ML20207M692

Monthly Operating Repts for Feb 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With 990310 Ltr

ML20207M692
Person / Time
Site:	Dresden
Issue date:	02/28/1999
From:	Abrell G, Heffley J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-REGGD-01.016, RTR-REGGD-1.016 GL-97-02, GL-97-2, JMHLTR:#99-0032, JMHLTR:#99-32, NUDOCS 9903190158
Download: ML20207M692 (11)

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• Commonwealth IMimn Company Dresden Generating Station 65c0 North Dresden Road Morris, 11.60150 Tel HI4912 2920 March 10,1999 JMilLTR: #99-0032 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Subject:

Monthly Operating Data Report for February 1999 Dresden Nuclear Power Station Commonwealth Edison Company Docket Nos.50-010. 50-237, and 50-249 Enclosed is the Dresden Nuclear Power Station Monthly Operating Summary Report for February 1999.

This information is supplied to your office as required by Technical Specification 6.9.A.5, in accordance with the instructions set forth in Regulatory Guide 1.16.

and Generic Letter 97-02.

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Respectfully, I l

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,1. le y 1 '

' e Vice Pr sident i Dresden Statio

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Enclosure 100007 cc: NRC Region 111 OfTice NRC Senior Resident Inspector, Dresden Nuclear Power Station /g h UDI, Inc. - Washington, DC /

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9903190150 990228 PDR ADOCK 05000010 R PDR A Unicom Company

MONTHLY NRC

SUMMARY

OF 01ERATING EXPERIENCE, PER REGULATORY GUIDE 1.16 FOR DRESDEN NUCLEAR POWER STATION COMMONWEALTH EDISON COMPANY FOR FEBRUARY 1999 UNIT DOCKET LICENSE 1 050-010 DPR-2 2 050-237 DPR-19 3 050-249 DPR-25 i

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l' 1 l.- . i I I TABLE OF CONTENTS FEBRUARY 1999 NRC REPORT 1.0 Introduction 2.O Summary of Operating Experience 2.1 Unit 2 Monthly Operating Experience Summary.

2.2 Unit 3 Monthly Operating Experience Summary.

3.0 Operating Data Statistics 3.1 Operating Data Report - Dresden Unit 2 3.2 Operating Data Report - Dresden Unit 3 3.3 Unit 2 Shutdowns 3.4 Unit 3 Shutdowns 4.0 Unique Reporting Requirements 4.1 Main Steam Relief and/or Safety Valve Operations - ,

Unit 2 and Unit 3 {

4.2 Technical Specification Amendments I

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1.0 Introduction Dresden Nuclear Power Station is a three reactor generating facility owned and operated by the Comed Company of Chicago, Illinois. Dresden Station is located at the confluence of the Kankakee and Des Plaines Rivers, in Grundy County, near Morris, Illinois.

Dresden Unit 1 is a General Electric Boiling Water Reactor with a design net electrical output rating of 200 megawatts electrical (MWe). The unit is being decommissioned with all nuclear fuel removed from the reactor vessel. Therefore, no Unit 1 operating data is provided in this report.

Dresden Units 2 and 3 are General Electric Boiling Water Reactors; each licensed at 2527 megawatts thermal. The gross outputs of Units 2 and 3 are 832 and 834 megawatts electrical, respectively, with design net electrical output ratings of 794 MWe each. The commercial service date for Unit 2 is 11 August 1970 and 30 October 1971 for Unit 3.

Waste heat is rejected to a man-made cooling lake using the Kankakee River for make-up and the Illinois River for blowdown.

The Architect-Engineer for Dresden Units 2 and 3 was Sargent and Lundy of Chicago, Illinois.

Gary Abrell of Dresden Regulatory Assurance Staff compiled this report for February 1999, telephone number (815) 942-2920, extension 2959, 3

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2.0

SUMMARY

OF OFERATING EXPERIENCE FOR FEBRUARY 1999 2.1 UNIT 2 MONTHLY OPERATING EXPERIENCE

SUMMARY

Unit 2 operated throughout the period at full power except for short periods for surveillance and maintenance.

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1 2.0

SUMMARY

OF OPERATING EXPERIENCE FOR FEBRUARY 1999 2.2 UNIT 3 MONTHLY OPERATING EXPERIENCE

SUMMARY

Unit 3 began the period in refueling outage D3R15.

Following completion of scheduled work activities and the vessel hydrostatic test, the reactor start-up began at 0753 on February 24, 1999. The reactor was critical at 1228 that day. At 2118 on February 24, 1999, electromatic relief valves were tested ratisfactorily in accordance with DOS 250-04. The turbine roll began at 1246 on February 25 to support various modification tests.

The unit was synchronized to the grid at 2143 on that day to complete the refueling outage in 26 days. The generator was separated from the grid at 0337 on February 26 for turbine overspeed and other planned tests. The generator was  ;

synchronized to the grid again at 0611 that day.

The unit continued power ascension testing for the I remainder of the period.

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l 3.0 OPERATING DATA STATISTICS 3.1 OPERATING DATA REPORT - DRESDEN UNIT TWO DOCKET No. 050-237 DATE March 4, 1999 I

COMPLETED BY Gary Abrell TELEPHONE (815) 942-2920 OPERATING STATUS

1. REPORTING PERIOD: February 1999

2. CURRENTLY AUTHORIZED POWER LEVEL (MWth): 2,527 MAXIMUM DEPENDABLE CAPACITY (MWe NET): 772 DESIGN ELECTRICAL RATING (MWe Net): 794

3. POWER LEVEL TO WHICH RESTRICTED (MWe Net) : No restrictions

4. REASONS FOR RESTRICTIONS (IF ANY): See Section 2.1 of this report.

REPORTING PERIOD DATA l PARAMETER THIS MONTH YEAR TO DATE CUMULATIVE 5 HOURS IN PERIOD 672 1,41f 250,272 6 TIME REACTOR CRITICAL 672 1,41f 184,037 7 TIME REACTOR FESERVE SHITTDOWN (Hours) C C L 8 TIME GENERATOR ON-LINE (Hours) 672 1,41C 175,691 9 TIME c:NERATOR RESERVE SHUTDOWN (Hc,urs) C C 4 10 THERMAL ENERGY GENERATED (WHt Gross) 1,690,527 3,559,811 371,483,87(

11 ELECTRICAL ENERGY GENERATED (HWEHe Gross) 557,893 1,173,939 118,805,675 12 ELECTRICAL TM.RGY GENERATED (MNEHe Net) 537,628 1,128,33C 112,441,369 13 REACTOR SERVICE 3 ACTOR (%) 100.01 100.01 73.51 14 REACTOR AVAILABILITY FACTOR (%) 100.01 100.01 73.51 15 GENERATOR SERVICE FACTOR (%) 100.01 100.01 70.21 16 GENERATOR AVAILABLILITY FACTOR (%) 100.01 100.0i 70.21 17 CAPACITY FACTOR (Using ED Net) (%) 103.61 103.21 58.21 18 CAPACITY FACTOR (Using DER Net) (%) 100.8% 100.41 56.61 19] EDRCED OUTAGE FACTOR (%) 0% 0.01 12.31 6

3.0 OPERATING DATA STATISTICS 3.2 OPERATING DATA REPORT - DRESDEN UNIT THREE j l

DOCKET No. 050-249 I DATE March 4, 1999 COMPLETED BY G. Abrell TELEPHONE (815) 942-2920 OPERATING STATUS

1. REPORTING PERIOD: Fearuary 1999

2. CURRENTLY AUTHORIZED POWER LEVEL (MWth): 2,527 MAXIMUM DEPENDABLE CAPACITY (MWe Net): 773 DESIGN ELECTRICAL RATING (MWe Net): 794

3. POWER LEVEL TO WHICH RESTRICTED: No restriction

4. REASONS FOR RESTRICTIONS (IF ANY): See Section 2.2 of this report.

REPORTING PERIOD DATA PARAMETER ' THIS MONTH YEAR TO DATE CUMULATIVE 5 HOURS IN PERIOD 672 1,41f 239,592 6 TIME REACTOR CRITICAL 108 805 170,5E 7 fIME REACTOR RESERVE SHUTDOWN (Hours) O C C i 1

8 TIME GENERATOR ON-LINE (Hours) 74 771 163,35 9 TIME GENERAMR RESERVE SHUTDOWN (Hours) C C 1 10 THERMAL ENERGY GENERATED (MWHt Gross) 88607 1822343 345,074,766 11 ELECTRICAL ENERGY GENERATED (MNEHe Gross) 27,518 595,837 110,574,64C 12 ELECTRICAL ENERGY GENERATED (MNEHe Net) 21,998 569,235 104,910,743 13 REACTOR SERVICE FACTOR (%) 16.0% 56.81 73.44 14 REACIOR AVAILABILITY FACTOR (%) 16.01 56.81 73.41 15 GENERATOR SERVICE FACTOR (%) 11.01 54.41 70.01

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16 GENERATOR AVAILABLILITY FACTOR (%) 11.0% 54.41 70.01 17 CAPACITY FACTOR (Using MCD Net) (%) 4.2% 52.11 57.91 1C CAPACITY FACTOR (Using DER Net) (%) 4.1% 50.61 56.34 19 mRCED OUTAGE FACTOR (%) 01 0.01 12.4%

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e 3 UNIT 2 SHUTDOWNS REPORT MONTH OF FEBRUARY 1999 NO DATE TYPE DURATION REASON METHOD OF ' CORRECTIVE (1) (HOURS)* (2) SHUTTING ACTIONS /

DOWN COMMENTS REACTOR (3) i _

Year-to-date forced outage hours = 0 ,

Cumulative forced outage hours = 24691 TABLE KEY:

(1) (3)

F: Forced Method: l S: Scheduled 1. Manual i

2. Manual Scram (2) Reason: 3. Automatic Scram j A Equipment Failure (Explain) 4. Other (Explain)

B Maintenance or Test 5. Load Reduction C Refueling D Regulatory Restriction E Operator Training &

Licensing Exam F Administrc.tive G Operational Error H Other ( Expla.in )

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I 3.4 UNIT 3 SHUTDOWNS REPORT MONTH FEBRUARY 1999 NO DATE TYPE (1) DURATION REASCN(2n METHOD OF CORRECTIVE th00RS)* SHUTTING ACTIONS /

DOWN COMMENTS PEACTOR (3) 1 990130 s 598 C 5, 2 D3R15 w

Year-to-date forced outage hours = 0 Cumulative forced outage hours = 26,212 TABLE KEY:

(1) (3)

F: Forced Method:

S: Scheduled 1. Manual

2. Manual Scram (2) 3. Automatic Scram Reason: 4. Other (Explain)

A Equipment Failure 5. Load Reduction (Explain; B Maintenance or Test C Refueling D Regulatory Restriction  ;

E Operator Training &

Licensing Exam l F Administrative G Operational Error H Other (Explain) i l

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e s 4.O UNIQUE REPORTING REQUIREMENTS 4.1 MAIN STEAM RELIEF AND/OR SAFETY VALVE OPERATIONS -

UNIT 2 - NONE UNIT 3 - Electromatic relief valves tested in accordance with DOS 250-04 on February 24, 1999 as part of start-up testing upon completion of D3R15.

4.2 Technical Specification Amendments Amendment 170 and 165 for Dresden Unit 2 and Unit 3 respectively was issued on February 8, 1999.

The amendment relocated the requirement to remove the Reactor Prctection System shorting links under certain conditions to the UFSAR from the technical specifications. Removal of the shorting links enables a non-coincidence high flux scram from any neutron-monitoring instrument Amendments 171 and 166 for Dresden Unit 2 and Unit i 3 respectively was issued on February 16, 1999. l The amendment revised the Technical Specifications ]

to reflect the use of Siemans Power Corporation l ATRIUM-98 fuel.

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