ML20151Y271

Monthly Operating Repts for Aug 1998 for Dresden Nuclear Power Station,Units 1,2 & 3.With

ML20151Y271
Person / Time
Site:	Dresden
Issue date:	08/31/1998
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:#98-0243, JMHLTR:#98-243, NUDOCS 9809180177
Download: ML20151Y271 (11)

Text

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Commonw calth lilison Company

• i Drexicn Generating StJtiott J.

' 6MH) Nortti Dirxlen Road yo7,,s u n ivi Tel31S W J-2920 September 8,1998 JMHLTR: #98-0243 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Monthly Operating Data Report for August 1998 Dresden Nuclear Power Station n

Commonwealth Edison Company Docket Nos.50-010,50-237, and 50-249 Enclosed is the Dresden Nuclear Power Station Monthly Operating Summary Report for August 1998.

This informatio: 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.

Sincer ly, i

1 a

mo J. M. He ey

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Site Vice President Dresden Station Enclosure cc:

NRC Region III Office Illinois Dept. of Nuclear Safety, State ofIllinois NRC Senior Resident Inspector, Dresden Station UDI, Inc. - Washington, DC File / Numerical 9809100177 980631 PDR ADOCK 05000010 R

PDR tnnpon 4 vt/cvU A t'nkom Company

i MONTHLY NRC

SUMMARY

OF OPERATING EXPERIENCE, PER REGULATORY GUIDE 1.16 FOR 1

DRESDEN NUCLEAR POWER STATION 1

1 COMMONWEALTH EDISON COMPANY FOR AUGUST 1998 UNIT DOCKET LICENSE 1

050-010 DPR-2 2

050-237 DPR-19 3

050-249 DPR-25 L: 8360\\8301\\ misc \\98\\98050501.GA 1

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TABLE OF CONTENTS AUGUST 1998 NRC REPORT 1

1.0 Introduction 1

3.0 Summary of Operating Experience 2.1 Unit 2 Monthly Operating Experience Summary.

2.2 Unit 3 Monthly Operating Experience Summary.

1 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 -

j Unit 2 and Unit 3 4.2 Technical Specification Amendments L: 8360\\8301\\ misc \\98\\98050501,GA 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.

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

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2.0

SUMMARY

OF OPERATING EXPERIENCE FOR. August 1998 2.1 UNIT 2 MONTHLY OPERATING EXPERIENCE SUMt1ARY Unit 2 operated throughout the period at full power except for the D2F34 forced outage to resolve intermittent grounding problems plaguing the Unit 2 generator.

i Unit 2 was separated from the system at 0051 on August 8 and returned to the system at 0256 on August 9, 1998.

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Unit 2 reached full power at 0553 on August 13, 1998.

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i 2.0

SUMMARY

OF OPERATING EXPERIENCE FOR August 1998

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l 2.2 UNIT 3 MONTHLY OPERATING EXPERIENCE

SUMMARY

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

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' 3 '. O OPERATING DAT7' STATISTICS 3.1 OPERATINt >ATA REPORT - DRESDEN UNIT TWO DOCKET No.

050-237 DATE September 3, 1998 i

i COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 OPERATING STATUS 1.

REPORTING PERIOD: August 1998 2.

CURRENTLY AUTHORIZED POWER LEVEL (MWth): 2,527 MAXIMUM DEPENDABLE CAPACITY (MWe NET): 772

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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 PERK)D DATA PARAMETER THIS MONTH YEAR TO DATE CUMULATIVE 5 HOURS IN PERIOD 744 5,831 245,927 6 T M REACTTR CRITICAL 744 4,684 179,692 7 TM REACTOR RESERVE SIRTIDONN (Hours)

O C

0 8 TM GENERATOR CN-LINE (Hours) 719 4,567 171,321 9 T M GENERATOR RESERVE SHUTDONN (Hours) 0 3

4 10 THEISAL ENERGY GENERATED (14fHt Gross) 1,714,57E 10,866,857 360,630,280 11 EIECTRICAL ENERQf GENERATED (lefEHe Gross) 548,427 3,519,367 115,253,202 12 ELECTRICAL ENERGY GENERATED (14fEHe Net) 523,733 3,356,439 109,036,614 13 REACTOR SERVICE FACTOR (%)

100.0%

80.3%

73.14 14 REACTOR AVAIIABILITY FACTOR (%)

100.01 80.3%

73.1%

15 GENERATOR SERVICE FACTOR (%)

96.6%

78.3%

69.74 16 GENERA 20R AVAIIABI LITY FACTOR (%)

96.6V 78.4%

69.74 17 CAPACITY FACTOR (Using ICD Net) (%)

91.21 74.6%

57.44 18 CAPACITY FAC'ITE (Using DER Net) (%)

88.7%

72.5%

55.84 19 FORCED OUTAGE FACTOR (%)

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

DOCKET No.

050-249 DATE' September 3,1998 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 OPERATING STATUS 1.

REPORTING PERIOD: AUGUST 1998 2.

CURRENTLY AUTHORIZED POWER LEVEL (MWth): 2,527 MAXIMUM DEPENDABLE CAPACITY (MWe Net): 773 DESIGN ELECTRICAL RATING (MWe Net): 794 3.

PCWER LEVEL TO WHICH RESTRICTED: No restriction 4.

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

REPORTING PERIOD DATA PARANETER THIS MONTH YEAR TO DAT CUMULATIVE 5

HOURS IN PERIOD 744 5,831 235,247 6

TDE REACTOR CRITICAL 744 5,325 167,266 7

TIME REACTOR RESERVE SHUTDOWN (Hours) 0 0

0 8

TDE GENERATOR CN-LINE (Hours) 744 5,22E 159,652 9

TDE GENERATOR RESERVE SHUTDOWN (Hours) 0 1

1 10 THERMAL ENERGY GENERATED ()SfHt Gross) 1,861,708 12,747,829 335,952,802 11 EIJ:CHICAL ENERGY GE:NERATED 04fEHe Gross) 598,651 4,124,023 107,612,182 12 ELECTRICAL ENERGY GENERATED ()SfEHe Net) 574,563 3,959,565 102,066,482 13 -

REACTOR SERVICE FACTOR (%)

100.0%

91.3%

71.14 14 REACTOR AVAIIABILITY FACTOR (%)

100.0%

91.3%

71.14 15 GENERATOR SERVICE FACTOR (%)

100.0%

89.7%

67.94 16 GENERATOR AVAIIABLILITY FACTOR (%)

100.01 89.7%

67.94 17 CAPACITY FACTOR (Using 1(:D Net) (%)

100.0%

88.01 56.24 18 CAPACITY FACTOR (Using DER Net) (%)

97.3%

85.5?

54.6%

19 EVRCED OUTAGE FACTOR (%)

0.04 4.91 14.14 j

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3.3-UNIT 2 SHUTDOWNS REPORT MONTH OF AUGUST 1998 NO 'DATE TYPE DURATION REAECT METHOD OF CORRECTIVE (1)

(HOURS)*.

(2)

SHUTTING ACTIONS /

DOWN CCN!OITS REACTOR (3) 5 980808 1

25 A

5 See Sec. 2.1 l'

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u Year-to-date forced outage hours =' 263 Cumulative forced outage hours = 24691 TABLE KEY:

(1).

(3)

F:

Forced Method:

S:

Scheduled 1.

Manual 2.

Manual Scram (2)

Reason:

3.

Automatic Scram

- A Equipment Failure (Explain) 4.

Other (Explain)

B Maintenance or Test 5.

Load Reduction C

. Refueling D

Regulatory Restriction l

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Operator Training &

l' Licensing Exam F

Administrative G

Operational Error l

H Other (Explain) l 1

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3.4 UNIT 3 SHUTDOWNS REPORT MONTH AUGUST 1998 O

DATE TYPE (1)

DURATION REASON (2)

METHOD OF CORRECTIVE (HOURS)*

SHUTTING ACTIONa/

DOWN COMMENTS REACTOR (3) 4-Year-to-date forced outage hours = 272 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 F

Administrative G

Operational Error H

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

UNIT 2.

None 4.2 Technical Specification Amendments

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Amendment 163 to DPR-25 for Dresden U-3 was issued on August 7, 1998.

It revises Technical Specification 4.6.E to allow a one-time extension of the 40-month i

surveillance interval requirement to set pressure test or replace all main steam safety' valves (MSSVs) to a maximum interval of 6-0 months as currently allowed by the American Society of' Mechanical Engineers Boiler and Pressure Vessel Code.

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