ML19242D125

Monthly Operating Rept for Jul 1979

ML19242D125
Person / Time
Site:	Beaver Valley
Issue date:	08/07/1979
From:	Spitznogle A DUQUESNE LIGHT CO.
To:
Shared Package
ML19242D119	List: ML19242D118 ML19242D125
References
NUDOCS 7908140525
Download: ML19242D125 (5)

Text

. , .

OPERATING DATA REPORT DOCKET NO. 50-334 DATE 8 /7 /70 COMPLETED BY A.E.SD1tznogle TELEPHONE. 412-o43-5023 OPERATING STATUS

1. Unit Name: Beaver Valley Power Station, Unit #1 Notes

2. Reporting Period: Julv. 1979

3. Licensed Thermal Power (MWt): 2440

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): 817

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): None

10. Reasons For Restrictions,if Any:. N/A This Month Yr. to.Date "Camulative

11. Hours in Reporting Period _

744 5,087 27,767

12. Number Of Hours Reactor Was Critical 0 1,166.6' 11,362.68

13. Reactor Reserve Shutdown Hours 0 0 4,482.801

14. Hours Generator On Line 0 1,106.57 10,710. I

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 2,557,151.22 23,425,546.17

17. Gross Electrical Energy Generated (MWH) 0 834,600 7,173,340

-18. Net Eier :al Energy Generated (MWH) 0 744,939 6,567,357

19. Unit Ser. ice Factor 0 21.7 40.6

20. Unit Availability Factor 0 21.7 40.6

21. Unit Capacity Factor (Using MDC Net) 0 17.9 34.7

22. Unit Capacity Factor (Using DER Net) 0 17.1 _

33.2

23. Unit Forced Outage Rate 100 78.2 51.3

24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Eacht:

Scotenber, 1979 - Major Modification and Refueling Outage

25. If Shut Down At End Of Report Period. Estimated Date of Star;up:

26. Units in Tnt Stattrs (Prior to Conracrcial Operation,. Forecast Achieved INITIAL CRITICA LITY N/A N/A INITIA L ELECTRICITY N/A N/A COMMERCIAL OPER ATION N/A N/A 7908140 m GN " '"""

AVERAGE DAILi UNIT POWER LEVEL DOCKET NO. 50-334 UNIT BVPS Unic #1 DATE 8/7/79 COMPLETED BY A.E.Spitznogle TELEPHONE 412-643-5023 MONTH July, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 g7 0 0 y3 0 2

0 0 3 39 4 0 0 20 0 0 S 21 0 0 6 22 7 0 y o 0 0 8 24 9 0 0 25 0 0 10 26 0 0 11 27 0 0 12 28 13 0 29 0 0 I4 30 15 0 3, o 16 0 INSTRUCTIONS On this format. fist the serage daily unit power lealin MWe Net for each day in the reporting nmnth. Compute to the nearest whole negawait.

(9/77)

L2cI.[$

DOCKET NO. 50-334 UNIT SIIUTDOWNS AND POWER REDUCTIONS 11VPS Unit #1 UNIT NAME .

DATE 8/7/79 COMPLETED BY A. E. Spitznogle REPORT Af0NTil July, 1979 TELENIONE 412-643-5023 "O.,

grn- re.

@ .! E 3 Y Licensee ,E-t, 'o Cause & Corrective y*%D Na i . DJte -h 3@ j .2 s ci: Event y 9E Acti.m to m s H j= 4 5gg Repori:t vi O C

E' Prevent Recurrence

%=~: ' 6 EI5; r, p Df4 12 790601 F# 744 s 1 78-53 zz zzzzzz Reactor shutdown for design review of "a&2 fi piping supports for Reactor Coolant

[lD and other Category I piping.

ym 1 2 3 4 F: Farced Reason: Method: Exhibit G - Instructions f.

l. .

5: Schetiu!cd A Equipment Failure (Explain) l-Manual for Pseparation of Data B. Maintenance ei Test 2-Manual Scram. Entr> Sheets for Licensee 7- C Refueling 3 Automatic Scram. Eveni Repori ILERI File INUREG c'* D-Regulatory Restriction -1 Olher (Explain) 01611 G'] I:-Opesatm Training & Litense Examination 9 F Administrative 5 G-Operational Er ror Ilixplain t Eshibit 1. Same' Source I'l/77) 11 Other (lixplain)

DUQUESNE LIGHT COMPANY Beaver Valley Power Station Narrative Summary Of Operacing Experience - July, 1979 Date Event_

July 1 to Station in Operational Mode 5 with Tavg between 100F and July 22 110F. The RCS level was being maintained at the elevation of the system cold leg pipe centerlines.

July 22 to Began filling the Reactor Coolant System at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br /> on July 26 July 22. The fill was secured at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on July 23, with a pressurizer level of 56%. This pressurizer level was maintainud and the coolant system temperature was maintained between 100F and 110F.

July 26 to While maintaining a pressurizer level of 50%, at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> July 31 on July 26, began increasing the reactor coolant temperature from 105F to 170F for performance of an operational leak test of the steam generator feedwater system. Reached 170F at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on July 27. Maintained temperature between 145F and 170F through July 31.

Major Safety Related Maintenance - July, 1979

1. Repair and concurrent inspection of the steam generator feedwater piping has been in progress throughout July. Completion of the repairs and final examination of the welds is expected the first week of August,

2. The reactor coolant pump motors installation, alignment and coupling after seal overhaul and installation of the Westinghouse WRAPS seal maintenance system was completed. Final restoraticn of supports and structural members is in progress.

3. Snubb inspection, testing and overhaul continued throughout the month.

Final testing and 1.stallation is expected to be completed early in August.

4. Began routine checks of 480V transformers af ter failure of the 3E transformer.

These inspections are still in progre=s.

5. Inspection and modifications of the pipe hangers and supports continued.

6. The motors for the inside recirculation spray pumps were installed, aligned and coupled.

7. Replacement of the impeller for the 1A Reactor Plant River Water Pump is still in progress.

8. The solenoid control valves were replaced on the valve actuators for the reactor coolant system letdown isolation valves and the pressurizer power-operated relief valves.

c n -

" b" e' l. (, r )

o

Beaver Valley Power Station, Unit No. 1 Major Safety Related Maintenance - Julv, 1,'79 (continued)

9. Rerouting of cables for safety injection isolation valves {MOV-SI-860B and MOV-SI-864B] is in progress.

,e..e,,

vm e _ '. :.tj a