ML20217H720

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Monthly Operating Repts for Sept 1997 for Dresden Nuclear Power Station,Units 1,2 & 3
ML20217H720
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 09/30/1997
From: Abrell G, Jamila Perry
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, JSPLTR-97-0174, JSPLTR-97-174, NUDOCS 9710170028
Download: ML20217H720 (11)


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Dresten Generating Mation 6Mm Worth Drexten Road Morris,11. 60 i%0 Tri HI 49 (2-2920 October 8,1997 JSPLTR 97-0174 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Monthly Operating Data Report for September 1997 Dresden Nuclear Power Station Commonwea!*h Edison Company Docket Nos.50-010,50-237, and 50-249 Enclosed is the Dresden Nuclear Power Station Monthly Operating Summary Report for September 1997.

This information is supplied to your ollice 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, J. tephen Perry Site Vice President l

Dresden Station

]L Enclosure cc:

NRC Region III Oflice Illinois Dept. of Nuclear Safety, State ofIllinois NRC Senior Resident inspector, Dresden Station UDI, Inc. - Washington, DC File / Numerical

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9710170028 970930 PDR ADOCK 05000010 R

PDR b h A Unicum Company

MONTHLY NRC SUt44ARY OF OPERATING EXPERIENCE, PER REGULATCRY GUIDE 1.16 FOR DRESDEN NUCLEAR POWER STATION COMMONWEALTH EDISON COMPANY FOR SEPTEMBER 1997 UNIT DOCKET LICENSE 1

050-010 DPR-2 2

050-237 DPR-19 3

050-249 DPR-25 1

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1 TABLE OF CONTENTS SEPTEMBER 1997 NRC REPORT 1.0 Introduction 2.0 Sununary 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 l

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luu 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.

This report for SEPTEMBER 1997, 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 SEPTEMBER 1997 2.1 UNIT 2 MONTHLY OPERATING EXPERIENCE

SUMMARY

Unit 2 operated near full power for the period except for short periods for maintenance and surveillance testing, c

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2.0

SUMMARY

OF OPERATING EXPERIENCE FOR SEPTEMBER 1997 2.2 UNIT 3 MONTHLY OPERATING EXPERIENCE

SUMMARY

Unit 3 operated near full power for the period except for short periods for maintenance and surveillance testing.

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

050-237 DATE OCTOBER 4, 1997 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 OPERATING STATUS 1.

REPORTING PERIOD:

SEPTEMBER 1997 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 A

this report.

REPORTING PERIOD DATA PARAMETER ITHIS MONTHIYEAR TO DATE' CUMULATIVE HOURS IN PERIOD 720 6,551 237,887 TIME REACTOR CRITICAL 720 5,716 172,878 TINE REACTOR RESERVE SHU'1IXMN (Hours) 0 0

0 TIME GENERATOR ON-LINE (Hours) 720 5,627 164,642 TIME GENERATOR RESERVE SHUTDOWN (Hours) 0 0

1 THERMAL ENERGY GENERATED (MWHt Gross) 1,745,883 13,157,439 344,861,340 ELECTRICALENERGYGENE]ATED (MWEHe Gross) 562,427 4,236,922 110,134,858 ELECTRICAL ENERGY GEh% RATED (MWEHe Net) 537,955 4,049,296 104,151,025 REACTOR SERVICE FACTOR (t) 100.04 87.3%

72.71 REACTOR AVAILABILITY FACTOR (t) 100.01 87.3%

72.7%

GENERATOR SERVICE FACTOR (t) 100.0%

85.9%

69.2%

GENERATOR AVAILABLILITY FACTOR (t) 100.05 85.9%

69.2s CAPACITY FACTOR (Using MCD Net) (t) 96.8%

80.1%

56.7%

CAPACITY FACTOR (Using DER Net) (t) 94.1t 77.8%

55.15 l FORCED OUTAGE FACTOR (t) 01 14.li 12.91 20.

Shutdowns scheduled over the next 6 months: none 21.

If shutdown at end of report period, estimated date startup: N/A 6

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1 3.0 OPERATING DATA STATISTICS 3.2 OPERATING DATA REPORT - DRESDEN UNIT THREE DOCKET No.

050-249 DATE OCTOBER 4, 1997 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 OPERATING STATUS 1.

REPORTING PERIOD:

SEPTEMBER 1997 2.

CURRENTLY AUTHORIZED POWER LEVEL (MWth):

2,527 MAXIMUM DEPENDABLE CAPACITY (MWe Net) :

773 DESIGN ELECTRICAL RATING (MWe Net):

794 3.

POWE4 LEVEL TO WHICH RESTRICTED: No restriction 4.

REAStIS FOR RESTRICTIONS (IF ANY):

See Section 2.2 of this report.

I REPORTING PERIOD DATA PARAMETER THIS MONTH YEAR TO DATE CUMULATIVE 5

HOURS IN PERIOD 72C 6,551 227.20i 6

TIME REACTOR CRITICAL

'12 C 3952 159,009 7

TIME REACTOR RESERVE SHUTDOWN (Hours)

O.c c

0 8

TIME GENERATOR ON-LINE (Hours) 7at 3,19 t 132,315; 9

TIME GENERATOR RESERVE SHUTDOWN (Hours)

O.C L

L 10 THERMAL ENERGY GENERATED (MWHt Gross) 1,/14,68:

1,954,68J 318,16i,1bl 11 ELECTRICAL ENERGY GENERATED (MHe Gross) bs0,02t 2,573,451 101,84c 5 %

12 ELECTRICAL ENERGY GENERATED (MWEHe Net) 557,458 2,446,943 96,b29,444 13 REACTOR SERVICE FACTOR (t) 100.0%

60.39

~10. 3 5 14 REACTOR AVAILABILITY FACTOR (t) 100.0t 60.36 70.39 15 GENERATOR SERVICE FACTOR (t)

  • .uu.0%

$7.9%

67.09 16 GENERATOR AVAILABLILITY FACTOR (t) 100.04 57.9%

67.01 17 CAPACITY FACTOR (Using MCD Net) (t) 100.34 48.4%

55.01 18 CAPACITY FACTOR (Using DER Net) (t) 97.Se 47.09 53.59 19 l FORCED OUTAGE FACTOR (t) 0.09' 16.79 14.59 20.

Shutoowns scheduled over the next 6 months: None 21.

If shutdown at end of report period, estimated date of startup: N/A 7

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3.3 UNIT 2 SHUTDOWNS REPORT MONTH OF SEPTEMBER 1997 NO DATE TYPE DURATION REASON METHOD CORRECTIVE (1)

(HOURS)*

(2)

OF ACTIONS /

SHUTTING COMMENTS DOWN REACTOR (3)

Year-to-date forced outage hours = 925 Cum. lative forced outage hours = 24,331 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 r

Administrative G

Operational Error H

Other (Explain) 8 LI N6 360\\ 0 301\\ MISC \\ 97 \\97100601.rA

,e-3.4 UNIT 3 SHUTDOWNS REPORT MONTH SEPTEMBER 1997 NO DATE TYPttl)

DURATION REASON (2)

METHOD OF CORRECTIVE (HOURS)

  • SHUTTING ACTIONS /

DChN CO@ TENTS REACTOR (3)

Year-to-date forced outage hours =

760

  • Cumulative forced outage hours =

25,836 *

  • Adjusted October 1997 to agree with official company Production Data Bank hours year-to-date.

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 l

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e 4.0 UNIQUE REPORTING REQUIREMENTS 4.1 MAIN STEAM RELIEF AND/OR SAFETY VALVE OPE 14ATIONS - UNIT 2 AND UNIT 3 None 10 L \\9360\\9301\\M15 \\97\\97100601.GA

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