ML20065T245

Monthly Operating Rept for Aug 1982.Narrative Summary Encl

ML20065T245
Person / Time
Site:	Beaver Valley
Issue date:	09/02/1982
From:	Weaver L DUQUESNE LIGHT CO.
To:
Shared Package
ML20065T237	List: ML20065T235 ML20065T245
References
NUDOCS 8211020284
Download: ML20065T245 (5)

Text

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DUQUESNE LIGHT COMPANY Beaver Valley Power Station NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE - AUGUST 1982 The Station is in Operational Mode 1 at a nominal 100% reactor power August 1 The Reactor Coolant System leak from the primary to secondary level.

through side of the 1C Steam Generator has steadily increased from approximately August 25

.03 GPM to approximately.07 GPM.

On August 10, at 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> reactor power was reduced to 95% for the performance of testing at 2155 hours0.0249 days <br />0.599 hours <br />0.00356 weeks <br />8.199775e-4 months <br /> commenced increasing reactor power back to 100%.

Main Feedwater Regulating Valve [FCV-lFW-478] air inlet nipple to the August 26 valve diaphragm was sheared off resulting in the loss of air pressure the valve closure, and the loss of feedwater to the valve diaphragm, flow to the 1A Main Steam Generator which resulted in a reactor trip At 1209 hours0.014 days <br />0.336 hours <br />0.002 weeks <br />4.600245e-4 months <br /> Reactor start-up was commenced, at at 0337 hours0.0039 days <br />0.0936 hours <br />5.57209e-4 weeks <br />1.282285e-4 months <br />.

1254 hours0.0145 days <br />0.348 hours <br />0.00207 weeks <br />4.77147e-4 months <br />, the Reactor was critical, and at 1420 hours0.0164 days <br />0.394 hours <br />0.00235 weeks <br />5.4031e-4 months <br /> the Main Unit Generator output breakers were closed. At 1845 hours0.0214 days <br />0.513 hours <br />0.00305 weeks <br />7.020225e-4 months <br /> commenced load reduction from a nominal 45% reactor power to go on By-pass Flow Control Valve [FCV-1FW-499] as Main Feedwater Regulating Valve [FCV-1FW-498]

was isolated due to excessive leak by.

Holding reactor power stable at a nominal 28% for 1C Steam Generator August 27 At 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, the by-pass flow control on the feedwater supply.

Reactor was manually tripped due to an appsrent dropped control rod.

The dropped rod indication resulted from testing that was in progress.

A shorted lead in a piece of test equipment caused the primary to Indication for the P-8 secondary voltage output to go to zero.

control rod subsequently indicated zero. The outage scheduled to begin at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> on the 27th has begun 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> early due to the reactor 1855 hours0.0215 days <br />0.515 hours <br />0.00307 weeks <br />7.058275e-4 months <br /> commenced borating to cold shutdown Zenon free trip. At At 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> Shutdown Banks A and B were withdrawn.

conditions.

Reactor Coolant System cooldown commenced at 0045 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br /> at a rate of August 28 50*F/ hour, and at 0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br />, the station entered Hot Shutdown Mode 4.

At 1202 hours0.0139 days <br />0.334 hours <br />0.00199 weeks <br />4.57361e-4 months <br />, the Residual Heat Removal System was placed in service, at 1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br />, the station entered Cold Shutdown Mode 5, and at 1347 hours0.0156 days <br />0.374 hours <br />0.00223 weeks <br />5.125335e-4 months <br /> containment vacuum was broken.

At 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on the 29th containment purge was started, at 1959 hours0.0227 days <br />0.544 hours <br />0.00324 weeks <br />7.453995e-4 months <br /> Augus t 29 on the 30th began to drain the C Reactor Coolant Loop Hot Leg, and at through Augus t 31 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on the 31st, the C Reactor Coolant Loop Stop Valve Pressur-The Reactor Coolant System Tavg. and ization was placed in service.

pressure are at 120*F and 270 psig.

8211020284 820908 PDR ADOCK 05000334 R

PDR

DUQUESNE LIGHT COMPANY Beaver Valley Power Station MAJOR SAFETY RELATED MAINTENANCE - AUGUST 1982 Steam Generator [RC-E-lC] tube plugging in progress to eliminate 1.

Reactor Coolant System leakage to the secondary side.

The Charging Pump [CH-P-1C] shaf t-driven lube oil pump was replaced 2.

because the gear drive would not hold pressure.

Outboard seal on Component Cooling Pump [CC-P-1A] was replaced.

3.

Fire Protection check valve [FP-30] on the discharge of the Pressure 4.

Maintenance Pump [FP-P-3] was replaced due to excessive seat leakage which decreased system pressure and caused frequent operation of the pump.

9 OPERATING DATA REPORT DOCKET NO. 50-334 DATE 9-2-82 COMPLETED BY

_L.

W. Wehver TELEPHONE. - 4' ? ^41-9301 OPERATING STATUS NOL*5 Beaver Valley Power Station. Unit #1

1. Unit Name:

August 1982

2. Reporting Period:

2660

3. Licensed Thermal Power (MWt):

923

4. Nameplate Rating (Gross MWe):

852

5. Design Electrical Rating (Net MWe):

860

6. Maximum Dependable Capacity (Gross MWe):

810

7. Maximum Dependable Capacity (Net MWe):

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

None

9. Power Level To which Restricted. lf Any (Net MWe):

N/A

10. Reasons For Restrictions.If Any:

This Month Yr to.Date

' Cumulative 744 5,827 iss saq

11. Hours in Reporting Period 630.7 1,177.9 22,237.2

12. Number Of Hours Reactor was Critical 0

0

-4,482.8

13. Reactor Reserve Shutdown Hours 629.3 1,098.9 21,233.0

14. Hours Generator On.Line 0

0 0

15. Unit Reserve Shutdown Hours r

1,597,913.7 2,573,336.4 46.202.276.88

16. Gross Thermal Energy Generated (MWH) 511.600 819,200 14.469.640

17. Gross Electrical Energy Generated (MWH) 4815.828-773.677 13.268.253

18. Net Electrical Energy Generated (MWH) 84.6 18.9 39.7

19. Unit Service Factor 84.6 16 9 39.7

20. Unit Availability Factor 80.8 15.8 32.4

21. Unit Capacity Factor (Using MDC Net) 76.8 15.1 30.8

22. Unit Capacity Factor (Using DER Net) 36*9 1*7 5.7

23. Unit Forced Outage Rate

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

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

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achieved N/A N/A INITIA L CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION (9/77)

- - -... - _ ~

9 o

AVERAGE DAILY UNIT POWER LEVEL 50-334 DOCKET NO.

UNIT 37?S Uni: El

~~

DATE L. W. Weaver COMPLETED BY TELEPHONE (412)643-53%

MONTH

^ " " " "

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net 792 l

7R6 g7 786 13 eng 2

805 804 3

j, 800 4

20 804 ana 5

21 6

22 821 800 813 7

23 796 791 g

34 796 804 9

25 190 804 26 10 804 II 27 93 0

Ros gg 12 0

808 39 13 808 0

14 30 0

804 3g 15 796 16 INSTRUCTIONS On this format.!ist the aver:ge daily unit power fesel in MWe Net for each day in the reporting snunrh. Gempute to the nearest whole megawatt.

(4/77)

50-334 DOCKET NO. __BVPS Unit #1 UNIT SilUIDOWNS ANDPOWER REDUCTIONS UNIT N AME 9-2-82 DATE COMPLETED BY

_L._W.__Wea ve> r REPORT MONTil Aucust TELErtlONE (412) 643-5303 "i:

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(,ause & Cou rettise C

1. 9 M

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Preven Recuitente 4

d 04 820826 F

10.7 A

3 82-31/03L CH VALVEX Main Feedwater Regulating Valve (FCV-lFW-478) closed after the air inlet nipple to the valve diaphragm was sheared off resulting in the i

loss of air pressure to the valve diaphragm, the valve closure, and the loss of feedwater flow to the lA Main Steam Generator. The sheared nipple was replaced and air pressure to the valve diaphragm was restored.

05 820827 S

104 B

2 N/A CC HTEXCll Manually tripped the reactor due to an apparent dropped rod.

Plant remained shut down for scheduled Steam Generator (RC-E-lC) tube repair.

4 I

I 2

3 Exhibii G - Instinctions il F.ated Reason:

Hethod:

for Pseparati.m of Data S. Sthedu!cil A-l.iguipment Failuie(Explaint 1-Manual Entr> Sheets for Iicensee B Maintenance sii Test 2-Manual scram 14cnt Repius II.I RiI Ile INURI G C Itefueling 3-Automatic Scram D Regulatory Resteiction

4. Continued From Previous Month 01611 I Opesatin Tiaining A l.icense 1:xaminalism 5-Reduction 1 Administrative 9-Other hinbil 1 SJme Nomic

( Operatsunal Iisos ll.xplaint l's/77) 11 Oiher llNpl. sin)

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