ML19274D154

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Monthly Operating Rept for Dec 1978
ML19274D154
Person / Time
Site: Beaver Valley
Issue date: 01/05/1979
From: Witkowsky F
DUQUESNE LIGHT CO.
To:
Shared Package
ML19274D152 List:
References
NUDOCS 7901150106
Download: ML19274D154 (7)
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, , OPERATING DATA REPORT DOCKET NO. 50-334 DATE 1/5/79 COMPLETED BY F. P. Witkowsky TELEPHONE. 41')-641- 5023 OPERATING STATUS

1. Unit Name: Beaver Valley Power Station, Unit #1 Notes
2. Reporting Period: December, 1978
3. Licensed Thermal Power (MWt): 2AA0
4. Nameplate Rating (Gross MWe): 923
5. Design Electrical Rating (Net MWe): 852
6. Maximum Dependable Capacity (Gross MWe): 845
7. Maximum Dependable Capacity (Net MWe): 800 S. If Changes Occur in Capacity Ratings (Irems Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted,if Any (Net MWe). None
10. Reasons For Re'strictions,if Any:. N/A This Month Yr to-Date Cu:::.ttive
11. Hours in Reporting Period 744 8,760 23,400
12. Number Of Hours Reactor Was Critical 317.25 3,748.17 10.196.07
13. Reactor Reserve Shutdown Hours 744 3,841.63 4.800.03
14. Hours Generator On Line 257.7 3,572.83 9,604.1,3
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 504,540.35 8,798,901.15 20,868,394.95
17. Gross Electrical Energy Generated (MWH) 157,700 2,664,500 6,338,740
18. Net Electrical Energy Generated (MWH) 139,069 2,480,496 5,792,368
19. Unit Service Factor 34.6 40.8 47.3
20. Unit Availability Factor 34.6 40.8 47.3
21. Unit Capacity Factor (Using MDC Net) 23.4 19.4 41_ ')
22. Unit Capacity Factor (Using DER Net) 21.8 33.2 38.7
23. Unit Forced Outage Rate 65.0 51.0 39.3
24. Shutdowns Scheduled Over Next 6 Months (Type, Date.and Duration of Eacht:

Refueling in April, 1979

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 N/A N/A INITIAL ELECTRICITY N/A N/A

. COMMERCIAL OPERATION N/A N/A 7901150lOfo N 7)

, AVERAGE DAILY UNIT POWER LEVEL 4

DOCKET NO. 50-334 UNIT BVPS Unit #1 DATE 1/5/79 COMPLETED BY F.P. Witkowsky TELEPHONE 412-643-5023 MONTH December, 1978 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 0-37 2 0 0 18 3 0 39 110 4 __

0 20 172 5 0 182 21 6 0 348 22 7 0 522 23 8 0 24 7R4 9 0 710 25 10 0 747 26 11 0 27 63 12 0 745 28 0 120 13 29 14 0 749 30 IS 0 801 33 16 0 INSTRUCTIONS On this furmat list the average daily unit power lesel in MWe-Net for each day in the reporting inonth. Compute to the nearest whule megawatt.

(9/77)

DOCKETNO. 50-334 UNITSIIUTDOWNS AND POWER REDUCTIONS UNIT NAME BVPS Unit #1 DATE 1/5/79 REPORT AION rli December, 1978 COMPLETED BY F. P. Witkowsky TELErilONE 412-643 .5023 Page 1 of 2 I

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N"- DJ'e 3:- .3 _e 5? 4 2s5 Event s7 '

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23 780728 F 421.71 A 3 LER 78-43 EB TRANSF A generator differential / main transformer differential trip initiated a reactor and turbine trip when a fault in the A phase of the main generator main' transformer resulted in failure of the transformer.

24 781218 F 17.50 A 3 None Cil VALV0P Reactor trip on Ili-Hi steam generator level at 15% F.P. The malfunction of the 1B main feed regulation was repaired and the valve functionally checked.

25 781220 S 8.52 B 1 None HA TURBIN The main unit was taken off the line to perform a turbine overspeed trip test.

I 2 3 4 F: Forced Reason: Method: Exhibit G Instructions S: Schedu!cd A. Equipment Failure (Explain) 1 Manual for Preparation of Data B-Maintenance of Test 2 Manual Scram. Entr> Sheets for Licensee C Refueling 3 Automatic Scram. Event Report (LElli File (NUREG D Regulatory Restriction 4 Other iExplain) 01611 E Operato Training & Ucense Examination F- Administ rative 5 G-Operation il Eiror (lixplain t Eshibit I Same'Sonice (9/77) Il-Othe r ( E xplain )

DOCKET NO. 50-334 UNIT SIIUTDOWNS / ND POWER REDUCTIONS UNIT N AME BVPS Unit #1 DATE 1/5/79

- REPORT MONTil December, 1978 COMPLETED BY F. P. Witkowsky TELEPilONE 412-643 5023 Page 2 of 2

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No. Date h

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.2 s s Licensee Event 2-r, 3?

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$5 E j5g Report 2 NU j' , Prevent Recurrence -

6 26 781226 F 20.7 G 3 None CH HTEXCH Turbine / reactor trip on Hi-Hi steam s generator level after the IB heater drain pump tripped on low NPSH and a main feed pump tripped on low suction pressure. Upon restarting the main feed pump, the steam generator level surged high resulting in the turbine / '

reactor trip.

27 781229 F 17.87 A 3 None CH HTEXCH -

Reactor trip on Lo-Lo IB steam generator level after both heater '

drain pumps tripped off.

I 2 3 4 F: Forced Reason: Method: Exhibit G Instructions S: Schedu!cd A. Equipment Failure (Explain) l-Manual for Preparation of Data B-Maintenance ci Test 2-Manual Scram. Entr> Sheets for Licensee C Refueling 3 Automatic Scram. Event Report (LFR) File (L37.G D Regulatory Restriction 4-Other (Explain) 0161)

E-Operato Training & Ucense Examination F Administrative 5 G-Operalional Eiros ( Explain t Estubit I - Same'Somce (9/77) Il-Other ( Explain t I

DUQUESNE LIGHT COMPANY

. Beaver Valley Power Station Narrative Summary Of Operating Experience - December, 1978 Date Event December 1 to During this period the replacement main transformer December 10 installation was completed and tested by backfeeding from the system grid. The main unit turbine oil flush was also completed.

December 11 to Inleakage to the boron injection tank could not be stopped December 13 because of leakage through the bypass valve [1SI-91] and outlet valves [MOV-lSI-867C,D] and the plant was cooled down to Mode 5 to repair these valves.

December 14 to At 1250 hours0.0145 days <br />0.347 hours <br />0.00207 weeks <br />4.75625e-4 months <br /> on December 14, the plant returned to Mode 4 December 15 and held there until 1559 hours0.018 days <br />0.433 hours <br />0.00258 weeks <br />5.931995e-4 months <br /> to allow time to establish acceptable reactor coolant chemistry. Heatup was then continued to 340F and held there to establish condensate chemisery and to borate the boron injection tank. At 0705 hours0.00816 days <br />0.196 hours <br />0.00117 weeks <br />2.682525e-4 months <br /> on December 15, the plant entered Operational Mode 3 and, by 2355 hours0.0273 days <br />0.654 hours <br />0.00389 weeks <br />8.960775e-4 months <br />, reactor coolant system dilution was completed.

December 16 to At 0147 hours0.0017 days <br />0.0408 hours <br />2.430556e-4 weeks <br />5.59335e-5 months <br /> on December 16, reactor startup commenced.

December 19 Reactor was critical at 0229 hours0.00265 days <br />0.0636 hours <br />3.786376e-4 weeks <br />8.71345e-5 months <br />. By 0620 hours0.00718 days <br />0.172 hours <br />0.00103 weeks <br />2.3591e-4 months <br /> on December 16, the turbine was at 1700 RPM. At 1018 hours0.0118 days <br />0.283 hours <br />0.00168 weeks <br />3.87349e-4 months <br />, the generator field breaker was closed and the generator tripped due to field excitation problems. At 1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br />, unit was again at synchronous speed. Four attempts were made to synchronize unit but each time generator would not transfer to load control because of EH controller problems. On December 17, plant was in Operational Mode 2. At 0008 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, an attempt was made to manually synchronize the main generator to the system grid. Main generator and turbine tripped on overall differential which had been set low to provide additional protection until the revised protection required by main transformer replacement could be proven. At 1152 hours0.0133 days <br />0.32 hours <br />0.0019 weeks <br />4.38336e-4 months <br />, had reactor trip due to voltage transient on No. 2 Vital Bus.

At 1245 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.737225e-4 months <br />, reactor coolant system cooldown commenced because of steam generator chemistry limitations. Plant was heated back up and, at 1018 hours0.0118 days <br />0.283 hours <br />0.00168 weeks <br />3.87349e-4 months <br /> on December 18, reactor was critical and, at 1343 hours0.0155 days <br />0.373 hours <br />0.00222 weeks <br />5.110115e-4 months <br />, main unit was synchronized with system.

Turbine-reactor trip at 1427 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.429735e-4 months <br /> when problems were encountered while transferring feedwatar control from bypass to main regulating valves. At 0515 hours0.00596 days <br />0.143 hours <br />8.515212e-4 weeks <br />1.959575e-4 months <br /> on December 19, reactor startup commenced. At 0535 hours0.00619 days <br />0.149 hours <br />8.845899e-4 weeks <br />2.035675e-4 months <br />, reactor was critical. At 0757 hours0.00876 days <br />0.21 hours <br />0.00125 weeks <br />2.880385e-4 months <br /> on December 19, the main unit was synchronized with the system.

Narrative Summary Of Operating Experience - December, 1978 (continued)

Date Event December 19 to At 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on December 20, began power decrease to take December 25 generator off line to allow for turbine overspeed tests.

Overspeed tests were completed at 2119 hours0.0245 days <br />0.589 hours <br />0.0035 weeks <br />8.062795e-4 months <br /> on December 20.

At 0515 hours0.00596 days <br />0.143 hours <br />8.515212e-4 weeks <br />1.959575e-4 months <br /> on December 21, the main unit was synchronized with the system. On December 22, with reactor at 68% power, it was noticed that the No. 9 bearing was showing sparks periodically across the oil seal. At 1120 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.2616e-4 months <br />, started a 1% per minute ramp-down. Sparking stopped at 42% power but ramp was continued until 15% power was reached at 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br />.

At 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br /> on December 22, it was found that No. 9 bearing oil temperature detector was grounded to the pedestal. The ground was removed and, on December 25 at 0454 hours0.00525 days <br />0.126 hours <br />7.506614e-4 weeks <br />1.72747e-4 months <br />, commenced increasing power at 3% per hour as required by the system.

December 26 to At 2226 hours0.0258 days <br />0.618 hours <br />0.00368 weeks <br />8.46993e-4 months <br /> on December 26, the heater drain pump tripped on December 28 low net positive suction pressure. At 2233 hours0.0258 days <br />0.62 hours <br />0.00369 weeks <br />8.496565e-4 months <br />, reactor trip on Hi-Hi steam generator level caused by ensuing transient.

Reactor was critical again at 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br /> on December 27 and the main unit was synchronized at 1912 hours0.0221 days <br />0.531 hours <br />0.00316 weeks <br />7.27516e-4 months <br />. Plant was in Operational Mode 1 at 75% reactor power on December 28.

December 29 to At 0332 hours0.00384 days <br />0.0922 hours <br />5.489418e-4 weeks <br />1.26326e-4 months <br /> on December 29, the reactor tripped on low-low December 31 level 1B steam generator caused by power decrease transient and trying to save main feed pumps from tripping on low suction pressure when heater drain tank high level dump valve inadvertently opened causing loss of heater drain pump flow.

At 0525 hours0.00608 days <br />0.146 hours <br />8.680556e-4 weeks <br />1.997625e-4 months <br /> on December 29, reactor was crit' cal again. At 0645 hours0.00747 days <br />0.179 hours <br />0.00107 weeks <br />2.454225e-4 months <br /> on December 29, reactor trip and turbine trip on Hi-Hi level in lA steam generator. At 1313 hours0.0152 days <br />0.365 hours <br />0.00217 weeks <br />4.995965e-4 months <br />, reactor critical again. December 30 through December 31, plant was continuing to increase power level.

Major Safety Related Maintenance - December,1978

1. Main unit turbine-generator overhaul was completed on December 13.
2. Repairs were made to [lSI-91] and [MOV-SI-867A,B] and completed on December 13.

TRAINING SCHEDULE WEEK 0F /!f ff DESCRIPTION Mon TUES WED THURS FRI DISTRIBUTION

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/ f /0 // /2-STATION ORINETATION (STATION AND y DIATION INDOCTRINATION) GWM JAW, JFB Neu.-rea C u rsec.w o,Q -

RADIATION WORKER TRAINING - LECTURE RMM HPW JW ll<u--7ef OcA ssca>n 0960 Wan i.GS ARo RADIATION WORKER TRAINING - PRACTICAL hAhlta6 k!sjug /30o CONTINUOUS RADIATION WORKER TRAINING RTZ FJB JJC CLASS & OF 16 m

- s' 6/ved4 e/O RADCON RFB CONTINUING RADIATION WORKER TRAINING

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