ML20039G230

Monthly Operating Rept for Apr 1981

ML20039G230
Person / Time
Site:	Beaver Valley
Issue date:	05/05/1981
From:	Timko D DUQUESNE LIGHT CO.
To:
Shared Package
ML20039G225	List: ML20039G224 ML20039G230
References
NUDOCS 8201150404
Download: ML20039G230 (6)

Text

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DUQUESNE LIGHT COMPANY Beaver Valley Power Station NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE - APRIL 1981 April 1 Station in operational Mode 5 with the Reactor Coolant System (RSC) at approximately 120 PSIG and 120 F.

The 1C RCS, which had been isolated and drained for repairs of the 1C Reactor Coolant Pump (RCP),

was filled, vented and pressurized to approximately 100 PSIG.

April 2 Station in Operational Mode 5 with the Reactor Coolant System at approximately 320 PSIG and 120 F.

The 1A RCP was started to heat-up the RCS, preparatory to restoring the 1C RCS loop to service.

April 3 Station in Operational Mode 5 with the Reactor Coolant System at approximately 335 PSIG and 170 F.

The IC RCS loop was returned to service.

April 4 Station in Operational Mode 5 with the Reactor Coolant System at approximately 345 PSIG and 110 F.

At 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br />, a pressure reduction i

was begun to permit repairs to Safety injection hot leg isolation check valve [1SI-22].

RCS pressure was less than 100 PSIG by 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br />.

April 5 Station in operational Mode 5 with the Reactor Coolant System at approximately 75 PSIG and 110 F.

Pressure was reduced to 50 PSIG at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> to facilitate repairs to [lSI-22]. At 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, the RCS was repressurized to check the 1C RCP for possible oil leakage at the motor. A small amount of leakage was noted so a maintenance crew began repairs.

April 6 Station in Operational Mode 5 with the Reactor Coolant System at through approximately 360 PSIG and 120 F.

The IC RCP repairs were completed April 7 and RCS heat-up was commenced April 7.

April 8 Station in Operational Mode 5 with the Reactor Coolant System at through approximately 360 PSIG and 170F.

The containment airlock passed a April 11 Type B test after adjustment to the inner door hinge.

Commenced drawing the CNMT vacuum on April 9 and the main condenser vacuum l

on April 10.

The Station entered Operational Mode 4 at 0825 hours0.00955 days <br />0.229 hours <br />0.00136 weeks <br />3.139125e-4 months <br /> on April 10.

Final sealing of safety injection system check valve

[SI-22] was completed early on April 11 and the Station entered Operational Mode 3 at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />.

l April 12 Station in Operational Mode 3 with the Reactor Coolant System at l

through approximately 1100 and 440 F.

The RCS heat-up was in progress, reaching April 15 operating pressure and temperature at 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br />. The reactor was critical at 2144 hours0.0248 days <br />0.596 hours <br />0.00354 weeks <br />8.15792e-4 months <br /> on April 13.

Final adjustments were made to meet secondary side chemistry specifications and the main unit generator was synchronized at 0219 hours0.00253 days <br />0.0608 hours <br />3.621032e-4 weeks <br />8.33295e-5 months <br /> on April 15.

The plant tripped due to high water level in the lA Steam Generator during the load increase to 20%

power. The reactor was critical at 0534 hours0.00618 days <br />0.148 hours <br />8.829365e-4 weeks <br />2.03187e-4 months <br /> and the main unit synchronized at 0627 hcurs.

G201150404 810511 PDR ADOCK 05000334 R

PDR

DUQUESNE LIGHT COMPANY Beaver Valley Power Station NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE - APRIL 1981 (continued)

April 16 Station in Operational Mode 1 at nominal 58% power.

Load increase was through in progress at 3% power per hour to 80%, then at 1% per hour.

Station April 17 at full power by 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on April 17.

April 18 Station in Operational Mode 1 at nominal full power.

through April 23 April 24 Station ir operational Mode 1 at nominal full power. At 2010 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.64805e-4 months <br />, through began reducing power to shutdown the IB Main feedwater Pump for seal April 27 replacement, stablizing at 65% power by 2150 hours0.0249 days <br />0.597 hours <br />0.00355 weeks <br />8.18075e-4 months <br />.

Maintenance was completed and power escalation was begun at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br /> on April 25.

The Station reached full power by 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on April 27.

April 28 Station in Cperational Mode 1 at nominal full power.

through April 30 4

DUQUESNE LIGHT COMPANY Beaver Valley Power Station MAJOR SAFETY-RELATED MAINTENANCE - APRIL 1981 1.

An oil leak from the top flange on the lower lube oil reservoir of the IC Reactor Coolant Pump Motor was repaired.

OPERATING DATA REPORT DOCKET NO. 50-334 DATE 5/5/81 COMPLETED BY

.P.

R. Timko TELEPHONE. 417 443-5308 OPERATING STATUS Beaver Valley Power Station, Unit #1 Notes

1. Unit Name:

2. Reporting Period:

April, 1981

3. Licensed Thennal Power (MWt):

WO 923

4. Nameplate Rating (Gross MWe):

852

5. Design Electrical Rating (Net MWe):

845

6. Maximum Dependable Capacity (Gross MWe):

810

7. Mstimum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (Irems Number 3 Through 7) Since Last Report. Give Ressons:

9. Power Level To Which Restricted. If Any (Net MWe):

None

10. Reasons For Restrictions.If Any; N/A "Iltis Month Yr.-to Date

' Cumulative II. Hours In Reporting Period 719 2879 ay m

12. Number Of Hours Reactor Was Critical 405.67 1330.46 15.861.13

13. Reactor Reserve Shutdown Hours 0

0 4,482.8

14. Hours Generator On-Line 377.22 1279.76 14,986.01

15. Unit Reserve Shutdown Hours 0

0 0

915,878.02_(, 6.9 % 900-2.912.775.68 31,020,668.83

16. Gross Thermal Energy Generated (MWH) 297,100 93,,

9,564,240

17. Gross Electrical Energy Generated (MWH)

18. Net Electrical Energy Generated (MWH) 273.317 858,128 8,707,280

19. Unit Service Factor 52.5 44.4 35.1

20. Unit Availability Factor 52.5 44.4 35.1

21. Unit Capacity Factor (Using MDC Neti 46.9 36.3 27.2

22. Unit Capacity Factor (Using DER Net) 44.6 34.5 25.9

23. Ur it Forced Outage Rate 47.5 55.6 47.2

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

Major Modification Outace, May 15, 1981. 7 weeks.

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

5/7/81

26. Units h Test Status (Prior to Commerect Operation):

Forecast Achined INITIAL CRITICALITY N/A N / A _ __

INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERAT!ON N/A N/A' (9/77)

AVERAGE DAILY UNIT POWER LEVEL 50-334 DOCKET NO.

I UNIT BVPS Unit #1 ff 5/5/81 DATE D. R. Mo COMPLETED BY

-[

TELEPHONE 412-643-5308

9y r

b.th: p 4

? /f MONTH Aoril, 1981

!i ff DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) g (MWe-Net) 0 j

795 g7 1

0 2

gg 800 0

812 3

39 ih 810 0

n 20 4

fI 808 0

21 3

808 6

0 22 a

0 J

1 796 23 7

0 3

24 776

}9j 25 527 0

9 10 0-h 26 682

. }

804 II O

27 0

796 12 28 I3 0

]

796 29 N

808 0

30 14

[

189 is yi 613 2 i 16

.y ly l

F

?,

IE lg[ $.

INSTRUCTIONS d~

t{v

' h day in the reporting inonth. Compute io On this furrnat.hst the average dady unit power

• j t c

the nearest whole megs*att.

'F f

M J

(4/77)

v a

r-e UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-334 UNIT NAME BVPS Unit #1 -

DATE.5/5/81 REPORT MONTig April, 1981 COMPLETED BY D. R. Timko 7ELEPHONE,,412-643-5308 E

E jE 3

jY5

'ucensee 5-r, ft, Cause & Costective Date

(

5g 4

2gE Event g3 e.3 Acti m to RE E

j@g Repose a mo j'

Prevens Recurrence 6

4 810415 F

338.31 A

1 81-014 CB' PIPE XX Reactor coolant system leakage exceeding Tech. Spec, limit at pressure tap for RCS pressure transmitter. Line was removed and the socket capped.

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

5 810415 F

3.47 A

3 Cll INSTRU Bypass feed regulating valves control problems resulted in a high steam generator level reactor trip during startup.

l l

3.

4 F: Forced Reason:

5: Schedu!cd A. Equipment Failure (Explain)

. Method:

Exhibit G Instructions l-Manual for Pseparation of Data H.Malatenance of Test 2 Manual Scram.

Ener) Sheets for Licensee C Refueling

• J Automati<; Scram.

Eveni Rep.us iLFRt File tNURFG l

D. Regulatory Resitiction 4-Olher (Explain) 0161)

I -Operato Trainingi Licenge Exas.nination F Adnumstsative G. Operational Eyor (E aplanal Estubis 1 SJme'Souice i

t9/77)

II.Other (E splam )

l i

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