ML17208B078

Monthly Operating Rept for Mar 1980

ML17208B078
Person / Time
Site:	Sequoyah
Issue date:	04/03/1980
From:	Walker F TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML17208B077	List: ML17208B076 ML17208B078
References
NUDOCS 8004180394
Download: ML17208B078 (15)

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TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT MARCH 1, 1980 - MARCH 31, 1980 DOCKET NUMBER 50.-327 LICENSE NUMBER DPR"77 Submitted By; Plant S erintendent 8064180 Q'Pf

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TABLE OF CONTENTS Operations Summary .

'Significant Operational Events ~ 0 2 Average Daily Unit Power Level . ~ ~ ~ 0 3 Operating Data Report 4 Unit Shutdown and Power Reduction ~ 0 5 Plant Maintenance Summary 6 Outage Maintenance Summary . ~ 0 7

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0 erations Summar March 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 March.

Initial fuel loading for unit 1 commenced on March 1 and was completed on March 5. One hundred ninety-three fuel elements were loaded.

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Si nificant 0 erational Events Date Time Event 3/01/80 1419 The first fuel assembly was loaded in the unit 1 reactor vessel in location G-l.

3/05/80 0830 Completed loading unit 1 fuel.

AVERAGE DAILYUNIT POWER LEVEL DOCKET NO.

UNIT 1 COMPLETED BY TELEPHONE MONTH March 1980 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) (M We-Net)

I 0 17 0 IS 0 19 0 0 20 0 5 21 0 '22 0 0 23 0 0 24 0 9 0 25 0

'I 0 0 26 0 0 0.

12 28 0 13 0 29 0 14 0 30 0 IS 0 31 16 INSTRUCTIONS On this format, list the avcragc daily unit power level in MWc.Nct for each day in thc reporting month. Compute to thc nearest whole megawatt.

('I/77)

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OPERATING DATA REPORT DOCKET NO. MM22 DATE COi) IPLETED BY TELEPHONE

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~1@~2-0295 Walker OPERATING STATUS Notes

1. Unit Name

2. Reporting Period:

3. Licensed Thermal Po)vcr (MWt): *

4. Nameplate Rathig (Gross illWc):

5. Design Electrical Rating (Nct MWe):

6. Maximum Dependable Capacity (Gross MIVc)

7. Maximum De p endablc Ca I)acit y(Net l)IWc: ) 1148

8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9. Power Level To IVhich Restricted, If Any (Nct MWe):

10. Reasons For Restrictions, If Aoy:

This iblooth Yr.-to.Date C))n)))iat)vc

11. Hours h) Reporting Period 744 744

12. Number Of Hours Reactor IVas Critical 0 0 0

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator Oo-Linc 0 0 0

15. Unit Reserve Shutdown Flours s

17. Gross Electrical Energy Generated (MWH) 0 0

0 0.

0

18. Net Electrical Fnergy Gcncratcd (MWH) 0 0 0

19. Unit Service Factor A N A

20. Unit Availability Factor N A /*

N A N/A ~,=-. -..--::- N/A "2. Unit Capacity Factor (Using DER Nct) N/A N A

23. Unit Forced Outage Rotc

24. Shutdowlls Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

25. If Shut Down At End Of Rcport Period, Estiinatcd Date of Startup:

26. Units In Te'st.Status (Prior to Coo)merci))l Operation): Forecast Achieved INITIAL CRITICALITY Ma~9 1980 INITIAL ELECTRICITY COi~t M ERCIA L Ol'ER ATION Jul~

August 18 1980 .

1980

+ Low power physics testing license issued. (o/77) 4

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l)OCKET NO. 50-327 UNIT Sl IUTI)OIUNS ANI) I'OIUEI( REI) UCTIONS UNIT NAhfE Se uo ah 1 l)A'IE COMI'I.I!'I'EI)IIY Walker I I I I I I IONG ~615 842-0~2 If rt cn ~

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> a Lv(!Itl Aotiott ((t Rcport ~-' I rcvent Rc(.urr(.n(.c I': I'oreed Reason: hlcthod: I'.xhibit G - Instructions S: Scheduled A Ii(luiprncnt I'ailurc (Explain) I hlanual for Preparation ot Data I).Maintenance nr Test 2-hi annal Scram. Lntry Sheets tor Licensee 6-Rct'ucling 3-Auton>atic Scratn. Event Report (LLR) File (NUREG-D Regulatory Restriction 4.Other (Explain) 016l)

E-Operator Training (t; Liccnsc Examination F-Administ rat ivc G-Operational Error (Explain) Exhibit I - Sa>ne Source

(')/77) ~ I I.Other (Explain)

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Plant Maintenance Summar No major maintenance was performed on CSSC equipment during the month of March.

Outa e Maintenance Summar During March, the three low pressure turbine spindles were inspected for cracks to meet NRC requirements.

The control rod drive upper guide tube support pins were replaced upon recommendation from Westinghouse.

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