ML020850624

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February 2002 Monthly Operating Report for Limerick Generating Station, Units 1 & 2
ML020850624
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 03/15/2002
From: Braun R
Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML020850624 (10)


Text

Exelon Nuclear www.exeloncorp.com Exelon. Nuclear Limerick Generating Station PO. Box 2300 Pottstown, PA 19464 T.S.6.9.1.6 March 15, 2002 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Limerick Generating Station, Unit 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353

Subject:

Limerick Generating Station Monthly Operating Report For Units 1 and 2 Enclosed are the monthly operating reports for Limerick Units 1 and 2 for the month of February 2002 forwarded pursuant to Technical Specification 6.9.1.6.

In addition, attached is a revised copy of the Unit 2 Summary Page of the December 2001 Monthly Operating Report which incorrectly reported that there were no Main Steam Safety Relief Valve challenges year-to-date when in fact there was a challenge on Feb. 23, 2001.

Also, included are some typographical changes to the Unit 2 Summary Page of the January 2002 Monthly Operating Report.

If you have any questions or require additional information, please do not hesitate to contact us.

Very truly yours, Robert C. Braun Plant Manager Attachments cc: H. J. Miller, Administrator, Region I, USNRC A. L. Burritt, LGS USNRC Senior Resident Inspector

bcc: W. Levis, GML 5-1 C. Mudrick, SSB 3-1 S. T. Gamble, SSB 2-4 S.P. Breeding, SSB 2-3 J.C. Toro, SMB 1-2 E. Kelly, SSB 3-1 G. Lee, SSB 3-1

Docket No. 50-352 Attachment to Monthly Operating Report for February 2002 Limerick Generating Station Unit 1 February 1 through February 28, 2002 Narrative Summary of Operating Experiences Unit 1 began the month of February 2002 at 97% of rated thermal power (RTP) in end of-cycle coastdown.

Throughout the month, unless specified below, when the unit operated at less than 100% RTP, it was due to end-of-cycle coastdown.

On February 101h at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, reactor power was reduced from 93.3% to 77.8% RTP to remove the 1 B reactor feed pump from service. On February 11th at 0050 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />, reactor power was restored to 91.4% RTP.

On February 1 5th at 1203 hours0.0139 days <br />0.334 hours <br />0.00199 weeks <br />4.577415e-4 months <br />, reactor power was reduced from 91.6% to 79.10% RTP to restore the 1 B reactor feed pump back in service. At 1607 hours0.0186 days <br />0.446 hours <br />0.00266 weeks <br />6.114635e-4 months <br />, reactor power was restored to 89.6% RTP.

On February 1 7 th at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, reactor power was reduced from 90.6% to 76.6% RTP to remove the 1C reactor feed pump from service. At 2352 hours0.0272 days <br />0.653 hours <br />0.00389 weeks <br />8.94936e-4 months <br />, reactor power was restored to 89.6% RTP.

On February 22nd at 0003 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, reactor power was reduced from 89.4% to 76.8% RTP to restore the 1C reactor feed pump back to service. At 0413 hours0.00478 days <br />0.115 hours <br />6.828704e-4 weeks <br />1.571465e-4 months <br />, reactor power was restored to 86.5% RTP.

On February 2 4 th at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, reactor power was reduced from 88.2% to 78.8% RTP to remove the 1A reactor feed pump service. On February 2 5 th at 0006 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, reactor power was restored to 86.7% RTP.

Unit 1 ended the month of February 2002 at 86% RTP in end-of-cycle coastdown.

Challenges to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief Valves during the month of February. There have been no challenges to the Main Steam Safety Relief Valves on Unit 1 year-to-date.

OPERATING DATA REPORT DOCKET NO. 50-352 DATE MARCH 8,2002 COMPLETED BY EXELON CORPORATION G. J. LEE REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3707 OPERATING STATUS

1. UNIT NAME:
2. REPORTING PERIOD: FEB.RUARY.200.2.
3. DESIGN ELECTRICAL RATING:............................................................. ------- 1191
4. MAXIMUM DEPENDABLE CAPACITY (GROSS MW E): ---------------------------------------- ..................... 4 S..................
5. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1134 THIS MONTH YR-TO-DATE CUMULATIVE
6. NUMBER OF HOURS REACTOR WAS CRITICAL 672.0 1,416.0 122,971.2
7. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
8. HOURS GENERATOR ON-LINE 672.0 1,416.0 121,080.1
9. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
10. NET ELECTRICAL ENERGY GENERATED (MWH) 691,034 1,539,889 124,021,888

UNIT SHUTDOWNS AND SIGNIFICANT LOAD REDUCTIONS DOCKET NO. 50-352 UNIT LIMERICK UNIT 1 DATE MARCH 8,2002 COMPLETED BY EXELON CORPORATION G. J. LEE REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATFING STATION REPORT MONTH FEBRUARY 2002 TELEPHONE (610) 718-3707 GENERATOR OFF LINE TYPE DURATION REASON METHOD OF SHUTTING NO. DATE (1) (HOURS) (2) DOWN REACTOR (3) CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE (1) (2) (3)

Type Reason Method F-- Forced A -- Equipment Failure 1 -- Manual S-- Scheduled B -- Maintenance or Test 2 - Manual Scram C - Refueling 3 -- Automatic Scram D -- Regulatory Restriction 4 -- Other (Explain)

E -- Operational Training & License Examination F -- Administrative G -- Operational Error (Explain)

H -- Other (Explain)

Docket No. 50-353 Attachment to Monthly Operating Report for February 2002 Limerick Generating Station Unit 2 February 1 through February 28, 2002 Narrative Summary of Operating Experiences Unit 2 began the month of February 2002 at 100% of rated thermal power (RTP).

On February 2 3 'd at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, reactor power was reduced to 92% RTP for quarterly turbine valve and MSIV testing. On February 2 4 th at 0520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br />, reactor power was restored to 100% RTP.

Unit 2 ended the month of February 2002 at 100% of RTP.

Challenges to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief Valves during the month of February. There have been no challenges to the Main Steam Safety Relief Valves year-to-date.

OPERATING DATA REPORT DOCKET NO. 50-353 DATE MARCH 8, 2002 COMPLETED BY EXELON CORPORATION G. J. LEE REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3707 OPERATING STATUS LIMERICK UNIT 2

1. U NIT NA ME: ....

FEBRUARY 2002

2. R E P O R T ING P E R IO D: ------------------------------------------------------.................
3. DESIGN ELECTRICAL RATING:...................................................................................

1174

4. MAXIMUM DEPENDABLE CAPACITY (GROSS MW E): ---------------------------------------

1134

5. MAXIMUM DEPENDABLE CAPACITY (NET MW E): ------------------------- .. ............................. .. . .

THIS MONTH YR-TO-DATE CUMULATIVE 1,416.0 98,849.0

6. NUMBER OF HOURS REACTOR WAS CRITICAL 672.0 0.0 0.0 0.0
7. REACTOR RESERVE SHUTDOWN HOURS 672.0 1,416.0 97,178.9
8. HOURS GENERATOR ON-LINE 0.0 0.0 0.0
9. UNIT RESERVE SHUTDOWN HOURS 791,723 1,665,936 103,290,660
10. NET ELECTRICAL ENERGY GENERATED (MWH)

UNIT SHUTDOWNS AND SIGNIFICANT LOAD REDUCTIONS DOCKET NO. 50-353 UNIT LIMERICK UNIT 2 DATE MARCH 8,2002 COMPLETED BY EXELON CORPORATION G. J. LEE REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3707 REPORT MONTH FEBRUARY 2002 GENERATOR OFF LINE TYPE DURATION REASON METHOD OF SHUTTING NO. DATE (1) (HOURS) (2) DOWN REACTOR (3) CAUSE AND CORRECTIVE ACTION TO PREVENTRECURRENCE (2) (3)

(1) Method Type Reason I -- Manual F -- Forced A -- Equipment Failure 2 -- Manual Scram S -- Scheduled B -- Maintenance or Test 3 - Automatic Scram C -- Refueling 4 -- Other (Explain)

D -- Regulatory Restriction E -- Operational Training & License Examination F -- Administrative G -- Operational Error (Explain)

H -- Other (Explain)

Docket No. 50-353 Attachment to Monthly Operating Report for December 2001 Limerick Generating Station Unit 2 December 1 through December 31, 2001 Narrative Summary of Operating Experiences Unit 2 began the month of December 2001 at 100% of rated thermal power (RTP).

There were no power changes this month on Unit 2.

Unit 2 ended the month of December 2001 at 100% of RTP.

Challenges to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief Valves during the month of December. There has been one challenge to the Main Steam Safety Relief Valves on Unit 2 year-to-date.

Docket No. 50-353 Attachment to Monthly Operating Report for January 2002 Limerick Generating Station Unit 2 January 1 through January 31, 2002 Narrative Summary of Operating Experiences Unit 2 began the month of January 2002 at 100% of rated thermal power (RTP).

On January 3 rd at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, reactor power was reduced to 96% RTP for rod pattern adjustment. At 2329 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.861845e-4 months <br />, reactor power was restored to 100% RTP.

On January 51h at 2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br />, reactor power was reduced to 71% RTP for rod pattern adjustment and control rod scram time testing. On January 6 th at 1244 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.73342e-4 months <br />, reactor power was restored to 100% RTP.

On January 2 6 1h at 0958 hours0.0111 days <br />0.266 hours <br />0.00158 weeks <br />3.64519e-4 months <br />, reactor power was reduced to 99% RTP due to a reactor level and power transient that occurred during the quarterly testing of HV-001 209, main steam to condenser hotwell steam sparger valve, at 0955 hours0.0111 days <br />0.265 hours <br />0.00158 weeks <br />3.633775e-4 months <br />. At 1045 hours0.0121 days <br />0.29 hours <br />0.00173 weeks <br />3.976225e-4 months <br /> reactor power was restored to 100% RTP.

Unit 2 ended the month of January 2002 at 100% of RTP.

Challenges to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief Valves dur~ng the month of January. There have been no challenges to the Main Steam Safety Relief Valves year-to-date.