ML19263D722
ML19263D722 | |
Person / Time | |
---|---|
Site: | Beaver Valley |
Issue date: | 04/01/1979 |
From: | Spitznogle A DUQUESNE LIGHT CO. |
To: | |
Shared Package | |
ML19263D719 | List: |
References | |
NUDOCS 7904130187 | |
Download: ML19263D722 (5) | |
Text
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OPERATING DATA REPORT DOCKET NO. 50-334 DATE 4/1/74 EL P 10.NE. I -
OPERATING STATUS
- 1. Unit Name: Beaver Valley Power Station, Unit #1 Notes
- 2. Reporting Period: March, 1979
- 3. Licensed Thermal Power (51Wt): AA
- 4. Nameplate Rating (Gross 5the): 923
- 5. Design Electrical Rating (Net StWe): 852
- 6. Sf aximum Dependable Capacity (Gross 51We): 845
- 7. hinximum Dependable Capacity (Net 5tWe): 817
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since List Report. Give Reasons:
Item 7 upgraded due to power output increase gained from modifications to moisture separator reheaters. -
- 9. Power Level To Which Restricted if Any (Net 51We): None
- 10. Reasons For Restrictions. If Any: N/A This 51onth Yr. to Date ~ Cumulative
- 11. !!ours in Reporting Period 744 2,160 26,976
- 12. Number Of flours Reactor Was Critical 163.59 1,166.61 11,362.68
- 13. Reactor Resene Shutdown flours 0 0 4.482.80
- 14. Ilours Generator On Line 146.24 1.106.57 10.710.74
- 15. Unit Reserve Shutdown flours 0 0 0
- 16. Gross Thennal Energy Generated (31Wil) 336,146.31 _2,557.151.22 23,425,546.17
- 17. Gross Electrical Energy Generated (31Wil) 110.700 834.600 7.173.340
- 18. Net Electrical Energy Generated (5twil) 109 171 774_099 6.567.357
- 19. Unit Service Factor 19.7 51.2 47.8
- 20. Unit Availability Factor 19.7 51.2 47.8
- 21. Unit Capacity Factor (Using SIDC Net) 16.8 43.9 40.8
- 22. Unit Capacity Factor (Using DER Net) 16.1 42.1 39.1
- 23. Unit Forced Outage Rate 80.3 49.1 40.9
- 24. Shutdowns Scheduled Over Next 6 Stonths (Type. Date.and Duration of Eacht:
Major Modification and Refueling Outage on July 2, 1979.
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup: MAV II 1979
- 26. Units In Test Status (Prior to Commercial Operationi: Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A C0515t ERCIAL OPER ATION __N/A N/A 70041301%1 s T
AVERAGE DAll UNIT POWER LEVEL DOCKET NO. 50-334 UNIT - BVPS Unit #1 DATE 4/2/79 COMPLETED BY A.E. Spit:nogle TELEPilONE 412-643-5023 MONTil March, 1979 LAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net) (MWe NetI g 742 g7 0 2 746 3g 0 3 0 g9 0 4 566 20 0 5 644 0 21 6 0 0 22 7 367 0 23 8 734 0 24 9 491 0 25 10 0 0 26 11 0 0 27 12 0 0 28 13 0 0 29 14 0 0 30 15 0 ,
3, o 16 0 INSTRUCTIONS On this format. list the nerage daily unit power leselin MWe Net for each day in the reporting month. Coinpute to the nearest whole megawatt.
19/77)
DOCKET NO. 50-334 UNITSHUTDOWNS AND POWER REDUCTIONS BVPS Unit ul UNIT NAME DATE 4/2/79 March, 1979 COMPLETED DY A. E. SDitznogle REPORT MONTil TELEPilONE 412-643-5023
- , jE 3g hYk Licensee 5-t, E,7 Cause & Correctise No. Date g g jgE Event 7
@.? Action to
- j: E j 5, g Repor! = WO j' Prevent Recurrence 6
10 790303 F 26.41 A 3 None HA TURBIN Reactor tripped during turbine thrust bearing trip check. Checked thrust bearing; repaired TV-MS-105B.
11 790305 F 36.25 F 1 None ZZ ZZZZZZ Reactor shutdown due to high water level (greater than 680') in Ohio River. Unit returned to service after river level decreased.
12 790309 F 535.1 F 1 79-7 ZZ ZZZZZZ Reactor shutdown for design review of piping supports for Reactor Coolant ,
and various other Category I piping.
I 2 3 4 F: Forced Reason: Method: Exhibit G Instructions S: Schedu!ed A Equipment Failure (Explain) 1 -Manual for Preparation of Data B Maintenance ei Test 2-Manual Scrarn. Entr> Sheets for Licensee C Refueling 3- Automatic Scram. Event Report iLERn rife (NUREG D-Regulatory Restriction 4-Ot her I E xplain) 01611 I? Operator Training & License Examination F. Ad nunist rative 5 G-Operational Error (lixplain t E stubit I - Saine'Somce 19/77) Il Other (lisplain )
1 a
DUQUESNE LIGHT COMPANY Beaver Valley power Station Narrative Summary Of Operating Experience - March, 1979 Date Event March 1 to Station was in Operational Mode 1 at 90% reactor power.
March 2 March 3 Reactor tripped from 90% power at 0043 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br /> during the turbine thrust bearing trip check. The reactor was critical at 0209 hours0.00242 days <br />0.0581 hours <br />3.455688e-4 weeks <br />7.95245e-5 months <br />. One of the turbine driven auxiliary feedwater pump steam supply trip valves Jammed partially open and the pump was removed from service to repair the valve. Due to the inability of the maintenance isolation valves to provide tight shutoff, a reactor shutdown and system partial cooldown was initiated at 1038 hours0.012 days <br />0.288 hours <br />0.00172 weeks <br />3.94959e-4 months <br /> to repair the trip valve [TV-MS-105B]. After repairs to the trip valve, a reactor heatup was commenced at 1930 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.34365e-4 months <br /> and the reactor was critical at 2254 hours0.0261 days <br />0.626 hours <br />0.00373 weeks <br />8.57647e-4 months <br />.
At 2350 hours0.0272 days <br />0.653 hours <br />0.00389 weeks <br />8.94175e-4 months <br />, the reactor tripped due to low-low steam generator level during the transfer from the auxiliary feedwater pump to the main feedwater pump with an operations trainee performing the operation.
March 4 Reactor startup from Operational Mode 3 commenced at 0110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br /> and the reactor was critical at 0135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br />. The main unit was synchronized at 0308 hours0.00356 days <br />0.0856 hours <br />5.092593e-4 weeks <br />1.17194e-4 months <br />. Unit loading was increased in accordance with system demands.
March 5 to Station in Operational Mode 1 at 90% power. At 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />, March 7 the Ohio River level reached 674.5 feet and level surveillance was begun. Station shutdown commenced at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> and, by 2255 hours0.0261 days <br />0.626 hours <br />0.00373 weeks <br />8.580275e-4 months <br />, the river level had reached the current administrative limit for station shutdown at 680 feet. Entry into Operational Mode 4 occurred at 0535 hours0.00619 days <br />0.149 hours <br />8.845899e-4 weeks <br />2.035675e-4 months <br /> on March 6th.
The river elevation dropped below 680 feet at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> and the plant heatup began at 2240 hours0.0259 days <br />0.622 hours <br />0.0037 weeks <br />8.5232e-4 months <br />. At 0758 hours0.00877 days <br />0.211 hours <br />0.00125 weeks <br />2.88419e-4 months <br /> on March 7th, the reactor was critical. The main unit was synchronized at 1009 hours0.0117 days <br />0.28 hours <br />0.00167 weeks <br />3.839245e-4 months <br /> and the reactor power was increased to 90%.
March 8 Station in Operational Mode 1 at 90% power.
March 9 to Station in Operational Mode 1 at 90% power. At 1445 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.498225e-4 months <br />, March 10 commenced weekend shutdown for fuel conservation and engineering resolution of pipe stress analyses. The main unit was taken off line at 1655 hours0.0192 days <br />0.46 hours <br />0.00274 weeks <br />6.297275e-4 months <br /> and reactor shutdown was completed at 1704 hours0.0197 days <br />0.473 hours <br />0.00282 weeks <br />6.48372e-4 months <br />. Commenced cooldown to Mode 4, entering Mode 4 at 0237 hours0.00274 days <br />0.0658 hours <br />3.918651e-4 weeks <br />9.01785e-5 months <br /> on the 10th.
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Narrative Summary Of Operating Experience - March,1979 Date Event March 11 to Station in Operational Mode 4 with RCS Tavg approximately March 12 340F, March 13 to Station in Operational Mode 4 with RCS Tavg approximately March 14 340F, After discussion of the preliminary results of pipe stress reruns by the Onsite and Offsite Safety Committees, it was decided to place the plant in the cold shutdown mode. Began RCS depressurization at 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br /> and systems cooldown to Mode 5 at 1010 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.84305e-4 months <br />. Entered operational Mode 5 at 1855 hours0.0215 days <br />0.515 hours <br />0.00307 weeks <br />7.058275e-4 months <br /> and broke the containment vacuum at 1954 hours0.0226 days <br />0.543 hours <br />0.00323 weeks <br />7.43497e-4 months <br />.
March 15 to Station in Operational Mode 5 with RCS Tavg at 150F.
March 17 Degassing RCS in progress.
March 17 to Station in Operational Mode 5 with RCS Tavg at 150F.
March 31 Major Safety Related Maintenance - March,1979
- 1. Performed alignment and operational surveillance testing on the 1A Charging Pump on March 1, 2 and 5.
- 2. Inspected and then realigned the pump and motor of the 1A Reactor Plant Component Cooling Water Pump on March 9, 10 and 12.
- 3. Partially disassembled the 1B Reactor Coolant Pump motor on March 15 and 16 in preparation for replacing the pump seals.
- 4. Replaced failed bearing in the IC Containment Air Recirculation Fan March 17 through March 27.
- 5. Installation of high density spent fuel racks continued through the month.