ML18026A961

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
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)

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

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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

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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

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~ 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

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'~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

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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~.

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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

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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