Text

Monthly Operating Rept for Jul 1982
	ML20065C584
Person / Time
Site:	Beaver Valley
Issue date:	08/04/1982
From:	Weaver L; DUQUESNE LIGHT CO.
To:	;
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ML20065C582	List: ML20065C580; ML20065C584;
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	NUDOCS 8209240213
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DUQUESNE LIGIT CMPANY Beaver Valley Power Staiton NARRATIVE

SUMMARY

OF LONTHLY OPERATING EXPERIENCE - JULY 1982 July 1 Station is in Cold Shutdown tede 5 awaiting the repair of the IB Reactor Coolant Punp. The Reactor Coolant System Tavg and pressure are at 110'F and 300 psig.

July 2 Started seal injection to Reactor Coolant Punp [RC-P-1B] at 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months and at 1355 hours0.0157 days 0.376 hours 0.00224 weeks 5.155775e-4 months the B Reactor Coolant Loop Stop Valve Pressurization was taken out of service and began filling Reactor Coolant Loop B.

July 3 At 2134 hours0.0247 days 0.593 hours 0.00353 weeks 8.11987e-4 months , Reactor Coolant Punp [RC-P-1B] was started and the B Reactor Coolant Loop hot Leg and cold Leg stop valves were opened.

At 2335 hours0.027 days 0.649 hours 0.00386 weeks 8.884675e-4 months , the Reactor Coolant Punps were shutdown to begin the vent procedure of the Reactor Coolant Jystem.

July 4 The vent procedure of the Reactor Coolant System was conpleted at 0153 hours0.00177 days 0.0425 hours 2.529762e-4 weeks 5.82165e-5 months . At 1135 hours0.0131 days 0.315 hours 0.00188 weeks 4.318675e-4 months began pulling containment vacuum and at 1612 hours0.0187 days 0.448 hours 0.00267 weeks 6.13366e-4 months the containment vacuum air ejector secured. At 1502 hours0.0174 days 0.417 hours 0.00248 weeks 5.71511e-4 months , Reactor Coolant Punp [RC-P-1A] was started, at 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months , Ibactor Coolant Punp [RC-P-lC] was started, and at 1818 hours0.021 days 0.505 hours 0.00301 weeks 6.91749e-4 months Reactor Coolant Punp [RC-P-1B] was started and heat-up into Hot Shutdown Mode 4 comenced. At 1926 hours0.0223 days 0.535 hours 0.00318 weeks 7.32843e-4 months the station entered Hot Shutdown Mode 4.

July 5 Reactor Coolant System Tavg and pressure at 305'F and 400 psig.

At 0005 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months the Residual Heat Renoval System was taken out of service and by 0129 hours0.00149 days 0.0358 hours 2.132936e-4 weeks 4.90845e-5 months the station entered Hot Stand-by Mode 3 with the Reactor Coolant System Tavg and pressure at 465 F and 1450 psig. At 0850 hours0.00984 days 0.236 hours 0.00141 weeks 3.23425e-4 months , Main Feed Water Punp [EW-P-lAl was started. At 1930 hours0.0223 days 0.536 hours 0.00319 weeks 7.34365e-4 months the Reactor Coolant System Tavg and pressuri reached 547'F and 2235 psig.

July 6 Surveillance Testing in progress. At 1558 hours0.018 days 0.433 hours 0.00258 weeks 5.92819e-4 months began pulling Shutdown Banks A and B for approach to criticality.

At 1730 hours0.02 days 0.481 hours 0.00286 weeks 6.58265e-4 months Control Bank A was pulled.

July 7 All control banks are at 228 steps except Control Bank D which is through at 160 steps with a boron dilution rate c? 50 GPM. At 0245 hours0.00284 days 0.0681 hours 4.050926e-4 weeks 9.32225e-5 months July 9 on the 7th with control Bank D at 215 steps initial criticality was achieved. The Core Design Check Test started at 1230 hours0.0142 days 0.342 hours 0.00203 weeks 4.68015e-4 months on the 7th and was in progress through July 9 when it was cocpleted at 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months . The Reactor Power was then increased to a ncninal 2% to place Steam Generator Blowdown in service.

B209240213 820805 PDR ADOCK 05000334 R

PDR

DUQUESNE LIGff COMPANY Beaver Valley Power Station NARRATIVE

SUMMARY

OF t0NTHLY OPERATING EXPERIENCE - JULY 1982 (Cont.)

July 10 Began rolling the turbine at 0010 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months and at 0316 hours0.00366 days 0.0878 hours 5.224868e-4 weeks 1.20238e-4 months the main unit generator was syncronized to the grid. At 0630 hours0.00729 days 0.175 hours 0.00104 weeks 2.39715e-4 months the N-41 Power Range Detector was declared inoperable due to intermitant spiking which was giving positive and negative rate trips. At 1230 hours0.0142 days 0.342 hours 0.00203 weeks 4.68015e-4 months began a 2%/ min load reduction for the performance of the Turbine overspeed Trip Test. At 1330 hours0.0154 days 0.369 hours 0.0022 weeks 5.06065e-4 months , the Main Generator Output Breaker was opened while the Reactor was at a nominal 7% power.

At 1420 hours0.0164 days 0.394 hours 0.00235 weeks 5.4031e-4 months the turbine overspeed trip setpoint was verified at 1994 RPM and at 1518 hours0.0176 days 0.422 hours 0.00251 weeks 5.77599e-4 months the Main Generator Output Breaker was closed.

July 11 Ranping reactor power at 3%/ hour to hold point of 40% for the through performance of a Full Core Flux Map. At 0103 hours0.00119 days 0.0286 hours 1.703042e-4 weeks 3.91915e-5 months on the lith July 12 a nominal 40% reactor power was achieved. At 1730 hours0.02 days 0.481 hours 0.00286 weeks 6.58265e-4 months on the 12th, the 40% reactor power Full Core Flux Map was conpleted. At 2250 hours0.026 days 0.625 hours 0.00372 weeks 8.56125e-4 months on the 12th core analysis data was evaluated satisfactorily and an increase in reactor power to a nominal 75% was conmensed at a rate of 3%/ hour.

July 13 At 0330 hours0.00382 days 0.0917 hours 5.456349e-4 weeks 1.25565e-4 months stopped reactor power increase and stabilized below 50% reactor power for Conputer Alarm Operability requirements (Tech. Spec. 3.2.1). At 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months began 3%/ hour load increase to a nominal 75% reactor power. At 1210 hours0.014 days 0.336 hours 0.002 weeks 4.60405e-4 months Main Feedwater Punp

[Mi-P-1A] started for plant load increase. At 1833 hours0.0212 days 0.509 hours 0.00303 weeks 6.974565e-4 months began reducing the station load to a nominal 60% reactor power level to remove 31-P-1A from service, at 1933 hours0.0224 days 0.537 hours 0.0032 weeks 7.355065e-4 months M+-P-1A was shutdown.

July 14 At 0540 hours0.00625 days 0.15 hours 8.928571e-4 weeks 2.0547e-4 months started Main Feedwater Punp [RV-P-1A] for maintenance observation, at 0600 hour0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months began to ranp reactor power at 3%/ hour to 1 75% reactor power.

July 15 At 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months , released by system operator to cmrence reactor power reduction at 1%/ min. for the repair of Excore Power Range Detector N-41.

At 2132 hours0.0247 days 0.592 hours 0.00353 weeks 8.11226e-4 months the Main Generator Output Breaker was opened at 2135 hours0.0247 days 0.593 hours 0.00353 weeks 8.123675e-4 months tripped the Turbine and at 2226 hours0.0258 days 0.618 hours 0.00368 weeks 8.46993e-4 months all Control Rods inserted and the Reactor shutdown.

July 16 Peactor shutdown for the repair of the N-41 Power Range Detector Poactor Coolant System Tavg. and Pressure at 547*F and 2235 psig.

July 17 At 2205 hours0.0255 days 0.613 hours 0.00365 weeks 8.390025e-4 months Poactor Start-up was cormenced and at 2250 hours0.026 days 0.625 hours 0.00372 weeks 8.56125e-4 months the Reactor was critical.

o DUQUESNE LIGff COMPANY Beaver Valley Power Station NARRATIVE

SUMMARY

OF 10NTHLY OPERATING EXPERIENCE - JULY 1982 (Cont. )

July 18 Conmenced turbine roll at 0005 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and at 0120 hours0.00139 days 0.0333 hours 1.984127e-4 weeks 4.566e-5 months the main generator was syncronized to the grid. At 0140 hours0.00162 days 0.0389 hours 2.314815e-4 weeks 5.327e-5 months the reactor tripped on a Hi/Hi Steam Generator level signal due to control prob 3 ems with the Feedwater By-pass Control Valves. At 0210 hours0.00243 days 0.0583 hours 3.472222e-4 weeks 7.9905e-5 months reactor start-up armenced at 0225 hours0.0026 days 0.0625 hours 3.720238e-4 weeks 8.56125e-5 months the reactor wnt critical and at 0312 hours0.00361 days 0.0867 hours 5.15873e-4 weeks 1.18716e-4 months the main generator was syncronized to the grid.

At Otl5 hours a nominal 40% reactor power hold was established to calibrate the N-41 Power Range Detector.

July 19 At 0305 hours0.00353 days 0.0847 hours 5.042989e-4 weeks 1.160525e-4 months on the 19th, the station reached a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months hold point through at 781, reactor power for xenon equilibriation and to perform a Full July 22 Core flux Map. At 2030 hours0.0235 days 0.564 hours 0.00336 weeks 7.72415e-4 months on the 21st the flux map was ocuple.:ed and began ranping to a nominal 85% reactor power at 3%/ hour.

At 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months on the 22nd a nminal reactor power level of 85% was reache?, will begin ranping reactor power at 1%/ hour. At 0410 hours0.00475 days 0.114 hours 6.779101e-4 weeks 1.56005e-4 months cn the 22nd a hold point at nominal 90% reactor power was established until the calibrations of Power Range Detectors N-42, N-43, N-44 were conplete. At 1205 hours0.0139 days 0.335 hours 0.00199 weeks 4.585025e-4 months on the 22nd the 01emistry Dapartment reported reactor coolant system inleakage into the secondary side of the Steam Generator [RC-E-1C] at a rate of.001 GPM. At 1750 ho:rs reactor power was increased to a nominal 95% at I 1%/ min.

July 23 Stition in operational Mode 1 with the reactor at a nominal 96%

through ponr and the Reactor Coolant System at normal operational July 31 tenyxature and pressure. The Steam Generator [RC-E-lC] primary side :o secondary side tube leak is slowly increasing. At 1130 hou.9 on the 28th, the reactor reached nominal full power.

l

DUQUESNE LIGff COMPA!TI Beaver Valley Power Station MAJOR SAFErY RELATED MAINTENANCE - JULY 1982 1.

Beplaced the N-41 Power Range Detector because of damage that occurred due to refueling seal ledage.

2.

The A Incore Detector was replacril due to shorted leads.

3.

Started the replacement of the Mr or Thrust Bearing on Cooling Tower Punp [Cr-P-lC).

4.

Beplaced the Inboard and Outboard Motor Bearings cn Conponent Cooling Punp [CC-P-lC].

5.

Installed tenporary Gem. Nuclear emineralizers to clean-up condensate and Steam Generator Blowdown.

1

~'

OPERATING DATA REPORT DOCKET NO. 50-334

/4/82 3

DATE COMPLETED BY

-L. W. Weaver TELEPHONE. 47 '-A41 i;303 OPERATING STATUS I. Unit Name: Beaver Valley Power Station. Unit #1 Notes

2. Reporting Period:

Julv, 1982

3. Licensed Thermal Power (MWt):

24A0

4. Nameplate Rating (Gross MWe):

923

5. Design Electrical Rating (Net MWeJ:

852

6. Maximum Dependable Capacity (Grots MWe):

860

7. Maximum Dependable Capacity (Net MWe):

810

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

9. Power Level To which Restricted. !f Any (Net MWe):

None

10. Reasons For Restrictions. If Any:

N/A This Month Yr to.Date

' Cumulative

!!. Hours In Reporting Period 744 5, f.$ 3 54.7o1

12. Number Of Hours Reactor Was Critical 547.2 5f7.2 21.606.5

13. Reactor Reserve Shutdown Hours 0

__0 4,482.8

14. Hours Generator On-Line 469.6 409.6

15. Unit Reserve Shutdown Hours 0

20.623.7 0

0

16. Gross Thermal Energy Generated (MWH) 975.422.7 975,422.7 44 604.363.18,

17. Gross Electrical Energy Generated (MWH) 307.600 307.600 13.958.040

18. Net Electrical Energy Generated IMWH) 286.849 286,349 12.781.425

19. Unit Sersice Factor "3*I 92 39 0

20. Unit Asailability Factor D3'I 92 39 0

21. Unit Capacity Factor (Using MDC Nett 47.6 6.1 31.7

22. Unit Capacity Fac:nriUsing DER Net) 45.3 6.0 30.1

23. Unit Forced Outage Rate 1a.5 10.5 39.6

24. Shutdowns Scheduled Over Next 6 Months iType. Date.and Duration of Each L

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

26. Units In Test Status IPrior to Commercial Operations:

Forecast Achieved INITIA L CRITICA LITY

'I /A_

N/A INITIAL ELECTRICITY N/A N/A COM\\lERCI AL OPER A TION N/A N/A (o/77)

O AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.30-334 UNIT 3V"5 Uni: dl 8/4/82 DATE CDMPLETED BY L. '4. '4eaver TELEPHONE (412) 643-5303 MONTH J"lY DAY AVERAGE I

ER LEVEL DAY AVERAGE DALLY POWER LEVEL (MWe-Neti I

O 3

0 U

18 412 3

0 19 572 4

n 588

,o 5

23 604 6

0 716 0

23 782 j

0 8

24 791 9

0 774 23 10 174 26 766 33 765 27 33^

~

28 782 13 457 29 802 I4 795 30 15 555 31 790 16 0

INSTRUCTIONS n

e" r ese. ay in the repurune month. Compute io neste wnoie t

(9/77)

s e

IJNIT SIIUTDOWNS AND POWER REDtICTIONS DOCKET NO.

50-134 UNIT NAME BVPS Unit #1 DATE 6 4 -62 REPORT AIONfil July COMPl.EIED fly

_t. W,_.Veitver IEl.EPilONE (412) 643-5103 l

=.)

E

=

35 5

553 Ii'c"$ce 5't E).,

Cause A Conscisne s',~

p', #

f J

"5 3

53e Event 3,7 g?

A,,,,,n, o 3mj RcPort :

-a L j'

P,esen Recursense

.00 x

c5 01 820710 S

1.8 B

9 N/A zz zzzzzz Turbine overspeed trip test Main Unir Generator taken off line, but the reactor was not tripped.

l 02 820715 F

51.8 A

1 82-023/03L IA INSTRU Water was found in the cable and connector of the N-41 Detector (Model No. WL-23-743).

Both the N-41 Detector, its associated cable, and the field cable connector were replaced. The water was a result of l

inleakage through the Refueling j

Cavity Seal during the last refuelint outage.

03 820718 F

1.5 A

3 N/A Cl!

VALV0P Control problems with By-pass Flow I

control valves in the automatic l

mode.

Station tripped on 111/111 B l

Steam Generator level.

l 1

3 I

I, *tical Reason:

4 l

tte t ho<!:

S S( bciln!cil A I.guipenent Fai!ure(laplatn) 1:sinbit G Instructions 1-Manual ll41aintenance o( Test los Pseparanon of Data 2-Hanual Scram l'.ntes Sheets I.n I siemec C RefuelinK 3-Automatic Scram lien't Repini il l R l l ele (NilRI G

1) Reyniatos) Restrictiini 4-Continued From Previous Month Oltil l 1 Opesaio: liainmg A I tiense l'samination 5-Reduction l

1 -Atinunists.siisc 9-Other 5

j G Opesaltunal I seos il kplJini j

08/77) 11 Olhes 11 api. sin) l'sinint I S.nne'Sinnic

-

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