ML20217M376

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Monthly Operating Repts for July 1997 for BFN
ML20217M376
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 07/31/1997
From: Abney T, Davenport J
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9708220171
Download: ML20217M376 (13)


Text

,

Tennessee Valley Authority. Post offee Box 2000. Decatur. Alabama 35609-2000 August 14, 1997 i,

L!

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 t--

BROWNS FERRY NUCLEAR PLANT (BFN) - JULY 1997 MONTHLY OPERATING REPORT

=The_ enclosure provides the July 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.

- Sij1cerely n _.

)

1

,6 Manage Licensi g h7 a

an Industry Aff rs j

~

Enclosure cc:

See page.2 9708220171 970731 PDR ADOCK 05000259 R

PDR

U.S. Nuclear Regulatory Commission Page 2 August 14. 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 l

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

Atlanta, Georgia 30339-5957 Mr. James Lang, Manager I

Advanced Reactor Department Electri'c Power Research Institute 3340 Hillview Avenue-4 Palo Alto, California 94304 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Read 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 1

____U

ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

MONTHLY OPERATING REPORT JULY 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

I

e OPERATIONAL SUt44ARY JULY 1997-BROWNS FERRY NUCLEAR PLANT UNIT 1 Unit I remains shutdown on administrative hold to resolve various TVA and NRC concerno.

Unit 1 has been on adminf.strative 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 July, Unit 2 generated 796,910 megawatt hours gross electrical power and operated at a net capacity factor of 98.0 percent.

As of July 31, 1997, Unit 2 has operated continuously for 95 days.

l l

BROWNS FERRY NUCLEAR PLANT UNIT 3 For the month of July, Unit 3 generated 794,650 megawatt hours gross electrical power with a net capacity factor of 97.8-percent.

As of July-31, 1997, Unit 3 has operated continuously for_140_ days.

E-1

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-259 UNIT NO.

ONE DATE: August 15, 1997 COMPLETED BY:

J. W. Davenport TELEPHONE 205-729-2690 MONTH July 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 l

4.

0 20.

0 5.

0 21.

O i

6.

0 22.

O 7.

0 23.

0 8.

0 24.

0 l

9.

0 25.

0 10.

0 26.

0 11.

0 27.

O 12 0

28.

0 13.

0 29.

0 14.

0 30.

0 15.

0 31.

0 16. -

0 E-2

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-260 UNIT NO.

TWO DATE:

August 15, 1997 COMPLETED BY:

J. W. Davenport TELEPHONE 205-729-2690 MONTH July 1997 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL l

DAY DAY-(MWe-Net)

(MWe-Net)

1. -

1051 17.

1057 2.

1059 18, 1052 3.

1053 19.

1036 4,

1053 20.

1034-5.

1054 21.

1050 6.

1053-22.

1023 7.

1062 23, 1037 8.

1054 24.

1050 9.

1035 25.

1034-

-10.

1028 26.

1039

'11.

1047 27.

1044 12 1050 28.

1025-13.

1049 29.

1027 14.

1050 30.

1027

- 15, 1045 31.

1047 16.

1036 E _

t AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-296 UNIT NO.

THREE DATE:

August 15, 1997 Cot 4PLETED BY:

J. W. Davenport TELEPHONE 205-729-2690

-MONTH July 1997 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY DAY.

(MWe-Net)

(MWe-Net) 1.

1069 17.

1042 2.

1070 18.

1043

-3.-

1063 19.

831 4.

1069 20.

879 5.

1058 21.

-1051 6,

1044 22, 1050 7,

1073 23.

1052 8.

'1076 24.

1048 9.

1050 25.

1053 1

10.

-1067 26.

1047 11.

1050 27.

1037 12 1056..

29.

1031 13, 1051 29.

1057 14.

1064 30.

1038 15, 1061 31.

1054 16, 1047 E-4

OPERATING DATA REPORT Docket No.

$0-259 Date:

Aucust 15.1997 Completed By:

1 W. Davenport Telephone:

205-729-2690 1.

Unit Name:

BFN Unit i 2.

Reporting Period:

July 1997 3.

Licensed Thermal Power (MWt):

3293 4.

Nameplate Rating (Gross Mwe):

1I52 5.-

Design Electrical Rating (Net Mwe):

1065 6.

Maximum Dependable Capacity (Gross MWe)-

g 7.

Maximum Dependable Capacity (Net MWe):

0 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 get MWe): 0 10.

Reasons for Restrictions, If any: Administrative lloid 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 Foret;d Outage Rate 0

0 25.6 24.

Shutdowns Scheduled Over Next 6 Months (Type, Date, cnd 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 a

(June 1,1985 to present)

E-5 l

OPERATING DATA REPORT Docket No.

50-260 Date:

August 15.1997 Completed By:

J. W. Davenpon Telephone:

205-729-2690 1.

Unit Name:

BFN Unit 2 2.

Reporting Period:

July 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):

1098.4 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 l

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 744.0 5087.0 144702 12, Number of Hours Reactor was Critical 744.0 5029.0 103678 13.

Reactor Reserve Shutdown Hours 0.0 0.0 14200 14.

Hours Generator On-Line 744.0 5024.0 101306 15.

Unit Reserve Shutdown Hours 0.0 0.0 0

16.

Gross Thermal Energy Generated (MWh) 2443632.0 16073088 300260188 17.

Gross Electric Energy Generated (MWh) 796910.0 5362180 99783548 18.

Net Electrical Energy Generated (MWh) 776674.0 5233565 97066731 19.

Unit Service Factor 100.0 98.8 70.0 20.

Unit Availability Factor 100.0 98.8 70,0 21.

Unit Capacity Factor (Using MDC Net) 98.0 96.6-63.0 22.

Unit Capacity Factor (Using DER Net) 98.0 96.6 63.0 23.

Unit Forced Outage Rate 0.0 1.2 14.4

. 24.

Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration ofEach): 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 Staitup: N/A

  • Excludes hours under Administrative lloid (June 1,1985 to May 24,1991)

E-6 m

_A

4 i,

OPERATING DATA REPORT Docket No.

50-296 Date:

August 15.1997 Completed By:

J. W. Davenport Telephone:

205-729-2690 1.

Unit Name:

BFN Unit 3 2.

Reporting Period:

July 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.

Maximu'm 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 744.0

-5087.0 87924 12.

Number ofHours Reactor was Critical 744,0 4647.0 59401 13.

Reactor Reserve Shutdown Hours 0.0 0.0 5150 14.

Hours Generator On-Line 744,0 4629.2 58048 15.

Unit Reserve Shutdown Hours 0.0 0.0 -

0 16.

Gross Thermal Energy Generated (MWh) 2416872,0 14263656 175494313 17.

- Gross Electric Energy Generated (MWh) 794650.0 4743580 58767720 18.

Net Electrical Energy Generated (MWh) 774689.0 4622462 56304593 19.

Unit Service Factor 100.0 91.0 66.0 20.

Unit Availability Factor 100.0 -

91.0 66.0 21.

Unit Capacity Factor (Using MDC Net) 97.8-85.3 60,1 22.

Unit Capacity Factor (Using DER Net) 97.8 85.3 60.1 23.

Unit Forced Outage Rate 0.0 0.0 17.6 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: N/A

  • Excludes hours under Administrative Iloid (June 1,1985 to November 19,1995)

E-7

-_ J

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: JULY 1997 DOCKET NO:

50-259 UNIT NAME:

BFN-1 DATE:

August 151997 COMPLETED BY: J. W. Davenport TELEPHONE:

(205) 729-2690 No.

s.Datet

!Typeh Durationi Reason- Method of Licensee SystesmL,Cesapement Cause and Corrective Action to PrevenO (Hours)[

Sbstting Event Report Code Code' Recurrence d~

. Dews.

No; -

^

Reacted 1

06/01/85 S

744 F

4 N/A N/A N/A Administrative hold to resoh e various TVA and NRC concerns.

i

' F: Forced Reason:

Method

  • Exhibit G -Instmeticus for(NUREG 2

8 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 - 1922 D-Regulatory Restriction 4-Continuation of Existing E-Operator Training and License Outage Examination 5-RMuction

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

H-Other (Explain)

E-8

~

~

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: JULY 1997 i

i DOCKET NO:

50-260 UNIT NAME:

BFN-2 DATE:

August 15,1997 I

COMPLETED BY: J. W. Davenport TELEPHONE:

(205) 729-2690-L Reason *i Method of Licensee

_ Systems.1 Cossponent

_Cause and Corrective Action to Prevent !

No?

h Da'ted Type"

-Duration -

jHosrk)}

Shutting Event Report Code' C0de.a Recurmece s

Down No.?

.ggQef

^

N/A j

  • F: Forced

' Reason:

' Method

  • Exhibit G -Inst wctions 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 - 1922 D-Regulatory Restriction 4-Continuation ofExisting E-OperatorTraining and License Outage Examination 5-Reduction s Exhibit I-Samee Searce F-Administrative 9-Other G-Operational Error (Explain)

H-Other (Explain)

E-9

e UNIT SHUTDOWNS AND POWER REDUCTIONS REPORTMONTH: JULY 1997 DOCKET NO:

50-2% -

UNIT NAME:

BFN-3 DATE:

August 15,1997 COMPLETED BY: J. W. Davenport TELEPHONE:

(205) 729-2690 No.5

? Datel Type' Duration-Reason ' Method of Licensee Systesu Component; Cause and Corrective Action to Prevent :

2

.(Hours) 9 Shutting Event Report CodeV CodeV Recurrence

~

'~ '

..Down !-..

NoE

~~

2r R$ actor'!

~

4 07/18/97 S

0 B

5 N/A N/A N/A Power reduction for scheduled maintenance and testing.

  • F: Ferrad Reason:

' Method

  • Exhibit G -Instructions 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 Eirst 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-Same Source F-Administratist 9-Other G-Operational Error (Explain)

H-Other (Explain)

E-10