ML20084E320

Monthly Operating Rept for Mar 1984

ML20084E320
Person / Time
Site:	Beaver Valley
Issue date:	03/31/1984
From:	Carey J, Holtz J DUQUESNE LIGHT CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8405020231
Download: ML20084E320 (8)

Text

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NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE - MARCH, 1984 March 1 The station in operational mode 1 with reactor power a nominal through 100%. The Reactor Coolant System was at normal operating March 8 temperature and pressure.

March 9 The station was in operational mode 1 at a nominal 100%

reactor power. Due to a high RCS leakrate, it was decided to

. take the station off-line to effect coolant system repairs and perform other plant maintenance. At 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br />, a power reduc-tion was begun. Reactor power was held at 75%, 50s, and 20% to allow primary and secondary volte e readings to be taken on the Rod Position Indicators.

March 10 The Main Unit Generator output breakers were opened at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. The Main Turbine was tripped at 0002 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Reactor power was being maintained at 6 x 10-6 amps in the intermediate range.

March 11 The station was in operational mode 2 with reactor power being through maintained at 2 x 10-6 amps. Work was proceeding on repairing March 12 the leak in the IC RCS loop and on balancing the turbine. It was decided to de-escalate reactor power and cooldown the RCS to facilitate leak repairs. At 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on the 12th, as the reactor was being shutdown, a reactor trip occurred as source rango fuses were being installed.

March 13 The station was in operational mode 3 with reactor power at 2000 counts per second. Cooldown of the RCS was begun in order to repair various Reactor Coolant System Icaks. The station entered modo 4 at 0720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> and the RHR system was placed in service at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />. The station entered mode 5 at 2126 hours0.0246 days <br />0.591 hours <br />0.00352 weeks <br />8.08943e-4 months <br /> and containment vacuum was broken at 2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br />.

March 14 The station was in operational modo 5 with the RHR system in through service controlling decay heat. Work was continuing on the March 15 repair of RCS leaks. The 1A Reactor Coolant Pump was started at 1520 hours0.0176 days <br />0.422 hours <br />0.00251 weeks <br />5.7836e-4 months <br /> on the 15th.

March 16 The station was in operational mode 5. At 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, oporations bogan drawing vacuum in containment in preparation for plant startup.

March 17 Problems wore encountered in preparation for plant startup.

MOV-CH-289, the Charging Header containment Isolation Valve, gave dual indication whilo closed. Also, the breech lock on the innor door of the containment Personnel Air Lock was mal-functioning. Plant startup was delayed while these items were repaired.

8405020231 840331 DR ADOCK 05000334 PDR i

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March 18 The Containment Personnel Air Lock was returned to service at 0340 hours0.00394 days <br />0.0944 hours <br />5.621693e-4 weeks <br />1.2937e-4 months <br />. Repairs were completed on MOV-CH-289 and the valve was tested satisfactorily at 1428 hours0.0165 days <br />0.397 hours <br />0.00236 weeks <br />5.43354e-4 months <br />. The 1B Reactor Coolant Pump was started at 1503 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.718915e-4 months <br /> and immediately shutdown due to high seal leak-off. Reactor coolant system heatup continued and the station entered mode 4 at 1532 hours0.0177 days <br />0.426 hours <br />0.00253 weeks <br />5.82926e-4 months <br />. The 1C Reactor Coolant Pump was started at 1557 hours0.018 days <br />0.433 hours <br />0.00257 weeks <br />5.924385e-4 months <br />. l March 19 The station entered mode 3 at 0250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br />. Reactor Coolant Pumps 1A and 1C were in service. Investigation continued in an attempt to correct the IB Reactor Coolant Pump seal leak-off problems.

At 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br />, with RCS pressure at 1000 psig, the #1 seal on the pump reseated itself when the seal leak-off isolation valve was opened. The pump was then started without incident. The plant continued heating up at 25eF/HR and the RHR system was taken out of service at 2010 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.64805e-4 months <br />. At 2124 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.08182e-4 months <br />, a containment entry was made to Furmanite the loop IC Cold Leg Manifold Inlet Isolation Valve, RC-31. The flange for flow orifice RC-482 was tightened also.

March 20 Reactor startup was begun at 0131 hours0.00152 days <br />0.0364 hours <br />2.166005e-4 weeks <br />4.98455e-5 months <br /> and the reactor was taken critical at 0220 hours0.00255 days <br />0.0611 hours <br />3.637566e-4 weeks <br />8.371e-5 months <br />. The maintenance crew in containment had been unable to stop the leak on flange for PIS-RC-482A & B. It

, was decided to install a drip collector hood around the flange to I

direct the leakage to the sump. A containment entry was made at 0656 hours0.00759 days <br />0.182 hours <br />0.00108 weeks <br />2.49608e-4 months <br /> to perform the work.

The Main Turbine had been rolled and was at 1800 RPM at 0520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br /> awaiting completion of the work in containment. The turbine was tripped at 0925 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.519625e-4 months <br /> when it became apparent that the containment work would take longer than originally anticipated. At 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br />, the nonreturn valve on the line from the 3A feedwater heater to the condenser, NRV-ES-103A, was found to be jammed. Repairs were begun on the valve actuator.

At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />, the maintenance crew departed containment. Repairs

) to NRV-ES-103A were completed at 1755 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.677775e-4 months <br /> and turbine startup was begun immediately. The Main Unit Generator was synchronized to the grid at 1834 hours0.0212 days <br />0.509 hours <br />0.00303 weeks <br />6.97837e-4 months <br />.

March 21 The station was in operational mode 1 with reactor power at 666 at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. An escalation of reactor power was in progress and 100% power was achieved at 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />.

March 22 The station was in operational mode 1 with reactor power a nominal through 1004. The Reactor Coolant System was at normal operating temperature March 31 and pressure.

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i MAJoh MAINTENANCE - MARCII, 1984 l

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1. Tubes in Component Cooling Water lleat Exchangers CC-E-3A & 3B l were cleaned.

2. The Main Unit Turbine was balanced.

3. The outboard seal and suction gasket were replaced on the 1B Main Feedwater Pump, FW-P-1B.

, 4. Repaired leaks on flow orifices RC-481, 482 on the 1C Reactor l Coolant loop.

1

5. Motor operator on MOV-Cll-289, Charging Header Containment Isolation Valve, was repaired.

6. Repaired the breach ring lock pin of the inner Containment Personnel Airlock door.

7. The nonreturn valve on the 3A Feedwater Heater [NRV-ES-103A] was repaired.

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OPERATING DATA REPORT DOCKET NO. 50-334 DATE 4-9-84 COMPLETED BY 3. L. ifo l_t z

, TELEPHONE. L 1 - A L 1-1369 OPERATING STATUS I. Unit Name: Beaver Valley Power Station, Unit #1 Notes

2. Reporting Period: M f'ch> 1"4

3. Licensed Thermal Power (MWt): # # ^

4. Nameplate Rating (Grou MWe): 923

5. Design Electri:al Raung (Net MWe): 835

6. Maximum Dependable Capacity (Gross MWe): 860

7. Maximum Dependable Capselty (Net MWe): 810

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

9. Pow-er Level To Which Restricted.lf Any (Net MWe): Non'

10. Reasons For Restrdetions,If Any: N/A This Month Yrto.Dete ' Cumulative

11. Ilours In Reporting Period 744 21R4 69,40s .

12. Number Of Hours Reactor Was Critical 571.7 1985.7 32,865.1

13. Reactor Resene Shutdown Hourt O O 44R2,R

14. Hours Generator 0n.Line 4RS.4 1837.5 31,616.3 l$. Unit Resene Shutdown llours 0 0 0 .

16. Gross Thermal Enetyy Generated (MWil) 1.?63.131.7 4,626,931.2 72,216,469.7

17. Gross Electrical Energy Generated (MWH) 409,000 1,500,500 _22,929,440

18. Net Electrical Energy Generated (MWH) 17n.910 1.41n. dis .21.299.303

19. Unit service Factor , 65.2 94.1 47.7

20. Unit Atallability Factor 65.2 R4.1 47.7

21. Unit Capacity Factor (Using MDC Net! 62.9 79.7 _

41.4

22. Unit Capacity Factor (Using DER Net) 61.0 77.4 40.1

23. Unli Forced Outage Rate o 4.6 29.a

24. Shutdowns Scheduled Over Next 6 Months tType.Date,and Duration of Eschi:

23. If Shul Down Al End Of Report Period. Estimated Date of 5tartup:

26. Units in Test Status (Prior to Commeretal Opmtioni: Forecent AcMeved INITI A L CRITICA LITY _ M / A __ _ ?f / A INITI AL ELECTRICITY **

N/A __N/A C0\l%IERCI AL OPER ATION _ N/A _ N/A (9/77)

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)' AVERAGE DA3Li UNIT POWER LIVEL l

r DOCKIT NO. O 33' ugg7 M S Ur.it di DATE 4~9-84 COMPLITED BY J. L. Holtz 4

. TELEPHONg M) 643-136 MONTH Mar h . -

l' DAY AVERACE DAILY POWER LIVEL

• DAY AVERACE DAILY POWER LEVIL (MWe Net) .

(MWe Net)

,1 783 17 0 2 824 gg o 3 784

• 19 ' o I

- 4 817 20 En i

3 743 783 21 ,

} 6 829 ' '

825 22

{ 7 783 -

ag 784 3 823 825 24 9 713 784 23 10 0 - #

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, 23 825 i3 e j

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• The gross generation integrator installed in February reads only to the I

nearest 1000 MWH, as opposed to the original integrator which read to the nearest 100 MWH. Given this reduction in meter accuracy, a 24 haur period I

does not provide enough readings to yleid on accurate station daily average.

] The not generation strip chart recorder, however, shows that the station

' output during the month remained steady, averaging between 800 and 810 MWe for those times when the reactor was at 100% power. This is consistent with previous months' data. This integrator j investigated for any necessary changes. problem is presently being i l

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O l-UNIT SIMJIllOWNS ant 3 POWER REIMJCTIONS IMICKET NO. 50-We UNIT NAME BVI'S Unitt #1 f)A1E 4-10-84 REFOR T MONIII _ Ma rch CDMFt.ETEll NY _ .7 _ t_ nog _

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i 5 3/10/84 - S 258.6, B 3 84-15 CB PIPEXX The station was taken off-line at 0000 3/20/84 hours on the loth to repair various leaks on the IC reactor coolant loop and perform other plant maintenance.

An attempt was made to repair the leaks while keeping the reactor critical. It soon became apparent, however, that the reactor coolant 1

system would have to be cooled down in

-

• order to effect the necessary repairs.

lihile shutting down the reactor manually, a reactor trip occurred whil<

fuses were being inserted in the source range instrumenta. tion in the control room. The fuses had been removed to prevent an overvoltage condition on the instrumentation at higher flux levels., The operators attempted to hold off inserting the fuses until I .' 3 4 F: F =.cd Res==:

5 5.hedn'cJ es thed: -EshiNo G -Inseins elems A.F , _', . _ ; Failme ll.=ylsini g.ai t ~..e reepsesei.. ..e pasa R. N ee.i Test 2-ttanesel scran C Refuelingt I:nte> Shuts t.n 1.i.cmre 3-Auta.wetIc scram Tsent Wrr.=5 fl I R8 I ele iNIIMI G 17 Regulasen) Resteksina 4.continnee.1 Free Previo.e9 Ploseth Illt ll I t)presee., isaienng A IAenw F.zassenessieme 3 gig.ctgo.

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l o UNITSHU1 DOWNS AND FUWER REIM)CTIONS IM KE l ug NA E InI t n 1 t. I1 ipa TE 4-10-84 REFORT MONIH w, rr h MrLEltu RY _J. L. HO m IFLErtIONE f4D) 643-13fi9 50 3 - EU l isrmee E*

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5 3/10'/84 - S 258.6 B 3 84-15 CB PIPEXX 3/20/84 - just before the P6 permissive signal

• was de-energized. They were unable to insert the fuses quickly enough, however, and once P6 was disabled, the reactor tripped due to the tripped source range bistables.

The station remained off-line until 1834 hours0.0212 days <br />0.509 hours <br />0.00303 weeks <br />6.97837e-4 months <br /> on the 20th.

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'A>N Telephone (412) 393-8000 Nucteer Division P.O. Boa 4 Shippingpoff. PA 1$071 0004 April 9, 1984 Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Monthly Operating Report United States Nuclear Hogulatory Commission Director, Office of Management Information & Program Control Washington, D.C. 20555 Gontlemons In accordance with Appendix A, Technical Specifications, the Monthly Operating Report is submitted for the month of March, 1984.

Very truly yours, D' '

J. J. Carey Vice President Nuclear Division Enclosures cca NRC Regional Office, King of Prussia, PA

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