ML20203J708

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Monthly Operating Repts for Nov 1997 for Browns Ferry Nuclear Plant,Units 1,2 & 3
ML20203J708
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 11/30/1997
From: Abney T, Davenport J
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9712220048
Download: ML20203J708 (13)


Text

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. ng Tennessee Valley Authcrity, Post Office 804 2000, Decator. Alabama 35609 December 12, 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 Authe !.ty

)

50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - NOVEMBER 1997 MONTHLY OPERATING REPORT The enclosure provides the November 1997 Monthly Operating Report as required by BFN Technical Specifications Section 6.9.1.3.

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

S ncerel,

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he and I ustry Affa rs 3

A.I ') n

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Manager of M censitg 7

c Enclosur cci See pa e--2 /

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9712220048 97113')

PDR.ADOCK 05000259 R

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U.S. Nuclear Regulatory Commissi i.

Page 2 December 12, 1997 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 Office of Nuclear Reactor Regulation, Mail 13 H3 Washington, D.C.

20555 INPO Records Center Instituce 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 Companiec 1200 G Street,.N.W.

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

ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN) d MONTHLY OPERATING REPORT NOVEMBER 1997 UNIT 1 DOCKET NUMBER 50-259 LICENSE NUMBER DPR-33 UNIT 2 DOCKET NUMBER 50-260 LICENSE'h0MBER DPR-52 UNIT 3 DOCKET NUMBER 50-296

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LICENSE NUMBER'DPR-68

OPERATIONAL

SUMMARY

NOVEMBER 1997 BROWNS FERRY NUCLEAR PLANT UNIT 1 Unit i remains shutdown on administrative nold 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 3

of reporting hours is suspended since the unit has a maximun.

6ependable capacity of zero MNe.

Accordingly, TVA does not consider reporting cumulative hours for the period beginning June 1, 1985, when calculhting the operating st'atus variable..

BROWNS FERRY NUCLEAR PLANT UNIT 2 For the month of November, Unit 2 generated 794,210 megawatt hours gross electrical power and operated at a net capacity

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factor of 101.3 percent.

As of November 30, 1997, Unit 2 has operated contir.uously for 32 days.

R O

BROWNS FERRY NUCLEAR PLANT UNIT 3 For the month of November, Unit 3 generated 787,210 megawatt hours-gross electrical power with a net capacity factor of 100.3 percent.

As of November 30, 1997, Unit 3 has operated continuously for 262 days.

'E E-l

4 AVERAGE DAILY UNIT POWER LEVEL 4

DOCKET NO.

50-259 UNIT NO.

ONE DATE:

Dec. 15, 1997 COMPLETED BY:

J. W. Davenport TELEPIIONE 205-729-2690 MONTH November 1997 h

AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL E

DAY (MWa-Net)

DAY (MWe-Net) s 1.

0 17.

0 2.

0 18.

O K

3.

0 19.

0 4.

0 20.

O i

I 5.

0 21.

0 6.

0 22.

0 7.

0 23.

0 8.

0 24.

0 9.

0 25.

O a

10.

0 26.

0 11.

0 27.

0 12 0

28.

0 13.

0 29.

0 14.

0 30.

0 15.

0 16.

O I

E-2

1 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-260 UNIT NO.

TWO DATE:

Dec. 15, 1997 COMPLETED BY:

J. W. Davenport TELEPHONE 205-729-2690 MONTH November 1997 AVERAGE C3ILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY DAY (MWe-Net)

(MWe-Net) 1.

1057 17.

1086 2.

1059 18, 1093 3.

1057 19, 1088 4.

1091 20.

1084 5.

1091 21.

1099 6.

1092 22.

1087 7,

983 23.

1092 8.

1054 24, 1089 9.

964 25.

1091 10, 1090 26.

1092 11.

1087 27.

1090 12 1091 28.

-1099 13.

1093 29.

1092 14.

1104 30.

1091 15.

1087 16.

1086 E-3

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-296 UNIT NO.

THREE DATE:

Dec. 15, 1997 COMPLETED BY:

J. W. Davenport TELEPHONE 205-729-2690 MONTH November 1537 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY DAY (MWe-Net)

(MWe-Net) 1.

1065 17, 1085 2.

1054 18, 1091 3.

1051 19.

1077 4.

1072 20.

1083 5.

1072 21, 1099 6.

1071 22.

995 7.

983 23, 1073 8.

1016 24.

1089 9.

1066 25.

1086 10.

1087 26; 1090 11.

1089 27, 1088 12

-1084 28.

1098

-13.

1083 29.

1048 14.

1098 30.

1057 15.

-1047 16.

1052 E-4

OPERATING DATA REPORT Docket No.

50-259 Date:

December 15.1997 Completed By:

J. W. Davenport Telephone:

205-729-2690 1-Unit Name:

BFN Unit 1 2.

Reporting Period:

November 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 cbmges 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 lloid Ihis 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 Hot.rs 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 Faaor (Using MDC Net) 0 0

52.8 22.

Unit CapaS:y 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 !!old a

(June 1,1985 to present)

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OPERATING DATA REPORT Docket No.

50-260 Date:

December 15.1997 Completed By:

J. W. Davenno.t Telephone:

205-729-2690 1.

Unit Name:

HFN Uni; 2 2.-

Reporting Period:

November 1997 3.

Licensed Thermal Power (h1Wt):

3293 4.

Nameplate Rating (Gross hiwe):

1152 5.

Design Electrical Rating (Net hiwe):

1065 6.

hiaximum Dependable Capacity (Gross h1We):

1098.4 7.

hiaximinn Dependable Capacity (Net htWe):

1065 8.

If changes Occur in Capacity Rating (1:em Numbers 3 Through 7) Since Last Report, Give Reuons: N/A 9.

Power Level To Which Restricted, if any (net h1We): N/A 10.

Reasons for Restrictions, if any: N/A This 51onth Yr-To-Date Cumulative

  • 11.

Hours in Reporting Period 720.0 8016.0 147631 12.

Number of Hours Reactor was Critical 720.0 7413.0 106062 13.

Reactor Reserve Shutdown Hours 0.0 0.0 14200 14.

Hoiirs Generator On-Line 720.0 7386.9 103669 15.

Unit Reservc Shutdown Hours 0.0 0.0 0

16.

Gross Thermal Energy Generated (h1Wh) 2351952.0 23400960 307588060 17.

Gross Electric Energy Generated (hiWh) 794210.0 7752060 102173428 18.

Met Electrical Energy Generated (h1Wh) 776582.0 7562627 99395792 19.

Unit Service Factor 100.0 92.1 70.2 20.

Unit Availability Factor 100.0 92.1 70.2 21.

Unit Capacity Factor (Using AfDC Net) 101.3 88.6 63.2 22.

Unit Capacity Facter (Using DER Net) 101.3 88.6 63.2 23.

Unit Forced Outage Rate 0.0 1.4 14.2 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 ho' irs under Administrative lloid (June 1,1985 to Stay 24,1991)

E-6

OPERATING DATA REPORT Docket No.

59d96 Date:

December 15.1997 Completed By:

J. W. Davenoort Telephone:

205-729-2690 1.

Unit Name:

HFN Unit 3; 2.

Reporting Period:

November 1997 3.

Licensed Thermal Power (MWt):

3293 4

Nameplate Fating (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 Nembers 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 i

This Month Yr-To Date Cumulative

  • 11.

Honts in Reporting Period 720.0 8016.0 90853 12.

Number of Hours Reactor was Critical 720.0 7576.0 62330 13.

Reactor Reserve Shutdown Hours 0.0 0.0 5150 14.

Hours Generator On-Line 720.0 7558.2 60977 15.

Unit Reserve Shutdown Hours 0.0 0.0 0

16.

Gross Thermal Energy Generated (MWh) 2335752.0 23775432 185006089 17 Gross Electric Energy Gererated (MWh) 787210.0 7918410 61942550 i

18.

Net Electrical Energy Generated (MWh) 769202.0 7721347 59403478 19.

Unit Service Factor 100.0 94.3 67.1 20 Unit Availability Factor 100.0 94.3 67.1 21.

Unit Capacity Factor (Using MDC Net) 100.3 90.4 61.4 3

22.

Unit Capacity Factor (Using DER Net) 100.3 90.4 61.4 23.

Unit Forced Outage Rate 0.0 0.0 16.9 24.

Shutdowns Scheduled Over Nex; 6 Months (Type, Date, and Duration of Eacl.). N/A 25.

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

  • Excludes hours ander Administrative Hold (June 1,1985 to November 19,1995)

E-7

I UNIT SIIUTDOWNS AND POWER REDUCTIONS REPORT MONTil: NOVEMBER 1997 DOCKET NO:

50-259 UNIT NAME:

BFN-1 DATF:

December 15,1997 COMPLETED BY: J W. Davenport TELEPIIONE:

(205) 729-2690 Na

~ Date..

Type' Duration Reason

  • Metho I of.

System Component Cause and Corrective Action to Prevent Licensee -

5 L, (flours)

Sinutting Event Report Code' Code Recurrence Down'

' No.

3 Reactor 1

06/01/85 S

720 F

4 N/A N/A N/A Administrative hold to resolve various TVA and NRC concerns, f

I l

' F: Forced Reason:

a Method

  • Exhibit G -Instmetions for (NUREG 2

S: Scheduled A-Equipment Failure (Explain) 1-Manual Preparation of Data Entry sheets B-Maintenance or Test 2-Manual Scram for Licensee Esent Report (LER)

C-Refueling 3-Aatomatic Scram File - NUREG - 1922 D-Regulatory Restriction 4-Continuation of Existing E-Operator Training and License Outage 8

Examination 5-Reduction Exhihit I-Same Source F-Administrative 9-Other G-Operational Enor (Explain) iI-Other (Explain)

E-8

UNIT SIIUTDOWNS AND POWER REDUCTIONS REPORT 310NTII: NOVEMBER 1997 DOCKET NO:

50-260 UNIT NAME:

BFN-2 DATE:

December 15,1997 COMPLETED BY: J. W. Davennort TELEPilONE:

(205) 729-2690 l

No.

c Datel Type' f Duration

- Reason' Method of Licensee System Component Cause and Corrective Action to Prevent f

(flours).-

Shutting l Event Report Code' Code' Recurrence '

Down.

No.

l Reactdr' 1

N/A I

r

' F: Forced

Heason:

' Alethod

  • Exhibit G -Instructions for (NUREG S: Schedofed A-Equipment Failure (Explain) 1-hianual Preparation of Data Entry sheets B-hfaintenance or Test 2 %1anual Scram for Licensee Event Report (LER)

C-Refueling 3-Automatic Scram File - NU REG - 1022 D-Re2uhtory Restriction 4-Continuation, of Existing E-Operator Training and License Outage 8

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

H-Other (Explain)

E-9 l

4 UN?T SIIUTDOWNS AND POWER REDUCTIONS REPORT MONTII: NOVEMBER 1997 DOCKET NO:

50-296 UNIT NAME:

BFN-3 DATE:

December 15,1997-COMPLETED BY: J. W. Davent ort TELEPIIONE:

(205) 729-2090 1.

I Nr..

Date -

Type' Duration Reason l Method of Licensee System Component Cause and Corrective Action to Prevent 2

I (Ilours)

Shutting..

Event. Report Code

  • Code' Recurrence Down No. '

ll Reactor' N/A l

l 1

i r

' F: Forced Reason:

' Method

  • Exhibit G -Instructions for (N UREG 2

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

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

C-Refueling 3-Automatic Scram File - N UREG - 1022 l

D-Regulatory Restriction 4-Contimaation of Existing E-Operator Training and License Outage 5

Examination 5-Reduction Exhibit 1-Sana Source F-Administrative 9-Othn G-Operational Error (Explain)

Il-Other (Explain)

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