ML19323H617

Monthly Operating Rept for May 1980

ML19323H617
Person / Time
Site:	Sequoyah
Issue date:	06/03/1980
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML19323H616	List: ML19323H615 ML19323H617
References
NUDOCS 8006130296
Download: ML19323H617 (9)

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1, TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER P

SEQUOYAH NUCLEAR PLANT

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MONTHLY OPERATING REPORT i

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MAY 1, 1980 - MAY 31, 1980 l

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l DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 l

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i Submitted By:

Plant Superintendent.

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TABLE OF CONTENTS Operations Summary..

.1 Significant Operational Events

.2 Average Daily Unit Power Level.

.3 Operating Data Report

.4 Ur.it Shutdown and Power Reduction

.5 Plant Maintenance Summary

.6 Outage Maintenance Summary.

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i Operations Summary May 1980 The following summary describes the significant opecational activities 1

i during the reporting period.

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

4 There were twenty-seven Licensee Event Reports submitted to the NRC during the month of May.

1 During the month, heatup to normal operating temperature for pre-operational testing and initial criticality was begun. A pipe hanger on the CVCS letdown line was determined to be incorrectly installed and the reactor was returned to cold shutdown. The reactor remains in cold shut-down while hanger inspection and repair is in progress.

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Significant Operational Events Date Event 5/08/80 RCS in Mode 4 5/11/80 RCS in Mode 3 5/16/80 Due to hanger problems, cooling down RCS, RCS in Mode 4.

5/17/80 RCS in Mode 5 5/31/80 RCS in Mode 5 2

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l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-327

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1 UNIT

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DATE 6-3-80

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l CO\\1PLETED BY hank :<f. Walker i

(615) 8h2-0293 i

TELEPil0NE i

MONTli ih't 1NO i

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DAY AVER AGE DAILY POhER LEVEL DAY AVER AGE D \\lLY POWER LEVEL e \\1he-Net i t \\twe Neti I

O 0

g7 0

g3 0

0 0

J 3.,

39 4

0 0

20 5

0 0

3g 0

O l

6 7

0

3 0

8 0

24 0

9 0

25 0

10 0

0 26 II 27 O

0 1

0 0

12 33 13 0

29 0

14 0

0 q

30 15 0

o 3,

j 16 0

INSTRUCTIONS

.)i On this format. list the average daily unit power lesel in MWe-Net for each day in the reporting mor.1. Compute to the nearest whole megawatt.

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OPERATING DATA REPORT I

DOCKET NO. __50-3?7 DATE

• ~0-U" COSIPLETED BY Mart al. Wallter l

TELEP110NE (615) c42-0295 OPERATING STATUS l

SeCHOyBh Notes I. Unit Name:

2. Reporting Period:

by 1980

3. Licensed Thermal Power (5thti:

4. Nameplate Rating IGross.\\lWe):

1220 5

5. Design Electrical Rating (Net.\\lWe):

6..\\latimum Denendable Capacity iGross.\\tWeI:

5 7.\\lasimum Dependable Capacity INet.\\lw l:

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5. If Changes Occur in Capacity Ratings litems Number 3 Through 7)Since Last Report. Give Reasons:

9. Power Lesel To which Restricted if Any (Net 31We):

10. Reasons For Restrictions. If Any:

l This Stonth Yr.-to-Date Cumulative 6

11. Ilours In Reporting Period 7hh 2208 2208 f

12. Number Of flours Reactor Was Critical 0

0 0

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13. Reactor Reserve Shutdown Hours 0

0 0

14. Ilours Generator On-Line 0

0 0

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15. Unit Reserve Shutdown flours 0

0 0

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

0

17. Gross Electrical Energy Generated (.\\tWH) 0 v

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18. Net Electrical Energy Generated (SIWH)

O 0

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19. Unit Service Factor N/A N/A U/A

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

21. Unit Capacity Factor (Using.\\lDC Net)

II/A II/A U/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 Scheduled Over Nest 6 Stonths (Type. Date,and buration of Eacht:

25. If Shut Down A: End Of Report Period. Estimated Date of Startup:

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

Forecast Achiesed

' I INITIA L CRITICALITY 7-07-80 i

JNITIA L ELECTRICITY 8-21-80 d

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Plant Maintenance Summary A new stuffing box extension to casing gasket was installed in RHR i

pump 1B-B to stop leakage problem. The leakage was not stopped and the Problem is still being evaluated.

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Replaced a blown gasket on the oil lift pump lines inside the RCP #2 motor.

The shaft on IA-A safety injection seized. The pump was dismantled and the affected parts returned to Pacific Pump Co. for repairs. The cause of the seizing has not been determined. Unit 2 pump 2A-A was installed in place of 1A-A.

The unit 1 pump IB-B was disassembled and no problems were found.

Staking of the component cooling heat exchanger "A" tubes is approxi-mately 70% complete. This modification is being made to reduce the tube vibration.

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Outage Maintenance Summary Inspected pipe hangers on safety related systems inside and outside containment in accordance with a conformation of action letter from NRC and IE bulletin 79-14.

Added remote indication for the ABGTS filter differential pressures.

This resulted from NRC requirements.

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