ML20236M604

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Monthly Operating Repts for June 1998 for Dresden Nuclear Power Station,Units 1,2 & 3
ML20236M604
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 06/30/1998
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:#98-0191, JMHLTR:#98-191, NUDOCS 9807140154
Download: ML20236M604 (11)


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+ ' Commonw ealth I dison Company j

. Drcsden bencrating Statson MOO North Drr%1cn Ro.ed Morris, IL 00 650 Tel HI 49 s.' 2920 July 8,1998 JMHLTR: #98-0191 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Monthly Operating Data Report for June 1998 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 June 1998.

This information is supplied to your oflice 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.

Sincerely, i

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J, M. HefIle Site Vice President Dresden Station Enclosure l

l' cc: NRC Region III Office Illinois Dept. of Nuclear Safety, State ofIllinois l NRC Senior Resident Inspector, Dresden Station j UDI, Inc. - Washington, DC i File / Numerical l

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MONTHLY NRC

SUMMARY

OF OPERATING EXPERIENCE, PER REGULATORY GUIDE 1.16 FOR DRESDEN NUCLEAR POWER STATION COMMONWEALTH EDISON COMPANY FOR JUNE 1998 UNIT DOCKET LICENSE 1 050-010 DPR-2 2 050-237 DPR-19 3 050-249 DPR-25 i

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1 TABLE OF CONTENTS JUNE 1998 NRC REPORT 1.0 ' Introduction 2.0 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 i 3.3 Unit 2 Shutdowns i 3.4 Unit 3 Shutdowns 4.0 Uniqua-Reporting Requirements 4.1 Main Steam Relief and/or Safety Valve Operations -

Unit 2 and Unit 3 4.2. Technical Specification Amendments j.

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. . j 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 (bme) . The unit is being I 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. I Waste heat is rejected to a man-made cooling lake using l the Kankakee River for make-up and the Illinois River for blowdown. l The Architect-Engineer for Dresden Units 2 and 3 was

Sargent and Lundy of Chicago, Illinois.

! Gary A. Abrell of Dresden Regulatory Assurance Staff compiled this report for JUNF. 1998, telephone number (815) 942-2920, extension 3749.

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2.0

SUMMARY

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

SUMMARY

Unit 2 began the period operating at full power except for brief periods for minor maintenance and-surveillance testing.

On June 20, 1998 at 1206, the reactor shutdown automatically as the result of low electro-hydraulic control (EHC) pressure while paralleling EHC Pumps.

A reactor startup commenced at 0219 on June 22, 1998, and the reactor was critical at 0607 that day. The unit was placed on system at 2208 that evening. The unit began a load increase and reached full power at 0432 on June 24, 1998.

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SUMMARY

OF OPERATING EXPERIENCE FOR JUNE 1998 2.2 UNIT 3 MONTHLY OPEPATING EXPERIENCE

SUMMARY

Unit 3 operated throughout the period at full power except for short periods for surveillance l and maintenance.

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

, DATE July 6,1998 L

COMPLETED BY- G. A. ABRELL TELEPHONE (815) 942-2920 OPERATING STATUS

1. REPORTING PERIOD: JUNE 1998 l 2. CURRENTLY AUTHORIZED POWER LEVEL (MWth): 2,527 i

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l' 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.

i REPORTING PEROD DATA

! PARAktit:M TMS MONTH YEARTO DATE CLMAATNE 1 5 100RS IN PERIOD 720 4,343 244,439 6 TDE arJcitR CRITICAL 678 3,196 178,204 '

7 TDE REACER RESERVE SHEMDOHN (ikmrs) 0 0 0 8 TDE G!2ERAKR CN-LINE (!kurs) 663 3,104 169,856 9 TDE GEtERAITR RESERVE SHLMDOWN (Hours) 0 3 4 10 THERAL EIERGY G!2 ERA 2ED 06Eit Gross) 1,619,001 7,305,870 357,069,293 11 zzaCTRICAL ENERGY GBODUWED Osane Gross) 523,057 2,370,234 114,104,069 12 EIJ!lC2RICAL EIERGY GllNERA2ED 04EHe Net) 499,425 2,258,294 107,938,469 13 REACER SERVI 3 FACITR (%) 94.21 73.69 72.94 14 REACER AVAILABILITY FACITR (%) 94.24 73.6% 72.94 15 GI: TERA 2TR SERVIG TACTOP, (t) 92.1% 71.5% 69.5t 16 GDERA2tR AVAIIABLILITY FACKR (%) 92.1V 71.5V 69.54 17 CAPACITY FACER (Using ICD Net) (%) 89.94 67.4% 57.24 18 CAPACITY FACITR (Using DER Net) (%) 87.4% 65.5% 55.64 19 ICRQ!D CUTAGE FACITR (%) 81 7.1% 12.74 l

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3.0 OPERATING DATA STATISTICS

-3.2 OPERATING DATA REPORT - DRESDEN UNIT THREE DOCKET No. 050-249 DATE July 6,1998 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 OPEPATING STATUS

1. REPORTING PERIOD: JUNE 1998
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 CUMULATIVE DATE HOURS IN PERIOD 720 4,343 233,759 TIME REACTOR CRITICAL 720 3,837 165,778 TIME REACTOR RESERVE SHUTDOWN (Hours) 0 0 0 TIME GENERATOR ON-LINE (Hours) 720 3,740 158,164 TIME GENERATOR RESERVE SHUTDOWN (Hours) 0 1 1 THERMAL ENERGY GENERATED (MNHt Gross) 1,789,769 9,032,233 332,237,206 ELECTRICAL ENERGY GENERATED (NNHe Gross) 577,567 2,929,763 106,417,922 ELECTRICAL ENERGY GENERATED (WWHe Net) 554,414 2,813,105 100,920,022 REACTOR SERVICE FACTOR (%) 100.0t 88.3t 70.9t REACTOR AVAILABILITY FACTOR (%) 100.0t 88.31 70.91 GENERATOR SERVICE FACTOR (%) 100.0t 86.1% 67.7t GENERAT7R AVAILABILITY FACTOR (%) 100.0t 86.1t 67.7e CAPACITY FACTOR (Using MCD Net) (t) 99.7Y 83.9% 55.9V CAPACITY FACTOR (Using DER Net) (%) 97.0% 81.6Y 54.4t FORCED OUTAGE FACTOR (%) 0.0t 6.8t 14.2e i

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. . i 3.3 UNIT 2 SHUTDOWNS REPORT MONTH OF JUNE 1998 No DATE TYPE DURATION REASON METHOD OF cokkECTIVE (1) (HOURS)* (2) . JTTING REACTOR (3) 4 980620 F 57 A 3 LER 2-98-10 l

Year-to-date forced outage hours = 238 Cumulative forced outage hours = 24,666 TABLE KEY:

(1). (3)

F: Forced Method:

S: Scheduled 1. Manual l

2. Manual Scram (2) Reason: 3. Automatic Scram J

! A Equipment Failure (Explain) 4. Other (Explain) i B Maintenance or Test 5. Load Reduction C Refueling D Regulatory Restriction E Operator Training &

Licensing Exam F Administrative G Operational Error l H Other (Explain) l 4

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3.4 , UNIT 3 SHUTDOWNS REPORT MONTH JUNE 1998 NO DATE TYPE (1) DURATION REASON (2) METHOD OF CORRECTIVE (HOURS)* SHUTTING ACTIONS /

DOWN COMMENTS REACTOR (3)

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Year-to-date forced outage hours = 272 Cumulative forced outage hours = 26,212 l TABLE KEY:

(1) (3) l

! F: Forced Method:

Scheduled 1. Manual
2. Manual Scram I (2) 3. Automatic Scram Reason: 4. Other (Explain)

! A Equipment Failure 5. Load Reduction L

(Explain)

B Maintenance or Test C Refueling D Regulatory Restriction E Operator Training &

Licensing Exam F Admini~strative G Operational Error H Other (Explain) l l

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i i 4.O UNIQUE REPORTING REQUIREMENTS 4.1 MAIN STEAM RELIEF AND/OR SAFETY VALVE OPERATIONS - J' UNIT 2.

None 4.2 Technical Specification Amendments =

None I

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