem i I+K-.Im/L OMz~+Qgg 1600 15M 14M ZZ>1300 D 1200 1100 0 I-1000 CO Li 900 800 iL'-O 700 IL'00 I-500 ILJ 400 C0 3OO 200 100 312 PS BOL 70'ROWNS FERRY U 3 CURVES 1, 2, K 3 ARE VAUD FOR E Y OF OPERATION Curve No.1 Minimum temperature for pressure tests such as required by Section XI.Curve No.2 Minimum temperature for mechanical heatup or cooldown following nuclear shutdown.Curve No.3 Minimum temperature for core operation (criticality). | | 1600 BROWNS FERRY Curve No 1 1500 U Minimum temperature for pressure tests such as required by Section XI. |
| Notes These curves include sufficient margin to provide protection against feedwater nozzle degradation. | | 1300 Curve No 2 c3 1200 Minimum temperature for mechanical heatup or 1100 cooldowh following nuclear shutdown. |
| The curves allow for shifts in RTNOT of the Reactor vessel beltline materials, in accordance with Reg.Guide 1.99 Rev.2 to compensate for radiation embrittlement for FPY.0 50 100 150 200 250 300 350 400 MIMMUM REAGTQRYESSEL MEl'AL TEMPERATURE('Fi Figure 3.4.9-1 Pressure/Temperature Limits BFN-UNIT 3 3.4-29 Amendment No.212 II I/I 1600 1500 BROWNS FERRY UNIT 3 1400 1300 1200 o 1<<0 O 1000 g 900 W OC g 800 O 700 I 600 D cn 600 i 400 300 200 100 0 60 100 150 200 260 300 350 400 MINIMUM REACTOR VESSEL METAL TEMPERATURE (4F) | | 1000 |
| I' ENCLOSURE 4 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)Units 2, and 3 PROPOSED I MPROVED TECHN I CAL SPEC I F I CAT I ON CHANGE TS 393 I SUPPLEMENT 1 REVISED PAGES I.AFFECTED PAGE LIST Unit 2-Page 3.4-29 Unit 3-Page 3.4-29 II.REVISED PAGES See attached. | | ~ |
| | wsoo Curve No. 3 Minimum temperature for 500 core operation '(criticality). |
| | I-O 700 Notes 800 These curves include sufficient margin to provide 500 protection against feedwater nozzle degradation. The curves 312 PSIG allow for shifts in RTNOT of 3OO the Reactor vessel beltline materials, in accordance 200 CURVES 1,2, 8 3 ARE VAUD FOR with Reg. Guide 1.99 FPY OF OPERATION Rev. 2 to compensate for 100 radiation embrittlement for 0 |
| | FPY. |
| | 0 50 100 150 200 250 300 350 400 MIQMUM REACTORVESSEL MEfALTEMPERATURE('F) |
| | Figure 3.4.9-1 Pressure/Temperature Limits BFN-UNIT2 3.4-29 Amendment No. 253 |
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| | II |
| | * I |
| | { l 1 |
| | 1 |
| | |
| | 1600 BROWNS FERRY UNIT 2 1500 1400 1300 1200 o 1100 |
| | ~1000 O |
| | I g coo 0 |
| | CC g 800 z 7oo 600 C |
| | D N 600 400 300 200 100 0 60 100 160 200 250 300 360 400 MINIMUMREACTOR VESSEL METALTEMPERATURE ('F) |
| | |
| | RCS P/T Limits 3.4.9 |
| | /~~~7- ~lc H Q~RP~S HEem i I+K-. Im/ L OMz~+ Qgg 1600 FERRY Curve No. 1 15M U 3 Minimum temperature for pressure tests such as 14M required by Section XI. |
| | ZZ> 1300 Curve No. 2 D 1200 Minimum temperature for mechanical heatup or 1100 cooldown following nuclear 0 |
| | I-CO 1000 70'ROWNS shutdown. |
| | Li 900 Curve No. 3 Minimum temperature for iL'- |
| | 800 core operation (criticality). |
| | O 700 IL'00 Notes I- These curves include sufficient margin to provide 500 protection against ILJ feedwater nozzle 400 degradation. The curves C0 312 PS allow for shifts in RTNOT of 3OO the Reactor vessel beltline materials, in accordance 200 CURVES 1, 2, K 3 ARE VAUD FOR with Reg. Guide 1.99 E Y OF OPERATION Rev. 2 to compensate for 100 BOL radiation embrittlement for FPY. |
| | 0 50 100 150 200 250 300 350 400 MIMMUMREAGTQRYESSEL MEl'ALTEMPERATURE('Fi Figure 3.4.9-1 Pressure/Temperature Limits BFN-UNIT 3 3.4-29 Amendment No. 212 |
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| | II I |
| | / |
| | I |
| | |
| | 1600 BROWNS FERRY UNIT 3 1500 1400 1300 1200 o 1<<0 O 1000 g |
| | W 900 OC g 800 O |
| | 700 I |
| | 600 D |
| | i cn 600 400 300 200 100 0 60 100 150 200 260 300 350 400 MINIMUMREACTOR VESSEL METALTEMPERATURE (4F) |
| | |
| | I' ENCLOSURE 4 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN) |
| | Units 2, and 3 PROPOSED IMPROVED I II I TECHN CAL SPEC F CAT ON CHANGE TS 393 I SUPPLEMENT 1 REVISED PAGES I. AFFECTED PAGE LIST Unit 2 Page 3.4-29 Unit 3 Page 3.4-29 II. REVISED PAGES See attached. |
| | |
| ~, | | ~, |
| RCS P/T Limits 3.4.9 1600 1500 1400 1300 1200 1100 1000 900 soo 700 C 600 500 P 4oo 300 312 PSI BROWNS FERRY UNIT 2 1 2 3 Curve No.1 Minimum temperature for pressure tests such as required by Section XI.Curve No.2 Minimum temperature for mechanical heatup or cooldown following nuclear shutdown.Curve No.3 Minimum temperature for core operation (criticality). | | RCS P/T Limits 3.4.9 1600 Curve No. 1 BROWNS FERRY UNIT 2 Minimum temperature for pressure 1500 tests such as required by Section 1 2 3 XI. |
| Notes These curves include sufficient margin to provide protection against feedwater nozzle degradation. | | 1400 Curve No. 2 Minimum temperature for 1300 mechanical heatup or cooldown following nuclear shutdown. |
| The curves allow for shifts in RTrior of the Reactor vessel beltline materials, in accordance with Reg.Guide 1.99, Rev.2, to compensate for radiation embrittlement for 16 EFPY.200 100 BOLTUP 82'F CURVES1,2,&3ARE VALID FOR 16 EFPY OF OPERATION 0 50 100 150 200 250 300 350 400 Minimum Reactor Vessel Metal Temperature | | 1200 Curve No. 3 1100 Minimum temperature for core operation (criticality). |
| ('F)Figure 3.4.9-1 Pressure/Temperature Limits BFN-UNIT 2 3.4-29 | | 1000 Notes 900 These curves include sufficient margin to provide protection against feedwater nozzle soo degradation. The curves allow for shifts in RTrior of the Reactor 700 vessel beltline materials, in C accordance with Reg. Guide 1.99, 600 Rev. 2, to compensate for radiation embrittlement for 16 500 EFPY. |
| | P 4oo 312 PSI 300 200 CURVES1,2, & 3ARE 100 BOLTUP VALIDFOR 16 EFPY OF 82'F OPERATION 0 50 100 150 200 250 300 350 400 Minimum Reactor Vessel Metal Temperature ('F) |
| | Figure 3.4.9-1 Pressure/Temperature Limits BFN-UNIT 2 3.4-29 |
| | |
| | RCS P/T Limits 3.4.9 1600 Curve No. 1 BROWNS FERRY UNIT 3 Minimum temperature for pressure 1500 1 2 3 tests such as required by Section XI. |
| | 1400 Curve No. 2 1300 Minimum temperature for mechanical heatup or coo!down following nuclear shutdown. |
| | 1200 Curve No. 3 1100 Minimum temperature for core operation (criticality). |
| | 4i 1000 Notes 0 |
| | 600 These curves include sufficient margin to provide protection against feedwater nozzle 800 degradation. The curves allow for shifts in RTNpT of the Reactor 700 vessel beltiine materials, in accordance with Reg. Guide 1.99, 600 Rev. 2, to compensate for radiation embrittlement for 20 EFPY. |
| | g 500 o |
| | 400 312 PS 300 200 CURVES 1,2, & 3ARE 6OLTUP VALIDFOR 20 EFPY OF 100 OPERATION 70'F 0 50 100 150 200 250 300 350 400 Minimum Reactor Vessel Metal Temperature ('FI Figure 3.4.9-1 Pressure/Temperature Limits BFN-UNIT 3 3.4-29 Amendment No. 212 |
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| RCS P/T Limits 3.4.9 1600 1500 1400 1300 1200 1100 4i 1000 0 600 800 700 600 g 500 o 400 300 312 PS BROWNS FERRY UNIT 3 1 2 3 Curve No.1 Minimum temperature for pressure tests such as required by Section XI.Curve No.2 Minimum temperature for mechanical heatup or coo!down following nuclear shutdown.Curve No.3 Minimum temperature for core operation (criticality).
| | 0 0}} |
| Notes These curves include sufficient margin to provide protection against feedwater nozzle degradation.
| |
| The curves allow for shifts in RTNpT of the Reactor vessel beltiine materials, in accordance with Reg.Guide 1.99, Rev.2, to compensate for radiation embrittlement for 20 EFPY.200 100 6OLTUP 70'F CURVES 1,2,&3ARE VALID FOR 20 EFPY OF OPERATION 0 50 100 150 200 250 300 350 400 Minimum Reactor Vessel Metal Temperature
| |
| ('FI Figure 3.4.9-1 Pressure/Temperature Limits BFN-UNIT 3 3.4-29 Amendment No.212 0 0}}
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML18039A8811999-09-28028 September 1999 Proposed Tech Specs Re Increased MSIV Leakage Rate Limits & Exemption from 10CFR50,App J ML18039A8241999-07-28028 July 1999 Proposed Tech Specs Providing TS for Operation of Oscillation PRM Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A8001999-06-0303 June 1999 Proposed Tech Specs,Reducing Allowable Value Used for Reactor Vessel Water Level - Low,Level 3 for Several Instrument Functions ML18039A6991999-02-22022 February 1999 Proposed Tech Specs & Bases Pages Incorporating NRC Approved TS Change 354,requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation ML18039A6601998-12-15015 December 1998 Proposed Tech Specs,Revising pressure-temp Curves to Extend Validity of Curves to 32 EFPY ML18039A5041998-09-0808 September 1998 Proposed Tech Specs Providing TS for Operation of Oscillation Power Range Monitor Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A5001998-09-0404 September 1998 Proposed Tech Specs Re Use of Containment Overpressure for ECCS Pump Net Positive Suction Head Analyses ML18039A4791998-08-14014 August 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-33, DPR-52 & DPR-68 to Change Ts.Proposed Changes Decrease Frequency of once-per-cycle Instrument Calibrations by Substituting 24 Months for 18 Months ML18039A4611998-07-31031 July 1998 Proposed Tech Specs B 3.6-2,B 3.6-7 & B 3 3.7-2 for Power Uprate Operation Omitted Pages ML18039A4481998-07-17017 July 1998 Proposed Tech Specs,Adding LCO 3.4.10 & Accompanying TS Bases Provisions from Improved TS-362 Conversion Package as Adapted for Power Uprate Conditions ML18039A4091998-06-26026 June 1998 Proposed Tech Specs Section 3.4,allowing Units 2 & 3 to Operate at Uprated Power Level of 3458 Mwt ML18039A4021998-06-19019 June 1998 Proposed Tech Specs (TS) Converting from Existing Custom TS to Improved TS ML18039A3921998-06-12012 June 1998 Proposed Tech Specs Change 390,decreasing Frequency of once-per-cycle SRs by Substituting 24 Months for 18 Months in Affected TS SRs ML20249A5661998-06-10010 June 1998 Proposed Tech Specs Section 5.0,revising Administrative Controls ML20248C5151998-05-27027 May 1998 Proposed Tech Specs Section 3.8.1,revising AC Sources- Operating ML18039A3181998-04-16016 April 1998 Proposed Rev 2 to Tech Specs Section 3.6, Containment Systems, Converting from Current TS to Improved TS ML18039A2711998-03-16016 March 1998 Proposed Tech Specs Re Power Uprate Operation ML18039A2671998-03-13013 March 1998 Proposed Tech Specs,Converting to Improved Std Ts,Per NUREG- 1433,rev 1, Std TS for GE BWRs (BWR/4). ML18039A2641998-03-12012 March 1998 Proposed Tech Specs ITS Section 3.8 Re Electrical Power Sys. ML18039A2611998-03-0303 March 1998 Proposed Tech Spec Changes TS 393 Re Reactor Vessel Pressure Temperature Curves ML20199E8051998-01-23023 January 1998 Proposed Tech Specs Section 5.0 Re Administrative Controls ML18039A2221997-12-30030 December 1997 Proposed Tech Specs Re RHR SW Pumps Required for multi-unit Operation & Cold Shutdown ML18039A2151997-12-23023 December 1997 Proposed Tech Specs Section 3.7 Re Plant Sys ML18039A2181997-12-22022 December 1997 Proposed Tech Specs Section 3.8 Re Electrical Power Sys ML18039A2101997-12-0404 December 1997 Proposed Tech Specs Pages Re TS Change 362,suppl 7 Re ITS Section 3.1, Reactivity Control Sys. ML18039A2071997-12-0404 December 1997 Proposed Tech Specs Pages Re Suppl 9 to TS Change 362, Including Rev Pages to Improved TS Section 3.5 ML18039A2011997-12-0303 December 1997 Proposed Tech Specs Section 3.9 Re Refueling Operations & Section 3.10, Special Operations. ML18039A1981997-12-0303 December 1997 Improved Tech Specs Pages Re Section 5, Administrative Controls. ML20199D5471997-11-14014 November 1997 Proposed Tech Specs Section 3.0, Limiting Condition for Operation (LCO) Operability & Section 4.0, Design Changes ML20199E1361997-11-14014 November 1997 Proposed Tech Specs Section 3.4 Re Reactor Coolant Sys ML20198Q4521997-11-0505 November 1997 Proposed Tech Specs,Incorporating Improved TS (ITS) Bases Revs & Changes to Supporting Documentation Resulting from Responding to NRC Questions ML18038B9611997-10-0101 October 1997 Proposed Tech Specs,Allowing Bfn,Units 2 & 3,to Operate at Uprated Power Level of 3458 Mwt ML18038B9361997-08-15015 August 1997 Proposed Tech Specs,Extending Existing 7-day EDG Allowed Outage Time to Fourteen Days ML18038B9061997-06-19019 June 1997 Proposed Tech Specs Supporting one-time 14-day Limiting Condition for Operation for Each EDG to Accommodate Pending Vendor Recommended Maint Activities ML20138J3781997-05-0101 May 1997 Proposed Tech Specs,Revising TS-362 Amend for Section 3.8, Electrical Power Sys Which Addresses NRC Review Comments ML18038B8651997-04-24024 April 1997 Proposed Tech Specs,Submitting Revised BFN TS Bases Section 3.5.N, References, Reflecting Updated LOCA Analyses for Units 2 & 3 ML20137U1691997-04-11011 April 1997 Proposed Tech Specs Re Pr Neutron Monitor Upgrade W/ Implementation of Average Pr Monitor & Rod Block Monitor TS (ARTS) Improvements & Max Extended Load Line Limit Analyses ML18038B8341997-03-12012 March 1997 Proposed Tech Specs Re Extended EDG Allowed Outage Time ML20136F7851997-03-0606 March 1997 Proposed TS Supporting Planned Replacement of Current Power Range Monitoring Portion of Existing Nms W/Ge Digital Nuclear Measurement Analysis & Control Power Range Neutron Monitor Retrofit Design ML20134G5401997-02-0505 February 1997 Proposed Tech Specs Revising Bases Section 3.7.A/4.7.A, Primary Containment, to Delete Wording Re Maintaining Drywell to Suppression Chamber Differential Pressure Constant for Duration of Drywell to Suppression Chamber ML20132B7401996-12-11011 December 1996 Proposed Tech Specs 2.2.A Re Safety/Relief Valve Setpoint Requirements for Reactor Coolant Sys Integrity ML20117P3341996-09-15015 September 1996 Proposed Tech Specs to Change Unit 3 TS LCO 3.6.F.1 in Order to Perform Repairs & Maint Necessary to Return RCS Recirculation Loop a to Operations ML18038B7541996-09-0606 September 1996 Proposed Conversion from Current TSs to Improved STS Consistent w/NUREG-1433,rev 1 ML20117G7121996-08-30030 August 1996 Proposed Tech Specs Re License Condition on Compliance W/Thermal Water Quality Stds ML20113B1951996-06-21021 June 1996 Proposed Tech Specs,Revising Change in SLMCPR & Bases Description of RHR Suppl Fuel Pool Cooling Mode ML20112G3891996-06-0606 June 1996 Proposed Tech Specs,Revising Section 6, Administrative Controls, to Be More Closely Aligned W/Requirements of Improved Std TSs ML20117H5231996-05-20020 May 1996 Proposed Tech Specs Implementing Guidance of GL 87-09 & NUREG-1433,Rev 1 ML20108D9021996-05-0303 May 1996 Proposed Tech Specs,Withdrawing Amend 219,temporary TS 343T, Rv Water Level Instrumentation & Amend 228,temporary TS 347T,250 Volt DC Control Power Supply Sys AOT for Unit 2 ML20107F9721996-04-14014 April 1996 Proposed Tech Specs,Revising Minimum Required Number of Operable Rv Water Level Trip Sys During Period That RCS Instrument Line Excess Flow Check Valve Surveillance Tests Being Performed ML20096C4401996-01-10010 January 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B,Performance Based Testing 1999-09-28
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18039A8811999-09-28028 September 1999 Proposed Tech Specs Re Increased MSIV Leakage Rate Limits & Exemption from 10CFR50,App J ML18039A8241999-07-28028 July 1999 Proposed Tech Specs Providing TS for Operation of Oscillation PRM Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A8001999-06-0303 June 1999 Proposed Tech Specs,Reducing Allowable Value Used for Reactor Vessel Water Level - Low,Level 3 for Several Instrument Functions ML18039A6991999-02-22022 February 1999 Proposed Tech Specs & Bases Pages Incorporating NRC Approved TS Change 354,requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation ML18039A6601998-12-15015 December 1998 Proposed Tech Specs,Revising pressure-temp Curves to Extend Validity of Curves to 32 EFPY ML20206F8131998-12-0303 December 1998 Rev 12 to ODCM, for BFN ML18039A5041998-09-0808 September 1998 Proposed Tech Specs Providing TS for Operation of Oscillation Power Range Monitor Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A5001998-09-0404 September 1998 Proposed Tech Specs Re Use of Containment Overpressure for ECCS Pump Net Positive Suction Head Analyses ML18039A4791998-08-14014 August 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-33, DPR-52 & DPR-68 to Change Ts.Proposed Changes Decrease Frequency of once-per-cycle Instrument Calibrations by Substituting 24 Months for 18 Months ML18039A4611998-07-31031 July 1998 Proposed Tech Specs B 3.6-2,B 3.6-7 & B 3 3.7-2 for Power Uprate Operation Omitted Pages ML18039A4481998-07-17017 July 1998 Proposed Tech Specs,Adding LCO 3.4.10 & Accompanying TS Bases Provisions from Improved TS-362 Conversion Package as Adapted for Power Uprate Conditions ML18039A4091998-06-26026 June 1998 Proposed Tech Specs Section 3.4,allowing Units 2 & 3 to Operate at Uprated Power Level of 3458 Mwt ML18039A4021998-06-19019 June 1998 Proposed Tech Specs (TS) Converting from Existing Custom TS to Improved TS ML18039A3921998-06-12012 June 1998 Proposed Tech Specs Change 390,decreasing Frequency of once-per-cycle SRs by Substituting 24 Months for 18 Months in Affected TS SRs ML20249A5661998-06-10010 June 1998 Proposed Tech Specs Section 5.0,revising Administrative Controls ML20248C5151998-05-27027 May 1998 Proposed Tech Specs Section 3.8.1,revising AC Sources- Operating ML18039A3181998-04-16016 April 1998 Proposed Rev 2 to Tech Specs Section 3.6, Containment Systems, Converting from Current TS to Improved TS ML18039A2711998-03-16016 March 1998 Proposed Tech Specs Re Power Uprate Operation ML18039A2671998-03-13013 March 1998 Proposed Tech Specs,Converting to Improved Std Ts,Per NUREG- 1433,rev 1, Std TS for GE BWRs (BWR/4). ML18039A2641998-03-12012 March 1998 Proposed Tech Specs ITS Section 3.8 Re Electrical Power Sys. ML18039A2611998-03-0303 March 1998 Proposed Tech Spec Changes TS 393 Re Reactor Vessel Pressure Temperature Curves ML20199E8051998-01-23023 January 1998 Proposed Tech Specs Section 5.0 Re Administrative Controls ML18039A2401998-01-15015 January 1998 Bfnp Unit 2 Cycle 10 Power Ascension Test Program Start-Up Rept, for Period 970929-1105 ML18039A2221997-12-30030 December 1997 Proposed Tech Specs Re RHR SW Pumps Required for multi-unit Operation & Cold Shutdown ML18039A2151997-12-23023 December 1997 Proposed Tech Specs Section 3.7 Re Plant Sys ML18039A2181997-12-22022 December 1997 Proposed Tech Specs Section 3.8 Re Electrical Power Sys ML20217P5051997-12-0808 December 1997 Rev 10 to ODCM, Containing Markups to Rev 9 & 10 ML18039A2101997-12-0404 December 1997 Proposed Tech Specs Pages Re TS Change 362,suppl 7 Re ITS Section 3.1, Reactivity Control Sys. ML18039A2071997-12-0404 December 1997 Proposed Tech Specs Pages Re Suppl 9 to TS Change 362, Including Rev Pages to Improved TS Section 3.5 ML18039A2011997-12-0303 December 1997 Proposed Tech Specs Section 3.9 Re Refueling Operations & Section 3.10, Special Operations. ML18039A1981997-12-0303 December 1997 Improved Tech Specs Pages Re Section 5, Administrative Controls. ML20199D5471997-11-14014 November 1997 Proposed Tech Specs Section 3.0, Limiting Condition for Operation (LCO) Operability & Section 4.0, Design Changes ML20199E1361997-11-14014 November 1997 Proposed Tech Specs Section 3.4 Re Reactor Coolant Sys ML20198Q4521997-11-0505 November 1997 Proposed Tech Specs,Incorporating Improved TS (ITS) Bases Revs & Changes to Supporting Documentation Resulting from Responding to NRC Questions ML18038B9611997-10-0101 October 1997 Proposed Tech Specs,Allowing Bfn,Units 2 & 3,to Operate at Uprated Power Level of 3458 Mwt ML18038B9361997-08-15015 August 1997 Proposed Tech Specs,Extending Existing 7-day EDG Allowed Outage Time to Fourteen Days ML20210V1171997-07-29029 July 1997 Qualification Plan & Rept MIL-STD-462D,CS114,Conducted Susceptibility,Bulk Cable Injection Numac Reactor Bldg Vents Radiation Monitor TVA Bfn,Units 1,2 & 3 ML18038B9061997-06-19019 June 1997 Proposed Tech Specs Supporting one-time 14-day Limiting Condition for Operation for Each EDG to Accommodate Pending Vendor Recommended Maint Activities ML20138J3781997-05-0101 May 1997 Proposed Tech Specs,Revising TS-362 Amend for Section 3.8, Electrical Power Sys Which Addresses NRC Review Comments ML18038B8651997-04-24024 April 1997 Proposed Tech Specs,Submitting Revised BFN TS Bases Section 3.5.N, References, Reflecting Updated LOCA Analyses for Units 2 & 3 ML20137U1691997-04-11011 April 1997 Proposed Tech Specs Re Pr Neutron Monitor Upgrade W/ Implementation of Average Pr Monitor & Rod Block Monitor TS (ARTS) Improvements & Max Extended Load Line Limit Analyses ML18038B8341997-03-12012 March 1997 Proposed Tech Specs Re Extended EDG Allowed Outage Time ML20136F7851997-03-0606 March 1997 Proposed TS Supporting Planned Replacement of Current Power Range Monitoring Portion of Existing Nms W/Ge Digital Nuclear Measurement Analysis & Control Power Range Neutron Monitor Retrofit Design ML20134G5401997-02-0505 February 1997 Proposed Tech Specs Revising Bases Section 3.7.A/4.7.A, Primary Containment, to Delete Wording Re Maintaining Drywell to Suppression Chamber Differential Pressure Constant for Duration of Drywell to Suppression Chamber ML18038B8281997-01-31031 January 1997 Rev 1 to GE-NE-B13-01805-22, Internal Core Spray Line Flaw Evaluation Handbook for Browns Ferry Units 2 & 3. ML18038B8111997-01-22022 January 1997 Rev 0 to Browns Ferry Nuclear Plant,Surveillance Instruction,Inservice Insp Program,Unit 3. ML20132B7401996-12-11011 December 1996 Proposed Tech Specs 2.2.A Re Safety/Relief Valve Setpoint Requirements for Reactor Coolant Sys Integrity ML20117P3341996-09-15015 September 1996 Proposed Tech Specs to Change Unit 3 TS LCO 3.6.F.1 in Order to Perform Repairs & Maint Necessary to Return RCS Recirculation Loop a to Operations ML18038B7541996-09-0606 September 1996 Proposed Conversion from Current TSs to Improved STS Consistent w/NUREG-1433,rev 1 ML20117G7121996-08-30030 August 1996 Proposed Tech Specs Re License Condition on Compliance W/Thermal Water Quality Stds 1999-09-28
[Table view] |
Text
ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
Units 2 and 3 PROPOSED IMPROVED TECHNICAL SPECI FICATION CHANGE TS 393 I SUPPLEMENT 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION MARKED PAGE S I. AFFECTED PAGE LIST Unit 2 Page 3.4-29 Unit 3 Page 3.4-29 II. REVISED PAGES See attached.
98i2240i64 98i2i5 ~I PDR ADOCK 05000260 P PDR j
RCS P/T Limits 3.4.9 I=/a~
] l-/K /-0/MMMM@ PAg~
1600 BROWNS FERRY Curve No 1 1500 U Minimum temperature for pressure tests such as required by Section XI.
1300 Curve No 2 c3 1200 Minimum temperature for mechanical heatup or 1100 cooldowh following nuclear shutdown.
1000
~
wsoo Curve No. 3 Minimum temperature for 500 core operation '(criticality).
I-O 700 Notes 800 These curves include sufficient margin to provide 500 protection against feedwater nozzle degradation. The curves 312 PSIG allow for shifts in RTNOT of 3OO the Reactor vessel beltline materials, in accordance 200 CURVES 1,2, 8 3 ARE VAUD FOR with Reg. Guide 1.99 FPY OF OPERATION Rev. 2 to compensate for 100 radiation embrittlement for 0
FPY.
0 50 100 150 200 250 300 350 400 MIQMUM REACTORVESSEL MEfALTEMPERATURE('F)
Figure 3.4.9-1 Pressure/Temperature Limits BFN-UNIT2 3.4-29 Amendment No. 253
II
{ l 1
1
1600 BROWNS FERRY UNIT 2 1500 1400 1300 1200 o 1100
~1000 O
I g coo 0
CC g 800 z 7oo 600 C
D N 600 400 300 200 100 0 60 100 160 200 250 300 360 400 MINIMUMREACTOR VESSEL METALTEMPERATURE ('F)
RCS P/T Limits 3.4.9
/~~~7- ~lc H Q~RP~S HEem i I+K-. Im/ L OMz~+ Qgg 1600 FERRY Curve No. 1 15M U 3 Minimum temperature for pressure tests such as 14M required by Section XI.
ZZ> 1300 Curve No. 2 D 1200 Minimum temperature for mechanical heatup or 1100 cooldown following nuclear 0
I-CO 1000 70'ROWNS shutdown.
Li 900 Curve No. 3 Minimum temperature for iL'-
800 core operation (criticality).
O 700 IL'00 Notes I- These curves include sufficient margin to provide 500 protection against ILJ feedwater nozzle 400 degradation. The curves C0 312 PS allow for shifts in RTNOT of 3OO the Reactor vessel beltline materials, in accordance 200 CURVES 1, 2, K 3 ARE VAUD FOR with Reg. Guide 1.99 E Y OF OPERATION Rev. 2 to compensate for 100 BOL radiation embrittlement for FPY.
0 50 100 150 200 250 300 350 400 MIMMUMREAGTQRYESSEL MEl'ALTEMPERATURE('Fi Figure 3.4.9-1 Pressure/Temperature Limits BFN-UNIT 3 3.4-29 Amendment No. 212
II I
/
I
1600 BROWNS FERRY UNIT 3 1500 1400 1300 1200 o 1<<0 O 1000 g
W 900 OC g 800 O
700 I
600 D
i cn 600 400 300 200 100 0 60 100 150 200 260 300 350 400 MINIMUMREACTOR VESSEL METALTEMPERATURE (4F)
I' ENCLOSURE 4 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
Units 2, and 3 PROPOSED IMPROVED I II I TECHN CAL SPEC F CAT ON CHANGE TS 393 I SUPPLEMENT 1 REVISED PAGES I. AFFECTED PAGE LIST Unit 2 Page 3.4-29 Unit 3 Page 3.4-29 II. REVISED PAGES See attached.
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RCS P/T Limits 3.4.9 1600 Curve No. 1 BROWNS FERRY UNIT 2 Minimum temperature for pressure 1500 tests such as required by Section 1 2 3 XI.
1400 Curve No. 2 Minimum temperature for 1300 mechanical heatup or cooldown following nuclear shutdown.
1200 Curve No. 3 1100 Minimum temperature for core operation (criticality).
1000 Notes 900 These curves include sufficient margin to provide protection against feedwater nozzle soo degradation. The curves allow for shifts in RTrior of the Reactor 700 vessel beltline materials, in C accordance with Reg. Guide 1.99, 600 Rev. 2, to compensate for radiation embrittlement for 16 500 EFPY.
P 4oo 312 PSI 300 200 CURVES1,2, & 3ARE 100 BOLTUP VALIDFOR 16 EFPY OF 82'F OPERATION 0 50 100 150 200 250 300 350 400 Minimum Reactor Vessel Metal Temperature ('F)
Figure 3.4.9-1 Pressure/Temperature Limits BFN-UNIT 2 3.4-29
RCS P/T Limits 3.4.9 1600 Curve No. 1 BROWNS FERRY UNIT 3 Minimum temperature for pressure 1500 1 2 3 tests such as required by Section XI.
1400 Curve No. 2 1300 Minimum temperature for mechanical heatup or coo!down following nuclear shutdown.
1200 Curve No. 3 1100 Minimum temperature for core operation (criticality).
4i 1000 Notes 0
600 These curves include sufficient margin to provide protection against feedwater nozzle 800 degradation. The curves allow for shifts in RTNpT of the Reactor 700 vessel beltiine materials, in accordance with Reg. Guide 1.99, 600 Rev. 2, to compensate for radiation embrittlement for 20 EFPY.
g 500 o
400 312 PS 300 200 CURVES 1,2, & 3ARE 6OLTUP VALIDFOR 20 EFPY OF 100 OPERATION 70'F 0 50 100 150 200 250 300 350 400 Minimum Reactor Vessel Metal Temperature ('FI Figure 3.4.9-1 Pressure/Temperature Limits BFN-UNIT 3 3.4-29 Amendment No. 212
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