ML19305E880

Monthly Operating Rept for Apr 1980

ML19305E880
Person / Time
Site:	Sequoyah
Issue date:	05/07/1980
From:	Walker F TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML19305E879	List: ML19305E878 ML19305E880
References
NUDOCS 8005200568
Download: ML19305E880 (9)

Text

.

O 800s20o549 TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR PJWER SEQUOYAll NUCLEAR PLANT

?!0NTHLY OPERATING REPORT APRIL 1, 1980 - APRIL 30, 1980 DOCKET NUl!BER 50-327 LICENSE NUMBER DPR-77 Submitted By:

Plant Superintendent i

TABLE OF CONTENTS 3

Operations Summary.

Significant Operational Events

.2

.3 Average Daily Unit Power Level.

.4 Operating Data Report

.5 Unit Shutdown and Power Reduction Plant Ifaintenance Summary

.6 Outage flaintenance Si'mmary

.7

~

Operations Summary April 1980 The following summary describes the significant operational activities during the reporting period.

In support of this summary, a chronological log of significant events is included in this report.

There were sixteen Licensee Event Reports submitted to the NRC during the month of April.

One fuel assembly, H-6, failed the RCCA drag test and the RCCA was replaced. After replacement, the RCCA drag test was satisfactory.

1

Significant Operational Events Date Event 4/08/80 Fuel assembly H-6 passed RCCA drag test af ter RCCA was changed out.

4/21/80 RCS pressure at 325 psi.

4/26/80 Reactor coolant system heated up to 180 F.

2

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-327

!! NIT I

DATE 5-7-80 CON 1PLETED BY Frank M. Walker (615)842-029d TELEPl!ONE Nf0 N Ill April 1980 l

AVER AG' DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL DAY E

l OlWe Net)

(.glwe Net) 0 0

I g7 2

0 0

g3 O

0

3..

j9 4

0 0

20 5

0 0

21 6

0 0

22 7

0 0

23 0

0 8

24 9

0 25 0

10 0

2c, O

0 0

11 2.,

12 0

0

,3 0

0 13 29 0

0 14 3g 0

0 15 3

0 1 (,

INSTRUCll0NS On this format,!:st the avera< e daily unit power lesel in N1We Net for each day in the reporting inonth. O.apute to g

the nearest whole megawatt.

(9/77)

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v e

a

-w----

4 l

OPERATING DATA REPORT DOCKET NO.

50-327 DATE 5-7-80 COSIPLETED BY prnnk M-_ Walker -

TELEPil0.NE (A10 W -0295 OPEllATING STATUS

1. Unit Name:

Ronunvnh 1 Notes

2. Reporting Period:! ___,

April 1980

3. Licensed Thermal l'ower (51Wt):

170*

4. Nameplate Rating (Gross 51We):

1220,5

5. Design Electrical Rating (Net SIWE):

1148

6. Slaximum Depend 5ble Capacity (Gross alwe):

1185

7. Staximum Dependable Capacity (Net alWe):

1148

8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report, Give Reasons:

9. Power Level To Which Restricted,if Any (Net 51We):

10. Reasons For Restrictions.If Any:

This 51onth Yr.-to.Da t e Cumulative i1. Ilours In Reporting Period 720 1464 1464

?

12. Number Of Ilours Reactor Was critical 0

0 0

13. Reactor Reserve Shutdown flours 0

0-0-

14. Ilours Generator On Line 0

0 0

15. Unit Reserve Shutdown llours 0

0 0

16. Gross Thermal Energy Generated (51Wil) 0 0

0

17. Gross Electrical Energy Generated (.\\lWil)-

0___.

0 0

18. Net Electrical Energy Generated (alWil) 0 0

'0

19. Unit Senice Factor N/A N/A-N/A

20. Unit Asailability Factor' N/A N/A N/A

21. Unit Capacity Factor (Using 51DC Net)

N/A N/A' N/A

22. Unit Capacity Factor (Using DER Net)

N/A N/A N/A

23. Unit Forced Outage Rate N/A N/A

-N/A.

24. Shutdowns Scheduk;d Over Next 6 Slonths (Type, Date.and buration of Each):

.I

.1

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

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achiesed L

t

'lkITIA L CRITICALITY

'May 21. 1980 I

dNI.I'IA L ELECTRICITY

' July 6. 1980

'1 CONI 5lERCIA L OPER ATION

August 18, 1980

-l

• Low Power Physics : Testing License Issued t

{

(9/77) 141 i.

Plant Maintenance Summary No major maintenance was performed on CSSC equipment during the month of April.

6

Outage Maintenance Summary During April, the inspection and reassembly of the main turbine was completed.

The installation of reactor intervals and reactor pressure vessel head was completed.

Completed the replacement of the control rod drive upper guide tube support pins.

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