Download pdf - October 11, 1984 Mr. Hugh G. Parris · 2012. 11. 18. · October 11, 1984 Docket Nos. 50-259/260/296 Mr. Hugh G. Parris Manager of Power Tennessee Valley Authority 500A Chestnut Street,

October 11, 1984

Docket Nos. 50-259/260/296

Mr. Hugh G. Parris Manager of Power Tennessee Valley Authority 500A Chestnut Street, Tower II Chattanooga, Tennessee 37401

Dear Mr. Parris:

On April 30, 1984, we issued Amendment Nos. 98, 92 and 65 to Facility Operating License Nos. DPR-33, DPR-52 and DPR-68 in response to your applications dated July 29, 1977, as supplemented April 29, 1979, July 20, 1979, and November 17, 1981.

As you noted in your letter dated May 4, 1984, those amendments contain editorial errors. Corrected copies of pages requiring correction are enclosed.

Sincerely,

Ri ard J. C ark, Project Manager Op rating Reactors Branch #2 Division of Licensing

Enclosures: As stated

cc w/enclosures: See next page

DISTRIBUTION Docket File NRC PDR Local PDR ORB#2 Reading DEisenhut OELD SNorris WLong RClark Gray File

DL •ORB#2 SNo isajs 10/10/84

DL:ORB#2( WLong 10/1s /14

JPartlow LJHarmon ELJordan JNGrace TBarnhart (12) Wdones DBrinkman ACRS (10) OPA, CMiles RDiggs Extra - 5

DL:ORB"4

RClar 10/j/ /84

PL:ORB#2 DVassallo 1o////84

8410121eIi PDR ADOCK 05000259

PDR

Mr. Hugh G. Parris Tennessee Valley Authority Browns Ferry Nuclear Plant, Units 1, 2 and 3

cc:

H. S. Sanger, Jr., Esquire General Counsel Tennessee Valley Authority 400 Commerce Avenue E 1IB 330 Knoxville, Tennessee 37902

Mr. Ron Rogers Tennessee Valley Authority 400 Chestnut Street, Tower II Chattanooga, Tennessee 37401

U. S. Environmental Protection Agency

Region IV Office Regional Radiation Representative 345 Courtland Street, N. W. Atlanta, Georgia 30308

Resident Inspector U. S. Nuclear Regulatory Route 2, Box 311 Athens, Alabama 35611

Commission

Mr. Charles R. Christopher Chairman, Limestone County Commission Post Office Box 188 Athens, Alabama 35611

Ira L. Meyers, M.D. State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36130

Mr. H. N. Culver 249A HBD 400 Commerce Avenue Tennessee Valley Authority Knoxville, Tennessee 37902

James P. O'Reilly Regional Administrator Region II Office U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

Mr. Donald L. Williams, Jr. Tennessee Valley Authority 400 West Summit Hill Drive, Knoxville, Tennessee 37902

WlOB85

George Jones, Manager, BFNP Tennessee Valley Authority Post Office Box 2000 Decatur, Alabama 35602

Mr. Oliver Havens U. S. Nuclear Regulatory Commission Reactor Training Center Osborne Office Center, Suite 200 Chattanooga, Tennessee 37411

James A. Coffey Site Director, BFNP Tennessee Valley Authority Post Office Box 2000 Decatur, Alabama 35602

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 pages.

Page

iii

vii

182

183

184

replace with identically numbered

Correction

Page number for "3.6.G" corrected.

Table 4.6.A deleted.

Title of "3.6.F" changed. Expired footnote deleted.

Margin bar corrected.

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

8411010300 841011 PDR ADOCK 05000259 P PDR

S ec,: i on

C. Coolant Leakaoe . . . . . . . . . .

0. Relief Valves

E. Jet Pumo

F. Re:±r:uiatin .,UmP Overaz.on

G. Structural Integrity.............

H. Seismic Restraints, SupDorts, and

2.7/4.7 Containment Systems

A. Primary Conftai nm.,cnt

B. Standby aas Tr•manent Sys .tm .

C. Secondary Containment

D. Primary Containment isola:ion Valves

E. Control Room Emergency Ventilation

F. Primary Containment Purge System .

Pac! No.

180

132

.. . . .. . IE3

Snubbers . laS

.. . . .. . Z27

27-: . . . . . 24

S.. . . . . 240

244

.. .. .. . . 246

G. Containment'Atmospnere Dilu'tion System (CAD)

Hi. Containment Atmosp•tere Moni:oring (CAM) Syst-em H.i analyz?.

2.8/4.8 Radio.2ctive Materials

A. Liquid Effluent: .......... .....

B. Air-borne Effluents. .............

C. Mechanical Vacuum Pump .............

D. 4iscellaneous Radioactive Materials Sourcas

3.9/4.9 Aux!liar-y Eie :rical System . . . . . . . . . . .

A. Auxiliary Electrical c-uiomer.:. ........

,. )cration with lroerable Clnulent

C. Oweration in Cold Shut.down .

3.10/4.10 Cre Alterations .

Rce n ; Lerlo7ýs.s ..... ..............

2 48

Z49

Z31

* • 286

25

298

293

iii

Amendment No. 921 98

I

LIST OF TABLE'S (Cont'd)-

Table Title ?a2e No.

4..Z.F mn Test and Calibration Frequency for SurvQeillance Insr= entat±0n ........... 105

4.Z.G Surveillance Requirements for Contol Room

4solazion Inswenta±on ...... . ..... 106

4.Z.3H Mnimu Teas and Calibration Frequency for

Flood Protec:tion nstumentaion ...... 107

4. Z.J Sesm.c blon±=oring Znstrament SurveI'llance ..... 108

3.5-1 Mini== M and Z P=p Assigent .. 152La

3.5.1 HAPLMR Versus Ave.age Planar Exposure ....... 171, 172, 172la

3.7.A ftima=7 Concai•enC I•slation Valves ......... 250

3.7.3 Testablea Pnetratons wit• Double O-Rin• Seals . . . 256

3.7. C Testable PenaCzat.ns- with Tascable Bellows .... . 257

3.7.D Air Tested .solatiom Valves ...... ...... ....... 258

3.7. E im7 Conca'=en Zsolation Valves which Temiatsa below the Suppression Pool Water Leval. 262

Sa........................

3.7.F ?fimazy Contai±-ent :solaroU Valves Loca:pd in Water Sealed Seismic Class I Lines ..... ......... 2563

3.7.H Testable Electrical Penetrations ...... .......... 265

4.8.A Radioactive Liquid Waste Sampling and Aalysis .. 287

4.8.3 Radioactive Gaseous Waste Sampling and Analysis 288

4.9.A.4.C Voltage Relay Setoints/Diesal Generator •tarr... 298a

3.11.A Fire Protection System Hydraulic Requirements . 324

6.8.A Minim== Shift Crew Requirements ....... .......... 360

.Amendment No. 98

LIMITING CONDITIONS FOR 0PEP�ATION SURVEILLANCE REOLTIREMENTS

3.6.F Recirculation Pumn Oneration

1. The reactor shall not be operated with one

recirculation loop out of service for more than 24

hours. With the reactor operating, if one 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 one pump operation, the discharge valve of the low speed pum~p may not be opened unless the speed of the 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. During such interval restart of 7

the recirculation pumps is permitted, provided the loop discharge temperature is within 750F of- the

saturation temperature of the reactor vessel water as determined by dome pressure. The total elapsed time in natural circulation and one pump operation must be no greater than 24 hours.

I

Amendment No. t$, 8$ , 89, 98

4.6.E Jet Pumvs

b. The 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 more than 10%.

2. Whenever there is recirculation flow with the reactor in the Startup or Run Mode and one recirculation pump is operating with the equalizer valve closed, the diffuser to lower plenum differential pressure shall be checked daily and tahe differential 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 10%.

4.6.F Recirculation Pumn Operation

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

.2. No additional surveillance required.

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

182

LIIITING C0,I•ITIONS FOR OPEPRATIOIN SURVEILLANCE REOUIREZYEIS

I

SIJRVtILLAHCE R�OU LRk2�F.NTSbLj.tL".r I t_C! )4 T-, n-!P F. -- -!•RA -'T T 0 N

3 .6 .G Nt!r ,,ct ,,rk I Inte gritc

1. 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.

18.

Yeadwater

MAin steam

KHR

Core Spray

G7W-9, k7W-13 GMJ-12, CFV-26, KYW-31, GFC-29, X7W-39, CUW-15, KX'-38, and CFW-32

- S-S6, KKS-24, G1S-32, KS-104 GCS-15, and CMS-24

- DSRILR-4, DS7Lwý-7; DSRHR- 8A

- DSCS-12, D•St-L, D5CS-5, and DSCS-4

Amendment No. 98

4.6.G Structural Incenrity

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 inspactions shall be performed on certain circumferenCisl pipe weids an listed to provide additional protection Againnt pipe whip, which could 4amage auxiliary and control mystnems.

.SURVEILLANCI REOU [RUX.ENM

I

DIMITINC CONDITIONS FOR OPERATION %SRVF7.IANC1. RQUIIRII-7rNT.

.6.•C Structural Integrity 4.6. r Structural Integritv

Re.-ic or

Cleanup - DSRWC-4, DSRWC-3 DSRWC-6, DSRWC-5

HPCI - THPCI-152 THFPCI-153B TrHCI-l, 3 THPCI-154

3. For Unit 1 an augmented inservice

surveillance program shall be performed to monitor pdtential corrosive effects of chloride residuereleased during the March 22. 1975 f:re. The augmented inservice surveillance program is specified as follows:

a. Browns Ferry Mechanical Maintenance Instruction 53, dated September 22. 1975, paragraph 4. defines the liqiuid penetrant examinations required during the first, second, third and fourth refueling outages following'the fire restoration.

b. Browns 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

. I



DOCKET NO. 50-260


1. Remove the following pages and pages.

Page

iii

vii

183

replace with identically numbered

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.

Secti on Pace K3.

C. Coolant Leakage . . . . .. . . . . . . . .. . 183

D. Relief Va-.ves . . . . . . . . . . . . . . . . . 131

E. Jet Pumps . . .. . . . . . . . . . . . . . . . 181

F. Recirculation Pp=- O~erarion . ........ 182

G. Structural Integrity ...... . .*...... 183

H. Seismic Restraints, Supports, and Snubbers 185

3.7/4.7 Containment Systems ....... ................ ... 227

A. Primary Containment ..... ..... ........... 227

B. Standby Gas Treatment System ............. ... 236

C. Secondary Containment ..... ............. ... 240

D. Primary Containment Isolation Valves .... ...... 242

E. Control Room Emergency Ventilation ......... ... 244

F. Primary Containment Purge System ............ 246

S. Containment Atmosphere Dilution System (CAD) . 248

H. Containment Atmosphere Monitoring (CA1J) System H2 Analyzer ........ , .... . I . 249

3.8/4.8 Radioactive Materials ...... ............... 281

A. .Liquid Effluents ............. . .. ....... 281

B. Airborne Effluents ....... ............... 282

C. Mechanical Vacuum Pump .... ............. ... 286

0. Miscellaneous Radioactive Materials Sources . 286

3.9/4.9 Auxiliary Electrical System .... ............ ... 292

A. Auxiliary Electrical Equipment ..... ......... 292

B. Operation with Inoperable Equipment ........ .. 295

C. Operation in Cold Shutdown .... .......... ... 298

3.10/4.10 Core Alterations ....................... ... 302

A. Refueling Interlocks ............... ..... 302

1i4i

/ e nen-ent 8o P'5H 92

1

LIST OF TABLES-(Cczmt d)

Table Title

4..Z.7 Mini=m Test and Calibration Frequency for

Suailze2lance, Zns:tz-entation.......

4.2. G Survailance Requirements fo: Control Room

Isolation Ins..entati...

4.Z.3 Xi•n± Tas-t andr Callbration T:equa=c for

Flood Protection Ins=-•encation ........

4.Z.J Seismic. Monito•ins •t•trt nz Surveillance

3.5-i M4,nm.3 MSW and. MC7 Pup Assignment .

3.5.Z MAPLEG1 Ve:sus Average Planar Exposure . . .

* . . .

3.7.A ?riia%7 Conta--nt - Is lation Valves ...........

3.7.3 Testable PenetaaciOn5L with Double 0-Ring Seals

3.7. C Testable Pencc-at±ans- with -Tastabl Bellows ....

3.7.3 Air Tasted Isol~ation Valves .. ........... .. .. ...

3.7. Z Primwr7 Con inn Isolatiodn Valves -which Terminata below the Ssapessan. Pool Water ILave/l. .* . . . -* " ".....................

3.7.F P-imary Conta±Sflnt Isolation Valves Locatd in

Water Sealed Seismic Class L Lines .... .......

3.7.H Testable Electical Penetrations ...............

4.8.A Radioactive Liquid W asc Sampling and Analysis

4.8.3 Radioactive Gas"ous Waste Sampling and. Analysis

4.9.A.4.C Voltage Relay Setpoints/Diasel. Generator Star .

3.11.A. Fire P=roection System Hyd-aullc Requirements

6.8.A Mnmi== Shift Crew Requirements ..........

A • Amendment No. a'5, 92

Page No.

r

105

106

107

108

52a.

171, 172,

250

256

257

2.58

262

253

265

Z87

288

298a.

324

360

?TTMTT~n rn mThTTfl F'OR OPERATIONSU ELACE E0IEN

3.6c.. ruct~srlI~nre.riv1


I S'

4.6.G Structural Inteurity

1. Inservice inspection of ASY-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 CYR 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) (1).

2. Additional inspoc:ion3 shall be parformed an certain circumferontiAl pipe welds as listed to providc additional protcc:ion Aaianst pipe whip, which could 4amage auxiliary and control xyxtemaa.

Yeadwater

MAin steam

RHR

Core Spray

CF,'-9. xYW-!3 C7W-12, CW--26, XYV-31, G'-9

"WT.-39, C,--!, 014-38, and CF",;-32

SMS-6, )O'S-24, Q45-32, QiS-104 CXS-15, and CMS-2 4

- SRUL•-.,•,D•m; 0 R -4,0S 7

TCS-407 TCS-423

TSCS-408 TSCS-424

Amendment No. 7 96

SURVEILLANCE REOUIEMENT

£-



DOCKET NO. 50-296


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

Page Correction

vii Table 4.6.A deleted.

196 Editorial changes to "3.6.G.1" for consistency with Units 1 and 2 Margin bar added for "4.6.G.1."

197 Restores Amendment No. 65 changes erroneously omitted when Amendment No. 69 was issued.

209 - 214 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.

4.2.E Minimum Test and Calibration Frequency for Drvweli Leak Detection Instrumentation

4.2.F Minimum Test and Calibration Frequency for Surveillance Instrumentation

4.2.G Surveillance Requirements for Control Room Isolation Instrumentation

4.2.x M inimum Test and Calibration Frequency for Flood Protection Instrumentation

4.2.j Seismic Monitoring Instrument Surveillance Requirements 3.5.-1 Minimum FMRSW and EECW Pump Assignment 3.5.1 MUALHCR vs. Average Planar Exposure

3.7.A Primary Containment Isolation Valves 3.7.B Testable Penetrations with Double O-Ring Seals 3.7.C Testable Penetrations with Testable Bellows 3.".D Air Tested Isolation Valves 3.7.E Primary Containment Isolation Valves which Terminate Below the Suppression Pool Water Level 3.J..F Primary Co,.tainment Isolation Valves Located in Water Sealed Seismic Class 1 Lines

3.7.G Deleted

3.7.H Testable Electrical Penetrations 4 .8.A Radioactive Liquid Waste Sampling and Analysis 4.8.B Radioactive Gaseous Waste Sampling and Analysis 4.9.A.4.c Voltage Relay Setpoints/Diesel

Generator Start 3.11.A Fire Protection System Hydraulic Requirements

6.8.A Minimum Shift Crew Requirements

10I

102

103

104

105

156a

1H 182,

262

268

269

270

279

280

283

310

311

32 6a

955.

39o

vii

Am e ndm e nt No . >-< 96/ S •, 745,7 8

I 182a, 182b

I

4IMITING CONDITIONS FOR OPERATION

PRI MRJY SYST"!M BOVNDARY

G. Structural Integrity


$.

4.6 PRIMARY SYSTEM BOUNDARY

G. Structural Inteqrity

1. Inservice inspection of ASHE Code Class 1, Class 2, and Class 3 components shall be performed in accordance with Section XI of the AME 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. 5 5 a (g) (6) (1).

2. 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 systemse

Feed

196

hiater- GFW-9, KFW--13., GFW-12, GFW-26, KFW-31, GFW-29, KFW-39, GFW-15, KFW-38, and GFW-32

Amendment Nos./,•, ,' , 65

SURVEILLANCE REOUIREIMUTS

I -

LIMITING CONDITICSS Frt OPEPA'flON:8R!LAC !V RMET

3. 6 PRIMqARY 3YS?'"I BOUNDARX 11.6 pW1jA=R SySTZM SOUNUARY

Main steam-G246e ICZ-241 (24S-32f KNs-1O'4. GHS-15, and GNtS-2'4

RHR -=HR1-i, DsRHR-7, and 1OSREHR4

Core Spray-'TCS-407 TCS-423 Reactor TSCS-408 TSCS-424

Cleanup

HPC1

-OSRWC-4, OSRiC-3. OSRWC-6, and OSR.¶C-5

-THPCI-70 THPCI-70A

rH.PCI-71, and THPCI-72

R =V1 MICE

1. Plant Saiety-Afalysis (BFNP ?SAR subsect.Ofl

43. 12-)

197

SURVZXLLANCZ R=UIRI-MENTS

PAGES DELETED

209-214

Amendment No. 65