L-02-116, November 2002 Monthly Operating Report for Beaver Valley Units 1 & 2

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November 2002 Monthly Operating Report for Beaver Valley Units 1 & 2
ML023540129
Person / Time
Site: Beaver Valley
Issue date: 12/06/2002
From: Bezilla M
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-02-116
Download: ML023540129 (6)
v • d • e


Text

FENOC Nxftear Opera',n Ctp Fs,-s1EneqT.y a "BeaverValley PowerStation P. O. Box 4 Shippingport,PA 15077 L-02-116 December 6, 2002 Beaver Valley Power Station Unit 1 - Docket No. 50-334, License No. DPR-66 Unit 2 -Docket'No-50-412,1License No.NPF-73 .

Monthly Operating 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 6.9.4, the "Monthly Operating Report" is submitted for Unit 1 and Unit 2 for the month of November 2002.

Respectfully, M. B. BezillaV Vice-President DTJ/cmg Enclosures cc: NRC Regional Office King of Prussia, PA oP

I UNIT SHUTDOWNS DOCKET NO. 50-334 UNIT NAME BVPS Unit #1 DATE December 3, 2002 COMPLETED BY David T. Jones TELEPHONE (724) 682-4962 REPORTING PERIOD: November 2002 No. Date Type Duration Reason Method of Cause / Corrective Actions (Y/M/D) F: Forced (Hours) (1) Shutting S: Scheduled Down (2) Comments 021111 S 216.0 B 2 While shutting down for a "scheduled" 9 day maintenance outage and with the Unit operating at approximately 53% output, the reactor was manually tripped due to a

-......... turbine motoring condition alarm from the turbine anti-motoring circuit. The cause for the alarm was due to failure of a high-low pressure turbine differential pressure indicator. The indicator was replaced with a different model instrument.

2 021120 F 53.9 A 4 Startup from the 9 day scheduled maintenance outage was forced to be extended for the following reasons:

1. To repack the "B" Motor-Driven Auxiliary Feedwater Pump.
2. To repair a packing leak on an RCS Wide Range Pressure Transmitter Isolation Valve located inside Containment.
3. To adjust the Main Unit Generator voltage regulator in order to support synchronization of the Unit.

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

F - Administrative G - Operational Error (Explain)

H - Other (Explain)

SUMMARY

The Unit began the report period operating at a nominal value of 100% output. At 1520 hours0.0176 days <br />0.422 hours <br />0.00251 weeks <br />5.7836e-4 months <br /> on 11/11/02, the Unit began to shutdown for a planned maintenance outage to clean and inspect the reactor vessel head and to enhance the performance of the Unit's steam supply and cooling water systems. At 1946 hours0.0225 days <br />0.541 hours <br />0.00322 weeks <br />7.40453e-4 months <br /> on 11/11/02 while at approximately 53% output, the reactor was manually tripped due to a turbine motoring condition alarm. The Unit was stabilized in Mode 3. The Unit continued to cooldown and depressurize, entering Mode 4 at 0143 hours0.00166 days <br />0.0397 hours <br />2.364418e-4 weeks <br />5.44115e-5 months <br /> on 11/12/02. During the

UNIT SHUTDOWNS DOCKET NO. 50-334 UNIT NAME BVPS Unit #1 DATE December 3, 2002 COMPLETED BY David T. Jones TELEPHONE (724) 682-4962 REPORTING PERIOD: November 2002

SUMMARY

(continued):

depressurization of the reactor coolant system (RCS), one of the Pressurizer Power Operated Relief Valves (PORV's) was cycled three times per station shutdown procedures in order to reduce RCS

-pressure from 975 psig to 475 psig. (Note: Because this event was considered to be a challenge to a PORV, it is being reported-in' the -Month ype-ra~ing-Re156it"a§"requiredby Technical Specification 6.9.4.) The Unit continued to cooldown and depressurize, but could not enter Mode 5 (cold shutdown) until the Residual Heat Removal Inlet Isolation Valve could be manually opened (valve is scheduled to be repaired during 1R15). Upon opening of the valve, the Unit entered Mode 5 at 1125 hours0.013 days <br />0.313 hours <br />0.00186 weeks <br />4.280625e-4 months <br /> on 11/12/02. After completion of the maintenance activities planned for during the scheduled maintenance outage, the Unit began to heat up, entering Mode 4 at 1108 hours0.0128 days <br />0.308 hours <br />0.00183 weeks <br />4.21594e-4 months <br /> on 11/19/02. Entry into Mode 3 was delayed until the "B" Motor-Driven Auxiliary Feedwater Pump could be successfully repacked. Following repack of the "B" Motor-Driven Auxiliary Feedwater Pump, Mode 3 was entered at 0954 hours0.011 days <br />0.265 hours <br />0.00158 weeks <br />3.62997e-4 months <br /> on 11/20/02. Entry into Mode 2 was delayed in order to repair a packing leak on an RCS Wide Range Pressure Transmitter Isolation Valve in Containment. Upon completion of repairs, Mode 2 was entered at 0559 hours0.00647 days <br />0.155 hours <br />9.242725e-4 weeks <br />2.126995e-4 months <br /> on 11/22/02. The Reactor was taken critical at 0638 hours0.00738 days <br />0.177 hours <br />0.00105 weeks <br />2.42759e-4 months <br /> and Mode 1 was entered at 0801 hours0.00927 days <br />0.223 hours <br />0.00132 weeks <br />3.047805e-4 months <br /> on 11/22/02. Synchronization was delayed due to problems with the Main Unit Generator voltage regulator. After completing an adjustment, the Unit was synchronized to the electrical grid at 0141 hours0.00163 days <br />0.0392 hours <br />2.331349e-4 weeks <br />5.36505e-5 months <br /> on 11/23/02, and escalation to full power began. With the Unit operating at approximately 98% output, a load rejection of approximately 200 MWe occurred at 1022 hours0.0118 days <br />0.284 hours <br />0.00169 weeks <br />3.88871e-4 months <br /> on 11/24/02. This was caused by failure of the #1 Governor Valve to stay open due to failure of its LVDT.

Reactor power also reduced and was stabilized at approximately 87% output before being returned to approximately 92% output following the transient. The Unit remained operating at approximately 92%

output while troubleshooting of the #1 Governor valve continued. Upon restoration of the #1 Governor Valve to service, escalation to full power resumed at 1803 hours0.0209 days <br />0.501 hours <br />0.00298 weeks <br />6.860415e-4 months <br /> on 11/261102. A nominal value of 100% output was achieved at 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br /> on 11/26/02. The Unit continued to operate at a nominal value of 100% output for the remainder of the report period.

I OPERATING DATA REPORT DOCKET NO.: 50-334 UNIT NAME: BVPS UNIT #1 REPORT DATE: 12/02/02 COMPLETED BY: DAVID T. JONES TELEPHONE: (724) 682-4962

"* Notes: Rated thermal power at

  • la. REPORTING PERIOD: NOVEMBER 2002 "* BVPS-1 was uprated from 2652 MWt*

"* to 2689 MWt on 10/20/01. Net

  • I. DESIGN ELECTRICAL RATING (Net-MWe):*__ 835 -_

- *MDC wasdIls6-uprated from - *

  • 810 MWe to 821 MWe. *
2. MAX. DEPENDABLE CAPACITY (Net MWe): 821 . * * * * * * * * * * * * * * * *
  • THIS MONTH YEAR TO DATE CUMULATIVE 8016.0 233040.0 3a. HOURS IN REPORTING PERIOD: 720.0 7765.1 159847.5
3. NO. OF ERS. REACTOR WAS CRITICAL: 469.1 7746.1 157368.0
4. SERVICE HOURS GENERATOR ON LINE: 450.1 0.0 0.0
5. UNIT RESERVE SHUTDOWN HOURS: 0.0 6364574.0 118030717.0
6. NET ELECTRICAL ENERGY GEN. (MWH): 354854.0 6741564.0 126008350.0
7. GROSS ELECT. ENERGY GEN. (MWH): 381024.0 20638578.0 388273383.5
8. GROSS THERMAL ENERGY GEN. (MWE): 1157615.0 96.6 69.0
9. UNIT AVAILABILITY FACTOR (M): 62.5 96.7 64.3
10. UNIT CAPACITY FACTOR (MDC) (k): 60.0 0.7 15.7
11. UNIT FORCED OUTAGE RATE (b): 10.7

UNIT SHUTDOWNS DOCKET NO. 50-412 UNIT NAME BVPS Unit #2 DATE December 3, 2002 COMPLETED BY David T. Jones TELEPHONE (724) 682-4962 REPORTING PERIOD: November 2002 No. Date Type Duration Reason Method of Cause / Corrective Actions (Y/M/D) F: Forced (Hours) (1) Shutting S: Scheduled Down (2) Comments NONE (1) Reason (2) Method A - Equipment Failure (Explain) 1 - Manual B - Maintenance or Test 2 - Manual Trip / Scram C - Refueling 3 - Automatic Trip I Scram D - Regulatory Restriction 4 - Continuation E - Operator Training / Ucense Examination 5 - Other (Explain)

F - Administrative G - Operational Error (Explain)

H - Other (Explain)

SUMMARY

The Unit operated at a nominal value of 100% output for the entire report period.

OPERATING DATA REPORT DOCKET NO.: 50-412 UNIT NAME: BVPS UNIT #2 REPORT DATE: 12/02/02 COMPLETED BY: DAVID T. JONES TELEPHONE: (724) 682-4962

"* Notes: Rated thermal power at

  • Ia. REPORTING PERIOD: NOVEMBER 2002 "* BVPS-2 was uprated from 2652 MWt*

"* to 2689 Mwt on 10/30/01. Net

  • I-. DESIGN -ELECTRICAL RAT11T (Net-MWe):- -- 836 .

"* MDC wai al Souprated from

2. 831

"* 820 MWe to 831 MWe.

  • MAX. DEPENDABLE CAPACITY (Net MWe): * * * * * * * * * * * * * * * * *
  • THIS MONTH YEAR TO DATE CUMULATIVE 720.0 8016.0 131823.0 3a. HOURS IN REPORTING PERIOD:

720.0 7456.6 108811.1

3. NO. OF ERS. REACTOR WAS CRITICAL:

720.0 7389.9 108082.5

4. SERVICE HOURS GENERATOR ON LINE:

0.0 0.0 0.0

5. UNIT RESERVE SHUTDOWN HOURS:

610818.0 5986913.0 84565005.0

6. NET ELECTRICAL ENERGY GEN. (MWH):

ENERGY GEN. (MWH): 640715.0 6309144.0 89383887.0

7. GROSS ELECT.

(MWH): 1933715.0 19229494.0 272637075.0

8. GROSS THERMAL ENERGY GEN.

100.0 92.2 82.0

9. UNIT AVAILABILITY FACTOR (M):

102.1 89.9 77.4

10. UNIT CAPACITY FACTOR (MDC) Mp}):
11. 0.0 0.2 9.8 UNIT FORCED OUTAGE RATE (M):
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