Text

Monthly Operating Rept for May 1983
	ML20077A392
Person / Time
Site:	Beaver Valley
Issue date:	06/10/1983
From:	Carey J, Holtz J; DUQUESNE LIGHT CO.
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8307220308
	Download: ML20077A392 (8)
	v • d • e

r NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE - MAY, 1983 May 1 The' station was'in operational mode 1 with reactor power at a through nominal 100 percent and the reactor coolant system at normal May 23 operating / temperature and pressure. The following load changes took place at the request of the system operator: A load re-duction of 150 MWe was begun at 0140 hours0.00162 days 0.0389 hours 2.314815e-4 weeks 5.327e-5 months on the 8th and completed at 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months . Reactor power was 88 percent. Power was increased to 100 percent at 0630 hours0.00729 days 0.175 hours 0.00104 weeks 2.39715e-4 months on the 9th. At 0037 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months on the 15th, a load. reduction of 100 MWe was begun and was completed at 0103 hours0.00119 days 0.0286 hours 1.703042e-4 weeks 3.91915e-5 months . Reactor power.was 85 percent. Power was increased to 100 percent at 0840 hours0.00972 days 0.233 hours 0.00139 weeks 3.1962e-4 months on the same day.

May 24 The station was in operational mode 1 at a nominal 100 percent-reactor power. and the reactor coolant system at normal operating temperature and pressure. At 0945 hours0.0109 days 0.263 hours 0.00156 weeks 3.595725e-4 months , while testing relay 87109X1, relay 51-VD106X actuated, tripping and isolating the IDF 4160 Volt AC Bus.

The No. 2 Diesel Generator auto-started, re-energized the IDF Bus, and sequentially picked up all the.

appropriate loads. After the operators verified that the plant was stabilized, they began reducing the loads on the No. 2 Diesel Generator by running redundant equipment on the AE Emer-gency Bus.

The NRC was notified at 0955 hours0.0111 days 0.265 hours 0.00158 weeks 3.633775e-4 months . The IDF Bus was switched from the Diesel Generator to its normal power supply at 1437 hours0.0166 days 0.399 hours 0.00238 weeks 5.467785e-4 months . At 1325 hours0.0153 days 0.368 hours 0.00219 weeks 5.041625e-4 months , the Inverter trouble alarm annunciated on the No. 1 Inverter. Channel No. 1 of the contain-ment high-high pressure also alarmed intermittently, and relays in the reduction monitoring racks started " buzzing", indicating low voltage on the No. 120 VAC Vital Bus.

A check of the No.'l Inverter showed an output of 110 volts. At 1332 hours0.0154 days 0.37 hours 0.0022 weeks 5.06826e-4 months , the No. 1 120 VAC Vital Bus supply was transferred from the inverter to auxiliary supply, restoring bus voltage to normal. At 1450 hours0.0168 days 0.403 hours 0.0024 weeks 5.51725e-4 months , following repair, the No. 1 Inverter was placed back in service.

May 25

. The station was in operational mode 1 with reactor power at a through nominal 100 percent and the reactor coolant system at normal

-May 27 operating temperature and pressure.

May 28 The station was in operational mode 1 with reactor power at a nominal 100 percent and the reactor coolant system at normal operating temperature and pressure. At 1118 hours0.0129 days 0.311 hours 0.00185 weeks 4.25399e-4 months on the 28th, 4160V Bus lA Supply Breaker ACB-41A and 4160V Bus IB Supply Breaker 141A tripped open due to the inadvertent operation of Pilot Wire Pair No. 4 Protection Relays. As a result, 4160V Busses A & B de-energized causing reactor coolant pumps

[RC-P-1A,1B, and 1C] to trip on 2/3 coolant pump bus 'under-

. voltage,'thereby causing a reactor trip and turbine trip. The operators followed emergency procedure E-5 and stabilized the

'8307220308 830610 PDR ADOCK-05000334 R

PDR

t NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE - MAY, 1983 May 28 plant in operational mode 3.

The No.1 Emergency Diesel Generator through auto-started re-energized 4160V Emergency Bus lAE, and sequentially May 31 picked up the essential loads. At 1121 hours0.013 days 0.311 hours 0.00185 weeks 4.265405e-4 months , RC-P-lC was re-(continued) started to restore RCS flow. At 1122 hours0.013 days 0.312 hours 0.00186 weeks 4.26921e-4 months , normal power was restored to 4160V Busses A & B by closing air circuit breakers 41A and 141A. At 1130 hours0.0131 days 0.314 hours 0.00187 weeks 4.29965e-4 months , normal power supply was restored to 4160V Bus LAE and Emergency Diesel Generator No. I was shutdown.

An unusual event was declared on the loss of the off-site AC power source to Emergency Bus lAE and terminated upon return to the nor-mal power supply.

At 1145 hours0.0133 days 0.318 hours 0.00189 weeks 4.356725e-4 months , Source Range Detector [N-31] was energized and had normal voltage, but had no count rate indication.

Source Range Detector [N-32] was operating properly. At 1620 hours0.0188 days 0.45 hours 0.00268 weeks 6.1641e-4 months , the count rate indication on detector [N-32] began spiking high and was declared inoperable.

Initially, this was attributed to high back-ground noise. A successful surveillance test was completed on

[N-32] and it was returned to service at 1659 hours0.0192 days 0.461 hours 0.00274 weeks 6.312495e-4 months . At 1949 hours0.0226 days 0.541 hours 0.00322 weeks 7.415945e-4 months ,

[N-32] again began spiking high and was again declared inoperable along with [N-31].

The appropriate action statements of the Technical Specifications were complied with during the period of no source range indication.

Instrument and Control technicians began preparations for inspection and repair of both source range detectors.

Both detectors were replaced on the 30th; [N-31] was declared operable at 1540 hours0.0178 days 0.428 hours 0.00255 weeks 5.8597e-4 months on the 30th and (N-32] was declared operable at 0010 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months on the 31st. At 0102 hours0.00118 days 0.0283 hours 1.686508e-4 weeks 3.8811e-5 months , reactor startup was commenced, and the reactor was taken critical at 0310 hours0.00359 days 0.0861 hours 5.125661e-4 weeks 1.17955e-4 months .

The Main Unit Generator was synchronized to the grid at 0505 hours0.00584 days 0.14 hours 8.349868e-4 weeks 1.921525e-4 months .

With reactor power at 36 percent, a problem was noted with the "C" Main Feedwater Regulating Valve. Local inspection found that the valve stem was broken. Reactor power was then reduced to 31 percent in order to place the "C" Feedwater Bypass Valve in service. After the valve stem on the Main Feedwater Bypass Valve was replaced and tested, reactor power escalation was commenced at 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months .

MAJOR SAFETY-RELAT D MAINTENANCE - MAY, - 1983

- 1.

Continued overhaul-of River Water Pump WR-P-1A.

2.

Containment entry was made to rod out incore detector thimbles in order that a flux map u uld be taken.

3.

.Both-Source ~ Range Detectors [N-31 and N-32] were replaced.

4.

-The stiem of "C" Main Feed Regulating Valve [FCV-lFW-498] was replaced.

L

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKETNO.

50-334 UNIT NAME BVPS Unit il DATE _ June 10, 1983 REPORT MONill 11ay COMPLETED BY J. L. Iloltz TELEPilONE 412-643-1369

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Psevent Recurrence S

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83-16 EB RELAYX At 1118 hours0.0129 days 0.311 hours 0.00185 weeks 4.25399e-4 months , 4160 VAC Bus 1B supply breaker [141A] tripped open due to the inadvertent operation of Pilot Wire Pair #4 protection relays. As a

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result, 4160 VAC busses A & B de-energized, causing reactor coolant pumps [RCP-1A, 1B, and IC] to trip on 2/3 coolant pump bus undervoltage 1

thereby causing a reactor / turbine trip. After restoration of normal power supply to busses lA, 1B, and 1AE, problems were found with both Sotirce Range Detectors [N-31 and N-32) l Both were replaced and tested satis-factorily. At 0102 hours0.00118 days 0.0283 hours 1.686508e-4 weeks 3.8811e-5 months on the 31st, reactor startup was commenced and the i

reactor was taken critical at 0310 hours0.00359 days 0.0861 hours 5.125661e-4 weeks 1.17955e-4 months .

The main unit generator was I

2 3

F: Forced Reason:

4 Hethod:

Exhibit G. insieuctiims S: Scheihded A Fquipment Failure (Explain) 1-Hanual for Pseparati.m of Data B Maintenance of Test i

2-Manual Scram C Refueling Entr> Sheets for I.icensee 3-Automatic Scram Event Repost il I RII:ile tNURI'G D-Regulatory Restriction 4

4-Continued From Frevious Month 0161)

E.Operato Training A l.icense Examinati'm 5-Iteduction F-Administrative 9-Other 5

j G.O sratismal 1 ssus (Explaint i

19/77)

II Other (E.splain)

Exhibit I Same, Source

o UNITSHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-334 UNIT NAME BVPS Unit #1 DATE _ June 10. 1983 REPORT MONTH May COMPLETED BY J. L. IIoltz TELEPil0NE 412-643-1369

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830528 1

65.8 11 3

83-16 EB RELAYX synchronized to the grid at 0505 hours0.00584 days 0.14 hours 8.349868e-4 weeks 1.921525e-4 months .

Causes of the pilot wire protection relay actuation are under investigation.

I 2

3 F: Forced Reason:

-8 Hethod:

Exhible G - Instructions S: Scheduled A-Equipmens Failure (Explain) 1-Manual for Preparailon of Data B Maintenance of Test 2-Manual scram Entr> Sheces for I.icensee C Refueling 3-Automatic Scram D-Regulator) Restriction Event Repius it.I'Riiile tNilRI.G 4-Continued From Frevious Month 0161I lEOperaine Training & l.icense Examination 5-Reduction F Administrailve 9-Other G-Oper.iiional Enor IExplain t 19/77)

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Exhihin 1 Same, Source a

OPERATISG DATA REPORT DOCKET NO. 50-334 DATE 6-8-83 COMPLETED BY J. L. Holtz TELEPHONE. 412 441-1369 OPERATING STATUS Beaver Valley Power Station, Unit #1 Notes I. Unit Name:

May, 1983

2. Reporting Period:

3. Licensed Thermal Power (MWt):

WO 923

4. Nameplate Rating (Gioss MWe):

t 4

852

5. Design Electrical Rating (Net MWe):

860

6. Maximum Dependable Capacity (Gross MWe):

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. If Any (Net MWe):

None N/A

10. Reasons For Restrictions.If Any:.

This Month Yr to-Date

' Cumulative 744 3,623 62,087

11. Hours la Reporting Period

12. Number Of Hours Reactor Was Critical 680.1~

3,477.7 28,295.2 0

0 4,482.8

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line 678.2 3,468.3 27,269

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 1,732,946.7 8,891,434.6 61,401,616 562,300 2,899,500 19,412,140

17. Gross Electrical Energy Generated (MWH) l

18. Net Electrical Energy Generated (MWH) 535,693 2.767.982 17.980,099

19. Unit Service Factor 91.2 95.7 46.1

20. Unit Availability Factor 91.2 95.7 46.1 L

21. Unit Capacity Factor (Using MDC Net) 88.9 94.3 39.4 84.5 89.7 37.4

22. Unit Capacity Factor (Using DER Net) l

23. Unit Forced Outage Rate 8.8 4.3 33.1

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

l Shutdown for refueling is scheduled to begin June 11, 1982. Projected duration is 68 Days.

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

26. Units in Test Status IPrior to Commercial Operation):

Forecast Achieved i

l INITIAL CRITICALITY N/A N/A l

INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A (9/77)

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AVERAGE DA/L UNIT POWER LEVEL 50-334 DOCKET NO.

3V?S Unic #1 UNIT June 8, 1983_

DATE J. L. Holtz COMPLETED BY 412-643-1369 TELEPHONE

Ifay, 1983 gg DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Ned (MWe-Neo 826 813 g7 g

817 805 gg 2

1 809 809 g,

3 809 822 20 4

826 830 21 3

805 818 g

4 809 786 23 7

822 734 3

y 814 788 25 9

i 830 826 3

10 801 817 II 7

365 814 32 3

0 813 f

13 39 801 0

14 30 160 780 g3 3

s 834 I6 INSTRUCTIONS l

On this format.!ist the average daily unit power leset in MWe. Net for esch day in the reporting month. Compute su the nearest whole mepwatt.

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Nuclear Division P.O. Dox 4 Shippir,gport, PA 15077-0004 June 10, 1983 Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Monthly Operating Report

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United States Nuclear Regulatory Commission Director, Office of Management Information & Program Control Washington, D.C.

20555 Gentlemen:

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

Very truly yours, l

d6 J, J. Carey i

Vice President Nuclear Division Enclosures NRC Regional Office, King of Prussia, PA cc:

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ML20077A392

Text

SUMMARY

SUMMARY

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