|
---|
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 SUPPLEMENT 1)
>>osieoz44>>000+@
QQQCK 05 pgg pgg P
k +
J ~1 ~
j
~ 0 PROPOSED UNIT 1 TECHNICAL SPECIFICATION REVISIONS
I
~
~
LIMITING CONDITIONS FOR OPERATION SURVEXILANCE klPUIREHENTS 3.1 REACTOR PROTECTION SYSTEM 4el REACTOR PROTECTION SYSTEM A licabilit ~A 11c~ettlt t Applies to the instrumentation Applies to the surveillance of and associated devices which the instrumentation nnd asso-initiate a reactor scram. ciated devices which initiate reactor scram.
~0b ecetve ~0b ective To assure the operability of the To specify the type and frequency reactor protection system. of surveillance to be applied to the protection instrumentation.
S ecification S ecification When ther'e is fuel in the vessel, A. Instrumentation systems shall the setpoints, minimum number of be functionally tested and trip systems, and minimum number calibrated as indicated in of instrument channels that must Tables 4.1.A and 4.1.9 respec-be operable for each position of tively.
the reactor mode a~itch shall be as given in Table 3.1.A.
B. Twn RPS power monitoring channels fnr each inscrvice'PS flG sets or alternate sour' shall bu ceper'able.
- 1. With one RPS electric pnwer monitoring channel for inservice RPS MG set or alternate power supply inoperable, restore the inoperable channel to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> nr remove the associated RPS MG set or alternate power supply from service.
31
'I NOTES FOR TABLE 3.1.A
- 1. There shall be two operable or tripped trip systems for each function. If the minimum number of operable instrument channels per trip system cannot be met for one trip system trip the inoperable channels or entire trip system within one hour, or, alternatively, take the below listed action for that trip function.
If the minimum number of operable instrument channels cannot be met by either trip system, the appropriate action listed below (refer to right-hand column nf Table) sliall be taken. An inoperable cliannel pepd not be placed in the tripped condition where this would cause php trip function to occur. In these cases, the inoperable channel sliall be restored to operable status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or take the action listed below for. that trip function.
A. Initiate insertion of operable rods and complete insertion of all operable rods within four hours.
In refueling mode, suspend all operations involvinp core alterations and fully insert all operable control rods
~~ithin one hnut.
B. Reduce power level to ZRN range and place mode switch in the'Startup/Hot Standby position within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C ~ Reduce turbine load and close main steam line isolation valves within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
D. Reduc power to less than 30$ of rated.
- 2. Scram discharqe volume high bypass may be used in shutdown or refuel to bypass scram discharge volume scram with control rod block for reactor protection system reset.
- 3. Bypassed 'if reactor pressure < 1055 psig and mode switch not in run.
- 4. Bypassed when turbine first stage pressure is less than 154 p iq
- 5. IRx's are bypassed when APRH'o are onocalo and the reactor switch io in the run position. 'ode
- 6. The desiqn permits cloouro of any two linea without a scram be ing ini ti at cd.
when the reactor is subcritical and the reactor water tenp rature is less than 212 F, only the following trip function" need to be operable:
t A. Node switch in shutdown B. Hanual scram C. High flux IRH D. Scram discharge volume high level E. APRN 15% scram
- 8. trot required to he operablo when primary containment integrity is not required.
- 9. Hot required if all main stoamlinea are isolated.
35
PROPOSED UNIT 2 TECHNICAL SPECIFICATION REVISIONS UNITING C05IDXTIONS FOR OPERATION SURVEILLkiCE RE UIRE29'.NTS 3.1 REACTOR PR TECTION SYSTEM 4~1 REACTOR PROTECTIOiV SYSTEM
~Al~icatlllt App1ies to the instrumentation Applies to the surveillance of and associated devices which the instrumentation and asso-initiate a reactor scram. ciated devices which initiate reactor scram
~at ectf.va Ob ective To assure the operability of the To pecify the type and frequency reactor protection system. of surveillance to be applied to tne protection instrumentation.
S ecification ."necl f lean lan N<en there is fuel in the ves"el, the setpoints, minimum number of A. Inutrume>>t:it I>>n Syati.ill 'ah ~ lit be functionally tc::ted <<nd trip systems, and minimum number calibrated as indicated'in of instrument channels that must Tables 4al.h and 4.1.8 respec-be operable for each position of tively.
the reactor mode switch shall be as given in Table 3.1.A.
31
0 NOTES FOR TABLE 3. 1.A 1'. There shall be two operable or tripped trip systems for each function. If the minimum number of operable instrument channels per trip system cannot be met for one trip system trip the inoperablechannels or entire trip system within one hour, or, alternatively, take the below listed action for that trip function.
If the minimum number of operable instrument channels cannot be met by either trip system, the appropriate action listed below (refer to jight-Pand column of Table) shall be taken. An inoperable channel need not be placed in the tripped condition where this would cause the trip function to occur. In these cases, the inoperable channel shall be restored to operable status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or take the action listed below for that trip function.
A. Initiate insertion of operable rods and complete insertion of all operable rods within four hours.
In refueling node, suspend all operations involvinp core alterations and fully insert all operable contxol rods wit? in nne hoot.
B. Reduce power level to XRM range and place mode switch in the Startup/Hot Standby position within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C. Reduce turbine load and close main steam line isolation valves ~ithin 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
D. Reduce power to less than 30% of rated.
- 2. Scram discharqe,volume high bypass may be used in shutdown or refuel to.bypass scram discharge volume scram with control rod block for reactor protection system reoet.
- 3. Bypaosed if reactor preosure < 1055 psig and mode switch not in run.
- 4. Bypassed when turbin first otage pressure io less than 154 pslqo
- 5. IRM's are bypassed when APRM'o are onocale and the reactor "
mode switch io in the run position.
- 6. The deoiqn permits cloouro of any two lineo without a scram be ing ini tiat ed.
- 7. when the reactor is oubcritical and the reactor water temperature io less than 212~F, only the following trip tunction" need to be operable:
A. Mode switch in shutdown B. Manual scram C. High flux IRM D. Scram discharge volume high level E. APRM 15% scram
- 8. Not required to be operablo when primary containment integrity io not required.
- 9. ?tot required if all main stoamlineo are J
isolated.
35
! ~'
PROPOSED UNIT 3 TECHNICAL SPECIFICATION REVISIONS
. LIHITINC CONDITIONS POR OPERATION SURVEILLANCE REQUIREMENTS 3 1 REACTOR'PROTECTION SYSTEM 4a 1 REACTOR PROTECTION SYSTEM A licabilit A licabilit Applies to the surveillance of Applies to the instrumentation the instrumentation and 4nd associated devices which associated devices which ini ~~ate a reactor scram. ini tia te reactor scram.
Q+b a: Giye To specify the type and
~Ob 6LtiV6 frequency of surveillance to be applied to the protection To assure the operability of instrumentation.
the reactor protection system.
NL S ecificetion A- Instrumentation systems shall befunctionally tested and calibrated as ti'hen there is fuel in the vessel, indicated in Tables 4. 1.A The 'setpoints, minimum number and 4. 1. B respectively.
of trip systems, and minimum number of instrument channels that must be operable for each position of the reactor mode switch shall be as given in Table 3.1.A.
31
0 NOTFS FOR TABI.E 3. l.h
- 1. 'fhero . hall be two operab]o or tri))p(d trip svst(ms fol each function. If the minimum number of operable instrument channels per trip system cannot be met for one trip system trip the inoperable channels or entire trip system within one hour, or, alternatively, take the below listed action for that trip function.
If the minimum number of operable instrument channels cannot be met by eitj>er trip system, the appropriate action listed below (refer to right-hand column of Table) shall be taken. An inoperable channel need not be placed in the tripped condition where this would"cause the trip function to occur. In these cases, the inoperable channel shall be restored to operable status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or take the action listed below for that trip function.
Initiate insertion of operable rode and complete insertion of all operable rode vithin four hours.
In zefuclinB cade, suspend sll operations Involving core Llterscions and fully Insert all operable control rods vier) In one hoot'.
B. Reduce pover level to ZRM range and placo mode evitch in the Startup/Hot Standby position vithin B hours.
C. Reduce turbine load and close main atoam line iaolat5.on valves vithin 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
D. Reduce pover to leaa than 30% of rated.
Scram discharqe volume high bypass may be used in ehutdovn or refuel to; bypass scram discharge volume scram vith control rod block for reactor protection system reset.
3 Deleted.
Bypassed vhen turbine first etage preaaurc ia less than 154
, pslge
- 5. IRM's are bypaaaed vhcn APRM'a are onacale and tho reactor mode ovitch ia in the run position The design permits closure of any tvo linea without a scram being initiated.
when the reactor is subcritical and the rea8tor voter tent)erature ia less than 212oF, only tho folloving trip functions need to be operable!
A. Mode avitch in shutdovn B. Manual scram C. High flux ZRM D. Scram discharge volume high level.
E. APRM 15% scram
- 8. Hot required to be operabla vhen primary containment integrity ia not required.
- 9. Hot requi'red if all main atoamlinea are isolated.
- 10. Hat required to be operabl'o vhen the reactor proaeuro veeaol head is not bolted to thc veaael ~
- 11. The ApRM dovnscale trip'unction ia only active vhcn tho reactor mode avitch ia in run.
la r~W
ENCLOSURE 2 DESCRIPTION AND JUSTIFICATION (TVA BFNP TS 200 SUPPLEMENT l)
Description of Change Technical Specification section 4.1.C contains 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 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 critical parameter, with two channels in each trip system. The outputs of the channels in a trip system are combined in logic such that ei,ther channel trip will trip that trip system. The simultaneous tripping of both trip systems will produce a reactor 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 change note 1 forTable 3.1.A to provide an alternative of tripping the inoperable channels within one hour or taking the action listed for that trip function.
The note would also allow two hours to restore operable status to one channel, if placing that channel in the tripped condition would cause the trip function to occu'r. The proposed amendment is consistent with the Standard Technical Specifications.
Justification The FSAR section 7 .2.2.7 .b states: "Any one intentional bypass, maintenance 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 untripped condition for up to eight hours in order to functionally test the other trip systems. This could possibly lead to a situation which could impair the ability of the RPS to respond correctly. By tripping the channel within one hour, the probability of
~
impairing the response of the RPS is decreased, and thus, the margin of safety is increased. The proposed revision also makes this section like that in the Standard Technical Specific'ations.