ML20004F381

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Monthly Operating Rept for May 1981
ML20004F381
Person / Time
Site: Beaver Valley
Issue date: 06/03/1981
From: Timko D
DUQUESNE LIGHT CO.
To:
Shared Package
ML20004F380 List:
References
NUDOCS 8106180268
Download: ML20004F381 (5)
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a OPERATING DATA REPORT DOCKET NO. 50-334 DATE June 3, 1981

COMPLETED BY D. R. Timko j TELEPHONE. 412-641-9308  !

OPERATING STATUS Notes  !

1. Unit Name:- Beaver Valley Power Station, Unit *#1
2. Reporting Period: * ' ' 1091
3. Licev-d Thermal Power (MWt): 7660
4. Nam vre Aating (Gross MWe): 923 S. Design t ectrical Ratmg (Net MWe): 852
6. Maximuen Dependable Capacity (Gross MWe):

845

7. Maximum Dependable Capacity (Net MWe): 810
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,if Any; N/A This Month Yr to.Date Cumulative
11. Hours la Reporting Period 744 1.671 4'4,567
12. Number Of Hours Reactor Was Critical 556.75 ._ 1,887.21 16.417.88
13. Reactor Reserve Shutdown Hours 0 0 4,482.8
14. Hours Generator on.Line 554.58 1,833.34 15,540.59 IS. Unit Reserve Shutdown Hours 0 0 0
16. Grom Thermal Energy Generated (MWH) 1.300.796.al 4.303.572.09 32.411.465.24
17. Gross Electrical Energy Generated (MWH) 475.800 ._. 1.466.700 10,040.040
18. Net Electrical Energy Generated !MWH) 444.716 1,290,492 9,151.906
19. Unit Service Factor 74.5 50.6 35.9
20. Unit Availability Factor 74.5 50.6 35.9
21. Unit Capacity Factor (Using MDC Nett 73 .8 44.0 28.3
22. Unit Capacity Factor iUsing DER Net) 70.2 41.8 26.0
23. Unit Forced Outage Rate 25.5 40.4 46.6
24. S~aardowns Scheduled Over Next 6 MonthsIType.Date,and Duration of Cacht:

None 2S. If Shut Down At End Of Report Period. Estimated Date of Startup: N/A

26. Units in Test StatusiPrior o Commercist Operation 1: Forecast Achieved INITIAL CRITICALITY -- N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A (9/77)

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-334 UNIT BVPS Unit #1 DATE June 3, 1981 COMPLETED BY D. R. TW TELEPHONE 412-643-5308 MONTH Mav, 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) g 793 37 804 2 46 33 816 3 0 19 804 4 0 20 808 5 0 23 816 6 0 22 813 7 0 23 817 3

0 817 24 9 0 23 813 10 743 26 800 g3 808 27 805 12 820 gg 816 13 820 29 805 14 804 30 816 15 816 33 817 16 821 INSTRUCTIONS On this format.!ist the awrage daily unit power lesel in MWe Net for each day in the reputting nwnth.Cmnpute to the nearest whole megawatt.

(9/77)

k

..s DOCKET NO. 50-334 ,

UNIT SHUTDOWNS AND POWER REDUCTIONS BVPS Unir #1 UNIT N AME DATE Jtme 3. 1981 COMPLETED BY _D. R. Tlako REPORT MONTil Pf a v . 1981 TELEPilONE 412-643- 5308 ,

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5'O g3 Assion su 3: $ j ;y3 g Rep.us = g' Pseveni Recurscoce .

d 6 810502 F 189.42 A 3 81-32 Cll VALVEX Halfunction of "A" feed regulating valve due to disconnected actuator to positioner feedback linkage and a fractured valve stem resulted in a high-high steam generator level reactor trip. The "A" and "C" valve

  • stems were replaced, all three valves were rebuilt, the stem locking anti-rotation devices cere properly installed, and all valve actuator to positioner linkage connections were sealed with loc-tite.

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'l 2 , 3 4 F: Fouced Reason: , Methal: Exinbit G . Instructions 5: Schedu!cd A.Equipmens Failure (Explain)  ! l Manual fin Piepaiation of Dana B Maintenance eiTesi 2 Manual Ses'am. Enten Sheets fin Licensee C Refueling 3 Auto'matic Suam. liveni Repou ILER) Fde INtlREG D Regulaiory Resisicaina 4 Othes (Explain) 01611 1 Ope:4tos Trainingi 1icense limanunation F Adnumstsasive 5 G Operaison.d Enos llimplaint ,

E sinbis 1 - Same'Sousee 19/77) 11 Othes ( E splain)

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, _ -DUQUESNE LIGHT COMPANY Beaver Valley P,ower Station NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE - MAY". 1981 May.1 Station in Operational Mode 1 at nominal full Reactor power. After a

'through series of vibration transients on the "A" Main Feedwater Lines, the

May 2 Reactor tripped at 0208 hours0.00241 days <br />0.0578 hours <br />3.439153e-4 weeks <br />7.9144e-5 months <br /> on May 2.on a High-High "lA" Steam Generator Level due to a malfunction of the "A" Main Feedwater E Regulating Valve. The vibrating of the Main Feedwater lines caused some damage to several snubbers in containment which required a cold plant shutdown for taking radiographs of the "A" Main Feedwater lines -

to check for possible damage.

May 3 ' Station in Operational Mode 3 with the Reactor Coolant System pressure and temperature at approximately 2235 PSIG and 547F. At 0012 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, cooldown of the' Reactor Coolant system was begun for repairs and radiographs of the Feedwater lines in Containment. At 0714 hours0.00826 days <br />0.198 hours <br />0.00118 weeks <br />2.71677e-4 months <br /> the Station entered operational Mode 4. Commenced warm-up of-the

' Residual Heat Removal System at 1045 hours0.0121 days <br />0.29 hours <br />0.00173 weeks <br />3.976225e-4 months <br />. The Residual Heat Removal System was put in service at 1548 hours0.0179 days <br />0.43 hours <br />0.00256 weeks <br />5.89014e-4 months <br />. -The Station entered operational Mode 5 at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> and Containment vacuum was broken at 2035 hours0.0236 days <br />0.565 hours <br />0.00336 weeks <br />7.743175e-4 months <br />.

May 4 Station in Operational Mode 5 with the Reactor Coolant System pressure and temperature at approximately 250 PSIG and 184F. At 0715 hours0.00828 days <br />0.199 hours <br />0.00118 weeks <br />2.720575e-4 months <br />, drainage of tha 1A Steam Generator Feedwater line was begun. .

At 2345 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.922725e-4 months <br />, the Feedwater lines finished draining.

May 5 Station in Operational Mode 5 with the Reactor Coolant System pressure through .- and temperature at 0 PSIG and 109.5F. On May 5 at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, May 7 Radiography was begun onlthe "A" Feedwater lines in Containment and was completed on May ' at 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br />. At 1455 hours0.0168 days <br />0.404 hours <br />0.00241 weeks <br />5.536275e-4 months <br /> on May 7 pressurization of the Reactor Coolant system was begun at 1722 hours0.0199 days <br />0.478 hours <br />0.00285 weeks <br />6.55221e-4 months <br /> drawing containment vacuuu was commenced.

May 8 ~ Station in Operational Mode 5 with the Reactor Coolant System pressure and temperature at 340 PSIG and 158F. At 0627 hours0.00726 days <br />0.174 hours <br />0.00104 weeks <br />2.385735e-4 months <br />, Mode 4 was achieved and at 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br /> the Reactor Coolant System was held at 3400 F to make adjustments on the Residual Heat Inlet Isolation Valve (MOV-RH-700). At 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> the Residual Heat Removal System was taken out of service. The Station entered Mode 3 at 1238 hours0.0143 days <br />0.344 hours <br />0.00205 weeks <br />4.71059e-4 months <br />.

May 9 Station in Operationel Mode 3 with the Reactor Looiant System pressure and temperature at 2240 PSIC and 546F. Criticality was achieved at 2044 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.77742e-4 months <br /> but the Reactor tripped at 2129 hours0.0246 days <br />0.591 hours <br />0.00352 weeks <br />8.100845e-4 months <br /> due to Low-Low "lC" Steam Generator Level. Criticality was achieved again at 2204 hours0.0255 days <br />0.612 hours <br />0.00364 weeks <br />8.38622e-4 months <br />.

The Main unit was synchronized at 2332 hours0.027 days <br />0.648 hours <br />0.00386 weeks <br />8.87326e-4 months <br />.

-May 10 Station in Operational Mode 1 at nominal 3% Reactor power level. By 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> the Reactor was 98% of full power.

i May 11 Station in Operational Mode 1 at nominal full Reactor Power Level.

through May 31 J

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  • -4 DUQUESNE LIGHT COMPANY Beaver Valley Power Station MAJOR SAFETY-RELATED MAINTENANCE - MAY 1981 1.- Repairs were made on ITT Grinnell Snubbers on the "A" Main Feedwater line in Containr.ent due to a series of vibration transients which damaged them.
2. Radiography of the "A" Main Feedwater line in Containment to check for possible damage after finding' snubber damage.

3 .- Repairs on the "A" Main Feedwater Regulating Valve were performed prior to plant start-up.

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