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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML18039A8811999-09-28028 September 1999 Proposed Tech Specs Re Increased MSIV Leakage Rate Limits & Exemption from 10CFR50,App J ML18039A8241999-07-28028 July 1999 Proposed Tech Specs Providing TS for Operation of Oscillation PRM Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A8001999-06-0303 June 1999 Proposed Tech Specs,Reducing Allowable Value Used for Reactor Vessel Water Level - Low,Level 3 for Several Instrument Functions ML18039A6991999-02-22022 February 1999 Proposed Tech Specs & Bases Pages Incorporating NRC Approved TS Change 354,requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation ML18039A6601998-12-15015 December 1998 Proposed Tech Specs,Revising pressure-temp Curves to Extend Validity of Curves to 32 EFPY ML18039A5041998-09-0808 September 1998 Proposed Tech Specs Providing TS for Operation of Oscillation Power Range Monitor Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A5001998-09-0404 September 1998 Proposed Tech Specs Re Use of Containment Overpressure for ECCS Pump Net Positive Suction Head Analyses ML18039A4791998-08-14014 August 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-33, DPR-52 & DPR-68 to Change Ts.Proposed Changes Decrease Frequency of once-per-cycle Instrument Calibrations by Substituting 24 Months for 18 Months ML18039A4611998-07-31031 July 1998 Proposed Tech Specs B 3.6-2,B 3.6-7 & B 3 3.7-2 for Power Uprate Operation Omitted Pages ML18039A4481998-07-17017 July 1998 Proposed Tech Specs,Adding LCO 3.4.10 & Accompanying TS Bases Provisions from Improved TS-362 Conversion Package as Adapted for Power Uprate Conditions ML18039A4091998-06-26026 June 1998 Proposed Tech Specs Section 3.4,allowing Units 2 & 3 to Operate at Uprated Power Level of 3458 Mwt ML18039A4021998-06-19019 June 1998 Proposed Tech Specs (TS) Converting from Existing Custom TS to Improved TS ML18039A3921998-06-12012 June 1998 Proposed Tech Specs Change 390,decreasing Frequency of once-per-cycle SRs by Substituting 24 Months for 18 Months in Affected TS SRs ML20249A5661998-06-10010 June 1998 Proposed Tech Specs Section 5.0,revising Administrative Controls ML20248C5151998-05-27027 May 1998 Proposed Tech Specs Section 3.8.1,revising AC Sources- Operating ML18039A3181998-04-16016 April 1998 Proposed Rev 2 to Tech Specs Section 3.6, Containment Systems, Converting from Current TS to Improved TS ML18039A2711998-03-16016 March 1998 Proposed Tech Specs Re Power Uprate Operation ML18039A2671998-03-13013 March 1998 Proposed Tech Specs,Converting to Improved Std Ts,Per NUREG- 1433,rev 1, Std TS for GE BWRs (BWR/4). ML18039A2641998-03-12012 March 1998 Proposed Tech Specs ITS Section 3.8 Re Electrical Power Sys. ML18039A2611998-03-0303 March 1998 Proposed Tech Spec Changes TS 393 Re Reactor Vessel Pressure Temperature Curves ML20199E8051998-01-23023 January 1998 Proposed Tech Specs Section 5.0 Re Administrative Controls ML18039A2221997-12-30030 December 1997 Proposed Tech Specs Re RHR SW Pumps Required for multi-unit Operation & Cold Shutdown ML18039A2151997-12-23023 December 1997 Proposed Tech Specs Section 3.7 Re Plant Sys ML18039A2181997-12-22022 December 1997 Proposed Tech Specs Section 3.8 Re Electrical Power Sys ML18039A2101997-12-0404 December 1997 Proposed Tech Specs Pages Re TS Change 362,suppl 7 Re ITS Section 3.1, Reactivity Control Sys. ML18039A2071997-12-0404 December 1997 Proposed Tech Specs Pages Re Suppl 9 to TS Change 362, Including Rev Pages to Improved TS Section 3.5 ML18039A2011997-12-0303 December 1997 Proposed Tech Specs Section 3.9 Re Refueling Operations & Section 3.10, Special Operations. ML18039A1981997-12-0303 December 1997 Improved Tech Specs Pages Re Section 5, Administrative Controls. ML20199D5471997-11-14014 November 1997 Proposed Tech Specs Section 3.0, Limiting Condition for Operation (LCO) Operability & Section 4.0, Design Changes ML20199E1361997-11-14014 November 1997 Proposed Tech Specs Section 3.4 Re Reactor Coolant Sys ML20198Q4521997-11-0505 November 1997 Proposed Tech Specs,Incorporating Improved TS (ITS) Bases Revs & Changes to Supporting Documentation Resulting from Responding to NRC Questions ML18038B9611997-10-0101 October 1997 Proposed Tech Specs,Allowing Bfn,Units 2 & 3,to Operate at Uprated Power Level of 3458 Mwt ML18038B9361997-08-15015 August 1997 Proposed Tech Specs,Extending Existing 7-day EDG Allowed Outage Time to Fourteen Days ML18038B9061997-06-19019 June 1997 Proposed Tech Specs Supporting one-time 14-day Limiting Condition for Operation for Each EDG to Accommodate Pending Vendor Recommended Maint Activities ML20138J3781997-05-0101 May 1997 Proposed Tech Specs,Revising TS-362 Amend for Section 3.8, Electrical Power Sys Which Addresses NRC Review Comments ML18038B8651997-04-24024 April 1997 Proposed Tech Specs,Submitting Revised BFN TS Bases Section 3.5.N, References, Reflecting Updated LOCA Analyses for Units 2 & 3 ML20137U1691997-04-11011 April 1997 Proposed Tech Specs Re Pr Neutron Monitor Upgrade W/ Implementation of Average Pr Monitor & Rod Block Monitor TS (ARTS) Improvements & Max Extended Load Line Limit Analyses ML18038B8341997-03-12012 March 1997 Proposed Tech Specs Re Extended EDG Allowed Outage Time ML20136F7851997-03-0606 March 1997 Proposed TS Supporting Planned Replacement of Current Power Range Monitoring Portion of Existing Nms W/Ge Digital Nuclear Measurement Analysis & Control Power Range Neutron Monitor Retrofit Design ML20134G5401997-02-0505 February 1997 Proposed Tech Specs Revising Bases Section 3.7.A/4.7.A, Primary Containment, to Delete Wording Re Maintaining Drywell to Suppression Chamber Differential Pressure Constant for Duration of Drywell to Suppression Chamber ML20132B7401996-12-11011 December 1996 Proposed Tech Specs 2.2.A Re Safety/Relief Valve Setpoint Requirements for Reactor Coolant Sys Integrity ML20117P3341996-09-15015 September 1996 Proposed Tech Specs to Change Unit 3 TS LCO 3.6.F.1 in Order to Perform Repairs & Maint Necessary to Return RCS Recirculation Loop a to Operations ML18038B7541996-09-0606 September 1996 Proposed Conversion from Current TSs to Improved STS Consistent w/NUREG-1433,rev 1 ML20117G7121996-08-30030 August 1996 Proposed Tech Specs Re License Condition on Compliance W/Thermal Water Quality Stds ML20113B1951996-06-21021 June 1996 Proposed Tech Specs,Revising Change in SLMCPR & Bases Description of RHR Suppl Fuel Pool Cooling Mode ML20112G3891996-06-0606 June 1996 Proposed Tech Specs,Revising Section 6, Administrative Controls, to Be More Closely Aligned W/Requirements of Improved Std TSs ML20117H5231996-05-20020 May 1996 Proposed Tech Specs Implementing Guidance of GL 87-09 & NUREG-1433,Rev 1 ML20108D9021996-05-0303 May 1996 Proposed Tech Specs,Withdrawing Amend 219,temporary TS 343T, Rv Water Level Instrumentation & Amend 228,temporary TS 347T,250 Volt DC Control Power Supply Sys AOT for Unit 2 ML20107F9721996-04-14014 April 1996 Proposed Tech Specs,Revising Minimum Required Number of Operable Rv Water Level Trip Sys During Period That RCS Instrument Line Excess Flow Check Valve Surveillance Tests Being Performed ML20096C4401996-01-10010 January 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B,Performance Based Testing 1999-09-28
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18039A8811999-09-28028 September 1999 Proposed Tech Specs Re Increased MSIV Leakage Rate Limits & Exemption from 10CFR50,App J ML18039A8241999-07-28028 July 1999 Proposed Tech Specs Providing TS for Operation of Oscillation PRM Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A8001999-06-0303 June 1999 Proposed Tech Specs,Reducing Allowable Value Used for Reactor Vessel Water Level - Low,Level 3 for Several Instrument Functions ML18039A6991999-02-22022 February 1999 Proposed Tech Specs & Bases Pages Incorporating NRC Approved TS Change 354,requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation ML18039A6601998-12-15015 December 1998 Proposed Tech Specs,Revising pressure-temp Curves to Extend Validity of Curves to 32 EFPY ML20206F8131998-12-0303 December 1998 Rev 12 to ODCM, for BFN ML18039A5041998-09-0808 September 1998 Proposed Tech Specs Providing TS for Operation of Oscillation Power Range Monitor Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A5001998-09-0404 September 1998 Proposed Tech Specs Re Use of Containment Overpressure for ECCS Pump Net Positive Suction Head Analyses ML18039A4791998-08-14014 August 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-33, DPR-52 & DPR-68 to Change Ts.Proposed Changes Decrease Frequency of once-per-cycle Instrument Calibrations by Substituting 24 Months for 18 Months ML18039A4611998-07-31031 July 1998 Proposed Tech Specs B 3.6-2,B 3.6-7 & B 3 3.7-2 for Power Uprate Operation Omitted Pages ML18039A4481998-07-17017 July 1998 Proposed Tech Specs,Adding LCO 3.4.10 & Accompanying TS Bases Provisions from Improved TS-362 Conversion Package as Adapted for Power Uprate Conditions ML18039A4091998-06-26026 June 1998 Proposed Tech Specs Section 3.4,allowing Units 2 & 3 to Operate at Uprated Power Level of 3458 Mwt ML18039A4021998-06-19019 June 1998 Proposed Tech Specs (TS) Converting from Existing Custom TS to Improved TS ML18039A3921998-06-12012 June 1998 Proposed Tech Specs Change 390,decreasing Frequency of once-per-cycle SRs by Substituting 24 Months for 18 Months in Affected TS SRs ML20249A5661998-06-10010 June 1998 Proposed Tech Specs Section 5.0,revising Administrative Controls ML20248C5151998-05-27027 May 1998 Proposed Tech Specs Section 3.8.1,revising AC Sources- Operating ML18039A3181998-04-16016 April 1998 Proposed Rev 2 to Tech Specs Section 3.6, Containment Systems, Converting from Current TS to Improved TS ML18039A2711998-03-16016 March 1998 Proposed Tech Specs Re Power Uprate Operation ML18039A2671998-03-13013 March 1998 Proposed Tech Specs,Converting to Improved Std Ts,Per NUREG- 1433,rev 1, Std TS for GE BWRs (BWR/4). ML18039A2641998-03-12012 March 1998 Proposed Tech Specs ITS Section 3.8 Re Electrical Power Sys. ML18039A2611998-03-0303 March 1998 Proposed Tech Spec Changes TS 393 Re Reactor Vessel Pressure Temperature Curves ML20199E8051998-01-23023 January 1998 Proposed Tech Specs Section 5.0 Re Administrative Controls ML18039A2401998-01-15015 January 1998 Bfnp Unit 2 Cycle 10 Power Ascension Test Program Start-Up Rept, for Period 970929-1105 ML18039A2221997-12-30030 December 1997 Proposed Tech Specs Re RHR SW Pumps Required for multi-unit Operation & Cold Shutdown ML18039A2151997-12-23023 December 1997 Proposed Tech Specs Section 3.7 Re Plant Sys ML18039A2181997-12-22022 December 1997 Proposed Tech Specs Section 3.8 Re Electrical Power Sys ML20217P5051997-12-0808 December 1997 Rev 10 to ODCM, Containing Markups to Rev 9 & 10 ML18039A2101997-12-0404 December 1997 Proposed Tech Specs Pages Re TS Change 362,suppl 7 Re ITS Section 3.1, Reactivity Control Sys. ML18039A2071997-12-0404 December 1997 Proposed Tech Specs Pages Re Suppl 9 to TS Change 362, Including Rev Pages to Improved TS Section 3.5 ML18039A2011997-12-0303 December 1997 Proposed Tech Specs Section 3.9 Re Refueling Operations & Section 3.10, Special Operations. ML18039A1981997-12-0303 December 1997 Improved Tech Specs Pages Re Section 5, Administrative Controls. ML20199D5471997-11-14014 November 1997 Proposed Tech Specs Section 3.0, Limiting Condition for Operation (LCO) Operability & Section 4.0, Design Changes ML20199E1361997-11-14014 November 1997 Proposed Tech Specs Section 3.4 Re Reactor Coolant Sys ML20198Q4521997-11-0505 November 1997 Proposed Tech Specs,Incorporating Improved TS (ITS) Bases Revs & Changes to Supporting Documentation Resulting from Responding to NRC Questions ML18038B9611997-10-0101 October 1997 Proposed Tech Specs,Allowing Bfn,Units 2 & 3,to Operate at Uprated Power Level of 3458 Mwt ML18038B9361997-08-15015 August 1997 Proposed Tech Specs,Extending Existing 7-day EDG Allowed Outage Time to Fourteen Days ML20210V1171997-07-29029 July 1997 Qualification Plan & Rept MIL-STD-462D,CS114,Conducted Susceptibility,Bulk Cable Injection Numac Reactor Bldg Vents Radiation Monitor TVA Bfn,Units 1,2 & 3 ML18038B9061997-06-19019 June 1997 Proposed Tech Specs Supporting one-time 14-day Limiting Condition for Operation for Each EDG to Accommodate Pending Vendor Recommended Maint Activities ML20138J3781997-05-0101 May 1997 Proposed Tech Specs,Revising TS-362 Amend for Section 3.8, Electrical Power Sys Which Addresses NRC Review Comments ML18038B8651997-04-24024 April 1997 Proposed Tech Specs,Submitting Revised BFN TS Bases Section 3.5.N, References, Reflecting Updated LOCA Analyses for Units 2 & 3 ML20137U1691997-04-11011 April 1997 Proposed Tech Specs Re Pr Neutron Monitor Upgrade W/ Implementation of Average Pr Monitor & Rod Block Monitor TS (ARTS) Improvements & Max Extended Load Line Limit Analyses ML18038B8341997-03-12012 March 1997 Proposed Tech Specs Re Extended EDG Allowed Outage Time ML20136F7851997-03-0606 March 1997 Proposed TS Supporting Planned Replacement of Current Power Range Monitoring Portion of Existing Nms W/Ge Digital Nuclear Measurement Analysis & Control Power Range Neutron Monitor Retrofit Design ML20134G5401997-02-0505 February 1997 Proposed Tech Specs Revising Bases Section 3.7.A/4.7.A, Primary Containment, to Delete Wording Re Maintaining Drywell to Suppression Chamber Differential Pressure Constant for Duration of Drywell to Suppression Chamber ML18038B8281997-01-31031 January 1997 Rev 1 to GE-NE-B13-01805-22, Internal Core Spray Line Flaw Evaluation Handbook for Browns Ferry Units 2 & 3. ML18038B8111997-01-22022 January 1997 Rev 0 to Browns Ferry Nuclear Plant,Surveillance Instruction,Inservice Insp Program,Unit 3. ML20132B7401996-12-11011 December 1996 Proposed Tech Specs 2.2.A Re Safety/Relief Valve Setpoint Requirements for Reactor Coolant Sys Integrity ML20117P3341996-09-15015 September 1996 Proposed Tech Specs to Change Unit 3 TS LCO 3.6.F.1 in Order to Perform Repairs & Maint Necessary to Return RCS Recirculation Loop a to Operations ML18038B7541996-09-0606 September 1996 Proposed Conversion from Current TSs to Improved STS Consistent w/NUREG-1433,rev 1 ML20117G7121996-08-30030 August 1996 Proposed Tech Specs Re License Condition on Compliance W/Thermal Water Quality Stds 1999-09-28
[Table view] |
Text
ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATIONS BROWNS FERRY NUCLEAR PLANT (TVA BFNP TS 210) 8507020505 850626 PDR ADOCK 05000259 PDR
PROPOSED CHANGES UNIT 1
r
?. Scconda Containment Incezritv
- 1. Secondary containmenc integrity means conditions chat the reactor
"-k~ building is inta'ct and the following are met:
a) At least one door in each access opening to the tu"bio '1'd ur ine b uil'ding, '
control bay and out-of-doors is closed.
b) The standbv.gas vacep treatment svstem is oressuie negaciveexisc.
is..s aceo.co operabl in' venose area~eV~ wnere seconaarymaintain e and can
'c 0.2g conte>n>enc inches oi es.o.
Mcegricg c) All secondary containment penetratxons requir uire d tto e closed durin usr uring accident conditions are either:
Capable of being closed by an operable seco con d aryy containment automatic isolation system, or
- 2. Closed by at least one secondary containment nment automatic isolation valve deactivated in the isolated position.
- 2. Reactor zone secondary containment integrity means the unit reactor building is intact and the following conditions are mec:
. a) Ac least one door between any open-'ng co cbe curbine bui1ding, contro1 bay and ouc-of-doors is closed.
b) The standby gas teatment system is operable'and can maintain 0.25 inches water negative pressure on the unit zone, c) All the unit reactor building ventilation system penetrations required to be closed during accident conditions are either:
I. Capable of being closed by an operable reactor building ventilation system automatic isolation system, or
- 2. Closed by at least one reactor building ventilation system automatic isolation valve deactivated in 'the isolated position.
Xf it is oesirable for operational considerations, a reactor zone mav be isolated from tne other reactor zones'and che refuel zone by maincai.ning at'east one closed door in eacn cor, ...on passageway between zones. ~ Reactor zone safety related features are not co;.,promisea by openings between adjacent units or re uel one,. unless it is des'rec co isolate a given zone.
~ To ef ectively control zone isolacio~, all cesses co the affected zone or guarded to p-.event uncoacroll access'wl 1 be 3.ocked ro e d passage to the unaffected zcneso
- 3. Refuel zone secondary containment integrity neans the ref ue 1 intact
~
zone xs ~
,<<and 'the following'zonditions are met:
a) At least one door in each access opening to the cut of-doors is c'osed nt, system is operable and dan'maintain .2S inches C
b)) one standby gas trearm
~ster negative pressure on the refuel zone.
c) All the refuel zone ventilation system penetrations required to be closed during accident conditions are either:
- 1. Capable of being closed by an operable refuel zone ventilation system automatic isolation system, or
- 2. Closed by at least'ne refuel zone ventilation system automatic isolation valve deactivated in the isolated position.
it If is desirable for operatio~al considerations, the refuel zone m y be isolated from the reactor zones by maintaining all hatches in place between refuel floor and reactor zones and at least'ne closed door in each access between the refuel zone and the re ctor bu'ild'ng.-'
Refuel, zone safety related features are not co;. ro...ised b- ope i the reactor ui ing unless it is des'red to isolate a given zone.
o e ective'ly control zone isolatiog, all accesses to the affected zone
~ill be locked or guarded to prevent uncontrolled passage to the unaffected zones ~
4B
PROPOSED CHANGES UNIT 2
- 7. Seconda Containment Tntezritv Secondary containment integrity means that the reactor
- 1. following conditions are met:
is intact and the
~
building 0
a) At least one door in each access opening to the ttur-b:ine buildingi '
control bay and out-of-doors is closed. .
b) The standbv .gas treatment svstem' n
is operable
" and can 5 h oary conraznment.~tegritj c) All secondary containment penetrations requirerequired to be closed close during accident conditions are either:
Capable of being closed by an operable se'condar containm automatic isolation system, or
- 2. Closed by at least one secondary contai n a nment automatic isolation valve deactivated in the isolated position.
1
~ ~ Reactor zone secondary containment integrity means the unit reactor building is intact and the following conditions re met.
. a) At least one door between any. opening to the turbine building, control bay and out-of-doors is closed. ~ ~ ~
b) The standb y g as t eatment system is operable'd can maintain 0.25 ~ ~
inches water negative pressure on the unit zone.
c) All the unit reactor building ventilation system penetratxons pe et t' required to be closed during accident conditions are either:
I Capable of being closed by an operable reactor b uz. zng vents.sation ld'r
~ ~ ~
system automatic isolation system, or
- 2. Closed by at least one reactor building ventilation system automatic solation valve deactivated in 'the isolated position.
Xf it is desirable for operationa'onsideracions, z reactor zone mav be isolated from the other reactor zones hnd the refuel zone by maistaf. ~ ann'no ' at 'east one closed door in each cor. ...on passage~ay between zones. ~ Reac"or eac.or ~one zone safety related features are not co"...promised by openings between adjacent it
~
units or re uel one,. unless is des'rec to isolate a given zone 1
~o e g ectively control zone isol tio~, all acce ses to
'>>wll b lod d guar d e d to p-.event uncontrolled p ssage to the unaffected
- 3. Refuel zone seconda"y containment integrity neans the refuel zone is intact and the following condition are met:
a) At least one door in each access opening to the cut-of-doors is closed Z
\ J b} ~ne standby gas treatm nt system is operable and (an"maintain .25 inches
~
<<ster negative pressure on the refuel zone.
c} All the refuel zone ventilation system penetrations required,,to be closed during accident conditions are either:
- 1. Capable of being closed by an. operable refuel zone ventilation system automatic isolation system, or
- 2. Closed by at least'ne refuel zone ventilation system automatic isolation valve deactivated in the isolated position.
it lf is desirable for operatio~al considerations, the refuel zone nay be isolated from the reactor zones by maintaining a11 hatches in place between refuel, floor and reactor zones and at least one closed door in each access between the refuel zone and the re cror bu'ilding.<<'
Refuel zone safety related features are not co" "o...ised '
...'se b y openings between the reactor building unless it is desired to isol-ate a given zone.
'so
~ :o e.=ectively control zone isol tiog, all accesses too thee a ffectedd zone "
<<"'ll be locked or guarded u to p-.event. uncontrolled passage t o t h e una fected "c dies ~
PROPOSED CHANGES UNIT 3
y7~
P. Seconda Containment Intezritv Secondary containment integrity means that. the reactor
- l. is intac't and the following conditions are met:
- .~~.building a) At 3.east one door in each access opening to thee ur -ne uilding, bay and out-of-doors is closed tu-b-'ontrol
~ ~
b) The standbv .gas treatment svstem
<ate~ ne~qi e aressuie i L'those h
is "
operable
- unere are-s and can secona noary contaxnmenc.ante>> t
')
All secondary'ontainment penetrations requi u re d to t be closed duuring accident conditions are either'.
1 Capable of being closed by an operablee secon se d aryy containmentnment automatic isolation system, or 2, C3.osed by at least one secondary contain a nment automatic isolation valve deactivated in the isolated position.
2~ Reactor zone secondary containment integrity means the unit reactor building is intact and the following conditions re met:
. a) At least one door betveen any open-'ng co the turbine building, control bay and out-of-doors is closed. W ~ 0 b) The standb y g as teat ment system is operable nd can maintain 0.25 inches eater negative pressure on the unit zone. r c) All the unit reactor building ventilation system penet penetrations required t'm to be closed during accident conditions are either:
-, 1. Capable of being closed by an operable reactor building ventilation system automatic isolation system, ox
- 2. Closed by at least one reactor building ventilation ion ssys t em automatic issolation valve deactivated in 'the. isolated position.
Zf it is desirable for operationa'onsiderations, a reactor zone mav be isolated rom the other reactor zones,:and tne refuel zone by maiptaining at'3.east one closed door in eacn cor.=..on passages y bet~can "ones. ~ Reactor 'zone
. safety related features are not co-...promised by openings between adjacent units or refuel one,. unless it is desirec to isolate a driven zone
- To e 'ectively control zone isolation, all accesses to t". e
>>ill be 3.ocked uar e to p.event uncontrolled passage to the unaff u Larzecte d zcneso 4A
- 3. Refuel zone secondary containment integrity neans the refuel e uc zone is intact and 'the following'conditions are met:
a) At least one door in each access opening to the cut-of-.doors is closed b) The stand&y gas treatment system
~ater negative pressure on the is refuel operable and Can"rr'ain n maxntaxn'25
. a inches zone.
c) All the refuel zone ventilation system penetrations required to be closed during accident conditions are either:
- 1. Capable'of being closed by an operable refuel zone ventilation system automatic isolation system, or
- 2. Closed by at least'ne refuel zone ventilation system automatic isolation valve deactivated in the isolated position.
it If is desirable for operatioaal considerations, the refuel zone nay be isolated fro h s y maintaining all hatches in place between refuel floor and reactor zones and at le st one c1.osed door in iz eac e h access bemeen the re C uel zone and the re cror bu'ilding."-
0 r e uel zone safety related features are not co-.. ro...ised b o enin s bet~
he ."eactor b 'ld' 1 't is d es're i '" d to isolate a given .zone.
.o
'P e pc ectively control zone isolatio. all a. acce ses to the affected zone
'e oc e or guarded to prevent .uncontrolled passage to the unaffected 4B
ENCLOSURE 2 DESCRIPTION, JUSTIFICATION, AND SAFETY ANALYSIS BROWNS FERRY NUCLEAR PLANT UNITS ls 2o AND 3 (TVA BFNP TS 210)
DESCRIPTION The amendment would expand-.the technical specification definitions to state that secondary containment integrity exists when a valve in a ventilation system penetration is deactivated in the isolated position.
JUSTIFICATION The present technical specification for secondary containment will not permit maintenance on an automatic isolation valve when secondary containment is to be maintained. This presents a potential safety concern in that it could severely limit the plant's ability .to perform maintenance on secondary containment automatic isolation valves when it is necessary. This provides the possibility of having the isolation system in a degraded condition for the;-;
period of time needed to achieve primary containment integrity as required by the present technical specifications. During refueling operations the time to achieve primary containment integrity would be long and the risks involved in doing so would be much greater than performing the needed maintenance with the penetration already isolated by another valve in the line.
SAFETY ANALYSIS Secondary containment ventilation system isolation dampers are normally open isolation valves which close to prevent a radiological release from the secondary containment to the environs. Each reactor building and refuel zone ventilation penetration has two such dampers in series. If one damper must, be made inoperable (for example, to perform maintenance), deactivating the other damper in the isolated position will ensur'e that the secondary containment function will be fulfilled'for that penetration. Hence there is no reduction in the margin to safety as described in the FSAR. The proposed definition of secondary containment integrity is consistent with BWR Standard Technical Specifications.
ENCLOSURE 3 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION BROGANS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 (TVA BFNP TS 210)
DESCRIPTION OF AMENDMENT RE VEST The amendment would expand the technical specification definitions to state that secondary containment integrity exists when a valve in a ventilation system penetration is deactivated in the isolated position.
BASIS FOR PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION The Commission has provided guidance for the application of criteria for no significant hazards consideration determination by providing examples of amendments that are considered not likely to involve significant hazards considerations (48 FR 14870). These examples include: "(vi) A change which either may result in some increase to the probability or consequences of a previously analyzed accident or reduce in some way a safety margin, but where the results of the change are clearly within all acceptable criteria with respect to the system or component specified in the Standard Review Plan (SRP): For example, a change resulting from the application of a small refinement of a previously-used calculational model or design method."
The proposed amendment is encompassed by this example in that the revision reflects the requirements established in the Standard Technical Specifications under the definition 1.30 Secondary Containment Integrity (NUREG-0123, Revision 3). Therefore, TVA proposes to determine that the proposed amendment does not involve a significant hazards consideration.