ML20037D225
| ML20037D225 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/04/1981 |
| From: | Dupree D TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20037D224 | List: |
| References | |
| NUDOCS 8105220312 | |
| Download: ML20037D225 (9) | |
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TENNESSEE V LLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT i
MONTHLY OPERATING REPORT APRIL 1, 1981 - APRIL 30, 1981 i
DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 i
Submitted By:
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PlantSyperintendent 4
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TABLE OF CONTENTS Operations Summary......
1 PORV's and Safety Valves Su ary..
1 Changes to the Offsite Dose Calculation Manual...
......,..... 1 Significant Operational Events.
2 Average Daily Unit Powtt Level.....................
3 Operating Data Report 4
Unit Shutdown and Power Reduction 5
Plant Maintenance Summary 6
Outage Maintenance Summary..
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o Operatiens Summary April, 1981 The f ' lowing summary describes the significant operational activities for the.
.h of April.
In suppcrt of this summary, a chronological log of significan, events is included in this report.
There were nineteen Licensee Event Reports and no Special Reports during April.
There were two scrams during April.
l Unit I was critical for 576.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, produced 633,923 MWH (gross) with 4.32 percent station use, resulting in an average hourly gross load of 1,102,187 KW during the month. The net heat rate for the month was 10,620 BTU /KWH.
There are 308.87 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 April 28, 1982. The capacity factor for the month was 73.5 percent.
Unit I was in mode 1 at 96% reactor power, generating 1086 MW(e) at the beginning of April, 1981. The unit operated between 95% ta 100% reactor power until 0715 Hrs, April 12, when the load was reduced for the Turbine Benchmark Test (STEAR-25). Reactor power was reduced to 63% to inhibit governor valve numbers 2 and 3.
Reactor power was then increased and main-tained at 78% for STEAR-25. At 1936 Hrs, April 12, governor valve numbers 2 and 3 were re-opened and reactor power was increased to 100%. The unit remained between 99%-100% reactor power until 0950 Hrs, April 23, when l
Start-Up Test 9.1, 10% load swing began. Start-Up Test 9.1 was completed at 1029 Hrs, April 23, and reactor power was increased to 100%. At 2240 Hrs, April 23, Start-Up Test 9.3 - 50% load rejection began. At 2242 Hrs, April 23, the reactor tripped (reactor trip #13) as a result of a low low l
steam generator level (#1) when two of the condensate booster pumps tripped during the 50% load rejection test. At 2341 Hrs, April 23, there was a safety injection caused by high steam flow with low Tavg indications. The unit was cooled down to the low end of mode 4 for required uaintenance. At 2042 Hrs, April 29, the reactor was taken critical and 100% reactor power was obtained at 1932 Hrs, April 30.
At 2241 Hrs, April 30, the reactor scramed as a result of a manual turbine trip as required by Start-Up Test i
9.4A.
At 2400 Hrs, April 30, the reactor was in mode 3.
PORV's and Safety Valves Summary Fo pressure operated relief safety valves were challenged during the month.
Changes to the Offsite Dose Calculation Manual There were no changes to the Offsite Dose Calculation Manual this month.
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Significant Operational Events Unit 1 Date Time Event 04/01/81 0001 Unit in mode 1, 96% Rx Pwr, 1086 MW(e).
04/12/81 0715 Began reducing Rx Pwr for Turbine Benchmark Test (STEAR-25). Rx Pwr held at ~ 78%, electrical generatiot not indicated.
04/12/81 1936 Increased Rx Pwr to 100%.
04/23/81 0950 Start-Up Test 9.1 - 10% load swing began.
04/23/81 1028 Start-Up Test 9.1 complete.
04/23/81 2240 Start-Up Test 9.3 - 50% load rejection.
04/23/81 2242 Reactor Trip #13 - Two cr'.densate booster pumps tripped during the 50% load rejection test (SU-9.3) causing a low low steam generator (#1) level.
04/23/81 2341 Safety injection caused by high steam flow with low Tavg indications.
04/29/81 2042 Peactor taken critical.
04/30/81 2241 Start-Up Test 9.4A - Reactor scramed (#14) as a result of a turbine trip (manual trip) at 100% power.
04/30/81 2400 Unit 1 in mode 3.
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AVERAGE DAILY UNIT POWER LEVEL j
DOCKET NO.
50-327 UNIT Se'quoyah One DATE May 4, 1981 COMPLETED BY David C. Dupree TELEP110NE (615) 842-0295 MONTH April
.:, DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HVe-Net) (MWe-Net) 1 1055 17 1101 2 '1072 18 1091 3 1069. 19 1111 4 1057 20 1102 5 1050 21 1098 6 1084 22 1087 7 1071 23 '1029 8 1063 24 0 .9 1053 25 0 10 1115 26 0 11 1101 27 0 j, 933 28 0 12 13 1105 29 0 14 109n 30 542 15 1097 31 16 1087 , 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) ' 't ,w ,w n -~ _-- .. ~ - -,
OPERATING DATA REPORT = DOCKET NO. 50-327 DATE May 1, 1981 COMPLETED BY David C. Dupree TELEPHONE (615) 842-0295 OPERATING STATUS 1. Unit Name: Sequoyah 1 Notes 2. Reporting Period: April 1981 3. Licensed Thermal Power (MWt): 3411 4. Nameplate Rating (Gross NWe): 1Z20.5 5. Design Electrical Rating (Net MWe): _ 1148 6. Maximum Dependabic Capacity (Grcss MWe): 1183 7. Maximum Dependable Capacity (Net HWe): 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 MWe): 10. Reasons For Restrictions, If Any: Thit Month Yr-to-Date Cumulative 11. Ilours in Reporting Period 719 '2879 10224 12. Number of !!ours Reactor Was Critical 576.7 1604.6 3143.2
- 13. -Reactor Reserve Shutdown Hours 0
0 0 14. Hours Generator On-Line 575.15 1446.85 1190.84 15. Unit Reserve Shutdown llours 0 0 0 16. Gross Thermal Energy Generated (MWH) 1,887,471 4,399,798 6,071,828 17. Gross Elect'rical Energy Generated (MWH) 633,923 1,507,723 2,065,044 18. Net Electrical Energy Generated (MWH) 606,568 1,436,062 1,954,902 19. Unit Service Factor 80.0 1 50.3 22.4 20. Ifnit Availability Factor 80.0 50.3 22.4 21. Unit Capacity Factor (Using HDC Net) 73.5 4 3. f. 16.7 22. Unit Capacity Factor (Using DER Net) 73.5 49.7 77.6 43.4 16.2 23. Unit Forced Outage Rate 20.0 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): 2 weeks Outage in September, 1981 for ice weighting and Type C entmt penetration leak testing. 25. If Shut Down At End Of Report Period, Estimated Date of Startup: May 1, 1981
- 26. Units 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 5-1-80 (9/77) 4_
I UNIT SHUTDOWNS AND P0kTR RELUCTIONS DOCKET NO. 50-327 UNIT NAME Seauovah One DATE May 4, 1981 COMPLETED BY David C. Dupree REPORT MONTH April TELEPHONE (615) 842-0295 "$ co B Licensee M Cause & Corrective cm m No. Date SE E .o " M Event E*o Action to ~. R yg g j ti j Report # %3 8.3 Prevent Recurrence $5 E U5c N" xmg o u o 9 13 810412 S 11.8 B 5 Unit derated for turbine base test (STEAR 25) 11 810423 F 142.55 A 3 Reactor Trip; Low Low Steam General Level (#1) During 50% Load Rejection when Cnd. Bstr Pmps 1B & IC Tripped O' 12 810430 B 1.3 B 2 Start-Up Test 9.4A, Turbine Trip at 100% Pwr, (Plant Trip Test) 6 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) Exhib~t I-Same Source
k Plant Maintenance Summary The following significant maintenance items were completed during the month of April, 1981: Mechanical Maintenance 1. Repaired residual heat removal isolation valve 1-FCV-74-2. 2. Replaced vacuum pump in 1-RM-90-119. Electrical Maintenance 1. Changed out the motor on 1-FCV-74-2. 2. Checked the clutches on the incore detector drives. 3. Replaced bad cables to the ice condeaser temperature recorder. 4. Cleared the grounds on the vital battery boards. 5. Adjusted the frequency en the vital inverters, j Instrument Maintenance 1. Repair the containment sump level transmitter 1-LT-63-178. Outage Maintenance Unit 1 1. Work continues on hanger repairs and inspections as per IE Bulletin 79-14. I 2. In an effort to resolve level instrumentation problems, modifications were made to the pressurizer level indication instrumentation and associated tubing. 3. During the outage significant progress vos made to the installation of a surge suppression network modules to all solid-state Caydon Controls, Incorporated relays. Unit 2 1. The Outage Sec' tion's fortion of the Unit 2 IE Bulletin 79-14 hanger work was completed. 4 <
.~ Outage Maintensuce (Continued) 2. Work began on the fabrication of piping for additional Unit 2 fire sprinklers. This work is required to meet an NRC commitment and i must be completed by Unit 2 fuel loading. Unit 0 or Items Affecting Unit I and 2 f 1. Work progressed to revise piping to the HVAC equipment _ serving the main control room. This revision will increase ERCW flow and avoid corrosica problems. 2. Work started to provide. security access screens to the auxiliary building exhaust fan housings. 3. Additional auxiliary control capability for the station fire pumps is 75% complete. 1 1,. 4. Work was completed to provide vital power for the NRC phones in the main control rooms. 5. The installation of the perimeter Alert II detection system was com-pleted. 6. Hnager work resulting from the re-analysis of support systems for piping with insulation loading continues. 4 i 7. Work began to add over/under voltage annunciation and protection for the 6.9 kilovolt shutdown boards. i h i s l.. f - - -. -}}