ML18029A221

Corrected Amends 98,92 & 65 to Licenses DPR-33,DPR-52 & DPR-68,respectively,correcting Editorial Errors

ML18029A221
Person / Time
Site:	Browns Ferry
Issue date:	10/11/1984
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML18029A222	List: ML18029A221
References
DPR-33-A-098, DPR-52-A-092, DPR-68-A-065 NUDOCS 8411010300
Download: ML18029A221 (18)

Text

CORRECTION TO LICENSE AMENDMENT NO.

98 FACILITY OPERATING LICENSE NO.

DPR-33 DOCKET NO. 50-259 Revise Appendix A as follows:

1.

Remove the following pages and replace with identically numbered pages.

~Pa e

Vll 182 183 Correction Page number for "3.6.G" corrected.

Table 4.6.A deleted.

Title of "3.6.F" changed.

Expired footnote deleted.

Hargin bar corrected.

"4.6.G.6" changed to "4.6.G.3."

8411010300 841011 PDR ADOCK 05000259 P

PDR

)

tt I'I'

C.

Coolan Leakage 0.

Relic= Valves Jet pumps 180 181 181

."-.. Re ir"ul.ation "."u~ One-.ation 182 3.7/4.7 G.

Structural integrity H.

Seismic Restraints,

Supports, ance Saubbers Containment Sys-ems

'A.

Primary Containment B.

Standby Gas Treatment Syst m

18S 227 7

C.

Secondary Containment 0.

Primary Containment isolat>on Valv s

Control Room Emeroency Vent'1 at>on F.

Primary Containment Purge System 240 2c,a 246 G.

Containment 'Atmospnere Dilute>on System (C 0) '.

248 H.

Containmen Atmospd re Hon.'coring (CN) System aaa3.yzer 3.8/4.8 Radioactive Haterial s 249 28 I A.

Liquid Effluent 8,

Ai.borne Efflucnts 281 282 C.

Hechanica 1

Vacuum

?ump 0.

Hisccllaneous Radcoac:ive Ha ter ials Sourc s

286 285 3.9/4.9 Aux: 1iary Ele trical Sys=em A,

Aux i 1 iary Electrical

=oui omen:

8.

Oocratson wi th lronerable Enu>oment C.

0"oration in Cola Shutdown 242 A%2 295 298 3

~ 10/4.10 Core Altcrations 3C2 A.

Rc. uc1 irg,'nterl oc}.s Amendment No. 92, 98

LIST OF TAB%M Cont'd Table Title eeee Ne.

4.Z.c

~nun-Test and Calibration Frequency far Surveillance Ins~ntatian......

~..

~

105 4.2.G Surveillance Requirements for Cant=al Room Isolation Ins &mactation

~

~

~

~

~

~ l

~

~

~

~

~

106 4.2.H Hinitsua Test and Calibration Prequency for F1ood %tee ian Instrumentation

~

~

~

~

~

~

~

~

~

107 4-2.J

3. 5-1 S eisa.c K)nitoring Instrument Surveillance Mnitnxm RHRSW and EECW Pump Assignment

~

~

~ e

~

108 152a 3.5. I MAPIRsR Versus Average Planar Exposure ~......

171, 172, 172a vM

't*

tC 3.7.A 3.7,E 3-7. C 3-7'-D 3-7.E:

3.7.Z Contakz55ent Isolation Valves

~

~

~

~

~

~

~

~

Testable Penetratians crf.th Douhle 0-Ring Seals Testable Penetratgans cath TestabLe Mlcws, Air Tested Isolatian Valves

~

~

e

~

~, ~

~

~

~

e Primary Containment Isa?aatqgz. Valves which Terminate beLacr the Suppression Paal Water

Level,

~

~

~

~

~

~

~

e 'e e "r

~

~

~

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T

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P~zy Containment Isolation VaLves Located

~m Water Sealed Seismic CLass 1 Lees 262 3-7.H Tes tab 1e Elec&caL PeneMeiaus

~

~

~

~

~

~

~

~

265 4.8.A Radioactive Liquid Waste Samp~g and Analysis 287 4.8.3 Radiaacrive Gaseous Waste Sampling and Analysis 288 4.9.A.4.C Voltage Relay Setpaints/Diesel Generator Star" 298a 3.LL.A Fire Protection System Hydraulic Requirements 324 6.8eA Mini".rta QxLt Cree Requirements 360

//I

'I

'mendment No.,98

LI:llTING CO?,'DITIO JS FOR OPE".ATION SURUEILLAKCE REQUIRE??E'.?TS 4.6.E 'et Pumas 3.6.F Recirculation Pumo Ooeration Foll owing one pump ope ation, the di schazge va lve o f the 1 ow speed pum.p may not be opened unless the speed of the fastex pump is less than 50% of its ra ted speed.

3.

S tea dy s

both rec out of s

hours is such int the reci permitte loop dis is withi sa turati the zeac dc term in pressure elapsed circ'ulat operatio gx'eater ta te opera t ion wi th i rcul ation pumps ervi ce for up to 12 permi t ted.

During I

erval res tart of rcul at ion pumps i s d, provided the charge tempexature n 75 F of'he on temperature of'oz vessel water as ed by dome The total time in natural ion and one pump n must be no than 24 houxs.

1.

The reactor shall not be

. opcxated with one recirculation loop out of service 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 sezvice, 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.

b.

The indicated value of core flow rate varies from the value derived from 1oop f 1 ow measurements by more than 10%.

c.

The diffusez to 1ower plenum differential pressure reading on an individual jet pump varies from the mean of all jet pump differential pressures by'ore than 10'%.

2.

Whenever there is rec ix cula tion flow wi th t he reactor in the Stax tup or Run

?fode and one recirculation pump is operating with the equalizex valve closed, the diffuse

,to lowex'lenum differential pressure shall be checked daily and the differentia.l pressure 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 1 0'5.

4.6.F Recirculation Pumn Operation 1.

Recirculation pump speeds shall be checked and logged at least once per day.

. 2.

Ho additional surveillance reauired.

3.

Before starting either recirculation pump durinn steady stare operation, checi and log the loop discharge temperature and dome saturation temperature.

Amendment No.

g, S$

182

SLJRVKILLANCK REOJ1Rt2'.FhTS 3

6 Q

' t v'lie't 4lrNI tnte 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.

4.6.C Structural lnteerit Enservice inspection of ASME Code Class 1, Class 2,

and Class 3 components shall be performed in accordance with Section ZZ 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 HRC pursuant to 10 CFR 50, Section 50.55a (g) (6) (i);

2 ~

Additional inspections shall be performed on certain circumferent-iall pipe Maids ss listed to pro-vide additional protection against pipe vhip, Mhich could damage suxilisry and control sys-tefls ~

Fcadvater CFV 9, KFw-13 C?V-12, CW-26, XFM 31, CFW-29, KFM 39 ~ CP4-15, L% 38, and Crw 32 Nein stean CMSW, NM-24, CMS-32, KHS-104 CMS<<15, and CMS-24 RHR OSRlB-4, OSR~B;,

OSRHR-8A Core Sprsy OSCS-12, 5SCS-l, ~,

DSCS-5, and DSCS-'mendment Ho.

98

LIHITZNCi CONDITIONS FOR OPERhTION t

3.6 O

Seruccurnl Xnce ri.t SVRVZnWNCr; R>qp TRr~RNYS 4

6 O Structural Tncc 'rt tv Rene tor Cleanup -

DSRMC-4 ~

DSRMC-3 DSRMC-6, DSRVC-S THPCZ-152 THPCE-1538 THPCZ-1 5 3 THPCI-1,54 3.

For Unit 1 an augmented inservice surveillance program shall be performed to moaitor potential corrosive effects of chloride residue released dur ing the March 22, 1975 <ice.

The augmented inservice surveillance program is specified as fol1ows:

a.

Srowas Ferry Mechanical Maintenance Instruction 53, dat d Seotember 22, 1975, paragraph 4. defines the liquid penetrant examinations required during the first,

second, third and Fourth refuel ing outages fo\\ 1 owing 'he fire res tora tfoa.

b-Srowns Ferry Mechanical Maintenance Instruction 46, dated July 1S 197'ppendix S, defines the. liquid peaetraat examinations requir d during the sixth refueling outage following the fire restoration.

184 Amendment t/o.

98

I CORRECTION TO LICENSE AMENDMENT NO.

92 FACILITY OPERATING LICENSE NO.

DPR-52 DOCKET NO. 50-260 Pevise Appendix A as follows:

1.

Remove the following pages and replace with identically numbered pages.

~Pa e

ill vii 183 Correction Page number for "3.6.G" corrected.

Table 4.6.A deleted.

Restores Amendment No.

92 changes erroneously omitted during issuance of Amendment No. 96.

Se" ion 3.7/4.7 C.

Coolant Leakag 0

~e ie< V~ves-E 1~ J.

~

Vel PL& Hps

~

~

~

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F.

":.ecirculat on Pt=n Ooeration" G.

Structural Integrity H-Seisad.c Restraints,

Supports, and Snubbers Containment Systems 18l 182

>as 185 227 A.

Primary Containment 227 B.

Standby Gas Treatment System 236 C.

Secondary Gontainment 240 D.

Primary Containment Isolation Valves 242 E.

Control Room Emergency Ventilation 244 1

3.8/4.8 F.

Primary Containment Purge System G.

Containment Atmosphere Dilution System (CAD)

H.

Containm nt Atmosphere Monitoring (CAM) System HZ2 Analyzer Radioactive Materials A. l,iquid Effluents B.

Airborne Effluents C.

M chanical Vacuum Pump 246 248 249 281 281 282 286 0.

Miscellaneous Padioactive Y~terials Sources 286 3.9/4.9 Auxiliary Electrical System A.

Auxiliary Electrical Equipment 292 292 B.

Operation with Inoperable Equipment 295 C.

Operation in Cold Shutdown...........

298 3.10/4.10 Core Alterations A.

Refueling Interlocks 302 302

,--,end-..e.;t llo. 85, 92 I

LIST OF TABXMv Cant'd Table 4.2.F T~ chic KLnfcnun Test and Calibratmn Frequency zar SurveQIance Ins~+ntatian

~

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Par~ Ãa.

105 4.2.G Surveillance Requirements Zor Cant aL Raam Isolation Ins cct1Rentacian

~

0

~

0

~

~

~

~

~

~

~

~

106 4.2.E Hinfcaua Test and Calibration Frequency for Flood Protection ITLstrumencation

~

~

~

~

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~

~

~

~

107 4.2.J

'eismic ~icaring, Instrument Surveillance 108

3. 5-1 3.5. Z

, Mnimum, EHRSW and.'ECW Pump Assi8nment

'NAPLBGR Versus Average Planar Zxposure.......

171, 172, 3.7.A..

Primary Containment Isolation Valves........

250 3.7.B 3-7.C.

3.7;D T.E 30 71F Tescable Penetra~

with Double 0-Riag Seals Tescabla Penecra~~ns'ith Testable Bellows.

Air Tested Isolation Valves

~

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Primary Can~~ant Isolation. Valves which Temrbxate below che Suppression Pool Water Le aL. '.

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e P~ry Conca~nt Isolation Valves Lacaced ~

Water Sea1ed Seismic Class 1 ~es 263

3. 7.H 4.8.A 4.8.B Testab le Fslec~~cal Pene~Mns

~

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Radioactive Liquid Waste Sampling and Analysis Radioactive Gaseous Waste Samp~g and Analysis 265 287 288.

4.9.A.4.C VoLcage Relay Setpamcs/Diesel Generacar Scarc

298a, 3.LL.A 6.8.A F~me PracecMn System Hydraulic Requirements

".finimum Shift Crew Requirements 324 360

,~~ Anendment No. g5, 92

LIMZTING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT r

.'.I ruct

~ir~J Lntemrf tv 4.&.C Structural lntecrftv 1.

The structural integrity of the primary system shall be main-tained at the level required by the original acceptance standazds thzaugnout tne lize of the plant.

The reactor shall be maintained in a cold shutnown condition until each indication oz a defec has been investigated and evaluated.

l.

Inservice inspection oz ASH Code Class 1, Class 2,

and Class 3 components shall be perzozmed in accordance with Section Zl oz the ASi~'ailer and Pressure Vessel Code and applicable Addenda as zeauired by 10 ~c 50, Section 50.55a(g),

ezcept wnere specizic written reliez has been granred by NRC pursuant to 10 CFR 50, Section 50.55a(g) (6) (i).

2.

. Addftfonal fnspoc fons shall ba parforaed on certain cfrcuokeron-tfal pfpe ~olds as lfsred ta pro-vfdc addftfanal protcc fon against pipe vhfp, Which could damage auxiliary and control ays-tt:Qs.i 7cad~o.t er C74-9, K7<-13 CTM-12 e CP '-26 e

K~-31, CP~-29,

~-39, C7w-l5, XZ'4-38, and Cr~-32 Hafn stcao CH5-&, QS-2 4, MS-32, KHS-104 CHS-15, and CMS-24 DS RILE 4 DS +3 DSH. q-6 I8 Core 5 pray TCS&07 TCS-423 TSCS-408 TSCS-424

'mendment No.

, g6

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

1.

Remove the following pages and replace with identically numbered pages.

~Pa e

vii 196 197 209 - 214 Correction Table 4.6.A deleted.

Editorial changes to "3.6.G.1" for consistency with Units 1 and 2

Margin bar added for "4.6.G.1."

Restores Amendment No.

65 changes erroneously omitted when Amendment No.

69 was issued.

Replaces 203 - 208 to correct error resulting from page renumbering.

2.

Restore the following pages which were incorrectly deleted by Amendment No. 65.

203 (Amendment No. 55) 204 (Amendment No. 55) 205 (Amendment No. 55) 206 (Amendment No. 55) 207 (Amendment No. 55) 208 (Amendment No. 55)

These pages (not enclosed) are available from your files.

4

4 ~ 2.E 4.2. F Minimum Test and Calibration Frequency for Drwcll Le.ak Detectian Instrumentation minimum Test and Calibration Frequenc for Surv Ins trumenca tion equency or Surveillance 101 102

4. 2.C 4.2.H 4.2.Z 3 ~ 5.-1 3.5.1 Surveillance Requir~~ents for Control Room Isolatfon Instrumentatton Hinimum Test and Caltbration Frequency far Fl Instrumentation

~

quency ar Flood Protection Seismi.c Honi.toring Instrument Survcillance Requtremcnt Hinimum RHRSM and KECK Pump Assignment HAPLHGR vs. Average Planar Exposure 103 104 105 156a

181, 182, 182ae

$8$$

3 7.h Primary Contatnmcnt Isolation Valves 262 3 7.B 3.7.C 3.>.D 3.7.E Tescable Penetrations vtth Double 0-Ring Sca)s Testable, Penetrations vtth Tescable Bellovs hir Tested Isolation Valves Primary Containment Isolation Valves vhtch ves v c

Terminate Bclov chc 268 270 279 3.J.F Primary Containment Isolation Valves Seismic Class 1 Lines Located in Mater Sealed 280

3. 7.0

3. 7.H 4.8.A 4.8.B 4i9A4 c 3 ~ 11.A b.B.A Deleted Testable Electrical Penetrations Radioactive Liquid Maste Sampling and Analysis Radioac ive Gaseous Maste Sampling and Analysis Volrage Relay Setpotnts/Diesel Cenerator Start Fire Proccction System Hydraulic Rcqutrcments Htntmum Shift Crev Requirements 283 310 311

'3" ba 355a 390 vit Amendment Nn. P.,~

.ZMZTZNG CONDITIONS tOR OPERATION SURVEILLANCE REQUZREY NTS

~PA R

PM 4 e 6 PRIMARY SYSTEM BO D

Y G.

S ructural Inre rit G

St ctural Znt rit l.

The structural integrity of the primary system shall be maintained 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 ARK Code Class 1, Class 2,

and Class 3 components shall be performed in ac'cordance with Section ZI of the ASP Boiler and Pressure Vessel Code and applicable Addenda as required by 10

~~

50, Section 50.55a(g),

except where specific written relief has oeen granted by NRC pursuant to 10 CPR 50, Sect'on 50.55a (g) (6) (i).

Additional inspections shall be performed on certain circumferent:ial pipe fields as listed to provide additional protection against pipe ship, which could damage au~iary and control systemsm Peedwater-GFW-9, KFM=l3,.

GFR 12m G& 26m

ÃFM 31m G~ 29 r KFM-39 ~

QFH 15 m KFM-38~ and G?M-32 Amendment Nos. P, p, d5

IMMIT INC CONDZTXOH8 FOR OPERATXOH 'QRVEXLLANCX RZQUZR~~S 3

b PR 5AR 4.6 Hain stern-QS-6

~ K%-24, 32 ~

KMS-104, GMS 15~

and GNS-24

-DSRHR-6, DSRHR-7, and DSRHR-4 Coz'8 SpraY 'TCS&07 TCS-423 TSCS-408 TSCS-424 Reac or C1 eanQp HPCX DSRMC 4r DSRM-3 ~

DSRMC-6 ~ and DS84C-5 THPCX-70 THPCX-7 OA THPCX-7l, and THPCX-72 PLant Safety Analys. s

{BFHP PSAR subsect'on 4i1

)

PAGES DELEiED 209-214 Amendment No.

65