ML20039G181

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Monthly Operating Rept for Mar 1981
ML20039G181
Person / Time
Site: Beaver Valley
Issue date: 04/01/1981
From:
DUQUESNE LIGHT CO.
To:
Shared Package
ML20039G180 List:
References
NUDOCS 8201150361
Download: ML20039G181 (5)
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Text

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DUQUESNE LIGHT COMPANY Beaver Valley Power Station Narrative Summary of Monthly Operating Experience - March, 1981_

March 1 Station in Operational Mode 5 with the Reactor Coolant System through (RCS) at atmospheric pressure and approximately 110F. ,

March 4 March 5 Station in operational Mode 5 with the Reactor Coolant System at atmospheric pressure and approximately 108F, drained to the mid-loop level. At 1825 hours0.0211 days <br />0.507 hours <br />0.00302 weeks <br />6.944125e-4 months <br />, the Residual Heat Removal (RHR)

System flow was degraded when the operating RHR pump began to air-bind. The RCS level was raised, the RHR pumps were vented and normal flow was restored by 1936 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.36648e-4 months <br />. The RCS level had gradually lowered due to instrument drift of the hard-piped (1/2 inch stainless steel tubing) level transmitter. Since no leaks were found, it was speculated that the water filled reference leg evaporated.

March 6 Station id Operational Mode 5 with the Reactor Coolant System at through atmospheric pressure and approximately 107F.

March 9 March 10 Station in Operational Mode 5. The Reactor Coolant System fill and vent was begun.

March 11 Station in Operational Mode 5 with the Reactor Coolant System at approximately 60 PSIG and 100F. Additional venting of the RCS was performed, then a steam bubble was drawn in the pressurizer.

From 1320 to 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br />, the RCS pressure was raised to approxi-mately 300 PSIG.

March 12 Station in Operational Mode 5 with the Reactor Coolant System at through 325 PSIG and 145F. The 1C Reactor Coolant Pump (RCP) failed to March 14 start while venting the RCS.

March 15 Station in Operational Mode 5 with the Reactor Coolant System at 350 PSIG and 160F. At 2050 hours0.0237 days <br />0.569 hours <br />0.00339 weeks <br />7.80025e-4 months <br />, the 1C charging pump was shutdown, but it was immediately restarted when the charging header pressure, acting backwards through an improperly scated check valve, started rotating the pump in the wrong direction.

Manual isolation valves [CH-27] and [CH-161] were closed and the IC pump was shutdown.

March 16 Station in Operational Mode 5 with the Reactor Coolant System at 365 PSIG and 170F. At 1655 hours0.0192 days <br />0.46 hours <br />0.00274 weeks <br />6.297275e-4 months <br />, RCS cooldown to less than 140F was initiated. At 1932 hours0.0224 days <br />0.537 hours <br />0.00319 weeks <br />7.35126e-4 months <br />, the RCS loop 1C hot leg and cold leg isolation valves were shut in preparation for drawing the 1C loop to repair the 1C RCP motor. ,

8201150361 810413 PDR ADOCK 05000334 R PDR

March 17 Station in Operational Mode 5 with the Reactor Coolant System at through approximately 325 PSIG and 100F. The 1C RCS loop was isolated March 22 and drained.

March 23 Station in Operational Mode 5 with the Reactor Coolant System at 350 PSIG and 105F. The 1C loop was isolated and drained. At 1935 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.362675e-4 months <br />, while isolating the 1C charging pump after an unsucces8ful check of the discharge check valve, the pump suction piping was overpressurized. During the pump isolation, -

the discharge valve was not fully seated and when the suction valves were shut, pressure built up before the operators could take corrective action. Pre;sure build-up was limited by leakage at gasketed flange joints. Neither personnel contamination nor equipment damage resulted from the incident.

March 24 Station in Operational Mode 5 with the Reactor Cool' ant Sys'em t at 350 PSIG and 1157. The 1C RCS loop _was isolated and drained.

March 25 Station in Operational Mode 5 with the Reacter Coolant System at 350 PSIG and 120F. The 1C loop was isolated and drained. The RCS was depressurized to 96 PSIG at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> to repair safety

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injection system hot Jeg check valve [SI-22].

March 28 March 29 Station in Operational Mode 5 with the Reactor Coolant System at through 150 PSIG and 120F. The IC loop was isolated and drained. The March 31 uncoupled 1C RCP motor was successfully tested after repairing a stator coil end turn connection. Preparations to return the 1C RCS loop, including coupling the RCP uotor were in progress.

Major Safety-Related Maintenance - March, 1981

1. A stator coil end turn connection on the IC Reactor Coolant Pump motor was repaired.

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! OPERATING DATA REPORT DOCKET NO. _50-334 DATE 4/1/81 l COMPLETED BY D. R. Timko TELEPHONE. 41' 441-9308 1

l OPERATING STATUS

1. Unit Name. Beaver Valley Power Station, Unit #1 Notes March, 1981

!' 2. Reporting Period: ,

3. Lleensed Thermal Power (MWt): WO
4. Namepiste Rating (Gross MWe): 923
5. Design Electrical Rating (Net MWe): 852 i

I 6. Maximum Dependable Capacity (Gross MWe), 845

7. Maximum Dependable Capacity (Net MWe): 610
8. If Changes Occur in Capacity Ratings (Irems Number 3 Tluough 7) Since Last Report. Give Reisons:
9. Power Level To Which Restricted. If Any (Net MWe): None N/A i 10. Reasons For Restrictions,If Any; ..

! ' This Month Yr. to-Date Cumulative

11. Hours In Reporting Period 744 2160 _

!43,104 i 12. Number Of Hours Reactor Was Critical 924.79 15,455.46 v 0 - 4,482.8

13. Reactor Reserve Shutdown Hours
14. Hours Generator on-Line 0 901.5,4 .14,607.79 0 u 0
15. Unit Reserve Shutdown Hours U 1,996.897.66 30,104,790.81 ,
16. Cross Thermal Energy Generated (MWH)
17. Gross Electrical Energy Generated (MWH) 0 6ff),800 9,267,140 f *

,- 572',459 8.433.963

18. Net Elecuical Energy Generated (MWH) i
19. Unit Service Factor U 'l'7 -
20. Unit Av;ilabiity Factor U '1*7 3'*7 f' 21. Unit Capacity Factor (Using MDC Net) 0 9.] 4 y . i 26.8 3/./ O ---

" Unit Capacity Factor (Using DER Net) 0 25.5 I 23. Unit Forced Octage Rate 100 58.3_ f 47.2

24. Shutdowns Scheduled Over Next 6 Months (Type.Date.and Duration of Each): ,7 -

Maior Modification n,,tnoa /May 15. 1091/7 vooh. _

i

25. If Shut Down At End Of Report Period. Estimated Date of Startup: 4/5/81
26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY N/A. N/A INITIAL ELECTRICITY N/A N/Ai COMMERCIAL OPERATION N/A _N/A (9/77) -

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AYERAGE DA!!3 UNIT POWER LEVEL DOCKET NO. 50-334

' IJNI7 BVPS ITnit #1 DATE 4/1/81 COMPLETED BY D. R. TW TELEPHONE 412-643-5308

  • March, 1981 MONTH .

DAY AVERAGE DA:LY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (yw,.Neti 1 0 37 0

2 0 3 0 3 19 0 0 0 4 :o .

5 0 23 0

0 0 6 n 7 .0 23 0

8 0 4 o

9 0 o 0 0 10 26 Ii 0 27 0

0 0 12 28 0 o 13 ,9 0 0 14 30 0 0 IS 3 16 0 INSHUCTIONS On this format. list the average daily unit power leselin MWe.Nu for each day in the reporting month. Compute to the nearest whole megswait.

. (4/77)

i i

UNIT SilHTDOWNS AND POWER RFDUC110NS DOCKET NO. 50-334 UNIT NAME BVPS Unic #1 DATE 4/1/81 REPOR F MONTig March, 1981 COMPLETED BY D. R. Timko TEll.PilONE 412-643- 5308 l

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, .2 E , g 3 .u, :sg Licensce E c, g% Cauw & Couseceive Nd- DJ's i 5? 4 .E 5 cc Event y? 9? Action so

$2 $ jsg Repent = WLe

.}' Psevens Recurrence f

6 4 810301 F 744 A 81-014 PIPEXX 1 CB Reactor coolant system leakage exceeding Tech Spec Limit at

' pressure tap for RCS pressure transmitter. Line was removed and the socket capped. Pressure i

transmitter [PT-RC-403] was tied into [PI-RC-405] sensing line.

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1 3 3 4 F: F.us ed Reason: Method: Exhibit G -lassenctions S: Schedu!cd A Figuipment FailureIL*rlain) 14tanual fin Ficpasati.m of Data B Maintenance ciTest 3 Manual Scram.

C.Ilefueling Eni 3 Sheets fin i scensee 3 Automatic Sciam. Even Rep.n Ill'R n Fde t NUMEG D llegniatory Resiriction 4 Othes t Explain) l'-Opesaim Training i 1.icense Examination 0161) 1 Adinnuserative , 5 G Opesational l'isos ll mplain t 19/77) ll Othes IINplain t Esinbit I Same*S.m.ce M

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