Text

Monthly Operating Rept for Feb 1983
	ML20071E722
Person / Time
Site:	Beaver Valley
Issue date:	03/03/1983
From:	Holtz J; DUQUESNE LIGHT CO.
To:	;
Shared Package
ML20071E717	List: ML20071E716; ML20071E722;
References
	NUDOCS 8303150337
	Download: ML20071E722 (8)
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DUQUESNE LIGHT COMPANY-Beaver Valley Power Station NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE - FEBRUARY 1983 February 1 The station was in operational mode 1 with reactor power at through- a nominal 100 percent and the reactor coolant system at February 5 , normal operating temperature and pressure.

February 6 At 0000 hours0 days 0 hours 0 weeks 0 months , a load reduction was started in preparation for a containment entry. This was completed at 0121 hours0.0014 days 0.0336 hours 2.000661e-4 weeks 4.60405e-5 months with reactor power at 48 percent. At 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months , a crew of electricians entered containment to investigate the cause of high stator temperatures on the "C" reactor coolant pump

[RC-P-lC]. At 0300 the electricians removed the inspection plates on the pump, and stator temperatures began to decrease.

The crew also added oil to all three reactor coolant pumps' lube oil reservoirs. All three were about 1" low. A reactor power increase was begun at 0615 hours0.00712 days 0.171 hours 0.00102 weeks 2.340075e-4 months at system's request. This was completed at 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months with reactor power ct nominal 100 percent.

February 7 The station was in operational mode 1 with reactor power at through a nominal 100 percent and the reactor coolant system at normal February 11 operating temperature and pressure.

February 12 At 1004 hours0.0116 days 0.279 hours 0.00166 weeks 3.82022e-4 months the plant experienced a reactor trip / safety injection actuation due to low steamline pressure. A sweated fitting on the air supply line to the trip valve on th'e "B" main steam line [TV-MS-101B] had separated, venting the air and allowing the valve to close. The subsequent steam flow increase in the "A" steam line momentarily dropped steam pressure sufficiently to cause a trip. An Unusual Event was declared at 1028 hours0.0119 days 0.286 hours 0.0017 weeks 3.91154e-4 months due to the Emergency Safeguards Features actuation. The reactor operators followed applicable procedures to stabilize the plant and then proceeded to recover from the trip and the safety injection. The Unusual Event was terminated at 1106 hours0.0128 days 0.307 hours 0.00183 weeks 4.20833e-4 months . The air line to the "B" main steam trip valve [TV-MS-101B] was repaired and a stroke test was performed at 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months . The valve failed to close and an investigation found that one of the actuator cylinder pistons was binding and would not stroke fully.

February 13 The station was in operational mode 3, Hot Standby. At 0005 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , the technical specification action statement dealing with an inoperable main steam isolation valve was met by disconnecting both of the valve actuator cylinders from the valve shaft in order to close the valve. At 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months , a containment entry was made to check the "B" loop cubicle for leaks; none were found. Disassembly of the "B" main steam trip valve actuator showed that the problem was due to a scored cylinder which in turn was attributed to a slightly de-formed piston. Repairs to the valve were completed at 1900 hours0.022 days 0.528 hours 0.00314 weeks 7.2295e-4 months .

C303150337 830303 gDRADOCK 05000334 PDR l

2 NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE - FEBRUARY 1983 February 14 Reactor startup was commenced at 0050 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months and the reactor was-taken critical at 0112 hours0.0013 days 0.0311 hours 1.851852e-4 weeks 4.2616e-5 months . The reactor tripped at 0135 hours0.00156 days 0.0375 hours 2.232143e-4 weeks 5.13675e-5 months on lo-lo steam generator level in the "C" steam generator.

The feedwater bypass valve (FCV-FW-499] had failed to respond to manual control. An investigation revealed a leaking "O" ring on the valve actuator that allowed cylinder equalization.

A stroke test showed that the valve would only open about 10 percent of the way. The actuator was repaired and the limit switches were adjusted. At 1020 hours0.0118 days 0.283 hours 0.00169 weeks 3.8811e-4 months , the valve was stroke tested satisfactorily and reactor startup was commenced at 1025 hours0.0119 days 0.285 hours 0.00169 weeks 3.900125e-4 months . The reactor went critical at 1049 hours0.0121 days 0.291 hours 0.00173 weeks 3.991445e-4 months and the main unit generator was synchronized at 1452 hours0.0168 days 0.403 hours 0.0024 weeks 5.52486e-4 months . Reactor power was steadily increased until,1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months , at which time it was held at 50 percent in order to test run the "A" main feedwater pump [FW-P-1A]. The pump was run satisfactorily and a reactor power increase was begun at 1658 hours0.0192 days 0.461 hours 0.00274 weeks 6.30869e-4 months . Reactor power reached a nominal 100 percent at 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months . .

February 15 Reactor power was reduced by 80 MW at 0027 hours3.125e-4 days 0.0075 hours 4.464286e-5 weeks 1.02735e-5 months co allow for isolation of the "B" first point heater (FW-E-1B], which had developed a tube leak. The isolation valves for the point heater were completely closed at 0032 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months but were leaking by. Reactor power was increased to a nominal 100 percent at 1335 hours0.0155 days 0.371 hours 0.00221 weeks 5.079675e-4 months .- Isolation valves for "B" first point heater were verified as closed and holding flow at 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months .

February 16 Station was in operational mode 1 with reactor pcwer at a nominal through 100 percent and the reactor coolant system at normal operating February 25 temperature and pressure.

February 26 Station in operational mode 1 with reactor power at a nominal 100 percent. Both trains of the reactor trip breaker under voltage trip function were tested as required on NRC IE Bulletin 83-01. Both trains tested satisfactorily.

February 27 The station was in operational mode 1 with reactor power at a through nominal 100 percent and the reactor coolant system at normal February 28 operating temperature and pressure.

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DUQUESNE LIGHT COMPANY Beaver Valley Power Station MAJOR SAFETY-RELATED MAINTENANCE - FEBRUARY 1983

1. A containment entry was made on February 6 to inspect reactor coolant pump RC-P-lC. The inspection plates were removed in order to allow the stator to cool. Also, oil was added to all three reactor coolant pumps' lube oil reservoirs. All had been about 1" low.

2. The air supply line to'the main steam trip. valve TV-MS-101B actuator had separated at a sweated fitting and was repaired. Subsequent attempts to stroke the valve wsre unsuccessful. An investigation found that the actuator piston was binding due to debris and a' loose pivot arm. Repeated operation of the valve over a period of. time had allowed the piston to strike the cylinder wall, " mushrooming" its leading edge. The inside cylinder was

-honed and the piston head was machined. The actuator was tested satisfactorily.

3. One of the steam generator feedwater bypass valves [FCV-FW-499] had failed to respond to manual control due to a leaking "0" ring on the valve actuator.

The "0" ring was replaced and the limit switches were adjusted.

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4. Auxiliary feedwater pump, FW-P-2, was repacked.

5. Verified operability of both "A" & "B" reactor trip breakers to comply with I.E. Bulletin No. 83-01.

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AVERAGE DAILI UNIT POWER LIVEL DOCKET NO.

'C-334 UNIT 37?S Unic #1 DATE 3*3-81 J. L. Holtz -

COMPLETED BY TELEPHONE 412-643-1369 .

P February *

MON 771 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Mwe-NeO (MWe Neti 3 817 ,

1 37 809 gg 813 2

821 3, 817 g9 817 809 .

4 3 813 g 821 23 676 809 6 22 813 809 j 7

809 g 813 24 821 817 825 26 . 821 10 817 11 27 332 813 32 3 13 29 30 30 14

- 15 31 1

821 16 i

4 INSTRUCTIONS On this format. fist the average dsdy unit power leselin MWe-Net for esch day in the reportine munch. Ca,npute to the nearest whole mepwatt, i9/77)

- - - - - - _ . - - - , = - - - _ - , . . . . . .. .- _.- . _ _. - _. - . . . - - - . - . - . . - - . - - . - _ - - . - - _

OPERATI G DATA REPORT DOCKET NO. 50-33'4 DATE 3-3-83 COMPLETED BY J. L. Holtz

.. TELEPHONE. 41?-641-1369 OPERATING STATUS -

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

2. Repo'rting Period: February

3. Licensed Thermal Power (MWt): 2660

4. Nameplate Rating (Gross MWe): 923

5. 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 (Irems Number 3 Through 7) Since Last Report, Give Reasons:

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9. Power Level To Which Restricted.lf Any (Net MWe): None

10. Reasons For Restrictions,if Any:. N/A .: .

4

. __ This Month -

Yr. to-Date ' Cumulative -

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11. Hours In Reporting Period 672 1l416 C'59,880 .

12. Number Of Hours Reactor Was Critical 623.6 1.334.6 26.152.1 13.' Reactor Reserve Shutdown Hours 0 0 e 4.402. 8'

14. Hours Generator On-Line 619.2 1,327.6 25,127.8

15. Unit Reserve Shutdown Hours 0 0 .0

16. Cross Thermal Energy Generated (MWH) 1.598.707.8 3.333.046.8 55,843,228

.I7. Gross Electrical Energy Generated (MWHj 522,500 1,093,600 17,606,240

18. Net Electrical Energy Generated (MWH) 498.117 1.042.611 16,254,728

19. Unit Service Factor 92.1 . 93.8- 43.9

20. Unit Availability Factor 92.1 ,

93.8 43.9

21. Unit Capacity Factor (Using MDC Net) 91.5- 90.9 36.9

22. Unit Capacity Factor (Using DER Net) 87.0 86.4 35.1

23. Unit Forced Outage Rate 7.9 6.25 35.0

24. Shutdowns Scheduled Over Next 6 Months (Type.Date.and Duration of Each1:

Shut;down for third refueling scheduled to begin June 11, 1983. Projected duration is 14 weeks.

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

26. Units in Test Status (Prior o Cornmercial Operation): Forecast Achieved INITIA L CRITICA LITY N/A N/A

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INITIAL ELECTRICITY N/A N/A COMM ERCIAL OPERATION N/A N/A (9/77)

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-334 UNIT NAME BVPS Unit #1 DATE 3-3-83

. REPORT MONTig _ FERUARY , COMPLETEI) RY J . L. Holtz TELErllONE _412-643-1369 1

! 't i e n o=2 3 i No. Date 8. $m! ! l$5 ""#

h1 {,% Cause & Correceive y gj o- E

= 5 = 8C j di y "HI R' Port a g3 u, o -} Action so p,,,,,,g,,,,,,,,,

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j 3 830212 F 52.8 A 3 83-005/99X CD VALV0P At 1004. hours, the plant experienced i

a safety inspection / reactor trip actu-

' atton due to low steamline pressure.

A sweated fitting on the air supply line to the trip valve on the "B" main steam line [TV-MS-101B) had separated, allowing [TV-MS-101B] to close. The subsequent rapid incredse in steam flow in the "A" and "C" steamlines j momentarily dropped steam pressure in 4

a the "A" steamline sufficiently to cause a safety injection / reactor trip I

on a low steamline pressure signal.

An Unusual Event was declared at 1028 hours0.0119 days 0.286 hours 0.0017 weeks 3.91154e-4 months due to ESF equipment actuation.

i The Unusual Event was terminated at 1106 hours0.0128 days 0.307 hours 0.00183 weeks 4.20833e-4 months .

i 5

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F: Foiced Reason:

i S: Schedided

^ n.chodi Exhibis G . instincthms A.Eiluipment Failure (Explain) 1-Manual for Pseparathni of Data i

B-Maintenance ci Test 2-Manual scram -

I C Refueling Entr> Sheels for 1.icensee 3-Automatic Scram Event Reping iLERI File iNLIREG D Regulaint) Restriellem 4-Continued From Previous Month 01611 E Operains Training & t.icense Examinaikm 5-Reduction F.Administrailve 9-oth.c .'

G Operailunal Enos IEmplahil Exhibit I Same, Source l'8/17) Il-Ollier ( E splain t

DOCKET NO. 50-334 UNIT SifUTDOWNS AND POWER REDUCTIONS '

UNIT NAME BVPS Unit #1

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

. REPORT Af 0NTil TELErilONE 419-641-1969 C Pg T 3

?,e3 O

.2 E = f .5 ;4 Licensee Et E% Cause A Corrective

\"- DJ'e k 5@ 4 255 Event E$ 93 Acilon to

jE E jgg Report n :N G

]L Prevent Recurrence 6

3 830212 F 52.8 A 3 83-005/99X CD VALVOP Following the repair of the air line at 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months on the 12th, the valve was stroke tested unsatisfac-torily. The problem was found to be

{

a piston that was ' binding in the -

actuator cylinder. At 0005 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months on the 13th, the technical specifi-cation action statement dealing with

an inoperable main steam isolation ,

valve was met by disconnecting both of the halve actuator cylinders from the valve shaft in order to close the valve. Valve actuator repairs were completed at 1900 hours0.022 days 0.528 hours 0.00314 weeks 7.2295e-4 months .

Reactor startup was commenced at 0050 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months on the 14th, and the reactor went critical at 0112 hours0.0013 days 0.0311 hours 1.851852e-4 weeks 4.2616e-5 months .

[ The reactor tripped at 0135 hours0.00156 days 0.0375 hours 2.232143e-4 weeks 5.13675e-5 months on i 2 3 4 f f.nsed Reason: Method: Extiibis G Insituttions S Schedn'eil A Etiuipmen,t Failure (Explain) 1-Manual for Picparation of Data B-Maintenance of Test 2-Manual Scram Entr> Sheets for 1.ieensee C.RcIncling 3-Automatic Scram Event Repost II.l:RI File INllRIIG D. Regulator) Resirletion 4-continued From Previous Month 0161) 1:-Operato Training & License Examination 5-Reduction F Administrative a-Other 5 ,

G Operational Enos (Explaint Estiibit 1 SJme Somee

4 f t) ll Olher lihplaini k

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UNITSifUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-334 UNIT NAME BVPS Unit il DATE _3-3-83

. REPORT MONTil FEBRUARY COMPLETED ny J. L. Iloltz TELEP110NE 412-643-1369 "L

e n % .S 2 No. Date E- 'S $ 75g f LI'"5 5*., $4 Cause & Corrective

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Report 8 '"R } j}

9- Action to Prevent Recurrence 3 830212 F 52.8 A 3 83-005/99X CD VALVOP lo-lo steam generator level in the

"C" steam generator. The feedwater bypass valve [FCV-FW-499] had failed to respond to manual control due to a leaking "O" ring on the valve actuator cylinder. Following repair and testing of.the valve, reactor startup was commenced at 1025 hours0.0119 days 0.285 hours 0.00169 weeks 3.900125e-4 months .

The reactor was taken critical at 1049 hours0.0121 days 0.291 hours 0.00173 weeks 3.991445e-4 months and the main unit gener-ator was synchronized at 1452 hours0.0168 days 0.403 hours 0.0024 weeks 5.52486e-4 months .

t I 2 3 -l F: FosccJ Reason:

S Scheduled Method: Exhible G . Instinctions A Eqbipment Failure (Explain) 1-Manual for Pseparation of Data B Maintenance ciTest 2-Manual scram Entr> Sheets for 1.icensee C RefuelinE 3-Automatic Scram Event Repost fl.l RI filt INUREG 1 D Regulatos) Restiletion 4-Continued From Frevious Month 0161) l~ Opesatos Tealning& Ucense Examination 5-Reduction

, F Aihninistrative 9-Other 5 G Openallonal Lines (Explain) -

Exhible 1 Same, Source l'8/77) ll Olher (E xplain p 9

ML20071E722

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