ML19331C471
| ML19331C471 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/05/1980 |
| From: | Ballentine J, Walker F TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19331C466 | List: |
| References | |
| NUDOCS 8008180444 | |
| Download: ML19331C471 (10) | |
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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 , J .- ! i I 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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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.
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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.
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During July, all low power physics tests were completed. I i 1
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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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a AVERAGE DAILY UNIT POWER LEVEL
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k' - 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
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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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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. (4 /77)
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f \ - 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 ' ' ~ ~ ' ~ - '
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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
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UNil'Silull60WNS ANilPOWl:M Hlllik'llONS IH M'l 1:l' NO. 50-327 ,4?
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,i UNil'NAntti hquoyah i l) Nil; R LRn .. ..
' ! COMPl.1lli D llY . frank .M._ Walker 't lli Pulfl AIONill 'Tuly 1980 'll 1.l l'IlONii
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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
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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
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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. , 3 _ . _ . _ -. I 2 .1 4 1: I .n.eil Itc.c..n : klellanl: 8 1%InI>it G insuncilinis
*. N iintulcil A 1 guipnient 1.nlure (I spl.on) 1 -h14n nal fin Peep. nasion of Data '
ll Alaintenance os l'ett 2 hiannal Scs.un. I:nity Sheets for 1.icenwe < C.Hefueling .l. Automatic & sani. INent Repost (l.l:lO l'ile (NURI G-D Regniatory itestrisiion 4 Other (l!xplaud 0161) C' 1 Opciatos haining & I acmc 1:samination , IN Ailinunst rative 5 G Opcianonal I.nus (l'xplain) 1:sinbis 1 S.nne Source i pt/77) 11 Other (1:s pl.iin) !
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UNil Silulil0WNS ANI)l' owl:R RI;DUCllONS IMM:KET No, _ 5D:327 # 1-3' UNil' NAMl; Sequoya
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ilNIE 8-5-fl0 COMI'I.E llill ilY Frank M. Walker Rt.I'Olt l' MON ~lll ..luly 14An ;
.ll.l.l l lloNg (615)_842-0295 ,
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i _ . . . _ . _ . , 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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. Plant Maintenance Sungnary Balanced the number four reactor coolant pump.
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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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