ML20066D351

Monthly Operating Rept for Sept 1982

ML20066D351
Person / Time
Site:	Beaver Valley
Issue date:	10/07/1982
From:	Weaver L DUQUESNE LIGHT CO.
To:
Shared Package
ML20066D339	List: ML20066D337 ML20066D351 ML20066D386 ML20066D409
References
NUDOCS 8211110295
Download: ML20066D351 (8)

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DUQUESNE LIGff COMPANY Beaver Valley Power Station NARRATIVE SIDNARY OF M)NTHLY OPERATING EXPERIENCE - SEPTE!@ER 1982 Septertber 1 Station in Cold Shutdown Mode 5 with Reactor Coolant System through Tavg at 130'F and a steam bubble in the pressurizer maintaining Septestber 6 pressure at approximately 300 psig. The 1C reactor m olant loop is isolated and drained for steam generator tube leak re-pair. At 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on the 2nd, Westinghouse reported the lo-cation of the steam generator tube leak. At 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> on the 3rd,1C steam generator secondary side draining was carmenced and at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on the 4th it was carplete. By 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> on the 5th main condenser vacuum was established, 1C loop fill started at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> and finished by 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />, and at 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br /> the 1C hot leg Toop Stop Isolation valve was opened.

Septertber 7 Reactor Coolant System tertperature and pressure are at 120'F and through 325 psig. At 0239 hours0.00277 days <br />0.0664 hours <br />3.95172e-4 weeks <br />9.09395e-5 months <br /> on the 8th shut down control rod banks September 8 A and B were withdrawn. At 0710 hours0.00822 days <br />0.197 hours <br />0.00117 weeks <br />2.70155e-4 months <br /> cortpleted drawing contain-ment vacuum, and at 1203 hours0.0139 days <br />0.334 hours <br />0.00199 weeks <br />4.577415e-4 months <br /> the station entered Hot Shutdown Mode 4. At 1459 hours0.0169 days <br />0.405 hours <br />0.00241 weeks <br />5.551495e-4 months <br /> on the 8th, during a purging operation, the Pressurizer Relief Tank rupture disc blew cut. By 2145 hours0.0248 days <br />0.596 hours <br />0.00355 weeks <br />8.161725e-4 months <br /> the disc was repaired. The Residual Heat Renoval System was isolated at 1940 hours0.0225 days <br />0.539 hours <br />0.00321 weeks <br />7.3817e-4 months <br />.

Septettber 9 The station entered Hot Standby lede 3 at 0207 hours0.0024 days <br />0.0575 hours <br />3.422619e-4 weeks <br />7.87635e-5 months <br />.

Septenber 10 Coninenced reactor start-up at 1043 hours0.0121 days <br />0.29 hours <br />0.00172 weeks <br />3.968615e-4 months <br /> and at 1130 hcurs the reactor was critical, but due to problems in the Rod Control System the reactor was made subcritical at 1226 hours0.0142 days <br />0.341 hours <br />0.00203 weeks <br />4.66493e-4 months <br />. By 1249 hours0.0145 days <br />0.347 hours <br />0.00207 weeks <br />4.752445e-4 months <br /> all control rod banks were at zero steps to aid in trouble shooting the H-14 rod position indicator. At 2052 hours0.0238 days <br />0.57 hours <br />0.00339 weeks <br />7.80786e-4 months <br />, after the calibration of the H-14 control rod position indicator was carplete, reactor start-up was cortnenced and at 2108 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.02094e-4 months <br /> the

{ reactor was critical.

September 11 The main unit generator was syncronized to the grid at 0027 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> and at 0117 hours0.00135 days <br />0.0325 hours <br />1.934524e-4 weeks <br />4.45185e-5 months <br /> the reac:or tripped on low-low 1C steam generator level. The reactor war, again taken critical at 0314 hours0.00363 days <br />0.0872 hours <br />5.191799e-4 weeks <br />1.19477e-4 months <br /> and the j main unit generator was syncronized to the bus at 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br />. A turbine trip, which was due to high level in the B steam generator, caused another reactor trip at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br />. The slow response of the Bypass Feedwater Regulating Valves was accountable for both i reactor trips. Reactor start-up was corvnenced at 2119 hours0.0245 days <br />0.589 hours <br />0.0035 weeks <br />8.062795e-4 months <br />; the reactor was critical at 2136 hours0.0247 days <br />0.593 hours <br />0.00353 weeks <br />8.12748e-4 months <br /> and at 2338 hours0.0271 days <br />0.649 hours <br />0.00387 weeks <br />8.89609e-4 months <br /> the main unit generator was syncronized to the grid.

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8211110295 821006 PDR ADOCK 05000334 R PDR

1' NARRATIVE SIM4ARY OF MJNTHLY OPERATING EXPERIENCE - SEPTEMBER 1982 (Continued)

September 12 Station is in Operational Mode 1 at a reminal 5% reactor power undergoing power escalation to 100%. At 0810 hours0.00938 days <br />0.225 hours <br />0.00134 weeks <br />3.08205e-4 months <br />, with a ncminal 50% reactor power, load was reduced 10% due to condenser vacuum problems. The problems were determined to be in the aux-iliary steam pressure to the air ejectors and also air in the circulating water system. Peactor power was again reduced 10% at 1624 hours0.0188 days <br />0.451 hours <br />0.00269 weeks <br />6.17932e-4 months <br /> after encountering problems with the turbine supervisory instrumentation indicating turbine rotor position greater than alarm set point. Reactor power increase was resumed at 1710 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.50655e-4 months <br /> after determining the problem to be faulty instrumentation. At 1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br /> another hold was put on the reactor power escalation due to the malfunction of Heater Drain Punp [SD-P-1A) . At 2109 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.024745e-4 months <br /> Heater Drain Punp [SD-P-1B] was returned to service and the reactor power escalation was resumed. At 2123 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.078015e-4 months <br />, with a ncminal 70% reactor power, Main Feedwater Punp [NP-1A] was started.

Septenber 13 At 1415 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br /> on the 13th the reactor power reached a mminal 100%.

through The Reactor Coolant System is at the normal operational Tavg and September 16 pressure of 575*F and 2235 psig.

September 17 At 0538 hours0.00623 days <br />0.149 hours <br />8.895503e-4 weeks <br />2.04709e-4 months <br /> the reactor power was reduced to a nominal 81% after through experiencing low level problems in the Steam Generators and in Septenber 18 the Heater Drain Tank. The levels returned to normal and at 0635 hours0.00735 days <br />0.176 hours <br />0.00105 weeks <br />2.416175e-4 months <br /> reactor power was increased back to 100%. At 2011 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.651855e-4 months <br />, reactor power was decreased 10% at 1%/ min and at 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br />, reactor power was increased 10% at 1%/ min for the power coef-ficient measurements.

September 19 Reduced load by approximately 100 MhT by request of the System Operator at 0423 hours0.0049 days <br />0.118 hours <br />6.994048e-4 weeks <br />1.609515e-4 months <br /> and at 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br /> reactor power increase back to 100% was conrnenced by request of the System Operator.

September 20 Reactor power is at a nominal 100% and the Reactor Coolant System through is at its normal operating terperature and pressure.

September 23 September 24 At 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> released by the System Operator to begin reactor power reduction to a rminal 25% for the repair of Main Feedwater Regulating Valve [FCV-%478] . At 2229 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.481345e-4 months <br /> the station reached a nominal 25% reactor power.

September 25 Station in Operational Mode 1 with reactor power at approximately 25%. At 0217 hours0.00251 days <br />0.0603 hours <br />3.587963e-4 weeks <br />8.25685e-5 months <br /> the reactor tripped on a low-low steam generator level due to the closure of the C bypass feedwater regulating valve and the station entered into Hot Standby Mxle 3.

September 26 The draining and refilling of all three steam generators and the condensate hotwell to inprove secondary chemistry is in progress.

At 1820 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.9251e-4 months <br /> the A and B shutdown Control Banks were pulled.

NARRREIVE SIM4ARY OF PONTHLY OPERREING EXPERIENCE - SEPTEMBER 1982 (ContinW)

Sepi.=ui.er 27 At 1135 hours0.0131 days <br />0.315 hours <br />0.00188 weeks <br />4.318675e-4 months <br /> reactor start-up was connenced, at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> the reactor went critical, at 1301 hours0.0151 days <br />0.361 hours <br />0.00215 weeks <br />4.950305e-4 months <br /> the main unit generator was syncronized to the grid, and by 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> the reactor power was at a naninal 98%.

i Septenber 28 Station in Operational Mode 1 with the reactor power at a

! through nominal 1001 and the Reactor Coolant System Tavg and pressure

Septenber 30 at 575'F and 2235 psig.

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1 DUQUESNE LIGff COMPANY Beaver Valley Power Station MAJOR SAFETY RELATED MAINTENANCE - SEPIEMBER 1982

1. Tube plugging in the Steam Generatcr [RC-E-1C], to eliminate Reactor Coolant System leakage to the secondary side, is conplete.

l 2. Removed and replaced the actuator, replaced the valve stem and repacked the Main Feedwater Regulating Valve [ECV-EW-478].

3. Renoved and replaced the actuator due to hydraulic fluid leakage and replaced the valve steam packing on the Main Feedwater Regulating Valve [EEV-EW-488] .

4. Replaced the valve steam packing on the Main Feedwater Regulating Valve

[ECV-EW-498] .

5. Overhauled the inboard seal cn the Main Feedwater Punp [EW-P-1A].

6. Realigned the r:otor and replaced bearings on the reactor plant Conponent Cooling Punp [CC-P-1B] .

i OPERATING DATA REPORT DOCKET NO. 50-334 DATF 10-7-62 COMPLETED BY L . '*' . We ave r

, TELEPHONE. 417 '41- 18.29 OPERATING STATUS

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

2. Reporting Period. September, 1982 2

3. Licensed Thermal Power (MWt): 7660

4. Nameplate Rating (Gross MWe): 923 S. Design Electrical Rating (Net MWe): 852

6. Maximum Dependable Capacity (Gross MWe): 860

7. Maximum Dependable 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 Period 720 6,551 ~!56,255

! 407 1,584.9

12. Number 6f Hours Reactor Was Critical 22,644.2

13. Reactor Reserve Shutdown Hours 0 0 " 4,482.8

14. Hours Generator On-Line 398.7 1,497.6 21,651.7

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 994.759.9 3,568,096.3 47,197,036.8,

! 17. Gross Electrical Energy Generated IMWH) 318.600_,_, 1.137,800 14,788,240 i 18. Net Electrical Energy Generated (MWH) 298.458 1,042,834 13,537,410

(' 19. Unit Service Factor 55.4 22.9 39.9

20. Unit Availability Factor 55.4 22.9 39.9

21. Unit Capacity Factor iUsing MDC Net) 51.2 19.7 32.7

22. Unit Capacity Factor IUsing DER Net) 48.7 18.7 31.1

23. Unit Forced Outaec Rate 16.9 9.0 38.6

24. Shutdowns Scheduled Over Next 6 Months IType. Date. and Duration of Each):

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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

i INITIA L CRITICA LITY N/A N/A l

INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A l

(9/77) 1

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AVERAGE DAILi UNIT POWER LEVEL .

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DOCKET NO. 50-334 (JNIT 3V?S Uni: il DATE '10/4/82 COMPLETED BY L. W. Weaver TELEPHONE (412) 643-182 MONTH September DAY AVERAGE DAILY POWER LEVEL DAY

~

AVERAGE DAILY POWER LEVEL IM N'8I (MWe-Net) -

1 0 '

804 37 2 0 812 13 3 0 775 19 4

0 808 20 g 0  ;; 812 6 0 22 809 7 0 811 23 8 0 729 24 9 0 o 3

10 0 0 26 11 0 293 27 12 348 808 23 13 797 gli 29 14 804 yo gog is 804 16 808 INSTRUCTIONS On this format.!tst the aver:ge dssly unit power !ese!in MWe. Net for esch day in ene recurring month. Compute to the nestest whoic mepwait.

(9/77) l

DOCKET NO. 50-334

-UNIT SHUIDOWNS AND POWER REDUCTIONS UNIT NAME ilVPS LInit #1 DATE October 7. 1982 REPORI MONIll September COMPLETED BY I- W. Weaver TELEPIIONE (412) 643- 1829 "i: -

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75d lif'"$

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g" n^. y -5 _E 5 51 5b 8 Came & Co'sectise I

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9. ? A , on in 5E 5 j5g RcPost " A0 j' Peevent Retuvrente 6

05 820827 S 240.5 B 2 N/A CC llT EXCII tianually tripped the reactor due to an apparent dropped rod. Station remained shut down for scheduled Steam Generator (RC-E-lC) tube re-pair.

06 820911 F 3.0 A 3 N/A Cl! VALVEt Tripped on low-low level indication in the 1C Steam Generator due to slow response time of the By-pass Feed-water control valves. Investigation is underway to reduce response time.

07 820911 F 19.1 A 3 N/A Cll VALVEX Turbine trip due to high level indi-cation in the 1B Steam Generator again due to slow response of Bypass Feedwater Control Valves in manual.

I 2 3 -l l': l'at t ed Reason: Hethod: Eshibis G . Insivuttions S: Si hed u!c.I A-I quipment FailureIExplain) 1-Manual fas Picparation of Data ll4faintenance of Test 2-Hanual Scram C Refueling l'.ntr) Sheets leu l.icensee 3-Automatic Scram INent Repos t ll l~ R l l' ele (Ni!RI G D Regulator) Restriction 4-Continued From Previous Month O l til i I -Operates Training A l.itense l'xamination 5-Reduction 1 - Adeninise r.etive 9-Other 5 G Operational l' eros ll xplaint ,

ITlubit 1 - SJme Somse P8/77) II Othes (I splaint

4 .

9 UNIT SilU1 DOWNS ANI) POWER REDUC 110NS DOCKET NO. 50-334 UNIT NAME BVPS Unit #1 I)A1E October 7 1982 REPORT AlONiil September COMPLETED RY 1. - W. Weavor 1 Ell PilONE (412) 643-1829 -

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Na. DJ'c } 33 h litel3hCe ,E -t, EQ CJuse A Consestsse E? 4 2s5 Event 3g n.? Asti m to 35 $ I5:!

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Peevens Recurrente 6

l 08 820925 F 58.7 C 3 N/A Cil While troubleshooting the Main Feed-VALVEX water Regulating Valve [FCV-FW-498]

not controlling at its progranuned set-  !

point the progranuned signal thereon was removed. This also removed the progranuned signal of the Bypass Feed-water Regualting Valve [FCV-FW-499]

causing it to go closed.

I 2 3 4 f: l ast ed Reason: teethod:

5' Sihedn!cil Esinbit G Iristnwei ms A-l'quipment Failure (I.xplaint 1-Hanual II4taintenance of Test fin PacPardei.m of Data 2-Hanual Scram 1:ntr> Sheets tan 1.icer 5cc C Reincling 3-Automatic Scram 1%cnt Repost 111 Ri f de (NilRI G ,

D RcFnI48'n) Restriction 4. Continued From Previous Month ()l til i I Opesatos Teaining A l.itense l'xarnination 5-Reduction

l' Ailnunisseative

' 9 0ther 5 G Opesational 1 n n ll mplaint lilnbit I Same,Sousse l'7/77) 11 Othe likplaing .