ML19331C471

Monthly Operating Rept for Jul 1980

ML19331C471
Person / Time
Site:	Sequoyah
Issue date:	08/05/1980
From:	Ballentine J, Walker F TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML19331C466	List: ML19331C465 ML19331C471
References
NUDOCS 8008180444
Download: ML19331C471 (10)

Text

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O TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR P0kT.R SEQUOYAH NUCLEAR PLANT MONTHLY fPERATING REPORT JULY 1, 1980 - JULY 31, 1980 DOCKET NUMBER 50-327 i

LICENSE NLHBER DPR-77 ,

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mh-Submitted by,. D w. Ditkii,g Plan) Superintendent f

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l TABLE OF CONTENTS Operations Susumary . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Significant Operational Events . . . . . . . . . . . . . . . . . . . . . . 2 Average Daily Unit Power Level . . . . . . . . . . . . . . . . . . . . . . 3 Operating Data Report . . . . . . . . . . . . . . . . . . . . . . . . . . 4 Unit Shutdown and Power Reduction . . . . . . . . . . . . . . . . . . . . 5-6 Plant Maintenance Summary . . .. . . . . . . . . . . . . . . . . . . . . 7 4

Outage Maintenance Summary . . . . . . . . . . . . . . . . . . . . . . . . 8 i

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O Operations Summary July 1980 The following summary describes the significant operational activities during the reporting perfod. In support of this summary, a chronological log of significant events is included in this report.

There were thirty-four Licensee Event Reports and one Special Report 80-2 on the positive moderator temperature coefficient.

On 7-5-80, 0410,- operation began pulling rods for the approach to initial criticality. At 1040 on 7-5-80, the reactor reached initial criticality.

There were scien reactor scrams during July of which two were manual scrams that occurred during low power physics tests.

During July, all low power physics tests were completed.

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Significant Operational Events Date Time Event 7/05/80 0410 Started pulling shutdown Rank A-rode to begin initial criticality.

7/05/80 1040 Initial criticality.

7/08/80 1532 A low power physics test manual reactor trip occurred.

7/08/80 2203 Tripped reactor for low power physics test.

7/08/80 2346 Reactor is in mode 2.

7/09/80 0913 Reactor was tripped manually.

7/09/80 2113 Reactor is critical.

7/11/80 1949 Reactor i, at 3% reactor power.

7/12/80 1951 Reactor trip was due to intermediate range nuclear instrumentation high flux trip.

7/13/80 0753 Started reducing power to hot zere power.

7/13/80 1225 Commenced rod withdrawal to bring reactor to 3% power.

7/13/80 1252 Reactor is at 3% power.

7/18/80 0717 Reactor trip was caused by turbine trip as a result of the P-1 interlock not being blocked below 10% power.

7/19/80 1212 Reactor is critical.

7/21/80 1905 Rolled the main turbine generator.

7/22/80 0108 The turbine generator was tied onto the TVA grid.

7/22/80 2349 Tripped main turbine generator.

7/23/80 1334 Decreasing reactor power in preparation for going to mode 4, 7/23/80 1914 Reactor trip was due to low steam generator level in #3 steam generator.

7/24/80 1847 Reactor coolant system is in mode 5.

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O a AVERAGE DAILY UNIT POWER LEVEL

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DOCKET NO. 50-327 I

UNIT DATE, 8-5-80 COMPLETED BY Frank M. Walker TELEPHONE (615) 842-0295

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MONTH July 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL IMWe-Net) (Mwe. Net) 1 0 17 0 2 0 ig o 3 0 g9 0 4 0 20 0 5 0 21 0 6 0 0 22 I 0 0 '.f 7, 23

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8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 ;g o 13 0 0 29 14 0 0 30 m

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INSTRUCTIONS

' " On this format. list the average daily unit power levelin MWe. Net for each day in the reporting inonth. Compute to the neareit whole megawatt.

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k OPERATING DATA REPORT

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DOCKET NO. 50-327 DATE R-9-An COSIPLETED BY Fr= nte M- Walker TELEPHONE -(615) 842-0295 OPERATING STATUS Seanovah 1 N"I'5

1. Unit Name:

2. Reporting Period: July 1980

3. Licensed Thermal Power (31Wt): 170*

4. Nameplate Rating (Gross 31We): 1220.5 -- ~

5. Design Electrical Rating (Net StWe)- 1148

6. Sfaximum Dependable Capacity (Gross 31We): 1185

7. Sfaximum Dependable Capacity (Net alWe): 1148 S. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Gi e Reason;:

9. Power Level To Which Restricted.If Any (Net alwe):

_ , _IO. Rnsons For Restrictions. If Any: *L w P wer Phvefee Tooeing

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'V- This afonth Yr..to.Date Cumulative

-- I1. Hours in Reporting Period 744 3672 3672

12. Number Of Hours Reactor Was Critical 371.81 371.81 371.81

13. Reactor Reserve Shutuown Hours 0 0 o

14. Hours Generator On-Line 18.35 18.35 Ig_3s

15. Unit Reserve Shutdown flours n n _ g

16. Gross Thermal Energy Generated (31WH) 12356.19 12356.19 12356.19 .

17. Gross Electrical Energy Generated (31WH) 230 , , ,

230 230 IS. Net Electrical Energy Generated (.\1WH) 0 0 0

19. Unit Service Factor NA NA NA

20. Unit Availability Factor NA - MA NA

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

22. Unit Capacity Factor (Using DER Net) NA _

NA NA

23. Unit Forced Outage Rate NA - MA . - -- _-WA---

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24. Shutdowns Scheduled Over Nest 6.\1onths (Type. Date, and Duration of Each N '~vC-s i -12'_M "# Y ' A :'-'-

8-30 9-8-80 Outane to Inse=11 Hyd'ronen Tenitnrn in conrmin nd ~ ~

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25. If Shur Down \t End Of Report Period, Estimated Date of Startup:- ,8-$-80"

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

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Forecasr Achies ed ' ' ~ ~ ' ~ - '

INITIA L CRITICA LITY 7-4-80 7-5-80

,. INITIAL ELECTRICITY 8-21-80 7-22-80 CO\l\lERCIA L OPER ATION 10-3-80 4 (9/77)

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7-8-80 S 6.52 B 2 NA ZZ ZZZZZ Low Power Physics Testing 7-8-80 S 1.71 B 2 NA ZZ ZZZZZ Low Power Physics Testing 1 7-12-80 F 10 A 3 NA TA INSTRUY Reactor Tripped Because I.R. High Flua Trip Exceeded Setpoint. Inst was 1

Checked and Found to be OK.

• 2 7-15-80 F 3.72 ,C 3 NA IA INSTRUR Recorders Used in Special Test were Connected Improperly. When Recorder

, was Turned on, the Over Temperature AT Tripped the Reactor.

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3 7-18-80 F 28.92 C 3 NA IA INSTRUE The P-1 Interlock was Open at 10%

Power Causing Turbine Trip Which j . Caused a Reactor Trip. -

7-23-80 S 5.08 2 1111 SUPORTA Aux 'Feedwater Supports were not Seismi c j

4 Qualiffed. ,

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4 7-23-80 F 196.76 G 3 NA IA INSTRUE A low-low Steam Generator Level Tripped Reactor in Process of Shutting Down

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• o Plant Maintenance Sungnary Balanced the number four reactor coolant pump.

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y Outage Maintena=ce Summary Inspected pipe hangers on safety related syscens inside and cutside ccatainment in accordance with a conformatica of actica letter free NRC and II bulletin 79-1/..

Repisced the steam valve room exhaust fans v-ith larger capacity fans.

This was done to ensare that the steam valve room can be kept at 30 tp 120'T.

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