ML20065C638

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Monthly Operating Repts for Jul 1982
ML20065C638
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 08/11/1982
From: Dupree D, Eddings M, Mason C
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20065C633 List:
References
NUDOCS 8209240261
Download: ML20065C638 (14)
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TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT JULY 1, 1982 - JULY 31, 1982 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER H-328 LICENSE NUMBER DPR-79 "30 vit- d By: M/

P5wer Plant Superintendent 8209240261 820811 DR ADOCK 05000327 PDR

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TABLE OF CONTENTS Operations Summary . . . . . . . . . . . . . .. . .. . . . . . . . ... 1

, Significant Operational Events . . . . . . . .. . .. . . . .. . . . .. 1-2 PORV's and Safety Valves Summary . . . . . . . . . .. . . . . . . . . .. 2 Licensee Events and Special Reports . . . . . . . .. . . .. . . . . . . 3-4 Offsite Dose Calculation Manual Changes . . .. . .. . . .. . . . . . . 5 Operating Data l Unit 1 ... ... ... . . . . .. . . .... . . . . . ... .. 6-8 i

Unit 2 . .... . ... . . . . .. . . . . .. . .. . . . . . .. 9-11 Plant Maintenance Summary .. . . . . .. . . . . . . . . .. . . .. . 12 Field Services Maintenance Summary . . . . . . . . . . . .. . . ... . . 12 i

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r Operatiens Summary i

July 1982 The following summary describes the significant operational activities for the month of July. .In support of this summary, a chronological log of significant events is included in this report.

Unit 1

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. Unit I was critical for 744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br />, produced 850,930 MWH (gross) with 3.32 percent station service use resulting in an average hourly gross load of 1,114,723 KW during the month. The net heat rate for the month was 10,545 BTU /KWH. There are 33.92 full power days estimated remaining until the end of cycle 1 fuel. With a capacity factor of 85 percent the target EOC exposure-would be reached September 9, 1982. The capacity factor for the month was 98.3 percent.

There were no reactor scrams, no manual shutdowns, and no power re-Jactivas during July.

Unit 2 Unit 2 was critical for 744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br />, produced 836,720 MWH (gross) with 3.49 percent station service use, resulting in an average hourly gross load of 1,124,624 kW during the month. The net heat rate for the month was 10,600 BTU /KWH. There are 276.42 full power days estimated remaining until the end of cycle 1 fuel. With a capacity factor of 85 percent the target EOC exposure would be reached June 22, 1983. The capacity factor for the month was 96.7 percent.

There were no reactor scrams, no manual shutdowns, and one power i reduction during July.

Significant Operational Events Unit 1 Date Time Event 07/01/82 0001 Reactor in mode 1 at 100% power pro-ducing 1145 MWe.

07/09/82 2345 Reactor reduced to 92% power, 1038 MWe for SI-90.1 - Reactor Trip l Instrumentation Monthly Check.

l 07/10/82 0530 Reactor at 100% power producing 1145 MWe.

T Significant Operstional Events (Continued)

Unit 1 Date Time Event 07/29/82 0625 Reactor at 96% power for SI-90.6 and SI-90.7 steam flow bistables.

1700 Reactor at 100% power producing 1145 MWe.

07/31/82 2355 Reactor in mode 1 at 100% power pro-ducing 1145 MWe.

Unit 2 07/01/82 0001 Reactor in mode 1 at 100% power pro-ducing 1140 MWe.

0622 Reactor at 95% power producing 1120 MWe for SI-90.62 - Steam Flow Bistables.

1400 Reactor at 100% power producing 1150 MWe.

07/13/82 2215 Began power reduction for an ice condenser inspection.

07/14/82 0345 Reactor at 23% power producing 189 MWe and holding while an inspection team is in the ice condenser.

1749 Began power ascension.

2130 Reactor at 100% power producing 1140 MWe.

07/30/82 0755 Reactor at 93% power for SI-90.72 - Steam Flow Deviation.

1135 Reactor at 100% power producing 1140 MWe.

07/31/82 2359 Reactor in mode 1 at 100% power producing 1140 MWe.

! Sequoyah Nuclear Plant had a station capacity factor of 97.5% with a com-bined gross output of 1,687,650 MWH's for the month.

PORV's and Safety Valves Summary No PORV's or safety valves were challenged during the month.

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Licensee Events cnd Sp:cial Raports The following Licensee Event Reports (LER's) were sent during July 1982, to the Assistant Director of Nuclear Power (Operations) for reporting to the Nuclear Regulatory Commission.

Unit 1 LER SUBJECT SQR0-50-327/82074 AFW automatic control valve 1-LCV-3-171 failed to open on demand due to low controller output signal. AFW valve 1-LCV-3-122 inoperable due to a failed hydraulic pump motor caused by a deadheaded pump.

SQRO-50-327/82075 Steam generator blowdown containment isolation valve 1-FCV-1-7 failed closed and would not open. The valve operator diaphragm ruptured due to high temperatures.

SQRO-50-327/82076 The ice condenser ice bed temperature monitoring syst m was inoperable. A wire was broken when the recorder drawer was being pulled out.

SQRO-50-327/82078 The oxygen concentration in the waste gas decay tank J was found to be 8.1% by grab sample. The oxygen monitor was inoperable due to out of spec calibration gas.

SQRO-50-327/82079 RWST level channel 1-LT-63-51 bistable was left in the test position, therefore, the channel was inoperable.

SQRO-50-327/82080 Various room coolers and other equipment was inoperable when the control and auxiliary vent board tripped because of a short in the control transformer to the control building emergency pressurization fan.

SQRO-50-327/82082 AFW level control valve 1-LCV-3-164 failed to control in automatic due to the setpoint indicator control belt slipping.

i SQRO-50-327/82086 AFW back pressure control valve 1-PCV-3-122 l was leaking oil from a cracked tube tee fitting.

SQRO-50-327/82088 Containment hydrogen monitor 1-H 2A-43-210 failed SI-287 due to a clogged sample line orifice.

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SQR0-50-327/82089 Waste gas system oxygen analyzer 0-0,A-43-5000 t failed surveillance because of a faulty zero setpoint potentiometer.

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r Licentee Events and Special R: ports Unit 1 (Continued)

LER SUBJECT SQRO-50-327/82092 AFW level control valve failed to open in auto during testing due to dirty handswitch contacts.

Unit 2 SQR0-50-328/82077 An ice condenser intermediate deck door was frozen closed due to a leaking drain line.

SQR0-50-328/82081 AFW automatic control valve 2-PCV-3-122 failed to open on demand due to leaking oil and servo valve failure. Dirty oil is believed to be the cause.

SQRO-50-328/82083 Loop 3 steam generator blowdown containment isolation valve would not open due to a grounded wire.

SQRO-50-328/82084 Containment pressure transmitter 2-PDT-30-43 bistable setting was out of limits due to instrument drift.

SQRO-50-328/82085 The ice condenser lower compartment average air temperature was greater than 27*F on two occasions due to leaking valves and air flow through an inoperable fan.

SQR0-50-32Cf82087 On July 9 at 2100C and July 13 at 0700C one point of the ice condenser ice bed exceeded 27*F. Missing floor drain papers, unsealed inlet doors and an open drain line were found as the cause.

SQRO-50-328/82090 AFW 1evel control valve 2-LCV-3-171 would not open past two-thirds open due to a loose diaphragm spring tension adjustmca.t nut.

SQR0-50-328/82091 Steam generator blowdown containment isolation valve 2-FCV-1-7 would not remain open. The upper limit switch was out of adjustment.

Special Reports There were no special reports sent during the month of July.

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Offaite Doze Calculation M: nuel Chrngu There were no changes to the Sequoyah Nuclear Plant ODCM during July.

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r OPERATING DATA REPORT DOCKET NO. 50-327 DATE August 3, 1982 COMPLETED BY M. Eddings TELEPHONE (615) 751-0343 OPERATING STATUS

~1. . Unit Name: Sequoyah One Notes

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2. Reporting Period: .Iuly 1982
3. Licensed Thermal Power (MWt): 3411
4. Nameplate Rating (Gross MWe): 1220.56 ___
5. Design Electrical Rating (Net MWe): 1148
6. Maximum Dependable Capacity (Gross MWe): 1163
7. Maximum Dependable Capacity (Net MWe): 1128
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 MWe):
10. Reasons For Restrictions, If Any:

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744 5087 9504
12. Number of Hours Reactor Was Critical 744 3745.7 6547
13. Reactor Reserve Shutdown Hours 0 0 'O
14. Hours Generator On-Line 744 3641.3 6331.6
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 2,532,497 11,864,679 19,929,633
17. Gross Electrical Energy Generated (MWH) 850,930 3,991,170 6,637,120

- 1, 8 . Net Electrical Energy Generated (MWH) 822,710 3,827,860 6,354,884

19. Unit Service Factor 100 71.6 66.6 .
20. Unit Availability Factor 100 71.6 66.6
21. Unit Capacity Factor (Using MDC Net) 98.0 66.7 59.3
22. Unit Capacity Factor (Using DER Net) 96.3 65.5 58.2
23. Unit Forced Outage Rate 0 21.0 20.0
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling / modification outage September 10 (scheduled) 6 months.

25. If Shut Down At End Of Report Period, Estimated Date of Startup:
26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY 7-4-80 7-5-80 INITIAL ELECTRICITY U-z i-U U /-zz-su COMMERCIAL OPERATION 7-1-81 7-1-81 (9/77)

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. _ 50-327 UNIT One DATE August 3, 1982 COMPLETED BY M. Eddings TELEPIIONE (615) 751-0343 MONTH July 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) -

1 1096 17 1100 2 1094 18 1098 3 1093 19 1098 4 1096 20 1098 i 5 1097 21 1099 6 1091 22 1098 7 1098 23 1099 8 1099 24 1096

-9 1093 25 1098 10 1086 26 1097 11 1098 27 1096 12 1100 28 1097 13 1101 29 1075 14 1100 30 1096 15 1099 31 1099 16 1102 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)

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UNIT SHUID0k'NS AND POkT.R REDUCTIONS DOCKET NO. 50-327 -

UNIT NAME Sequovah One DATE August 3, 1982 COMPLETED BY M. Eddings REPORT MONTH July 1982 TELEPHONE (bla) /31-0343 m

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a Ea Cause & Corrective 0 $ "g Dat* C "o .e y Event 3.g g.g Action to R

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No Shutdowns or Power Reductions Greater Than 20% During the Month s

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

E-Operator Training & License Examination Outage F-Administrative 5-Reduction L-Lperational Error (Explain) 9-Other 5 (9/77) H-Other (Explain) Exhibit I-Same Source

OPERATING DATA REPORT DOCKET NO. 50-328 DATE August 1, 1982 COMPLETED BY David Dupree TELEPHONE (615) 751-0343 OPERATING STATUS e

1. Unit Name: Sequoyah Two Notes
2. Reporting Period: July 1982
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 MWe): 1163
7. Maximum Dependable Capacity (Net MWe): ___ 1128
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: >

Turbine will not meet d4 sign specifications. Unit two is rated the same as Sequoyah One.

9. Power Level To Which Restricted, If Any (Net MWe):
10. Reasons For Restrictions, If Any:

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744 1464 1464
12. Number of Hours Reactor Was Critical 744 1441.3 1441.3
13. Reactor Reserve Shutdown Hours 0 0 0
14. Hours Generator On-Line 744 1402.95 1402.95
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 2,498,076.8 4,416,358 4,416,358
17. Gross Electrical Energy Generated (MWH) 836,720 1,483,130___ 1,483,130
18. Net Electrical Energy Generated (MWH) 807,539 1,427,581 1,427,581
19. Unit Service Factor 100 95.8 95.8
20. Unit Availability Factor 100 95.8 95.8
21. Unit Capacity Factor (Using MDC Net) 96.2 86.4 86.4
22. Unit Capacity Factor (Using DER Net)- 94.55 84.9 84.9
23. Unit Forced Outage Rate 0.0 4.2 4.2
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Ice weighing, 11-4-82, per Technical Specifications.

25. If Shut Down At End Of Report Period, Estimated Date of Startup: NA
26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY 11-5-81 11-5-81 INITIAL ELECTRICITY 12-31-81 12-31-81 COMMERCIAL OPERATION 6-1-82 6-1-82 (9/77) s# #

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-328 UNIT Two DATE August 4, 1982 COMPLETED BY David Dupree TELEPHONE (615) 751-0343 MONTH July 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1,110 17 1,105 2 1,098 18 1,102 3 1.096 19 1.102 4 1,108 20 1,102 5 1.109 21 1.103 6 1 I10 22 1,104 7 1,109 23 1,105 8 1,107 24 1,103 9 1,100 25 1,103 10 1,102 26 1,102 11 1,045 27 1,102 12 1,101 28 1,100 13 1,096 29 1,100 14 500 30 1.090 l 15 1.101 31 1.102 l

16 1,105 i INSTRUCTIONS On this format, list the average daily unit power Icvel in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

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UNIT SEUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-328 UNIT NAME Sequoyah Two DATE August 4, 1982.

COMPLETED BY David Dupree REPORT MONTH July TELEPHONE (615) 751-0343 m

b 4J g* e, n  % w3 Licensee g g Cause & Corrective "o .S $ @ .e .5 g Event 3.g g.g Action to R %8 y jgy Report # ge g.g Prevent Recurrence 05 a UE =

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xmlc 3 82/07/13 F 0 B 5 Unit derated to 25% reactor power for ice condenser inspection.

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

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

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Plant Maintenence Summary The following significant maintenance items were completed during the month of July 1982.

Mechanical Maintenance

1. Replaced the turbochargers on diesel generators 2A1 and 2A2.

Electrical Maintenance

1. Repairs continue on the spare reactor coolant pump.

Instrument Maintenance None reportable.

Field Services Maintenance

1. ECN 5158, WP 9119 R1 - Diesel Generator Batteries and Racks Replacement -

Diesel generator 2A-A batteries and racks were changed out. This ECN is complete.

2. ECN 5466, WP 9759 - Roof Hatch Alarm - 480v rooms 2A and 1A - Diesel Generator Building - All work is complete except for painting. The alarms are operational.
3. ECN 5464, WP 9761 - Vehicle Gate and PA System - The ECN is complete.
4. ECN 5216 - Replacement of Check Valve 1-77-956 With a Diaphragm Valve -

This ECN is complete.

5. ECN 5376, WP 9715 - Fire Protection Valve Post Indicators - This ECN is complete.

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