ML031420357

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Attachments 2 & 3 - Browns Ferry Unit 1 Response to Generic Communications Issued Since 1985 & Presentation Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 1 Regulatory Framework
ML031420357
Person / Time
Site: Browns Ferry 
Issue date: 05/13/2003
From: Jabbour K
NRC/NRR/DLPM/LPD2
To:
NRC/NRR/DLPM
References
TAC MB7679
Download: ML031420357 (40)
v • d • e


Text

BROWNS FERRY UNIT 1 RESPONSE TO GENERIC COMMUNICATIONS ISSUED SINCE 1985 File Name Date Description

Response

Bulletins BL-02-02' 08109/2002^^ Reactotr Prsure,esseHed ndV6ssel Head Penetraton Nozzle lnspection Toholdersfoperffrglicenses for oili stef.react for ifoimabon:'-'iS, BL-02-01 03118/2002 Retber.PressUre-Vessel Head DogrEdatioharid Reator C6olaiht Pissre;.. To'holdersbf operating licenses for.boiling sterreacor for.info' a

'__-_.________W Bo r ir

.;,,,s boilin waterreactor fo infomaton BLO1 -01 ' c,{>

08 /03/2-c 00X31 i" Clrcumfereli ail Cmcldng of Reactor. Prstire Vessel Head Penetration Nozzles To holders of 'beirating licenses for, pressunzed 'ater. nuclear owr react rs 1tF

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4 IIP BL-97-02:

0 /2311997.

PUnctU

.Te ftn bf'Shi n Pcaegbsdhd& 10 CFR Part 71

-^

For.Actloh-A Al holders of NUoleai Regulator -ComiiSlon Certficates of BL-97, il 7-01

i i

t3099 Po rtt for Etoh~~ isCalibration Dose Rcte, or,Redlato psure 7j For Acffot ;-onectr iice isees that possess Oneo

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~~________

ot-;>1g 4.a A:esurem sr iicoree ModeB 53 nd; 3Oi cgmeiter6e-Elec miiet r

~ef Iniess ch~~lti~

BL 96-04-^:i;

?2; 07105/1 998 ChP h

i a

bOt1e Read InSpntFuel Stor ge aid:

Actohi§-oily eu sted from oaddessees wh6 selicnsees iMth TratispiSrt~~~~~~t1onCtisks

~~~~~-7~~~'i:6n ot spnt strg Insa lation-

-db'fp

.~. ~

~hd l~ of ~e1i~tMo or linqf.spet,ue BL-96-03 05/06/1996 Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in

,__________ Boiling-Water Reactors BL-96-02 04/11/1996 Movement of Heavy Loads over Spent Fuel, over Fuel in the Reactor Core, or IVA letter dated May 13,1996 - No commitments made.

over Safet-Related Equipment SU 3-8/

6-C01 dlnrttlori Problems

Q;,.-.SentRt7'allShittrei

~~~~~~~~~~~~

~

~

~

~

~

~

~

~

J Ihoders of pressurzedWatter reator(PWR) opertibng lcehses;1`-

BL-95-02 10/17/1995 Unexpected Clogging of a Residual Heat Removal BL-95-O(]V 4- 01/13/19959 Quality Assurance Pr'gramhforTrnsriaton of Radioactive Materia.

For Aphy licensees-

.o C>-

BL-9 4-02.^;,.,f ;

c-1111411994 - CoIT6slon Problefi h'Certain Stainless Steel PackagingUsed toTransport, egistered users of Model NsNI-21PFI an'd:GE-21PF'1aAhium

,ia.-,;.

, s<,,G>

ex~ti'Uri Hex fuord'nrid trns" n

L-94-IL'"

04/i14/i1994. Potal Fuel PoDridnCasdbindequat MaineMande Practic.esat-For Actioh"AI holdOrs of liobnsesfor nuclearower eactors that are-,-"~7

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

~~~..

Diasd~~~~~~~~~~~~~~nUri1t1, In ihe fuel pool (exb~~~~~~~~~~~

Ipt)(ec p&nia~ehiy~hUtd&v~

with~pehfiie spent

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BL-93-02s1 02/18/1994 Debns Plugging of Emergency Core Cooring Sucbon Strainers BL-93-03 05/28/1993 Resolution of Issues Related to Reactor Vessel Water Level Instrumentaon in BWRs BL-93-02 05/11/1993 Debris Plugging of Emergency Core Cooling Suction Strainers BL9301

.i.

04tt201 993i> Release of.Patients After Brachytherpy.Treatrent With Remote-Afterloading.r Addressees -Brachytherapy,Licensees'AUthorized to Use Afterloadin 1~~~ DeVlce~~~~~~~

.4) tiracny~~~~~~~~~rneay lrit(6) Caiobl abf. Deliveing Dose ates Greerta50 BL-9203, L12/08/192k Release of PatlentsA For Act on Brachytharapy Licensees Authorized to Uses the Omnitron Model 2000 ghbo D ai (D

A dn hg ' E a erapy it BL-92-01 sl 08/28/1992 Failure of Thermo-Lag 330 Fire Baier System to Perform Its Specificed Fire TVA's April 14, 1993 letter commits to complete removal of thermo-lag.

Endurance Function Completion letter submitted October 29, 1996.

BL'-92-02

- 08/241992, Sefet,Concens Related to End of Life'of Aging Theratrnics.Teletherapy-'

For Action -All Teletherapy4Llcense r'

e ni-;,-,.t.

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tt-?Li V'~te I

BROWNS FERRY UNIT 1 RESPONSE TO GENERIC COMMUNICATIONS ISSUED SINCE 1985 File Name Date Description

Response

BL-92-01 06/24/1992 Failure of Thermo-Lag 330 Fire Barrier System... Cabling in Wide Cable Trays TVAs April 14,1993 letter commits to complete removal of thermo-lag.

& Small Conduits Free From Fire Damage Completion leter submitted October 29, 1996.

BL-9lo1s1*'

. '07/27/1993 ' Reporng L o Crcali SafeFt Cont ls t

-, orAction-AlueIfabrl' ofcilitie e::.'&:*;-.

BL-91.A01-f U-:c10Id8f199P.t Reo'rn Loss'ofCricli Sfeth Cbnrolst.W:/>7i Addrseas.II fUelcycle andaniunifelreeah and develo-ent

.i n-, osso ean ra s.,.'

--t-BL-90-01sl 12/22t1992 Loss of Fill-Oil in Transmitters Manufactured by Rosemount BL-90-02 03/20/1990 Loss of Thermal Margin Caused by Channel Box Bow TVA's April 24, 1990 letter Informed NRC that BFN does not use channel boxes for a second bundle lifetime.

BL-9-01 03/09/1990 Loss of Fill-Oil n Transmitters BL-8901 s2

-, O06/28/1991 Failure-of,WestInghdUse Steam Genehator-Tube Mechanical Plugs Addressees Al hiders of bperating loenses brbns iction permits SJl,sr-M ds fz;; */ f*;si

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'r'sS rt'4-' fteea"a n^4sbriss, b0-t'U m'

fori'.7" ;

r

~ ~~~~~~~~~.6e ed riI BL-89-Qlsi ~

As'>;:

'Il/14/11

.. Falturo 6f!Wdtlnghou's Steam Generatr TubeMechana IPlugs -:

Addre A

s holders ofoie,rattg lirises-or'66nstr on rmitsfor.i.<

'-~~~

-j

<K~~~.~~77~~P 7i-~~~::~~

-2>7~~~7~~-W pressUrl&

w"trr a

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'ff'Rei90pera Rsf'-^.',

fdffses' lti

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'rrn ;t t f BL-89-02 07/1911989 Stress Corrosion Cracking of High-Hardness Type 410.. Bolting.. Anchor TVA's January 17, 1990 letter informed NRC that BFN does not have any Darling S350W.. Swing Check Valves.. Similar check valves in its safety-related systems within the scope of NRCB 89-02.

BL-I-017a

,05/i51989-Failure ofWestlnghodse'Steam GeneratorTube Mechanical Plugsd Addrese :'-All holder of p n licenses or onstu...eris fortn

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.'-<,l,~,.

--.~

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pressu ze -watbafth wR BL-88-10 sl 08/03/1989 Nonconforming Molded-Case Circuit Breakers BL-807s1 12130/1988 Power Oscillations In Boiling Water Reactors (BWRs)

BL-88-1.' I>l; t

r- -.

/1220/1988 PressurIzer Sure Line Thermal,Stratificaton

'ddresse s AIholder o eatinglcansesor constu ctio ermitsfor

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1,

-,.~1

, 7 X BL-88-10 11/2211988 Nonconforming Molded-Case Circuit Breakers BL-88-9

/ 0712611988 ThimbleTube Thnnig in'Wstfnghouse Rea os

-ddresseesX' All holders of operatng licenses or onstructolo permit for

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  • ~~~~~~.T ntA-I`Wsbnh6ighR6so W&

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'-.dgl6dL clear.06er reaMtis -theUtz bI'tto 4~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~m n

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BL-88-08s2 08/04/1988 Thermal Stresses in Piping Connected to Reactor Coolant Systems TVA response provided October 24, 1988. TVA concluded that there were no unisolable sections of piping connected to the reactor coolant system (RCS) which could be subjected to the thermal stresses described by Bulletin 88-08.

BL-88-05s2 08/03/1988 Nonconforming Materials Supplied by Piping Supplies, Inc... and West Jersey TVA response provided August 25, 1988. Closed in Inspection Report 90-33.

Manufacturing Company BL-88-08s1 06/24/1988 Thermal Stresses In Piping Connected to Reactor Coolant Systems TVA response provided October 24, 1988. TVA concluded that there were no unisolable sections of piping connected to the reactor coolant system (RCS) which could be subjected to the thermal stresses described by Bulletin 88-08.

BL-88-08 06/22/1988 Thermal Stresses In Piping Connected to Reactor Cooling Systems TVA response provided October 24, 1988. TVA concluded that there were no unisolable sections of piping connected to the reactor coolant system (RCS) which could be subjected to the thermal stresses described by Bulletin 88-08.

BL-88-07 06/15/1988 Power Oscillations In Boiling Water Reactors (BWRs) 2

BROWNS FERRY UNIT 1 RESPONSE TO GENERIC COMMUNICATIONS ISSUED SINCE 1985 File Name Date Description

Response

BL-88-06 7z.

,' 06 1411988;Z Actions-ToBeTakerq forthe.Trnsp'rtor of ModelNo SPEC2-1""

Addr' e's:"'AIINRClicen'ee at ioHzed t 'manfc '- disribt br I.

R1au-lgeri Xp r Device r

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heate d

ia' i

c sUe ebur BL-88-05s1 06/15/1988 Nonconforming Materials Supplied by Piping Supplies, Inc.

and West Jersey TVA response provided August 25, 1988. Closed in Inspection Report 90-33.

Manufacturing Company.

BL-88-05 05/0611988 Nonconforming Materials Supplied by Piping Supplies, Inc.

and West Jersey TVA response provided August 25, 1988. Closed in Inspection Report 90-33.

Manufacturing Company...

BL-88-04 05/0511988 Potental Safety-Related Pump Loss BL-88-08s3 04/11/1989 Thermal Stresses in Piping Connected to Reactor Coolant Systems TVA response provided October 24, 1988. there are no unisolable sections of piping connected to the RCS which can be subjected to stresses from temperature stratfication or temperature oscillations which could induce unacceptable cycling stress fatigue.

BL-88-03 03/10/1988 Inadequate Latch Engagement in HFA Type Latching Relays Manufactured by General Electric (GE) Company Rap yPro~~~~~ag~~tlng Fatigue,Cracks in Steam Generator bf pert trcti BLB8-02 0

WO2KI5/1988 RaPId1ybs

,Pr JngAFaigue Crcks rinStAdeoGenefTubesaIng licenses or const on permit or

>:~~.::~

W~sdh~h6~'(X d

ns er. poer, reactors~t seam generaorsa-BL-88-01 02105/1988 Defects in Westinghouse Circuit Breakers TVA response, dated April 13, 1988, stated the Bulletin was not applicable to BFN.

BL-87-02s2 06/10/1988 Fastener Testing to Determine Conformance with Applicable Material TVA responded by letters dated March 16, 1988, April 15, 1988, July 6, 1988, Specifications September 12, 1988, and January 27, 1989. Closed by NRC letter dated August 18, 1989.

BL-87-02s1 04/22/1988 Fastener Testing to Determine Conformance with Applicable Material TVA responded by letters dated March 16, 1988, April 15, 1988, July 6, 1988, Specifications September 12, 1988, and January 27, 1989. Closed by NRC letter dated l______________________________________________________________

August 18, 1989.

BL-87-02 11/06/1987 Fastener Testing to Determine Conformance with Applicable Materal TVA responded by letters dated March 16, 1988, April 15, 1988, July 6, 1988, Specifications September 12, 1988, and January 27, 1989. Closed by NRC letter dated August 18, 1989.

BL-87-01 07/09/1987 Thinning of Pipe Walls in Nuclear The purpose of this bulletin is to request that licensees submit information conceming their programs for monitoring the thickness of pipe walls in high-energy single-phase and two-phase carbon steel piping systems. TVA responded by letter dated September 18, 1987. SER dated August 31, 1988.

BL-86-04" -

0/29/1986 > 8 Defes.Telethe'rapy.Timbr That May Not TerminatedJreatment Aose Addresses :-AI NRC licenses authorized to use cobaft-60teletherapy'units.

BL-8603 10/08/1986 Potential Failure of Multple ECCS Pumps Due to Single Failure of Air-Operated TVA responded by letter dated November 14, 1986. The single failure Valve in Minimum Flow Recirculation Line vulnerability discussed In this bulletin does not exist at any of the our nuclear facilities.

BL-86-02 07/18/1986 Static"0" Ring Differental Pressure Switches BL-86-01 05/23/1986 Minimum Flow Logic Problems That Could Disable RHR Pumps TVA responded by letter dated June 2,1986. BFN's as-constructed configuraton precludes the single failure vulnerability regarding the minimum flow valves for the RHR system.

3

BROWNS FERRY UNIT 1 RESPONSE TO GENERIC COMMUNICATIONS ISSUED SINCE 1985 4

File Name Date Description

Response

BL-85-03s1 04/27/1988 Motor-Operated Valve Common Mode Failures During Plant Transients due to TVA responded by letters dated May 13, 1986, September 30, 1986, May 1, Improper Switch Settings 1987, and July 15, 1988. Outstanding programmatic commitments to be Implemented under program that addresses Generic Letter 89-10.

BL-85-03 11t15/1985 Motor-Operated Valve Common Mode Failures During Plant Transients Due to TVA responded by leters dated May 13, 1986, September 30, 1986, May 1, Improper Switch Setffings 1987, and July 15,1988. Outstanding programmabc commitments to be implemented under program that addresses Generic Letter 89-10.

BL-85-02 11/05/1985 Undervoltage Trip Attachments of Westinghouse DB-50 Type Reactor Trip TVA responded by letter dated December 3, 1985. Brownsr Ferry does not Breakers utilize Westinnhouse DR-SO reactor trip breakers.

BL--01 W~>8N

.*0I29/198 Steam lndlng of Aulily F~eedter Pum ps 6ft Certin PWRlci seesndPR Pholder aretistedto take further tictioh to s,i~ ~iTI~I~OV~ntS ~rdiii ti~i~UTflui~ ~tth~iiitcioioles anbg d~~~~~~~~~~~~~~oe os hO e ns en&orpInnied29 is.

BROWNS FERRY UNIT I RESPONSE TO GENERIC COMMUNICATIONS ISSUED SINCE 1985 File Name I Date Descri tion Res onse Generic Letters g199002er 08t2311999 NRC Generic Leter 99-02 (Errata): Laboratory Testing of Nuclear-Grade November 18, 1999 TVA letter closed for all three units. Acceptable testing Activated Charcoal standards references in BFN Technical Specifications.

g199002 06103/1999 NRC Generic Letter 99-02: Laboratory Testing of Nuclear-Grade Activated November 18, 1999 TvA letter closed for all three units. Acceptable testing Charcoal standards references in BFN Technical Specifications.

g9901 0510311 II999 NRC Gee Ltt 01, Re'entNur Material fet aid Safeguards<; Addrsse rnat&rldlic nses

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l Deasioni 66; ng empuan s..q.<t,i t;i g1980059=4!-n><

11110/198. NRC Gener'cLeter9-0: Boil Watb' Reactor LlcenseesUsg of the4-,

This generi' letter,re4Uir n' pec1fic acton or Written response-8WRViP-0 5rtt6"R R

'cfieR e,fr6oAUTie6 Ekamjn g198004 07/14/1998 NRC Generic Letter 98-04: Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System after a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment gl98003 06)2-2!-

t99:

RC Generic Letter 98-3 NMS censees' dnd Certicate Holder'-Year.-,J. For Aciot¶ Altlicens or certii cate holdefsfor eianium heafluoi

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producton ln iink r nh ieni plnts fidr niui' fte fabniaton Rdddlh-'s6 Piiofpans xitis~&hU~c~

o5~at6n.

gl98001 05/11/1998 NRC Genenc Letter No. 98-01: Year 2000 Readiness of Computer Systems at

~~~~~Nuclear Power Plants' g198001sl 01/14/1999 NRC Generc Letter No. 98-01 Supplement 1: Year 2000 Readiness of Computer Systems at Nuclear Power Plants g19700,6,=,-2,,m,>le ;1V72/30/1997.- NRC Gehed Letter,97-06 Degradation of Steanm

'GeneratorA nternals

, Addresse Alholders of operating,lrense §foressurzed*terrea or

.l97004 10/07/17 NRs

,e xcepttho hnve nenty ceased operatio'h an8 haui d

for Emergency certifieling and Containmentd tha feo Phu banen reov r

gi97005,i"..t 'i; 1

Wf-711 1997s'f? ANR l Ftnaffcle t 7-o5 Stem-Re GeeratTu nspein Techner e AddresseesAll holdera f opern Licen esadrse§ for, pressunzeddWate -reat

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exett"osewh iVe~ penmanenty cease operations-andav 5,<4,,S,<,-ArS4

certdA, i e rtha't{'

fue has be pera Y rioed eV'om The rear rVe l

g197004 10/07/1 997 NRC Geneno Leter 97-04:Assurance of Sufficient NetPositive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps g197003

~~'07/09/1997,~! AnnUal Financial Update of,Surety Requiremnentis For Uraniumi RcvrAdressee Uaniumi Recovery Licensees and StateOfial 9172..'-

w --051151997: Rivsed Cohents ofhe Montl Operatng ReoU' ei'sA';w,;'<)

This generc,leterrequires'ho-specii'actonowntte resonse-:.;.-'-;.

g197001-',.X;.es

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04/01/1997' Dei'dation of.ControliRod Dnve Mechanisi Nozzle'and Other Vessel ClosUre' Addressees A l holde of? operating licenses for pressurized atereators

________________________5,L

l.

ead Penettions WR 5

BROWNS FERRY UNIT 1 RESPONSE TO GENERIC COMMUNICATIONS ISSUED SINCE 1985 File Name Date Description

Response

gl9607, "

i

',12/05119 Interim Guidance bh Transdortatorti of Steap G

tr Atingcensesanddeommissonigfacilies

~ -.w~.'. a u-... With possession-on in r, pee, gl96006sl 1111311997 NRC Generic Letter 96-06, Supplement 1: Assurance of Equipment Operability and Containment Integrity Dunng Design-Basis Accident Conditions g196006 09/3011996 Assurance of Equipment Operability And Containment Integrity During Design-Basis Accident Conditions g196005 09/18/1996 Periodic Verification of Design-Basis Capability of Safety-Related Power-Operated Valves g196004 06/26/1996 Boraflex Degradation In Spent Fuel Pool Storage Racks TVAs October 22, 1996 letter completed requested actions. No boraflex used.

g196002)

S;>,<

n 21 3/1 Reconsideration of Nuclid eribf Nuesar. Poe Plah eri re s Associa e te no specifi lio.or Written response

.1w?

gl96003 O1./5^i r 0/1996,'

NRCiGener1o LettdFS0:- ReTocaton of Th rsU emraueLmt censeeS' and applicant wo choose to~adopt this line item Improsvement are q196001 01/10/1996' Testng of Safety-Relabd Circuits R

g19501&-

ns n

+r

+12t511995 Rel6Oatiotl of SboadTechnicatlo SR u

Tee Reqteufrtte i1>

Llcohs that do notwi shto amend tecKnical speifictionsi ae notexpce 9196<iaig-t;W^W55.<..X=

lge eroW glS -4i1I03/199i.

Monit o rmiing alf,Shrinigofrs an a d CrlsofRadioactivte Maials'-.

No pe8 bll on h wrte r ohse' is rqUred -' >.~si $. H-.-r-I95

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i 9195007 08117/1995 Pressure Locking and Thermal Binding of Safety-Related Pover-Operated Gate Valves 0811511995 Changes in th'e Oeror Ucensin Program:'9--'.'-'- -

i This gceneric ietTer.aLI

`lresn siic actr-Writerlp gl95005 -;.-':Y.r/9 '

j1995 : Vo eBase,,Reair Criteria fr. WestinghoUse'Steam 'Gnertoru bes' Adde ssees:.'A ilholdesofoperain i ens s or, onstrton perm forn

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9

>7,t._g, AffeWdbjuIde T ohiiSr ion'6ai6n^r& C ;'a&re6os'PR g19c003 0412/1995 Clrcurng altrackted of SteamGeneratorTus ;r Addresse Allholdesof ertn enses orconstrcton pe

for, Stm 9

tt r

9

' ' ffi :' 6*tt -S~~~~~~~_qrem sasPh-dc 4re exob m

':N 2 edS g19504 0s.,';'

428/199.. Mof-o

-Theming o Sfhwmiedeksu aro Radio _

e ame Iss e N speCiC o

wrwn' r 5o',is require i, 3190 '1+

.;-Ys,6,,. t t19 Vountr.eFR50 "yfA NOtinalO5e6abria tIoaN ur Da '"'ttd,

-rorEleor oly

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g1950021 04t25t1994 Usterofanlarcpr S rep ortio racking ofdj C on Lhrcudsihg oigital NoWeaicatotrewrtnepneIsrqie ReactorstoDgia

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gl9402 04117/1995 LongTrm aouting and Carrad of aferieP ofRdo erOperat edates foi 7lterranlar SrstCorrosin CR

.195000g R

andCUpa of Itim Operating Recommendations fo Thermal-Hyri Intaiite inCBrsio 6

BROWNS FERRY UNIT 1 RESPONSE TO GENERIC COMMUNICATIONS ISSUED SINCE 1985 File Nane Date Description

Response

g194001

!O5/3I I.

994, Removal of Accelerated Testin and Special Reorting Re'urehient fort.

Licenseieaction topopses changes or'relie fomdcketed commitment'

___________ffff>-

i-,C;<,.->mergencye Geneor n

en r

i

/29(1199 ReoWon of Technical Specfica'ton Tb Of IstrUtentResporise Tim.

oTS thar,es iidrth --

dancold

'ofthis gnrien

~~~ Limits&~~~~~~~~~~~~~

'C KR fl~mbt Ulee is Voutry.

e-TSch4h gi93007rh9nT-<;w st12 1993 ' Modification of the TfnIc!i Speqicatbo-Administ Oil ConlReciemen Ucensee ao 0

T anes Undertheidahe fis ener c-77.7

.-';;er;

. >,j,,,.2l,j? ForS e cr4ai' cinf Plans - w< Vi'*

g;K9 JU+' letter i'~i~ia~2 2 ~'Ki~:<Q?'K

9,

, 1/219 Research Resultn Generc cSafetyl'sUe10, -iping'a' eU he'aof Hehl ' In th gened letter eth NRC is onlyx mmunaing Informat6o resul oU

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.74 i gl92008 12/17/1992 Thermo-Lag 33G-1 Fire Barriers TVANs April 14,1993 letter commits to complete removal of thermo-lag.

Completion lefter submitted October 29, 1996.

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~:1O0/192 'X 01i9'e of NUclear'Reacto sR'eulation'Redrgehizatori ss'-".

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g192004 09/0411992 RCorkhop on the sstemeatict Rectrn ofslae Lcensel erformnion i

eei,~rcnan oIfriOinclabnr~leet.

BWRs Pursuant to 10 CFR 50.54(f)___________________________

gI92001 rs.html 05119/1995 NRC Generic Leter 92-01, Revision 1, Supplement 1: Reactor Vessel

.Structurl integrity g192001 rs 05/19/1995 NRC Generic Letter 92-01, Revision 1, Supplemenyt 1: Reactor Vessel

__________Struclurl Integrity___________________________

g192003 03/19/1992C 4' Comaton'of th Urh icnigBssqRqetfr outr ariiai

. Inlgiig-this letter,~the-NRC Is Imposing no-neW requiremients orta

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. n Pitotl4 i4aT~ih~

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03106/1992 V Resolution of Geirldi Issue 79;.Unanalyzebd Rdabtor.Vessel.(PWR),Thermal1 Ini issUin this. l6ttelt~ the NRC Is imosngn nbW 7

BROWNS FERRY UNIT 1 RESPONSE TO GENERIC COMMUNICATIONS ISSUED SINCE 1985 File Nanie Dbte Description

Response

g192001 ri Reactor Vessel Structural Integrity gl92001 0212811992 - Reactor Vessel Structural Integrity gl91 019 1;t:i.g.

21i9/119 Infomiatlon to Addrsse Regarding NewTelehone Numbers for NRC Offices No secif actionr ten onse Irequired e,->,;-i:,,b,.;

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.,:-Wh.z9,¢L i Nor t 2f ';

r g11018 i

711 1 Ifo n

a 90

'ReingTw'NRC I-'jPs On Resltionof )

D ded' a

' No-see a lns are

red g191017 4 10171991 Generic Safety lsslJd.

'BlTI6ng De dadon ordFailure in NUclear_er.

i-lowever the suggstonsdnt iie inti on n ngon a,

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0191 018/197, RC`erbf6 Lttr9-l8R Inort9tiO tiLcesethRgadlni hisgeerc dtt hotie lWhspciicactonorr Gdheo6 66 Ni Dsgtutoh ofF~eaild& ii' Nohcon rtI RC

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t-c~ ed9p~rtttr Ndcea' fIi r

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un 5iI

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BI9Oprakers,"

i~

Pursuant Oterated Valve ProbleR 50t evaluation actions oncrluted thatthe adiisthtigels i let gi9iOo8'-

>=--*:- 5 1 gj 1R' o atflo >

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-E g19100 Resolution7 ofGnrcIseA3,rdqyo aeyRltdD oe a 7 92dcmne TV eopeto WHO commitesS alneenis Supplies

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ehandueietoP S-...+. :-.Nrsos'hsetelr ie.'-'>*j.<-S:.t 9i91,<X~~~~Oerto NaionWx tMa hagmienaiiSiot S

ur updated scheules to be oluntari Ay ruThth thedNR s?lugq en frSeturned t olha ?

gl9Ol-:-

i-o19 Resolution ofe aI 48, v LCs.n..2Val Ins. Buses" an4~51-9. "Itlcks Tie 1As Api-019 opee o l hreuis a opee t le fil~ ~

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0518199 Remoa oin omisp loriLtsFo Tehnca Specflcatiosprl>

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04/02/991 Changes biTebnical SecificatoSeillanc ItrastAcoodta24nyrsoIe o hedlb NRtuoeto for' SUIchalftgesjUd isblttre o-gl91003 0731061992 Res,outn oiSf GIs48,LCs...

htE Via lnt ue, ad4,"nerok.

i Thes Arin In, t9Is completed foralre vounits BF aopeet g191 002

~~~~~~reers," Pursantllovii

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tor PreprCdFR 5Diposa L evso n has o rnded thf the obainstrieporoefs nd dlaevaiony thn ecomdabon ofitheR GLureret.110 F I~

Moifcaibi~'fsirellnc ItNa-WWti

'ssinletir PW,P Tisjttl. dotto a

pp 8

BROWNS FERRY UNIT 1 RESPONSE TO GENERIC COMMUNICATIONS ISSUED SINCE 1985 File Name Date Description

Response

g190O1

'T-0`110411991 Remvloh hdule fof of Reator Vel ia te in s o

t idance provided i this: e tI'l""

i9007>

gm d..

1 11h1/199 O ebtor iceiilnt Nattal E5camin"ion Sche ulen -

h0-'d Yor a

dules, tob#:Vbltntlyi biii fnlokd gl9000t6>fY 08 9

o e soon of G ic sues 70; "PORV. and lokValve Reriab0ite 4,-

,P0R TO:eiALLbPRESSUJIZED WATERREACTOR LICENSEES AND'ATE-RE T

P

'-;tV+ AaaffinSioP LIOIfyIot~CDOf i iR*!

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C1NkWVC N

E ti1CENEEE g190005r <.tJn, q z 08110/19902 Gtidane fi~OrformlhgTempory Nbr1Cod'Rjalr of ASME.Cod6'CIaks51L e

t d

ta wi b Idrdby the NRC,staff Si 01d6flif SM" M`~~~~~~~~~~~~h

~

hdittief Is~ ~iritd "

lJh fo ay o-cd 1900082" N.'p713111i92, FaiiyEOepliAi hsGiio W

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g190004 06/25/1990 Request for Information on the Status of bcensee Implementation of GSIs The requested status of FSl's was provided on May 30, 1990. There were no Resolved With Imposition of Requirements or CAs commitments made in the submittal.

g190003s1 06(1 511 99Q Re1ixt1off t Star P6§jtJ1oh l 6Motbtwte83-2~hl hdh:Qdfi cto

_______n e

Qr1 in itp onyad MW~n ri1 g!ss~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~Cffw,s jili -

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w

-,At"Atte furdhi1bbts fOlShUbbbi~ eiat1he6i on nt ra1 C cteCo irewthh nmtlTeqreme rfial Inspeto nevl I

-~~~

Actio~h~

P

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gl90003 04/25/1990 Relaxation of Staff Position in Genenc Letter 83-28, Item 2.2 Part 2 "Vendor TVA responded on August 24, 1990. TVA nto'fied N RC that all commitments Interface for Safety-Related Components' had been completed by letter dated October 15 1990.

032/990"t Alentv eur'~t o ulAssemblies Ini the Design l7witures'Section -of No repOseI rbquird to, thI9 letter-g190002,,

.02101/19'0 Atat' ReqUf'mOnts fdr Fuel Asserblls in the Deslgn Fres Sdion of This encsute proMdes guidah for,the prepar on of a license amendment X.

. gm

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t

° zS.,6 (TSi g19001 1111190 RuAs fo V~rntay P tilp~Ion~ '

4 VOLNTAY P3TIIPAIO! IN NRCR.

LtRY IMPACT. SURVEY gl89001s1a.-; ~^1lj4/1.9'i NUREG13 abd:2 "Offsft Dose Calculato Mahal GUidakrib-Standadr Enclosed,nforornifor is a copy f thebje NURE6rePor This

-` ~-.t,b

rcEt, u,n,,

eURtEt n

is rapr coat nt rmpose ahynew tefu'rements or sf,'

___.'.i_______

S,-S/Se osfIl~ Wit. use; I-el6r,t,ailyvolunt-r X,=

-t

.x -

g189010s3 10/25/1990 Consideration of the Results of NRC-Sponsored Tests of Motor-Operated Valves g189023

1023/1989 i NRC Staff Responses' To Questlns Pertaining To Implemehtion Of 10 CFR% The attached NUREGdoes not constituteanyne requirehents beyond 10 I~~~~~~

7 C~~~~~~~~~FRPairt2FU,.norririta Nfh NIREG doe o~~

-~~~~~~~~~~

'2-i-ti-

-i 1

ne~~~~~~~~~~~`8, aorY r~e ns q-g189022

' 10/19/1989t Potental F~ircea'd§d Roof Lds.D.eTo Recent Charge'ln Probable T"

This infofion ispr ded foryour,r fei*

nd determinoion of apropriate-i-

M t;'i-r,dt t'or

,Crlter

. <.-$i *.-r i-h,if anyMNp' a ohm'Cr eroaquIry-.-o 9

BROWNS FERRY UNIT 1 RESPONSE TO GENERIC COMMUNICATIONS ISSUED SINCE 1985 File Name Date Description

Response

g189021 10/1911989 Request For Information Conceming Status Of Implementabon of Unresolved TVA provided the requested status informaton by leter dated November 15, Safety Issue (USI) Requirements 1989. There were no commitments made in the letter.

gl89020 Tj9I8 1989.^ Prot ed Area LoLg-Tem HousekF ing 7-

.'Th T AL E UEL CYCLE FACILITY LICENSEES WHO POSSESSi USE, OR

~~

PROOE~~~~~S FORMuLA~~~~ QATITIES OF.STRATEGtCSPECIALN UCLEA

% I-r~~~~~~~~~~~~

g189019 09/2011989 Request For Actions Related To Resolution Of Unresolved Safety Issue A-47, TVA responded by letter dated August 29, 1994. Closure documented by

" Pursuant To 10 CFR 50.54(f)

NRC letter dated September 21, 1994.

gl907h,.09106/1989.; Planned Adr iisieChahgesTToT T

NRCO eratorLicensing Wrteh-2 No sG e

i gl89018.

%09119891 ReSollbhOfUn oSf6ty lssies-A-17iSy e 1htcti6inNcler N sicad oW ttente ns Isqur b thisleer g189016 09101/1989 Installation of a Hardened Wetwell Vent Wi914->

i

/unetem:trnprve2me1tn11r9cniai Specrl1caioiinRevl OlVOf 3.25 fJmitOn L s es'a e

edT g 189015-,t'l,-D3, 08/21/1989; EeUeicy Rip5ohse Data $St fi

.D

-e, Tli-s ofiileneb th e te'r sb-plabo ho g18900 i9198ftW~h~o SWf~T Co 1tf~, PAnnifhig 1o1-. sulfift Vebd'~r*5r N ti U

r it i gl?db gi89010s2 08/03/1990 Availability of Program Descriptions 0189013 07/18/1989 Service Water System Problems Affecting Safety-Related Equipment

_r

__b g18901 0s5 08/28/1993 Inaccuracy of Motor-Operated Valve Diagnostic Equipment_______________________________

p89010 06/28/1989 Safety-Related Motor-Operated Valve Testing And Surveillance g18901 0s1 06/13/1990 Results of the Public Workshops gI89009:-~;s-0/8/199.

ASME Secton IIICooent ReplacementsA.-\\.No.ritten.reponse to tis Generi uette.

wNorequired g189008 05/02/1989 Erosion/Corrosion-Induced Pipe Wall Thinning g189007 04/28/1989 Powner Reactor Safeguards Contingency Planning For Surface Vehicle Bombs Response was security related. Compliance documented in Inspection Report

_______n_s__n_

_ _96-11.

gi89006 0412/V1989 Task Action Item l.D.2 - Safety Paramete2r Display System - 10 CFR 50.54 (f) g189013s1. -, 8N5;te 04/04/990; Service Water,System Problems Afeng Safety-Related Equipment,; ag r

This supplement contains the questions-and answr edit h rncit A

U'r ~~~~~~~~Cnidshteestdniatc§ti~nth~oia r t~t5td bmt g189005s g

-t 4/04 UT98 PilotTe,stind Of The Fuhdar n Its ExintionS.W-*;,,.

tis,<-,

' ;-,' *, Cah eansclo tereste t Zt ei

  • n'

'in W

' pt r 'U.i2bKW M 'a-1 Ue d'

m g18904s1g

..-;,04041995 Guidanbe on Developing Acceptabl nservce Testng Prorani s-j,*;

r - Thiso geH'&

letter' nly' teUsts 'pplicbte1 Iforatounethprvsnsf in V g18 34

' 04/111989' Gidhic n DDe ingAcceptabfecnsei Tety-Prrm s Nortten" so'se ntt ene eteta lred g18901 035 03/24/1989 Opeator Ucensi g Examiation Schedule No Wsittqn rment to ts Gnr Lt w

requira 10

BROWNS FERRY UNIT 1 RESPONSE TO GENERIC COMMUNICATIONS ISSUED SINCE 1985 File Name Date Description

Response

gl8

' 0311989' AcionsTo Improv' he Detection Of Counterit Aid Frdulentiy,Markete No responseo t thi.leter Is-re ired g18901 0s6 03S0811994 nformation on Schedule And Grouping, And Staff Responses to Additional Public Questons g18901 0s4 0211211992 Considerabon of Valve Mispositioning in Boiling Water Reactors

~~~-folw/1989,t oh Of PrbgmmConfaoIsfo a

Rd Iologicaln ar6h d 4 nourag-ed t gi89001-..>i<

011/1989 mplentatoh OPrrammio And Proeduai.

r' Licensees'ateehrfr o propse:changestoTS thata consistent' it'

~

the

~

propere a

snto, Isr~j#ve,Ws requireid g189010s7 01t24/1996 Consideration of Valve Mispositioning In Pressurized-water Reactors g188020 11t2311988 Individual Plant Examinabon For Severe Accident Vulnerabilities On September 1, 1992, TVA responded to Generic Letter 88-20 for all three units. TVA completed and submitted the single unit BFN PRA.

gl88019 102811988 Us Of Deadly Fo1c By Licensee Guar To Prent Te f S i Nuclear Noas5iflc actio s or Wtten respnscs reued byh n

Iter.t I

m~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

1l80801--;1<

jW 1012011988 Put Rb6o 'dW StoI~~tflpitiDs i'

nadheurN ftis gCeio leter jsbtl Infrniedesse ht >the^5. staff gi 8 8 0 1

-i

~

~

1 ftb&keerneIap Roettj6iait r W X

t g18O

~ ~~i/

?198~ ~fP~1 eTAMA<

TQf iL HLDERS,OF,OPER UN LCNSES OR,C'=

U~O 9188011 012/11988 NR oiip nRdito mbilicaO ectrVselMtral n

t XX t<A, ttitred.f.e~~~"

(6~

gl88020s4 0910811995 IdMdual Plant

_aiation External Its PEEE) foSevere# Accdet t"-

riq ofthdate bfthi e

t l addressees Who voltarly iIWo'+d re qUtd Ut tP I

d de~cFlbed ea Ulejouriies6~et~

raFr 5Q54 xarril-afidK Fof)btrde scodpettofns1`

N6L' ofGeb-88 bitt Vulnerabilities

~

~

~

~

~ ~ ~ ~ ~~bl n ddi d ca716th,bcp g188014 0810811988 Instrument A1ir Supply System Problems Affecting Safety-Related Equipment q188013 h

~~~181§jOeao iesi~E~litos 2NWttnr sne as rrd,for, this GenricLotter

.';,~~

g188012

~

08102/1988 Rehi6yaI o Fire Protectioni RbureneteFrm'Techiia 1ISpeci icai

'lmpiemenrtationbftho h6comhMd6d Fire ProtcinehIa ecfain g18801 1 07112/1988 NRC Positon on Radiation Embrittlment Of Reactor Vessel Matenials And Its Impat O Plnt Operatons__

g180203 0/06199~'Comleton0f8Cntanmnt,erfrmaceomprvpentProratandFowaringThi geeri ltte psvidstiforaton hatmayassst icnsesfIormfo nin g188010A 07I01/1988~~~~~~~"

Pi[rchtihse'fbfGSA:Approved Sectirty CotaIe§' -

2y"h-i2i This letter. As for Ilffoniionh adde o euiearsoe;--.-

I gI88020s4 06128/1991 Indivdual Plant Examination of Extemnal Events (IPEEE) for Severe Accident Vulnerabilities

BROWNS FERRY UNIT 1 RESPONSE TO GENERIC COMMUNICATIONS ISSUED SINCE 1985 File Name Date Description

Response

gi88009 05/17/1985 Pilot Testing of Fundamentals Examination No.written response war requir,ed. However, Licensees interested in

:- iparticipatinginthisprogramarerequestedtosubmittheenclosedapplicatior g9'soos 05/0311988 Mail Sent or Delivered To The Offce Of Nuclear Reactor Reguiation.

This generic letter provides guidance on how mail Is to be sent or delivered tc te Ofice of Nucl earRecoRgutin

-.d C-

!:: L/071988,'-' --- :-:1- ;-5--:

-Ef; - i

, CF^ :,;-.

r- :-6na Qu -fi gl88007 0

10711 98 Modified Enfrcemernt PolCY.. 10 CFR 5A9, "Environmen ta Qualificion Of This letter does rot require anyresponse d therefore does not need Elctrical -

Equipment Irmpr n To: 8 St

'p a

pr o

fficeo ana'ement nd Budet gi86020s2

-40411590 Accident M emt Sttaies for Consideration in the Individual Plant This genaric letter supplement does not retblish any requirements for 0~ ~ ~ ~~Exmntd Prce liesa to tak 11, spoii acidn maaemn staege int acon a1-f r

PtN

° 0t E

S I G

supplement is volunta.

o 9o88001 0312211988 Removal Of Ornn ChaC r From A nical Sp ation Adinistrativ/

Ucleses and Applcants ir TS tha gl8716

.i: 111219Q, Constrol Reureet NUE-22-Ases oQetrsO mleetto 0Te ooiesexesten wit theidnepovdre inencl suret and Howee ntt X.

~~~Cot 9 i=oiciide gl8705';: ; t:.'111Q4M98

' PlicySat'r,n D tPI t0

- e-s.t kcomplita tieluwasr netorreeruireens gIBBOO 031198 oi Ai oro,no Cron SteeliReadtor Ptibiur Bonr1opoet TO ALL 'LI ESES OF OPERATING PWRS AND HOLDERS OF

_________In PR-plants COSRCION'PERMITS FOR, PWRS 18004 02/23/1988 D.Itrito of easi6icat InaRsat ch A t

ors This letter is for InformEit ly a o

g188003 RG fey I I

APPLICANT S FOROPERATING LCENSES Pumps" I HQLDEI~S OF CONSTRUOTION PERMITS FORPRESSURIZED WATER gai8l si 0210411992 RCa Poifon ori:nferan tesCorri SCn BWR No rittenresponse sruir yd tcnta in GL 88-01 g18800l 01/25/1988 NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping gI88002 01 2011 988 Integrated Safety Assessment Program 11 (ISAP ii)

Participation in the Integrated Safety Assessment Program was voluntary.

g18701 6 11298 Trnsmittal of NUR G16,"nwers To Questons, On Implementation Of,10 The views expressed in the repr aeIntended as guidance, and are meant to CFR 55 On '-Ope' i" X. <

,ratorsP Licese re terlandits s m

rations. The views are not intended to Intr r

nor does the document increase or 12ecreaseanyrequiments ofthe rule.

g18701 5 1/4/97 PoiySttmn On ferred Plants Th oiySaeetdoes ntncdeayewregulatory,requirements.

g1871081187 OetoLiesn E~miainsYuscels,ith enclosed sgetdfra,should be returned to.

g187013 0/10/1887 ntegrityof equalfIcatio Exminain ANo-weRacrsTO)ALL~

NON-POWER REACTOR LICENSEE g187012

~07/09/1987_

Loss oReiual Hea Reoa hl h

ector CoolatSytms aily ALIL LIENSeESO PRTN WSADHLESO g18701_________ReFilled COSTLI CTIONNPERMLTERFOOFPWR g18701 i 0619/1987 Relxation in Abitrary ntermediate, Pipe Rupture Requireiments.

No wltte response wasrequired g18010 061/97 Ipeetto fCR73,7,i Reurmnts Fo BICiinaHitr Nbwtenesoews eued gI87009 060/97bcin.

rd40o tnadTch Specsa On LHimtngConditionsa For Licnesedaplcrt reecuae to propose, changes to their TS that Operaioh nd SrveilanceRequremets aecnitn ihthgiec rvddi thela enlsrs owever, these chagsaevlnayfo l iese n urrent OLapicns 12

BROWNS FERRY UNIT 1 RESPONSE TO GENERIC COMMUNICATIONS ISSUED SINCE 1985 File Name Date Description

Response

1I ?m plem er io hof 10 C FR 73. 55 M l oceRI an rheoU sA m nd eW n e a nd Search N

ro nt erb d -.

g7007 No 119

>,e.

tire e

qu'r.

Ig18707-i. D.:,O3e19187i7 Infrm ton Trarsmittal of Final Rulemakn i For REVlons'To Opedritor 2,.

No Wtein tesponse wi rbqule.H

  • -v-->>___,_______

Liileensin1-CFR $And o f min, Ard i&e't i g187006 03/13/1987 Periodic Verification Of Leak Tight Integrity Of Pressure Isolaton Valves TVA responded by letter dated March 13, 1987. NRC closed by letter dated July 6,1988.

g187005 Rqst Add'i Info Assessment... Degradation Of Mark I Drywells TVA responded by letter dated May 29, 1987.

Yj; 03/06/1987, TOmjorary Eemto rhi ProV,1elohiOfThe F8 Onla itoyRl or N

rte r~

,-quithd.

aa 187003;>-' -nt;i>.

of-f 01 7Mechanical and Electrical Equipent l'.ii..^'Ci Theino r,atldeVloSd4n'sIn t

?th IUSlA-isdesrlb6d Ih the' g187002 02119/1987 Verification of Seismic Adequacy of Mechanical and Electrical Equipment In' Operating Reactors (USI A-46) g187002s1 02/1411992 Transmits SSER No. 2 on SQUG Generic Implementation Procedure, Revision 2, as Corrected February 14, 1992 (GIP-2) g18700125,.->c, a081 '1.87., Pubilq'AMilabillt No.,enNRC

.'i

"-.aaN r

rep6nso Wa' quI d gl8601S~-a~ ~,;.10r221989.ja, W(Atn9jItoU*t&EGCS,Evbal tf ModbldI`

yg

~y OAtPeUzdWt~'~cb ~ldns§diese

,18ODI?

,16.>'

-A (3l1 19'

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EAllbIMPS f

dridMltsL'O^-1j Nc460 e

pp g186015 a~-~'-'~*

1Q9/22MWI1988

,'4Mhprt OCFRO9 KEQ bf, Elttfi~

AII ete~i rofgq 5

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mW~~~~~~~~~~~a MU h

,1~~~~~~~~~~F

-n'.-i t1driv.tw g186013E i,

'p72319869 P

IonsIet edyBetween2PInt Safety wAle san Tehnl-T l ;.:.-' ~;"

O: AL. 'OWER REACTOR CEISEE6 AND WPLIANTS.Wi aa I~6011!~~-~4-`

1031 fpvcxors qu a-dia o

on

&188012K>--

97I>03198B.

Crte for Uhiq,ue, Putposep E,r pton Fro, CohVersion Frorr,The Use ofI-IU.-. TO: ALL NON-POWER REACTOR LICENSEES"AUTHORIZED TO USEo-F8601 1

pmud5/198 Dlstrild,PPbUCta.JidedIhReearch RdactoiD -.

TOALL,'NOWPOWERREACTOR;LICENSEE-a i

-a 8

a-~:

a:.

~O/29/i88 Iplebtitlo~ OfTMtAllonIteiI.K3,5 "AMUt6maITrpo Resctoi-Coolant" rALAPIANTS AND LI ESEES,WITH COMBUSTION ~2 gI186005.O 5/2911986.

Ilmem518Uoh Of TMI ActIOn Item llK3 5 'Auema Trp OfReatol' COOtn TO ALL'APPCANTS AND UCENSEES WIT BABCOCK AND WILCOXa-tu m ps$.~<

a ~ aa a a4aa a

a ~ &~ N) £M ES IG b W O S fUP l S yS (tSFS s)t I'P W

§ -

a a

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~~

04/2411~988-

$enlieun6 F.,

tciiiR~Id¶ns aa ~

N frniW1 Wpdnq fthii Genii fe as~um;a g18F:. 9 S - O3"'.._.

Are ch ficatp so1Liti b

ne ro6 H Issu e 8-59 (n I) L o O p r to n in OW R s And :his e i d

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gIB8OlOsl 03/2511994V FIre W~~ra~ -Te tAbbptanc CriofeatbI Fir Bae yt'sUe oaaa'TOe~en cin eUes or..eportin t~u

~ts So Icatd with:,Z,a "a.

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BROWNS FERRY UNIT 1 RESPONSE TO GENERIC COMMUNICATIONS ISSUED SINCE 1985 File Name Date Description

Response

gl86 OOSz lk-

,--325t118,' Availablity of SUpplement 4 to NUREG3, A Prioritzation of Generlo Safety This letter does not nWini.an tnw requireinents or guidance fo licensees of oI~~~~~~~p19is~~~~~~~d~~~uIred

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BROWNS FERRY UNIT 1 RESPONSE TO GENERIC COMMUNICATIONS ISSUED SINCE 1985 File Name Date Descriptlon

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15

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNIT 1 REGULATORY FRAMEWORK

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Meeting Objective To facilitate NRC review and approval of the regulatory framework for the restart of Browns Ferry Unit 1.

Tim Abney 2

Agenda

Background

Proposed Regulatory Framework for Unit 1 Licensing and Project Schedule Summary and Conclusion Tim Abney 3

=

Background===

All three BFN Units are essentially identical GE BWIR4, Mark I Containment reactors Designed and constructed by TVA Units 1, 2, and 3 licensed in 1973, 1974, and 1976 respectively All three BFN units voluntarily shutdown by TVA in March 1985, because of regulatory and management issues NRC issued a "show cause" letter for all TVA nuclear plants in September 1985, under 10 CFR 50.54 (f), and requested TVA to specify corrective actions TVA submitted the Nuclear Performance Plan, Volume 3, in August 1986.

It outlined the steps needed to recover the BFN units and was specifically directed to Unit 2 TVA committed to obtain NRC approval prior to restart of any BFN unit Tim Abney 4

Background (Cont.)

NRC considers BFN management concerns successfilly resolved on July 31, 1990 TVA executed Unit 2 restart plan, obtained NRC approval, and restarted Unit 2 on May 24, 1991 TVA proposed regulatory framework for restart of Units 1 and 3 in July 1991, outlining improvements to the Unit 2 restart plan NRC approved the regulatory framework in April 1992 TVA executed the Unit 3 restart plan, obtained NRC approval, and restartedUnit3 onNovember 19, 1995 TVA requested Unit 1 be removed from the "Watch List" on April 16, 1996 Major management and cultural changes implemented at TVA Tim Abney 5

Background (Cont.)

NRC removed Unit 1 from the "Watch List" on June 21, 1996 based on TVA commitments Implement the same special programs employed for Unit 3 recovery Not to restart Unit 1 without Commission approval TVA Board of Directors decided on May 16, 2002, to restart Unit 1 after detailed study and favorable Supplemental Environmental Impact Statement Unit 1 Restart Principles BFN units will be operationally the same upon completion of Unit 1 restart Unit 1 restart activities will use plant processes and procedures TVA submitted a proposed update to the regulatory framework for Unit 1 on December 13, 2002 Addresses regulatory requirements, special programs, commitments and Technical Specification changes implemented for restart of Units 2 and 3 Tim Abney 6

Proposed Regulatory Framework for Unit 1 TVA needed to update the Unit 1 regulatory framework Reflect the current list of Technical Specifications and generic communications Incorporate lessons-learned from Unit 3 restart Make framework consistent with changes in regulatory requirements and processes since the Unit 1 framework was developed in 1991 Propose methodology for satisfying Unit 1 License Condition Supplement submitted on February 28, 2003 Bulletin 79-12 inadvertently omitted from list of open generic communications NRC's March 11, 2003 letter states that Manual Chapter 0350 applies to plants with performance problems, which is not the case for Browns Ferry Unit 1 Tim Abney 7

Proposed Regulatory Framework for Unit 1 (Cont.)

Review of the proposed Unit 1 regulatory framework

  • Generic Communications
  • Special Programs
  • Commitments
  • Operational Readiness
  • Communications
  • Technical Specifications Tim Abney 8

Proposed Regulatory Framework for Unit 1 (Cont.)

Generic Communication (Three categories)

Commitments defined and tracked.

(See Table 1, Page E1-7*)

Commitment not explicitly defined. Submittal required.

(See Table 1, top half of Page E1-8)

Commitments defined and tracked. Originating generic communication required notification of completion within a specific timeframe.

(See Table 1, bottom half of Page E1-8)

  • - Note that Bulletin 79-12 was inadvertently omitted from the table. Correction was submitted on February 28, 2003.

Tim Abney 9

Proposed Regulatory Framework for Unit 1 (Cont.)

Generic Communication (Completion)

TVA will formally notify NRC when these issues are completed Issues will be completed prior to fuel load unless completion physically tied to work that can only be completed after fuel load TVA will strive to meet notification timeframes requested in the generic communication, but these timeframes are no longer as significant New generic communications will be resolved for Unit 1 in accordance with their schedule requirements Tim Abney 10

Proposed Regulatory Framework for Unit 1 (Cont.)

Special Programs Definition of a "Special Program"

  • A corrective action plan to resolve major issues or address an area of specific concern Eighteen Special Programs (Thirty one subprograms) listed in the framework letter
  • Five closed for all three units
  • Twenty six open for Unit 1 (Listed in Table 3, Page El-10)

For Unit 2 restart, NRC issued Safety Evaluation Reports for both design criteria and program implementation methodology For Unit 3 restart, NRC issued Safety Evaluation Reports for all changes to design criteria and most changes in program implementation Tim Abney 11

Proposed Regulatory Framework for Unit 1 (Cont.)

Special Programs (Cont.)

Lessons learned from Unit 3 Restart

  • TVA intends to implement the programs in accordance with the Unit 3 implementation and criteria precedents e Implementation can be more efficient in certain areas (e.g., drywell steel)
  • Changes to design criteria and program implementation need to be addressed using today's regulatory requirements and processes (i.e., 50.59 and 50.90)

Commitment closure packages for each special program will be prepared by the line organization, reviewed by Licensing, and closure documented in accordance with TVA's commitment management process TVA will formally notify NRC upon completion of each of these special programs Tim Abney 12

Proposed Regulatory Framework for Unit 1 (Cont.)

Commitments TVA's commitment management program is consistent with NEI 99-04, "Guidelines for Managing NRC Commitments", which was endorsed by Regulatory Issue Summary 00-17 TVA does not intend to formally notify NRC of the completion of each commitment TVA's processes ensure that all restart commitments will be completed In the Framework letter, TVA proposes that previous "commitments", that are not commitments under today's regulatory guidance, be dispositioned or implemented using current plant processes.

Tim Abney 13

Proposed Regulatory Framework for Unit 1 (Cont.)

Operational Readiness Self Assessments

  • Implementation of the special programs
  • Additional resources required for three unit operation
  • Completion of restart prerequisites Independent Reviews
  • Nuclear Assurance
  • Nuclear Safety Review Board

Proposed Regulatory Framework for Unit 1 (Cont.)

Communications Periodic project status meetings Issue-specific meetings as needed Tim Abney 15

Proposed Regulatory Framework for Unit 1 (Cont.)

Validation of Current Unit 1 Technical Specifications NRC approved the Unit 1 Improved Technical Specification (ITS) conversion with the following License Condition (2.C.4):

The licensee shall review the Technical Specification (TS) changes made by License Amendment No. 234 and any subsequent TS changes, verify that the required analyses and modifications needed to support the changes are complete, and submit them for NRC review and approval prior to entering the mode for which the TS applies. This amendment is effective immediately and shall be implemented prior to entering the mode for which the TS applies.

TVA proposal to satisfy the License Condition

  • TVA will formally notify NRC that Unit 1 specific analyses have been completed to support Amendment 234 (ITS conversion) and TS 405 (new source term) for which the Unit 1 analyses were not complete
  • If any Technical Specification changes are required as a result of these analyses, TVA will request an amendment Tim Abney 16

Proposed Regulatory Framework for Unit 1 (Cont.)

Validation of Current Unit 1 Technical Specifications (Background)

TVA converted to the ITS format for BFN Units 1-3 while Unit 1 was in its extended outage Required analyses for Unit 1 identified and documented in TVA's application for conversion to the ITS format

  • ITS Table 3.3.1.1 Calibration Frequencies for High Reactor Pressure, High Drywell Pressure, and Reactor Low Water Level
  • ITS Table 3.3.5.1 Calibration Frequencies for Reactor Low Water Level, High Drywell Pressure, Reactor Low Pressure, and Reactor High Water Level
  • ITS Table 3.3.5.2-1, Calibration Frequencies for Reactor Low Water Level and Reactor High Water Level

Tim Abney 17

Proposed Regulatory Framework for Unit 1 (Cont.)

Validation of Current Unit 1 Technical Specifications (Background -

Cont.)

Required analyses for Unit 1 identified and documented in TVA's application for conversion to the Improved Technical Specification format (Cont.)

  • ITS Table 3.3.6.2 Reactor Low Water Level and High Drywell pressure calibration frequencies
  • ITS Table 3.3.7.1 High Drywell pressure calibration frequency Unit 1 analyses completed for all amendments implemented since NRC approved the Unit 1 ITS conversion (TS 234)

Tim Abney 18

Proposed Regulatory Framework for Unit 1 (Cont.)

Validation of Current Unit 1 Technical Specifications (Background -

Cont.)

Proposed use of the alternate source term (TS 405) specifically stated that Unit 1 LOCA, Main Steam Line Break and Control Rod Drop accidents analyses would be completed and submitted to NRC prior to restart in accordance with License Condition 2.C.4

  • Times or setpoints revised in LCQ 3.1.7, SR 3.1.7.3, new Section 3.9.9 and Program/Manuals 5.5.7
  • Other ITS sections affected include Tables 3.3.6.2-1 and 3.3.7.1-1, LCOs 3.6.4.1, 3.6.4.2, 3.6.4.3, and 3.7.3 TVA will formally notify NRC that Unit 1 specific analyses have been completed to support Amendment 234 and TS 405 for which the Unit 1 analyses were not complete If any Technical Specification changes are required as a result of these analyses, TVA will request an amendment Tim Abney 19

Proposed Regulatory Framework for Unit 1 (Cont.)

Technical Specifications needed for Unit 1 restart All but three ofthe Technical Specifications listed in Table 2 (Page E1-9) were previously approved for Units 2 and 3

  • Reduction in the number of ECCS systems needed to respond to a LOCA (applies to all three units)
  • Miscellaneous I&C changes Tim Abney 20

Unit 1 Project Overview and Schedule Licensing Schedule Forecast submittal dates routinely communicated by use of the Unit 1 Licensing Project Plan

  • Regulatory Framework submitted on December 13, 2002
  • Majority of Technical Specifications to be submitted in 2004
  • Extended Power Uprate to be submitted in June 2005 Unit 1 restart currently scheduled for May 2007 Tim Abney 21
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Summary and Conclusion Tim Abney TVA PROPOSAL lJULSTIFICATIONl Generic Communications List of open generic communications is as shown in Extensive reviews performed.

Table 1.

Compliance with timeframe for completion Timeframes are no longer as significant.

notification contained in the original generic communication is no longer considered a requirement.

Special Programs TVA may modify implementation precedent for No current requirement or need for regulatory Special Programs at its discretion.

review of implementation methodology.

Changes in BFN design criteria will be evaluated Need and process for obtaining NRC approval under 10 CFR 50.59. Annual summary of changes determined using current regulatory requirements to be submitted to NRC. Changes requiring NRC (10 CFR 50.59 and 10 CFR 50.90). Notification approval will be submitted as a License amendment.

exceeds regulatory requirements (24 months).

23

Summary and Conclusion (Cont.)

TVA PROPOSAL JUSTIFICATION TVA Commitments Previous "commitments", that are not commitments Consistent with NEI 99-04, "Guidelines for under today's regulatory guidance, will be Managing NRC Commitments, which was endorsed dispositioned or implemented using current plant by Regulatory Issue Summary 00-17.

processes.

TVA will not notify NRC of the completion of each Consistent with NEI 99-04, "Guidelines for commitment. TVA will notify NRC of the Managing NRC Commitments, which was endorsed completion of Special Programs and generic by Regulatory Issue Summary 00-17.

communications as noted in Table 1.

Operational Readiness Review Will focus on changes associated with operating a TVA has demonstrated excellence in operating tlree unit site.

Units 2 and 3.

Will consist of self-assessments and independent Provides sufficient internal oversiglht.

reviews.

Tim Abney 24

Summary and Conclusion (Cont.)

Tim Abney TVA PROPOSAL l

JUSTIFICATION Communications Protocol Periodic project status meetings.

Maximizes TVA / NRC resource utilization.

Issue specific meetings, as requested.

Maximizes TVA / NRC resource utilization.

Technical Specifications TVA will satisfy License Condition 2.C.4 by Maximizes TVA / NRC resource utilization.

submitting a list of Unit 1 TS changes that were Satisfies License Condition wording and intent.

made without the supporting analyses and verifying that the required analyses have been completed.

25

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