Proposed TS Table 3.2.F Re Surveillance Instrumentation for Drywell Pressure,Drywell Temp,Suppression Chamber Air Temp & Drywell Temp & Pressure & TimerML18036A828 |
Person / Time |
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Site: |
Browns Ferry |
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Issue date: |
08/25/1992 |
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From: |
TENNESSEE VALLEY AUTHORITY |
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To: |
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Shared Package |
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ML18036A826 |
List: |
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References |
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NUDOCS 9209020076 |
Download: ML18036A828 (9) |
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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 TECHMCAL SPECIFICATION CHANGE BROWNS HURRY NUCLEAR PLANT UNITS 2, AND 3 (TVA BFNP TS 327) 9209020076 920825 PDR ADOCK 05000260 PDR
'1$
pt
TABLE 3.2.F Surveillance Instrumentation Minimum ¹ of Operable Instrument Type Indication Channels Instrument ¹ Instrument and Ran e Notes LI-3-46 A Reactor Water Level Indicator 155" to (1) (2) (3)
LI-3-46 8 +60" PI-3-54 Reactor Pressure Indicator 0-1500 psig (1) (2) (3)
PI-3-61 XR-64-50 Drywell Pressure Recorder -15 to +65 psig (1) (2) (3)
PI-64-67 Indicator -15 to +65 psig TI-64-52 Drywell Temperature Recorder, Indicator (1) (2) (3)
XR-64-50 0-400'F XR-64-52 Suppression Chamber Recorder 0-400'F (1) (2) (3)
Air Temperature N/A Control Rod Position 6V Indicating )
Lights )
N/A Neutron Moni toring SRM, IRM, LPRM ) (1) (2) (3) (4) 0 to 1005 power )
PS-64-67 Drywell Pressure Alarm at 35 psig )
)
XR-64-50 and Drywell Temperature Alarm if temp. )
PS-64-58 B and and Pressure and > 281'F and ) ()) (2) (3) (4)
IS-64-67 Timer pressure >2.5 psig )
after 30 minute )
delay )
-- LI-84-2A CAD Tank "A" Level Indicator 0 to 100/
LI-84-13A CAD Tank "8" Level Indicator 0 to 100/
TABLE 3.2.F Surveillance Instr'umentation Hinimum 0 of Operable Instrument Type Indication ft Channels Instrument 4 Instrument and Ran e Notes LI-3-58A Reactor Water Level Indicator -155" to (1) (2) (3)
LI-3-58B +60 ll Pi-3-74A Reactor Pressure Indicator 0-1200 psig (1) (2) (3)
PI-3-?48 XR-64-50 Drywell Pressure Recorder -15 to +65 psig (1) (2) (3)
PI-64-67B Indicator -15 to +65 psig XR-64-50 Drywel1 Temperature Recorder, Indicator (1) (2) (3)
T I-64-52AB 0-4004 F XR-64-52 Suppression Chamber Recorder 0-400'F (1) (2) (3)
Air Temperature 4J N/A Control Rod Position 6V Indicating )
Lights )
N/A Neutron Honitoring SRH, IRH, LPRH ) (1) (2) (3) (4) 0 to 100K power )
I PS-64-67B Drywell Pressure Alarm at 35 psig )
I
)
TS-64-52A 8 PIS-64-58A 8 Drywell Temperature and Pressure and
" Alarm if temp.
>'281'F and
)
) (1) (2) (3) (4)
IS-64-67A Timer pressure >2.5 psig )
after 30 minute )
delay )
LI-84-2A CAD Tank "A" Level Indicator 0 to 100/
LI-84-13A CAD Tank "8" Level Indicator 0 to 100/
ENCLOSURE 2 BROWNS H<22RY NUCLEAR PLANT (BFN)
DES CRIPTI A TIFI ATI F R THE PR ED HAN ARY F HA EF R 2A FOR UNITS 2 and 3 on Table 3.2.F, "Surveillance Instrumentation," change the indicated range for the indicator and recorder from 0-80 psia to -15 to +65 psig for the low range drywell pressure indication (i.e., instrument numbers PR-64-50 and PI-64-67 for Unit 3 and XR-64-50 and PI-64-67B for Unit 2).
On Unit 3, Table 3.2.F, the recorder instrument number for 1) drywell pressure, 2) drywell temperature, and 3) drywell temperature and pressure and timer will be revised to XR-64-50.
The instrument recorder number for suppression chamber air temperature will be revised to XR-64-52. On Unit 2 Table 3.2.F, instrument No. TI-64-52AB for drywell temperature indication will be relocated from being associated with drywell pressure indication.
R nfr hn The changes are administrative changes of the indicated range of the indicator and recorder from 0-80 psia to -15 to +65 psig for the low range drywell pressure indication and to correct the labeling of various recorders. These changes are the result of a resolution of a Human Engineering Discrepancy (HED) identified through the Control Room Design Review (CRDR) effort for BFN.
ifi ionfr hne These changes are administrative changes of the indicated range of the indicator and recorder from 0-80 psia to -15 to +65 psig for the low range drywell pressure indicator and recorder and to correct the labeling of various recorders. These changes do not affect the design basis or safety function of the Primary Containment System. These changes will result in improved man-machine interface characteristics and, thus, enhance operator performance during abnormal and emergency plant conditions. The revised range will allow for easier comparison with other containment and atmospheric pressure indications. Additionally, existing plant documentation supports the use of "psig" as the preferred engineering units for indication.
ENCLOSURE 3 BROWNS FERRY NUCLEAR PLANT (BFN)
PR ED DETER ATI F I AZARD IDERATI D ri i n fPr T i I ifi i nAmen m The technical specifications for BFN Units 2 and 3 are being revised to change the indicated range for the indicator and recorder for the low range drywell pressure indication and to correct the labeling of various recorders.
B i fr inifi n H r n'e i nD rmin in NRC has provided standards for determining whether a significant hazards consideration exists as stated in 10 CFR 50.92(c). A proposed amendment to an operating license involves no significant hazards considerations if operation of the facility, in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (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 significantly increase the probability or consequences of an accident previously evaluated.
The proposed changes are administrative changes of the indicated range of the indicator and recorder for the low range drywell pressure indicator and to correct the labeling of various recorders. The proposed changes do not effect the design basis or the safety functions of the Primary Containment System, since the sensing range of the drywell pressure is not changed. Therefore, the proposed changes do not significantly increase the probability or consequences of an accident previously evaluated.
- 2. The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed changes are administrative changes of the indicated range of the low range drywell pressure indication and to correct the labeling of various recorders, which resolves a HED identified through the CRDR effort. There are no automatic actions effected by the proposed change. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. The proposed change does not involve a significant reduction in a margin of safety.
The proposed changes are administrative changes to indicated range and to correct the labeling of various recorders, and does not affect the setpoint, calibration interval or functional test interval of the low range drywell pressure indication. The proposed changes do not affect any limiting conditions of operation or analysis assumption found in the technical specifications or their bases. Therefore, the changes do not involve a significant reduction in any margin of safety.
A