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| issue date = 05/04/1984
| issue date = 05/04/1984
| title = Forwards marked-up Tech Specs from 840430 Amends 98,92 & 65 to Licenses DPR-33,DPR-52 & DPR-68,respectively,re Inservice Insp Requirements,Correcting Errors
| title = Forwards marked-up Tech Specs from 840430 Amends 98,92 & 65 to Licenses DPR-33,DPR-52 & DPR-68,respectively,re Inservice Insp Requirements,Correcting Errors
| author name = MILLS L M
| author name = Mills L
| author affiliation = TENNESSEE VALLEY AUTHORITY
| author affiliation = TENNESSEE VALLEY AUTHORITY
| addressee name = DENTON H R
| addressee name = Denton H
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000259, 05000260, 05000296
| docket = 05000259, 05000260, 05000296
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:REGULATOR NFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:8005080087 DOC.DATE: 80/05/00 NOTARIZED:
{{#Wiki_filter:REGULATOR   NFORMATION DISTRIBUTION SYSTEM       (RIDS)
YES FACIL:50-259 Browns Ferry Nuclear Power Stat{oni Unit li Tennessee 50-260 Browns Ferry Nuclear Power Stations Unit 2r Tennessee 50-296 Browns Ferr'y Nuclear Power Stations Unit 3i Tennessee AUTH BYNAME AUTHOR AFF I LI A T ION MILLS i L.th.Tennessee Valley Authority REC IP~NAME RECIPIENT AFFILIATION DENTONeH~RE Office of Nuclear Reactor Regul at ion~Director DOCKET 4 05000259 05000260 05000296
ACCESSION NBR:8005080087           DOC.DATE: 80/05/00     NOTARIZED: YES           DOCKET 4 FACIL:50-259 Browns Ferry       Nuclear Power Stat{oni Unit       li Tennessee   05000259 50-260 Browns Ferry Nuclear Power Stations Unit 2r Tennessee BYNAME 05000260 50-296 Browns Ferr'y Nuclear Power Stations Unit 3i Tennessee               05000296 AUTH                   AUTHOR AFF I LI A T ION MILLSi L. th.         Tennessee Valley Authority REC IP ~ NAME         RECIPIENT AFFILIATION DENTONeH ~ RE         Office of Nuclear Reactor     Regul at ion~   Director


==SUBJECT:==
==SUBJECT:==
Forwards marked-up Tech Specs from 840430 Amends 98~92 L 65 to Licenses DPR"33iDPR-52 8 DPR-68 respectivelyire inservice insp requirementsicorrecting errors.DISTRIBUTION CODE: A001S COPIES RECEIVED:LTR ENCL SIZE: Bl TITLE: OR Submittal:
Forwards marked-up Tech Specs       from 840430 Amends 98~92       L 65 to Licenses DPR"33iDPR-52 8 DPR-68 respectivelyire inservice insp requirementsicorrecting errors.
Gene'ral Distribution NOTES:NMSS/FCAF 1cy.1cy NMSS/FCAF/PM, NiviSS/FCAF 1cy~1cy NMSS/FCAF/PM
DISTRIBUTION CODE: A001S COPIES RECEIVED:LTR               ENCL       SIZE:   Bl TITLE: OR Submittal: Gene'ral Distribution NOTES:NMSS/FCAF 1cy. 1cy NMSS/FCAF/PM, NHSS/FCAF/PM'5000259 NiviSS/FCAF 1cy ~ 1cy NMSS/FCAF/PM ~
~NMSS/FCAF 1cy.1cy NHSS/FCAF/PM'5000259 05000260 05000296 RECIPIENT ID CODE/NAME NRR ORB2 BC 01 INTERNAL: ELD/HDSP NRR/DL DIR NRR/METB F IL 00 COP IF S LTTR ENCL 7 7 0 1 1 1 1 1 RECIPIENT ID CODE/NAME.
NMSS/FCAF 1cy. 1cy 05000260 05000296 RECIPIENT         COP IF S          RECIPIENT            COPIES ID CODE/NAME        LTTR ENCL      ID CODE/NAME.        LTTR ENCL NRR ORB2 BC     01     7        7 INTERNAL: ELD/HDSP                           0  NRR/DE/MTEB              1     1 NRR/DL DIR                      1  NRR/DL/ORAB             1    0 NRR      /METB          1        1  NRR/DS I/RAB             1 F IL      00      1       1   RGN2                    1     1 EXTERNAL: ACRS               09     6       6   LPDR            03      1     1 NRC PDR        02      1       1   NSIC             05     1     1 NTIS                    1       1 NOTES; TOTAL NUMBER OF COPIES REQUIRED: LTTR           27   ENCL     25
NRR/DE/MTEB NRR/DL/ORAB NRR/DS I/RAB RGN2 COPIES LTTR ENCL 1 1 1 0 1 1 1 EXTERNAL: ACRS NRC PDR NTIS NOTES;09 02 6 6 1 1 1 1 LPDR NSIC 03 05 1 1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 25 0 tl tt lI tl e~I ll r o tt e ff II 1I tt ll IA II tt tt h II TENNESSEE YALLEY AUTHORITY CHATTANOOGA.
TENNESSEE 37401 400 Chestnut Street Tower II May 4, 1984 Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555


==Dear Mr.Denton:==
0 tl tt                lI tl              e    ~     I e
In the Matter of the Tennessee Valley Authority Docket Nos.50-259 50<<260 50-296 By letter from R.J.Clark to H.G.Parris dated April 30, 1984, Amendment Nos.98, 92, and 65 were issued to license Nos.DPR-33, DPR-52, and DPR-68 for the Browns Ferry Nuclear Plant units 1, 2, and 3.Those amendments revised the technical specifications to refer ence 10 CFR 50.55a(g)for inservice inspection requirements.
ll r                         o   tt ff    II tt    ll 1I IA II tt tt h
A review of the issued technical specifications revealed that they contained a number of inadvertent error s.We, therefore, cannot implement those technical specifications issued by the subject amendments.
II
We have marked the technical specifications for each unit to indicate the errors found.Those marked pages are provided in enclosure 1.The corrected pages which are needed are provided-in enclosure 2.This was discussed with R.J.Clark of your staff on May 4, 1984.Very truly yours, TENNESSEE VALLEY AUTHORITY<.Subscribe
~d sworn to efore me this~day of II r Notary Public My Commission Expires L..Mill.s, Manager Nuclear Licensing 1984.Enclosures cc: See page 2-8405080087, 840504 PDR ADOCK 05000259 P'DR pg)I An Equal Opportunity Employer 0 I" a l l/+I 4 h\/j rg g~V Mr.Harold R.Denton cc (Enclosures):
U.S.Nuclear Regulatory Commission Region IE ATTN: James P.O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 Mr.R.J.Clark Browns Ferry Project Manager U.S.Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20810 ATTACHMENT TO LICENSE AMENDMENT NO.98 FACILITY'PERATING LICENSE NO.DPR-33 DOCKET NO.50-259 Revise Appendix A as follows: 1.Remove the following pages and replace with identically numbered pages.182 183 184 209 210 211 212 213 214 2.The marginal lines on these p ges denote the areas being changed.
]IMITINC CONDITIONS FOR 0 TION SURVEI).LANCE'KQU?
RENE?)TS ge.~Mok~c Pv~Gp~~M 3.6.l'cL--F'a-vsccateh l.l, C~J(The ladle~ted valw af cree flav fate varies fra tlv value derived f mes leep f lov ureeurascata by sac'r.thaa]OX.The di (i>>see t~lover p li avn d)f ferencial praaiur~raid Lnt 0@I an LadtTilucl
]~L pveip e ariea free cha urau pf all$ec p~C'frran-tial preaaveaa by care thar 10Z.Th'eactor shall not bc, opera ed vith one recircu'oticn lo ip out of scrvf c.fur more than 2h hours<<with the reactor operatitg,.lf'ne recirad.ation loop is oui.of.service, the plant shall be placed La a hot shuidcrm condition vitl n 24 hen~s uiuess tne loop ia sooner ret'.tm d to serricc.Uhencver Chere ia recirculate
'eae flov vith che ccactpc in the Startup ar Run Node and cne-e-Circulat ion pvnp ia uperat:n l vs eh the eeueltarr vrlve air>>C, Che dif fusser to lover please differential penna>>re ahall checbed (all-, and chr dtf(ere tinl pceaaure of an Lndlvle'.uel get pump in~lue p shall oat vary frer rhr ncaa of all'et pump elf ereacial pceiaurea la that lonp by mire chan lot.3.F>11'.,qnlt one pucp ope.<<ion~the diacharfe valve of the lov speed]n~cay not be opened ua!ass the speed o.the faster pm's 1css than cOn of ita rated speed.Str~dy stat." operation~<th both r ec)rcul at)nn pumps out of ser-vice for up to 12 hrs is per-mi t ted.Ourihg such inter val restart of).h.recircu)ation unos is perm>tted.
provided the sop discharge temperature is<ith)n 75 F of the saturation temperaturr of the reactor vessel vater as determined by'oiw pressure.The.to(a 1 elapsed time in natural circula<<lion and o ie pump o)erat)on must h.no grcalrr than 24 nrs.F.Recirculation Pump eration 1ecittulacsoa pmp apeeda~hs]l be chac)eed and lagged at least knee pcc day.2.Nn ndrli t lnnn)'nurvel1 lane c requtrcrl.
l.Before start inn c]thrr rec ircu]at i on pump dur ina steady state operac ion, c)reck and loR the loop discharpe temperature and dome saturation temperacure.
*Section 3.6.F.l is amended to permit operation with one recirculation loop out of service from January 25, 19S3 to midnight (CST)January 31, 1983 in.accordance with the conditions of Section 3.6."F.4]R2 Amendment No.g, g$
0 ef L,JMI.1 J.": C!)NnnLQ kS.':t rivet iir~l Intc~rl~t 1.The structural integrity of the primary system shall be main-tained at the level required by the original acceptance standards throughout the life of the plant.The reactor shall be maintained in a cold shutdown condition until each indication of a defect has been investigated and evalua'ted.
(~p p~[5Z-SllRVE ILLAHCE REOJ'HF.NTS 4.6.C,Structural genre rit 1.Inservice inspection of ASME Code Class 1, Class 2, and Class 3 components shall be performed in accordance with Section ZI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by NRC pursuant to 10 CFR 50, Section 50.55 (g)(6)(i).
2.Additional inspections shall ba performed on certain circuraferon-tial pipe voids as listed to pro-vide additional protection against pipe vhip, Mhich could damage auxiliary and control sys-tems~'cadwater CFM-9, CTV-12, KFV-31, KTM-39, KFM-38, KF w-13 CPM-26, CFM-29, GFw-15, and G FV-3 2 Hain scca%CMS-6, KHS-24, CHS-32, KMS-104 GMS-15, and CMS-24 18 Core Spray DSiUlR-4 DSCS-12 DSCS-5, DSRP~-I DS~-SA DSCS-11, and DSCS 4 Amendment No.98


Vo LINITINl.CONDITIONS FOR OPERATION SURVFIT.7ANCE R EQNIREMENTS N~II I I 1 3.6.0 Structural Inte rit 4.6.C.Structural Intc ritv Reactor Cleanup-DSRWC-4, DSRWC-3 DSRWC-6, DSRWC-S HPCI THYCI-152 THPCI-153B" THPCX-153 THPCI-154<~" y For Unit 1 an augmented inservice surveillance program shall be performed to moni tor potential corrosive effects of chloride residue-released during the March 22, 1975 fire.The augmented inservice surveillance program is specified as follows: a.Browns Ferry Mechanical Maintenance Instruction 53, dated September 22, 1975, paragraph 4, deFines the liquid penetrant examinations required during the first, second, third and fourth refueling outages following the fire restoration.
TENNESSEE YALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 400 Chestnut  Street Tower    II May  4, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
b.Srowns Ferry Mechanical Maintenance Instruction 46, dated July 18, 1975, Appendix 8, defines the liquid penetrant examinations required during the sixth refueling outage following the fire restoration.
184 Amendment No.98


PAGES-DELETED 209-214 Amendment No.98
==Dear Mr. Denton:==


ATTACHMENT TO LICENSE AMENDMENT NO.92 FACILITY OPERATING LICENSE NO.DPR-52 DOCKET NO.50-260 Revise Appendix A as follows: 1.Remove the following pages and replace with identically nUmbered pages.182 183 184 209 210 211 212 213 214 2.The marginal lines on these pages denote the areas being changed.  
In the Matter of the                                      Docket Nos. 50-259 Tennessee      Valley Authority                                      50<<260 50-296 By letter from R. J. Clark to H. G. Parris dated April 30, 1984, Amendment Nos. 98, 92, and 65 were issued to license Nos. DPR-33, DPR-52, and DPR-68 for the Browns Ferry Nuclear Plant units 1, 2, and 3. Those amendments revised the technical specifications to refer ence 10 CFR 50.55a(g)    for inservice inspection requirements. A review of the issued technical specifications revealed that they contained a number of inadvertent error s. We, therefore, cannot implement those technical specifications issued by the subject amendments.
We    have marked the technical specifications for each unit to indicate the errors found. Those marked pages are provided in enclosure 1. The corrected pages which are needed are provided- in enclosure 2.
This  was  discussed with R. J. Clark of your        staff  on May 4, 1984.
Very  truly yours, TENNESSEE VALLEY AUTHORITY L. . Mill.s, Manager Nuclear Licensing
        .Subscribe me II this    ~~d    sworn to day of efore 1984.
r Notary Public My Commission  Expires Enclosures cc: See page    2 pg) I
                    'DR 8405080087, 840504 PDR ADOCK 05000259 P
An Equal Opportunity Employer


LI!!I.l.':0 CONDITIO".:5 FOR OPER.TTOM" SURVEII.LhMCE RFOUIRRMENT 4.6.E Jc t Pun<<s:.ec=="ulation Pu.n Oneratian 2.'oll o<<ing operation valve of nay not b the speed pump is 1 its rated one panp the discharge thc-1 o<<speed pump e opeacd unless of the faster ess than 50%of speed.state opesa t ion<<i th ci seal at ion pumps service for up to 12 s permitted.
0 I"
During terval restart of i rcu 1 a t i on pumps 1 s ed, provided the schar" e tcmpesatuse in 754F of the ion tcnpcsa tuse of ctor vessel<<ates as ned by done e.The total tine in natural tion and onc pump on must be no thaa 24 hours.3.S t eady'oth re out of hours i such in the rec pernitt loop di i s<<ith saturat t e sea de terni pse s sar elapsed c i rcula operati gsea ter 1.There" ctor shall not be opera ted>>it,h one recirc latioa)oop out of serv ice f or nore than 24 hours.Vi th the reactor opcsa t ing, if oae reci reals t ion loop is out of se v ice, the plant shal 1 be placed in a hot shutdo<<n condition<<ithin 24 hours unless the loop is sooner returned to service.b.The indi ca ted value of core flo>>rate varies from the value derived from loop flow measurements by nore th an 10%.er to lower f ere at i al eading on au jet punp n the mean of c.The di f fus plenum dif pressure r iad ividua 1 verses fro all get pu differenti by nore th np al pressures an 10%.2~Whenever there is recirculation flo>><<ith the reactor in the Startup or Run Hode and one recirculati on pump is opera ting<<i th the equalizer valve closed, the diffuses to lo<<es plenum d iffeseatial pressure shall bc checked daily and the differential pressure of an individual jet pump in a loop shall not vary iron the mean.of all jot pump differential pressures in that 1oop by morc than 1 0%.I Recirculation Puno Onera-ion 1.Recirculation pump speeds sha)1 bo checked and logged at least once per day.2.No additional surveillance required.3.Before starting either recirculation pump during steady state operation, check and log the loop discharge temperature and dome saturation temperature.
a l /+l I
amendment lio.gg, gg, 85, 92 ld2
4  h
                    \ /j rg
              ~
g V


1 lMa'!-1%i; C<)N~nn,kS
Mr. Harold R. Denton cc (Enclosures):
.':t r!!ct>>r<<l 1ntr~r t~t SURVEILLANCE REOJ F NTS 4.6.C Structural Inte rit 1.The structural int'egrity of the primary system shall be main-tained at the level required by the original acceptance standards throughout the life of the plant.The reactor shall be maintained in a cold shutdown condition until each indication of a defect has been investigated and evaluated.
U.S. Nuclear Regulatory Commission Region IE ATTN:   James P. O'Reilly, Regional Administrator 101  Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 Mr. R. J. Clark Browns Ferry Project Manager U.S. Nuclear Regulatory Commission 7920  Norfolk  Avenue Bethesda,   Maryland  20810
l.Inservice inspection of ASME Code Class 1, Class 2, and Class 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda's required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by NRC pursuant to 10 CFR 50, Section 50.55a (g)(6)(i).2.Additional inspoctions shall be perfor!ded on certain circu!!!Eeron-tial pipe ualda as listed to pro-vide additional protection against pipe Mhip, Mhich could da!!!age auxiliary and control ays-te!!!s.Pcod&dter GPV-9, KFW-13 GTV-12, CPM-26, KFM-31, CPW<<29, K?M-39<CPw-15<KFM-3S, and CFM-32 Main stcam CMS-6, KMS-24, CMS-32, KMS-104 CMS-15, and CMS-24)8 RHR Core Spray DSRIE-w DSR1!R os~-6 DSCS-12.OSCS-11, DSCS-S, and DSCS-4 Amendment No.92


I LZMZTZ'NG CONDITIONS FOR dPERATZ SURVEILLANCE RE UIREMENTS 3.6.G Structural Znte rit 4.6,C S.=ucrurx'7 aaggr g'~l.~anus'S.i'riC-4, DS3;.'C-S,+~5;U%4 r~one DSYs~C-5 HPCZ-THPCZ-70 THPCZ-70A THPCZ-71, and THPCZ-72'I~184 Amendment No.92 l
ATTACHMENT TO LICENSE AMENDMENT NO. 98 FACILITY'PERATING LICENSE NO. DPR-33 DOCKET NO. 50-259 Revise Appendix A as follows:
PAGES.DELETED 209-214 Amendment No.92 i.+.o Y ATTACHMENT TO LICENSE AMENDMENT NO.65 FACILITY OPERATING LICENSE NO.DPR-68 DOCKET NO.50-296 Revise Appendix A as follows: 1.Remove the following pages and replace with identically numbered pages.t 196 19/za9~Z.to g.g p 2.f3 p/+, 2.The marginal lines on these pages denote the areas being changed.  
: 1. Remove the following pages and replace with     identically numbered pages.
182 183 184 209 210 211 212 213 214
: 2. The marginal lines on these p ges  denote the areas being changed.


LI H l T I NC CONG ITIOUS FOR OPERATION SURVEILLANCE REQU I REHENTS 3.6 1'.2l err 9"T 4 6 P 9 Y S STPM UHOARY Co Structura Intearit G.Structural Tntearit The structural integrity of the primary system shall be maintained at the level required by the ariqinaL acceptance standards throughout.
          ] IMITINC CONDITIONS FOR 0                TION                          SURVEI).LANCE'KQU?RENE?)TS ge.~Mok~c Pv~ Gp~~M                                l.l, C ~J(
the life af the plant The reactor shall be maintained in a cold shutdcm candition until each indication of a gross de f ect,which could adversely affect the structural integrity af the reactor coolant pressure boundary, has been investigated and evaluated.
3.6.l'cL- -F'a -vsccateh                                                    The    ladle ~ ted valw af cree flav fate varies fra tlv value derived f mes leep f lov ureeurascata by sac'r.
l.Enservice inspection of ASP"" Cade Class 1, Class 2, and Class 3 components shall be per<<formed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CER 50, Section 50.55a(g), except wnere specific written relief has been granted by KK pursuant ta 10 CZR 50, Sectian 50.55a(g)(6)(i)~f7 c,~Ear c'.$~ge..sligo Ice 6e.wMK A~p~.z6&j-t(~gpQc Q Q j$Qo~info is p~2.Additional inspections shall be performed an certain circumf erential pipe fields as Listed to provide additional protection against pipe i>hip, which could cicmage auxiliary and control systems.Amendment Nos,, 65'p6 Feedwater-Gc 4-CFN-RFH Xr~-Ri Pi4 9, KFH-13,~2~CP4 2(~3lg Vl t pQ~39 C~ii-'3&)fly'Qg R J~
thaa ]OX.
q 4..s LIMITINC CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3 b RZMAR S 4~6 Main steam-GMS-6, KMS-24 GMS-32, KMS-104~GNS-15~and GMS-24 RHR DSRHR-6~DSRHR-7 and DSRHR-4 Core Spray-DSCS-12,'SCS-11 DSCS-5, and DSCS-4 Reactor Cleanup-DSRWC-4, OSRM-3 DSRWC-6 and DSRWC-5 HPCX-THPCI-70 THPCX-70A THPCZ-7l, and THPCX-72 R~~>P E~ilCB Plant, Safety Analysis (BFNP FSAR subsection 4~12)l97 Amendment, HQ.65
The   di ( i>>see t ~ lover p li avn d)  f ferencial praaiur ~ raid Lnt 0@I an LadtTilucl ] ~ L pveip e ariea free cha urau pf tial all  $ ec  p~    C'frran-preaaveaa    by care thar 10Z.
Uhencver Chere ia recirculate          'eae flov vith che ccactpc in the Th'eactor shall           not bc,                           Startup ar Run Node and cne -e-opera ed vith one recircu'oticn                              Circulat ion pvnp ia uperat:n l vs eh the eeueltarr vrlve air>>C, lo ip out of scrvf c. fur more                              Che dif fusser to lover please than 2h hours<<with the reactor                              differential penna>>re ahall operatitg,     . lf'ne    recirad.ation                    checbed (all-, and chr dtf(ere loop is oui. of.service, the                                tinl pceaaure of an Lndlvle'.uel plant shall be placed La a hot                              get pump in ~ lue p shall oat shuidcrm condition vitl n                                    vary frer rhr ncaa of all 'et 24 hen~ s uiuess tne loop ia pump elf ereacial pceiaurea la sooner ret'.tm d to serricc.                                 that lonp by mire chan lot.
F>11'.,qnlt one pucp ope. <<ion        ~
F. Recirculation          Pump      eration the diacharfe valve of the lov speed ]n~ cay not be opened                                  1ecittulacsoa pmp        apeeda  ~ hs]l ua! ass the speed o. the faster                              be chac)eed      and lagged at    least pm's        1css than cOn of ita rated speed.
knee pcc day.
Str~dy stat." operation ~<th both                        2. Nn  ndrli t lnnn) 'nurvel1 lane      c 3.
r ec ) rcul at) nn pumps out of ser-                          requtrcrl.
vice for up to 12 hrs is per-mi t ted. Ourihg such inter val                      l. Before start inn c]thrr restart of        ).h. recircu)ation                        rec ircu] at i on pump dur ina unos  is perm>tted. provided the                          steady state operac ion, c)reck sop  discharge temperature is                              and loR the loop discharpe
                      <ith)n    75  F    of the saturation                        temperature and dome temperaturr of the reactor                                  saturation temperacure.
vessel vater        as  determined by pressure. The. to(a 1            'oiw elapsed time in natural circula<<
lion and o ie pump o) erat)on must
: h. no grcalrr than 24 nrs.
*Section 3.6. F.l is amended to permit operation with one recirculation loop out of service from January 25, 19S3 to midnight (CST) January 31, 1983 in .
accordance with the conditions of                                  ]R2 Section 3. 6."F. 4 Amendment No.      g,   g$


PAGES DELETED 203-208 Amendment No.65 Vy ENCLOSURE 2 CORRECT TECHNICAL SPECIFICATIONS FOR INSERVICE INSPECTION REQUIREMENTS (TVA BFNP TS 89 AND TVA BFNP TS 169)BROGANS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 ATTACHMENT TO.LICENSE AMENDMENT NO.98 FACILITY OPERATING LICENSE NO.DPR-33 DOCKET NO.50-259 Revise Appendix A as follows: Remove the following pages and replace with identically numbered pages.182 183 184-209 210 211 212 213 214 2.The marginal lines on these pages denote the areas heing changed.
0 ef SllRVE ILLAHCE REOJ          'HF.NTS L,JMI. 1 J.": C!)NnnLQ kS
.Llitl;TING CONDITIONS FOR OP TION SURVEILLANCE REQUX ENTS 3.6.F Recirculation Pumn Operation 1.The reactor shall not be opera te d w i th one recirculation loop out of serv icc f or more than 24 hours.Kith the reactor operating, if one recirculation loop is out of service, the plant shall be placed in a hot shutdown conditi.on within 24 hours unless the loop is sooner returned to service.2.Following one pump operation, the discharge valve of the low speed pump may not be opcncd unless the speed of thc faster pump is less than 50%of its rated speed.3.Steady state operation with both recirculation pumps out of service for up to 12 hours is permitted.
        .':t rivet iir~l Intc~rl~t            4.6.C,Structural         genre    rit
During such interval restart of thc recirculation pumps is permitted, provided the loop discharge temperature is within 754F of the saturation temperature of'he reactor vessel water as determined by dome prcssure..The total elapsed time in natural circulation and one pump operation must be no greater than 24'hours.b.The indi ca tcd value of.core flow rate varies from the value derived from loop flow mcasuremcnts by more than 10%.c.The dif fusez to lower plenum differential pressure reading on an individual jet pump varies from the mean of all jet pump differential pressures by more than 10%.4.6.F Recirculation Pump 0 eration 2.Recirculation pump speeds shall be checked and logged at least once'per day.No additional surveillance required.2.Whenever there is"recirculation flow with the reactor in the Startup or Run btode and one recirculation pump is operating with the equalizer valve closed, the diffuser to lower plenum differential pressure shall be checked daily and the diffcrcntial pressure of an individual jet pump in a loop shall not vary from the mean of all j e t pump diffezential pressures in that loop by more than 10%.3.Before starting either recirculation pump during steady state operation, check and log the loop discharge temperature and dome saturation temperature.
: 1. The structural integrity of the         1. Inservice inspection of            ASME primary system shall be main-                 Code Class        1, Class 2, and tained at the level required by               Class 3 components shall be the original acceptance standards             performed in accordance with throughout the life of the plant.             Section ZI of the            ASME Boiler The reactor shall be maintained               and Pressure Vessel Code and in a cold shutdown condition                 applicable Addenda as required until each indication of a   defect           by 10   CFR 50, Section 50.55a(g),
182 Lg aiXI'l gr." C!)g~nQikS.~OJ~'lAZU1U 3~6 G."l lucT ursI Inta r it SllRVKILLAHCE Rt:OJ'ARE'HFNTS 4.6.C Structural Intc rit 1.The structural integrity of the primary system shall be main-tained at the level required by the original acceptance standards throughout the life of the plant.The reactor shall be maintained in a cold shutdown condition until each indication of a defect has been investigated and evaluated.
has been investigated and                      except where specific written evalua'ted.                                  relief has been granted by NRC pursuant to 10 CFR 50, Section 50.55 (g)(6)(i).
l.Inservice inspection of ASHE Code Class 1, Class 2, and Class 3 components shall be performed in accordance with Section ZI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by NRC pursuant to 10 CFR 50, Section 50-55a (g)(6)(i)~2.Additional inspactions shall ba"=performed on certain circutafercn-tial pipe Molds as listed to pro-vide additional protection agafnat pipe.vhip, Mhich could damage auxiliary and control aya-tellus~Feedvater Ha in s t can GFM-9, KFV-13 CFV-12, CFw-26, KFV-31, CFW-29, KFV-39, GFw-15, KFM-38, and GEM-32 GMS-6, KMS-24, GMS-32, KMS-104 GMS-15, and GMS-24 18 RHR Core Spray DSRIIR-4, DSRHR-7, DSRHR-8P, DSCS-12, OSCS-11, DSCS-5, and OSCS-4 Amendment No.98 LIMITING CONDITIONS FOR OPERATION BURVFII.IANCE RKqHIRIZHNTS 3.6.O Structural Inte rit 4-6 t Structural Into'ritv Rene tor Cleanup-DSRWC-4, DSRWCr3 DSRWC-6, DSRWC-5 HPCI THYCI-152 THPCI-153B THPCI-153 THPCI-154~f 0 g~~'I.I~P, 3..For Unit 1 an augmented inservice il lance ro ram shall be surve p g performed to monitor potential corrosive effects of chloride residue.released during the March 2Z, 1975 fire.The augmented inservice surveillance program is specified as follows: a.8rowns Ferry Mechanical Maintenance Instruction 53, dated September 22, 1975, paragraph 4.defines the liquid penetrant examinations required during the irst, second, third and fourth refueling outages following the fire restoration.
(~p 5Z-p~    [
b.8rowns Ferry Mechanical Maintenance Instruction 46, dated July 18, 1975, Appendix 8, defines the liquid penetrant examinations required during the sixth refueling outage following the fire restoration.
: 2.       Additional inspections shall ba performed on certain circuraferon-tial pipe voids as listed to pro-vide additional protection against pipe vhip, Mhich could damage auxiliary and control sys-tems ~
184 Amendment t<o.98  
                                                                    'cadwater CFM-9,   KF w-13 CTV-12, CPM-26, KFV-31, CFM-29, KTM-39, GFw-15, KFM-38, and G FV-3 2 Hain scca%              CMS-6, KHS-24, CHS-32, KMS-104 GMS-15, and CMS-24 DSiUlR-4   DSRP~- I DS~-   SA Core Spray              DSCS-12     DSCS-11, DSCS-5,   and DSCS  4 18 Amendment No. 98


PAGES DELETED 209-214 Amendment No.98 ATTACHMENT TO LICENSE AMENDMENT NO.92 FACILITY OPERATING LICENSE NO.DPR-52 DOCKET NO.50-260 Revise Appendix A as follows: 1.Remove the following pages and replace with identically numbered pages.182 183 184 209 210 211 212 213 214 2.The marginal lines on these pages denote the areas being changed.
N
C
                                                                            ~  II I
.LIltlTING CONDITIONS FOR OPTION SURVEILLANCE REOU-fENTS V/" 3.6.F Recirculation Pumo 0 eration 1.The reactor shall not be opera ted with onc roc ircula t ion loop out of serv icc f or more than 24 hours.With the reactor operating, if onc recirculation loop is out of service, the plant shall be placed in a hot shutdown condition within 24 hours unless the loop is sooner returned to service.2.Following onc pump operation, the di scharge valve of the low speed pump may not bc opened unlessthe speed of the faster pump is less than 50%of its rated speed.3.S teady s ta te opera tion wi th both recirculation pumps out of service for up to 12 hours is permitted.
I Vo                                                  1 LINITINl. CONDITIONS FOR OPERATION            SURVFIT.7ANCE  R EQNIREMENTS 3.6.0   Structural Inte rit          4.6.C.     Structural Intc  ritv Reactor Cleanup  -  DSRWC-4, DSRWC-3 DSRWC-6, DSRWC-S HPCI        THYCI-152 THPCI-153B"        < ~"
During, such interval restart of, the recirculation pumps is pcrmittcd, provided the loop discharge temperature is within 750F of the saturation temperature of'he reactor vessel water as dc term inc d by dome pressure..Thc total elapsed time in natural circulation and one pump operation must be no greater than 24'hours.b.Thc indicated value of.core flow rate varies from the value derived from loop flow measurements by more than 10%.c.The dif fuser to lower plenum differential pressure reading on an individual jet pump varies from the mean of all jet pump differential pressures by mox e than 10%.2.Whenever there i s'recircula tion flow wi th the reactor in the Star tup or Run hfode and one recirculation pump is operating with the equalizer valve closed, the diffuser to lower plenum differential pressure shall be checked daily and the differential prd'ssurc of an individual jet pump in a loop shall not vary from the mean of all jet pump differential pressures in that loop by more than 10%.4.6.F Recirculation Pump Operation l.Recirculation pump speeds shall be checked and logged at least once'per day..2.No additional surveillance required.3.Before startinp either recirculation pump during steady state operation, check and log the loop discharge temperature and dome saturation temperature.
THPCX-153 THPCI-154        y For  Unit an augmented inservice 1
182
surveillance program shall be performed to moni tor potential corrosive effects of chloride residue-released during the March 22,            1975 fire.
The augmented    inservice surveillance program is specified as follows:
: a. Browns Ferry Mechanical Maintenance Instruction 53, dated September 22, 1975, paragraph 4, deFines the liquid penetrant examinations required during the first, second, third and fourth refueling outages following the fire restoration.
: b. Srowns Ferry Mechanical Maintenance Instruction 46, dated July 18, 1975, Appendix 8, defines the     liquid penetrant examinations required during the sixth refueling outage following the fire restoration.
184 Amendment No. 98


LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 4.6.C Structural ante rit 1.The structural integrity'of the primary system shall be main-tained at the level required by the original acceptance standards throughout the life of the plant.The reactor shall be maintained in a cold shutdown condition until each indication of a defect has been investigated and evaluated.
PAGES-DELETED 209-214 Amendment No. 98
1.Inservice inspection of ASME Code Class 1, Class 2, and Class 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has'been granted by NRC pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).2.Additional inspections shall be performed on certain circumferen-tial pipe uelda as listed to pro-vide additional protection against pipe Mhip, vhich cou)d damage auxiliary and control sys-tems.I Pcod'voter GPv-9, KFV-13 GTV-12, GFM<<26, KFM-31, CPJ-29, K?M-39, GFw-15, KFW-38, and GR!-32 Mhin I t earn CMS-6, KMS-2 4, GMS-32, KMS-104 CMS-15, and CMS-24 RHR DSRlE-4, DSR}B-7, OSRHR-6 18 Core Spray-DSCS-12, DSCS-11, DSCS-5, and'DSCS-4 Amendment No.92 LIMIT" NG CONDITIONS FOR dPERAT~~3.6.G Structural Inte rit+/~I 4~6.C St."ucturzi
".nt-'rc."t ac'I nnup DSZriC-~, DSR'.iC-.', DSVriC-S, inc DSR,'riC-5 SURVEILLANCE RE REMENTS~h I nI>~H I/~I HPCI-THPCI-70 THPCI-70A THPCI-71, and THPCI-72<~I 184 Amendment No.92


PAGES-DELETED 209-214 Amendment No.92
ATTACHMENT TO LICENSE AMENDMENT NO. 92 FACILITY OPERATING LICENSE NO. DPR-52 DOCKET NO. 50-260 Revise Appendix  A as  follows:
: 1. Remove the following pages and replace with    identically nUmbered pages.
182 183 184 209 210 211 212 213 214
: 2. The marginal  lines  on these pages denote the areas being changed.


ATTACHMENT TO LICENSE AMENDMENT NO.65 FACILITY OPERATING LICENSE NO.DPR-68 DOCKET NO.50-296 Revise Appendix A as follows: 1.Remove the following pages and replace with identically numbered pages.196 197.209 210 2>l 212 213 214 2.The marginal lines on these pages denote the areas being changed.  
LI!!I . l.':0        CONDITIO".:5 FOR OPER .TTOM        "
SURVEII.LhMCE RFOUIRRMENT 4  .6. E    Jc t Pun<<s
:.ec=="ulation    Pu .n  Oneratian            b. The indi ca ted value of core flo>> rate varies
: 1. There" ctor shall not be                                        from the value derived opera ted>> it,h one                                              from loop flow recirc latioa )oop out of                                        measurements by nore serv ice f or nore than 24                                      th an 10%.
hours. Vi th the reactor opcsa t ing, if oae                                        c. The di f fus er to lower reci reals t ion loop is out                                    plenum  dif f ere at i al of        se    v ice, the plant shal 1                          pressure    r eading on au be placed in a hot shutdo<<n                                      iad ividua jet punp 1
condition <<ithin 24 hours                                        verses fro n the mean of unless the loop is sooner                                        all get pu np returned to service.                                            differenti al pressures by nore  th an 10%.
2.'oll o<<ing              one    panp operation the discharge                              2 ~  Whenever    there is valve of thc - o<<speed pump1                                recirculation flo>> <<ith          the nay not b e opeacd unless                                  reactor in the Startup or the speed of the faster                                    Run Hode and one pump is 1 ess than 50% of                                  recirculati on pump        is its rated speed.                                            opera ting <<i th the equalizer valve closed, the
: 3. S t              state opesa t ion <<i th                  diffuses to lo<<es plenum re ci seal at ion pumps                    d iffeseatial pressure          shall eady'oth out of service for up to 12                                bc checked daily and the hours i s permitted. During                                differential pressure of an such in terval restart of                                  individual jet pump in a the rec i rcu 1 a t i on pumps            1 s              loop shall not vary iron pernitt ed, provided the                                    the mean .of all jot pump loop di schar" e tcmpesatuse                              differential pressures in i s <<ith in 754F of the                                    that    1oop by morc than saturat ion tcnpcsa tuse of                                1 0%.
t e sea ctor vessel <<ates as                                          I de  terni ned          by done                            Recirculation    Puno  Onera-ion pse      s  sar e. The total elapsed tine in natural                              1. Recirculation          pump  speeds c i rcula        tion  and  onc pump                    sha)1    bo checked    and  logged operati on must be no                                      at least once per day.
gsea ter thaa 24 hours.
: 2. No  additional surveillance required.
: 3. Before starting either recirculation pump during steady state operation, check and log the loop discharge temperature and dome saturation temperature.
ld2 amendment          lio. gg, gg, 85,      92


>ZHITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREHENTS.P~R R H 4~6 PR HARY SYSTEH ND Y G.'tructural Inte rit G St uctural Znte rit The structural integrity of the primary system shall be maintained et the level required by the original acceptance standards throughout the life of the plant.The reactor shall be maintained in a cold shutdown condition until each.indication of'a defect has been investigated and evaluated.
SURVEILLANCE REOJ        F  NTS 1 lMa'!-1%i; C<)N~nn,kS
1.Inservice inspection of ASME Code Class 1, Class 2, and Class 3 components shall be performed in accordance with Section XI of the ASHE Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by NRC pursuant to 10 CFR 50, Section 50.55a (g)(6)(i).196 2 0 Additional inspections shall be performed on certain circumferential pipe welds as listed to provide additional protection against pipe whip, which could damage auxiliary and control systems.Feedwater-GFW-9, KFW-13~GFW 12r GFW 26~KFW 31~GFW-29~KFW 39m GFW-15m KFW-38, and GFW-32
      .':t r!!ct >>r<<l 1ntr~r t~t              4.6.C Structural Inte       rit
: 1. The     structural int'egrity of the       l. Inservice inspection of        ASME primary system shall be main-                  Code Class    1, Class 2, and tained at the level required by               Class 3 components shall be the original acceptance standards             performed in accordance with throughout the life of the plant.             Section XI of the ASME Boiler The reactor shall be maintained               and Pressure Vessel Code and in a cold shutdown condition                   applicable Addenda's required until each indication of a defect             by 10 CFR 50, Section 50.55a(g),
has been      investigated and                except where specific written evaluated.                                    relief has been granted by NRC pursuant to 10 CFR 50, Section 50.55a (g) (6) (i) .
: 2. Additional inspoctions shall be perfor!ded on certain circu!!!Eeron-tial pipe ualda as listed to pro-vide additional protection against pipe Mhip, Mhich could da!!!age auxiliary and control ays-te!!!s.
Pcod&dter            GPV-9, KFW-13 GTV-12, CPM-26, KFM-31, CPW<<29, K?M-39 CPw-15 KFM-3S, and CFM-32 Main stcam          CMS-6, KMS-24, CMS-32, KMS-104 CMS-15, and CMS-24 RHR                  DSRIE-w  DSR1!R os~-6 Core Spray          DSCS-12. OSCS-11, DSCS-S, and DSCS-4
                                            )8 Amendment No. 92


A/~0+~f L HI T I NG CONDITIONS FOR OPERANT!ON SUgygILLANCE gggUI RESENTS 3 b RIOR 8 4~6 Hain steam-GMS-6
I LZMZTZ'NG CONDITIONS FOR dPERATZ            SURVEILLANCE RE UIREMENTS 3.6.G  Structural Znte rit          4.6,C S.=ucrurx
~KHS-24,~GHS 32~KHS-104~GMS-15, and GMS>>24:-OSRHR-6, DSRHR-7~and DSRHR-4 4'I.Core Spray-OSCS-12,'SCS-11, DSCS-5, and DSCS-4 Reactor Cleanup HPCI DSRWC-4~DSRbC-3~DSRWC-6, and DSRNC-5 THPCI-70 THPCI-70A THPCI-71, and THPCI-72 R~R ETC S Plant: Safety Analysis (BFHP PSAR subsection 4~12)l97 Amendment No.65 PAGES DELETED 209-214 Amendment No.65 o t}}
                                          '7 aaggr g
                                          '~l.~anus'S.i'riC-4,      +~5;U%4 r ~
DS3;.'C-S, one DSYs~C-5 HPCZ      - THPCZ-70 THPCZ-70A THPCZ-71, and THPCZ- 72
                            'I ~
184 Amendment No. 92
 
l PAGES .
DELETED 209-214 Amendment No. 92
: i. +.o Y
ATTACHMENT TO LICENSE AMENDMENT NO. 65 FACILITY OPERATING LICENSE NO. DPR-68 DOCKET NO. 50-296 Revise Appendix  A as    follows:
: 1. Remove the following pages and replace with identically numbered pages.
t 196
                                        ~19/
za9 Z.to g.g p 2.f3 p/+,
: 2. The marginal    lines  on these pages denote the areas being changed.
 
LIH l T I NC CONG  ITIOUS FOR OPERATION    SURVEILLANCE REQU I REHENTS
: 3. 6 1'.2l err    9  "T                      4 6  P  9  Y S STPM      UHOARY Co    Structura        Intearit                G. Structural Tntearit The  structural                      l. Enservice inspection of ASP""
integrity of the                          Cade Class primary system shall                                  1, Class 2, and be  maintained at the                    Class 3 components shall be per<<
level required by the                    formed  in accordance with ariqinaL acceptance                      Section XI of the      ASME  Boiler standards throughout.                    and Pressure Vessel Code and the life af the                          applicable Addenda as required plant The reactor                        by 10 CER 50, Section 50.55a(g),
shall be maintained                      except wnere specific written in a cold shutdcm                        relief has been granted by KK candition until each                      pursuant ta 10 CZR 50, Sectian indication of a gross                    50.55a(g) (6) (i) de f ect,which could                                        ~
adversely affect the structural integrity af the reactor coolant pressure boundary, has been  investigated and f7 c,~
evaluated.                                                              Ear c'.$  ~ge.. sligo Ice 6e. wMK A ~p~.
z6 &j t(~
gpQc          Q Q    j$ Qo
          ~info            is p~
: 2. Additional inspections shall be performed an certain circumf erential pipe fields as Listed to provide additional protection against pipe i>hip, which could cicmage auxiliary and control systems.
Feedwater-  Gc  4- 9, KFH-13, CFN- ~ 2 ~ CP4 2( ~
RFH 3lg Vl t pQ ~
                                            'p6                            Xr~- 39      C ~ii-  '
Ri Pi4  3&)  fly  'Qg R J Nos,,
                                                                                                        ~
Amendment                      65
 
q 4..s LIMITINC CONDITIONS  FOR OPERATION      SURVEILLANCE REQUIREMENTS 3 b  RZMAR  S                      4~ 6 Main steam-GMS-6,    KMS-24 GMS-32, KMS-104 ~
GNS-15~ and GMS-24 RHR          DSRHR-6~  DSRHR-7 and DSRHR-4 Core Spray-DSCS-12,'SCS-11 DSCS-5,  and DSCS-4 Reactor Cleanup      -DSRWC-4, OSRM-3 DSRWC-6    and DSRWC-5 HPCX        -THPCI- 70 THPCX-70A THPCZ-7l, and THPCX-72 R~~>P E~ilCB Plant, Safety Analysis (BFNP FSAR  subsection 4 ~ 12) l97 Amendment, HQ. 65
 
PAGES DELETED 203-208 Amendment No. 65
 
Vy ENCLOSURE 2 CORRECT TECHNICAL  SPECIFICATIONS FOR INSERVICE INSPECTION REQUIREMENTS (TVA BFNP TS 89 AND TVA BFNP TS 169)
BROGANS FERRY NUCLEAR PLANT UNITS 1,  2, AND 3
 
ATTACHMENT TO .LICENSE AMENDMENT NO. 98 FACILITY OPERATING LICENSE NO. DPR-33 DOCKET NO. 50-259 Revise Appendix  A as  follows:
Remove the following pages and replace with      identically numbered pages.
182 183 184-209 210 211 212 213 214
: 2. The marginal  lines  on these  pages  denote the areas heing changed.
 
  .Llitl;TING CONDITIONS    FOR OP    TION        SURVEILLANCE REQUX      ENTS 3.6.F Recirculation    Pumn  Operation                  b. The indi ca tcd value of
                                                              . core flow rate varies from the value derived
: 1. The reactor shall not be                                  from loop flow opera te d w i th one                                  mcasuremcnts    by more recirculation loop out of                              than 10%.
serv icc f or more than 24 hours. Kith the reactor                          c. The    dif fusez to lower operating, if one                                      plenum  differential recirculation loop is out                              pressure reading on an of service, the plant shall                            individual jet pump be placed in a hot shutdown                            varies from the mean of conditi.on within 24 hours                            all jet pump unless the loop is sooner                              differential pressures returned to service.                                  by more than 10%.
: 2. Following one pump                            2. Whenever there is operation, the discharge                        "recirculation flow with          the valve of the low speed pump                      reactor in the Startup or may not be opcncd unless                        Run btode and one the speed of thc faster                        recirculation pump is pump is less than 50% of                        operating with the its rated speed.                                equalizer valve closed, the diffuser to lower plenum
: 3. Steady state operation with                        differential pressure shall both recirculation pumps                        be    checked  daily  and  the out of service for up to 12                    diffcrcntial pressure of          an hours is permitted. During                      individual jet pump in a such interval restart of                        loop shall not vary from thc recirculation pumps is                      the mean of all j e t pump permitted, provided the                        diffezential pressures in loop discharge temperature                      that loop by      more  than is within 754F of the                          10%.
saturation temperature reactor vessel water as of'he determined by dome                        4.6.F Recirculation    Pump 0  eration prcssure.    .The  total                        Recirculation  pump speeds shall be elapsed  time in natural                        checked and  logged at least once circulation      and one pump                    'per day.
operation    must be no                      2. No  additional surveillance greater than 24'hours.                          required.
: 3. Before starting either recirculation pump during steady state operation, check and  log the loop discharge temperature and dome saturation temperature.
182
 
SllRVKILLAHCE Rt:OJ      'ARE'HFNTS Lg aiXI'l gr." C!)g~nQikS.~OJ~'lAZU1U 3 ~ 6 G ."l lucT    ursI Inta r it                  4.6.C Structural Intc          rit
: 1. The structural integrity of the              l. Inservice inspection of            ASHE primary system shall be main-                    Code Class        1, Class 2, and tained at the level required by                  Class 3 components shall be the original acceptance standards                performed in accordance with throughout the life of the plant.                Section ZI of the ASME Boiler The reactor shall be maintained                  and Pressure Vessel Code and in a cold shutdown condition                    applicable Addenda          as required until      each indication of a defect          by 10    CFR    50, Section 50.55a(g),
has been investigated and                        except where specific written evaluated.                                      relief has been granted by NRC pursuant to 10 CFR 50, Section 50-55a (g) (6) (i)      ~
: 2. Additional inspactions shall ba"=
performed on certain circutafercn-tial pipe Molds as listed to pro-vide additional protection agafnat pipe. vhip, Mhich could damage auxiliary and control aya-tellus ~
Feedvater                GFM-9, KFV-13 CFV-12,  CFw-26, KFV-31,  CFW-29, KFV-39,  GFw-15, KFM-38,  and GEM-32 Ha  in  s t can        GMS-6, KMS-24, GMS-32, KMS-104 GMS-15, and GMS-24 RHR                      DSRIIR-4, DSRHR-7, DSRHR- 8P, Core Spray              DSCS-12, OSCS-11, DSCS-5, and OSCS-4 18 Amendment No. 98
 
LIMITING CONDITIONS FOR OPERATION            BURVFII.IANCE RKqHIRIZHNTS 3.6.O  Structural Inte  rit          4-6 t      Structural  Into 'ritv Rene tor Cleanup  -  DSRWC-4, DSRWCr3 DSRWC-6, DSRWC-5 HPCI        THYCI-152 THPCI-153B      ~~
                                                                                ~ f 0  g THPCI-153              'I.
THPCI-154        I
                                                                          ~  P, 3.. For Unit 1 an augmented inservice il surve lance p ro g ram shall be performed to monitor potential corrosive effects of chloride residue.
released during the March 2Z,        1975  fire.
The augmented  inservice surveillance program is specified as follows:
: a. 8rowns Ferry Mechanical Maintenance Instruction 53, dated September 22, 1975, paragraph 4 . defines the liquid penetrant examinations required during the irst, second, third and fourth refueling outages following the fire restoration.
: b. 8rowns Ferry Mechanical Maintenance Instruction 46, dated July 18, 1975, Appendix 8, defines the    liquid penetrant examinations required during the sixth refueling outage following the fire restoration.
184 Amendment t<o. 98
 
PAGES DELETED 209-214 Amendment No. 98
 
ATTACHMENT TO LICENSE AMENDMENT NO. 92 FACILITY OPERATING LICENSE NO. DPR-52 DOCKET NO. 50-260 Revise Appendix  A as  follows:
: 1. Remove the following pages and replace with      identically numbered pages.
182 183 184 209 210 211 212 213 214
: 2. The marginal  lines  on these  pages  denote the areas being changed.
 
C
  . LIltlTING CONDITIONS      FOR  OPTION            SURVEILLANCE REOU        -fENTS V/ "
3.6.F Recirculation        Pumo 0      eration                    b. Thc indicated value of
                                                                      .core flow rate varies from the value derived
: 1. The reactor shall not be                                        from loop flow opera ted with onc                                            measurements      by more roc ircula t ion loop out of                                  than 10%.
serv icc f or more than 24 hours. With the reactor                                  c. The    dif fuser to lower operating, if onc                                            plenum    differential recirculation loop is out                                    pressure reading on an of service, the plant shall                                  individual jet pump be placed in a hot shutdown                                  varies from the mean of condition within 24 hours                                    all jet pump unless the loop is sooner                                    differential pressures returned to service.                                          by mox e than 10%.
: 2. Following onc pump                                  2. Whenever there          is operation, the di scharge                              'recircula tion flow        wi th the valve of the low speed pump                              reactor in the Star tup or may not bc opened unless                                Run hfode and one the speed of the faster                                recirculation pump is pump is less than 50% of                                operating with the its rated speed.                                        equalizer valve closed, the
: 3. S teady    s ta te opera tion wi th diffuser to lower plenum both recirculation pumps differential pressure shall be checked daily and the out of service for up to 12                            differential prd'ssurc of an hours is permitted. During,                            individual jet pump in a such    interval restart of,                            loop shall not vary from the  recirculation pumps is                          the mean of all jet pump pcrmittcd, provided the                                differential pressures in loop discharge temperature                            that loop by more than is within 750F of the                                  10%.
saturation temperature reactor vessel water as of'he dc term  inc d by    dome                    4.6.F Recirculation      Pump  Operation pressure.        .Thc  total                      l. Recirculation      pump speeds shall be elapsed      time in natural                            checked and logged at least once circulation        and one pump                        'per day.
operation      must be no
: 2.      additional surveillance greater than 24'hours.                          .      No required.
: 3. Before startinp either recirculation pump during steady state operation, check and  log the loop discharge temperature and dome saturation temperature.
182
 
LIMITING CONDITIONS  FOR OPERATION              SURVEILLANCE REQUIREMENT 4.6.C Structural ante    rit
: 1. The  structural integrity 'of the      1. Inservice inspection of      ASME primary system shall be main-              Code Class 1, Class 2, and tained at the level required by            Class 3 components shall be the original acceptance standards          performed in accordance with throughout the life of the plant.          Section XI of the ASME Boiler The reactor shall be maintained            and Pressure Vessel Code and in a cold shutdown condition                applicable    Addenda as required until each indication of a defect          by 10 CFR 50, Section 50.55a(g),
has been  investigated  and              except where specific written evaluated.                                  relief has'been granted by NRC pursuant to 10 CFR 50, Section 50.55a(g) (6) (i) .
: 2. Additional inspections shall be performed on certain circumferen-tial pipe uelda as listed to pro-vide additional protection against earn pipe Mhip, vhich cou)d damage  auxiliary and control sys-tems.                              I Pcod'voter        GPv-9, KFV-13 GTV-12, GFM<<26, KFM-31, CPJ-29, K?M-39, GFw-15, KFW-38, and GR!-32 Mhin  It          CMS-6, KMS-2 4, GMS-32, KMS-104 CMS-15, and CMS-24 RHR                DSRlE-4, DSR}B-7, OSRHR-6 Core Spray      -  DSCS-12, DSCS-11, DSCS-5, and'DSCS-4 18 Amendment No. 92
 
LIMIT"NG CONDITIONS FOR dPERAT                      SURVEILLANCE RE        REMENTS
        ~ ~
3.6.G  Structural Inte rit                  4 ~ 6.C St."ucturzi ".nt -'rc."t
                              +/
ac'
                                  ~  I I  nnup      DSZriC-~,  DSR'.iC -.',
DSVriC-S,  inc  DSR,'riC-5 h
                          ~
I nI        > ~ H I/
HPCI  - THPCI-70
                              ~          I THPCI-70A THPCI-71, and THPCI- 72
                            < ~
I 184 Amendment No. 92
 
PAGES-DELETED 209-214 Amendment No. 92
 
ATTACHMENT TO LICENSE AMENDMENT NO. 65 FACILITY OPERATING LICENSE NO. DPR-68 DOCKET NO. 50-296 Revise Appendix  A as  follows:
: 1. Remove the following pages and replace with    identically numbered pages.
196 197.
209 210 2>l 212 213 214
: 2. The marginal  lines  on these pages denote the areas being changed.
 
>ZHITING CONDITIONS FOR OPERATION          SURVEILLANCE REQUIREHENTS
.P~R    R          H                  4~6    PR HARY SYSTEH      ND  Y G.  'tructural    Inte  rit                G    St uctural Znte    rit The  structural integrity of the primary system                  1. Inservice inspection of      ASME shall be maintained et                      Code Class 1, Class      2, and the level required by the                  Class 3 components      shall be original  acceptance                      performed in accordance with standards  throughout the                  Section XI of the ASHE Boiler life of the plant. The                      and Pressure Vessel Code and reactor shall be maintained                applicable Addenda      as  required in a cold shutdown                          by 10 CFR 50, Section 50.55a(g),
condition until each .                      except where specific written indication of 'a defect has                relief has been granted by NRC been investigated and evaluated.                                  pursuant to 10 CFR 50, Section 50.55a (g) (6) (i) .
20  Additional inspections shall be performed on certain circumferential pipe welds as listed to provide additional protection against pipe whip, which could damage auxiliary    and  control systems.
Feedwater- GFW-9,      KFW-13 ~
GFW  12r  GFW 26 ~
KFW 31~ GFW-29~
KFW 39m    GFW-15m 196                            KFW-38, and GFW-32
 
A
                                                                                                /~
0+ ~
f L HI T I NG CONDITIONS FOR OPERANT! ON     SUgygILLANCE gggUI RESENTS 3 b     RIOR   8                     4~ 6 Hain steam-GMS-6 ~ KHS-24,     ~
GHS 32~   KHS-104~           4 GMS-15, and GMS>>24:       'I.
                                                                      -OSRHR- 6, DSRHR-7 ~
and DSRHR-4 Core Spray-OSCS-12,'SCS-11, DSCS-5, and DSCS-4 Reactor Cleanup     DSRWC-4 ~ DSRbC-3 ~
DSRWC-6, and DSRNC-5 HPCI        THPCI-70 THPCI-70A THPCI-71, and THPCI-72 R~R ETC S Plant: Safety Analysis (BFHP PSAR subsection 4~ 12) l97 Amendment No. 65
 
PAGES DELETED 209-214 Amendment No. 65
 
o t}}

Latest revision as of 17:38, 3 February 2020

Forwards marked-up Tech Specs from 840430 Amends 98,92 & 65 to Licenses DPR-33,DPR-52 & DPR-68,respectively,re Inservice Insp Requirements,Correcting Errors
ML18026A961
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 05/04/1984
From: Mills L
TENNESSEE VALLEY AUTHORITY
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NUDOCS 8405080087
Download: ML18026A961 (52)
v • d • e


Text

REGULATOR NFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8005080087 DOC.DATE: 80/05/00 NOTARIZED: YES DOCKET 4 FACIL:50-259 Browns Ferry Nuclear Power Stat{oni Unit li Tennessee 05000259 50-260 Browns Ferry Nuclear Power Stations Unit 2r Tennessee BYNAME 05000260 50-296 Browns Ferr'y Nuclear Power Stations Unit 3i Tennessee 05000296 AUTH AUTHOR AFF I LI A T ION MILLSi L. th. Tennessee Valley Authority REC IP ~ NAME RECIPIENT AFFILIATION DENTONeH ~ RE Office of Nuclear Reactor Regul at ion~ Director

SUBJECT:

Forwards marked-up Tech Specs from 840430 Amends 98~92 L 65 to Licenses DPR"33iDPR-52 8 DPR-68 respectivelyire inservice insp requirementsicorrecting errors.

DISTRIBUTION CODE: A001S COPIES RECEIVED:LTR ENCL SIZE: Bl TITLE: OR Submittal: Gene'ral Distribution NOTES:NMSS/FCAF 1cy. 1cy NMSS/FCAF/PM, NHSS/FCAF/PM'5000259 NiviSS/FCAF 1cy ~ 1cy NMSS/FCAF/PM ~

NMSS/FCAF 1cy. 1cy 05000260 05000296 RECIPIENT COP IF S RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME. LTTR ENCL NRR ORB2 BC 01 7 7 INTERNAL: ELD/HDSP 0 NRR/DE/MTEB 1 1 NRR/DL DIR 1 NRR/DL/ORAB 1 0 NRR /METB 1 1 NRR/DS I/RAB 1 F IL 00 1 1 RGN2 1 1 EXTERNAL: ACRS 09 6 6 LPDR 03 1 1 NRC PDR 02 1 1 NSIC 05 1 1 NTIS 1 1 NOTES; TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 25

0 tl tt lI tl e ~ I e

ll r o tt ff II tt ll 1I IA II tt tt h

II

TENNESSEE YALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II May 4, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton:

In the Matter of the Docket Nos. 50-259 Tennessee Valley Authority 50<<260 50-296 By letter from R. J. Clark to H. G. Parris dated April 30, 1984, Amendment Nos. 98, 92, and 65 were issued to license Nos. DPR-33, DPR-52, and DPR-68 for the Browns Ferry Nuclear Plant units 1, 2, and 3. Those amendments revised the technical specifications to refer ence 10 CFR 50.55a(g) for inservice inspection requirements. A review of the issued technical specifications revealed that they contained a number of inadvertent error s. We, therefore, cannot implement those technical specifications issued by the subject amendments.

We have marked the technical specifications for each unit to indicate the errors found. Those marked pages are provided in enclosure 1. The corrected pages which are needed are provided- in enclosure 2.

This was discussed with R. J. Clark of your staff on May 4, 1984.

Very truly yours, TENNESSEE VALLEY AUTHORITY L. . Mill.s, Manager Nuclear Licensing

.Subscribe me II this ~~d sworn to day of efore 1984.

r Notary Public My Commission Expires Enclosures cc: See page 2 pg) I

'DR 8405080087, 840504 PDR ADOCK 05000259 P

An Equal Opportunity Employer

0 I"

a l /+l I

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Mr. Harold R. Denton cc (Enclosures):

U.S. Nuclear Regulatory Commission Region IE ATTN: James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 Mr. R. J. Clark Browns Ferry Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20810

ATTACHMENT TO LICENSE AMENDMENT NO. 98 FACILITY'PERATING LICENSE NO. DPR-33 DOCKET NO. 50-259 Revise Appendix A as follows:

1. Remove the following pages and replace with identically numbered pages.

182 183 184 209 210 211 212 213 214

2. The marginal lines on these p ges denote the areas being changed.

] IMITINC CONDITIONS FOR 0 TION SURVEI).LANCE'KQU?RENE?)TS ge.~Mok~c Pv~ Gp~~M l.l, C ~J(

3.6.l'cL- -F'a -vsccateh The ladle ~ ted valw af cree flav fate varies fra tlv value derived f mes leep f lov ureeurascata by sac'r.

thaa ]OX.

The di ( i>>see t ~ lover p li avn d) f ferencial praaiur ~ raid Lnt 0@I an LadtTilucl ] ~ L pveip e ariea free cha urau pf tial all $ ec p~ C'frran-preaaveaa by care thar 10Z.

Uhencver Chere ia recirculate 'eae flov vith che ccactpc in the Th'eactor shall not bc, Startup ar Run Node and cne -e-opera ed vith one recircu'oticn Circulat ion pvnp ia uperat:n l vs eh the eeueltarr vrlve air>>C, lo ip out of scrvf c. fur more Che dif fusser to lover please than 2h hours<<with the reactor differential penna>>re ahall operatitg, . lf'ne recirad.ation checbed (all-, and chr dtf(ere loop is oui. of.service, the tinl pceaaure of an Lndlvle'.uel plant shall be placed La a hot get pump in ~ lue p shall oat shuidcrm condition vitl n vary frer rhr ncaa of all 'et 24 hen~ s uiuess tne loop ia pump elf ereacial pceiaurea la sooner ret'.tm d to serricc. that lonp by mire chan lot.

F>11'.,qnlt one pucp ope. <<ion ~

F. Recirculation Pump eration the diacharfe valve of the lov speed ]n~ cay not be opened 1ecittulacsoa pmp apeeda ~ hs]l ua! ass the speed o. the faster be chac)eed and lagged at least pm's 1css than cOn of ita rated speed.

knee pcc day.

Str~dy stat." operation ~tted. provided the steady state operac ion, c)reck sop discharge temperature is and loR the loop discharpe

<ith)n 75 F of the saturation temperature and dome temperaturr of the reactor saturation temperacure.

vessel vater as determined by pressure. The. to(a 1 'oiw elapsed time in natural circula<<

lion and o ie pump o) erat)on must

h. no grcalrr than 24 nrs.
  • Section 3.6. F.l is amended to permit operation with one recirculation loop out of service from January 25, 19S3 to midnight (CST) January 31, 1983 in .

accordance with the conditions of ]R2 Section 3. 6."F. 4 Amendment No. g, g$

0 ef SllRVE ILLAHCE REOJ 'HF.NTS L,JMI. 1 J.": C!)NnnLQ kS

.':t rivet iir~l Intc~rl~t 4.6.C,Structural genre rit

1. The structural integrity of the 1. Inservice inspection of ASME primary system shall be main- Code Class 1, Class 2, and tained at the level required by Class 3 components shall be the original acceptance standards performed in accordance with throughout the life of the plant. Section ZI of the ASME Boiler The reactor shall be maintained and Pressure Vessel Code and in a cold shutdown condition applicable Addenda as required until each indication of a defect by 10 CFR 50, Section 50.55a(g),

has been investigated and except where specific written evalua'ted. relief has been granted by NRC pursuant to 10 CFR 50, Section 50.55 (g)(6)(i).

(~p 5Z-p~ [

2. Additional inspections shall ba performed on certain circuraferon-tial pipe voids as listed to pro-vide additional protection against pipe vhip, Mhich could damage auxiliary and control sys-tems ~

'cadwater CFM-9, KF w-13 CTV-12, CPM-26, KFV-31, CFM-29, KTM-39, GFw-15, KFM-38, and G FV-3 2 Hain scca% CMS-6, KHS-24, CHS-32, KMS-104 GMS-15, and CMS-24 DSiUlR-4 DSRP~- I DS~- SA Core Spray DSCS-12 DSCS-11, DSCS-5, and DSCS 4 18 Amendment No. 98

N

~ II I

I Vo 1 LINITINl. CONDITIONS FOR OPERATION SURVFIT.7ANCE R EQNIREMENTS 3.6.0 Structural Inte rit 4.6.C. Structural Intc ritv Reactor Cleanup - DSRWC-4, DSRWC-3 DSRWC-6, DSRWC-S HPCI THYCI-152 THPCI-153B" < ~"

THPCX-153 THPCI-154 y For Unit an augmented inservice 1

surveillance program shall be performed to moni tor potential corrosive effects of chloride residue-released during the March 22, 1975 fire.

The augmented inservice surveillance program is specified as follows:

a. Browns Ferry Mechanical Maintenance Instruction 53, dated September 22, 1975, paragraph 4, deFines the liquid penetrant examinations required during the first, second, third and fourth refueling outages following the fire restoration.
b. Srowns Ferry Mechanical Maintenance Instruction 46, dated July 18, 1975, Appendix 8, defines the liquid penetrant examinations required during the sixth refueling outage following the fire restoration.

184 Amendment No. 98

PAGES-DELETED 209-214 Amendment No. 98

ATTACHMENT TO LICENSE AMENDMENT NO. 92 FACILITY OPERATING LICENSE NO. DPR-52 DOCKET NO. 50-260 Revise Appendix A as follows:

1. Remove the following pages and replace with identically nUmbered pages.

182 183 184 209 210 211 212 213 214

2. The marginal lines on these pages denote the areas being changed.

LI!!I . l.':0 CONDITIO".:5 FOR OPER .TTOM "

SURVEII.LhMCE RFOUIRRMENT 4 .6. E Jc t Pun<> rate varies

1. There" ctor shall not be from the value derived opera ted>> it,h one from loop flow recirc latioa )oop out of measurements by nore serv ice f or nore than 24 th an 10%.

hours. Vi th the reactor opcsa t ing, if oae c. The di f fus er to lower reci reals t ion loop is out plenum dif f ere at i al of se v ice, the plant shal 1 pressure r eading on au be placed in a hot shutdo<<n iad ividua jet punp 1

condition <<ithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> verses fro n the mean of unless the loop is sooner all get pu np returned to service. differenti al pressures by nore th an 10%.

2.'oll o<<ing one panp operation the discharge 2 ~ Whenever there is valve of thc - o<<speed pump1 recirculation flo>> <<ith the nay not b e opeacd unless reactor in the Startup or the speed of the faster Run Hode and one pump is 1 ess than 50% of recirculati on pump is its rated speed. opera ting <<i th the equalizer valve closed, the

3. S t state opesa t ion <<i th diffuses to lo<<es plenum re ci seal at ion pumps d iffeseatial pressure shall eady'oth out of service for up to 12 bc checked daily and the hours i s permitted. During differential pressure of an such in terval restart of individual jet pump in a the rec i rcu 1 a t i on pumps 1 s loop shall not vary iron pernitt ed, provided the the mean .of all jot pump loop di schar" e tcmpesatuse differential pressures in i s <<ith in 754F of the that 1oop by morc than saturat ion tcnpcsa tuse of 1 0%.

t e sea ctor vessel <<ates as I de terni ned by done Recirculation Puno Onera-ion pse s sar e. The total elapsed tine in natural 1. Recirculation pump speeds c i rcula tion and onc pump sha)1 bo checked and logged operati on must be no at least once per day.

gsea ter thaa 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2. No additional surveillance required.
3. Before starting either recirculation pump during steady state operation, check and log the loop discharge temperature and dome saturation temperature.

ld2 amendment lio. gg, gg, 85, 92

SURVEILLANCE REOJ F NTS 1 lMa'!-1%i; C<)N~nn,kS

.':t r!!ct >>r<<l 1ntr~r t~t 4.6.C Structural Inte rit

1. The structural int'egrity of the l. Inservice inspection of ASME primary system shall be main- Code Class 1, Class 2, and tained at the level required by Class 3 components shall be the original acceptance standards performed in accordance with throughout the life of the plant. Section XI of the ASME Boiler The reactor shall be maintained and Pressure Vessel Code and in a cold shutdown condition applicable Addenda's required until each indication of a defect by 10 CFR 50, Section 50.55a(g),

has been investigated and except where specific written evaluated. relief has been granted by NRC pursuant to 10 CFR 50, Section 50.55a (g) (6) (i) .

2. Additional inspoctions shall be perfor!ded on certain circu!!!Eeron-tial pipe ualda as listed to pro-vide additional protection against pipe Mhip, Mhich could da!!!age auxiliary and control ays-te!!!s.

Pcod&dter GPV-9, KFW-13 GTV-12, CPM-26, KFM-31, CPW<<29, K?M-39 CPw-15 KFM-3S, and CFM-32 Main stcam CMS-6, KMS-24, CMS-32, KMS-104 CMS-15, and CMS-24 RHR DSRIE-w DSR1!R os~-6 Core Spray DSCS-12. OSCS-11, DSCS-S, and DSCS-4

)8 Amendment No. 92

I LZMZTZ'NG CONDITIONS FOR dPERATZ SURVEILLANCE RE UIREMENTS 3.6.G Structural Znte rit 4.6,C S.=ucrurx

'7 aaggr g

'~l.~anus'S.i'riC-4, +~5;U%4 r ~

DS3;.'C-S, one DSYs~C-5 HPCZ - THPCZ-70 THPCZ-70A THPCZ-71, and THPCZ- 72

'I ~

184 Amendment No. 92

l PAGES .

DELETED 209-214 Amendment No. 92

i. +.o Y

ATTACHMENT TO LICENSE AMENDMENT NO. 65 FACILITY OPERATING LICENSE NO. DPR-68 DOCKET NO. 50-296 Revise Appendix A as follows:

1. Remove the following pages and replace with identically numbered pages.

t 196

~19/

za9 Z.to g.g p 2.f3 p/+,

2. The marginal lines on these pages denote the areas being changed.

LIH l T I NC CONG ITIOUS FOR OPERATION SURVEILLANCE REQU I REHENTS

3. 6 1'.2l err 9 "T 4 6 P 9 Y S STPM UHOARY Co Structura Intearit G. Structural Tntearit The structural l. Enservice inspection of ASP""

integrity of the Cade Class primary system shall 1, Class 2, and be maintained at the Class 3 components shall be per<<

level required by the formed in accordance with ariqinaL acceptance Section XI of the ASME Boiler standards throughout. and Pressure Vessel Code and the life af the applicable Addenda as required plant The reactor by 10 CER 50, Section 50.55a(g),

shall be maintained except wnere specific written in a cold shutdcm relief has been granted by KK candition until each pursuant ta 10 CZR 50, Sectian indication of a gross 50.55a(g) (6) (i) de f ect,which could ~

adversely affect the structural integrity af the reactor coolant pressure boundary, has been investigated and f7 c,~

evaluated. Ear c'.$ ~ge.. sligo Ice 6e. wMK A ~p~.

z6 &j t(~

gpQc Q Q j$ Qo

~info is p~

2. Additional inspections shall be performed an certain circumf erential pipe fields as Listed to provide additional protection against pipe i>hip, which could cicmage auxiliary and control systems.

Feedwater- Gc 4- 9, KFH-13, CFN- ~ 2 ~ CP4 2( ~

RFH 3lg Vl t pQ ~

'p6 Xr~- 39 C ~ii- '

Ri Pi4 3&) fly 'Qg R J Nos,,

~

Amendment 65

q 4..s LIMITINC CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3 b RZMAR S 4~ 6 Main steam-GMS-6, KMS-24 GMS-32, KMS-104 ~

GNS-15~ and GMS-24 RHR DSRHR-6~ DSRHR-7 and DSRHR-4 Core Spray-DSCS-12,'SCS-11 DSCS-5, and DSCS-4 Reactor Cleanup -DSRWC-4, OSRM-3 DSRWC-6 and DSRWC-5 HPCX -THPCI- 70 THPCX-70A THPCZ-7l, and THPCX-72 R~~>P E~ilCB Plant, Safety Analysis (BFNP FSAR subsection 4 ~ 12) l97 Amendment, HQ. 65

PAGES DELETED 203-208 Amendment No. 65

Vy ENCLOSURE 2 CORRECT TECHNICAL SPECIFICATIONS FOR INSERVICE INSPECTION REQUIREMENTS (TVA BFNP TS 89 AND TVA BFNP TS 169)

BROGANS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3

ATTACHMENT TO .LICENSE AMENDMENT NO. 98 FACILITY OPERATING LICENSE NO. DPR-33 DOCKET NO. 50-259 Revise Appendix A as follows:

Remove the following pages and replace with identically numbered pages.

182 183 184-209 210 211 212 213 214

2. The marginal lines on these pages denote the areas heing changed.

.Llitl;TING CONDITIONS FOR OP TION SURVEILLANCE REQUX ENTS 3.6.F Recirculation Pumn Operation b. The indi ca tcd value of

. core flow rate varies from the value derived

1. The reactor shall not be from loop flow opera te d w i th one mcasuremcnts by more recirculation loop out of than 10%.

serv icc f or more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Kith the reactor c. The dif fusez to lower operating, if one plenum differential recirculation loop is out pressure reading on an of service, the plant shall individual jet pump be placed in a hot shutdown varies from the mean of conditi.on within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> all jet pump unless the loop is sooner differential pressures returned to service. by more than 10%.

2. Following one pump 2. Whenever there is operation, the discharge "recirculation flow with the valve of the low speed pump reactor in the Startup or may not be opcncd unless Run btode and one the speed of thc faster recirculation pump is pump is less than 50% of operating with the its rated speed. equalizer valve closed, the diffuser to lower plenum
3. Steady state operation with differential pressure shall both recirculation pumps be checked daily and the out of service for up to 12 diffcrcntial pressure of an hours is permitted. During individual jet pump in a such interval restart of loop shall not vary from thc recirculation pumps is the mean of all j e t pump permitted, provided the diffezential pressures in loop discharge temperature that loop by more than is within 754F of the 10%.

saturation temperature reactor vessel water as of'he determined by dome 4.6.F Recirculation Pump 0 eration prcssure. .The total Recirculation pump speeds shall be elapsed time in natural checked and logged at least once circulation and one pump 'per day.

operation must be no 2. No additional surveillance greater than 24'hours. required.

3. Before starting either recirculation pump during steady state operation, check and log the loop discharge temperature and dome saturation temperature.

182

SllRVKILLAHCE Rt:OJ 'ARE'HFNTS Lg aiXI'l gr." C!)g~nQikS.~OJ~'lAZU1U 3 ~ 6 G ."l lucT ursI Inta r it 4.6.C Structural Intc rit

1. The structural integrity of the l. Inservice inspection of ASHE primary system shall be main- Code Class 1, Class 2, and tained at the level required by Class 3 components shall be the original acceptance standards performed in accordance with throughout the life of the plant. Section ZI of the ASME Boiler The reactor shall be maintained and Pressure Vessel Code and in a cold shutdown condition applicable Addenda as required until each indication of a defect by 10 CFR 50, Section 50.55a(g),

has been investigated and except where specific written evaluated. relief has been granted by NRC pursuant to 10 CFR 50, Section 50-55a (g) (6) (i) ~

2. Additional inspactions shall ba"=

performed on certain circutafercn-tial pipe Molds as listed to pro-vide additional protection agafnat pipe. vhip, Mhich could damage auxiliary and control aya-tellus ~

Feedvater GFM-9, KFV-13 CFV-12, CFw-26, KFV-31, CFW-29, KFV-39, GFw-15, KFM-38, and GEM-32 Ha in s t can GMS-6, KMS-24, GMS-32, KMS-104 GMS-15, and GMS-24 RHR DSRIIR-4, DSRHR-7, DSRHR- 8P, Core Spray DSCS-12, OSCS-11, DSCS-5, and OSCS-4 18 Amendment No. 98

LIMITING CONDITIONS FOR OPERATION BURVFII.IANCE RKqHIRIZHNTS 3.6.O Structural Inte rit 4-6 t Structural Into 'ritv Rene tor Cleanup - DSRWC-4, DSRWCr3 DSRWC-6, DSRWC-5 HPCI THYCI-152 THPCI-153B ~~

~ f 0 g THPCI-153 'I.

THPCI-154 I

~ P, 3.. For Unit 1 an augmented inservice il surve lance p ro g ram shall be performed to monitor potential corrosive effects of chloride residue.

released during the March 2Z, 1975 fire.

The augmented inservice surveillance program is specified as follows:

a. 8rowns Ferry Mechanical Maintenance Instruction 53, dated September 22, 1975, paragraph 4 . defines the liquid penetrant examinations required during the irst, second, third and fourth refueling outages following the fire restoration.
b. 8rowns Ferry Mechanical Maintenance Instruction 46, dated July 18, 1975, Appendix 8, defines the liquid penetrant examinations required during the sixth refueling outage following the fire restoration.

184 Amendment t<o. 98

PAGES DELETED 209-214 Amendment No. 98

ATTACHMENT TO LICENSE AMENDMENT NO. 92 FACILITY OPERATING LICENSE NO. DPR-52 DOCKET NO. 50-260 Revise Appendix A as follows:

1. Remove the following pages and replace with identically numbered pages.

182 183 184 209 210 211 212 213 214

2. The marginal lines on these pages denote the areas being changed.

C

. LIltlTING CONDITIONS FOR OPTION SURVEILLANCE REOU -fENTS V/ "

3.6.F Recirculation Pumo 0 eration b. Thc indicated value of

.core flow rate varies from the value derived

1. The reactor shall not be from loop flow opera ted with onc measurements by more roc ircula t ion loop out of than 10%.

serv icc f or more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With the reactor c. The dif fuser to lower operating, if onc plenum differential recirculation loop is out pressure reading on an of service, the plant shall individual jet pump be placed in a hot shutdown varies from the mean of condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> all jet pump unless the loop is sooner differential pressures returned to service. by mox e than 10%.

2. Following onc pump 2. Whenever there is operation, the di scharge 'recircula tion flow wi th the valve of the low speed pump reactor in the Star tup or may not bc opened unless Run hfode and one the speed of the faster recirculation pump is pump is less than 50% of operating with the its rated speed. equalizer valve closed, the
3. S teady s ta te opera tion wi th diffuser to lower plenum both recirculation pumps differential pressure shall be checked daily and the out of service for up to 12 differential prd'ssurc of an hours is permitted. During, individual jet pump in a such interval restart of, loop shall not vary from the recirculation pumps is the mean of all jet pump pcrmittcd, provided the differential pressures in loop discharge temperature that loop by more than is within 750F of the 10%.

saturation temperature reactor vessel water as of'he dc term inc d by dome 4.6.F Recirculation Pump Operation pressure. .Thc total l. Recirculation pump speeds shall be elapsed time in natural checked and logged at least once circulation and one pump 'per day.

operation must be no

2. additional surveillance greater than 24'hours. . No required.
3. Before startinp either recirculation pump during steady state operation, check and log the loop discharge temperature and dome saturation temperature.

182

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 4.6.C Structural ante rit

1. The structural integrity 'of the 1. Inservice inspection of ASME primary system shall be main- Code Class 1, Class 2, and tained at the level required by Class 3 components shall be the original acceptance standards performed in accordance with throughout the life of the plant. Section XI of the ASME Boiler The reactor shall be maintained and Pressure Vessel Code and in a cold shutdown condition applicable Addenda as required until each indication of a defect by 10 CFR 50, Section 50.55a(g),

has been investigated and except where specific written evaluated. relief has'been granted by NRC pursuant to 10 CFR 50, Section 50.55a(g) (6) (i) .

2. Additional inspections shall be performed on certain circumferen-tial pipe uelda as listed to pro-vide additional protection against earn pipe Mhip, vhich cou)d damage auxiliary and control sys-tems. I Pcod'voter GPv-9, KFV-13 GTV-12, GFM<<26, KFM-31, CPJ-29, K?M-39, GFw-15, KFW-38, and GR!-32 Mhin It CMS-6, KMS-2 4, GMS-32, KMS-104 CMS-15, and CMS-24 RHR DSRlE-4, DSR}B-7, OSRHR-6 Core Spray - DSCS-12, DSCS-11, DSCS-5, and'DSCS-4 18 Amendment No. 92

LIMIT"NG CONDITIONS FOR dPERAT SURVEILLANCE RE REMENTS

~ ~

3.6.G Structural Inte rit 4 ~ 6.C St."ucturzi ".nt -'rc."t

+/

ac'

~ I I nnup DSZriC-~, DSR'.iC -.',

DSVriC-S, inc DSR,'riC-5 h

~

I nI > ~ H I/

HPCI - THPCI-70

~ I THPCI-70A THPCI-71, and THPCI- 72

< ~

I 184 Amendment No. 92

PAGES-DELETED 209-214 Amendment No. 92

ATTACHMENT TO LICENSE AMENDMENT NO. 65 FACILITY OPERATING LICENSE NO. DPR-68 DOCKET NO. 50-296 Revise Appendix A as follows:

1. Remove the following pages and replace with identically numbered pages.

196 197.

209 210 2>l 212 213 214

2. The marginal lines on these pages denote the areas being changed.

>ZHITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREHENTS

.P~R R H 4~6 PR HARY SYSTEH ND Y G. 'tructural Inte rit G St uctural Znte rit The structural integrity of the primary system 1. Inservice inspection of ASME shall be maintained et Code Class 1, Class 2, and the level required by the Class 3 components shall be original acceptance performed in accordance with standards throughout the Section XI of the ASHE Boiler life of the plant. The and Pressure Vessel Code and reactor shall be maintained applicable Addenda as required in a cold shutdown by 10 CFR 50, Section 50.55a(g),

condition until each . except where specific written indication of 'a defect has relief has been granted by NRC been investigated and evaluated. pursuant to 10 CFR 50, Section 50.55a (g) (6) (i) .

20 Additional inspections shall be performed on certain circumferential pipe welds as listed to provide additional protection against pipe whip, which could damage auxiliary and control systems.

Feedwater- GFW-9, KFW-13 ~

GFW 12r GFW 26 ~

KFW 31~ GFW-29~

KFW 39m GFW-15m 196 KFW-38, and GFW-32

A

/~

0+ ~

f L HI T I NG CONDITIONS FOR OPERANT! ON SUgygILLANCE gggUI RESENTS 3 b RIOR 8 4~ 6 Hain steam-GMS-6 ~ KHS-24, ~

GHS 32~ KHS-104~ 4 GMS-15, and GMS>>24: 'I.

-OSRHR- 6, DSRHR-7 ~

and DSRHR-4 Core Spray-OSCS-12,'SCS-11, DSCS-5, and DSCS-4 Reactor Cleanup DSRWC-4 ~ DSRbC-3 ~

DSRWC-6, and DSRNC-5 HPCI THPCI-70 THPCI-70A THPCI-71, and THPCI-72 R~R ETC S Plant: Safety Analysis (BFHP PSAR subsection 4~ 12) l97 Amendment No. 65

PAGES DELETED 209-214 Amendment No. 65

o t

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