ML19350B437

Monthly Operating Rept for Feb 1981

ML19350B437
Person / Time
Site:	Sequoyah
Issue date:	03/04/1981
From:	Eddings M TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML19350B435	List: ML19350B434 ML19350B437
References
NUDOCS 8103200545
Download: ML19350B437 (11)

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TENNESSEE VALLEY AUTHORITY j

DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY JPERATING REPORT 1

FEBRUARY 1, 1981 - FEBRUARY 28, 1981 t

DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 i

. \ 4 Submitted By: us i (E Plant \ Superintendent i

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TABLE OF CONTENTS 1

Operations Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 PORV's and Safety Valves Summary . . . . . . . . . . . . . . . . . . . . . 1 Significant Operational Events . . . . . . . . . . . . . . . . . . . . . . 2-3

' Average Daily Unit Power Level . . . . . . . . . . . . . . . . . . . . . . 4 I

Operating Data Report . . . . . . . . . . . . . . . . . . . . . . . . . . 5 Unit ' Shutdown and Power Reduction . . . . . . . . . . . . . . . . . . . . 6 Plant Maintenance Summary . . . . . . . . . . . . . . . . . . . . . . . . -7 Outage Maintenance Summary . . . . . . . . . . . . . . . . . . . . . . . . 8-9 s

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Operations Summary February, 1981 The following summary describes the significant operational activities for the month of February. In support of this summary, a chronological log of significant events is included in this report. ,

There were eight Licensee Event Reports, one Special Report, and one 10 CFR Part 21 Report during the month.

There was one scram during February.

Unit I was critical for 95.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, produced 71,302 MWH (gross) with 6.61 percent station use, resulting in a average hourly gross load of 813,020 KW du. ring the month. .The net heat rate for the month was 10,;72 STU/KWH.

There are 342.9 full power days estimated remaining until the end of cycle 1 fuel. With a capacity factor of 85 percent the target E0C exposure would be reached April 9, 1982. The capacity factor for the month was 9.0 percent.

The unit was manually shutdown February 5 due to excessive vibration in the main generat'or/ exciter. The unit was taken to mode 5 for ice basket weighing and ice loading as required. On February 11, RHR spray valve 72-40 was' opened and the SRO declared the unit in a L.O.C.A. and an onsite emergency was declared.- The RHR spray valve was isolated and the unit was returned to normal mode 5 operational status.

At the end of the month,.the reactor was in mode 5.

PORV's and Safety Valves Summary The pressurizer pressure operated relief valves were challenged at 1832

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on 2-1-81 due to high reactor coolant system pressure during reactor scram 37.

No other pressure operated relief safety valves were. challenged during the month.

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Significant Operational Events Date Time Event 02/01/81 0001 Rx Pwr 96%; 1120 MW's.

02/01/81 1832 Rx Trip #37 - Unidentified signal in the EHC system caused the main turbine valves to close, S/G levels shrunk causing a Lo-Lo S/G

1. 1 level and reactor trip.

02/01/81 1832 PZR PORV opened.

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02/01/81  ? PZR PORV closed - Immediately after pressure fell.

02/02/81 0410 Rx critical.

02/02/81 0546 Turbine on-line.

02/02/81 1800 Rx Pwr 63%; 700 MW's - Holding.

02/02/81 0200 Began load increase.

02/03/81 0600 Rx Pwr 70%; 780 MW's.

02/03/81 1130 Load decrease by 1% - #2 governor valve modulating. .

02/03/81 1205 Load decreased by 1% - Loa /. swing = 40 MW's.

02/03/81 1400 Rx Pwr 65%; 736 MW's.

02/03/81 2200 Rx Pwr 62%; 700 MW's.

02/04/81 0200 Began increasing load.

02/04/81 0600 Rx Pwr 74%; 820 MW's.

02/04/81 0932. Load increase at' 50 MW increments - start 840 MW's.

02/04/81 - 0939 Load holding at 900 MW's - Vibration measure-ments on exciter.

Began ~ load increase at 50 MW increments - Start 02/04/81 1009 910 MW's.

.02/04/81 1015 Load holding at 960 MW's - Vibration measure-ments on exciter.

02/04/81 1025 ' Began load increase of 50 MW's - Start 970 MW's.

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Significant Operational Events (Continued)

Date Time Event 02/04/81 1030 Load holding at 1020 MW's - Vibration measure-ments on exciter.

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02/04/81 1051 Began load increase of 50 MW's - Start 1030 MW's.

02/04/81 1100 Load holding at 1060 MW's; Rx Pwr 98% - Vibration problems with exciter.

' 02/04/81 1115 Rx Pwr 98%; 1080 MW's. -

02/04/81 2123 Started load reduction at 1% per min. manually bringing the unit to mode 5.

02/04/81 2249 Started 5% load reduction to 60% Rx Pwr.

02/05/81 0257 Turbine off-line.

02/05/81 0845 Entered mode 2.

02/06/81 1032 Entered mode 5 - Vibration problem on the exciter and ice basket weighing.

02/58/81 ~0020 Lost all annuncistors when lost spare inverter -

Transferred to normal inverters.

02/08/81' 0020 Lost power to most rad monitor for 2 5 minutes causing an auxiliary building isolation.

02/11/81 . 1940 SRO declared Unit 1.in a L.O.C.A.

- 02/11/81 1945 On-site emergency declared - Plant evacuation alarm initiated.

01/11/81 2012 Initiated -auxiliary building isolation (manual).

02/11/81 2013 SIS pump.1A injection' initiated.

D2/11/81 2015 RHR spray Vlv-72-40 discovered open. Valve was isolated'and PZR level began to increase.

SIS pump 1A r ed.

02/11/81 2045 - RCS back on Rha letdown.

02/28/81 2400 - Unit 1 in mode 5 - Outage continued for repairs-on the generator exciter and decontamination

- due to containment spray down on February 11,

-1981.

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-327 UNIT 1 DATE February 1981 COMPLETED BY M. Eddings TELEPHONE (615) 842-0293 MONTH February 1981 DAY AVERAGE DAILY POWER LLVEL DAY AVERAGE DAILY POWER LEVEL

(MWe-Net) (MWe-Net)

-1 825 17 0 2 361 _

18 0 3 698 . 19 0 4 880 20 _

0

!5 10 21 0.

6 _.,_

0 22 0 .

7 0 -23 0 8 - 0 24 0

,9 0 25' O

- 10~ O' 26 1 0 ,

11_. 0. 27 0

12. 0 28 0

?l3- -0 ~29' 14 - :0 30

-15 O 31.

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INSTRUCTIONS-

On .this format,l list' the: average daily unit power level'in MWe-Net. for each day in the reporting month. 1 Compute to the nearest whole megawatt.

'(9/77)

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OPERATING DATA REPORT DOCKET NO. 50-327 DATE 3-4-81 COMPLETED BY Mike Eddings TELEPHONE (615) 842-0295 OPERATING STATUS

1. Unit Name: Seouoyah One Notes

2. Reporting Period: February, 1981

3. Licensed Thermal Power (MWt): 3411- -

4. Nameplate Rating (Gross MWe): 1220.58

5. Design Electrical Rating (Net MWe): 1148

6. Maximum Dependable Capacity (Gross MQe): 1183

7. Maximum Dependable Capacity ( Net 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 ( Net tNe):

10. Reasons For Restrictions, If Any: __.

This Month Yr-to-Date Cumulative

11. Hou'rs in Reporting Period 672 1416 8761

12. Number of Hours Reactor Was Critical 95.8 691.9 2230.3

13. . Reactor Reserve Shutdown Hours 0 0 0

14. . Hours Generator On-Line 87.7 562.5 1406.49

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 214112 1612767 3284797

17. Gross Electrical Energy Generated.(MWH). 71302 568550 1125871

18. Net Electrical Energy Generated (MWH) 67312 541710 1060550 19 .- Unit-Service Factor 13.1 76.9 76.9

20. Unit' Availability Factor .

13.1 76.9 76.9

21. Unit Capacity Factor (Using MDC Net) 8.7 64.2 64.2

22. Unit Capacity Factor (Using DER Net) 8.7 64.2 64.2

23. Unit Forced Outage Rate' 2- 9 38

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:

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March 7, 1981

26. TUnits In Test Status (Prior to Commercial Operation):

Forecast- Achieved

' INITIAL CRITICALITY 7-4-80 7-5-80 INITIAL ELECTRICITY -

8-21-80 =7-22-80 COMMERCIAL OPERATION - '2-21-81 (9/77)

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30-327 UNIT SHUTDO N3 AND' POWER REDUCTIONS DOCKET NO. .

UNIT NAME Sequoyah Oae DATE 3-4-61 COMPLETED.BY Mike Eddings REPORT HONTil February TELEPil0NE (6T5) 542-0295-~

".S em n o c. 3 Licensee N Cause & Corrective No. Date ~. S 0- 8 o5% Event $$ E*e Action to N $- $ jU$ Report # .$ 3 Prevent Recurrence 85 $- 2 & h3 o"

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f* u 37 2-1-81 F 11.2 A* 3 *0scillations in EllC system.

2-5-81 F 573.1 A 1- Excessive vibrations in generator exciter.

i' I 2 3 4 Fi Forced Reason: Method: I'xhibit G-Instructions S:. Scheduled A-Equipment Failure (Explain) a-Manual for Preparation of Data .

B-Haintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction. 4-Other (Explain) 0161)

E-Operator Training & License Examination F-Administrative G-Operational Error (Explain) 5 (9/77) li-Other (Explain) Exhibit I-Same Source t

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4 Plant Maintenance Summary The following significant maintenar items were completed during the month of February.1981:

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1. Rebuilt the fluid drive on the Unit i reciprocating charging pump.

2. Weighed Unit 1 ice baskets (SI-106) and added ice as required.

3. Began ice-loading in Unit 2 ice condenser.

) 4. Placed in service new vital inverters 2-I; 2-II; 2-III, and 2-VI.

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Outage Maintenance Summary February, 1981 The following significant maintenance items were completed during the month of February,1981.

Unit 1

1. Work was completed on containment cleanup and decontamination as result of the inadvertant RER spray down.

2. Investigation was conducted and work completed on the excessive vibration problem on the main generator / exciter. ,

3. Removed the steam strainers from the #1 and #2 steam lines.

4. The seats were changed out on the #1 and #4 governor valves as requested by Westinghouse.

5. Work was completed on the change out of the hydrogen igniter transformers for 32 transformers. There are still 13 transformers to be installed.

6. Completed the installation of the H2analyzer Pump modification kit as per NCR SQN EEB 8016.

7. Changed the AC and DC power on the level loops of the turbine driven auxiliary feedwater pump so it will be independent of the AC and DC pov6r on the level loops of the motor driven auxiliary feedwater pumps as per NCR SQN EEB 8020.

8. Work continued on hanger repair and inspection as per IE Bulletin 79-14.

Unit 2

1. Replaced the vital inverters with Solid State Controls inverters to meet voltage requirements for safety related equipment.

2. Work is continuing on changing various breakers and overloads on the 480V diesel auxiliary boards; 480V reactor MOV boards; 480V reactor vent boards; and the 480V control and auxiliacy building vent boards.

The breaker interrupting capacity will be increased from 14,000 amps RMS to 25,000 amps RMS and removing the current limiting reactors from the,480V shutdown boards. This work is required to reduce the minimum 161 kV grid voltage required for Unit 2.

3. Work was completed on the steam generator eddy current test.

Outage Maintenance Summary Februa ry, 1981 (Continued)

Unit 0 Or Items Affecting Unit I and 2

1. Completed the change out of the EGTS dampers to minimize damper leakage. *

2. Work is continuing on the replacement of the Public Safety repeater antenna system with everything except the ERCW, intake and diesel generator building in service.

3. The re-routing of train B power cables for the fire pumps continues. _

4. To fulfill NRC commitments work is continuing to coat exposed surfaces of cables outside primary containment containing one or both safety related divisions.

5. Structural restraints to reinforce the concrete block walls in the auxiliary building to seismically qualify them has been completed for the ones that affects the safety of Unit 1 equipment while work con-tinues on the remaining walls.

6. Work continues to add auxiliary control capauility for the station fire pumps. An exposure fire in panel 1-M-15 can cause a total loss of fire pump control. This auxiliary control will enable the fire pumps to be controlled from the 480V shutdown boards.

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