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)

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DUQUESNE LIGHT COMPANY Beaver Valley Power Station NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE - AUGUST 1982 August 1 The Station is in Operational Mode 1 at a nominal 100% reactor power through level.

The Reactor Coolant System leak from the primary to secondary August 25 side of the 1C Steam Generator has steadily increased from approximately

.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%.

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

August 27 Holding reactor power stable at a nominal 28% forAt1C1600 Steam Generator hours, 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 secondary voltage output to go to zero. Indication for the P-8 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 trip. At 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 conditions. 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.

August 28 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 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.

Augus t 29 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 /> through on the 30th began to drain the C Reactor Coolant Loop Hot Leg, and at 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-ization was placed in service. The Reactor Coolant System Tavg. and 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

1. Steam Generator [RC-E-lC] tube plugging in progress to eliminate Reactor Coolant System leakage to the secondary side.

2. The Charging Pump [CH-P-1C] shaf t-driven lube oil pump was replaced because the gear drive would not hold pressure.

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

4. Fire Protection check valve [FP-30] on the discharge of the Pressure 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 Beaver Valley Power Station. Unit #1 NOL*5

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):

6. Maximum Dependable Capacity (Gross MWe): 860 810

7. Maximum Dependable Capacity (Net MWe):

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

9. Power Level To which Restricted. lf Any (Net MWe): None

10. Reasons For Restrictions.If Any: N/A 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 -4,482.8 0 0

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

14. Hours Generator On.Line 0 0 0

15. Unit Reserve Shutdown Hours r 2,573,336.4 1,597,913.7 46.202.276.88

16. Gross Thermal Energy Generated (MWH)

17. Gross Electrical Energy Generated (MWH) 511.600 819,200 14.469.640

18. Net Electrical Energy Generated (MWH) 4815.828- 773.677 13.268.253 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) 30.8 76.8 15.1

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

- - - - . . . - _ ~

9

. o AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-334 UNIT 37?S Uni: El

~~

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

MONTH ^""""

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL '

(MWe-Net) (MWe-Net 7R6 g7 792 l

786 eng 2 13 805 j, 804 3

800 4 20 804 ana 5 21 800 22 821 6

813 7 23 791 796 g 34 .

796 25 804 9

804 190 10 26 804 27 93 II Ros gg 0 12 0

13 808 .

39 808 0 14 30 0

15 804 3g 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 UNIT SilUIDOWNS ANDPOWER REDUCTIONS DOCKET UNIT N AME NO. __BVPS Unit #1 DATE 9-2-82 COMPLETED BY _L._W.__Wea ve> r REPORT MONTil Aucust TELErtlONE (412) 643-5303 "i:

C #9 M e-E",,, (,ause & Cou rettise 7,, 2e E pEX Es.censee c% Assion to

\d - D 8'c i 3? 4 255 Even: 32 4!

Nu jgg Preven Recuitente 4

8. E d Repine : j' d

CH VALVEX Main Feedwater Regulating Valve 04 820826 F 10.7 A 3 82-31/03L

! (FCV-lFW-478) closed after the air inlet nipple to the valve diaphragm i

was sheared off resulting in the 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.

2 N/A CC HTEXCll Manually tripped the reactor due to 05 820827 S 104 B an apparent dropped rod. Plant remained shut down for scheduled Steam Generator (RC-E-lC) tube repair.

3 4 I' I 2 Exhibii G - Instinctions il F.ated Reason: Hethod:

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

4. Continued From Previous Month 01611 D Regulatory Resteiction 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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