ML20202F783

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Monthly Operating Repts for Jan 1998 for Dresden Nuclear Power Station
ML20202F783
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 01/31/1998
From: Abrell G, Heffley J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-97-02, GL-97-2, JMHLTR:#98-0041, JMHLTR:#98-41, NUDOCS 9802190296
Download: ML20202F783 (11)


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Commonu calth I Alivin Cornjiany

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  • Drexten Generating Station 6W North Drtvlen Rn,d

. Morrn.11. 60440 let 815-912 2920 February 6,1998 JMllLTR: #98 0041 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Monthly Operating Data Report for January 1998 Dresden Nuclear Power 5tation Commonwealth Edison Company Docket Nos.50-010,50-237, and 50-249 Enclosed is the Dresden Nuclear Power Station Monti? <*erating Summary Report for January 1998.

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l This information is supplied to your oflice as required by Technical Specification 6.9. A.5, l

in accordance with the instructions set forth in Regulatory Guide 1,16. and Generic Letter 97-02. ]

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Sincerely, l

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@hNhifh 6 Vice Pre. ' dent Dresden Static Enclosure cc: NRC Region 111 Oflice Illinois Dept. of Nuclear Safety, State ofIllinois NRC Senior Resident inspector, Dresden Station UDI, Inc. - Washington, DC File / Numerical ,g

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MONTHLY NRC SUNNARY OF OPERATING EXPERIENCE, PER REGUIATORY GUIDE 1.16 FOR DRESDEN-NUCLEAR POWER STATION CO N NWEALTH EDISON COMPANY FOR JANUARY 1998 UNIT DOCKET LICENSE' 1 050-010 DPR-2 2' 050-237 DPR-19 3 050-249 DPR-25

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TABLE OF CONTENTS-JANUARY 1998 NRC REPORT-1.0 Introduction  !

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2.0 Sumary of Operating Experie~nce 2.1 Unit 2 Monthly Operating Experience Summary.-

2.2 Unit:3 Monthly Operating Experience Summary.-

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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 2

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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 et 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-aas Sargent and Lundy of Chicago, Illinois.

This report for JANUARY 1998, was compiled by Gary A.

Abrell of Dresden Regulatory Assurance Staff, telephone number (815) 942-2920, extension 3749.

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2.0

SUMMARY

OF OPERATING EXPERIENCE FOR JANUARY 1998 2.1 UNIT 2 MONTHLY OPERATING EXPERIENCE

SUMMARY

Unit 2 began the period near full power. At 1904 on January 13, 1998 an automatic scram occurred from turbine stop valve closure. During an instrument surveillance procedure, a pressure transient in the instrument sensing line caused the scram.

Following minor maintenance activity, the unit was started up at 0920 on January 17, 1998, and achieved criticality at 1208 on January 17. The unit was placed on system at 0510 on January 18, and began load increase. The unit reached full power on January 23, 1998.

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2.0

SUMMARY

OF OPERATING EXPERIENCE FOR JANUARY 1998 2.2 UNIT 3 MONTHLY OPERATING EXPERIENCE

SUMMARY

Unit 3 began the period near full power and operated at that level throughout the period except for brief load reductions for maintenance and surveillance testing.

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s 3.0 OPERATING DATA STATISTICS 3.1 OPERATING DATA REPORT - DRESDEN UNIT TWO DOCKET No. 050-237

, DATE February,-1998 COMPLETED BY G. A. ABRELL TELEPHONE . ( 815) 942-2920 OPERATING STATUS

1. REPOP. TING PERIOD: JANUARY 1998
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 4

this report.

4 l REPORTING PERIOD DATA PARAMETER THIS MONTH YEAR TO DATE CUMULATIVE 5 HOURS IN PERIOD 744 744 240,H4t 6 TIE REACTOR CRITICAL 655 655 175,b63 7 TIM REACTOR RESERVE SHU1DOWN (Hours) 0 L (

8 TIME GENERATOR ON-LINE (Hours) ti3 9 b3' 167,393 9 TIME GENERATOR RESERVE SHUTDOWN (Hours) 0 0 1 l 10 THERMAL ENERGY GENERATED (MWHt Gross) 1,4 % ,592 1,4343,592 351,200,01E 11 ELEcrRICAL ENERuY GENERATED OefEHe Gross) 4bH,189 4 t,8,18 4 112,202,024 12 ELECTRICAL ENERGY GENERATED (MWEHe Net) 447,393 447,393 106,127,5bF 13 REACTOR SERVICE FACTOR (4) HH.0% 88.0% 72.94 14 REACTOR AVAILABILITY FACTOR (%) 68.04 ti 8 . 0 % 72.9V 15 GENERATOR SERVICE FACTOR (4) 85.9% 85.91 69.5%

16 GENERATOR AVAILABLILITY FACTOR (4) 85.9% H5.9% b9.54 17 CAPACITY FACTOR (Using MCD Net) (4) 77.9% 77.9% 57.1%

18 CAPACITY FACTOR (Using DER Net) (%) 75.7% 75.7% b5.5%

19 FORCED OUTAGE FACTOR (4) 141 -14.1% 12.84 1

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3.0 OPERATING DATA STATISTICS 3.2 OPERATING DATA REPORT - DRESDEN UNIT THREE DOCKET'No. 050-249

-DATE February 4,1998 COMPLETED BY G. A. ABRELL

~ TELEPHONE (815) 942-2920 OPERATING STATUS

1. REPORTING PERIOD: JANUARY 1998
2. CURRENTLY AUTHORIZED POWER' LEVEL (MWth): 2,527 MAXIMUM DEPENDABLE CAPACITY (MWe Net) : 773 DESIGN ELECTRICAL RATING (MWe Net): 794 l 3. POWER LEVEL TO WHICH RESTRICTED: No restriction l 4 '. REASONS FOR RESTRICTIONS - (IF ANY) : See Section-2.2 of this report.

I REPORTING PERIOD DATA PARAMETER THIS MONTH YEAR TO DATE CUMULATIVE S HOURS IN PERIOD 144 744 23 0, l e(

6 tim REACTOR CRITICAL 744 744 lez,cet 7 TIM REACTOR RE8ERVE SHUTDOWN (Hours) e t. 0 8 TI M GRE RATOR ON-LINE (Hours) 144 144 ISS, lee

~9, tim OERRATOR RESERVE SHU1DOWN (Hours) L L t-10 THFJNAL ERRGY GENERATED (MWHt Gross) 1,H41,149 1,841,149 .s.' S,0 4 6,7 2; 11 EI2CTRICAL RNERGY GEMRATED (MIEMe Gross) 605,331 605,331 10 4, o 9 3,4 9L 12 ELECTRICAL ER AGY GEERATED (HNEHe Net) SH2,2HS $s2,285  % , e H 9,20 e 13 REACTOR SERVICE FACTOR (t) leo,oa 10o,oa 7o,7g 14 REACTOR AVAIIABILITY FACTOR (4) 100.0n 100.0% Jo.7%

15 GENERATOR SERVICE FACTOR (t) loo,og loo,og e],4g 16 GENERATOR AVAILABLILITY FACTOR (t) 100,03 100,04 e1,4g 17 CAPACITY FACTOR (Using MCD Net) (t) 101.4% lol.4h SS.S*

18 CAPACITY FACTOR Nsing DER Net) (t) -%,ew qu,et 54,e1 19 (FORCED OUTAGE FACTOR (t) o,oi I o,0$ t4,3g 7

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3.3 UNIT 2 SHUTDOWNS REPORT MONTH OF JANUARY 1998 NO DATE TYPE DURATION REASON METHOD CORRECTIVE (1) (HOURS)* (2)- OF ACTIONS /

SHUTTING CCittENTS DOWN REACTOR (3) 1 980113 F 105 G 3 LER 9P ,002 Year-to-date forced outage hours = 105 Cumulative forced outage hours = 24533 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 (Explain) 5. Load Reduction B Maintenance or Test C Refueling D Regulatory Restriction E Operator Training &

Licensing Exam F Administrative G Operational Error H Other (Explain) 8 L:\8 40\0101\M1'JC\90\08020301.GA

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l 3.4 UNIT 3 SHUTDOWNS REPORT MONTH JANUARY 1998 11 0 DATE TYi'E ll) rusAthw FI.As w(2) METWC OF CORPICTIVE (WW.f PS)

  • SHUTTING ACTidNS/

S HN CWNENTS PI. ACTOR (3) i Year-to-date forced outage hours = 0 Cumulative forced outage hours = 25,940 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 F Administrative G Operational Error H Other (Explain) 9 Lt \8100\9 301\ MISC \Hi\#802C501.GA

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UNIQpE REPORTING REQUIREMENTS 4.1 MAIN STEAM RELIEF AND/OR SAFETY VALVE OPERATIONS - UNIT 2 AND UNIT 3 None a

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