ML20077Q106

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Monthly Operating Repts for Jul 1991 for Browns Ferry Nuclear Plant
ML20077Q106
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 07/31/1991
From: Carier P, Ratliff S
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9108210063
Download: ML20077Q106 (16)


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AUS 1 199; U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C.

20555 Gentlemen:

In the Matter of

)

Docket Hos. 50-259 Tennessee Valley Authority

)

50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - MONTilLY OPERATING REPORT FOR Tile MONTil 0F JULY 1991 In accordance with the requirements of the BFN Technical Specifications (TS) section 6.9.1.3, the Monthly Operating Report for the month of July 1991 is Enclosure 1. contains a revision to June 1991 Monthly Operating Report.

This revision provides clarification to the Unit 2 shutdowns and power reduction events.

If you have any questions, please telephone me at (205) 729-3566.

Very truly yours, TENHF. EE VALLEY A TIIORITY

'4fLW'jlsa,L Patrick P. Car er, Manager of Site Licensing Enclosures cc: See page 2

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2 U S. Nuclear Regulatory Commission

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Al'D i b l57e Enclosures cc (Enclosures):

INPO Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30389 Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, F-

'900 Atlanta, Georgia 30323 Mr. Frederick J. Hebdo,

...or Project Directorate II-4 Division of Reactor Projects I-II Office of Nuclear Reactor Regulation, Mail 13 H3 Washington, D. C. 20555 Mr. Ted Marston, Director Electric Power Research Institute P. O. Box 10412 Palo Alto, California 94304 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II Regulatory Ccomission 101 Marietta Street, NW, Suite 2900 Atlanta Georgia 30323 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000 Mr. Fred Yost, Director of Research Services, Utility Data Institute, Inc.,

1700 K Street N. W., Suit e 400 Washington, D.C.

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ENCLOSURE 1 i

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OPERATIONAL SUIMARY JULY 1991 UNIT 1 Unit remains on administrative hold to resolve various TVA and NRC concerns.

t' Unit is still in the power ascension testing program.

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Unit remalus on administrative hold to resolve various TVA and NRC concerns.

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MONTHLY OPERATING REPORT BROWNS FERRY NUCLEAR PLANT TENNESSEE VALLEY AUTHORITY JULY 1991 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 l

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AVERAGE DAILY UNIT POWER LEVEL O

DOCKET NO.

50-259 Unit One PREPARED BY S..A._Batliff TELEPHONE (205) 729-2937 MONTH JULY 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 0

17 0

2 0

18 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 31 0

h 16 0

l-0449k/8 l

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-210 Unit Two PREPARED BY S. A. Ratliff TELEPHONE (205) 729-2937

. MONTil JULY 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 103 17 596 2

133 18 745 l

3 141 19 477 4

211 20 563 5

252 21 571 6

-254 22 671 7

304 23 706 8

362 24 809 9

397 25 897-10 389 26 966 11 492 27 982 12 436 28 927 13 435 29 937 L

14 439 30 965

(_

i 15 468 31 744 16 452 0449k/10

.o AVERACE DAILY UNIT POWER LEVEL DOCKET NO.

50-296 UNIT

_Thrfe PREPARED BY S. A. Ratliff TELEPHONE 1205) 729-29?1 MONTH JULY 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 0-17 0

2 0

18 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

l 9

0 25 0

l 10 0

26 0

11 0

27 0

i l

12 0

28 0

13 0

29 0

14 0

30 0

15 0

31 0

l 16 0

0449k/10

r OPERATING DATA REPORT

_50 2J9 DOCKET NO.

2 PREPARED BY

$1_A. Ratlitf__

TELEPHONE [205) 729-2937 OPERATING STATUS

! Notes 1.

Unit Name:

Browns Ferry Unit One 2.

Reporting Period:

July 1991 3.

Licensed Thermal Power (MWt): _3221, 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 If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

8.

N/A r'

9.

Power Level To Which Restricted, If Any (Net MWe):

N/A

10. Reasons Fo-Restrictions, If Any:

N/A This Month Yr-t o-Da te Cumulative

11. Hours in Repor4 ing Period 744 5087 149071
12. Number of Hours e, 'ctor Was Critical 0

0 59521

13. Reactor Reserve Shutuewn Hours 0

0 6997

14. Hours Generator On-Line 0

0 58257

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 0 0

16S066787

17. Gross Electrical Energy Generated (MWH) 0 0

55398130

13. Net Electrical Energy Generated (MWH)

-2947

-14875 53545595 0

0 39.1

19. Unit Service Factor
20. Unit Availability Factor 0

0 39.1

21. Unit Capacity Factor (Using M.DC Net) 0 0

33.7

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

33.7

23. Unit Forced Outage Rate 100 100 55. l__
24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):

N/A

25. If Shut Down At End Of Report Period, Estimated Date of Startup: To be determined 0449k/11

OPERAVING DATA REPORT

'O DOCRET NO.

50-260 PREPARED BY S. A. Ratliff TELEPHONE (205) 729-2937 OPERATING' STATUS

! Notes 1.

Unit Name:

Browns Ferry Unit Two 2.

Reporting Period:

July 1991 3.

Licensed Thermal Power (MWt): _3203__

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 Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

N/A 1

F 9.

Power Level To Which Restricted, If Any (Net MWe):

N/A

10. Reasons For Restrictions, If Anyt N/A This Month Yr-to-Date Cumulative
11. Hours in Reporting Period 744.0 5087.0 143958
12. Number of Hours Reactor Was Critical 744.0 1199.6 57060
13. Reactor Reserve Shutdown Hours 0

0 14200

14. Hours Generator On-Line 740.9 756.6 55095
15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Therral Energy Generated (MWH) 1460511.2 1509437.3 154754605
17. Gross Eler.trical Energy Generated (MWH) 418210.0 419860.0 51191658
19. Net Ele'.trical Energy Generated (MWH) 404538.0 369663.0 494207B4
19. Unit service Factor 99.6 14.9 38.3 20 Unit Availability Factor 99.6 14.9 38.3
21. Unit Capacity Factor (Using MDC Net) 51.1 6.8 32.2
22. Unit Capacity Factor (Using DER Net) 51.1 6.8 32.2
23. Unit Forced Outage Rate 0

85.1 55.0

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

N/A

25. If Shut Down At End Of Report Period, Estimated Date of Startup:

N/A 0449k/13

OPERATING DATA REPORT DOCKET NO.

50-296 PREPARED BY S. A. Ratliff TELEPHONE (205) 729-2937 QPERATING STATUS

! Notes 1.

Unit Name:

Browns Ferry Unit Three 2.

Reporting Period:

July 1991 3.

Licensed Thermal Power (MWt): 3293 4.

Ntteplate Rating (Gross MWe): 1152 5.

Design Electrical Rating (Net MWe): 1065 6.

Mauimum Dependable Capacity (Gross MWe): 1098.4 7.

Maximum Dependable Capacity (Net MWe): 1065 If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since last Report, Give Reasons:

8.

N/A 5

9.

Power Level To Which Restricted, If Any (Net MWe):

N/A

10. Reasons Fcr Restrictions, If Any:

N/A This Month

" -to-Date Cumul ati ve

11. Hours in Reporting Period 744 5037 12635)
12. Number of Hours Reactor Was Critical 0

0 45603

13. Reactor Reserve Shutdown Hours 0

0 5150

14. Hours Generator On-Line 0

0 44195

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 0 0

131868267

17. Gross Electrical Energy Generated (MWH) 0 0

43473760

18. Net Electrical Energy Generated (MWH)

-1705

-11259 41961277 0

0 35.0

19. Unit Service Factor 0

0 35.0._

20. Unit Availability Factor
21. Unit Capacity Factor (Using MDC Net) 0 0

31.2

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

31.2 100 100 59.7

23. Unit Forced Outage Rate
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

l N/A To be determined

25. If Shut Down At End Of Report Period, Estimated Date of Startep:

0449k/13

DOCKET NO:

50-259 te4IT NAME:

Qng UNIT SHUTDOWNS AND POWER REDUCTIONS PREFARED BY:$. A. Ra,11iff REPORT NDNTH:

July 1991 TELEPHONE:(205) 729 293Z

! Method of

! Licensee Cause and Corrective !

Action to

! Duration !

! Shutting Down ! Event

! Systgm

!Compgnent!

3

! Report No.

.! Code'

! Code Prevent Recurrence j

2

! Reactor

! No.

! Date

! Type

! (Hours) ! Reason

! 315

! 05/01/85 !

F

! 744 F

4

! Administrative hold to !

! resolve varicus TVA and !

! NRC concerns.

dExhibit G-Instructions 3 Method:

I - Fcreed 2

F Reason:

for Preparation of Data S: Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual 5: ram Entry sheets for Licensee Event Report (LER) File C-Refueling 3, Automatic Scram 4-Continuation of Existing Outage (NUREG-051)

D-Regulatory Restriction E-Operator Training and License Examination 5-Reducti on F-Administrative 9-Other SExhibit I-Same Source G-Operational Error (Explain)

H-Other (Explain) r 0449k

DOCKET f:3:

50-260

^

UNIT SHUT 00WNS AND POWER REDUCTIONS UNIT NAME:

Two

+

COMPLETED BY:5. A. Ratliff REPORT MONTH:

July 1991 TELEPHONE:(205) 729-2937 l-

! Method of

! Licensee Cause and Corrective !

! Duration !

! Shutting Down ! Event

!Systy

!Compgnent!

Action to

! No.

! Date

! Type

! (Hours) ! Reason 2 l

! Reactor 3

! Report No.

! Code

! Code Prevent Recurrence

! 4 107/01/91 '!

S

! 1.25 B

1

! Turbine trip test

'l

! 5

!O7/01/91.!

5

! 1.83 B

1

! Turbine trip test l'

I IF: Forced 2 Reason:

3 Method:

  1. xhibit G-Instructions E

5: Scheduled

- A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Nanual Scram Entry sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continuation of Existing Outage (NUREG-051)

E-Operator Training and License Examination 5-Reduction F-Administrative 9-Other SExhibit I-Same Source G-Operational Error (Explain)

. H-Other (Explain) 0449k r

I t

i

00CPET tJ0:

50-296 UNIT SHUTDOWNS AND POWER REDUCTIONS

  • "'!'i NAME:

Three C0t*LETED BY:$1_A. Ratliff

^ 5LEPHONE:(2050 729-29311 REPORT MONTH:

June 1991 6

t I

! Method of-

! Licensee.

Cause and Corrective !

! Duration ! '

! Shutting Down ! Event

!Systgm

! Corpgnent !

Action to

! No, 1 Date

! Type)

! (Hours) ! Reason 2

! Reactor.

! Report No.

! Code

! Code Prevent Recurr2nce 3

1

! 157

! 03,93/85 !

F

! 744 F

4

! Administrative hold to !

! resolve various TVA and !

.! NRC concerns.

4 I: Forced 2 Reason:

3 Method:

Erhibit G-Instructions F

S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continuation of Existing Outage (NUREG-061)

E-Operator Training and License Examination 5-Reduction F-Administrative 9-Other SEnhibit I-Same Source G-Operational Error (Explain)

H-Ottar (Explain) 0449k/33 h

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4-0 ENCLOSURE 2

.___.__E_____'m_'__.___ _ _ _ _ _ _ _ _. _ _. _. _ _ _. _ _ _ _ _ _ _ _ _ _

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DOCKET NO:

50-%k0 UNIT NAME:

Two UNIT SHUTDOWNS AND POWER REDUCTIONS EOMPLETED BY:5. A. Ratliff REPORT HONTH:

June 1991 TELEPHONE:(205) 729-2917

! Method of

! Licensee Cause and Corrective !

! Duration !

! Shutting Down ! Event

! System

! Component !

Action to

! No.

! Date

! Type

! (Hours) ! Reason

! Reactor

! Report No.

! Code

! Code 5 Prevent Recurrence l

2 3

4

! 1 109/15/84 ! F

! 644.7 8

4

! Power ascension testing !

! and training

! 2 106/28/91 ! 5 1

6.8 8

1

! Controlled shutdown for !

! turbine balancing 7

! 3 106/28/91 ! 5

! 52.9 B

1

! Power ascension

! testing program 4 Exhibit G-Instructions 3Hethod:

2 IF: Forced Reason:

for Preparation of Data 1-Manual 5: Scheduled A-Equipment failure (Explain)

Entry sheets for Licensee 2-Manual Scram B-Maintenance or Test Event Report (LER) File 3-Automatic Scram C-Refueling 4-Continuation of Existing Outage (NUREG-061)

D-Regulatory Restriction E-Operator Training and License Examination 5-Reduction 9-Other F-Admiristrative SEnhibit I-Same Source G-Operational Error (Explain)

H-Other (Explain) 0449k

_ _ _ _ -