ML020600189

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January 2002 Monthly Operating Report for Limerick Generating Station, Units 1 & 2
ML020600189
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 02/08/2002
From: Braun R
Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML020600189 (7)


Text

Exelon.

Exelon Nuclear Limerick Generating Station P.O. Box 2300 Sanatoga, PA 19464 www.exeloncorp.com Nuclear T.S.6.9.1.6 February 8, 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 January 2002 forwarded pursuant to Technical Specification 6.9.1.6.

In addition, the Design Electrical Rating (DER) has been revised from 1143 MWe to 1191 MWe to reflect the current plant design since the turbine retrofits. This rating is retroactive to June 1998 for Unit 1 and June 1999 for Unit 2.

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

Very truly yours, Robert C. Braun Plant Manager gjl Attachments cc:

H. J. Miller, Administrator, Region I, USNRC A. L. Burritt, LGS USNRC Senior Resident Inspector

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Docket No. 50-352 Attachment to Monthly Operating Report for January 2002 Limerick Generating Station Unit 1 January 1 through January 31, 2002 Narrative Summary of Operating Experiences Unit 1 began the month of January 2002 at 99% 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 January 3 rd at 1110 hours0.0128 days <br />0.308 hours <br />0.00184 weeks <br />4.22355e-4 months <br />, reactor power was reduced from 97.9% to 96.7% RTP to remove 6C feedwater heater from service. At 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />, reactor power was restored to 100% RTP.

On January 81h at 1346 hours0.0156 days <br />0.374 hours <br />0.00223 weeks <br />5.12153e-4 months <br />, reactor power was reduced from 98.7% to 96.5% RTP to remove 6B feedwater heater from service. At 1450 hours0.0168 days <br />0.403 hours <br />0.0024 weeks <br />5.51725e-4 months <br />, reactor power was restored to 100% RTP.

On January 15 h at 1206 hours0.014 days <br />0.335 hours <br />0.00199 weeks <br />4.58883e-4 months <br />, reactor power was reduced from 98.7% to 96.5% RTP to remove 5C feedwater heater from service. At 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />, reactor power was restored to 100% RTP.

On January 1 8 th at 1127 hours0.013 days <br />0.313 hours <br />0.00186 weeks <br />4.288235e-4 months <br />, reactor power was reduced from 99.3% to 96.5% RTP to remove 5A feedwater heater from service. At 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br />, reactor power was restored to 100% RTP.

On January 22 n at 1246 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.74103e-4 months <br />, reactor power was reduced from 99.5% to 96.6% RTP to remove 5B feedwater heater from service. At 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />, reactor power was restored to 100% RTP.

Unit 1 ended the month of January 2002 at 97% 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 January. 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 FEBRUARY 8, 2002 COMPLETED BY EXELON CORPORATION G. J. LEE REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3707 OPERATING STATUS 1. U N IT N A M E :------------------

2. REPORTING PERIOD:
3. DESIGN ELECTRICAL RATING:.
4. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):............
5. MAXIMUM DEPENDABLE CAPACITY (NET MWE):

THIS MONTH

6. NUMBER OF HOURS REACTOR WAS CRITICAL
7. REACTOR RESERVE SHUTDOWN HOURS
8. HOURS GENERATOR ON-LINE
9. UNIT RESERVE SHUTDOWN HOURS
10. NET ELECTRICAL ENERGY GENERATED (MWH) 744.0 0.0 744.0 0.0 848,855 YR-TO-DATE 744.0 0.0 744.0 0.0 848,855 LIMERICK UNIT.1 JANUARY 2002 1174 1134 CUMULATIVE 122,299.2 0.0 120,408.1 0.0 123,330,854

UNIT SHUTDOWNS AND SIGNIFICANT LOAD REDUCTIONS REPORT MONTH JANUARY 2002 DOCKET NO.

50-352 UNIT LIMERICK UNIT 1 DATE FEBRUARY 8, 2002 COMPLETED BY EXELON CORPORATION G. J. LEE REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION 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 (2)

Reason A -- Equipment Failure B -- Maintenance or Test C -- Refueling D -- Regulatory Restriction E -- Operational Training & License Examination F --Administrative G -- Operational Error (Explain)

H -- Other (Explain)

(3)

Method 1 -- Manual 2 -- Manual Scram 3 -- Automatic Scram 4 -- Other (Explain)

(1)

Type F-- Forced S -- Scheduled

Docket No. 50-353 Attachment to Monthly Operating Report for January 2000 Limerick Generating Station Unit 2 January 1 through January 31, 2000 Narrative Summary of Operating Experiences Unit 2 began the month of January 2000 at 100% of rated thermal power (RTP).

On January 3rd 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 5 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 6th 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 26 h 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 2000 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 January. There have been no challenges to the Main Steam Safety Relief Valves year-to-date.

OPERATING DATA REPORT DOCKET NO. 50-353 DATE FEBRUARY 8, 2002 COMPLETED BY EXELON CORPORATION G. J. LEE REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATIltIG STATION TELEPHONE (610) 718-3707 1

OPERATING STATUS LIMERICK UNIT 2 JANUARY 2002

1. U N IT N A M E :
2. R E PO R T IN G PE R IO D :..
3. DESIGN ELECTRICAL RATING:
4. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):..
5. MAXIMUM DEPENDABLE CAPACITY (NET MWE):...............

THIS MONTH

6. NUMBER OF HOURS REACTOR WAS CRITICAL
7. REACTOR RESERVE SHUTDOWN HOURS
8. HOURS GENERATOR ON-LINE
9. UNIT RESERVE SHUTDOWN HOURS
10. NET ELECTRICAL ENERGY GENERATED (MWH) 744.0 0.0 744.0 0.0 874,213 YR-TO-DATE 744.0 0.0 744.0 0.0 874,213 CUMULATIVE 98,177.0 0.0 96,506.9 0.0 102,498,937 1174 1134

UNIT SHUTDOWNS AND SIGNIFICANT LOAD REDUCTIONS REPORT MONTH JANUARY 2002 DOCKET NO.

50-353 UNIT LIMERICK UNIT2 DATE FEBRUARY 8, 2002 COMPLETED BY EXELON CORPORATION G. J. LEE

/

REPORTS ENGINEE SITE ENGINEERING LIMERICK GENERATING STATION 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 (2)

Reason A -- Equipment Failure B -- Maintenance or Test C -- Refueling D -- Regulatory Restriction E -- Operational Training & License Examination F -- Administrative G -- Operational Error (Explain)

H -- Other (Explain)

(3)

Method 1-- Manual 2 -- Manual Scram 3 -- Automatic Scram 4 -- Other (Explain)

(1)

Type F-- Forced S -- Scheduled