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 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 ILIA T ION MILLSi 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

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, 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.

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

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II

TENNESSEE YALLEYAUTHORITY 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 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.

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

<.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

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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 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 flov ureeurascata by sac'r.

thaa

]OX.

The di ( i>>see t ~ lover pliavn d) fferencial 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 diffusser 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 ~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 ion 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, KFw-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.

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<<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.

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

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

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

amendment lio. gg, gg, 85, 92 ld2

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

.':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.

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

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.

LIHlTINC CONG ITIOUS FOR OPERATION SURVEILLANCE REQU IREHENTS

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.

the life af the plant The reactor shall be maintained in a cold shutdcm candition until each indication of a gross defect,which could adversely affect the structural integrity af the reactor coolant pressure

boundary, has been investigated and evaluated.

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) ~

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2.

Additional inspections shall be performed an certain circumferential 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~-

RiPi4 9,

KFH-13,

~ 2 ~

CP4 2(

~

3lg Vl t pQ ~

39 C ~ii- '

3&)

fly

'Qg R J ~

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 1.

The reactor shall not be opera te d w ith one recirculation loop out of serv icc for 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 operating, if one recirculation loop is out of service, the plant shall be placed in a hot shutdown conditi.on within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is permitted.

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 diffusez 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.

182

Lg aiXI'lgr." 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.

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 illance 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.

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 1.

The reactor shall not be opera ted with onc roc ircula t ion loop out of serv icc for 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 operating, if onc recirculation loop is out of service, the plant shall be placed in a hot shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 unless the 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is permitted.

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 diffuser 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.

182

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.

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 It earn CMS-6, KMS-24, 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.

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 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.

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

A

/ ~

0+ ~

f LHITING CONDITIONS FOR OPERANT!ON SUgygILLANCE gggUI RESENTS 3

b RIOR 8

4 ~ 6 Hain steam-GMS-6

~

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

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