Proposed Changes to Tech Spec Table 3.7.A,reflecting Correct Valve Positions for Operating Pressure Suppression Head Tank SysML20085A764 |
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Site: |
Browns Ferry |
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Issue date: |
06/24/1983 |
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From: |
TENNESSEE VALLEY AUTHORITY |
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To: |
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Shared Package |
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ML20085A763 |
List: |
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References |
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NUDOCS 8307070124 |
Download: ML20085A764 (6) |
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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
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ENCLOSURE 1 l PROPOSED TECHNICAL SPECIFICAION REVISIONS TVA BFNP TS 176 SUPPLEMENT 8 BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 1
i lDR DD 0 000 P
TA31.E 3.7. A
- FAI'tARY COWAIWDT ISol.ATION VG 9ES Nu=iber of Power Maximun Action en Operated Valves Operating Normal lettiattog Croup C9tbcard Tine (sec.) Position Signal ._
Valve Identification Inbc :rd
~3 CC 1 % 10 steamitne isolatfor. valves 4 4 3<T<5 0 (FCV-1-14,26,3 7,651 jl-15, 27, 38, & 52) 1 Main steam 1 toe drain isolation 1 1 15 0 CC valves PCV-t-55 & 1-56 SC 1* Reactor Unter sample itne isole- 'l 1 5 C tion valves 4
I$ .
2 RHRS shutdowrt cooling supply isolation valves FCV-74-48 & 47 1 1 40 c SC 2 RalRS - 1.FCI to reactor FCV-74-53, 67 2 30 C SC 2 Reactor vessel head spray isole-tion valves FCi-74-77, 78 . 1 1 30 C SC 2 RHRS flush and drain vent to
- suppreoston chauber 4 20 C SC FCV-74-102, 103,'119 & 120 2 suppression Chamber Drain 2 15 0(1) GC e FCV 75-57. -58 ~
z 2 Dr79t11 squipe.ent drain discharge $
15 0 GC
, isoletion estves FCV-77-15A, & 15B 2 -
2 Dry.iell floor drata discherse 2 0 g taalattua valves FCV-77-2A & 23 is
- *These valves isolate only on reactor vessel low low water level (470") and main steam line high radiation of Group 1 isolations.
NOTES
- 1. These valves are normally open when the pressure suppression head tank is aligned to serve the RHR and CS discharge piping and closed when the condensate head tank is used to serve the RHR and CS discharge piping. (See Specification 3.5.H)
e .
TABLE 3. 7. A FRIPARY CONrAIMHDiT ISotArIOff VALVES Maximus Action on Number of Power 13ormal Init ia t i n4 Operating crerated valves Tame (sec.I Position Signal Inboard Outboard Group Valve Idetification 0 cc 4 4 3<T< 5 1 Itain steamline isolation valves (FCV-1-It, 26, 37, s $1; l-15, 27, 3S & 52)
O CC 1 1 15 1 Main steasta,ne drain isolation
' valves (FCV-1-55 5 1-56) se
1* Reactor water sample line isola- 1 tion valves 2 REAS shutdown cooling supply 1 40 C SC 1
isolation valves (rcv-74-48 s 47) SC J0 C 2
2 RIUt3 - LPCI to reactor .
(rcV-74-53 & 67) 2 Reactor vessel head spray isola- 1 30 c SC 1
tion valves (PCV-74-77 5 76)
N 2 RERS flush and drain vent to 20 c
y suppression chamber (FCV-74-102, 103, 119, & 120) 2 15 0(1) GC l 2 suppression chamber Crain (FCV-7 5-57 s 58) .
Drywell equipment drain discharge 15 0 cc 2 2 isolation valves (FCV-77-15A & 158) 2 Drywell floce drain discharge 15 0 cc 2
isolation valves (FCV-77-2A 5 25) ligned Notes:
1.
These valves are normally open when the pressure suppression head tank is ad when E y the co to serve the RHR and CS discharge piping and close (See specification 3.5.10 is used to serve the RHR and CS discharge piping. u
- These valves isolate only on, reactor vessel low low water level.(470") and main steam line high radiation of Croup 1 isolations.
s . .
j . . . ,
a * .
a TAELE 3.7.A PRIMARY CDPTAIIMDiT ImLATICN VALVES 4
Kazimum Actico on
. , Numbe r of Puwe r ograting Normal Ini t i at i g
> operated valves Position Signal Irloard .cutboard Taee (se=.3 ,
Group Valve Identification 0 A' 4 4 3<7<5 1 Main steaaline isolatio.1 valves
( FCV 14, 26, 37, 5 51; !
1-15, 27, 38 5 52) 15 0 GC 1 1 6 1 Main steamline drain iss14 tion valves (FCV-1-55 6 1-56 C SC
.I 1 5 1* Reactor Water sasple line isola-tion valves 2 RERS shutdown cooling supply 40 C SC 1 1 i solat.aon valves (It'V-74-4 8 s 47) 30 C SC 2
2 RifRS - LPCI t.o reactor (rcy-74-53 6 67) 2 Reactor vessel bead spray isola- ' 30 C SC 1 2 tion valves (FCV-74-77 & 78)
' RERS flush and .irain vent to SC 2 4 20 C U suppression c. baster
" (PcV-74-102, 103, 119, & 120) 2 Suppression Chamber Drain 2 15 0(1) GC (PCV-7 5-57 6 56) .
2 Drywell equipment drair. discharge 2 15 0 GC isolation valves (FCV-17-15A 5 158) 2 Drywell floor drain discharge 15 0 CC 2
isolation valves (FCV-77-2A & 23)
?
c:
z
, 4
~
u n
- These valves isolate only'on reactor vessel low low water level (470") and main steam li,e high radiation of Group 1 it.olations.
NOTES
- 1. These valves are normally open when the pressure suppression head tank is aligned to serve the RHR and CS discharg piping and closed when the condensate head tank is used to serve the RHR and CS discharge piping. (See specification 3.5.11)
1 ENCLOSURE 2 DESCRIPTION AND JUSTIFICATION l TVA BFNP TS 176 SUPPLEMENT 8 Description Page 250 (Units 1 and 2)
Page 262 (Unit 3)
For valves FCV 75-57, 75-58, Suppression Chamber drain, it is proposed to change the Normal Position from " closed" to "open" and Action on Initiation Signal from " stays closed" to "goes closed." Also, it is proposed to add the note: "These valves are normally open when the l pressure suppression head tank is aligned to serve the RHR and CS discharge piping and closed when the condensate head tank is used to serve the RHR and CS discharge piping. (See Specification 3 5.H)"
Justification 7
These changes are proposed for clarification of the normal position of the suppression chamber drain valves FCV 75-57 and 75-58. The changes also correct typographical errors in the designation of the suppression chamber drain valves to reflect proper valve numbers and proper action of valves on initiating signal.
These changes reflect the corect valve positions for operating the pressure suppression chamber head tank system. It will not be possible
. to operate the pressure suppression chamber head tank system with the valve alignment shown in the existing technical specifictions. This system was installed and will be used primarily to alleviate certain NRC concerns.
Page 250 for unit 1 includes the changes proposed in TS 176 Supplement 2.
Description and justification for those changes was provided in that submittal.
Page 262 for unit 3 includes the change, proposed in TS 176 Supplement 1, the addition of the footnote on the reactor water sample line isolation valves. ' As explained fully in that submittal the footnote was added to .
- more accurately represent the isolation trips for these valves. f l
Safety Analysis This revision is being made to clarify the normal position of the suppression chamber drain valves FCV 75-57 and 75-58. It does not alter in any way the present method of operation or the overall safety of the i plant. These valves will still go to the safe position in the event of a l containment isolation signal. !
_-__-___-______.._..__m._ _ _ _ _ _ _ . _ _ _ _ . _ . . . _ _ _
6 .
ENCLOSURE 3
. BROWNS FERRY NUCLEAR PLANT SIGNIFICANT HAZARDS CONSIDERATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGES
- 1. Does the proposed amendment. jnvolve a significant increase in the probability or consequences of an accident previously evaluated?
No - This revision does not alter in any way the system operation as described in the FSAR.
- 2. Does the proposed amendment create the proability of a new or different kind of accident from any accident previously evaluated?
No - This revision does not alter in any way the present method of operation or the overall safety of the plant.
3 Does the proposed amendment involve a significant reduction in a margin of safety?
No- This revision does not in any way alter a proscribed margin of safety.
1 l
I l
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