ML20082S913

Monthly Operating Rept for Oct 1983

ML20082S913
Person / Time
Site:	Beaver Valley
Issue date:	11/03/1983
From:	Holtz J DUQUESNE LIGHT CO.
To:
Shared Package
ML20082S900	List: ML20082S898 ML20082S913 ML20082S918
References
NUDOCS 8312150055
Download: ML20082S913 (9)

Text

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NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE - OCTOBER, 1983 October 1 Following the calibration of the excore instrumentation at 73 percent reactor power, the station was given the go ahead to increase to full power. At 0635 hours0.00735 days <br />0.176 hours <br />0.00105 weeks <br />2.416175e-4 months <br />, the increase in power was begun.

While withdrawing the rods in Control Bank 'D', Control Rod H-2

- was found to be reading greater than 12 steps above the group demand counter. The primary voltage read 218 steps, while the group demand counter read 202 steps. Upon investigation, it was found that the power supply voltage was out of adjustment high. The voltage was reduced to the lower limit setting, and the rod then read within specifications. Group demand read 213 steps, and primary voltage read 221 steps. The sta-tion recched a nominal 100 percent power at 1705 hours0.0197 days <br />0.474 hours <br />0.00282 weeks <br />6.487525e-4 months <br />.

, October 2 The station was in Operational Mode 1 at a nominal 100 percent, and the Reactor Coolant System was at normal operating temper-

.( ature and pressure.

October 3 The station was in Operational Mode 1 at a nominal 100 percent Through reactor power. The Reactor Coolant System was at normal oper-October 4 ating temperature and pressure. At 1048 hours0.0121 days <br />0.291 hours <br />0.00173 weeks <br />3.98764e-4 months <br /> on the 3rd, a reactor / turbine trip occurred when a meter control repairman inadvertently pulled the fu.ses to Power Range Channel N-44 while performing a calibration of the N-43 Power Range Channel.

Realizing his mistake, the repairman replaced the fuses to l N-44 and pulled the N-43 fuses without first resetting the high flux rate trip on N-44. This caused a 2/4 high flux rate signal on Detectors N-43 and N-44 and the subsequent trip.

The plant was stabilized and placed in Operational Mode 3, Hot Standby.

4 After the startup requirements were met, the reactor was taken critical at 1756 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.68158e-4 months <br />. The Main Unit Generator was synchro-i nized to the grid at 1852 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.04686e-4 months <br />.

l l At 2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br />, with reactor power at 73 percent, a chemistry sample of the IB Safety Injection Accumulator showed the boron concentration to be too high. The reactor power in-crease was temporarily halted until the accumulator could I be drained and refilled. This was completed at 0040 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> on the 4th. A chemistry sample showed the boron concentration to be within acceptable limits. At 0052 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br />, a power increase at a rate of 3 percent / hour was begun. Full power was reached at appro :imately 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />. ,

October 5 The station was in Operational Mode 1 with reactor power at Through a nominal 100 percent. The Reactor Coolant System was at October 8 normal operating temperature and pressure.

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NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE - OCTOBER, 1983 (Continued)

October 9- At 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, reactor power was reduced b percent to elim-

- inste the cycling the No. 1 Turbine Governor Valve had been experiencing at 100 percent power. This had been causing approximately 5 MW load swings on the Main Unit Generator.  ;

l At 0855 hours0.0099 days <br />0.238 hours <br />0.00141 weeks <br />3.253275e-4 months <br />, Power Range Detector N-41 failed. The appro-priate N-41 bistables were tripped, and a reactor power

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decrease was started at 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br /> to less than 75 percent as required by the abnormal operating procedures. Reactor power was brought below 75 percent at 1017 hours0.0118 days <br />0.283 hours <br />0.00168 weeks <br />3.869685e-4 months <br />. The N-41 detector high voltage power supply was replaced. At f 1254 hours0.0145 days <br />0.348 hours <br />0.00207 weeks <br />4.77147e-4 months <br />, N-41 was returned to service, and a reactor power increase was begun at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />. Full power was achieved at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />.

October 10 The station was in Operational Mode 1 at a nominal 100 per-cent reactor power. The Reactor Coolant System was at

• j normal operating temperature and pressure.

October 11 The station was in Operational Mode 1 at a nominal 100 per-cent reactor power. At 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br />, the Chemistry Department noted that steam generator conductivity and sodium concentra-tions were increasing. The problem was identified as condenser leakage in the 'B' Waterbox. At 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br />, the

'B' Waterbox was isolated, and draining was begun.

r At 1642 hours0.019 days <br />0.456 hours <br />0.00271 weeks <br />6.24781e-4 months <br />, reduction of the station load to less than 75 percent reactor power was commenced in order to begin an outage to repair the N-41 Power Range Detector. At 1742 hours0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.62831e-4 months <br />, l reactor power was stabilized at 73 percent. Load reduction continued at 1957 hours0.0227 days <br />0.544 hours <br />0.00324 weeks <br />7.446385e-4 months <br />, and the Main Unit Generator Output Breakers were opened at 2125 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.085625e-4 months <br />. The station entered Operational Mode 3 at 2137 hours0.0247 days <br />0.594 hours <br />0.00353 weeks <br />8.131285e-4 months <br />.

October 12 The N-41 repair was completed at 1037 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.945785e-4 months <br />. A surveillance test was completed satisfactorily, and the unit was declared operable at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />.

October 13 Station startup began at 0057 hours6.597222e-4 days <br />0.0158 hours <br />9.424603e-5 weeks <br />2.16885e-5 months <br />, and the reactor was taken critical at 0136 hours0.00157 days <br />0.0378 hours <br />2.248677e-4 weeks <br />5.1748e-5 months <br />. The Main Unit Generator was synchronized with the grid at 0305 hours0.00353 days <br />0.0847 hours <br />5.042989e-4 weeks <br />1.160525e-4 months <br />. A reactor trip

occurred at 0320 hours0.0037 days <br />0.0889 hours <br />5.291005e-4 weeks <br />1.2176e-4 months <br /> due to IB Steam Generator lo-lo level.

The plant was stabilized, and reactor startup was again begun.

! The reactor was taken critical at 0442 hours0.00512 days <br />0.123 hours <br />7.308201e-4 weeks <br />1.68181e-4 months <br />, and the Main Unit Generator was synchronized with the grid at 0505 hours0.00584 days <br />0.14 hours <br />8.349868e-4 weeks <br />1.921525e-4 months <br />.

Reactor power was being steadily increased when, at 0940 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.5767e-4 months <br /> and S7 percent reactor power, turbine vacuum began dropping.

This was attributed to the leak in the 'B' Conde"nser Waterbox.

Reactor power was decreased to find a stable power level.

Feedwater Pump FW-P-1B was secured at 1052 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />4.00286e-4 months <br />. Reactor power was stabilized at 48 percent at 1148 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.36814e-4 months <br />.

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NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE - OCTOBER, 1983 (Continued)

October 14 Reactor power was increased 7 percent to improve the_ delta I flux. The air was bled from the 1A Cooling Tower Pump. The other pumps were checked for air, and n6ne was found. At 0620 hours0.00718 days <br />0.172 hours <br />0.00103 weeks <br />2.3591e-4 months <br />,-Feedwater Pump FW-P-1B was started, and a power increase was begun. Reactor power was taken to 73 percent and held while the 'B' Waterbox was being filled. At

. 1645 hours0.019 days <br />0.457 hours <br />0.00272 weeks <br />6.259225e-4 months <br />, 'B' Waterbox was returned to serv 4ce, and a load increase was begun. Cooling Tower Pump 1A was started at

. 1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br />. Reactor power was stabilized at 95 percent for performance of a calorimetric. Power was then increased to a

' nominal 100 percent.

October 15 The station was in Operational Mode 1 with reactor power at r a nominal 100 percent. The Reactor Coolant System was at normal operating temperature and pressure.

October 16 At 0035 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br />, the station load was reduced 175 MW at the i request of the system operator. Reactor power was increhsed ,

back to a nominal 100 percent at 0916 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.48538e-4 months <br />.

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+ October 17 At 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />, the station load was reduced 5 MW to stop turbine governor valve oscillation. At 0440 hours0.00509 days <br />0.122 hours <br />7.275132e-4 weeks <br />1.6742e-4 months <br />, the load was again i, reduced 5 MW to stop the governor valve oscillation. Reactor power was increased 1 percent at 1015 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.862075e-4 months <br /> with no governor

. valve flutter.

j October 18 At 0715 hours0.00828 days <br />0.199 hours <br />0.00118 weeks <br />2.720575e-4 months <br />, reactor power was reduced 1 percent due to governor valve oscillation. Reactor power was a nominal 100 per-cent, and the Reactor Coolant System was at normal operating temperature and pre'ssure.

[ October 19 The station was in Operational Mode 1 with reactor power at Through a nominal 100 percent. The Reactor Coolant System was at l October 31 normal operating temperature and pressure.

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- MAJOR SAFETY-RELATED MAINTENANCE - OCTOBER, 1983

1. The high voltage power supply to Power' Range Detedtor N-41 was replaced.

2. The IB Instrument Air Compressor was overhauled.

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OPERATISG DATA REPORT DOCKET NO. 50-33/.

DATE 11-3-83 COMPLETED BY J. L. Holtz

. TELEPHONE. M 7-m-1369 OPERATING STATUS

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

2. ' Reporting Period: October, 1983

3. Licensed Thermal Power (MWt): Wo *

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

6. Maximum Dependable Capacity (Gross MWe): 860

7. Maxirnum Dwmdable Capacity (Net MWe): _ 810

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

10. Reasons For Restrictions.If Any:. N/A This Month Yr to.Date " Cumulative

11. Hours in Reporting Pariod 745 7.296 65.760

12. Number Of Hours Reactor Was Critical 715.7 4,628.3 29,445.8 l 13. Reactor Reserve Shutdown Hours 0 0 4,482.8

14. Hours Generator On.Line 705.5 4,567.2 28,367.4 l

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1,779,388 11,490,012.8 64,000,194.2

17. Gross Electrical Energy Generated (MWH) 579,000 3,742,300 20,254,940

18. Net Electrical Energy Generated (MWH) 552,402 3,555,591 18,767,708

19. Unit Service Factor 94.7 62.6 45.1

20. Unit Availability F etor 94.7 62.6 45.1

21. Unit Capacity Factor (Using MDC Net) 91.5 60.2 38.5

22. Unit Capacity Factor (Using DER Net) 88.8 58.4 37.4

23. Unit Forced Outare Rate- 1.4 3.5 32.1

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. Uni:s in Test Statu> (Pr;or to Cummercial OperationJ. Forecast -

Achieved INITIA L CRITICALITY '? / A. ': !A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A l

P/77)

. .. ___ _- , ._ .m. _ . _ . .

UNIT SifUTDOWNS AND POWER REDUCil0NS IM)CKET NO. 50-334 i

UNI.T NAME BVPS Unit #1 IMTE 11-3-83 REPORT MONiil October COMPLETEI) ny 1 L un'ltu

TELEPflONE (412) 641-1369 1

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? ., E y I.icensee gv, L. D. sic E. 55 5 1 Twent E-,

E$ &j (.anse A t ..:,etsigf c y .5 O: a:

3 f 3 a: Rep nl n .fic Ec As8. m to i '.t17, y c Peevent Recurrente j g i 7 10/11/83 F 29.67 A 1 N/A IA INSTRU The station was taken off-line at -

2125 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.085625e-4 months <br /> on the lith in order to repair the Power Range Detector N-4L The detector had failed, and the 1 station had been operating at re-duced power as required by the abnormal operating procedures.

The N-41 Detector was repaired, and

! station startup began at 0057 hours6.597222e-4 days <br />0.0158 hours <br />9.424603e-5 weeks <br />2.16885e-5 months <br /> on the 13th. The reactor was taken l- critical at 0136 hours0.00157 days <br />0.0378 hours <br />2.248677e-4 weeks <br />5.1748e-5 months <br />, and the Main

. Uni.t Generator was synchronized to the grid at 0305 hours0.00353 days <br />0.0847 hours <br />5.042989e-4 weeks <br />1.160525e-4 months <br />.

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il l'.uted Ressem

tiethod:

i S 5thedti'ed A.E.luipment f~allureII.mplaint Exhibit G. instinttiims 1-MannaL

' lin PseparJtiem of DJfa l H. Maintenance or Test

2-M.inual Scram lint ) Slicets lor I.icensec i

C.RefuelinR 3-Autosstic Scram Event RepinI II I It i I i'c I N*llRI G D.Rer"lator) Resteletiam 4-Continued From PrevioIri Month Of fil l

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vesto, Tosining A f irensc INaminathm 5-Pedttetfan t

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4 UNIT SifUTDOWNS AND POWER REDUC 1 IONS DOCKEtNO. 50-334 UNIT NAME BVPS Unit #1 UA1E 11-3-83 COMPLF.1F.D RY J. L. Holtz REPORT AtONill October TEl.ErllONE (412) 643-1369 1

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3e 5 _E j -3 5 d $'"5 $*., 5"<., Canse A Cuerettise

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?.? 63 Asti.m so j 0 " y i?i j M cP'"' "V j' Prevent Recurrente 6

8 10/13/83 F 1.75 A 3 N/A CH VALVEX While increasing reactor power with 1B Steam Generator Level Control in manual, a reactor trip occurred due

to lo-lo steam generator Icvel.

This was caused by the slow responne of the Feedwater Bypass Valve while the operator was attempting to

switch control from the Feedwater i Bypass Valve to the Main Feedwater Regulating Valve. A Design Change

package has been generated to re-duce the response time of the l S/C Bypass Valves.

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F.nted Reason: teethod:

S Stheiluted I:xhibit G. instnetihms A.Fignipment Failure (Expls:n) 1-Manual l'an Picparati.m sol Data ll-Maintenance e : Test 2-Manual Scram C Refueling I sit') Sheets l'" l Ire"5cc 3-Automatte Scram . I sent Repost iI I RII ile tNIIRI G D Heridatin) Restrictinel 4-Continued From Prevfnum Month Ultil l i Opciatin 1:aining A license I:xar.dnalism 5-Rediaction 1 Administe:itive 9-Other 5 G Oper.itiim.il I esos ll~ nplain t .

l'Thibit 1 5.ime S.me<;c P'/771 11 Other (INplain t l

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AVERAGE DAILi UNIT POWER LEVEL DOCXIT NO. 50-334 UNIT 3"? S ~~~- 1: #'

DATE 11-3-83 l

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. CDMPLETED BY J. L. Holtz TELEPHONE (412) 643-13e October, 1983 MONTH f DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe Nett g 693 37 814 817 gg 817 3

3 461 39 814 4 739 3 822 g 810 33 817 818 g 818 6

780 33 814 l 7 818 24 814 3

9 818 25 826 818 3 822 10 11 669 27 830 0 818 32 3 308 826 13 29 ,

626 30 850 14 15 809 33 822 16 731 INSTRUCTIONS ,

l On this format.hst the average datiy unit power iesci in MWe. Net icr each t.sy in the recurtine m. ntn. Gimou:e to the nearest whole mepws:t.

(4/77) i i

50-334 UNITSlIUTDOWNS AND POWER REDUC 110NS DOCKET NO. '

.. UNIT NAME BVPS Unit #1 11-3-83 DATE COMPLETED RY J. L. Holtz

. REPORT MONTil October (412) 643-1369 TELEPilONE i '\

I e ce .T y-- .2 E E 3 .me dsg Licefuce h 6t, s Cause A Conectilse Nd- D3'e 4 5? 4 -c I ac Event 3 ~! 6- Asti.m in

$E E j15g RcPani 2' MV y'3 Prevent Recmrense e d i

j 6 10/03/83 F 8.07 H 3 N/A IA INSTRU While perfor: Ling a quarterly calibra-tion of Power Range Channel N-43, a meter control repairman inadvertently j pulled the fuses to N-44. Realizing his mistake, he then replaced the fuses to N-44 and rutled the fuses to N-43 without first resetting the ,

j 2/4 high flux rate trip on Channel N-44. This created a 2/4 high flux

] rate signal and a reactor trip.

l 4' The, plant was stabilized and reactor

! startup was begun. The reactor van taken critical at 1756 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.68158e-4 months <br /> and the i Main Unit Generator was synchronized j to the grid at 1852 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.04686e-4 months <br />. -

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I: F.nted Reasim: Hethod Exhible G. Instiustiims

S Schedu'ed A Eiquipment Failuie(Explain) 1.Hanutil l'"8 P8cP3'JII+* "I UJ83 Il Maintenance i.i Test 2-Manual scram .

lintr> Shecis lor I.icemcc i

C ReIncling 3-Automatle Scram Event Repine iI I RIl'ile IN*llRI.G D Regulatin) Restelcilote 4-Continued From Previoua Hranth Ul(il l 110pessam Tealning A 1.icense Examinathm 5-Reduetton l' Ailministrailve 9-Other -" .

G Opcialkmal 1:nne II:nplaisil Eshibis 1 SJme Sonnec

! 19/771 II Other (Esplain t w