ML20071Q145

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Monthly Operating Rept for Oct 1982
ML20071Q145
Person / Time
Site: Beaver Valley
Issue date: 11/05/1982
From: Weaver L
DUQUESNE LIGHT CO.
To:
Shared Package
ML20071Q134 List:
References
NUDOCS 8212290230
Download: ML20071Q145 (6)
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Text

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DUQUESNE LIGHT COMPANY Beaver Valley Power Station NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE - OCTOBER 1982 October 1 Station in Operational mode 1 and the reactor power at a through nominal 100%. At 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br /> on the 13th began a reactor October 16 power reduction to approximately 65% to repair a broken air line (LCVSD106B). At 1545 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.878725e-4 months <br /> the broken air line was repaired and reactor power was increased back to a nominal 100%.

October 17 At 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> power was reduced by 150 MWe upon request from the system operator. At 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br /> reactor power was reduced to approximately 30%, due to oscillation of Main Feedwater Regulating Valve (MFRV)[FCV-FW-488], in order to place the Bypass Feedwater Regulating Valve (BFRV)[FCV-FW-489] in service. The benchboard control switch for FCV-FW-488 was found to faulty and was replaced and at 1710 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.50655e-4 months <br /> MFRV[FCV-FW-488] was success-fully returned to service. With the permission of the system operator, at 1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br />, the reactor power increase to 100% began and at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> the reactor reached 100%

pover.

October 18 At 0817 hours0.00946 days <br />0.227 hours <br />0.00135 weeks <br />3.108685e-4 months <br /> af ter experiencing problems with MFRV

[FCV-FW-488] oscillating and not properly controlling the B Steam Generator level a load reduction was commenced.

Then at 0826 hours0.00956 days <br />0.229 hours <br />0.00137 weeks <br />3.14293e-4 months <br /> the reactor ' tripped on a Hi-Hi level in the B Steam Generator. The Hi-Hi Steam Generator level Reactor trip caused both main feedwater pumps to be tripped electrically. When the main feedwater pump (FW-P-1B) was restarted it caused a system station IB transformer over-current trip. At 0850 hours0.00984 days <br />0.236 hours <br />0.00141 weeks <br />3.23425e-4 months <br /> an unusual event due to partial loss of offsite power was declared and at 0923 hours0.0107 days <br />0.256 hours <br />0.00153 weeks <br />3.512015e-4 months <br /> the unusual event was terminated as off site power was restored.

October 19 Station in Hot Standby mode 3. At 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br /> on the 19th through the reactor was taken critical and at 1051 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />3.999055e-4 months <br /> the Main Unit October 20 Generator was syncronized to the grid. At 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br /> a hold was placed on the reactor power increase at 35% to place the B Steam Generator on BFRV[FCV-FW-489] as the MFRV

[FCV-FW-488] was not controlling at its programmed setpoint.

At 1035 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.938175e-4 months <br /> on the 20th the MFRV[FCV-FW-488] was returned to to service and at 1050 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />3.99525e-4 months <br /> the reactor power increase was resumed. At 1220 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.6421e-4 months <br /> the reactor power reached approx-imately 96%.

October 21 Station in Operational mode 1 with the reactor power at

a nominal 100%. At 1136 hours0.0131 days <br />0.316 hours <br />0.00188 weeks <br />4.32248e-4 months <br /> the Main Steam Trip Valves j [TV-lMS-101A,B,C,] went closed, due to low instrument air 1 pressure, which resulted in a Low-Low level signal in the B Steam Generator and a Reactor trip. At 1755 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.677775e-4 months <br /> reactor startup was commenced, the reactor was then taken critical at 0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br />, and the Main Unit Generator was 8212290230 821108 PDR ADOCK 05000334 R PDR

NARRATIVE SWHARY T M3ffHLY OPERATING EXPERIENCE - OCIOIER 1982 (Continued) syncronized to the grid at 1907 hours0.0221 days <br />0.53 hours <br />0.00315 weeks <br />7.256135e-4 months <br />. Reactor power was then increased to 100%.

Oct

  • r 22 At 2216 hours0.0256 days <br />0.616 hours <br />0.00366 weeks <br />8.43188e-4 months <br /> on the 22nd began to decrease reactor power for evaluation of a possible seal failure in Beactor Ooolant Punp [RC-P-1A) . At 2250 hours0.026 days <br />0.625 hours <br />0.00372 weeks <br />8.56125e-4 months <br />, with reactor power below 10%, the Main Turbine was manually tripped.

Oct

  • r 23 At 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> on the 23rd the reactor tripped as the through reactor power level exceded the P-10 10% power range Oct
  • r 24 trip setpoints. The reactor power increase was caused by the IFRV's overfeeding the Steam Generators, thus decreasing Reactor Ooolant System tenperature and a corresponding increase in power. At 1242 hours0.0144 days <br />0.345 hours <br />0.00205 weeks <br />4.72581e-4 months <br /> en the 23rd the reactor as taken critical. At 2314 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.80477e-4 months <br /> Beactor Coolant Punp [RC-P-1A] was placed back in service, after replacing a faulty leakoff flow instrument. At 0122 hours0.00141 days <br />0.0339 hours <br />2.017196e-4 weeks <br />4.6421e-5 months <br /> on the 24th the Main Unit Generator was syncronized to the grid.

Oct

  • r 25 Station in Operational node 1 with reactor power at a through nominal 100% and the Reactor Ooolant System at normal October 28 operating tenperature and pressure.

October 29 At 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on the 29th load reduction was started through for the repair of MFRV[ECV-lM-488] . At 2155 hours0.0249 days <br />0.599 hours <br />0.00356 weeks <br />8.199775e-4 months <br />, October 31 with the reactor power at approximately 28%, ECV-EW-488 was shut and ECV-EW-489 was placed in service to control Steam Generator level. After repairs were made ECV-EW-488 was returned to service at 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br /> on the 31st. The following load changes took place upon request from the system operator: At 0550 hours0.00637 days <br />0.153 hours <br />9.093915e-4 weeks <br />2.09275e-4 months <br /> the load was increased by approximately 150 MWe to about 365 MWe ard 43%. reactor power; at 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br /> the load was increased by 100 MR3; and at 0740 hours0.00856 days <br />0.206 hours <br />0.00122 weeks <br />2.8157e-4 months <br /> the load was increasel to about 710 MWe and 83% reactor power. Ibiding reactor power and awaiting further notification from the system operator before load ircrease will begin.

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. 1 DUQUESNE LIGfT CCMPANY Beaver Valley Power Station l l

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MAJOR SAFETY RELATED MAINTENANCE - OCIOIER 1982 ,

1. Replaced the generator inboard bearings on the #2 Ibd Drive Motor Generator Set.

- 2. Maintenance work on the Mair. Feedwater Regulating Valve (KV-EW-488],

during the month of Oc

  • r, occurred twice. Maintenance replaced the cage, the valve stan, the packing and the plug. Instrument and Control replaced the actuator, the positioner, the I/P converter, an:1 the air regulators.

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OPERATING DATA REPORT DOCKET NO. 50-334 DATE 11-3-3Z COMPLETED BY L. W. Waaver TELEPHONE 412-643-1829~

OPERATING STATUS Beaver Valley Power Station, Unit #1 Notes

1. Unit Name:

OcL;,ber, 1982

2. Reporting Period:
3. f Iceawd Thermal Power (MWt): mn
4. Nameplate Rating (Gross MWe):

923

5. Design Electrical Rating (Net MWe):

852

6. Maximum Dependable Capacity (Gross MWe): 860
7. Maximum Dependable Capacity (Net MWe). 810 i
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.lf Any: N/A This Month Yr.-to.Date ' Cumulative
11. Hours In Reporting Period 745 /,296 757,000
12. Number Of Hours Reactor Was Critical 709.3 2.294.2 23.353.5
13. Reactor Reserve Shutdown Hours 0 0 '4,482.8
14. Hours Generator On-Line 684.5 2,182.1 22,336.2
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Th.armal Energy Generated (MWH) 1.633.910.4 5.202.006.7 48.830,947
17. Gross Ele.-trical Energy Generated (MWH) 524,400 , , , ,

1,662,200 15,312,640

18. Net Electrical Energy Generated (MWH) 498,310 1,541,144 14.035,720
19. Unit Service Factor 91.9 29.9 40.7 '
20. Unit Availability Factor 91.9 29.9 40.7
21. Unit Capacity Factor (Using MDC Net) 82.6 26.1 33.5
22. Unit Capacity Factor (Using DER Net) 78.5 24.8 31.8
23. Unit 'torced Outage Rate 8.1 8.7 37.9
24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Eacht:
25. If Shut Down At End Of Report Period. Estimated Date of Startup:
26. Units In Test Status 1 Prior io Commercial Operation): Forecast Ac. Sieved INITIA L CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A (9/77)

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DOCKET NO. 50--334 ,

UNIT SIIUIDOWNS AND POWER REDUCTIONS . BVI S Unit #1 UNIT NAME i

DALE 11-5-82 l COMPLETED BY _h._ L _Meitvor l

REPORT MONilg 0ctober !ELEPHONE (412) 643-1829

]g i h*t, Came & Consettne

%.. Daie E 72 4 hs' 2 E5 l.icemce Event

$-e, a> M Attion in C j@ y jj Repose s $0 Pievent Recuriente

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6 09 821018 F 26.4 A 3 N/A Cl! VALVEX Tripped on a liigh-high level in the B Steam Generator due to control problems with the B Main Feedwater Regulating Valve.

10 821021 F 7.5 G 3 N/A PA AIRDRY The inadvertent closure of IA-ll5, on the outlet of the Instrument Air Bypass Filters [IA-FD-1, 2] with the instrument air dryers in the bypass mode, resulted in low air pressure in the Instrument Air Receiver Tank

> and the temporary loss of instrument air.

11 821022 F 26.5 A 5 N/A ZZ ZZZZZZZ Reduced reactor power to below 10 percent and tripped the turbine to investigate possible Reactor Coolant Pump [RC-P-IA] Seal Failure. l I 3 3 2

F: F.u t et! Reasim: tie thod: F.xhibit G Insiinttions S Sthedn'ed A liluipment Failure (Esplain) 1-Manual fo Prepasation of Data

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it Maintenance or Test 2-Manual Scram 1:ntes Sheets for 1.icensee C RcIucting 3-Automatic Scram 13ent Repost 11 i Rll ite tNilRI G D Regulatory Restsittiint 4-Continued From Previous Month Ultil l i Operato: Tsaining A litenw I xaminati"" 5-Reduction "

I - Aihnimsts.itive 9-Other ,

G Operational 1 ison 11 splaml I.slubit 1 Same Som(e 19/77) 11 Other il splaml

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- . l AVERAGE DAll UNIT POWER LEVEL DOCKET NO. 50-334 UNIT SV?S Uni: #1 DATE 11-5-82 COMPLETED BY L. W. Weaver:

11LEPHONE 412-643-1829!

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l gg October l AVERAGE DAILY POWER LEVEL l DAY AVERAGE DAILY POWER LEVEL DAY (Mwe Net) (Mw,.Na s l 809 g7 469 g

2 809 33 273 3 801 19 82 801 486 I 4 3 801 510 3 21 801 22 765 6

808 0 7 23 801 24 698 8

809 , 805 9

801 801 10 26 805 801

- 27 805 793 I,. :s 809 726 13 29 305 171 14 30 813 514 g3 3, 16 817 INSTRUCTIONS On this format.!ist the average daily unit power lesel in MWe Net for each day 4n the reportine inuoth. Compute io

'the nearest whole megswatt.

l (4/77) l

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