ML031420357

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)

Text

BROWNS FERRY UNIT 1 RESPONSE TO GENERIC COMMUNICATIONS ISSUED SINCE 1985 File Name Date Description Response Bulletins BL-02-02' '. 08109/2002^^ ReactotrPrsure,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 00X31i" Clrcumfereliail Cmcldng of Reactor. Prstire Vessel Head Penetration Nozzles To holders of 'beirating licenses for, pressunzed 'ater. nuclear owr react rs

>_t_

1tF X

.2 t . t . rv4v , .! 7.

i, i * '-v- -t- - . S --

fin,_#'Shlor~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ IIP 4 BL-97-02: 0 /2311997. PUnctU .Te ftn bf'Shi n Pcaegbsdhd& 10 CFR Part 71 '- -^ For.Actloh-AAl 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

>~ ~~ ~~________

!: ot-;>1g A:esurem sr iicoree ModeB 53 nd; 3Oi cgmeiter6e- Elec miiet r 4.a ~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 wh6selicnsees iMth

~~~~~-7~~~'i:6n TratispiSrt~~~~~~t1onCtisks 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 inthe Reactor Core, or IVA letter dated May 13,1996 - No commitments made.

over Safet-Related Equipment SU 6-C01 3-8/

~ ~ Problems

~ dlnrttlori

~~~~~~~~~~~~ ~ ~  ;;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

.o Aphy licensees- 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,

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ with~pehfiie Ipt)(ec p&nia~ehiy~hUtd&v~ -

Inihe spent fuel pool (exb~~~~~~~~~~ <K>

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 dnhg' 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 .

i< V'~te tt-?Li <.,< ni-;,-,.t.

I Attachment 2

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

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

--t- ra

'

BL-90-01sl 12/22t1992 Loss of Fill-Oil inTransmitters 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

- + -g-g fz;; */Steam tGenehator-Tube f*;si Mechanical Plugs N* '!-' +5;.,<B. ,+. Addressees Al hiders of bperating Q.i 'r'sS rt'4-' fteea"a loenses n^4sbriss, brbns t'Uiction permits b0- m' fori'.7";

SJl,sr-M ds r ~ ~~~~~~~~~.6e ed riI 1 Addre s A holders ofoie,rattg lirises-or'66nstr on rmitsfor.i.<

BL-89-Qlsi ~ 'Il/14/1 As'>;: .. Falturo 6f!Wdtlnghou's Steam Generatr TubeMechana IPlugs -:

Bt03>""f> tn1,f tfffffff'SiPotfl Loii6f~[U'f --. <K~~~.~~77~~P fhf fnaD 7i-~~~::~~

'ff'Rei90pera -2>7~~~7~~-W pressUrl&

fdffses' lti a w"trr f' PW--S> Rsf'-^.',

- '-~~~ -j

.~~~~~~~~~~~~~~ibUi ,,_Sh- s<<s 6.iireaA§rutio tii lricen"'r,. < ,p-;.'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 -t

,*t:t:ti'

.'-<,l,~,., $ --,<@.~ i,,:,- ~-',$ < 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 constuctio ermitsfor

• ~~~~~~~~~~:"  !< -",;-,<  !, s;,,,,

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

- ~~~ I>,::

ntA-I`Wsbnh6ighR6so *~~~~~~.T W& (W '-.dgl6dL clear.06er reaMtis -theUtz bI'tto n Ms me on ._

4~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~m 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 rr - Device v ', ' 'i;6'. d ia' heate sUe i ebur c

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 in Steam Fatigue,Cracks Generator bf pert trcti BLB8-02 WO2KI5/1988 0 RaPId1ybs JngAFaigueCrcksrinStAdeoGenefTubesaIng ,Pr licenses or const on permit or

>:~~.::~

W~sdh~h6~'(X d nser. 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 Addresses :-AI NRC licenses authorized to use cobaft-60teletherapy'units.

Aose 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 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 PWRlci seesndPR Pholder aretistedto take further Certin

-  : tictioh to s,i~ ~iTI~I~OV~ntS ~rdiii ti~i~UTflui~ ~tth~iiitcioioles anbg

_____________ ___________ d~~~~~~~~~~~~~~oe hO os e ns en&orpInnied29 is.

4

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 'i, ,

,Y,*,,*gt-,,i, i 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 -, Thisgeneri' letter,re4Uir n' pec1fic acton or Written response-8WRViP-0 5rtt6"RR 'cfieRe,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 Letter98-3 NMS censees' dnd Certicate Holder'-Year.- ,J. ForAciot¶ Altlicens or certii cate holdefsfor eianium heafluoi

+> tlt2^fe- ,.s.,i 2 2bd'ea iiess Progr Rdddlh-'s6 P B -r S producton ln iinkr nh ieniplnts fidr niui' fte fabniaton 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 d ,excepttho hnve nenty ceased operatio'h an8 haui for Emergency and Containmentd Phu certifieling tha feo banen reov r gi97005,i". .t 'i; Wf-711 1 1997s'f? ANR l Ftnaffcle t 7-o5 Stem-Re GeeratTu nspein Techner e AddresseesAll holdera f opernLicen esadrse§ for, pressunzeddWate -reat

')) exett"osewh iVe~penmanenty cease operations-andav 5,<4,,S,<,-ArS4 certdA, i e -rtha't{'

fue has' be pera Y rioed rearrVe l TheeV'om 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 / -"; 04/01/1997' Dei'dation of.ControliRod Dnve Mechanisi Nozzle'and Other Vessel ClosUre' Addressees Al 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 SteapG 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) n 21 3/1 S;>,< Reconsideration eribf Nuesar.Poe Plah of Nuclid 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 9196<iaig-t;W^W55.<..X= eroWlge R -- -:

q196001 01/10/1996' Testng of Safety-Relabd Circuits g19501&- n ns +r ;+12t511995 Rel6Oatiotl of SboadTechnicatlo '

u SR Tee Reqteufrtte i1> Llcohs that do notwi shto amend tecKnical speifictionsiae notexpce glS -4i1I03/199i. Monitrmiing o alf,Shrinigofrs an a dCrlsofRadioactivte Maials'-. Nope8bll on h wrte r ohse'is rqUred -' >.~si$. H-.-r- >.;

I95 .p  ;-v - n.na tinn aneneCFR....... fr,0.. es .t..4..

flL....

C ~

ang'e§ ..4& f'Sc P taD*ftt Pro NRC^< No LI. ec n. .fl....t 'ofl riten'espns b i 9195007 08117/1995 Pressure Locking and Thermal Binding of Safety- Related Pover-Operated Gate Stm _

0811511995 9

Valves

< tt Changes inth'e Oeror Ucensin Program:'9--'.'-'- -

r 9 ' ' -_

ffi  :' 6*tt -S~~~~~~~_qrem i ,' , `lresn sasPh- dc This gceneric ietTer.aLI m

siic

':N _ _ _

2 actr-Writerlp 4re exob edS gl95005 -;.-':Y.r/9 ' j1995 : Vo eBase ,,Reair Criteria fr.WestinghoUse'Steam'Gnertoru bes' Addessees:.'A ilholdesofoperain i ens s or, onstrton perm forn

____________-,.giE6j :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, g19504 3190 '1+ t t19

.;-Ys,6,,. 0s.,';'

428/199 .. Vountr Mof- o .eFR50 -Theming "yfAoSfhwmiedeksu aro Radio ur

_ Da e ame Iss e, N

'"'ttd speCiC NOtinalO5e6abria- tIoaN o olywrwn' wunirysb

'6 r -rorEleor5o',is require i,d '

gl9402 ____________

04117/1995

__________ Thermal-Hyri LongTrm aouting Intaiite and inCBrsio of Carrad aferiePofRdo erOperat edates foi ________________________________

g1950021 04t25t1994 Usterofanlarcpr S reportio racking ofdj C on Lhrcudsihg oigital NoWeaicatotrewrtnepneIsrqie ReactorstoDgia ~ §9<: ~,

7lterranlar SrstCorrosinCR

.195000g R andCUpa of Itim Operating Recommendations fo 6

BROWNS FERRY UNIT 1 RESPONSE TO GENERIC COMMUNICATIONS ISSUED SINCE 1985 File Nane Date Description Response g194001

!O5/3I 994, I. Removal of Accelerated Testin and Special Reorting Re'urehient fort. Licenseieaction topopses changes or'relie fomdcketed commitment' n en r

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

'ofthis gnrien i /29(1199 ReoWon of Technical Specfica'ton Tb Of IstrUtentResporise Tim. oTSdancold thar,es iidrth --

~~~ Limits&~~~~~~~~~~~~~ KR fl~mbt Ulee is Voutry. e-TSch4h gi93007rh9nT-<;w st12

'C 1993 ' Modification of the TfnIc!i Speqicatbo-Administ ConlReciemen Ucensee aoOil ' 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

he'aof Hehl ' Inth gened letter eth NRC is onlyxmmunaing Informat6o resul oU 9, , 1/219 Research Resultn GenerccSafetyl'sUe10, -iping'a' eU

. _o5uhbbiea _ Ao 4 " er u s tC.n-o i ' 's'- .,

and ieno

'an6 o,. h 92008 12/17/1992Thermo-Lag330-1FireBarriersTVA's April 9ett conmmit co' rkalb thnRCon gi 2t0/2011095~\er0flfIdfof6f PlantRodbrd& ~ ~ .~ ~ Th1.Aoetin letter umite d tober 2ct .t nechle S Iicetlons 'anei'1to.hdoU.e sUr'ld  : icisai6 il r' is'ie ORoro m ocfd th g g1920 7-;V*->2; ?it'092711993' l4 O 99001 rs.html 0/1/1995 NRSCO Ghtrot i eReTING t s LICENSER-1:eo f~~~~~~~~~~~~~~~~~~~, ail.,

NUS~~~~~~~~~~~~~~cl 4.4reUatr 4

.. 4> ..,,

• 4.~~~ . N,*P. I'Wdi-~'. m6td5l Gtitl1ydee',trM  : eltypdihPe II 1a.

g93005- -- 09MX66hLjri- .- NRWroo'^ytmt'sesotfiesee e . - .-- ~~~~~~~~~~~~~~r~,

.74i rmac?+t- ThstnC rop ,, insr ib aginu 1 19200408/19/992 Rsolutin of te Isses Reltedof orRec VesselWter Cevlstrueto in~ll~DA gl92008 12/17/1992 Thermo-Lag 33G-1 FireStructural~ ~ ~~

Barriers ~ ~ ~ ~ ~ ~~~~~S IntecrityT TVANs April 14,1993 letter commits to complete N4OV removal of thermo-lag.

gl92001rs ~~~031211993 NRCPbl GeeicLter20.Rvsb,'uplmnt1-RatrVse Completion lefter submitted October 29, 1996.

g192007. .4 -.<~:1O0/192 j.>01i9'e 'X of NUclear'Reacto sR'eulation'Redrgehizatori ss'-" . Tisuineric i lte, ct nformatorl collectir'on requlremet dr, t .5^ W

';. f a rtconhl Examination Sche oshbUld b6 sbnt to -'

91920064>.>, >- " .-.09 Ussiin g192004 09/0411992 RCorkhop on the sstemeatict Rectrn ofslae Lcensel erformnion i eei,~rcnan oIfriOinclabnr~leet.

BWRs Pursuant to 10CFR 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 03/19/1992CComaton'of th Urh icnigBssqRqetfr outr ariiai 4' Inlgiig-this letter,~the-NRC IsImposing no-neW requiremients orta

~K'2~"n Pitotl4 i4aT~ih~ '-4,r-.'...

. foA>tr q4Ws'>t.. P.a'ticgpdt:or: 4, ruientsrstaff-gI92002, -,4~ 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 Dbte Description Response File Nanie g192001 ri Reactor Vessel Structural Integrity gl92001 0212811992 - Reactor Vessel Structural Integrity ten onse Irequired gl91 019 21i9/119 1;t:i.g. Infomiatlon to Addrsse Regarding NewTelehone Numbers for NRC Offices No secif actionr

.,-, ,  ;-<Z. .,:-Wh.z9,¢L i Nor t ';

2f r '

a lns are red e,->,;-i:,,b,.;

n a 90 I-'jPs On Resltionof D) ded' a 'No-see

g11018 i 711 1 Ifo

'ReingTw'NRC Generic Safety lsslJd. :'BlTI6ng De dadon ordFailure in NUclear_er . i-lowever the suggstonsdnt iie inti g191017 410171991  ; r o Wn= d on n ngon a, >>

hisgeerc lWhspciicactonorr dtt hotie

1. . ~~~~~~~~~~P g191~~~~~~~

16

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

RC`erbf6 Gdheo6 66 Lttr9-l8R

.ib.

0191 018/197, .

Ni Dsgtutoh ofF~eaild&

Inort9tiO tiLcesethRgadlni rtI ii' Nohcon one <pon, RC t- Ooid> c~ ed9p~rtttr Ndcea' fIi r iss,VFRobly Fb uy',z~,T s li eid itVgener1i e -

Metoro t ees r o* s o'n 6 g191016? -?'¢s

- (1 110311991..

9 g bs7 g i +2 _____._,____________ ___________________

6 , § nd N U 610;-r-17 0't/X;f>-Si'bir.dS clt' C b N h tnbOor~euW&~

s-VW<'tX'dt,~~~u

-thieance Ardd q,, s En jvier?e S ~ un 5iI ~~~~~~~~~~~SnC ett<tie 6, i tn iatitt tibif ardr 09123I109t-,-<

g191014 -l BI9Oprakers," Pursuant i~ 50t Oterated Valve ProbleR evaluation actions oncrluted thatthe adiisthtigels i let "j--i- -E R8,04.

-1 le fil~ ~ ~~ ~~~~~~~~hercmndtosofteG X. oieittItieS.eeE

',L~W l,.'

>=--*:-

gi9iOo8'- 5 1 gj;, 1ii.1R' o atflo > '

Xt-a,j1fP-IAN hi Satn .;-;m i wMLh-ENSE8N

'p' PjRlac 4.-,@i',t-;ji,<

'XzcLi'v-;t joDi, tif,w,$os;'^ ,S'<r,;s~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~b i"it ~~

SWi-i Gl2Rat0~ln 99 Pump I dn d Are en vaIrts~ar its t'0il fetTi ttonnhiir*i eei lt& ossso frei o ol o Icuiestoil bg91007- , V!219-a 7 92dcmne TV eopeto commitesS WHO alneenis g19100 Resolution7 ofGnrcIseA3,rdqyo aeyRltdD oe

~

Supplies ~ to, ~

10CR054f " Pusun biTebnical SecificatoSeillanc ItrastAcoodta24nyrsoIe ehandueietoP S-.. .+. :-.Nrsos'hsetelr o hedlb NRtuoeto for' SUIchalftgesjUd ie.'-'>*j.<-S:.t isblttre o-g!9I10 ..- :i 04/02/991 g191004 071181991> "~ Changes cneCm'raaer r .-

thedNRs?lugq enfrSeturned t olha ?

tMa ur updated scheules to be oluntari Ay ruThth 9i91,<X~~~~Oerto NaionWx hagmienaiiSiot S 00 v ... htE Via lnt an4~51-9."Itlcks Tie 1As Arin ue, ad4,"nerok . i Thes Api-019 opee foralre In,t9Is completed hreuis BF aopeet o lvounits a opee t gl91 gl9Ol-:- 3 i-o19 0731061992 Res,outn Resolution oiSf ofe GIs48,LCs 48,aILCs .n..2Val Ins. Buses" evso n has ornded thf the obainstrieporoefs nd dlaevaiony g191002 ~~~~~~reers," Pursantllovii tor ~5Diposa PreprCdFR L 919108ti-< .>

0518199

____________________ Remoa oin omisp loriLtsFo ItNa-Tehnca Moifcaibi~'fsirellnc WWtiSpecflcatiosprl> 'ssinletir PW,P .- . Tisjttl.

thnecomdabon ofitheR tic en GLureret.110 F

a rep0netoatbfl1ence oided dotto pp n Isegeercltr ad-ias' I~

<X__ _ __ _ 7.S, ~- / 1 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> 1 11h1/199 gm O ebtor iceiilnt Nattal E5camin"ionSche ulen - Yor d..a dules, tob#:Vbltntlyi biii fnlokd h0-'d gl9000t6>fY $ 08 9 o esoon of G ic sues 70; "PORV. ,P0R and lokValve Reriab0ite 4,- TO:eiALLbPRESSUJIZED WATERREACTOR T LICENSEES AND'ATE-RE

. P, ,, , '-;tV+ AaaffinSioP LIOIfyIot~CDOf i P iR*!' d <- ;E C1NkWVC N ti1CENEEE g190005r <.tJn, q z 08110/19902 Gtidane fi~OrformlhgTempory Nbr1Cod'Rjalr of ASME.Cod6'CIaks51L e t d ta wib Idrdby the NRC,staff Si 01d6flif SM" hdittief Is~~iritd "

~ M`~~~~~~~~~~~~h lJh fo ay o-cd 1900082" N.'p713111i92, FaiiyEOepliAi ' hsGiio W en1slb tGr ib i~ddr66s ott6e heed to-~

I ~~~~~~~~~~~ra.-N

-- *1~ ~ ~ ~ ~ ~~~~~~~tis ft)6H dh,6I i

-, Ai~~ ~~4~'~,-

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.

g190003s106(1 511 99Q Re1ixt1off t Star P6§jtJ1oh l 6Motbtwte83-2~hl hdh:Qdfi cto

_______n e Qr1 MW~n in itp onyad ri1

-,At"Atte furdhi1bbts fOlShUbbbi~ eiat1he6i on nt ra1 irewthh jili - tho nmtlTeqreme C cteCog!ss~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~Cffw,s

' " - . 7 wrfial Inspeto nevl

- I -~~~ Actio~h~ ';--- . -- P -- Ilun~

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. . gmzS.,6 , ) t ° (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 acopy f thebje NURE6rePor This

-` ~- t,b. , rcEt, u,n,, n eURtEt 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 NIREG doe Nfh o~~

_____________ '2-i-

-~~~~~~~~~~ ti- -i 1 ne~~~~~~~~~~~`8, aorY r~e q- ns g189022  ! ' 10/19/1989t Potental F~ircea'd§d Roof Lds .D.eTo Recent Charge'ln Probable This infofion T" ispr ded foryour,r fei* nd determinoion of apropriate-i- M t;'i- r,dt at'or ohm'Cr eroaquIry-.-o

,Crlter ' . <.-$i *.-r i-h,if anyMNp' 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 HousekF ing 7- LoLg-Tem

• ' - .'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.; PlannedAdr iisieChahgesTToTT 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 -- ________________________________________,-______________

i /unetem:trnprve2me1tn11r9cniai Specrl1caioiinRevl OlVOf 3.25 fJmitOn L s es'a e edT Wi914->

g189015- ,t'l,-D3, 08/21/1989; EeUeicy Rip5ohse fi Data $St -e,  ;,.- , .D  ;, . Tli- s ofiileneb e te'r sb- thho plabo g18900 i9198ftW~h~o SWf~T Co 1tf~, PAnnifhig 1o1-.sulfift Vebd'~r*5r N ti U rit 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 .-A \.No.ritten.reponse uette. to tis Generi U'r~~~~~~~~Cnidshteestdniatc§ti~nth~oia wNorequiredr t~t5td bmt 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 g189005s g -t 4/04 UT98 PilotTe,stind Of The Fuhdar n Its ExintionS .W-*;,, . - ' ;-,'* , Cah eansclo tis,<-, teresteW t Zt ei 'in*n' ' pt Mr 'U.i2bKW

'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 Gidhic n DDe ingAcceptabfecnsei Tety-Prrm s ntt ' Nortten" so'se ene eteta lred g18 34 ' 04/111989' 03/24/1989 Opeator Ucensi g Examiation Schedule No Wsittqn rment to ts Gnr Lt w requira g18901035 10

BROWNS FERRY UNIT 1 RESPONSE TO GENERIC COMMUNICATIONS ISSUED SINCE 1985 File Name Date Description Response gl8 ' 0311989' AcionsTo Improv' heDetection 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 ._.

gi89001-..>i< ;011/1989 ~~~-folw/1989,t mplentatoh oh Of PrbgmmConfaoIsfo OPrrammio And Proeduai. r' Rd a Iologicaln d4ar6hnourag-edot propse:changestoTS thata consistent' it' Licensees'ateehrfr

~ the ~ propere a Isr~j#ve,Ws snto, 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 fS i Nuclear Noas5iflc actio s or Wtten reued byh respnscs n Iter.t I gi-i8801

-* ~ ~ 1 ftb&keerneIap Roettj6iait

~

g18O 1l80801--;1< m~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

~~i/

jW 1012011988

?198~ ~fP~1 eTAMA<

Put Rb6o

'dW ...

StoI~~tflpitiDs i' TQf nadheurN HLDERS,OF,OPER iL UN LCNSES OR,C'=

ftis gCeio leter jsbtl Infrniedesse ht >the^5.staff U~O r W X t ,

gl88020s4 0910811995 IdMdual Plant External _aiation 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 9188011 012/11988 NR oiip nRdito mbilicaO ectrVselMtral n t

____________ 5Q54 xarril-afidK Fof)btrde ofGeb- N6L' scodpettofns1` bitt 88 XX t<A,  ; ttitred.f.e~~~" (6~

g188014 0810811988 Instrument A1ir Supply System Problems Affecting Safety-Related Equipment q188013 ~~~181§jOeao iesi~E~litos 2NWttnr sne h 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 Impat ~ ~ ~ ~ ~ ~ ~ ~ ~~blAnd Its NRC Positon on Radiation Embrittlment Of Reactor Vessel Matenials Vulnerabilities O Plnt Operatons__ _ _ _

n ddi d ca716th,bcp g180203 0/06199~'Comleton0f8Cntanmnt,erfrmaceomprvpentProratandFowaringThi geeri ltte psvidstiforaton hatmayassst icnsesfIormfo nin g188010A07I01/1988~~~~~~~" Pi[rchtihse'fbfGSA:Approved Sectirty CotaIe§' - 2y"h-i2i This letter. Asfor 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 Isto be sent or delivered tc

,CF^:,;-. r- :-6na Qu -fi te Ofice of NuclearRecoRgutin

!:: L/071988,'-'

- .d C- -Ef;- i

--- :-:1- ;-5--: -,

gl88007 ' 0 10711 98 Modified Enfrcemernt PolCY .. 10 CFR 5A9, "Environmen ta Qualificion Of This letter does rot require anyresponsend Budetd therefore does not need Equipment Elctrical Irmpr n To: St 8 . 'p pr o fficeo ana'ement a

gi86020s2 -40411590 Accident M emt Sttaies for Consideration in the Individual Plant This genaric letter supplement does not retblish any requirements for supplement isvolunta. S acidnI G maaemn staege int acon oa1-f 0~~ ~ ~~Exmntd Prce r PtN ° 0t liesa to tak E spoii 11, ir TS tha 9o88001 0312211988 Removal Of Ornn ChaCr FromA nical Sp ation Adinistrativ/ Ucleses and Applcants 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 InaRsatch A t ors This letter is for InformEit ly a o g188003 RG fey I I APPLICANT S FOROPERATING LCENSES I HQLDEI~S OF CONSTRUOTION PERMITS FORPRESSURIZED WATER X.

Pumps" 0Te ooiesexesten wit theidnepovdre inencl suret Howee and ntt NUE-22-Ases oQetrsO mleetto gai8l si gl8716 .i: 111219Q, ConstrolReureet 0210411992 ~~~Cot RCaPoifonori:nferan tesCorri

,n

t

.'111Q4M98

' PlicySat'r gl8705';: D tPI t0 - e- . , . :.

SCn BWR No rittenresponse sruir 9 s .t kcomplita netorreeruireens i=oiciideyd tcnta in GL 88-01 tieluwasr 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 inthe 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

,ratorsP55 On '-Ope' i"Licese CFR X. < 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.

g1870130/10/1887 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 i0619/1987 Relxation inAbitrary 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 nd SrveilanceRequremets Operaioh aecnitn ihthgiec rvddi thelaenlsrs 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 CFR 73. 55M l oceRI an rheoU sA m nd eWa nd Search N nterb n e ro d -.

g7007 119 >,e. No 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>. 01 7Mechanical of-f and Electrical Equipent l'.ii..^'Ci Theino r,atldeVloSd4n'sInt ?thIUSlA-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 gl8601S~-a~ ~,;.10r221989.ja, W(Atn9jItoU*t&EGCS,Evbal tf ModbldI`

.'i r No.,enNRC rep6nso Wa'

"-.aaN quI d

~y OAtPeUzdWt~'~cb ~ldns§diese yg

,18ODI?

,16.>' -A (3l1 19' ,; 'h 6f EAllbIMPS dridMltsL'O^-1j Nc460 e pp '

g186015 mW~~~~~~~~~~~a 1Q9/22MWI1988 a~-~'-'~* ,'4Mhprt MU OCFRO9 h KEQ bf, Elttfi~ ete~i AII rofgq 5 -a;dh<

,1~~~~~~~~~~F -n'.-i t1driv .tw g186013E i, 'p72319869 P IonsIet edyBetween2 PInt Safety wAlesan Tehnl-T ~;"

l ;.:.-' O: AL. 'OWER REACTOR CEISEE6 AND WPLIANTS.W aa ' .

I~6011!~~-~4-` 1031 fpvcxors qu o a-dia 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 . - Dlstrild,PPbUCta.JidedIhReearch pmud5/198 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 mps$.~<

a a -.- a.a-~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~e,Lterwa a ~ aa a a4aa a a ~ &~N)£M ES IG b W O SfUP l SWyS § -(tSFS s)t I'P

~~ 04/2411~988- $enlieun6 F., ;tciiiR~Id¶ns aa ~ N frniW1 Wpdnq fthii Genii fe as~um;a g18F:. 9 ',. S - O3"'. ._ . Arech ficatp so1Liti b ne ro6 H Issu e 8-59 (n I) L o O p r to nin OW Rs And :his e i d 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

_~~~~ _ v . -

',.-Aa.

-1 "a.

.  : i-a -a

',, a a ::t¶;9 r- *,a ~ :-

- - t ~ . - a-. s a-a § f obbra 'rt al"~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~a-a 13

BROWNS FERRY UNIT 1 RESPONSE TO GENERIC COMMUNICATIONS ISSUED SINCE 1985 File Name Date Description Response gl86OOSz 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

-- c s' oI~~~~~~~p19is~~~~~~~d~~~uIred .7~re g1078 }^r: 1503i2011988 Transmittal of NUREG-1190 RegatdingTeS Onofr Un-1 Loss of Powbi, This gehb& lt*e Is prvided fo inforrhatl6honly; and does notinvolve' ny -..

g186004 02/1311986 Policy Statement On Engineering Expertise On Shift TVA provided the requested nformation by letter dated May 29, 1986. There were no commitments contained in TVA's letter.

080-3-i j O l8 pplftio Fotl.Uicnsemndmoents $ N20/N' sp,ecfic t-e;bn?se to this lItter to rr g1850022

• ~ ~0t~31I98B1 TechniRestlIU0tiiof Gdnbirlsi B-19 -.Thedrmal ydalcSbit -' Thi 6e-r4 l6tt-brdoes' no nld n etii1 eqirInsbhaii"7 g186001" 010198~8 ComiriAAA661ted With Pl,13f6ks InThie SWI'Scafedted*'

y,~p A~~~~~~~~~FA 94;& , .A - i . .r!w zl81iiXi-;}2 ->l'I Gor, Gsf:IeLmftJtcatffLO*as.ffitl tOt I.-, l ' - M I ' g .

g185020~-'~ - ,1l0811985" RM1Lif' GoIb SdM9§otirnpo1 Ietted ajdeJ9 UIatblMAi"qNirSmSntT o an 85V. 1 *19MB-fi? Ae$^fRmW;,ol,oS oth. S } Et < ,SvSih* -le,2.fislr ¢-t e, g1501 9 j I0P2198-R, O~1~V Cwtft Ib&d1n ~k ~ ~ tIIilh l~~li gl~ S hsIt~~~

01850ZJ t .8:2* . , Milbl dfS Otidift 2 1d 3To NOREG-033 RA' Pidiatori'. Of , 1:I1;fttel de p. IZ*iI .uirm et dancO lcehseso ff

"* ' V1 b h 6A~

gIlS 168;%> '4011198 Hlbh:8oron Coiicahtfatj6ns^y 'n  ? i,' ,r, - ' Nb vbtttr_ re~oi Dior pe,iR"ooi 6I -Irb BTiaette

'^5fO4

!8> ld

,~~~~~~~~~~~~~100 o g151 37' 0811985;~~. CoItim~rcTa7 g185014 fnoitiaid Z& ODifris Storage At Po*~r r19FR5C.49.

R~~tor p o* ElectLctqulpnMinW Qtt~SO Of LeVel Radiobotive Wateb Thistitn No 3niietterpna bpr e4iohrefoi/

rpofi bo irqLreb a o' thislte ^ay.i

'.s.3o-hd

.- ,>..>  : *er, -C' <. -$ i??%t:v;

._________.__.__.__,________o__iffg_________-_

~(,805,~ Ttiifit 0:NUPRF-154,RegardTho Davi -8es-s- L6"OfA An Itn g185012 - 2> s ~405612985i!

- IhnlsIbetiafThnf Ant1oii Itbni ll.Ka; Trip Of Retdr C661n TO, nieHie-^A:iiflot w~~~~~~~~~~~~~~~~~~~~~At O AP ALICANTSAND 'LICENSEE LCENSEE WImTH WESTINGHOS (W)

K 'o~AM

-jlvL88'9aQj,'. Nhip'CFi*'8.'ei. ,T RSKO' ',-i,-, t>'t bE~IGN9'i NUdL LVA4StE~fS1b4dSS gIssO;i &.0658985

- *g C iblth'of.nPScha'eIIleo"Cor'l Ot'M IIevy,L eds At N,clear.P iffc c185010 "o V Te1hll$ F enrlIetter 83-28j,IthiS43 iind 44 , Novft' respoihaee1ffd1Woii riui6d thlVettdh

~ 523l85 eciIcIS~iicUn~V05e/23L09r 328 te 8 85`teIreio~6or,6dl TehI&eHIrdBhtIslttr g185008 .. 'i051231O85§*. 0O~CFR20.408,T itio,i fts o ~~l615~

0%oiit'~bi;l, t g185002 3/4017115' AtIg:-R~?~$Sn GnrtrTb htgly OAL?IUf WR 14CENSEE8SOF!ERATING,IECTR; PLIAT 4~~*

-,~~~'," ~~~ ' ,FO~~~~~ O~~~A11NG~~ 1cbtN i1'iAb~.~ -AND14 DELbS017 CWI'TRU0tION 14

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

-t 0111811985 Quality Asur Guidance for ATS EqipmentThat ls Not Safete-Relitedt Reporng ruirment relating th AIS are reet in 10 CFR

.~~~ ~ ~~ ~ ~~

.~~~ AT.rWaS rulen aree prheis

'.om ai "X , iateid

,M 0,~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

gi85005 - . T' ALL-PRESSURIZEDWATERREACTOR'LICENSEES r,.

gl804 01/2811s8 Operatlnd UniHxbmiihatn9  !->q >jolt-ZdUr ic du1des- t ~nco

'<<9<%;^'..Y; sits thl fomt gl8;02 - 11985;-,, n o le Conirol CaYcf StLndby liquid Corl :Them aI retoinltfor requirtsetsated bSysbm t thisge oo ite.

?

gl8501 11091985FIre p?rotebnPlc~teiI onnto Reor G.6dd6r Letter,(GL asWDRIF 650 6l~Udol bcmln tpbi Legend:

_____________ Listed as open In the framework letter.

___,-_;-,__;,_________ Not applicable or no response required.

15

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNIT 1 REGULATORY FRAMEWORK

- I

.49

- C *S ¶ $

4 C

"'C,'

'C

• C'C1,C

-C--

'C,

• CC.

I

'C' C -

C-h-.-

nfl...

- a,, NRR ROCfATJ I

4C .C *C C

-C--*-*-C-.----.-C,CC C----- -s

... -' -C-C

-I Il .1'--.

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

- Enclosure 1

• 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

• INPO Tim Abney 14

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

• ITS Table 3.3.6.1 Reactor Water Cleanup (RWCU), Reactor Core Isolation Cooling (RCIC) and High Pressure Coolant Injection (HPCI) Torus and Pump Room temperature functions and calibration frequencies. Reactor Low Water Level and High Drywell Pressure calibration frequencies. HPCI/RCIC steam supply low pressure and exhaust diaphragm high pressure instrument checks.

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)

• Deletion of LPCI MG sets

• 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

• License renewal to be submitted in December 2003

• 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

- w I M , ^l r. X r . -- I - . -- M0 1-' I , I ,* r - - - I . -- ,,, fI - M I M 0  ;

6

. . _ . I i . . . _

_ I _

&__~~~~~~~~~~~~~~~~~~~~~~

• SSSagMAC1tA.fl= 4

-- I mma~-

-_ 4. _ _ ._ .

_.-F

......... _ .-.-. ,_. . ,'LL 'aL'L.'

• 4 Cm r~~~~~~~~~~~~~~~~~~

I S ~ ~~~~~~~~~~~

' 4 4 .-

4 4> nn~~~~

I- _ w- - TVA EFN UNIT-1 MAJOR MILESTONES REV 2

• .- 9,.,

.0

Summary and Conclusion 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).

Tim Abney 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.)

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.

Tim Abney 25