ML20141G247

Monthly Operating Repts for Apr 1997 for Browns Ferry Nuclear Plant Units 1,2 & 3

ML20141G247
Person / Time
Site:	Browns Ferry
Issue date:	04/30/1997
From:	Abney T, Davenport J TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9705220236
Download: ML20141G247 (13)

Text

y- 8 -

Tennessee Valley Authcrity. Post office Box 2000. Decatur, Alabama 35609-2000 May 15, 1997 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - APRIL 1997 MONTHLY OPERATING REPORT The enclosure provic'es the April 1997 Monthly Operating Report as required by BFN Technical Specifications Section 6.9.1.3.

If you have any questions concerning this matter, please call me at (205) 729-2636.

Si1cerely, j

/ /

k.

E. Ab 2 Manager censing and ndustry Affairs  ;

I Enclosure i cc: See page 2 9705220236 970430 PDR ADOCK 05000259 R PDR lllljlllllll]l]ll]lllllllllllllll I

emee.o om. i

U.S. Nuclear Regulatory Commission Page 2 May.15, 1997 SMK:JWD:BAB cc (Enclosure):

Mr. Mark S. Lesser, Branch Chief U. S. Nuclear Regulatory Commission  !

Region II 61 Forsyth Street, S.W.

Suite 23T85 ,

Atlanta, Georgia 30323 Mr. Frederick J. Hebdon, Director Project Directorate II-4 Division of Reactor Projects I-II Office of Nuclear Reactor Regulation, Mail 13 H3 Washington, D.C. 20555 INPO Records Center Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, Georgia 30339-5957 Mr. James Lang, Manager Advanced Reactor Department Electric Power Research Institute

. 3340 Hillview Avenue Palo Alto, California 94304 .

NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 Regional Administrator U.S. Nuclear Regulatory Commisbion Region II 61 Forsyth' Street, S.W. ,

Suite 23T85 l Atlanta,: Georgia 30323 l 4

Ms. Barbara Lewis McGraw-Hill Companies 1200 G Street, N.W.

Suite 1100 Washington, D.C. 20005-3802 l

l 4

ENCLOSURE f

TENNESSEE VALLEY AUTHORITY j BROWNS FERRY NUCLEAR PLANT (BIN) ,

MONTHLY OPERATING REPORT 4

APRIL 1997

]

UNIT 1 DOCKET NUMBER 50-259 I LICENSE NUMBER DPR-33 UNIT 2 DOCKET NUMBER 50-260 LICENSE NUMBER DPR-52 n

l

UNIT 3 DOCKET NUMBER 50-296 LICENSE NUMBER DPR-68 1

s

e ,

OPERATIONAL SUMt4ARY APRIL 1997

/,

r. BROWNS FERRY NUCLEAR PLANT UNIT 1 Unit 1 remains shutdown on administrative hold to resolve various TVA and NRC concerns. Unit 1 has been on administrative hold

, since June 1, 1985. As a result, TVA considers that accrual of reporting hours is suspended since the unit has a maximum dependable capacity of zero MWe. Accordingly, TVA does not.

consider reporting cumulative hours for the period beginning

, June 1, 1985, when calculating the operating status variables.

BROWNS FERRY NUCLEAR PLANT UNIT 2 For the month of April, Unit 2 generated 695,400 megawatt hours gross electrical power and operated at a net capacity factor of 88.6 96r,ent. The unit scramed at 1814 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.90227e-4 months <br /> on April 24, 1997.

The Mcil Turbine and all three reactor feedwater pump turbines tripped when a high reactor water level signal was inadvertently generated during the performance of a unit surveillance instruction. The unit restarted on April 27, 1997, with breaker closure at 0932 hours0.0108 days <br />0.259 hours <br />0.00154 weeks <br />3.54626e-4 months <br />. As of April 30, 1997, Unit 2 has coerated continuously for 3 days.

l BROWNS FERRY NUCLEAR PLANT UNIT 3 For the month of April, Unit 3 generated 795,270 megawatt hours gross electrical power with a net capacity factor of 101.4 percent. As of April 30, 1997, Unit 3 has operated conti.. ;usly for 48 days.

E-1

l 1

)

4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-259 UNIT NO. ONE DATE: May 15, 1997 COMPLETED BY: J. W. Davenport TELEPHONE 20S-729-2690 l t

MONTH April 1997 AVERAGE DAILY POWER LEVEL AVEIGGE DAILY'PCWER LEVEL DAY (We-Net) DAY (We-Net)

1. 0 17. 0

2. 0 18. 0

3. 0 19. 0

4. 0 20. 0 v

5. 0 21. 0 ,

6. 0 22. 0

7. 0 23. O t

8. 0 24. 0

9. 0 25. 0

10. 0 26. 0

11. 0 27. 0 12 0 28. 0

13. 0 29. 0

14. 0 30. 0

15. 0

16. 0 E-2

ks - n n 4,m +4, u -e 4- a--L rda-- e +---,4 W AVERAGE DAILY UNIT POWER LEVEL t

DOCKET NO. 50-260 UNIT NO. TWO DATE: May 15, 1997 COMPLETED BY: J. W. Davenport TELEPHONE 205-729-2690 .

MONTH April 1997 j AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL ,

DAY  ;

~

DAY (MWe-Net) (MWe-Ne t) [

. 1. 1093 17, 1056 >

2. 1081 18. 1065 1

~

3. 1077 19. 1080

4. 1035 20. 1084

5. 828 21, 1078 l 6. 948 22. 1081

7. 1065 23, 1081

8. 1000 24. 817

9. 1081 25. O

! 10. 1083 26. 0

11. 1092 27. 241 i

12 1092 28. 841 i

13. 1092 29. 965

14. 1093 YO. 988

15. 1082

16. 1083 T

E-3

1 i . .

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-296 UNIT NO. THREE DATE: May 15, 1997 COMPLETED BY: J. W. Davenport TELEPHONE ' 5-729-2690 MONTH April 1997 AVERAGE DAILY PCHER LEVEL AVERAGE DAILY POWER LEVEL DAY DAY (MWe-Net) (MWe-Net)

1. 1061 17. 1065

2. 1084 18. 1065 3, 1093 19. 1085

4. 981 20. 1080

5. 1085 21. 1084 6, 1046 22. 1087

7. 1055 23. 1084

8. 1089 24. 1089

9. 1083 25. 1084

10. 1090 26. 1076

11. 1089 27. 1076 12 1093 28. 1090

13. 1093 29. 1081

14. 1093 30. 1092

15. 1094 16, 1088 E-4

~ "

OPERATING DATA REPORT Docket No. 50-259 Date: May 15.1997 Completed By: J. W. Davenport Telephone: 205-729-2690

1. Unit Name: BFN Unit 1

2. Reporting Period: April 1997

3. Licensed Thermal Power (MWt): 3293

4. Nameplate Rating (Gross Mwe): 1152

5. Design Electrical Rating (Net Mwe): 1065

6. Maximum Dependable Capacity (Gross MWe): 0

7. Maximum Dependable Capacity (Net MWe): 0

8. If changes Occur in Capacity Rating (Item Numbers 3 Through 7) Since Last Report, Give Reasons: N/A

9. Power Level To Which Restricted, If any (net MWe): 0

. 10. Reasons for Restrictions, if any: Administrative IIold This Month Yr-To-Date Cumulative *

11. Hours in Reporting Period 0 0 95743

12. Number of Hours Reactor was Critica! 0 0 59521

13. Reactor Reserve Shutdown Hours 0 0 6997

14. Hours Generator On-Line 0 0 58267

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWh) 0 0 168066787

17. Gross Electric Energy Generated (MWh) 0 0 55398130

18. Net Electrical Energy Generated (MWh) 0 0 53796427

19. Unit Service Factor 0 0 60.9

20. Unit Availability Factor 0 0 60.9

21. Unit Capacity Factor (Using MDC Net) 0 0 52.3

22. Unit Capacity Factor (Using DER Net) 0 0 52.8

23. Unit Forced Outage Rate 0 0 25.6

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): N/A

25. If Shutdown at End of Report Period, Estimate Date of Startup: To Be Determined

• Excludes hours under administrative hold (June 1,1985 to present)

E-5

. l OPERATING DATA REPORT F#ccket No. 50-260 Date: May 15.1997 Completed By: J. W. Davenport Telephone: 205-729-2690

1. Unit Name: BFN Unit 2

2. Reporting Period: Anril 1997

3. Licensed Thermal Power (MWt): 3293

4. Nameplate Rating (Gross Mwe): 1152

5. Design Electrical Rating (Net Mwe): 1065

6. Maximum Dependable Capacity (Gross MWe): 1098.4

7. Maximum Dependable Capacity (Net MWe): 1065

8. If changes Occur in Capacity Rating (Item Numbers 3 Through 7) Since Last Report, Give Reasons: N/A >

9. Power Level To Which Restricted, if any (net MWe): N/A

10. Reasons for Restrictions, If any: N/A This Month Yr-To-Da te Cumulative *

11. IIours in Reporting Period 719.0 2879.0 142494

12. Number ofIlours Reactor was Critical 661.0 2816.0 101465

13. Reactor Reserve Shutdown llours 0.0 0.0 14200

14. Ilours Generator On-Line 655.7 2816G 99098

15. Unit Reserve Shutdown liours 0.0 0.0 0

16. Gross Thermal Energy Generated (MWh) 28e232.0 8838192 293025292

17. Gross Electric Energy Generated (MWh) 695400.0 2968020 97389388

18. Net Electrical Energy Generated (MWh) 678114.0 2897717 94730882

19. Unit Service Factor 91.2 97.8 69.5

20. Unit Availability Factor 91.2 97.8 69.5

21. Unit Capacity Factor (Using MDC Net) 88.6 94.5 62.4

22. Unit Capacity Factor (Using DER Net) 88.6 94.5 62.4

23. Unit Forced Outage Rate 8.8 2.2 14.7

24. Shutdowns Scheduled Os er Next 6 Months (Type, Date, and Duration of Each): Unit 2 Cycle 9 Refueling Outage, Scheduled to begin 9/21/97, 23 days duration

25. If Shutdown at End of Report Period, Estimate Date of Startup: N/A

• Excludes hours under administrative hold (June 1,1985 to May 24,1991)

E-6 i

I OPERATING DATA REPORT Docket No. 50-296 Date: May 15.1997 i Completed By: J. W. Davenpon I Telephone: 205-729-2690  ;

1. Unit Name: BFN linit 3  ;

2. Reporting Period: April 1997

3. Licensed Thermal Power (MWt): 3293

4. Nameplate Rating (Gross Mwe): 1152

5. Design Electrical Rating (Net Mwe): 1065

6. Maximum Dependable Capacity (Gross MWe): 1098.4

7. Maximum Dependable Capacity (Net MWe): 1065

8. Ifchanges Occur in Capacity Rating (Item Numbers 3 Through 7) Since Last Report, Give Reasons: N/A

9. Power Level To Which Restricted, If any (net MWe): N/A

10. Reasons for Restrictions, If any: N/A

.This Month Vr-To-Date Cumulative *

11. Hours in Reporting Period 719.0 2879.0 85716

12. Number ofIlours Reactor was Critical 719.0 2439.0 57193

13. Reactor Reserve Shutdown flours 0.0 0.0 5150

14. IIours Generator On-Line 719.0 2421.2 55840

15. Unit Reserve Shutdown Hours 0.0 0.0 0

16. Gross Thermal Energy Generated (MWh) 2353584.0 7076880 168307537

17. Gross Electric Energy Generated (MWh) 795270.0 2347860 56372000

18. Net Electrical Energy Generated (MWh) 776528.0 2284743 53966874

19. Unit Service Factor 100.0 84.1 65.1

20. Unit Availability Factor 100.0 84.1 65.1

21. Unit Capacity Factor (Using MDC Net) 101.4 74.5 59.1

22. Unit Capacity Factor (Using DER Net) 101.4 74.5 59.1

23. Unit Forced Outage Rate 0.0 0.0 18.1

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): N/A

25. If Shutdown at End of Report Period, Estimate Date of Stanup: N/A

• Excludes hours under administrative hold (June 1,1985 to November 19,1995)

E-7

9 UNIT SIIUTDOWNS AND POWER REDUCTIONS ,

REPORT MONTil: APRIL 1997 ,

DOCKET NO: 50-259 UNIT NAME: BFN-1 -

DATE: May 15,1997 COMPLETJ, BY: J. W. Davenport TELEPIlONE: (205) 729-2690 NoO SDateJ Type.'r -Duration: Reason *! Method ofj ;Licenseejl Systear 'Componenti Cause and Corrective Action to Prevent 6

i(Hours)j Sh.uttingl Event Report Code */ Code' -

Recurrencej m lDow C l No.( , a m Reactob 1 06/01/S5 S 719 F 4 N/A N/A N/A Administrative hold to resolve various TVA and NRC concerns.

l

+

l  :

d

' F: Forced

• Reason: ' Method Exhibit G -Instructions for (NUREG ,

S: Scheduled A-Equipment Failure (Explain) 1-Manual Preparation of Data Entry sheets '

B-Maintenance or Test 2-Manual Scram for Licensee Event Report (LER)

C-Refueling 3-Automatic Scram File - NUREG - 1022 D-Regulatory Restriction 4-Continuation of Existing E-Operator Training and License Outage 8

Examination 5-Reduction Exhibit I-Same Soune F-Administrative 9-Other G-Operational Error (Explain)

H-Other(Explain)

E-8

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: APRIL 1997 ,

DOCKET NO: 50-260 UNIT NAME: BFN-2 -

DATE: May 15,1997 COMPLETED BY: 3. W. Davenpott TELEPHONE: (205) 729-2690 2

!N Q (Date 4 ! Type'! l Duration Reason ~ Method ofi; iUcenseef Systens Comiponent: Cause and. Corrective' Action to Prevent j W

fg (Hears)} Shutting j Evest Report Code" TCode F Recurrencel . -

~

-MW*

~ ~'

, y Dotynf... No.1 a

~'

^

Reactor' ~ ^ -

3 04/24/97 F 63.3 G 3 260/97001 N/A N/A Unit 2 scramed at 1814 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.90227e-4 months <br /> on 4/24/97.

He Main Turbine and all three reactor feedwater pump turbines tripped witen a high reactor water level signalwas inadvertently generated during the performance of a unit surveillance insttuction. The unit restarted on 4/27/97, with breaker closute at 0932 hours0.0108 days <br />0.259 hours <br />0.00154 weeks <br />3.54626e-4 months <br />.

8

• F: Forced ' Reason: Method

• Exhibit G -Instructions for(NUREG S: Scheduled A-Equipment Failure (Explain) 1-Manual Preparation of Data Entry sheets B-Maintenance or Test 2-Manual Scram for Licensee Ennt Report (LER)

C-Refueling 3-Automatic Scram File - NUREG - 1022  !

D-Regulatory Restriction 4-Continuation of Existing E-OperatorTraining and License Outage 8

Examination 5-Reduction Exhibit I-Same Source F-Administrative 9-Other G-Operational Error (Explain)

H-Other (Explain)

E-9

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: APRIL 1997 ,

DOCKET NO: 50-296 UNIT NAME: BFN-3

• DATE: May 15,1997 COMPLETED BY: J. W. Davenpor+

TELEPHONE: (205) 729-2696 lNo2

~

9Date;i Type' : Duration .

~

. Reason

• Method ofi l Licensee;

• Systena? . Component- LCauseland Corrective Action';tn Prevent;!

I(Hours)h Shutting] , Event Report C63e'l !Codef .REA M encei? u M W:

[$[

' ~~

W

~

Dodf . No.c

~

w , ~

/dj;;i-Reactor')

D'aQ!.

6:.!

N/A 2

' F: Forced Reason:

• Method

• Exhibit G -Instructions for (NUREG S: Scheduled A-Equipment Failure (Explain) 1-Manual Preparation of Data Eatry sheets B-Maintenance or Test 2-Manual Scram for Licensee Event Report (LER)

C-Refueling 3-Automatic Scram File - NUREG - 1022 D-Regulatory Restriction 4-Continuation of Existing E-Operator Training and License Outage Examination 5-Reduction s Exhibit I-Same Source F-Administrative 9-Other G-Operational Error (Explain)

H-Other (Explain)

E-10

- -. . . . - .