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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
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ENCLOSURE 1 BROVNS FERRY NUCLEAR PLANT REVISED TECHNICAL SPECIFICATION PAGES TECHNICAL SPECIFICATION NO.264 UNIT 2~~>>2SOIS2 Se>222 PDR ADOCK 05000260 PDC 4.1 REACTOR PROTECTION SYSTEM LIMITING CONDITIONS FOR OPERATION 3.1.B.(Cont'd)SURVEILLANCE REQUIREMENTS 4.1.B.;(Cont'd)2.With both RPS electric power monitoring channels for an inservice RPS'MG set or alternate power supply inoperable, restore at least one to OPERABLE status within 30 minutes or remove the associated RPS MG set or alternate power supply from service.2.At least once per 18 months by demonstrating the OPERABILITY of overvoltage, undervoltage and underfrequency protective instrumentation by simulated automatic logic actuation and verification of the circuit protector trip level setting as follows.(a)overvoltage (all device)g 126.5 VAC (b)undervoltage (MG Set)2.113.4 VAC (c)undervoltage (alt.supply)g 111.8 VAC (d)underfrequency (all devices)g'57.0 Hz BFN Unit 2 3.1/4.1-2
t ENCLOSURE 2 DESCRIPTION AND JUSTIFICATION BROWNS FERRY NUCLEAR PLANT (BFN)REASON FOR CHANGE In June 1978, during a review of the Hatch Unit 2 operating license, NRC questioned the adequacy of the Reactor Protective System (RPS)class 1E components against.possible overvoltage or undervoltage conditions from the non-class lE RPS power supplies.In applying single failure criteria, it was postulated that during a seismic event a non-class 1E Motor Generator (MG)voltage regulator could fail in a manner that would allow the MG output voltage to remain outside the voltage rating of the class lE RPS components.
Such an abnormal voltage could go undetected and if persisting for a'ufficient time, could result in damage to RPS components with the potential loss of c"p'ability to scram the plant.Subsequently, NRC informed each, utility with similar MG power supplies (Browns Ferry Plant was one of these)to implement interim surveillance procedures on the RPS, to log RPS voltage each shift, and to conduct additional RPS functional tests every six months, after detection of RPS bus voltage outside its designed range or after an operating basis earthquake.
NRC further required these utilities to install class 1E circuit protectors on the RPS power supplies to isolate the RPS bus upon detection of adverse RPS voltage.NRC also required that Limiting Conditions For Operation (LCOs), surveillance requirements and setpoints be developed for these circuit protectors and that they be included in the techni'cal specifications.
In response to the above NRC directive, BFN implemented the interim RPS surveillance requirements.
In March 1981, BFN implemented a design change which would install RPS power monitoring syeeem circuit protectors.
In TVA letter dated August 9, 1984, TVA committed to amend the technical specifications to reflect surveillance requirements for the RPS power monitoring system.DESCRIPTION AND JUSTIFICATION FOR THE CHANGE The new calibration surveillance requirements specified below provide additional assurance that the RPS components are being operated within their design voltage and frequency limits.'4.1.B.2 ADD THE FOLLOWING SURVEILLANCE: "At least once per 18 months by demonstrating the OPERABILITY of overvoltage, undervoltage, and underfrequency protective instrumentation by simulated automatic logic actuation and verification of the circuit protector trip level setting as follows: (a)overvoltage (all device)g 126.5 Vac (b)undervoltage (MG Set)>113.4 Vac (c)undervoltage (alt.supply)>111.8 Vac (d)underfrequency (all devices)57.0 Hz" Page 2 of 2 JUSTIFICATION
~The main function of the RPS is to automatically initiate a reactor scram in a timely manner in order to 1)preserve the, integrity of the fuel cladding, 2)preserve the integrity of the nuclear system=process barrier, and 3)limit the uncontrolled release of radioactive material following an accident.In order'o assure that the appropriate class lE RPS equipment is adequately protected from an overvoltage, undervoltage, or underfrequency condition resulting from a non-class lE system powered from the same MG,set, BFN implemented a-modification.
This modification, provides two redundant, class 1E, seismic category 1 power monitoring systems on the output of each RPS MG set and the alternate power supply transformer.
Each device, upon detection of one of the above mentioned.
conditions trips to open power contactors which isolate the class 1E RPS bus from the non-class 1E RPS power supply.The RPS components are rated at 115 g 10%Vac and 60+0/,-5/Hz.The upper voltage limit of 126.5 Vac is taken from the RPS components rating of 115 Vac+10%and is established as the upper voltage technical specification trip level setting limit for both the MG sets and the alternate supply.A calculation was performed in order to obtain their minimum voltages.These values are 113.4 Vac for the MG sets and 111.8 Vac for the alternate supply.These values are based on worst case line voltage drops for the current plant configuration and include a 10/load growth margin.The underfrequency lower component rating is taken as the technical specification trip level setting.As described above, the installation of the RPS power supply monitoring circuit protector devices protects class 1E equipment.
In accordance with 10CFR50.36, BFN technical specifications for unit 2 needs to be amended to reflect the design of the plant.The added surveillance assures that the installed protective device is performing as designed therefore, assuring that the class 1E RPS components will be protected from the above mentioned~non-class 1E conditions and perform their intended safety function.,
ENCLOSURE 3 0 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION BROWNS FERRY NUCLEAR PLANT (BFN).UNIT 2'ESCRIPTION OF PRO'POSED TECHNICAL SPECIFICATION The proposed amendment would change the BFN Technical Specifications (TS)for'nit 2 to add surveillance requirement 4.1.B.2.The addition of this surveillance would demonstrate the operability of the Reactor Protection System (RPS)overvoltage, undervoltage, and underfrequency protection.
instrumentation which has recently been installed.
BASIS FOR PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION NRC has provided standards for determining whether a significant hazards consideration exists as stated in 10CFR50.92(c).
A proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not 1)involve a s gnificant increase in the probability of consequences of an accident previously evaluated, or 2)create the possibility of a new or different kind of accident from an accident previously evaluated, or 3)involve a significant reduction in a margin of safety.1.The proposed change does not involve a significant increase in the probability or consequence of any accident previously evaluated.
A modification was made to install redundant class 1E circuit protection devices between the non-class 1E RPS power supplies and the class lE RPS power supplies.These circuit protective devices consist of a contactor which will open by 1)an overvoltage relay with a trip level setting of g 126.5 Vac, 2)an undervoltage relay with a trip level setting of g 113.4 Vac for the MG sets, 3)an undervoltage relay with t'1 settin of se ng o g 111.8 Vac for alternate supply, and 4)an underfrequency relay trip level setting of g 57 Hz on all devices.The cabinets and conduits for each RPS power monitoring system are located n the control building, which is a seismic category 1 structure.
This structure will provide protection from effects of tornadoes, tornado m ssiles, and external floods.The components of each monitoring system are also seismically qualified for class 1E application as required by GDC Page 2 of 3 In order to comply with GDC 21, there are two physically independent and fully redundant circuit interrupters provided for each RPS bus, including alternate supply.This redundancy provides single failure protection in case one circuit does not function properly.This also provides sufficient reliability to ensure the RPS performs its intended safety function.The BFN Final Safety Analysis (FSAR)section 7.2.3.2 states that the power to each of the two reactor protection trip systems is supplied-, via a separate bus, by its own high-inertia, a-c motor generator set.The high inertia is provided by a flywheel.The inertia is sufficient to maintain voltage and frequency within+5%of rated values for at least 1.0 second following total loss of power to the MG set.In applying this to section 14.5'.4.4.b of the FSAR accident analysis, loss of auxiliary power assumes the RPS NG set coastdown time until loss of MG generator output voltage to be 5.0 seconds.Thus the upper and lower bounds for voltage output and time delay are identified as significant performance parameters expected from the MG set design.The RPS power monitoring system installed is designed for the NG sets to provide no time del y C e ay.onsequently, the trip level settings for the RPS power monitor must be outside the expected operating range of the MG set.For a nominal 120 Vac MG output voltage, the 5%regulation band (114 to 126 volts)is within the technical specification trip level setting of 113.4 to 126.5 Vac.This will allow the NG set to function within its intended and designed time and voltage range before the RPS power monitoring system trips.These settings support the design and function of the high-inertia MQ sets, and therefore, support the assumptions made in the BFN FSAR.Therefore, the design, trip level settings, and intended function of the RPS power monitoring system are both bounded and support the current BFN FSAR accident analysis.2.The proposed amendment will not create the possibility of a new or different kind of accident.The proposed change does not affect the operation or intended function of any currently installed safety related equipment.
If all the protective circuits in one MG set fail to open, the redundant train of RPS systems is still available to mitigate any design basis accident.The RPS power monitoring system'does not perform any specific safety function therefore, failure would, at worst case, be bounded by the current BFN Final Safety Analysis.
~0~~0 Enclosure 3 Page 3 of 3 S 3.The proposed amendment will not involve a significant reduction in a margin of safety.f.The additional surveillance requirements resulting from the subject modification, enhance to overall dependability of the RPS system.By specifying overvoltage, undervoltage, and underfrequency values ensures that the RPS power monitoring system will protect the RPS components so they can perform their intended function.This system provides no direct safety function.It provides isolation between the non-class lE RPS power supplies and the class lE power distribution buses.It functions to isolate the RPS power distribution buses upon detection of overvoltage, undervoltage, and underfrequency on the RPS power supplies thereby preventing, possible adverse operation of the class 1E RPS components outside their designed voltage and current ranges.DETERMINATION OF BASIS FOR PROPOSED NO SIGNIFICANT HAZARDS Since the application for amendment involves a proposed changed that is encompassed by the criteria for.which no significant hazards consideration exists, TVA has made a proposed determination that the application involves no significant hazards consideration.
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