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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 1 PROPOSED TECHNICAL SPECIFICATIONS REVISIONS BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 (TVA BFN TS 224) 87021 80257 870Z05
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LIST OF TABLES (Cont'd)
TABLE Title ~Pa e Na.
4.2.E Minimum Test and Calibration Frequency for Drywell Leak Detection Instrumentation . 3.2/4.2-49 4.2.F Minimum Test and Calibration Frequency for Surveillance Instrumentation . 3.2/4.2-50 4.2.G Surveillance Requirements for Control Room Isolation Instrumentation. 3.2/4.2-52 4.2.H Minimum Test and Calibration Frequency for Flood Protection Instrumentation . 3.2/4.2-53 4.2.J Seismic Monitoring Instrument Surveillance Requirements 3.2/4.2-54 3 '-1 Minimum RHRSW and EECW Pump Assignment 3.5/4.5-11 3.5.I MAPLHGR Versus Average Planar Exposure 3.5/4.5-21 3.7.A Primary Containment Isolation Valves 3.7/4.7-25 3.7.B Testable Penetrations with Double 0-Ring Seals Deleted 3.7.C Testable Penetrations with Testable Bellows. Deleted 3.7.D Air Tested Isolation Valves. Deleted 3.7.E Primary Containment Isolation Valves which Terminate below the Suppression Pool Water Level. Deleted 3.7,F Primary Containment Isolation Valves Located in Water Sealed Seismic Class 1 lines Deleted 3.7.H Testable Electrical Penetrations Deleted 4.8.A Radioactive Liquid Waste Sampling and Analysis 3.8/4.8-9 4.8.B Radioactive Gaseous Waste Sampling and Analysis. 3.8/4.8-10 4.9.A.4.C Voltage Relay Setpoints/Diesel Generator Start . 3.9/4.9-16 3.11.A Fire Protection System Hydraulic Requirements. 3.11/4.11-10 6.8.A Minimum Shift Crew Requirements. 6.0-19 Vii BFN Unit 1
4 3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.7.A. Primar Containment 4.7.A.2.g (Cont'd)
The total leakage from all penetrations and isolation valves shall not exceed 60 percent of La per 24 hours. Leakage from containment isolation valves that terminate below suppression pool water level may be excluded from the total leakage provided a sufficient fluid inventory is available to ensure the sealing function for at least 30 days at a pressure of 54.6 psig. Leakage from containment isolation valves that are in closed-loop seismic class I lines that will be water sealed during a DBA will be measured but will be excluded when computing the total leakage.
BFN 3.7/4.7-7 Unit 1
THESE PAGES HAVE BEEN DELETED BFN 3.7/4.7-32 thru 40 Unit 1
LIST OF TABLES (Cont'd)
TABLE Title ~Pa e No.
4.2.E Minimum Test and Calibration Frequency for Drywell Leak Detection Instrumentation . 3.2/4.2-49 4.2.F Minimum Test and Calibration Frequency for Surveillance Instrumentation . 3.2/4.2-50 4.2.G Surveillance Requirements for Control Room Isolation Instrumentation. 3.2/4.2-52 4.2.H Minimum Test and Calibration Frequency for Flood Protection Instrumentation . 3,2/4.2-53 4.2.J Seismic Monitoring Instrument Surveillance Requirements 3.2/4.2-54 3.5-1 Minimum RHRSW and EECW Pump Assignment . 3.5/4.5-11 3.5.I MAPLHGR Versus Average Planar Exposure , 3.5/4.5-21 3.7.A Primary Containment Isolation Valves . 3.7/4.7-25 3.7.B Testable Penetrations with Double 0-Ring Seals Deleted 3.7.C Testable Penetrations with Testable Bellows. Deleted 3.7.D Air Tested Isolation Valves. Deleted 3.7.E Primary Containment Isolation Valves which Terminate below the Suppression Pool Water Level. Deleted 3.7.F Primary Containment Isolation Valves Located in Water Sealed Seismic Class 1 lines . Deleted 3.7.H Testable Electrical Penetrations Deleted 4.8.A Radioactive Liquid Waste Sampling and Analysis 3.8/4.8-9 4.8.B Radioactive Gaseous Waste Sampling and Analysis. 3.8/4.8-10 4.9.A.4.C Voltage Relay Setpoints/Diesel Generator Start . 3.9/4.9-16 3.11.A Fire Protection System Hydraulic Requirements. 3.11/4.11-10 6,8.A Minimum Shift Crew Requirements. 6.0-19 vii BFN Unit 2
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.7.A. Primar Containment 4.7.A.2.g (Cont'd)
The total leakage from all penetrations and isolation valves shall not exceed 60 percent of La per 24 hours. Leakage from containment isolation valves that terminate below suppression. pool water level may be excluded from the total leakage provided a sufficient fluid inventory is available to ensure the sealing function for at least 30 days at a pressure of 54.6 psig. Leakage from containment isolation valves that are in closed-loop seismic class I lines that will be water sealed during a DBA will be measured but will be excluded when computing the total leakage.
BFN 3.7/4.7-7 Unit 2
THESE PAGES HAVE BEEN DELETED BFN 3.7/4.7-32 thru 40 Unit 2
TABLE Title ~Pa e No.
4.2.E Minimum Test and Calibration Frequency for Drywell Leak Detection Instrumentation . 3,2/4.2-48 4.2.F Minimum Test and Calibration Frequency for Surveillance Instrumentation . 3.2/4.2-49 4.2.G Surveillance Requirements for Control Room Isolation Instrumentation. 3.2/4.2-51 4.2.H Minimum Test and Calibration Frequency for Flood Protection Instrumentation . 3.2/4..2-52 4.2eJ Seismic Monitoring Instrument Surveillance Requirements 3 '/4.2-53 3.5-1 Minimum RHRSW and EECW Pump Assignment . 3.5/4.5-11 3.5.I MAPLHGR Versus Average Planar Exposure 3.5/4.5-21 3.7,A Primary Containment Isolation Valves 3.7/4.7-24 3.7.B Testable Penetrations with Double 0-Ring Seals Deleted Testable Penetrations with Testable Bellows. Deleted 3.7.C'.7.D Air Tested Isolation Valves. Deleted 3.7.E Primary Containment Isolation Valves which Terminate below the Suppression Pool Water Levele ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Deleted 3.7.F Primary Containment Isolation Valves Located in Water Sealed Seismic Class 1 lines Deleted 3.7.H Testable Electrical Penetrations Deleted 4.8.A Radioactive Liquid Waste Sampling and Analysis 3.8/4.8-9 4.8.B Radioactive Gaseous Waste Sampling and Analysis. 3.8/4.8-10 4.9.A.4.C Voltage Relay Setpoints/Diesel Generator Start . 3.9/4.9-15 3.11.A Fire Protection System Hydraulic Requirements. 3.11/4.11-10 6.8.A Minimum Shift Crew Requirements. 6.0-19 vii BFN Unit 3
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.7.A. Primar Containment 4.7.A.2.g (Cont'd)
The total leakage from all penetrations and isolation valves shall not exceed 60 percent of La per 24 hours. Leakage from containment isolation valves that terminate below suppression pool water level may be excluded from the total leakage provided a sufficient fluid inventory is available to ensure the sealing function for at least 30 days at a pressure of S4.6 psig. Leakage from containment isolation valves that are in closed-loop seismic class I lines that will be water sealed during a DBA will be measured but will be excluded when computing the total leakage.
BFN 3.7/4.7-7 Unit 3
THESE PAGES HAVE BEEN DELETED BFN 3.7/4.7-32 thru 40 Unit 3
ENCLOSURE 2 DESCRIPTION AND JUSTIFICATION BROWNS FERRY NUCLEAR PLANT (BFN)
Descri tion of Chan e Browns Ferry Nuclear Plant Technical Specifications for units 1, 2, and 3 are changed to delete tables 3.7.B, 3.7.C, 3.7.D, 3.7.E, 3.7.F, 3.7.G, and 3.7.H which list primary containment penetrations and valves subject to certain provisions of 10 CFR 50, Appendix J.
Reason for Chan e The deleted tables provide lists of primary containment penetrations and isolation valves. These are duplicated in the Appendix J leak rate testing program. Duplication of these detailed tables in the technical specifications creates an unnecessary administrative burden.
Justification for Chan e Browns Ferry Nuclear Plant Technical Specification 4.7.A.2 requires that the provisions of 10 CFR 50, Appendix J, be satisfied for BFN units 1, 2, and 3.
Furthermore, 10 CFR 50.54 (o) requires that all water-cooled power reactors meet the containment leakage test requirements set forth in Appendix J.
Appendix J of 10 CFR 50 defines the primary containment penetrations for -which Type B and Type C leak rate tests are required to be performed.
Lists of primary containment penetrations for which Type B tests must be performed and lists of primary containment isolation valves for which Type C tests must be performed are maintained for BFN units 1, 2, and 3 in the Appendix J program. Since the information being deleted from BFN technical specifications is contained in the Appendix J program, and since a test report listing the penetrations tested is required to be submitted for NRC review after each integrated leak rate test, no reductions in testing requirements or NRC review will result due to this change. The Standard Technical Specifications do not contain lists of primary containment penetrations for leak rate test requirements. Table 3.7.A, which lists primary containment isolation valves and their operability requirements, is being retained as in Standard Technical Specifications.
For the reason stated above, TVA has concluded that these proposed technical specification changes will not reduce the margin of nuclear safety.
t ENCLOSURE 3 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION BROMNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, AND 3 Descri tion of Amendment Re uest The proposed amendment would change the technical specification for BFN units 1, 2, and 3 by deleting five tables. Three of the deleted tables identify BFN primary containment penetration with double 0-ring seals or bellows and electrical penetration which 10 CFR 50, Appendix J, Part II.G, requires Type B local leak rate tests to be performed. The other two deleted tables identify primary containment isolation valves for which 10 CFR 50, Appendix J, Part II.H, requires Type C leak rate tests be performed and which 10 CFR 50 Appendix J, Part III.B.2 (a) and (b), require to be leak tested, not as a fluid sealed system or as a fluid sealed system, whichever is appropriate.
Basis for Pro osed No Si nificant Hazards Consideration Determination The Commission has provided standards for determining whether a significant hazards consideration exists as stated in 10 CFR 50.92(c). A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety.
- 1. The proposed amendment will not involve a significant increase in the probability or consequences of an accident previously evaluated. This deletion of tables from BFN technical specifications is an administrative change to remove lists of primary containment penetrations and valves which must be leak rate tested in accordance with 10 CFR 50, Appendix J.
There is no change in the requirements of or BFN commitment to comply with the provisions of Appendix J of 10 CFR 50 and BFN technical specification 3/4.7.A.2. The appropriate lists are maintained in the BFN Appendix J program.
- 2. The proposed amendment will not create the possibility of a new or different kind of accident from any previously analyzed since it does not eliminate or modify any requirement or commitment to comply with the provisions of 10 CFR 50, Appendix J, or BFN technical specification 3/4.7.A.2.
- 3. The margins of safety will not be reduced since the requirements of and the BFN commitment to comply with the provisions of 10 CFR 50, Appendix J, and BFN technical specification 3/4.7.A.2 remain unchanged.
Since the application for amendment involves a proposed change that is encompassed by the criteria for which no significant hazards consideration exists, TVA proposes to determine that the proposed amendment does not involve a significant hazards consideration.