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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] Category:TEST REPORT
MONTHYEARML18039A2401998-01-15015 January 1998 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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Text
SUMMARY
REPORT REFUELING TEST PROGRAM BROWNS FERRY NUCLEAR PLA'!T UNIT 2 - CYCLE 3 ABSTRACT The second Browns Ferry Nuclear Plant Unit 2 refueling outage was conducted frcm April 27, 1979, through June 1, 1979. This report summ rizes those refueling tests performed at the conclusion of the outage as a result of commitments made by the TVA to the NRC.
I. INTRODUCTION On April 27, 1979, Browns Ferry Nuclear Plant Unit 2 was removed from service for its second refueling outage. During this outage 268 fuel a~ssemblies (7x7 design) were replaced by new assemblies (36 of 8x8 design and 232 of 8x8R design). Five strings of power range incore detectors were also replaced.
The startup tests identified in the Final Safety Analysis Repcrt (FSAR) were addressed, and those which involve areas which were affected by the outage and its activities were included in the refueling test program. The refueling test instructions were prepared by the Results Supervisor, reviewed and recoc= ended for approval by the Plant Operations Review Committee (PORC), and finally approved by the Plant Superintendent.
The Master Refueling Instruction (MRTI) coordinated and documented .
all test activities from fuel loading to the completion of the program.
This instruction provided guidance for the sequence of events, and control points for satisfactory test completion and review before power ascension. (,
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I. INTRODUCTION (Continued)
The successful implementation of this testing program ensures that the Unit 2 refueling cutage has created no conditions or system characteristics which could adversely affect the safe operation of the plant.
Test documents and data referenced in this report are filed at the plant and are available for inspection upon request.
Test sum = aries are provided only for those tests to which TVA was co=mitted by technical specifications or by our letter to Mr. Themas A.
Ippolito dated May 16, 1979.
II. REFUELING TEST
SUMMARY
- 1. Fuel Loading RTI-3 Incore shuffling of fuel began on Pay 4, 1979, and was completed on May 15, 1979. Core verification via video tape recording revealed that all fuel assemblies were in the proper location, but that 16 assemblies were misoriented and 2 were not properly seated. These ite=s were corrected and reverification perf ormed as required.
- 2. Full Core Shutdown Marain RTI-4 The full core shutdown margin was determined during the reactor criticality following the outage. The shutdown margin determination was in acceptable agreement with the predicted value of 1.26% calculated by General Electric. The actual shutdown margin was 1.953% ak/k compared ,
to the technical specification minimum required value of C.33% ak/k.
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L II. REFUELING TEST S T!ARY (Continued)
- 3. . Control Rod Drive System RTI-5 The following control rod drive (CRD) system tests were performed before and/or after completion of fuel loading:
- a. A functional test of each CRD to check rod position indication, rod-to-drive coupling, and insert / withdraw speed. .
- b. A continuous-in friction test of each CRD to check for drive line friction.
In addition, all Unit 2 control rods were scram timed at rated vessel pressure. All criteria were satisfied.
- 4. Core Pcwer Distribution RTI-18 Acceptable TIP uncertainty was verified by comparing symmetric TIP pairs. The total uncertainty was found to be less than the 9~. criterion.
Cross TIP signal symmetry comparisons 'etween symmetric TIP pairs verified that no deviatiota exceeded the 257. criteria.
- 5. Core Performance and Process Computer Core performance parameters were monitored throughout the startup program. Proper operation of the process computer was verified by comi .ing results with the offline computer calculations at power levels of 25% and 98%. In each case there was good agreement between the two methods. All observed core performance parameters were within the required limits, a
Ill. CCNCLUSION All refueling test items to which TVA was com.,itted have been satisfactorily completed.
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