Proposed Tech Specs,Clarifying Trip Level Setting in Table 3.2.A for Standby Gas Treatment Sys Relative Humidity HeaterML18032A344 |
Person / Time |
---|
Site: |
Browns Ferry, Oconee ![Tennessee Valley Authority icon.png](/w/images/c/ce/Tennessee_Valley_Authority_icon.png) |
---|
Issue date: |
05/29/1987 |
---|
From: |
TENNESSEE VALLEY AUTHORITY |
---|
To: |
|
---|
Shared Package |
---|
ML18032A343 |
List: |
---|
References |
---|
TAC-R00031, TAC-R00032, TAC-R00033, TAC-R31, TAC-R32, TAC-R33, NUDOCS 8706100333 |
Download: ML18032A344 (8) |
|
|
---|
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 ML20155C6391998-10-26026 October 1998 Proposed Tech Specs Tables 4.1-1 & 4.1-2,revised Surveillance Frequency of Refueling Outage to 18 Months ML20154C1021998-09-30030 September 1998 Proposed Tech Specs Changing UFSAR by Increasing Max Rod Internal Pressure in Spent Fuel Pool from 1,200 to 1,300 Psig 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 ML20236V9611998-07-27027 July 1998 Corrected TS Bases Pages 3.5-30b of 961211 & 3.16-2 of 970205,correcting Amend Numbers ML20236T5171998-07-20020 July 1998 Proposed Tech Specs Re one-time Extension to Functional Test Frequencies for Hydraulic & Mechanical Snubbers 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 ML20236R1901998-07-16016 July 1998 Proposed Tech Specs Extending TS Surveillances TS 4.20.2(a), Table 4.20-1,items 1,2 & 4,TS 4.1-1,Table 4.1-1,items 8,9,10 & 11 & TS 4.5.1.2.1,item b(1) 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 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 ML18039A2101997-12-0404 December 1997 Proposed Tech Specs Pages Re TS Change 362,suppl 7 Re ITS Section 3.1, Reactivity Control Sys. 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. ML20199E1361997-11-14014 November 1997 Proposed Tech Specs Section 3.4 Re Reactor Coolant Sys ML20199D5471997-11-14014 November 1997 Proposed Tech Specs Section 3.0, Limiting Condition for Operation (LCO) Operability & Section 4.0, Design Changes 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 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 ML20211A9881999-08-18018 August 1999 Rev 5 to DPC Nuclear Security Training & Qualification Plan 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 ML20204B4141999-03-27027 March 1999 Revised Oconee Nuclear Station Selected Licensee Commitments, List of Effective Pages 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 ML20155C6391998-10-26026 October 1998 Proposed Tech Specs Tables 4.1-1 & 4.1-2,revised Surveillance Frequency of Refueling Outage to 18 Months ML20154L7191998-10-0505 October 1998 Rev 8 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20154C1021998-09-30030 September 1998 Proposed Tech Specs Changing UFSAR by Increasing Max Rod Internal Pressure in Spent Fuel Pool from 1,200 to 1,300 Psig 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 ML20236V9611998-07-27027 July 1998 Corrected TS Bases Pages 3.5-30b of 961211 & 3.16-2 of 970205,correcting Amend Numbers ML20236T5171998-07-20020 July 1998 Proposed Tech Specs Re one-time Extension to Functional Test Frequencies for Hydraulic & Mechanical Snubbers 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 ML20236R1901998-07-16016 July 1998 Proposed Tech Specs Extending TS Surveillances TS 4.20.2(a), Table 4.20-1,items 1,2 & 4,TS 4.1-1,Table 4.1-1,items 8,9,10 & 11 & TS 4.5.1.2.1,item b(1) 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 ML20217F2841998-04-20020 April 1998 Rev 7 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations 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. ML20199E1361997-11-14014 November 1997 Proposed Tech Specs Section 3.4 Re Reactor Coolant Sys ML20199D5471997-11-14014 November 1997 Proposed Tech Specs Section 3.0, Limiting Condition for Operation (LCO) Operability & Section 4.0, Design Changes 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 ML20141F1521997-06-25025 June 1997 Rev 4 to Nuclear Security Training & Qualification Plan 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 1999-09-28
[Table view] |
Text
ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATIONS REVISIONS BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 (TVA BFN TS 232) 8706100333 8705>~
PDR ADOCK 05000259 p PDR
TABLE 3.2.A (Continued)
PRIMARY CONTAINMENT ANO REACTOR BUILDING ISOLATION INSTRUMENTATION Minimxn No.
Instrument Channels Operable er Tri S s 1 ll Function Tri Level Settin Action 1 Remarks Instrument Channel < 100 mr/hr or downscale F 1. 1 upscale or 2 downscale will Reactor Building a. Initiate SGTS Ventilation High b. Isolate refueling floor Radiation Refueling Zone c. Close atmosphere control system.
2(T) (8) Instrunent Channel >2000 cfm and < 4000 cfm H and Below trip setting, R. H.
SGTS Flow - Train A (A or F) heaters will shut off.
R. H. Heaters 2(T) (8) Instrenent Channel >2000 cfm and < 4000 cfm H and Below trip setting, R. H.
SGTS Flow Train B (A or F) heaters will shut off.
R. H. Heaters 2(l) (8) Instrument Channel >2000 cfm and < 4000 cfm H and Below trip setting, R. H.
SGTS Flow Train C (A or F) heaters will shut off.
R. H. Heaters Reactor Building Isolation 0 < t<2 secs. HorF l. Below trip setting prevents Timer (refueling floor) spurious trips and system perturbations fran initiating isolation.
Reactor Building Isolation 0 < t<2 secs. Gor A 1. Below trip setting prevents Timer (reactor zone) or H spurious trips and system perturbations from initiating isolation.
2(10) Group 1 (Initiating) Logic N/A 1 Refer to Table 3.7.A for list of valves.
BFN Unit 1
TABLE 3.2.A (Continued)
PRINRY CONTAINNENT AND REACTOR BUILDING ISOLATION INSTRUHENTATION Hinimm No.
Instrwent Channel s Operable Function Tri Level Settin Action 1 Remarks Instrument Channel < 100 mr/hr or downscale F 1. 1 upscale or 2 downscale will Reactor Building a. Initiate SGTS Ventilation High b. Isolate refueling floors Radiation Refueling Zone c. Close atmosphere control system.
2(7) (8) Instrument Channel >2000 cfm and < 4000 cfm H and Below trip setting, R. H.
SGTS Flow Train A (A or F) heaters w>11 shut off.
R. H. Heaters 2(7) (8) Instrunent Channel >2000 cfm and < 4000 cfm H and Below trip setting, R. H.
SGTS Flow Train B 4 (A or F) heaters w) ll shut off.
R. H. Heaters 2(7) (8) Instrwent Channel >2000 cfm and < 4000 cfm H and Below trip setting, R. H.
SGTS Flow Train C (A or F) heaters wi 11 shut off.
R. H. Heaters Reactor Building Isolation 0 < t<2 secs. HorF 1. Below trip setting prevents Timer (refueling floor) spurious trips and system perturbations frcm initiating isolation.
Reactor, Building Isolation 0 < t<2 secs. G or A 1 Below trip setting prevents Timer (reactor zone) or H spurious trips and system perturbat>ons frcm >n>t>at>ng isolation.
2(10) Group 1 (Initiating) Logic N/A 1. Refer to Table 3.7.A for list of valves.
BFN Unit 2
TABLE 3.2.A (Continued)
PRINARY CONTAINNENT AND REACTOR BUILDING ISOLATION INSTRUNENTATION Hiniaxm No.
Instrument Channels Operable Function Tri Level Settin Action 1 Remarks Instrunent Channel < 100 mr/hr or downscale F 1. 1 upscale or 2 downscale will Reactor Building a. Initiate SGTS Ventilation High b. Isolate refueling floor.
Radiation Refueling Zone c. Close atmosphere control system.
2(7) (8) Instrument Channel >2000 cfm and < 4000 cfm H and Below trip setting, R. H.
SGTS Flow Train A (A or F) heaters w> 11 shut off.
R. H. Heaters 2(7) (8) Instrument Channel >2000 cfm and < 4000 cfm H and Below we'llsetting, trip R. H.
SGTS Flow Train 8 (A or F) heaters w ll shut off.
R. H. Heaters 2(7) (8) Instrument Channel >2000 cfm and < 4000 cfm H and Below trip setting, R. H.
SGTS Flow Train C (A or F) heaters shut off.
R. H. Heaters Reactor Building Isolation 0 < t<2 secs. HorF 1. Below trip setting prevents Timer (refueling floor) spurious trips and system perturbations frcm initiating isolation.
Reactor Building Isolation 0 < t<2 secs. G or A 1. Below trip setting prevents Timer (reactor zone) or H spurious trips and system perturbations fran initiating isolation.
2(10) Group 1 (Initiating) Logic N/A 1 Refer to Table 3 7 A for list of valves.
BFN Unit 3
ENCLOSURE 2 DESCRIPTION AND JUSTIFICATION BROGANS FERRY NUCLEAR PLANT Descri tion of Chan e The Browns Ferry Nuclear Plant (BFN) Units 1, 2, and 3 Technical Specifications, table 3.2.A, page 3.2/4.2-9, is revised to clarify the trip level setting for the Standby Gas Treatment System (SGTS) relative humidity heater. The current requirement of "less than or equal to 2000 cfm" is changed to be "greater than or equal to 2000 cfm and less than or equal to 4000 cfm".
Reason for Chan e An ambiguity exists between the trip level setting column and the remarks column of table 3.2.A. The trip level set,ting requirement is less than or equal to 2000 cfm which would require the actual trip point to be below 2000 cfm. The remarks require the heater to be shut off below 2000 cfm and, therefore, require an actual trip point above 2000 cfm.
Justification for Chan e The SGTS provides a means for minimizing the release of radioactive material from the containment to the environs by filtering and exhausting the air from any or all zones of the Reactor Building and maintaining, the building at a negative pressure (such that air leakage is into, not out of, the building) during containment isolation conditions. The SGTS consists of three blower/filter trains which can take suction from any or all of the three reactor zone or refueling zone secondary containments. Each train is equipped with a 40-kw electric heater which'is designed to reduce the relative humidity of the inlet air to less than 70 percent relative humidity. The heater is energized automatically with the startup of the SGTS train and remains energized until the blower is stopped. The heater is interlocked with the airflow to prevent burnout of the elements with low airflow. A temperature sensor close to the heater also trips the heater if the temperature exceeds 180 F. The interlock with airflow is provided by redundant flow switches designed to operate at <50 percent of normal flow as stated in Final Safety Analysis Report (FSAR), section 5.3.3 from the blowers so that when the blower
'. In addition, th'e heaters are wired shuts down or loses power, the heater is deenergized.
The intent of the technical specification requirement in table 3.2.A for the relative humidity heater switch is to turn of;" the heater before a decreasing SGTS flow reaches 2,000 cfm. This would prevent damage to the SGTS filter banks by turning, off the heater before reaching a flow that would not adequately transfer the heat. A literal reading of the current technical specification wording would allow a setpoint of 0 cfm which does not fulfill the intent of the technical specifications. Therefore, the "less than or equal to" requirement should be changed to "greater than or equal to" in order to meet the intent of the technical specifications and achieve agreement with the design basis.
Justification for Chan e (Cont'd)
An upper bound of 4,000 cfm is imposed on the setpoint to ensure that the flow switches do not prevent the heaters from performing their function during normal blower operation. Technical specification 3.7.B.2.c requires that each train operate within + 10 percent of design flow (9,000 cfm). Therefore, when the system is initiated, the airflow for an operable train will be greater than 4,000 cfm and the heaters will perform their function.
The proposed change makes the technical specifications more consistent with the design basis and the FSAR and, therefore, will increase the margin of safety.
ENCLOSURE 3 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION BROWNS FERRY NUCLEAR PLANT (BFN) UNITS 1, 2, AND 3 Descri tion of Amendment The proposed amendment would modify the Browns Ferry Nuclear Plant Technical Specification fox units 1, 2, and 3 to clarify the trip level setting in Table.
3.2.A for the Standby Gas Treatment System (SGTS) relative humidity heaters.
The current setting is less than ox'qual to'2,000 cfm but a note to the table implies a setting above 2,000 cfm. The proposed amendment would revise the setting to be between 2,000 and 4,000 cfm.
Basis for Pro osed No Si nificant Hazards Consideration Determination 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 for a facility involves no significant hazards consideration if operation of the facility in accoxdance with a proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, or (2) create the possibility of a new or different kind of accident from any accident previously evaluated, ox (3) involve a significant reduction in a margin of safety.
- 1. The probability or consequences of a previously evaluated accident will not be significantly increased since the proposed amendment will provide consistency and clarification of table 3.2.A requirements and notes for the relative humidity heater shutoff setpoints without altering the funcLion. -Furthermore, the direction of the setpoint movement is conservative in respect to the switch function which is turning off the heaters before reaching a flow that would not adequately transfer the heat.
- 2. The possibility of a new or different kind of accident is not created since this'hange will not eliminate any protective functions and the setpoint change is in a conservative direction. Also, no new operational conditions will be permitted.
- 3. The proposed change will not involve a significant reduction in any margin of safety since the setpoint change is conservative and no functions or equipment changes are involved.
Si;:ce the application for amendment involves a proposed change that is encompassed by the criteria for which no significant hazards consideration exists, TVA proposes to determine that the proposed amendment does not involve a significant hazards consideration.