ML20062L929
From kanterella
| ML20062L929 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/25/1993 |
| From: | Burr C, Metcalf M NTS/SMA, INC. |
| To: | |
| Shared Package | |
| ML18037A638 | List: |
| References | |
| 60254.04-94N-1, NUDOCS 9401050421 | |
| Download: ML20062L929 (335) | |
Similar Documents at Browns Ferry | |
|---|---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18039A8811999-09-28028 September 1999
[Table view]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 Category:TEST REPORT MONTHYEARML18039A2401998-01-15015 January 1998
[Table view]Bfnp Unit 2 Cycle 10 Power Ascension Test Program Start-Up Rept, for Period 970929-1105 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 ML18038B7261996-06-25025 June 1996 Unit 2 Cycle 9 Final Refueling Test Rept. ML20116C3701996-06-0303 June 1996 Rev 1 to Test Rept for Fourier Transform ML20100L4171995-12-22022 December 1995 Final Refueling Test Rept ML18038B5751995-12-13013 December 1995 Simulator Four Yr Test Rept. ML18038B1201995-01-25025 January 1995 Reactor Containment ILRT Browns Ferry Nuclear Plant Unit 2 Conducted 941105-07, Test Rept ML18037A6401993-12-10010 December 1993 Test Rept for Analysis of Main Control Mapping Data & Ge/ C&C Numac Lab EMI Test Data for Brown Ferry Nuclear Plant. ML20062L9201993-06-25025 June 1993 Test Rept for Analysis of EMI Main Control Room Mapping Data & GE Rbvprm EMI Testing Data for Brown Ferry Nuclear Plant ML20062L9291993-06-25025 June 1993 Test Rept for Point of Installation Electromagnetic Interference (EMI) Mapping of Control Rooms & Refuel Floor, Brown Ferry Station Units 1,2 & 3 ML18037A6621993-02-17017 February 1993 Bend Radius Corona & Load Cycle Testing 4/0 AWG,Cu.,XLPE,5 Kv Cable. ML20086C6141991-10-30030 October 1991 Cycle 6 Final Power Ascension Test Rept,910220-0806 ML20155B6831988-09-22022 September 1988 Cable Issues Supplemental Rept Cable Testing ML18032A7191988-01-25025 January 1988 Secondary Containment Leak Rate Test Performed 871026. ML20215K7181986-09-11011 September 1986 Secondary Containment Leak Rate Test,Browns Ferry Nuclear Plant, 90 Day Rept ML20147E3241986-05-14014 May 1986 Vol I of Seismic Qualification/Verification of Various Aluminum Electrical Conduit Configurations ML20147E5861986-03-31031 March 1986 Preliminary Study of Vibration Damping in Electrical Conduit ML20147E6531986-03-31031 March 1986 Experimental Investigation of Vibration Damping in Aluminum Electrical Conduit, Interim Rept ML20140F6251985-06-0707 June 1985 Secondary Containment Leak Rate Test,Browns Ferry Nuclear Plant Unit 1 ML18025B9961983-07-22022 July 1983 Recirculation Sys Testing. ML18025B8521982-03-18018 March 1982 Revision a to Qualification Test Rept for Model 1801104-05 PSA 1/4 Shock. ML18025B4791981-04-24024 April 1981 Proposed Tech Spec Sections 1.O & 1.P,clarifying Definition of Secondary Containment Integrity ML18025A8771980-05-20020 May 1980 Reactor Bldg Containment Integrated Leak Rate Test, Conducted 800220-23 ML18025B8671980-05-12012 May 1980 Qualification Test Rept for Model 1801119-11 PSA-100 Shock Arrestor. ML18025B8561980-03-18018 March 1980 Revision a to Qualification Test Rept for Model 1801102-05 PSA 1 Shock Arrestor. ML18024B3521980-02-21021 February 1980 Reactor Bldg Containment Integrated Leak Rate Test for Facility,Conducted 791121-25. ML18025B8621980-02-0707 February 1980 Revision a to Qualification Test Rept for Model 1801112-11 PSA-35 Shock Arrestor. ML18025B8601980-01-25025 January 1980 Qualification Test Rept for Model 1801103-07 PSA 10 Shock Arrestor. ML18025B8581980-01-22022 January 1980 Qualification Test Rept for Model 1801106-05 PSA-3 Shock Arrestor. ML18025B8551979-12-12012 December 1979 Qualification Test Rept for Model 1801104-07 PSA 1/2 Shock Arrestor. ML19207C3941979-09-0404 September 1979 Summary Rept of Refueling Test Program,Cycle 3,conducted During Spring 1979 Outage ML18024B0131979-08-22022 August 1979 Secondary Containment Leak Rate Test. ML19270G9321979-05-11011 May 1979 Secondary Containment Leak Rate Test,90-Day Rept. ML19274D5521979-02-0909 February 1979 Results & Analysis of 781127 Secondary Containment Leak Rate Test.Shows Secondary Containment Capability to Main 1/4 Inch Water Vacuum Under Calm Wind W/Sys in Leakage Rate of Not More That 12,000 Scfm Before Refueling ML20064E2381978-11-0707 November 1978 Reactor Bldg Containment Integrated Leak Rate Test on 780613-15.Outlines Objectives,Principal Events & Special Equip Used in the Cilrt.Concludes That Accurate Results Can Be Obtained While Significantly Reducing Test Time ML19261C1981978-09-0909 September 1978 Secondary Containment Leak Rate Test Conducted 780909 for 90-day Period.Concludes Secondary Containment Sys Is Capable of Maintaining Greater than 0.25 Inch of Water Vacuum ML20050C9711978-04-12012 April 1978 Qualification Test Rept on Eight Cable Splice Assemblies to Be Used at Browns Ferry Unit 3, Vol 1 of 1 ML20104A4741978-03-20020 March 1978 Secondary Containment Leak Rate Test Conducted 780320 for 90-day Period.Concludes Secondary Containment Sys Is Capable of Maintaining Greater than 0.25 Inch of Water Vacuum 1998-01-15 |
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