ML20081M865

Monthly Operating Rept for Sept 1983

ML20081M865
Person / Time
Site:	Beaver Valley
Issue date:	10/04/1983
From:	Carey J, Holtz J DUQUESNE LIGHT CO.
To:	NRC
References
NUDOCS 8311170408
Download: ML20081M865 (8)

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If NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE - SEPTEMBER, 1983 S;ptember 1 The station was in Operational Mode 6 with fuel reloading in progress. Fuel movement was halted at 0615 hours0.00712 days <br />0.171 hours <br />0.00102 weeks <br />2.340075e-4 months <br /> due to malfunctioning of the fuel transfer system. After inspec-tion of the system, fuel movement was resumed. Loading of the core was completed at 1734 hours0.0201 days <br />0.482 hours <br />0.00287 weeks <br />6.59787e-4 months <br />.

S:ptember.2 At 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />, the upper internals were lif ted and placed on the reactor core. Rod latching and drag testing were begun soon afterward. At 1848 hours0.0214 days <br />0.513 hours <br />0.00306 weeks <br />7.03164e-4 months <br />, the refueling tube gate valve was closed.

Ssptember 3 Preparations were made for the replacement of the reactor vessel head. At 0740 hours0.00856 days <br />0.206 hours <br />0.00122 weeks <br />2.8157e-4 months <br />, the final valve lineup for pump- .

ing down the refueling cavity was begun. At 0810 hours0.00938 days <br />0.225 hours <br />0.00134 weeks <br />3.08205e-4 months <br />, draining of the refueling cavity was commenced. The level in the reactor vessel was reduced to approximately seven (7) inches below the vessel flange. At 1201 hours0.0139 days <br />0.334 hours <br />0.00199 weeks <br />4.569805e-4 months <br />, the vessel head was lowered into place.

Ssptember 4 The station was in Operational Mode 6. The Residual Heat Through Removal System was controlling decay heat. The Reactor Coolant Szptember 7 System was at atmospheric pressure. At 0605 hours0.007 days <br />0.168 hours <br />0.001 weeks <br />2.302025e-4 months <br /> on the 7th, the station entered Mode 5.

Szptember 8 The Reactor Coolant System was filled to 20 percent pressurizer Through level. On the 9th, RCS temperature was increased to 150*,

Szptember 9, while pressure was maintained at ambient conditions.

Szptember 10 The turbine was placed on turning gear at 2245 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.542225e-4 months <br /> to check, Through alignment. Continuad preparations for startup.

September 11 September 12 A steam bubble was established in the pressurizer at 0440 hours0.00509 days <br />0.122 hours <br />7.275132e-4 weeks <br />1.6742e-4 months <br />.

Reactor Coolant System temperature was 135*F; pressure was 325 psig.

Szptember 13 The station was in Operational Mode 5. Reactor Coolant System Through temperature and pressure were being maintained at 170*F and September 16 319 psig respectively. Startup testing was continuing.

Commenced drawing Containment vacuum at 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br /> on the 16th, and at 1155 hours0.0134 days <br />0.321 hours <br />0.00191 weeks <br />4.394775e-4 months <br />, the Containment Vacuum Air Ejector was secured. The } bin Feedwater System was filled and vented at 1245 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.737225e-4 months <br />. At 1906 hours0.0221 days <br />0.529 hours <br />0.00315 weeks <br />7.25233e-4 months <br />, the Containment Vacuum Air Ejector was started and a vacuum drawn. The Air Ejector was secured at 2240 hours0.0259 days <br />0.622 hours <br />0.0037 weeks <br />8.5232e-4 months <br />. Containment pressure was 9.2 psia.

Saptember 17 'At 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> the station entered Mode 4.

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'# NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE - SEPTEMBER, 1983 i

September 18 The Residual Heat Removal System was removed from service at 0350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br />. Reactor Coolant Pumps lA and 1C were running.

At 0542 hours0.00627 days <br />0.151 hours <br />8.96164e-4 weeks <br />2.06231e-4 months <br />, the IB Reactor Coolant Pump was started. RCS heatup and pressurization continued. The station entered Mode 3 at 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> with reactor coolant pressure and temper-ature at 575 psig and 350*F respectively.

September 19 The station was in Operational Mode 3, hot standby. Reactor Coolant System temperature and pressure were increased to 547'F and 2230 psig, respectively, and maintained at those levels.

While filling the 1A Safety Injection Accumulator, the level dropped below that required by the Technical Specifications.

The problem was found to be a broken weld on the Fill Line Vent Valve [SI-408). The plant was placed in Mode 4, hot shutdown, at 2246 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.54603e-4 months <br /> as required by the Technical Specifi-cations action statement. The normal fill line was isolated while the line was being welded. Filling of the accumulator was done through the Nitrogen Supply Line under a temporary operating procedure.

September 20 The weld repair on SI-408 was dye checked and the line was pressure tested satisfactorily at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />. The Reactor Coolant System was then heated up to enter Mode 3, which occurred at 1324 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.03782e-4 months <br />.

September 21 The station was in Operational Mode 3, hot standby, The Reactor Coolant System temperature and pressure were being increased to normal operating level. Surveillance testing was in progress.

September 22 Normal operating pressure, 2235 psig, and temperature, 547'F, were reached and maintained. At 0827 hours0.00957 days <br />0.23 hours <br />0.00137 weeks <br />3.146735e-4 months <br />, control rod ,

,ovement was begun for the initial approach to criticality.

. Problems were encountered in the withdrawal of Control Bank 'B',

i which stopped moving at 226 steps and would not move in or out.

l Voltage readings were taken on both the stationary and the moveable gripper coils and both were found to be energized.

The reactor was manually tripped and the logic cabinets were reset. Shutdown Banks 'A' and 'B' were pulled at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, and the initial approach to criticality was begun again.

Once again, problems were encountered with rod withdrawal.

Upon investigation, the problem was found to be a bad decoder card in the bank overlap system. The card was replaced, and the overlap system was tested satisfactorily. The initial aIproach to criticality was started at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />. At 2218 hours0.0257 days <br />0.616 hours <br />0.00367 weeks <br />8.43949e-4 months <br />, criticality was achieved with Control Bank 'D' at 195 steps.

September 23 During performance of the initial approach to criticality test, operators noticed that Control Rod J-7 in Shutdown Bank 'B' had exceeded its 12-step limit from the demand indication.

< N_ARRATIVE

SUMMARY

'0F'MONIHLY OPERATING EXPERIENCE - SEPTEMBER,,198,3_

September 23 The individual rod position indicated 215 steps while demand (Continued) read 228 steps. .The primary voltage was read in order to determine if the rod was misaligned. The primary voltage

-indicated that the rod was at 218 steps, within the 12-step limit. The signal conditioning module was recalibrated, and the RPI was returned to service at 0240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br />.

Core low-power physics testing was in progress.

September 24 The station was in Operational Mode 2 with the Reactor Coolant System at normal operating temperature and pressure. At 0118 hours0.00137 days <br />0.0328 hours <br />1.951058e-4 weeks <br />4.4899e-5 months <br />, the turbine was latched. The turbine was tripped immediately afterward due 'to the failure of the 15V Power Supply EHC System. The power supply was replaced, and the turbine was tripped a second time at 0328 hours0.0038 days <br />0.0911 hours <br />5.42328e-4 weeks <br />1.24804e-4 months <br /> due to high level in the shell. side of the 1A First Point Heater. This was found to be caused by the vacuum drag on the heater which caused the level column to see a high shell side level. The turbine was rolled and taken to 950 rpm at 0518 hours0.006 days <br />0.144 hours <br />8.564815e-4 weeks <br />1.97099e-4 months <br />.

- At 0903 hours0.0105 days <br />0.251 hours <br />0.00149 weeks <br />3.435915e-4 months <br />, the Main Unit Generator was synchronized to the grid. Reactor power was at 25 percent and being increased in 1%/20-minute increments. Reactor power was taken to 30 percent and maintained for performance of a calorimetric.

' At 1725 hours0.02 days <br />0.479 hours <br />0.00285 weeks <br />6.563625e-4 months <br />, operation began reducing reactor power to perform the Turbine Overspeed Trip Test. The Main Unit Generator was taken off line at 1808 hours0.0209 days <br />0.502 hours <br />0.00299 weeks <br />6.87944e-4 months <br />. The Overspeed Trip Test was completed at 1855 hours0.0215 days <br />0.515 hours <br />0.00307 weeks <br />7.058275e-4 months <br /> and the generator synchronized to the grid at 2335 hours0.027 days <br />0.649 hours <br />0.00386 weeks <br />8.884675e-4 months <br />. Reactor power was at 20 percent and an increase of 3%/ hour was begun at 2350 hours0.0272 days <br />0.653 hours <br />0.00389 weeks <br />8.94175e-4 months <br />.

September 25 Reactor power was at a 48 percent hold point to perform a Through. full-core flux map. The Reactor Coolant System was at normal September 26- operating pressure and temperature.

i- September 27 All nuclear parameters monitored in the 48 percent flux map Through were found to be within their Technical Specification limits.

September 28 An increase in reactor power level to 72 percent was begun at 1620 hours0.0188 days <br />0.45 hours <br />0.00268 weeks <br />6.1641e-4 months <br />. At 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on the 28th, three RPIs in Control Bank 'D'.were reading greater than 12 steps from

the group demand counter. New power curves were generated

, and the RPIs on all three control rods were within limits.

At 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br />, 73 percent reactor power was reached.

September 29 Reactor power was being maintained at 73 percent to perform Through a full-core flux map and 5 quarter-core maps for calibration

. September 30 of Power Range Detectors N-41, N-42, N-43, and N-44.

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MAJOR SAFETY-RELATED MAINTENANCE - SEPTDiBER 1983

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1. Overhaul of 1A and 1B Containment Air Recirculation Fan Motors.

2. Replaced seals in lA Main Feedwater Pump.

3. Repaired the actuator on the 1B Main Steam Trip Valve [TV-MS-101B).

4. Replaced the 'A' Incore Detector.

5. Repaired a broken weld on Vent Valve SI-408 on the 1A Safety Injection Accumulator Fill Line.

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OPERATI G DATA REPORT DOCKET NO. 50-334 DATE _10-4-til '

COMPLETED BY J. L. Noltz

. TELEPHONE. 41 ?-A43-1369 OPERATING STATUS

1. Urdt Name: Beaver Valley Power Station, Unit #1 Notes

2. Reporting Period: September, 1983

3. Licensed Thermal Power (MWt): 2AM

4. Nameplate Rating (Gross MWe): 923 S. Design Electrical Rating (Net MWe): 835

6. Maximum Dependable Capacity (Gross MWe): 860

7. Maximum Dependable Capacity (Net MWe): 810

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

9. Power Level To %'hich Restricted If Any (Net MWe): None

10. Reasons For Restrictions,if Any:. N/A

_ This Month Yr to-Date " Cumulative 6,551

11. Hours In Reporting Period 720 65,015

12. Number Of Hours Reactor Was Critical 193.7' 3,912.6 28,730.1

13. Reactor Reserve Shutdown Hours 0 0 4,482.8-

14. Hours Generator On-Line 153.5 3,861.7 27,661.9

15. Unit Reserve Shutdown Hours 0 0 0 -

16. Gross Thermal Energy Generated (MWH) 233,976 9,710,624.8 62,220,806.2

17. Gross Electrical Energy Generated (MWH) 72,120 3,163,520 19,676,160

18. Net Electrical Energy Generated (MWH) 62,092 3,003,409 18,215,526

19. Unit Service Factor 21.3 58.9 44.4

20. Unit Availability Fletor 21.3 58.9 44.4

21. Unit Capacity Factor (Using MDC Net) 10.6 56.6 37.8

22. Unit Capacity Factor (Using DER Net) 10.3 54.9 36.7

23. Unit Forced Outage Rate 0 3.8 32.7

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

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 CRITICA LITY "/A N/A INITIA L ELECTRICITY N/A N/A COMM ERCIAL OPERATION N/A N/A (9/77)

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t AVERAGE DAll. UNIT POWER LEVEL DOCKET NO. 50-334 UNIT 37?S Unde #1 DATE Oct her 4/83 COMPLETED BY J. L. Holtz TELEPHONE 412-643-1369 .

gg September DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe Net) 0 0 ,

1 37 0 gg 0

2 O j, o

3 0

0 4

0 o ,

$ n 0 0 t, i 6 22

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0 0 -

7 y 0 35 y 8 34  ;

0 294 h 9 ,

0 26 373 [

10 0 367 7 l gg 7 ,

0 531 12 25 0 593 a

) 13 0 603 14 30 ~

1 1

0 .

I 15 33 0 _

16 i

INSTRUC110NS On this format. list the average dstly unit power fesciin MWe-Net for esc.i day in the reporting munth. Gunpute to the nearest whole megswatt.

(9/77)

e' 50-334 ' -

UNITSilUTDOWNS AND POWER REDUCTIONS DOCKET NO.

] UNIT NAME BVPS Unit il DATE _10-4-83 COMPLETED BY J. L. lioltz

.REPORTMONTil Sentember 2

TELErilONE _412-643-1369

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i 5 06/10/83 S 2535.1 C 1 N/A ZZ ZZZZZZ Shutdown for 3rd refueling and major modifications outage.

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1 I 2 3 4 l' F: Forced Reason:

5: Scheduled Hethod: Exhibit G. Insituctions A.Eigulpment Failure (Explain) 1-Manual B Maintenance **(Test fin Peerasasi.m of Data

2-Manual Scram * '

Entr) Sheets for l_icensee C.ReIncling 3-Automatic Scram

, D Regulatin) Restricliam liven Repius a Ll'RI File iNUREG 4-Continued From Frevious Month 0161) l~ Opciato: Training & Liccuse lixaminalism 5-Reduction F.Administrailve 9-Other .*

G.Operatiimal Eisne llimplain t Exliible I . Same, Source

(*)/77) Il Olher IEsplain 3

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'Af l Telephone (412) 393-6000 Nuclear Div!sion )

l P.O. Box 4 Shippingport, PA 15077-0004 )

October 7, 1983 l

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Beaver Valley Power Station, Unit No. 1 -

j Docket No. 50-334, License No. DPR-66 Monthly Operating Report ll l

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United States Nuclear Regulatory Commission Director, Office of Management Information & Program Control f I

Washington, D.C. 20555 Gentlemen:

In accordance with Appendix A, Technical Specifications, the Monthly Operating Report is submitted for the month of September, 1983. j 1

Very tru y yours, i l

J. . Carey Vice President Nuclear Division Encisoures cc: NRC Regional Of fice, King of Prussia, PA i

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