ML19339C541

Monthly Operating Rept for Oct 1980

ML19339C541
Person / Time
Site:	Sequoyah
Issue date:	10/31/1980
From:	Dupree D TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML19339C539	List: ML19339C538 ML19339C541
References
NUDOCS 8011180571
Download: ML19339C541 (10)

Text

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4 l TENNESSEE VALLEY AUTHORITY j DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT

'i MONTHLY OPERATING REPORT 4

OCTOBER 1 - OCTOBER 31, 1980 1

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DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 i

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Submitted By: to tII \)0 tiV 1lio '

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TABLE OF CONT US Operations Summa ry . . . . . . . . . . . . . . . . . . . . . . . . . . . .1 Significant Operational Events . . . . . . . . . . . . . . . . . . . . . . 2-3 Average Daily Unit Power Level . . . . . . . . . . . . . . . . . . . . . .4 Operating Data Report . . . . . . . . . . . . . . . . . . . . . . . . . .5 Unit Shutdown and Power Reduction . . . . . . . . . . . . . . . . . . . .6 Plant Maintenance Summary . . . . . . . . . . . . . . . . . . . . . . .7 Outage Maintenance Summary . . . . . . . . . . . . . . . . . . . . . . . 8 1

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Operations Summary Octobe r, 1980 The following summary describes the significant operational activities during the month of October. In support of this summary, a chronological log of significant events is included in this report.

There were thirteen Licensee Event Reports and no Special Reports.

There were seven reactor scrams during October.

Unit I was in mode 2 at the beginning of the month and initially entered mode 1 at 0621 on October 2, 1980. The turbine was tied on-line with 40 MW at 2352 on October 4, 1980. The reactor was placed in mode 5 twice during the month for maintenance.

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Significant Operational Events Date Time Event 10/01/80 0001 Unit 1 in mode 2; Tavg 547'F @ 2235 psi.

10/02/80 0634 Tripped MFPT 1-A, High S/G level.

10/02/30 1135 Turbine tied on-line.

10/02/80 1336 Turbine tripped - reverse power.

10/02/80 2210 Reactor tripped - breakers closed during performance of SI-268.

10/03/80 0423 Turbine tied on-line @ 40 MW.

10/03/80 0540 Turbine trip - lost feedwater flow reactor in mode 2 @ 1% power.

10/04/80 2352 Turbine tied on-line @ 40 MW.

10/05/80 0618 Leak located in RCP f/3 seal water injec-tion line. Preparing to bring reactor down to mode 5.

i 10/05/80 2218 Reactor in mode 5.

10/11/80 0214 Reactor entered mode 4 10/12/80 1307 Reactor entered mode 1 @ 5% power.

10/12/80 1410' Turbine tied on-line.

10/12/80 1546 Turbine / reactor trip due to MFPTA trip.

10/13/80 0352 Reactor tripped @ 28% power.

10/13/80 0959 Reactor tripped @ 12% power.

10/13/80 1344 Started cooldown to E 360*F.

10/14/80 1226 Reactor entered mode 4 10/22/80 1534 NRC inspected hydrogen igniter system.

10/24/80 1350 Reactor entered mode 5 to work on governor valves.

10/29/80 0900 Reactor entered mode 4.

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I Significant' Operational Events Date Time Event j 10/30/80 2033 Reactor tripped - High S/G level.

1 j 10/31/80 0046 Reactor tripped - Lo level - S/G.

10/31/80 0602 Turbine tied on-line.

10/31/80 2400 Reactor in mode 1 at 30% power level and 274.7 MW output, i

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3 AVERAGE DAILY UNIT POWER LEVEL 1

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4 DOCKET NO. 50-327 UNIT 1 DATE 10-31-80 COMPLETED BY David Dupree TELEPHONE (615) 842-0295 i

MONTH October

! DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l

t (MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0 3 n. 19 0 4 0 20 0 l

j 5 0 21 0 i 6 0 22 0 7 0 23 0-j' 8 0 24 0 l- 9 o 25 0

! 10 0 26 0

, 11 o 27 0 12 0 28 0 13 0 29 0 14 0 30 0 i~ -

15 0 31 156 -l

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l INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77) 4

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OPERATING DATA REPORT i

DOCKET NO. 50-327 DATE 11-4-80 COMPLETED BY David Dupree TELEPHONE (615) 842-0295 OPERATING STATUS

1. Unit Name: Secuovah 1 Notes

2. Reporting Period: October 1980

3. Licensed Thermal Power (?Nt): 3411

4. Nameplate Rating (Gross ?Ne): 1220.5

5. Design Electrical Rating (Net PNe): 1148

6. Maximum Dependable Capacity (Gross MWe): 1185

7. Maximum Dependable Capacity (New MWe): 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 (New MWe):

} 10. Reasons For Restrictions, If Any:

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 745 5881 5881

12. Number of Hours Reactor Was Critical 143.58 685.58 685.58

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 17.96 36.31 36.31

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (%H) 29309.76 68669.27 68669.27

17. Gross Electrical Energy Generated (tNH) 4489 4719 4719

18. Net Electrical Energy Generated (FNH) 0 0 0

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

20. Unit Availability Factor N/A N/A N/A

21. Unit Capacity Factor (Using MDC Net) N/A N/A N/A

22. Unit Capa' city Factor (Using DER Net) N/A N/A N/A

23. Unit Forced Outage Rate

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N/A N/A N/A

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

25. If Shut Down At End Of Report Period', Estimated Date of Startup:

j 26. Units In Test Status (Prior.to Commercial Operation).

Forecast Achieved INITIAL CRITICALITY 7-04-80 7-05-80 INITIAL ELECTRICITY 8-21-80 7-22-80 COMMERCIAL OPERATION 12- 30-80 i

(9/77) 5 I

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UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-327 UNIT NAME Sequoyah 1 DATE 10-1-80 COMPLETED BY Dayid Dupree REPORT MONTII October TELEP110NE (615) 842-0295 "h

c -s n o eo 3 Licensee U Cause & Corrective No. Date 'b jj $ @ y fj M Event @ 't $#b Action to .

S Uo @ j$j Report # $3 E.3 Prevent Recurrence  !

05 a & 8 a

03la x v2 u 8 10-2-80 F 311R/17M [N G 3 N/A N/A N/A Reactor tripped on low feedwater level.

9 10-12-80 F 311R/4 MIN A 3 N/A N/A N/A Main feedwater pump 1A tripped on low vacuum which resulted in a reactor trip.

10 10-12-80 F 2ilR/39M 'N A 3 N/A N/A N/A Reactor tripped on low steam generator level when the #3 main feedwater bypass, valve did r.ot operate.

11 10-13-80 F 311R/8MIM A 3 N/A N/A N/A Reactor tripped on high steam generator level af ter operator had overfed steam generator.

12 10-13-80 F 211R/31M N 11 3 N/A N/A N/A Main feedwater pump 1A tripped on low vacuum which resulted in a reactor trip..

13 10-30-80 F 211R/46M ' N 11

. 3 ti/A N/A N/A Reactor tripped on high steam generator level af ter operator had overfed steam generator.

14 10-30-80 F lilR/36M :N 11 ,3 N/A N/A N/A Reactor tripped on low steam generator level while increasing power.

1 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Haintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Re fuel i ng 3-Automatic Scram. Event Report (LER) File '(NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F-Admin i s t ra t ive G-Operational Error (Explain) 5 (9/77) Il-Other (Explain) Exhibit I-Same Source w.

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Plant Maintenance Summary 4

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4 The following significant maintenance items were completed during the month i

of October, 1980:

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1. A leak was found in the reactor coolant pump #3 seal water injection 4

pipe on October 5. The seal water injection pipe and inlet flange were replaced to the reactor coolant pump #3 thermal barrier.

2. The IC main condenser was sucked in approximately 4". It was straightened and braces were added. Braces were also added to t

1A condenser.

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3. Cracked seats were found in the #1 and #4 main turbine governor valves on Unit 1. The seat pins were missing from governor valve

1. 1; pins were later found in the nozzel block. New original type seats were placed in governor valves #1 and #4, and new modified seats were placed in governor valves #2 and #3.

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4. At the end of October, the reactor was in mode 1 at 30% power and 4

) 275 MW output.

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Outage Maintenance Summary Continued to work on pipe hangers on safety related systems in accordance with IE Bulletin 79-14.

14ork continued on the installation of high density storage racks in the spent fuel pit. Work was completed on the solenoid change out on the auxiliary feedwater regulator valves and re-routing of cables for the auxiliary feedwater system.

Continue to repair containment isolation valves on Unit 2 that failed the TVA-2C preoperational leak rate test.

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