ML20210V033

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Monthly Operating Repts for Aug 1997 for BFN
ML20210V033
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 08/31/1997
From: Abney T, Davenport J
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9709230009
Download: ML20210V033 (13)


Text

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Tennessee Valley AuthoMy, Pos.t Offce Box 2000 Decatur, AJatwnsA3' M2000 September 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) - AUGUST 1997 MONTHLY OPERATING REPORT The enclosure provides the August 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.

S ncerely

. E. Ib Manager of Lip.erts ng .

and Indus ry Af airs

{[ b. Y.

Enclosure I cc: See page-

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U.S. Nuclear Regulatory Commission Page 2 September 15, 1997 Enclosure cc (Enclosure).

Mr. Mark S. Lesser, Branch Chief U. S. Nuclear Regulatori 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 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 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 l

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6 ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

MONTHLY OPERATING REPORT AUGUST 1997 UNIT 1 DOCKET NUMBER 50-259 LICENSE NUMBER DPR-33 UNIT 2 DOCKET NUMBER 50-260 LICENSE NUMBER DPR-52 UNIT 3 DOCKET NUMBER 50-296 LICENSE NUMBER DPR-68 l

, OPERATIONAL SUl44ARY AUGUST 1997 BROWNS FERRY NUCLEAR PLANT UNIT 1 Unit 1 remains shutdown on administrative hold to resolve various TVA and NRC concerns. Unit I 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 August, Unit 2 generated 785,400 megawatt hours gross electrical power and operated at a net capacity factor of 96.7 percent. The unit began its " coast down" on August 17, 1997, at 23:40 hours, for the cycle 9 refueling outage scheduled to begin on September 26, 1997. As of August 31, 1997, Unit 2 has operated continuously for 126 days.

BROWNS FERRY NUCLEAR PLANT UNIT 3 For the month of August, Unit 3 generated 803,170 megawatt hours gross electrical power with a net capacity factor of 98.9 percent. As of August 31, 1997, Unit 3 has operated continuously for 171 days.

E1

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-259 UNIT NO. ONE DATE: Sept. 15, 1997 COMPLETED BY: J. W. Davenport TELEPHONE 205-729-2690 ,

I MONTH August 1997 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net) DAY (MWe-Net)

1. 0 17 0
2. 0 18. 0
3. 0 19. - 0
4. 0 20. O i
5. 0 21. 0 l 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 E-2

1 l . .

4 j AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-260 ONIT NO. TWO DATE: Sept. 15, 1997 l

l COMPLETED BY: J. W. Davenport TELEPHONE 205-729-2690 I 1

j MONTH August 1997 l i

l  !

AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL l I DAY L . DAY . (HWe-Ne t) (MWe-Net) l 1. 1058 17, 979

2. 1044 18. 1010 l _

j 3. 1054 19. 1068

4. 1040 20. 981 l S. 1050 21. 1061 i

i 6. 1049 22. 973 i

7. 1048 23. 1022

{

8. 1050 24. 1034

! 9. 1058 25. 1023

)

i 10. 1030 26. 1022 i

l 11. 994 27 1007 1

l_ 12 -1041 28. 1016  ;

i j 13. 1040 29, 1000 14, 1052 30. 996 l 15. 1057 31. 991

16. 1068 e

i 4

J J

j E4-

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-296 UNIT No. THREE DATE: Sept. 15, 1997 COMPLETED BY: J. W. Davenport TELEPHONE 205-729-2690 MONTH August 1997 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY DAY (HWe-Net) (MWe-Net)

1. 1037 17. 1016 2, 1054 18. 1059
3. 1053 19. 1068 s
4. 1048 20. 1077
5. 1058 21, 1077
6. 1055 22, 1014
7. 1054 23. 1060 8, 1057 24. 1062
9. 1068 25. 1062
10. 1061 26, 1066
11. 1064 27, 1059 12 1068 28, 1060
13. 1065 29. 1053
14. 1065 30. 1062
15. 1030 31, 1054
16. 950 E-4

e OPERATING DATA REPORT Docket No. 50-259 Date: SIPlcmbsLIS.1997 Completed Ily: 1 W. DavenMt1 Telephone: 205-729 2690

1. Unit Name: IIFN Unit 1
2. Reporting Period: Aunust 1997
3. Licensed Thermal Power (htWt): 3293
4. Nameplate Rating (Gross hiwe): ,lJ,jg,
5. Design Electrical Rating (Net h1we): 1065
6. hiaximum Dependable Capacity (Gross htWe): 9
7. hiaximum Dependable Capacity (Net h1We): 2
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 h1We): 0
10. Reasons for Restrictions, if any: Administrative lloid This Month Yr-To-Date Cumulative *
11. llours in Reporting Period 0 0 95743
12. Number ofliours Reactor was Critical 0 0 59521
13. Reactor Reserve Shutdown llours 0 0 6997
14. l{ours Generator On Line 0 0 58267
15. Unit Reserve Shutdown llours 0 0 0
16. Gross Thermal Energy Generated (hiWh) 0 0 168066787
17. Gross Electric Energy Generated (htWh) 0 0 55398130
18. Net Electrical Energy Generated (htWh) 0 0 53796427
19. Unit Service Factor 0 0 60.9

, 20. Unit Availability Factor 0 0 60.9

21. Unit Capacity Factor (Using h1DC 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 hionths (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 lloid (June 1,1985 to present)

E5

OPERATING DATA REPORT Docket No. 50-260 Date: Ssniember 15.1997 Completed By: J W. Daven.ppli Telephone: 205 729 2690

1. Unit Name: HFN Unit 2
2. Reporting Period: Aunust 1997
3. Licensed Thermal Power (htWI): 2291 9
4. Nameplate Rating (Gross hiwe): JL1 S. Design Electrical Rating (Net hiwe): 1065
6. hiaximum Dependable Capacity (Gross h1We): 1098.4
7. hiaximum Dependable Capacity (Net htWe): 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 h1We): N/A
10. Reasons for Restrictions, if any: N/A This Month Yr-To Date Cumulative *
11. Ilours in Reporting Period 744,0 5831.0 145446
12. Number ofIlours Reactor was Critical 744.0 5773.0 104422
13. Reactor Reserve Shutdown flours 0.0 0.0 14200
14. Hours Generator On Line 744.0 5768.0 102050
15. Unit Reserve Shutdown Hours 0.0 0.0 0
16. Gross Thermal Energy Generated (htWh) 2430312.0 18503400 302690500
17. Gross Electric Energy Generated (h1Wh) 785480.0 6147660 100569028
18. Net Electrical Energy Generated (hiWh) 765924.0 5999489 97832655 19 Unit Sersice Factor 100.0 98.9 70.2
20. Unit Availability Factor 100.0 98.9 70.2
21. Unit Capacity Factor (Using hiDC Net) 96.7 96.6 63.2
22. Unit Capacity Factor (Using DER Net) 96.7 96.6 63.2
23. Unit Forced Outage Rate 0.0 1.1 14.3
24. Shutdowns Scheduled Over Next 6 hionths (Type, Date, and Duration of Each): Unit 2 Cycle 9 Refueling Outage, Scheduled to begin 9/26/97, 21 days duration 25, if Shutdown at End of Report Period, Estimate Date of Startup: N/A
  • Excludes hours under Administrative lloid (June 1,1985 to May 24,1991)

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OPERATING DATA REPORT Docket No. 50 296 Date: September 1 S.1997 Completed By: J. W. Davenport Telephone: 205-729 2690

1. Unit Name: HFN Unit 3
2. Reporting Period: Aunust 1997
3. Licensed Thermal Power (htWt): 3293
4. Nameplate Rating (Gross htwe): ,1,1,5J
5. Design Electrical Rating (Net hiwe): 1965
6. hiaximum Dependable Capacity (Gross hiWe): 1098.4
7. hiaximum Dependable Capacity (Net hiWe): 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 hiWe): N/A
10. Reasons for Restrictions, if any: N/A This Month Yr-To-Date Cu'nulative*
11. liours in Reporting Period 744.0 5831.0 88668
12. Number ofliours Reactor was Critical 744.0 5391.0 60145
13. Reactor Reserve Shutdown 11ours 0.0 0.0 5150
14. liours Generator On Line 744,0 5373.2 58792
15. Unit Reserve Shutdown liours 0.0 0.0 0
16. Gross Thermal Energy Generated (htWh) 2432592.0 16696248 177926905
17. Gross Electric Energy Generated (htWh) 803170.0 5546750 59570890
18. Net Electrical Energy Generated (htWh) 783263.0 5405725 57087856
19. Unit Service Factor 100.0 92.1 66.3
20. Unit Availability Factor 100.0 92.1 66.3
21. Unit Capacity Factor (Using hiDC Net) 98.9 87.0 60.5
22. Unit Capacity Factor (Using DER Net) 98.9 87.0 60.5
23. Unit Forced Outage Rate 0.0 0.0 17.4
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 (June 1,1985 to November 19,1995)

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UNIT SHUTDOWNS AND POWER REDUCTIONS REPORTMONTH: AUGUST 1997 ,

DOCKET NO: 50-259 UNIT NAME: BFN-1 DATE: September 15,1997 COMPLETED BY: 1 W. Davenport TELEPHONE: (205)'5!9-2690 No. .. . Date - Type' Deration Ressen: Method of Licensee Systems Consposest rame and Cervertive Action to Prevent -

(Heers) Shutting Event Report Code' Code' Recorrence Dews No.

Reacte/

F 4 N/A N/A N/A Adusnigrative hold to resolve v irious TVA I 06/01/85 S 744 and NRC concerns i

l l

l

' F: Forced 2

Reason: ' Method

  • Exhitut G - lastnsctises for (NUREG A-Equipment Failure (Explain) 1-Marst Preparation of Data Entry shcets S: Scheduled B-Maintenance or Test 2-Manual Scram for Licensee Event Report (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-Sasse Seurte F-Administrative 9-Other G-Operational Error (Explain)

H-Other (Explain)

E-8

UNITSHUTDOWNS AND POWER REDUCTIONS _

REPORTMONTH: AUGUST 1997 .

DOCKET NO: 50-260 UNIT NAME: BFN-2 DATE: September 15,1997 COMPLETED BY: L W. Davenport TELEPHONE: (205) 729-2690 No. Date . Type' . Duration Reason 2

Method of LL x; Systesu Cr;z : Cause and Corrective Acties to Prevent 5

Shatting Event Repost Code' Code- Recurrence (Hours)

Down No. .

Reacto/

N/A l

1 i

  • F: Forced 2

Reason: ' Method

  • Exhiint G -Instructions for (NUREG A-Equipment Failure (Explain) 141anual Preparatism of Data Entry sheets S: Scheduled B41aintenance or Test 2-htanual Scram for Ucensee Esent Report (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-Sasse Source F-Administratiu: 9-Other G-Operational Error (Explain)

H-Other (Explain)

E-9

UNITSHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: AUGUST 1997 .

DOCKET NO: 50-296 UNIT NAME: BFN-3 DATE: September 15,1997 COMPLETED BY: J. W. Davenport TELEPHONE: (205) 729-2690 No. = Date . Type'. Duration . Reason 2

Method of Th Systema CesoponesW Cause and Corrective Acties to Prevent Shatting Event Reper. Code'. - Code' Recurrence (Hears)

Down No. -

ReactM N/A I

' F: Forced

  • Reason:
  • Method
  • Exhibit G- lastructions for (NUREG A-Equipment Failure (Explain) 14tanual Preparation of Data Entry sheets S: Scheduled B-Maintenance orTest 24tanual Scram for Licemwe Event Report (LER)

C-Refueling 3-Automatic Scram File- NUREG - 1922 D-Pegulatory Restriction 4-Continuation of Edsting E-Operator Training and License Outage Examination 5-Reducuon ' EsheM I-Saane Soorre F-Adminis: %r 9-Otirr G-Operationa! Error (Explain)

II-Other(Eylain)

E-10

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