Text

Monthly Operating Rept for Nov 1983
	ML20086G793
Person / Time
Site:	Beaver Valley
Issue date:	12/08/1983
From:	Holtz J; DUQUESNE LIGHT CO.
To:	;
Shared Package
ML20086G791	List: ML20086G788; ML20086G793;
References
	NUDOCS 8401120407
	Download: ML20086G793 (9)
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NARRATIVE SdMMARY OF MONTHLY OPERATING EXPERIENCE - NOVEMBER, 1983 November 1 The station was in Operational Mode 1 with reactor power at Through a nominal 100 percent. The Reactor Coolant System was at

-November 2 normal operating temperature and pressure. At 1825 hours0.0211 days 0.507 hours 0.00302 weeks 6.944125e-4 months on the 2nd, it was discovered that TV-CC-107C, the 1C Reactor Coolant Pump Thermal Barrier CCR Outlet Isolation Valve, had tripped shut and could not be operated from the benchboard.

Pump temperatures were rising, and a containment entry was made to inspect the valve and attempt to restore it to oper-

_ ability.

Inspection of the valve revealed a blown diaphragm ij as the apparent cause of the problem. It was decided to

'i continue plant operation while plans were made to repair the valve.

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'l November 3 At 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months , the system operator released the station to i-reduce its load for repair of TV-CC-107C.

The load reduction was then begun. Reactor power was reduced to 30 percent and held at that level.

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November 4 At 0042 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months , the station once again began reducing load due to the high radiation levels near TV-CC-107C.

Reactor power was reduced to 1 percent. The Main Unit Cenerator j

was taken off line at 0127 hours0.00147 days 0.0353 hours 2.099868e-4 weeks 4.83235e-5 months . Containment entry was made at 0216 hours0.0025 days 0.06 hours 3.571429e-4 weeks 8.2188e-5 months to repair TV-CC-107C.

At 0645 hours0.00747 days 0.179 hours 0.00107 weeks 2.454225e-4 months , repairs were complete. The Main Unit Cenerator was synchro-nized to the grid at 0945 hours0.0109 days 0.263 hours 0.00156 weeks 3.595725e-4 months . At 1008 hours0.0117 days 0.28 hours 0.00167 weeks 3.83544e-4 months , the 'B' Main Feedwater Regulating Valve was placed in service with reactor-

?j power at 25 percent.

'A' and 'C' Main Feedwater Regulating Valves were out of service to allow their bonnet gaskets to be replaced. Reactor power was taken to 30 percent and held

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there until the gasket replacement on 'A' and 'C' Main Feed-i water Regulating Valves was complete. A load increase was

j begun at 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months following the return to service of 'A' it and 'C' Main Feedwater Regulating Valves. At 2310 hours0.0267 days 0.642 hours 0.00382 weeks 8.78955e-4 months , with reactor power at a nominal 100 percent, the turoine was man-1 ually tripped due to an inability to maintain vacuum in the

'B' Waterbox of the Main Condenser.

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November 5 An investigation of the problem in the condenser found that the leak was in the

'B' Waterbox Pressure Transmitter ll !

[PT-CN-103B]. The suction line equalizing vent of the hotwell sample pump is connected to [PT-CN-103B). When Maintenance i

removed the pump for repair, this created an air leak to the

'B' Waterbox. The line was isolated, and reactor startup began at 0241 hours0.00279 days 0.0669 hours 3.984788e-4 weeks 9.17005e-5 months . The reactor was taken critical at

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0326 hours0.00377 days 0.0906 hours 5.390212e-4 weeks 1.24043e-4 months , and the Main Unit Cenerator was synchronized to the grid at 0509 hours0.00589 days 0.141 hours 8.416005e-4 weeks 1.936745e-4 months . Reactor power was steadily increased ll to 95 percent and held to allow adjustment of the excore instrumentation. Reactor power was then increased to a i

nominal 100 percent. 8401120407 831208 PDR ADOCK 05000334 i

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NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE - NOVEMBER, 1983 November 6

.The station was in Operational Mode 1 with rea; tor power i

Through-at a nominal 100 percent. The Reactor Coolant System was November 17 1

. at ncrual operating temperature and pressare.

November 18 The station was in Operational Mode 1 with reactor power at a nominal 100 percent. At 1230 hours0.0142 days 0.342 hours 0.00203 weeks 4.68015e-4 months , the Auxiliary 011 pump on the 1A Main Feedwater Pump [FW-P-1A] started i

autcmatically. Operators were unable to secure the Auxiliary Oil Pump. At 1255 hours0.0145 days 0.349 hours 0.00208 weeks 4.775275e-4 months , station load was de-p creased in order to remove FW-P-1A from service. Reactor power was reduced to 65 percent, and FW-P-1A was secured i

at 1359 hours0.0157 days 0.378 hours 0.00225 weeks 5.170995e-4 months .

As FW-P-1A coasted to a stop, oil began l

seeping out of the suction pipe connection to the shaft-driven main oil pump. The piping was found to be cracked 7

l and FW-P-1A was placed on clearance for repair. Repairs to the oil pump suction piping were completed at 1739 hours0.0201 days 0.483 hours 0.00288 weeks 6.616895e-4 months .

The Main Feedwater Pump was returned to service and reactor f

power was increased to a nominal 100 percent.

Novecher 19

- The station was in Operational Mode 1 with reactor power jc Through at a nominal 100 percent. The Reactor Coolant System was November 20 at normal operating temperature and pressure.

November 21 Ine'etation was in Operational Mode I with reactor pcwer at a nominal 100 percent. At 0601 hours0.00696 days 0.167 hours 9.937169e-4 weeks 2.286805e-4 months , feedwater flow to

].

the 'lC' Steam Generator began decreasing. Oil was found to be leaking from the 'lC' Main Feedwater Regulating Valve !FCV-FW-498}. Operators attempted unsuccessfully to operate the valve manually to raise the steam generator j

level. At 0602 hours0.00697 days 0.167 hours 9.953704e-4 weeks 2.29061e-4 months , the plant was manually tripped due to an expected plant trip on lo-lo steam generator level.

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The plant was stabilized in Operational Mode 3.

FCV-FW-498 l!-

was cleared, and the actuator was replaced. A surveillance

)1 test on the valve was successfully completed at 1345 hours0.0156 days 0.374 hours 0.00222 weeks 5.117725e-4 months .

Reactor startup commenced immediately afterward, and the reactor was taken critical at 1409 hours0.0163 days 0.391 hours 0.00233 weeks 5.361245e-4 months . After encountering

,j some problems with the electro-hydraulic control on the tur-bine valves, the Main Unit Generator was synchronized to the I

grid at 1820 hours0.0211 days 0.506 hours 0.00301 weeks 6.9251e-4 months . Reactor power was taken to 30 percent

[

and held to recover delta flux. The normal boration rate was too slow for the rate of Xenon burnout. Emergency bora-tion was begun. After delta flux had been recovered, ascension to full power was begun.

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November 22 The station was in Operational Mode 1.

A nominal 100 percent Through reactor power was achieved at 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months . Reactor Coolant

,[

November 28 System temperature and pressure were at normal operating conditions.

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NARRATIVE SUMfARY OF MONTHLY OPERATING EXPERIENCE - NOVEMBER, 1983 November 29 The station was in Operational Mode 1.

At 1127 hours0.013 days 0.313 hours 0.00186 weeks 4.288235e-4 months , feedvater flow and level began decreasing in the IB Steam Generator. The Main Feedwater Regulating Valve was place 1 in manual control and opened fully. The Bypase Feedwater Valve was opened 60 percent. Feed flow and level tempor-

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1130 hours0.0131 days 0.314 hours 0.00187 weeks 4.29965e-4 months , the plant was manuallt arily recovered, but at tripped when the 'lB' Main Feedwater Regulating Valve began coming apart. The valve was isolated..and the plant was stabilized in Mode 3.

The 'lB' Main Feedwater Regulating Valve was placed on clearance. Plans were also made for an entry into containment to investigate a leak in pressuri=er liquid level transmitter, LT-RC-460.

The reactor was taken critical at 2228 hours0.0258 days 0.619 hours 0.00368 weeks 8.47754e-4 months , and reactor power was maintained at less than 5 percent.

November 30 The station was in Operational Mode 2.

Containment entry was

+

made at 0120 hours0.00139 days 0.0333 hours 1.984127e-4 weeks 4.566e-5 months to inspect and. repair LT-RC-460.

At 0350 hours0.00405 days 0.0972 hours 5.787037e-4 weeks 1.33175e-4 months , after restoring the LT-RC-460 and PT-RC-456 bistables, repairs were complete. Both bistables were de-clared operable.

Turbine startup began at 0355 hours0.00411 days 0.0986 hours 5.869709e-4 weeks 1.350775e-4 months .

The Main Unit Generator was synchronized with the grid at 0444 hours0.00514 days 0.123 hours 7.34127e-4 weeks 1.68942e-4 months . Reactor power was increased to 30 percent and held with the Steam Generator Feedwater Bypass Valves in operation.

Inspection and repair work was being done on all three Main Feedwater Valves, FCV-FW-478, 488, and 498. FCV-FW-488 had its actuator re-paired, and the valve was repacked. The actuators of the other two valves were disassembled and inspected.

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F MAJOR SAFETY-RELATED MAINTENANCE - NOVEMBER, 1983 1.

A level transmitter, LT-RC-460, for the pressurizer war repaired.

2.

The actuator on TV-CC-107C, 1C Reactor Coolant Pump Thermal Barrier CCR Outlet Isolation Valve, was repaired.

i 3.

- The actuators of the three Main Feedwater Regulating Valves wers disassembled, inspected, and re-installed.

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AVERAGE DALLY UNIT POWER LEVEL 50-334 DOCKET NO.

tjNIT 3T2S Cui:: 41 December 8/83 DATE COMPLETED BY J. L. Holtz TELEPHONE (412) 643-1369 s:

November MO M DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(MWeNet) 818 821 1

g7 809 gg 760 2

3 39 '

822 760 4

3 822 161 607 321 g

23 010

.808 6

2 822 819 7

3 822 1518 g

y 822 822 9

25 k

10 y

818 822 821 822 gg 27 822 810 12 3

822 381 13 29 818 156 g4 30 825 15 3;

818 g

t INSTRUCTIONS l

On this format.!ist the average daily unit power leset in MWe. Net for each day in the reportmg munih.Cmnpute o the nesrest whole megswatt.

(9/77)

W OPERATING DATA REPORT DOCKET NO. 50-334 DATE 12-8-83 COMPLETED BY J.

L. Holtz TELEPHONE. 41? '61-1369 OPERATING STATUS

1. Uni Name: Beaver Valley Power Station. Unit #1 Notes

2. Reporting Period:

November, 1983

3. Licensed Thermal Power (MWt):

2640

4. Nameplate Rating (Gross MWe):

923

5. Design Electrical Rating (Net MWe):

835

6. Maximum Dependable Capacity (Gross MWe):

860 i

7. Maximum Dependable Capacity (Net MWe):

310 l

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

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9. Power Level To Which Restricted. If Any (Net MWe):

None

10. Reasons For Restrictions. If Any:

N/A i

' This Month Yr.-to-Date

' Cumulative

11. Hours in Reporting Period 720 8,~016 66,4'80

12. Number Of Hours Reactor Was Critical 696.6 5,324.9 30,142.4

13. Reactor Reserve Shutdown Hours 0

0 '

4.482.8

14. Hours Generator On-Line 676.2 5,243.4 29.043.6

15. Unit Reserve Shutdown Hours 0

0 0

i

16. Cross Thermal Energy Generated (MWH) 1.695.802.9 13.185.815.7 65.695,997.1 y

17. Gross Electrical Energy Generated (MWH) 553,000 4.295.300 20.807.940

18. Net Electrical Energy Generated (MWH) 527,639 4,083,230

-19,295.347

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19. Unit Service Factor 93 9 65.4 45.7

20. Unit Availability Factor 93.9_-

65.4 45.7

21. Unit Capacity Factor (Using MDC Net) 90.5 62.9 39.2

22. Unit Capacity Factor (Using DER Net) 87.8 61.0 38.0 j

23. Unit Forced Outage Rate 6.1 3.8 31.6

24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each t:

.)

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

26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved I

INITIA L CRITICA LITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A (9/77) i ve m er~

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4 UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-334 UNIT NAME BVPS Unit #1_ _,

l DATE 12-8-83 COMPLETED BY J.

L. Holtz REPORT MONTI{ -

Nnva=her TELErilONE (412) 643-1369 4

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)Y Licensee E c, gk Cause & renscotise DJ'e y;

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2 E ac Event c; 2 ct '2 Atsi.m to

$3 jiji g Repen1

A0 E0 Psevent Recurrente 6

9 11/4/83 F

8.3 A

5 N/A CJ VALVEX The reactor power was reduced to 1 percent and the Main Unit Genera-tor was taken off line at 0127 hours0.00147 days 0.0353 hours 2.099868e-4 weeks 4.83235e-5 months in order to repair'TV-CC-107C.

Following the repair, the Main Unit Generator was synchronized to the grid at 0945 hours0.0109 days 0.263 hours 0.00156 weeks 3.595725e-4 months .

10 11/4/83 F

6.0 A

2 N/A HC ZZZZZZ While performing maintenance on a hotwell sample pump, an air leakage a

path was established to the conden-i ser.

At 2310 hours0.0267 days 0.642 hours 0.00382 weeks 8.78955e-4 months , the turbine was manually tripped due to the inabilit3 i

to maintain condenser vacuum. The j

leak was isolated and the reactor

. as taken critical at 0326 hours0.00377 days 0.0906 hours 5.390212e-4 weeks 1.24043e-4 months on w

the 5th.

The Main Unit Generator l

was synchronized to the grid at 4

0509 hours0.00589 days 0.141 hours 8.416005e-4 weeks 1.936745e-4 months .

I I

2 3

4-i l: F.nsed Reason:

Hethod:

Exhibil G - Instiut tiims 5: St hedu!cil A. Equipment Failure (Explain) 1-Manual fos Psepa:Jtiert of Data i

B. Maintenance iTest 2-Manual Scram Ente) Sheels for l_icensee C Refueling 3-Automatic scram INeni Repos e Il.I R t I de t NURI G D Regulatory Restriction 4-Continued From Previous Month 0161) l' Opesatin Training A 1.itense Examination 5-Reduction I

F Administrative 9-Ottier 5

G Operational linus il xplain t E shibit 1 - Same,Somsc l'8/77)

II Othee (E xplain)

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' UNITSHUTDOWNS ANDPOWER REDUCTIONS DOCKET NO.

50-334 UNIT NAME BVPS Unit #1 DATE 12-8-83 l

REPJRT 5f0 NTH November COMPLETED BY J. L. Holtz TELEPilONE (412) 643-1369 j

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=

3 a. :=g Licensee E.,

5*

c 2E g

[h'1, Cause & Cmsettive No.

Da'e

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3g j

j g oc Event 5i Atti.m to

$3 E

j15g Repo1m 5'0 Psevent Recurrente j

d 11 11/21/83 F

12.3 A

2 N/A CH VALV0P At 0602 hours0.00697 days 0.167 hours 9.953704e-4 weeks 2.29061e-4 months , the plant was manu-ally tripped due to a feedwater flow control valve failure. FCV-FW-498 was cleared, and the actuator was replaced. The reactor was taken critical at 1409 hcurs, and the Main Unit Generator was synchronized !

to the grid at 1820 hours0.0211 days 0.506 hours 0.00301 weeks 6.9251e-4 months .

12 11/29/83 F

17.2 A

2 N/A CH VALVEX At 1130 hours0.0131 days 0.314 hours 0.00187 weeks 4.29965e-4 months , the plant was manu-ally tripped due to a feedwater flow control valve failure.

FCV-FW-488 was cleared, and repairs l

were begun. At 2228 hours0.0258 days 0.619 hours 0.00368 weeks 8.47754e-4 months , the re-

]

actor was taken critical but held under 5 percent. At 0444 hours0.00514 days 0.123 hours 7.34127e-4 weeks 1.68942e-4 months on the 30th, the Main Unit Generator was synchronized to the main grid.

I 2

3

-4 l~: F.uted Reason:

Hethod:

Exliibit G Instruttisms 5: Sthedu'eil A Eiguipment Failure (Explain) 1-Manual for Pseparation of Data U Mahiter.ance viTest 2-Manual Scram 1:ntr) Sliects for 1.icensee C RcIuelinE D RegulaJor) Restriction Event Repine ll.l'RII de tNURI.G 3-Automatic Scram 4-Continued From Previous Month 01011 j

l'-Operatin Training & Iicense Examinatiim 5-Reduction F Administrative 9-other 5

G. Operational I? inn II'mplain)

I slobit 1 Same Somcc t'8/77)

Il Olher (E xplain t

F-THIRD REFUELING STEAM GENERATOR INSPECTION During the Third Refueling Outage, the primary side of the tubing in 'B' and 'C' Steam Generators was examined by Sabcock and Wilcox, util-izing Eddy Current examination techniques. Concurrent with these examinations, Westinghouse performed a visual examination of the secondary side of

'A',

'B', and 'C' Steam Generators. A total of 4128 tubes were examined, and, as a result of the examination, 8 tubes were removed from service.

Eddy Current examinations were conducted on 740 of the 3388 tubes in

'B' Steam Generator and on 100 percent (3387 tubes) of the tubes in

'C' Steam Generator. These examinations revealed that 1 (one) tube in

'B' r-

-Steam Generator and 3 (three) tubes in 'C' Steam Generator had through-wall defect indications in excess of the BVPS Technical Specifications limit of 40 percent.

In addition to the recording and retrieval of foreign objects, the scope of the visual examinations included the assessment of the condition of the secondary side of the tubes in the tube lane, the flow slot, and the peripheral areas.

Foreign objects were found in all three Steam Generators, and all objects were removed. Four tubes had to be severed between the tube sheet and the first support plate to allow for the re-moval of foreign objects in 'B' and 'C' Steam Generators.

The following tubes were removed from service by mechanically plugging both ends of the tube.

Steam Generator Tube Location Reason for Removal from Service B

Row 35, Column 77 De fect in excess of 40 percent limit Row 46, Column 54 To facilitate foreign object removal C

Row 30, Column 16 De fect in excess of 40 percent limit Row 31, Column 16 Defect in excess of 40 percent limit Row 43, Column 32 Defect in excess of 40 percent limit Row 31, Column 13 To facilitate foreign object removal Row 31, Column 14 To facilitate foreign object removal Row 31, Column 15 To facilitate foreign object removal Upon completion of all plugging, cutting, and retrieval activities, the Steam Generators were flooded, pressurized, and leak tested. No leakage was detected, and the Steam Generators were returned to service.

ML20086G793

Text

SUMMARY

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