Proposed Tech Specs Replacing Functional Test Requirement for Reactor Protection Sys W/Requirement to Trip Channel Containing Failure within 1 HML18029A140 |
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Site: |
Browns Ferry ![Tennessee Valley Authority icon.png](/w/images/c/ce/Tennessee_Valley_Authority_icon.png) |
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Issue date: |
09/21/1984 |
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From: |
TENNESSEE VALLEY AUTHORITY |
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To: |
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Shared Package |
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ML18029A137 |
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References |
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TVA-BFNP-TS-200, NUDOCS 8410020248 |
Download: ML18029A140 (15) |
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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 SPECIFICATION REVISIONS BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 (TVA BFNP TS 200) 84i0020248 84092k PDR ADOCK 05000259 PDR .
PROPOSED UNIT 1 TECHNICAL SPECIFICATION REVISIONS SVltVEIILANCE kl+UIREMENTS 3.1 REACI'OR 1'ROTECTION SYSTEM 4m 1 REACTOR PROTECTION SYSTEM A licabilit A licabilit Applies to the instrumentation Applies to the surveillance and associated devices the instrumentation and asso a reactor scram. which'nitiate ciated devices which initiate reactor scram.
~ob ective ~ob ective To assure the operability of the To specify the type and frequency reactor protection system. of surveillance to be applied to the protect'ion instrumentation.
S e'cification S ecification
~ When there is fuel in the vessel, A. Instrumentation systems shall the setpoints,'inimum number of be functionally tested and trip systems, ~ and minimum number calibrated as indicated in of instrument channels that mu'st Tables'.1.A and 4.1.9 respec-
.be operable for each position of tively.
the reactor mode switch shall be as given in Table 3.1.A".
2 When it is determined that one channel is failed in the unsafe condition, that channel con-taininE the unsafe failure will be tripped within one hour.
B. Two'PS power monitoring channels for each inscrvice'PS HP sets or alternate souri c shall hc: <ipurabl e.
- l. With one RPS cle'ctric
~,- pnwer monitoring channel for inservice RPS MG set or alternate power supply inoperable, restore the inoperable channel to opcral>le status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or remove the associated RPS MG set or alternate power supply from service.
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PROPOSED UNIT 2 TECHNICAL SPECIFICATION REVISIONS LIMITING CONDITIONS FOR OPERATION. SURVEILLANCE REQUIREMENTS 3~ 1 REACTOR PROTECTION SYSTEM 4e 1 REACTOR PROTECTION SYST A licabilit e Applies to the surveillance of Applies to the instrumentation the instrumentation and and 'associated devices which associated devices which initiate a reactor scram. initiate reactor scram.
~cb ective To specify the type and
~ob 'ective frequency of suxveillance to be applied to the protection To assure the operability of instrumentation.
the reactor protection system.
S cification
'I ecification Instrumentation systems S shall be functionally v tested and calibrated's
~ A. 1 Mhen thex'e is fuel in the vessel, indicated in Tables 4.1.A the setpoints~ minimum number of and 4.1.B respectively.
trip SyStems, and minimum number ~
of instrument channels that must, B. Daily during reactor power operation be operable for each position of, at greater than or equal to 25/
the reactor mode switch shall be thermal power, the ratio of fraction as given in Table 3.1.A.
of Rated Power (FRP) to Core 1 Maximum Fraction of Limiting Power Density {CMFLPD) shall be checked and the scram and APRH Rod Block 2 Mhen it is determined that one settings given by equations in channel is failed in the unsafe specifications 2.1.A.1 and 2.1.B condition, that channel con- shall be calculated.
taining the unsafe failut e will be tripped within one hour.
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PROPOSED UNIT 3 TECHNICAL SPECIFICATION "REVISIONS
LIMITING CONDITIONS POR OPERATION. SURVEILLANCE REQUIREMENTS 3~ 1 REACTOR PROTECTION SYSTEM 1 REACTOR PROTECTION 8 STEM A licabilit cab't Applies to the surveillance of Applies to the instrumentation the instrumentation and and associated devices which associated devices which initiate a reactor scram. initiate reactor scram.
Ob ective To specify the type and
~Oh QctivQ frequency of surveillance to be applied to the protection To assure the operability of instrumentation.
the reactor protection system.
S cification ecification A Instrumentation systems S
shall be functionally tested and calibrated as A. 1 When there is fuel in the vessel,, indicated in Tables 0.1.A the setpoints, minimum number of and 0.1.B respectively.
trip systems, and minimum number ~
B. Daily during reactor power operation of instrument channels that must be operable for each position of, at greater 'than or equal to 25%
the reactor mode switch shall be thermal power, the ratio of fraction as given in Table 3.1.A. of Rated Power (FRP) to Core Maximum Fraction of Limiting Power Density (CMFLPD) shall be checked and the scram and APRM Rod'lock When it is determined that one settings given by equations in channel is failed in the unsafe specifications 2.1.A.l and 2.1.B condition, that channel con- shall be calculated.
taining the unsafe failure will be tripped within one hour.
3l LJn)k 3
ENCLOSURE 2 DESCRIPTION AND JUSTIFICATION (TVA BFNP TS 2'00)
Descri tion of Cha e:
Technical specification section 4 .1.C contains a requirement that upon the failure of a reactor protection system ( RPS) channel in the unsafe condi-tion all RPS channels monitoring the same variable must be functionally tested. This testing must be performed immediately before the trip system containing the failure is tripped . The trip system may be in the untripped position for up to eight hours to perform the functional test.
The RPS is made up of two independent trip systems. There are usually four channels provided to monitor each cr itical parameter, with two channels in each trip. system. The outputs of the channels in a trip system are com-b1ned in logic such thateither channel trip will trip that trip system.
simultaneous tripping of both trip systems will produce a reactor 'he scram.
An unsafe failure means that the failure did not result in tripping the channel and thus the trip system. Testing the other channels ensures that there are no other unsafe failures. However, in order to do this testing, the trip system containing the failure can be left as is for up to eight hours in order to test the other trip system.
The proposed revision is to delete the functional test requirement and replace it with a requirement to trip the channel containing the failure within one hour. The proposed amendment reflects that of the Standard Technical Specifications.
Justification:
The FSAR section 7 .2 .2.7b states: "Any one intent'ional bypass, ma1ntenance
~
operation, calibration operation, or test to verify operational availability shall not impair the ability of the reactor protection system to respond correctly." The current technical specifications allow leaving the trip system containing the unsafe failure in the untr1pped condition for up to eight hours in order to functionally test the other trip system. This could
'ossibly lead to a situation which could impair the ability of the RPS .to respond correctly. By tr ipping the channel within one hour, the probability of impair ing the response of the RPS is decreased, and thus, the margin of
', safety is increased. The proposed revision also makes this section like
'hat in the Standard Technical Specif1cations.
~ ~ c l ENCLOSURE 3 PROPOSED NO SXGNXFICANT HAZARDS CONSIDERATXON DETERMINATION (TVA BFNP TS 200)
Descri tion of Cha e:
Technical specification section 4.1.C conta1ns a requirement that upon the failure of a reactor protection system (RPS) channel in the unsafe condition all RPS channels monitoring the same variable must be functionally tested.
This testing must be performed immediately before the trip system containing the failure is tripped . The trip system may be in the untr ipped position for up to eight hours to perform the functional test.
The RPS is made up of two independent trip systems. There are usually four channels provided to monitor each cr itical parameter, with two channels in each trip system. The outputs of the channels in a trip system are combined in logic such that either channel trip will trip that trip system. The simultaneous ff tripping of both trip systems will produce a reactor scram.
0 An unsafe failure means that the failure did not result in tr 1pping the channel and thus the trip system. Testing the other channels ensures that there are no other unsafe failures. However, in order to do this testing, the trip system containing the failure can be left as is for up to eight hours in order to test the other trip system.
The proposed revision is to delete the Anctional test requirement and replace it with a requirement to tr1p the channel containing the failure within one hour. The proposeg amendment reflects that of the Standard Technical Specifications.
Bas1s for Pro osed No S nificant Hazards Determination:
NRC has provided guidance concerning the application of the standards by'"
providing examples of actions that are not likely to involve s1gnificant hazards considerations (48FR14870). One example of act1ons not likely to involve a significant hazards consideration is a change which either may result in some increase to the probability or consequences of a previously-analyzed accident or may reduce in some way a safety .margin, but where the results of the change are clearly within all acceptable criteria with respect to the system or component specified in the Standard Rev1ew Plan.
The proposed amendment 1s encompassed by this example in that the revision
-reflects the requirements establ1shed in the Standard Techn'ical Specif1ca-tions. Also, by tripping the channel in one hour as opposed to -eight hours, the probability of impairing the ability of the RPS to respond correctly is decreased. This results in an increase in the margin of safety.
Therefore, TVA proposes to determine that the proposed amendment does not involve a s1gnificant hazards consideration.
1