ML20202G482

Monthly Operating Repts for Jan 1998 for Browns Ferry Nuclear Plant

ML20202G482
Person / Time
Site:	Browns Ferry
Issue date:	01/31/1998
From:	Abney T, Davenport J TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9802200138
Download: ML20202G482 (13)

Text

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MA.

Tev,mee Vawy A#.dedy Pou ON p Don m Deayr A rita+a M fM February 13, 1998 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) - JANUARY 1998 MONTHLY OPERATING REPORT The enclosure provides the January 1998 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.

S',ncerely,

/ r l

T. E. nef Manager o- Licenting and Ind1stry Afifairs Enclosure cc: See page 2 9002200138 980131 PDR ADOCK 05000259 R PDR v' g l

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, U.S. Nuclear Regulatory Commission

! Page 2

• j February 13, 1998 l l  ?

Enct '~ '

cc Snciosure):

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

-Region II 61 Forsyth Street, S.W.

Suite 23T85 ,

f Atlanta, Georgia 30303 i

Mr. Frederick J. Hebdon, Director i Project Directorate II-4 Division of Reactor Projects I-II Office of Nuclear Reactor Regulation, Mail 13 H3 4

Washington, D.C. 20555 .

l INPO Records Center Institute of Nuclear Power Operations 700 Galleria Parkway

, Atlanta, Georgia 30339-5957 i r i Mr. James Lang, Manager Advanced Reactor Department Electric Power Research Institute 3340 Hillview Avenue -

l Palo Alto, California 94304 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road -

Athens, Alabama 35611

! Regional Administrator U.S. Nuclear Regulatory Commission Region II 61 Forsyth Street, S.W.

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

Suite 1100

' Washington, D.C. 20005-3802

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ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

MONTHLY OPERATING-REPORT l

JANUARY 1998 -

l l

UNIT 1 DOCKET NUMBER 50-259 m

LICENSE NUMBER DPR-33 UNIT 2 DOCKET NUMBER 50-260 LICENSE NUMBER DPR-52 UNIT 3 DOCKET NUMBER 90-296 LICENSE NUMBER DPR-68

4 OPERATIONAL SUWARY JANUARY 1998 BROWNS FERRY NUCLEAR PLANT UNIT 1 Unit 1 remains shutdown on administrative hold to resolve various TVA and NRC cancerns. 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 mar.imum i 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 January, Unit 2 generated 829,730 megawatt hours gross electrical power and operated at a net capacity factor of 102.4 percent. As of January 31, 1998, Unit 2 has operated continuously for 94 days.

BROWNS FERRY NUCLEAR PLANT UNIT 3 For the month of January, Unit 3 generate'd ~!723150 megawatt hours gross electrical power with a net capacity factor of 95.2 percent. As of January 31, 1998, Unit 3 has cperated-continuously for 324 days.

El L-A&-

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-259 UNIT NO. ONE DATE: Feb. 15, 1998 COMPLETED BY: J. W. Davenport TELEPHONE 205-729-2690 MONTH January 1998 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL l DAY (MWe-Not) DAY (MWe-Ne t)

1. 0 17 O e

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

16. 0 E2

• c 4

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-260 UNIT NO. TWO DATE: Feb. 15, 1998 COMPLETED BY: J. W. Davenport TELEPHONE 205-729-2690 MONTH January 1998 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY DAY (MWe-Ne t ) (MWe-Net)

1. 1088 17, 1094

2. 1085 18. 1092

3. 1083 19. 1094

4. 1085 20. 1088

5. 1092 21, 1091

6. 1090 22, 1092 7, 1089 23, 1096

8. 1084 24. 1096

9. 1097 25. 1092

10. 1097 26, 1093

11. 1092 27 1093 12 1090 28. 1086

13. 1096 29. 1094

14. 1093 30. 1088 15, 1088 31. 1095

16. 1088 E3

p 4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-296 UNIT NO. THREE DATE: Feb. 15, 1998 COMPLETED BY: J. W. Davenport TELEPHONE 205-729-2690 MONTH January 1998 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY DAY (MWe-Net) (MWe-Net)

1. 1083 17, 1050

2. 1078 18. 1072

3. 1074 19. 1087

4. 1079 20, 664 5, 1075 21. 692

6. 1099 22. 842 7, 1081 23. 944 8, 1081 24, 1022

9. 1065 25. 880

10. 1023 26, 791 11, 1063 27, 953 12 1077 28. 1054 13, 1087 29, 1047 14, 1090 30, 1077

15. 1085 31, 1067

16. 1051 E-4

} Ol'ERATING DATA REPORT Docket No. 50 2$9

Date

Eclamtv15.1998 j Completed By: J W. Davenp.pt Telephone: 205 729 2690 i I, Unit Name: ilFN linit 1

2. Reporting Period: .lanua:V 1998 i

3. Licensed Thermal Power (htWt): 3293

4. Nameplate Rating (Gross hiwe): 1152

5. Design Electrical Rating (Net h1we): 1065

6. hiaximum Dependable Capacity (Gross hiWe): 0

7. hiaximum Dependable Capacity (Net htWe): 0

+

4

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 htWe): 0 i

! 10. Reasons for Restrictions, if any: Administrative lloid i

This Month Yr-To Date Cumulative a

11. 1-lours in Reporting Period 0 0 95743

12. Number ofilours Reactor was Critical 0 0 59521

13. Reactor Reserve Shutdown 11ours 0 0 6997

14. Ilours Generator On Line 0 0 58267 15, Unit Reserve Shutdown llours 0 0 0

16. Gross Thermal Energy Generated (h1Wh) 0 0 168066787 17, Gross Electric Energy Generated (h1Wh) 0 0 55398130

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

19. Unit Service Factor 0 0 60.9 l

20. Unit Availability Factor 0 0 60.9

21. Unit Capacity Factor (Using h1DC Net) 0 0 52.8

22. Ur.it Capacity Factor (Using DER Net) 0 0 52.8

23. Unit Forced Outage Rate 0 0 25,6 24; Shutdowns Scheduled Over Next 6 hionths (Type, Date, and Duration of Each)

N/A

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

• Excludes hours under Administrative lloid (June I,1985 to present)

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4 >

e OPERATING DATA REPORT Docket No. 10 260 Date: Echtuary 15.1998

Completed By

J. W. Davenpar1 Telephone: 205 729 2600

l. U& Hene: ilFN Iinit 2

2. Reporting /eriod: January 1998

3. Licensed Ttuac I!'ower (MWt): 219J

4. Nameplate keing (GK :s Mwe): J lf1

5. Design Electrical Rati,q;(Net Niwe): )o65

6. hiaximum Dependable Capacity (Gioss h1We): 1098.4

7. hiaximum Dependable Capacity (Net h1We): 1065

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

9. l'ower Level To Which R<. rtricted, if any (net htWe)

N/A

10. Reasons for Restrictions, if any: N/A This Slonth Yr-To-Date Cumulative *

11. Ifours ;n Reporting I'niod 744,0 744,0 149119

12. Number ofilours Reactor was Critical 744.0 744,0 107550

13. Reactor Reserve Shutdown 11ours 0,0 0.0 14200 4

14. Ilours Generator On-l.ine 744,0 744,0 105157 i

15. Unit Reserve Shutdown lleurs 0.0 0.0 0

16. Gross Thermal Energy Generated (htWh) 2448312,0 2448312 312483796

17. Gross Electric Energy Generated (htWh) 829730,0 829730 103832208

18. Net Electrical Energy Generated (h1Wh) si 1684,0 811684 101017775

19. Unit Service Factor 100.0 100,0 70,5

20. Unit Availability Factor 100.0 100.0 70.5

- 21. Unit Capacity Factor (Using htDC Net) 102.4 102,4 63,6

22. Unit Capacity Factor (Using DER Net) 102.4 102.4 63.6

'3. Unit Forced Octage Rate 0,0 0,0 14.0

24. Shutdowns Scheduled Over Next 6 hionths (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 lloid pune I,1985 to Stay 24,1991)

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OPERATING DATA REPORT Docket No. 50-290 Date: Februan'-15.1998 Completed By: J W. Davenpnn Telephone: 294.729 2690

1. Unit Name: liFN linit 3

2. Reporting Period: .lanuary 199H

3. Licensed Thermal Power (hiWt): 3293

4. Nameplate Rating (Gross hiwe): 1152

$. Design Electrical Rating (Net htwe): In65

6. hiaximum Dependable Capacity (Gross htWe): 1098.4

7. hiaximum Dependable Capacity (Net htWe): 1065

8. If changes Occur in Capacity Rating (l tem Numbers 3 Through 7) Since Last Report, Give Reasons: N/A 9 Power Level To Which Restricted, if any (net hlWe): N/A

10. Reasons for Restrictions, if any: N/A Thk Slonth Yr-To Date Cumulative *

11. llours in Reporting Period 744.0 744,0 92341

12. Number ofilours Reactor was Critical 744.0 744.0 63818

13. Reactor Resene Shutdown llours 0.0 0.0 5150

14. llours Generator On Line 744.0 744.0 62465

15. Unit Reserve Shutdown llours 0.0 0.0 0

16. Gross Thermal Energy Generated (h1Wh) 2299704.0 2299704 189734617

17. Gross Electric Energy Generated (htWh) 772150.0 772150 63535560

18. Net Electrical Energy Generated (h1Wh) 754399.0 754399 60959896

19. Unit Senice Factor 100.0 100.0 67.6

20. Unit Availability Factor 100.0 100.0 67,6

21. Unit Capacity Factor (Using h1DC Net) 95.2 95.2 62.0

22. Unit Capacity Factor (Using DER Net) 95.2 95.2 62,0

23. Unit Forced Outage Rate 0.0 0.0 16.5

24. Shutdowns Scheduled Over Next 6 hionths (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 lloid

(. lune 1,1985 to November 19,1995)

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UNITSIIUTDOWNS AND POWER REDUCTIONS -

REPORT 310 NTH: JANUARY 1995 DOCKET NO: 50-259 UNIT NA31E: BFN-1 DATE: February 15.1998 i CO31PLETED BY: J. W. Davenport

. TEllPilONE: (205) 729-2690 2

No. Date Type' Duration Reason Method of Licensee Systems Coenponent Cause and Corrective Action to Prevent (Hours) Shutting Event Report Code' Code' Itecurrence 4 Down- No.

) Reactor >

I 1 06/01/85 S 744 F 4 N/A N/A N/A Admirdstrative hold to resolve various TVA and NRC concerns.

}

i i

i 2

' F

Forced Reason:

• Method

• Exhibit G - Instructions for (NUREG

S

Scheduled A-Equipment Failure (Explain) 1-h!anual Preparation of Data Entry Acets j B-htaintenance or Test 2-htanual Scram for Licenere Escat Rcrert (LER)

C-Refueling 3-Automatic Scram File - NUREG - 1822 l D-Regulatory Restriction 4-Continuation of Existing E-Operator Training and License Outage Examination 5-Reduction ' Eskihis I-Sanee Source I

F-Administrative 9-Otler G-Operational Error (Explam) ,

i II-Othcr (Explain) j r

i E-3 l

1 . .

m _ _ ___ _. . __

.. i

]

. i UNIT SHUTDOWNS AND POWER REDUCTIONS

} REPORT MONTH: JANUARY 1998

] .  !

l DOCKET NO: 50-260  !

l UNIT NAME: BFN-2  ;

j DATE: February 15,1998 i COMPLETED BY: J. W. Davenport i TELEPHONE: (205) 729-2690  !

! Nr. Date . Type'. Duration Reason *_ Method of Licensee System Component Cause med Corrective Action to Prevent [

] (Hours) _ Shutting Event Report Code' Code' Recurrence l

Down No.

Reacto/

4 I

I N/A i

p I

4 5

I 2

j ' F: Forced Reason:

• Method

• Exhibit G - Ingractions for (NUREG S: Scheduled A-Equipment Failure (Explain) 1-Manual Preparation of Data Entry hs f;

j B-Maintenance or Test 2-Mamsal Scram for Licensee Escat Report (LER)

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

I li-Other (Explain) ,

l i E-9  ;

f l

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: JANUARY 1995 DOCKET NO: 50-296 UNIT NAME: BFN-3 DATE: February 15.1998 COMPLETED BY: J. W. Davenpott TELEPHONE: (205) 729-2690 2

Nr. Date Type' Duration Reason Method of Licensee Systesu Cosuponent Cause med Corrective Action to Prevent (Hours) Shutting Event Report Cod / Code Recurrence Down . No.

Reacteed-1 01/20/98 S 0 B 5 N/A N/A N/A Power reduction for maintenance and testing.

2 01/25/98 S 0 B 5 N/A N/A N/A Power reduction . CRD testing.

I

' F: Forced

• Reason: ' Metland

• Eshibit G - Instractions for (NUREG 5: Scheduled A-Equipment. Failure (Explain) I-htanual Preparation of Data Entry sJacets B-htaintenance or Test 2-Manual Scram for Licenwe Event Report (LER)

C-Refueling 3-Automatic Scram File- NUREG - 1922 D-Regulatory Restriction 4-Continuation of Esisting E-Operator Training and License Outage Examination 5-Reduction ' Eskihit I-Same Semere F-Administrative 9-Other G-Operational Error (Esplain)

II-Other (Explain)

E-10

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