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| TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT AUGUST 1, 1982 - AUGUST 31, 1982 4
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| UNIT I DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 Submitted By: /M Power Plant Superintendent 1
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| 8211020517 820915 ' ~ ~ ~
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| DR ADOCK 05000327
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| , PDR
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| I 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 Unit 1 . . .. . . .. . . . . . . . . . . . . . . . . . . . . . . . 6-8 Unit 2 .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9-11 Plant Maintenance Summary . . . . . . . . . . . . . . . . . . . . . . . . 12 l
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| 1 Oparetiens Summary August 1982 l
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| I The following summary describes the significant operational activities
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| ; for the month of August. In support of this summary, a chronological log of significant events is included in this report.
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| i Unit 1 Unit I was critical for 744 hours, produced 846,830 MWH (gross) with 3.30 percent station service use resulting in an average hourly gross load of 1,138,212 KW during the month. The net heat rate for the month was 10,600 BTU /KWH. There are 2.98 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 3, 1982. The capacity factor for the month was 97.9 percent.
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| There were no reactor scrams, no manual shutdowns, and one power re-duction during August.
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| Unit 2 Unit 2 was critical for 736.3 hours, produced 811,640 MWH (gross) with 3.45 percent station service use, resulting in an average hourly gross load
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| ), of 1,104,828 kW during the month. The net heat rate for the month was 10,430 i BTU /KWH. There are 247.27 full power days estimated remaining until the end of cycle 1 fuel. With a capacity factor of 85 percent the target EOC I exposure would be reached June 17, 1983. The capacity factor for the month was 93.8 percent.
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| There was one reactor scram, no manual shutdowns, and one power reduction during August.
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| Significant Operational Events Unit 1 Date Time Event 08/01/82 0001 Reactor in mode 1 at 100% power pro-ducing 1145 MWe.
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| 08/21/82 0014 Reactor at 100% power producing 1145 MWe. 3A heater drain tripped due to a low cil level. The reactor power was reduced to 90%
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| and the turbine was manually ran back to 85% power.
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| I Signifiernt Oparatienil Evrnts (Continued)
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| Unit 1 Date Time Event 08/21/82 0017 Auto turbine runback to ~ 75%. Manually ran back to 65%.
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| 0030 Began power ascension.
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| 0130 Reactor at 85% power and holding.
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| 0330 Began increasing power.
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| 0505 Reactor at 100% power producing 1145 MWe.
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| 08/27/82 0440 Began reducing power to clear the hi-steam flow bistables for SI-90.6.
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| 0643 Reactor at 92.5% power.
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| 0905 Began power ascension.
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| i 1430 Reactor at 100% power producing 1145 j MWe.
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| 08/31/82 2359 Reactor in mode 1 at 100% power pro-ducing 1145 MWe.
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| Unit 2 08/01/82 0001 Reactor in mode I at 100% power producing 1140 MWe.
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| 08/05/82 0640 Began reducing load for maintenance on #3A heater drain tank pump motor.
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| 0800 Reactor at 98% power, producing 1112 MWe.
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| ; 0825 Began power ascension.
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| 1000 Reactor at 100% power, producing 1140 MWe.
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| 08/11/82 0841 Began reducing load to check the oil level of #1 reactor coolant pump.
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| 1300 Reactor at 25% power producing 230 MWe.
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| 1637 Began power ascension.
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| l 3 .
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| m -a.. -,-- , - - - - -, -, - . . - , - - ,e-
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| Significent Operational Events (Continued)
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| Unit 2 Date Time Event 08/11/82 1830 Reactor at 74% power, producing 847 MWe and holding for maintenance on #7A heater drain tank pump motor.
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| 2300 Reactor at 70% power, producing 843 MWe.
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| 08/12/82 0229 Began power ascension.
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| 1325 Reactor at 100% power, producing 1150 MWe.
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| 08/26/82 1041 Began power reduction for maintenance on #7B heater drain tank pump.
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| 1214 Reactor at 90% power.
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| 1425 Began power ascension.
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| 1610 Reactor at 100% power, producing 1150 MWe.
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| 08/27/82 2001 Feedwater valve 3-48 failed closed due to water ir. the junction box causing the reacter to trip.
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| 08/28/82 0345 Reactor taken critical.
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| 0523 Unit tied on line. Power increased to 30%
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| and holding for secondary chemistry.
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| 1901 Began power ascension.
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| 08/29/82 0618 Reactor at 100% power producing 1135 MWe.
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| 1235 Began load reduction to repair an oil leak on #3C heater drain tank pump.
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| 1300 Reactor at 93% power, producing 1080 MWe.
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| 1322 Began power ascension.
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| 1515 Reactor at 100% power.
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| 08/31/82 2359 Reactor in mode 1 at 100% power, producing 1150 MWe.
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| 7 PORV's and Safety Valves Summary No PORV's or safety valves were challenged during the month.
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| Licensee Events and Special Reports The following Licensee Event Reports (LER's) were sent during August 1982, to the Assistant Director of Nuclear Power (Operations) for reporting to the Nuclear Regulatory Commission.
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| Unit I LER SUBJECT SQRO-50-327/82093 The ice condenser intermediate deck doors were iced over and would not pass SI-108 (Lift Test) due to a ruptured drain line leaking water.
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| SQR0-50-327/82094 Diesel generator IA-A was inoperable due to a broken oil sight glass.
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| SQRO-50-327/82095 A Westinghouse review discovered that an unde-tectable failure could exist in the on-line test system of the solid state protection system (SSPS) due to the possible failure of the switch contacts to close.
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| SQRO-50-327/82097 The upper containment personnel airlock inner door locking mechanism failed due to a broken pin on the door latch bar connecting red. This was caused by a weld failure during normal operation.
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| SQRO-50-327/82098 Waste gas decay tank C oxygen concentration indicated 2.74%. This was due to air in-leakage and the monitor was reading high due to a zero shift in the calibration of the indicator.
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| SQRO-50-327/82099 Refueling water storage tank level channel 1-LT-63-50 failed low due to a faulty circuit board in the transmitter.
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| SQRO-50-327/82100 AFW automatic control valve 1-LCV-3-174 would not operate in manual due to a leaking diaphragm at the operator flange.
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| SQRO-50-327/82101 The neutron instrumentation power range channel N41 failed low due to a defective high range power supply.
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| SQRO-50-327/82102 1Al-A control and auxiliary vent boards tripped rendering various ventilation equipment and rad monitors inoperable. They tripped due to a burned out phase bus link caused by a loose connection.
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| Licensee Evrnte and Spacial Rrparts Unit 2 LER SUBJECT SQRO-50-328/82096 Safety injection pump 2A-A failed to start due to an improperly locked locking ring on a plug connector in the back of the handswitch.
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| SQRO-50-328/82103 Pressurizer relief tank level channel 2-LT-68-312C failed due to a malfunction in the loop trans-mitter section. This instrument has been deleted by a Tech Spec change.
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| SQRO-50-328/82104 Overpower delta temperature channel 2-TI-68-2D failed low due to the resistance to voltage converters having an instrument span shift.
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| This resulted in the out-of-tolerance indica-tions.
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| SQRO-50-328/82105 Refueling water storage tank level channel 2-LT-63-52 failed low due to a faulty amplifier card.
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| Special Reports There were no special reports sent during the month of August.
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| Offsite Dose Calculation Manual Changes There were no changes to the Sequoyah Nuclear Plant ODCM during August.
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| I a
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| OPERATING DATA REPORT DOCKET NO. 50-327 DATE September 4,1982 COMPLETED BY M. Eddings TELEPHONE (615) 751-0343 OPERATING STATUS
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| : 1. Unit Name: Sequoyah One Notes
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| : 2. Reporting Period: August 1982
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| : 3. Licensed Thermal Power (MWt): 3411
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| : 4. Nameplate Rating (Gross MWe): 1220.58
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| : 5. Design Electrical Rating (Net MWe): 1148
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| : 6. Maximum Dependable Capacity (Gross MWe): 1163
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| : 7. Maximum Dependable Capacity (Net MWe): 1128
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| : 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
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| : 9. Power Level To Which Restricted, If Any (Net MWe):
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| : 10. Reasons For Restrictions, If Any:
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| This Month Yr-to-Date Cumulative
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| : 11. Hours in Reporting Period 744 5831 10248
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| : 12. Number of Hours Reactor Was Critical 744 4,489.7 7,291
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| : 13. Reactor Reserve Shutdown Hours 0 0 0
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| : 14. Hours Generator On-Line 744 4,385.3 7,075.6
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| : 15. Unit Reserve Shutdown Hours 0 0 0
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| : 16. Gross Thermal Energy Generated (MWH) 2,533,093 14,397,772 22,462,726
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| : 17. Gross Electrical Energy Generated (MWH) 846,830 4,838,000 7,483,950
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| : 18. Net Electrical Energy Generated (MWH) 818,626 4,646,486 7,173,510
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| : 19. Unit Service Factor 100 75.2 69.0
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| : 20. Unit Availability Factor 100 75.2 69.0
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| : 21. Unit Capacity Factor (Using MDC Net) 97.5 70.6 62.1
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| : 22. Unit Capacity Factor (Using DER Net) 95.9 69.4 61.0
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| : 23. Unit Forced Outage Rate 0 18.0 18.3
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| : 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
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| Refueling / Modification Outage, September 10 (Scheduled), 6 Months
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| : 25. If Shut Down At End Of Report Period, Estimated Date of Startup:
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| , 26. Units In Test Status (Prior to Commercial Operation):
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| Forecast Achieved INITIAL CRITICALITY 7-4-80 7-5-80 INITIAL ELECTRICITY s-zi-su /-zz-su COMMERCIAL GPERATION /-1-51 /-1-81 (9/77) t AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-327 UNIT Sequoyah One DATE September 4, 1982 COMPLETED BY M. Bradford TELEPHONE (615) 751-0343 MONTH August DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1,102 17 1,097 2 1,101 18 1,105 3 1,103 19 1,103 4 1,099 20 1,104 5 1,099 21 1,376 6 1,100 22 1,107 7 1,100 23 1,105 8 1,099 24 1,102 9 1,099 25 1,102 10 1,101 26 1,099 11 1.101 27 1,084 12 1,103 28 1,100 13 1,105 29 1,099 14 1.105 30 1,100 l 15 1,102 31 1,101 16 1,101 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.
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| l (9/77) l
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| UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-327 .
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| UNIT NAME sequoyah one DATE September 4, 1982 COMPLETED BY ti . t.odings REPORT MONTH August TELEPHONE (615) 751-0343 4
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| % u No. Date cn m o eo S Licensee g g, Cause & Corrective "o .S @ y. 8 Event 3.@ g.g Action to R
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| yg g juy Report # g3 g.g Prevent Recurrence A
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| $6 E $5
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| ::c m 5 O
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| 2 82/08/21 F A 5 #3 heater drain tank pump trip on Lo oil level. Turbine ran back to 65%.
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| 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)
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| 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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| F OPERATING DATA REPORT DOCKET NO. 50-328 DATE September 4, 1982 COMPLETED BY David Dupree TELEPHONE (615) 751-0343 OPERATING STATUS
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| : 1. Unit Name: Seouovh5 Two Notes
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| : 2. Reporting Period: August, 1982
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| : 3. Licensed Thermal Power (MWt): 3411
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| : 4. Nameplate Rating (Gross MWe): 1220.58
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| : 5. Design Electrical Rating (Net MWe): 1148
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| : 6. Maximum Dependable Capacity (Gross MWe): 1163
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| : 7. Maximum Dependable Capacity (Net MWe): 1128
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| : 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
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| : 9. Power Level To Which Restricted, If Any (Net MWe):
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| : 10. Reasons For Restrictions, If Any:
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| This Month Yr-to-Date Cumulative
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| : 11. Hours in Reporting Period 744 2208 2208
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| : 12. Number of Hours Reactor Was Critical 736.3 2177.6 2177.6
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| : 13. Reactor Reserve Shutdown Hours 0 0 0
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| : 14. Hours Generator On-Line 734.6 2137.6 2137.6
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| : 15. Unit Reserve Shutdown Hours 0 0 0
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| : 16. Gross Thermal Energy Generated (MWH) 2,386,212.4 6,802,570.4 6,802,570.4
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| : 17. Gross Electrical Energy Generated (MWH) 811,640 2,294,770 2,294,770
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| : 18. Net Electrical Energy Generated (MWH) 783,678.6 2,211,259.6 2,211,259.6
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| : 19. Unit Service Factor 98.7 96.8 96.8
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| : 20. Unit Availability Factor 98.7 96.8 96.8
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| : 21. Unit Capacity Factor (Using MDC Net) 93.4 88.8 88.8
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| : 22. Unit Capacity Factor (Using DER Net) 91.7 87.2 87.2
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| : 23. Unit Forced Outage Rate 1.3 2.2 2.2
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| : 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
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| Ice Weighing, 11-4-82. Por Technien1 Sp eci fi cn ei nns
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| : 25. If Shut Down At End Of Report Period, Estimated Date of Startup: NA
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| : 26. Units In Test Status (Prior to Commercial Operation):
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| 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) r AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-328 UNIT Sequoyah Two DATE September 3, 1982 COMPLETED BY David Dupree TELEPHONE (615) 751-0343 1
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| MONTH August 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE D'AILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1,104 17 1,101 2 1,104 18 1,099 3 1,105 19 1,104 4 1,103 20 1,107 5 1,099 21 1,107 6 1.100 22 1.105 7 1,100 23 1,106 8 1.100 24 1,104 9 1,101 25 1,103 10 1,101 26 1,085 11 762 27 915 12 1,008 28 241 13 1,105 29 1,058 14 1,105 30 1,103 i 15 1,105 31 1,096 16 1,103 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.
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| (9/77) f t
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| 4 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-328 '
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| UNIT NAME Sequoyah Two DATE September 4, 1982 COMPLETED BY David Dupree REPORT MONTH August TELEPHONE (613) 751-0343
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| % a e- ~ is e 3 Licensee a, g, Cause & Corrective 3* p# ''
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| o J3 0 $ m Ji g Event 3 jj g 4j Action to
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| $l $5 E SU$ Report # g, g gg Prevent Recurrence YD N NE O A
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| *:mfa 4 82/08/11 F 0 B 5 Reduce load to 25% for maintenance on #1 R.C.P. oil level.
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| 6 82/08/27 F 9.4 A 3 Water in junction box caused a short in
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| , solenoid circuit. Valve 3-48 (loop #2) failed closed caused unit to trip.
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| I 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)
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| 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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| Plent Mainteninca Summary The following significant maintenance items were completed during the month of August 1982:
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| Mechanical Maintenance
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| : 1. Allis-Chalmer concentrate pumps were installed on the boric acid evaporator package A.
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| : 2. Both Unit I and 2 positive displacement charging pumps were repacked and their plungers replaced.
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| Electrical Maintenance
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| : 1. Rebuilding of the spare reactor coolant pump motor continues.
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| : 2. lA-A control and auxiliary vent board phase bus link was replaced.
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| Instrument Maintenance None reportable.
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