ML20141H250

Monthly Operating Repts for June 1997 for BFN Per TS Section 6.9.1.3

ML20141H250
Person / Time
Site:	Browns Ferry
Issue date:	06/30/1997
From:	Abney T, Davenport J TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9707220143
Download: ML20141H250 (13)

Text

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s Bl4 Tennessee Valley Authority, Post Office Box 2000. Decatur, Alabama 35609-2000 July 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) - JUNE 1997 MONTHLY OPERATING REPORT The enclosure provides the June 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.

Sincerely, l

rie Manager of ' ensin and In stry Affai s Enclosure 4

cc: See pag 2 (S l 9707220143 970630 PDR ADOCK 05000259 R PDR lllllllll lll l lll

I I '

U..S. Nuclear Regulatory Commission l

Page 2 July 15, 1997 l

l l

l Enclosure '

cc (Enclosure):

Mr. Mark S. Lesser, Branch Chief U. S. Nuclear Regulatory Commission Region II 61 Forsyth Street, S.W.

Suite 23T85 Atlanta, Georgia 30303 Mr. Frederick J. Hebdon, Director Project Directorate II-4 ,

Division of Reactor Projects I-II l Office of Nuclear Reactor Regulation, Mail 13 H3 Washington, D.C. 20555 INPO Records Center Institute of Nuclear Power Operations 700 Galleria Parkway i Atlanta, Georgia 30339-5957 l Mr. James Lang, Manager Advanced Reactor Department Electric Power Research Institute 3340 Hillview Avenue Palo Alto, California 94304 l

NRC Recident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road I

Athens, Alabama 35611 Regional Administrator U.S. Nuclear Regulatory Commission Region II 61 Forsyth Street, S.W.

Suite 23T85 Atlanta, Georgia 30303 Ms. Barbara Lewis McGraw-Hill Companies 1200 G Street, N.W.

Suite 1100 Washington, D.C. 20005-3802

. a ENCLOSURE I

i' TENNESSEE VALLEY AUTHORITY

BROWNS FERRY NUCLEAR PLANT (BFN) 1 i-4 1

MONTHLY OPERATING REPORT i

j JUNE 1997

UNIT 1 DOCKET NUMBER 50-259 LICENSE NUMBER DPR-33 UNIT 2 1

k l DOCKET NUMBER 50-260 4

LICENSE NUMBER DPR-52 1 i i i

i i

I UNIT 3 DOCKET NUMBER 50-296 LICENSE NUMBER DPR-68 i

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(

. OPERATIONAL SUMt4ARY l JUNE 1997 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 June, Unit 2 generated 784,830 megawatt hours gross electrical' power and operated at a net capacity factor of 99.9 percent. As of June 30, 1997, Unit 2 has operated continuously for 64 days.

BROWNS FERRY NUCLEAR PLANT UNIT 3 For the month of June, Unit 3 generated 790,420 megawatt hours gross electrical power with a net capacity factor of 100.7 percent. As of June 30, 1997, Unit 3 has operated continuously for 109 days.

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4 AVERAGE DAILY UNIT POWER LEVEL 1 t

l DOCKET NO. 50-259 UNIT NO. ONE DATE: July 15, 1997 l

l COMPLETED BY: J. W. Davenport TELEPHONE 205-729-2690 .

l l l MONTH June 1997 i

1 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL I DAY (MWe-Net) DAY (MWe-Net)

1. 0 17. 0 ,

l 18.

2. 0 0

3. 0 19. 0

4. 0 20. 0

5. 0 21. 0

6. 0 22. 0

7. 0 23. 0

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. O l

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, AVERAGE DAILY UNIT POWER LEVEL-DOCKET NO. 50-260 UNIT NO. TWO DATE: July 15, 1997 COMPLETED BY: J. W. Davenport TELEPHONE 205-729-2690 MONTH June 1997 i

AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY DAY (MWe-Net) (MWe-Net) l 1. 1076 17. 1067

2. 1076 18. 1066  !

3. 1083 19. 1061 l

l 4. 1065 20. 1066 l 5. 1074 21. 941 6, 1074 22. 1066 l 7. 1073 23. 1074

8. 1072 24. 1049 9, 1079 25, 1070 i l

10. 1076 26, 1071 l

11. 1074 27. 1048 12 1069 28. 1049

13. 1071 29. 1050

14. 1071 30, 1070

15. 1070 l

l 16. 1068 E-3

AVERAGE DAILY UNIT POWER LEVEL 4

DOCKET NO. 50-296 UNIT NO. THREE DATE: July 15, 1997 >

COMPLETED BY: J. W. Davenport TELEPHONE 205-729-2690 J

MONTH June 1997 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY DAY (MWe-Net) (MWe-Net) 4

1. 1075 17. 1075 i 2. 1084 18. 1076

3. 1081 19. 1074 i

4. 1080 20. 1074

5. 1080 21. 1084 a

6. 1079 22. 1062

7. 1079 23, 1088 4

8. 1078 24. 1059

9. 1091 25. 1078

10. 1082 26. 1081

11. 1084 27, 1002 12 1083 28. 989

13. 1080 29. 1055

14. 1081 30. 1074

15. 1075

16. 1077 4

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, OPERATING DATA REPORT d

Docket No. 50-259 Date: Julv.151997 Completed By: J. W. Davenport Telephone: 205-729-2690

l. Unit Name: BFN Unit 1 i 2. Reporting Period: June 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): 9

7. Maximum Dependable Capacity (Net MWe): g

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 Hold This Month Yr-To-Date Cumulative *

11. Hours in Reporting Period 0 0 95743

12. Number of Hours Reactor was Critical 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 52.8

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) l E-5 l

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l OPERATING DATA REPORT Docket No. 50-260 Date: July 15.1997 Completed By: J. W. Davenport Telephone: 205-729-2690 l f  !

l. Unit Name: BFN Unit 2

2. Reporting Period: June 1997 )

3. Licensed Thermal Power (MWt): 3293 l

4. Nameplate Rating (Gross Mwe): 1152

! 5. Design Electrical Rating (Net Mwe): 1065 l

l 6.l Maximum Dependable Capacity (Gross MWe): 1998.4 1

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-Date Cumulative *

11. Hours in Reporting Period 720.0 4343.0 143958 )

12. Number of Hours Reactor was Critical 720.0 4285.0 102934 i

13. Reactor Reserve Shutdown Hours 0.0 0.0 14200

14. Hours Generator On-Line 720.0 4280.0 100562

15. Unit Reserve Shutdown Hours 0.0 0.0 0

~16. Gross Thermal Energy Generated (MWh) 2360016.0 13629456 297816556

17. Gross Electric Energy Generated (MWh) 784830.0 4565270 98986638

18. Net Electrical Energy Generated (MWh) 766034.0 4456892 96290057

19. Unit Service Factor 100.0 98.5 69.9

20. Unit Availability Factor 100.0 98.5 69.9

21. Unit Capacity Factor (Using MDC Net) 99.9 96.4 62.8

22. Unit Capacity Factor (Using DER Net) 99.9 96.4 62.8

23. Unit Forced Outage Rate 0.0 1.5 14.5

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Unit 2 Cycle 9 Refueling Outage, Scheduled to begin 9/26/97, 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)

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. OPERATING DATA REPORT Docket No. 50-296 Date: July 15.1997 Completed By: J. W. Davenport Telephone: 205-729-2690

1. Unit Name: BFN Unit 3

2. Reporting Period: June 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): 1998.4

7. Maximum Dependable Capacity (Net MWe): 1965

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 fn' ti ons, If any: N/A This Month Yr-To-Date Cumulative *

11. Hours in Rey ung Period 720.0 4343.0 87180

12. Number of Hours Reactor was Critical 720.0 3903.0 58657

13. Reactor Reserve Shutdown Hours 0.0 0.0 5150

14. Hours Generator On-Line 720.0 3885.2 57304

15. Unit Reserve Shutdown Hours 0.0 0.0 0

16. Gross Thermal Energy Generated (MWh) 2358864.0 11846784 173077441

17. Gross Electric Energy Generated (MWh) 790420.0 3948930 57973070

18. Net Electrical Energy Generated (MWh) 771840.0 3847772 55529904

19. Unit Service Factor 100.0 89.5 65.7

20. Unit Availability Factor 100.0 89.5 65.7

21. Unit Capacity Factor (Using MDC Net) 100.7 83.2 59.8

22. Unit Capacity Factor (Using DER Net) 100.7 83.2 59.8

23. Unit Forced Outage Rate 0.0 0.0 17.7

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: N/A

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

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UNIT SHUTDOWNS AND POWER REDUCTIONS

• REPORT MONTH: JUNE 1997 ,

DOCKET NO: 50-259 UNIT NAME: BFN-1 DATE: July 151997 COMPLETED BY: J. W. Davenport TELEPHONE: (205) 729-2690 System L :: Component: Cause and Corrective Action;to Preventi 2

N i:3 q Datej Type' Duration l  ; Reason Method of-l Licensee !

EventlRepohc Code? : Codese

~

.;(Hours) p S.hstting';- ~

Recurrence?

-Down(.. No.

- Reactor'I C 1 06/01/85 S 720 F 4 N/A N/A N/A Administrative hold to resolve various TVA and NRC concerns.

' F: Forced

• Reason: ' Method

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

C-Refueling 3-Automatic Scram File - NUREG - 1922 D-Regulatory Restriction 4-Continuation of Existing E-Operator Training and License Outage Examination 5-Reduction

• Exhibit I-Same Source F-Administrative 9-Other G-Operational Error (Explain)

H-Other (Explain)

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UNIT SHUTDOWNS AND POWER REDUCTIONS

• REPORT MONTH: JUNE 1997 DOCKET NO: 50-260 -

UNIT NAME: BFN-2 DATE: July 15,1997 COMPLETED BY: J. W. Davenport TELEPHONE: (205) 729-2690

'Nm ]Date) Typei ;Durationi LReason*  : Method 00 Licenseel System;; Componentj Cause and_. Corrective ActionLio Preventi

~

'(Hours)) -

Shuttingl{ LEQent Reportl 'Codey CodeF

^^

lRecurrenceil <

g,(- ;- :No.? ^

• ReactoN/

N/A l

R r

2

• 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 ofExisting E-Operator Training and License Outage Examination 5-Reduction s Exhibit 1-Same Source F-Administrative 9-Other s G-Operational Error (Explain)

H-Other (Explain)

E-9

~ ~

UNIT SHUTDOWNS AND POWER REDUCTIONS -

REPORT MONTH: JUNE 1997 .

DOCKET NO: 50-296 -

UNIT NAME: BFN-3 DATE: July 15,1997 COMPLETED BY: J. W. Davenport TELEPHONE: (205) 729-2690 Nin :Tyli e -Duration! . Reason' - Method of; Licenseel

- Date..'

Systemt <Componentj Cause and. Corrective Action to Prevent]

. Shutting j ~ Event.Reportl Codei LC$de7 Recurrencel i

(Hours)1

-D o w n 1... No.-

' ' ~

ReactAd N/A 2

' F: Forced Reason: ' Method

• Exhibit G -Instrictions 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 Examinotion 5-Reduction

• Exhibit I-Same Source F-Administrative 9-Other G-Operational Error (Explain)

H-Other (Explain)

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