ML20203D481

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Monthly Operating Repts for Jan 1999 for Bvps,Units 1 & 2, in Accordance with NRC GL 97-02.With
ML20203D481
Person / Time
Site: Beaver Valley  FirstEnergy icon.png
Issue date: 01/31/1999
From: David Jones, Ostrowski K
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-97-02, GL-97-2, L-99-020, L-99-20, NUDOCS 9902160218
Download: ML20203D481 (6)
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( Nuclear Group L-99-020 P.O. Box 4 Shippingport, PA 15077-0004 February 5,1999 Beaver Valley Power Station Unit 1 - Docket No. 50-334, License No. DPR-66 Unit 2 - Docket No. 50-412, License No. NPF-73 Monthly Operatine Report U. S. Nuclear Regulatory Commission Document Control Desk Washington,DC 20555 Gentlemen:

In accordance with NRC Generic Letter 97-02, " Revised Contents of the Monthly Operating Report", and Unit 1 and 2 Technical Specification 6.9.1.6, the " Monthly Operating Report"is submitted for Unit 1 and Unit 2 for the month ofJanuary,1999.

Respectfully, fl. ah K. L. Ostrowski l

Division Vice President, l Nuclear Operations Group }

Tl and Plant Manager

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l DTJ/ sip Enclosures

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t cc: NRC Regional Office King ofPrussia, PA wj T,h N'u,clea,r Professionals 9902160218 990205 PDR ADOCK 05000334 R PDR ,_

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e UNIT SHUTDOWNS l DOCKET NO. 50-334 UNIT NAME BVPS Unit #1 '

DATE February 2,1999 COMPLETED BY David T. Jones TELEPHONE (412) 393-4962 REPORTING PERIOD: January 1999 No. Date Type Duration Reason Method of Cause / Corrective Actions F: Forced (Hours) (1) Shutting s; scheduled Down (2) Comments 1 990123 F 58.2 G 2 The Reactor was manually tripped from approximately 73 % output due to degrading Condenser conditions. At the time of the trip, the "C" Condenser waterbox was out of service, the Condenser hotwell temperature, back-pressure and waterbox delta-T's were increasing, and the three running Cooling Tower Pumps were experiencing j cavitation. The root cause of the trip was J determined to be failure of the Operating l

, crew to properly confirm and maintain a l l stable inventory in the "C" waterbox outlet l piping following a closing adjustment to the j "C" waterbox inlet valve which was i

! experier cing in-leakage.

(1) Reason (2) Method A - Equipment Failure (Explain) 1 Manual B - Maintenance or Test 2 Manual Trip / Scram C - Refueling 3 - Automatic Trip / Scram D Regulatory Restriction 4 -Continuation E operator Training / Ucense Examination 5 - other (Explain)

F - Administrative G - operational Error (Explain)

H - Other (Explain) l I

SUMMARY

! The Unit began the report period operating at a nominal value of 100% output. At 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> l on 1/22/99, a power reduction to approximately 90% output was commenced to support '

1 cleaning of the Main Unit Condenser. An output of approximately 90% was achieved at 2258

hours.

Beginning at 0912 hours0.0106 days <br />0.253 hours <br />0.00151 weeks <br />3.47016e-4 months <br /> on 1/23/99, several small power reductions were commenced in an attempt to reduce increasing hotwell temperatures, and low Condenser vacuum conditions. At

. 1024 hours0.0119 days <br />0.284 hours <br />0.00169 weeks <br />3.89632e-4 months <br />, output had been reduced to approximately 73%, when the Reactor was manually 2

tripped due to degrading Condenser conditions. At the time of the trip, the "C" Condenser  ;

2 waterbox was out of service, the Condenser hotwell temperature, backpressure and waterbox

!, delta-T's were increasing, and the three running Cooling Tower Pumps were experiencing i

. UNIT SHUTDOWNS DOCKET NO. 50-334 )

UNIT NAME BVPS Unit #1 j DATE February 2,1999 COMPLETED BY David T. Jones l TELEPHONE (412) 393-4962 REPORTING PERIOD: January 1999

SUMMARY

(continued):

cavhtion. The Unit was subsequently stabilized in Mode 3. The root cause of the trip was determined to be failure of the Operating crew to properly confirm and maintain a stable inventory in the "C" waterbox outlet piping following a c'osing adjustment to the "C" waterbox inlet valve which was experiencing in-leakage.

Following completion of all corrective actions required for restart, Mode 2 was entered at 0353, the Reactor was taken critical at 0453 hours0.00524 days <br />0.126 hours <br />7.490079e-4 weeks <br />1.723665e-4 months <br />, and Mode 1 was entered at 0845 hours0.00978 days <br />0.235 hours <br />0.0014 weeks <br />3.215225e-4 months <br /> on i 1/25/99. At 1258 hours0.0146 days <br />0.349 hours <br />0.00208 weeks <br />4.78669e-4 months <br /> on 1/25/99, the Turbine was tripped with no load on the Main Unit l Generator, due to increasing Main Condenser backpressure caused by a lack of gland steam l adjustment. The Reactor remained critical. At 2038 hours0.0236 days <br />0.566 hours <br />0.00337 weeks <br />7.75459e-4 months <br /> on 1/25/99, the Main Unit l Generator was synchronized to the electrical grid, and output was escalated towards approximately 30% power. An output of approximately 27% was achieved at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on 1/26/99. The Unit remained at approximately 27% output while waiting for Chemistry l conditions to improve. At 1924 hours0.0223 days <br />0.534 hours <br />0.00318 weeks <br />7.32082e-4 months <br /> on 1/26/99, output was escalated towards approximately 75% power. An output of approximately 75% was achieved at 0447 hours0.00517 days <br />0.124 hours <br />7.390873e-4 weeks <br />1.700835e-4 months <br /> on 1/27/99. As i Condenser hotwell temperatures permitted, additional power escalations were able to be performed as various waterbox sections of the Condenser were cleaned and restored to service. The Unit was able to achieve an output of approximately 94% at the end of the report period on 1/31/99 while Main Unit Condenser cleaning continued.

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OPERATING DATA REPORT DOCKET NO. 50-334 l

UNIT NAME: BVPS UNIT #1 j REPORT DATE: 02/02/99 i COMPLETED BY: DAVID T. JONES l TELEPHONE: (412) 393-4962 4

l REPORTING PERIOD:

  • Notes la. JANUARY 1999 ,

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1. DESIGN ELECTRICAL RATING (Not Hwe): 835 . .
2. MAX. DEPENDABLE CAPACITY (Net Mwe): 810 ................

THIS MONTH YEAR TO DATE CUMULATIVE

- 3a. HOURS IN REPORTING PERIOD: 744.0 744.0 199464.0

3. NO. OF HRS. REACTOR NAS CRITICAL: 701.5 701.5 129981.5
4. 9ERVICE HOURS GENERATOR ON LINE: 685.8 685.8 127717.5
5. UNIT RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0  !
6. NET ELECTRICAL ENERGY GEN. (MWH): 523797.0 523797.0 94209689.0
7. GROSS ELECT. ENERGY GEN. (MWH): 557847.0 557847.0 100724622.0
8. GROSS THERMAL ENERGY GEN. [MWH): 1709974.0 1709974.0 311179751.5
9. UNIT AVAILABILITY FACTOR (%): 92.2 92.2 65.6
10. UNIT CAPACITY FACTOR (.M DC) (%): 86.9 86.9 60.4
11. UNIT FORCED OUTAGE RATE (%): 7.* 7.8 18.3 l

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IfNIT SHUTDOWNS DOCKET NO. 50-412 UNIT NAME BVPS Unit #2 DATE February 2,1999 COMPLETED BY David T. Jones TELEPHONE (412)393-4962 REPORTING PERIOD: January 1999 No. Date Type Duration Reason Method of Cause / Corrective Actions F: Forced (Hours) (1) Shutting s: scheduisd Down (2) Comments NO SHUTDOWNS l

l l

I (1) Reason (2) Method A Equipment Failure (Explain) 1 - Manual B ' Maintenance or Test 2 - Manaal Trip / Scram 1 C Refueling 3 - Automatic Trip / Scram {

D Regulatory Restriction 4 - Continuation I l

E operator Training / License Examination 5 - Other (Explain)

F + Administrative G - Operational Error (Explain)

H Cther(Explain)

SUMMARY

The Unit began the report period operating at a nominal value of 100% output. At 0905 hours0.0105 days <br />0.251 hours <br />0.0015 weeks <br />3.443525e-4 months <br /> on 1/31/99, a power reduction to approximately P5% output was commenced to remove the "A" First Point Heater from service in order to support required repairs to the 21A First Point Heater Normal Level Control Valve due to stem / plug separation. An output of approximately 95% was achieved at 1213 hours0.014 days <br />0.337 hours <br />0.00201 weeks <br />4.615465e-4 months <br /> on 1/31/99. Following removal of the "A" First Point Heater from service, small incremental power escalations were able to be performed with a final 4 output of approximately 98% achieved by the end of the report period on 1/31/99, as repairs to the 21 A First Point Heater Normal Level Control Valve continued.

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-n OPERATING DATA REPORT DOCKET NO.: 50-412 UNIT NAME: .BVPS UNIT #2 REPORT DATE: 02/02/99 COMPLETED BY: DAVID T. JONES TELEPHONE: (412) 393-4962 la. REPORTING PERIOD:~ JANUARY 1999

  • Notes *
1. DESIGN ELECTRICAL RATING (Not Mwe): 836
2. MAX. DEPENDABLE CAPACITY (Net Mwe): 820 .................

THIS MONTH YEAR TO DATE CUMULATIVE 3a. HOURS IN REPORTING PERIOD: 744.0 744.0 98247.0

3. NO. OF HRS. nEACTOR WAS CRITICAL: 744.0 744.0 78340.3
4. SERVICE HOURS GENERATOR ON LINE: 744.0 744.0 77773.1
5. ' UNIT RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0
6. NET ELECTRICAL ENERGY GEN. (MWH): 622447.0 622447.0 60023029.0
7. GROSS ELECT. ENERGY GEN. (MWH): 654543.0 654543.0 63511495.0
8. GROSS THERMAL ENERGY GEN. (MWH): 1963037.0 1963037.0 194467792.0
9. UNIT AVAILABILITY FACTOR (%): 100.0 100.0 79.2
10. UNIT CAPACITY FACTOR (MDC) (%): 102.0 102.0 74.2
11. UNIT FORCED OUTAGE RATE (%): 0.0 0.0 12.2 q

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