ML20065C584

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Monthly Operating Rept for Jul 1982
ML20065C584
Person / Time
Site: Beaver Valley
Issue date: 08/04/1982
From: Weaver L
DUQUESNE LIGHT CO.
To:
Shared Package
ML20065C582 List:
References
NUDOCS 8209240213
Download: ML20065C584 (7)
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Text

p m 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 <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> and at 1355 hours0.0157 days <br />0.376 hours <br />0.00224 weeks <br />5.155775e-4 months <br /> 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 <br />0.593 hours <br />0.00353 weeks <br />8.11987e-4 months <br />, 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 <br />0.649 hours <br />0.00386 weeks <br />8.884675e-4 months <br />, 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 <br />0.0425 hours <br />2.529762e-4 weeks <br />5.82165e-5 months <br />. At 1135 hours0.0131 days <br />0.315 hours <br />0.00188 weeks <br />4.318675e-4 months <br /> began pulling containment vacuum and at 1612 hours0.0187 days <br />0.448 hours <br />0.00267 weeks <br />6.13366e-4 months <br /> the containment vacuum air ejector secured. At 1502 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.71511e-4 months <br />, Reactor Coolant Punp [RC-P-1A] was started, at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br />, Ibactor Coolant Punp [RC-P-lC] was started, and at 1818 hours0.021 days <br />0.505 hours <br />0.00301 weeks <br />6.91749e-4 months <br /> Reactor Coolant Punp [RC-P-1B] was started and heat-up into Hot Shutdown Mode 4 comenced. At 1926 hours0.0223 days <br />0.535 hours <br />0.00318 weeks <br />7.32843e-4 months <br /> 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 <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> the Residual Heat Renoval System was taken out of service and by 0129 hours0.00149 days <br />0.0358 hours <br />2.132936e-4 weeks <br />4.90845e-5 months <br /> 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 <br />0.236 hours <br />0.00141 weeks <br />3.23425e-4 months <br />, Main Feed Water Punp [EW-P-lAl was started. At 1930 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.34365e-4 months <br /> the Reactor Coolant System Tavg and pressuri reached 547'F and 2235 psig.

July 6 Surveillance Testing in progress. At 1558 hours0.018 days <br />0.433 hours <br />0.00258 weeks <br />5.92819e-4 months <br /> began pulling Shutdown Banks A and B for approach to criticality. At 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br /> 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 <br />0.0681 hours <br />4.050926e-4 weeks <br />9.32225e-5 months <br /> 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 <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> on the 7th and was in progress through July 9 when it was cocpleted at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />. The Reactor Power was then increased to a ncninal 2% to place Steam Generator Blowdown in service.

B209240213 820805 PDR ADOCK 05000334 PDR R

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 <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> and at 0316 hours0.00366 days <br />0.0878 hours <br />5.224868e-4 weeks <br />1.20238e-4 months <br /> the main unit generator was syncronized to the grid. At 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br /> 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 <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> began a 2%/ min load reduction for the performance of the Turbine overspeed Trip Test. At 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />, the Main Generator Output Breaker was opened while the Reactor was at a nominal 7% power. At 1420 hours0.0164 days <br />0.394 hours <br />0.00235 weeks <br />5.4031e-4 months <br /> the turbine overspeed trip setpoint was verified at 1994 RPM and at 1518 hours0.0176 days <br />0.422 hours <br />0.00251 weeks <br />5.77599e-4 months <br /> 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 <br />0.0286 hours <br />1.703042e-4 weeks <br />3.91915e-5 months <br /> on the lith July 12 a nominal 40% reactor power was achieved. At 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br /> on the 12th, the 40% reactor power Full Core Flux Map was conpleted. At 2250 hours0.026 days <br />0.625 hours <br />0.00372 weeks <br />8.56125e-4 months <br /> 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 <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br /> 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 <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> began 3%/ hour load increase to a nominal 75% reactor power. At 1210 hours0.014 days <br />0.336 hours <br />0.002 weeks <br />4.60405e-4 months <br /> Main Feedwater Punp

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

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

July 15 At 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, 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 <br />0.592 hours <br />0.00353 weeks <br />8.11226e-4 months <br /> the Main Generator Output Breaker was opened at 2135 hours0.0247 days <br />0.593 hours <br />0.00353 weeks <br />8.123675e-4 months <br /> tripped the Turbine and at 2226 hours0.0258 days <br />0.618 hours <br />0.00368 weeks <br />8.46993e-4 months <br /> 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 <br />0.613 hours <br />0.00365 weeks <br />8.390025e-4 months <br /> Poactor Start-up was cormenced and at 2250 hours0.026 days <br />0.625 hours <br />0.00372 weeks <br />8.56125e-4 months <br /> 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 <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and at 0120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> the main generator was syncronized to the grid. At 0140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br /> 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 <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br /> reactor start-up armenced at 0225 hours0.0026 days <br />0.0625 hours <br />3.720238e-4 weeks <br />8.56125e-5 months <br /> the reactor wnt critical and at 0312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br /> 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 <br />0.0847 hours <br />5.042989e-4 weeks <br />1.160525e-4 months <br /> on the 19th, the station reached a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> 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 <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> 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 <br />0.114 hours <br />6.779101e-4 weeks <br />1.56005e-4 months <br /> 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 <br />0.335 hours <br />0.00199 weeks <br />4.585025e-4 months <br /> 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 DATE 3 /4/82 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

, 20.623.7

15. Unit Reserve Shutdown Hours 0 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 DATE 8/4/82 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 0 572

_ 19 4 n ,o 588 5 604

- 23 6 0 716 0

j 23 782 0

8 791 24 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" neste wnoie t r ese. ay in the repurune month. Compute io (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 35 553 Ii'c"$ce s' ,~ p' , # f 5 5't E)., Cause A Conscisne J "5 .

x 3 53e Event 3,7 g? A, , ,,,n , o

.00 3mj RcPort : -a L j' P,esen Recursense 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  ;

I I, *tical 3 4 l Reason:

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

1) Reyniatos) Restrictiini lien't Repini il l R l l ele (NilRI G 1 Opesaio: liainmg A I tiense l'samination 4-Continued From Previous Month Oltil l 5-Reduction l 1 -Atinunists.siisc j 9-Other 5 G Opesaltunal I seos il kplJini j 08/77) 11 Olhes 11 api. sin) l'sinint I S.nne'Sinnic -

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