ML20133K418

Monthly Operating Repts for Dec 1996 for Dresden Nuclear Power Station Units 1,2 & 3

ML20133K418
Person / Time
Site:	Dresden
Issue date:	12/31/1996
From:	Abrell G, Jamila Perry COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
JSPLTR-97-0004, JSPLTR-97-4, NUDOCS 9701210220
Download: ML20133K418 (13)

Text

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Commonw ealtli I dison Comp.in)

, Dresden Generating Mation

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. 6500 North DrrrJen Ro.id Storris. IL (O 150 Tcl H15 ') U-2')20 l

January 10,1997 JSPLTR 97-0004 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Monthly Operating Data Report for December 1996 Dresden Nuclear Power Station Commonwealth Edison Company Docket Nos.50-010,50-237, and 50-249 Gentlemen:

Enclosed is the Dresden Nuclear Power Station Monthly Operating Summary Report for December 1996.

This information is supplied to your office as required by Technical Specification 6.6. A.3, in accordance with the instructions set forth in Regulatory Guide 1.16.

Sincerely, J. Stephen Perry Site Vice President Dresden Station Enclosure cc:

NRC Region III Office Illinois Dept. of Nuclear Safety, State ofIllinois NRC Senior Resident Inspector UDI, Inc. - Washington, DC File / Numerical t

q#/ e 9701210220 961231 PDR ADOCK 05000010 R

PDR A Unimm Company

MONTHLY NRC

SUMMARY

OF OPERATING EXPERIENCE, PER REGULATORY GUIDE 1.16 FOR DRESDEN NUCLEAR POWER STATION COMMONWEALTH EDISON COMPANY FOR December 1996 UNIT DOCKET L CENSE 1

050-010 DPR-2 2

050-237 DPR-19 3

050-249 DPR-25 l

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l TABLE OF CONTENTS December 1996 NRC REPORT i

1.0 Introduction 2.0 Summary of Operating Experience 2.1 Unit 2 Monthly Operating Experience Summary.

l 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 Average Daily Unit 2 Power Level 3.4 Average Daily Unit 3 Power Level 3.5 Unit 2 Shutdowns and Power Reductions 3.6 Unit 3 Shutdowns and Power Reductions 4.0 Unique Reporting Requireimr.t:s 4.1 Main Steam Relief and/or Safety Valve Operations -

Unit 2 and Unit 3 4.2 Off-Site Dose Calculation Manual Changes 4.3 Major Changes to the Radioactive Waste Treatment Systems 4.4 Failed Fuel Element Indications 4.4.1 Unit 2 4.4.2 Unit 3 5.0 Technical Specification Amendments 5.1 Amendments to Facility License or Technical Specifications 5.1.1 Unit 2 5.1.2 Unit 3 2

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1 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

• confluence of the Kankakee and Des Plaines Riveta, 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 retired in place with all nuclear fuel removed from the reacter 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

'srgent and Lundy of Chicago, Illinois.

This report for December 1996, was compiled by Gary A.

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

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l 2.0

SUMMARY

OF OPERATING EXPERIdNCE FOR December 1996 2.1 UNIT 2 MONTHLY OPERATING EXPERIENCE

SUMMARY

l Unit 2 was on system at the beginning of the period at 550 MWE as a result of a load reduction for condensate demineralizer work.

On December 2, 1996, load was increased from 0130 until 1548 when the unit was at full power.

At 1700 December 20, 1996 a load drop began for surveillance testing including monthly turbine valve testing. At 0415 on December 21, #1 turbine control valve failed closed during the testing.

The unit load was ramped down to approximately 300 MWE and remained at that load for the remainder of the period while trouble shooting the valve.

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3.0

SUMMARY

OF OPERATING EXPERIENCE FOR December 1996 2.2 UNIT 3 MONTHLY OPERATING EXPERIENCE

SUMMARY

Unit 3 was shutdown for the entire month for repairs to the 3B recirculating pump motor were made.

Numerous other outage tasks were conducted i

at this time.

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

050-237 DATE January 7,1997 i

COMPLETED BY G. A. ABRELL l

TELEPHONE (815) 942-2920 OPERATING STATUS 1.

REPORTING PERIOD:

December 1996 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 i

this report.

REPORTING PERIOD DATA PARAMETER THIS MONTH YEAR TO DATE CUMULATIVE

)

HOURS IN PERIOD 744 8,784 231,336 TIME REACTOR CRITICAL 744 4,030 167,162 TIME REACTOR RESERVE SHUTDOWN (Hours) 0 0

0 TIME GENERATOR ON-LINE (Hours) 744 3,733 159,015 TIME GENERATOR RESERVE SHUTDOWN (Hours) 0 0

1 THERMAL ENERGY GENERATED (MWHt Gross) 1,463,656 7,166,827 331,703,901 ELECTRICAL ENERGY GENERATED (MWEHe Gross) 471,294 2,269,932 105,897,936 ELECTRICAL ENERGY GENERATED (MWEHe Net) 451,971 2,132,020 100,101,729 REACTOR SERVICE FACTOR (%)

100.0%

45.9%

72.3%

REACTOR AVAILABILITY FACTOR (%)

100.0%

45.9%

72.3%

GENERATOR SERVICE FACTOR (%)

100.0%

42.51 68.]

GENERATOR AVAILABLILITY FACTOR (t) 100.0%

42.5%

68.7%

CAPACITY FACTOR (Using MCD Net) (%)

78.7%

31.4%

56.1%

CAPACITY FACTOR (Using DER Net) (t) 76.5%

30.6%

54.5%

FORCED OUTAGE FACTOR ft)

On 37.91 12.6%

20.

SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS: NONE 21.

IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A 6

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3.0 OPERATING DATA STATISTICS 1

l 3.2 OPERATING DATA REPORT - DRESDEN UNIT THREE DOCKET No.

050-249

^

DATE January 6,1997 l

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

1.

REPORTING PERIOD:

December 1996 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.

l PARAMETER THIS MONTH YEAR TO DATE CUMULATIVE HOURS IN PERIOD 744 8,784 220,656 TIME REACTOR CRITICAL 0

4,358 155,857 TIME REACTOR RESERVE SHUTDOWN (Hours) 0.0 0

0 TIME GENERATOR ON-LINE (Hours) 0.0 4,273 148,524 TIME GENERATOR RESERVE SHUTDOWN (Hours) 0.0 0

0 THERMAL ENERGY GENERATED (MWHt Gross) 0 9,508,540 310,212,477 ELECTRICAL ENERGY GENERATED (MWEHe Gross) 0 3,096,338 99,273,141 ELECTRICAL ENERGY GENERATED (MNEHe Net)

-5,952 2,941,524 94,082,501 REACTOR SERVICE FACTOR (%)

0.0%

49.6%

70.6%

REACTOR AVAILABILITY FACTOR (%)

0.0t 49.6%

70.6%

NurRATOR SERVICE FACTOR (%)

0.0%

48.6%

67.3%

GENERATOR AVAILABLILITY FACTOR (%)

0.0%

48.6%

67.3%

CAPACITY FACTOR (Using }CD Net) (%)

-1.0%

43.4%

55.2%

CAPACITY FACTOR (Using DER Net) (%)

-1.0%

42.2%

53.7%

FORCED OUTAGE FACTOR (%)

100.01 51.4%

14.4%

20.

SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS: 26 April 1997.

21.

IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: January 14, 1997.

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3.3 AVERAGE DAILY UNIT 2 POWER LEVEL DOCKET No. 050-237 j

UNIT Dresden 2 l

DATE January 6,1997 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 MONTH:

December-96 DRESDEN 2 DAY AVERAGE DAILY NET DAY AVERAGE DAILY NET POWER LEVEL (MWe)

POWER LEVEL (MWe) 1 530 17 792 i

2 707 18 791 3

791 19 792 4

796 20 778 1

5 796 21 495 6

796 22 286 7

795 23 285 8

784 24 285 9

795 25 288 j

10 796 26 289 11 796 27 290 12 769 28 288 13 793 29 289 14 792 30 289 15 782 31 287 16 791 (Note:

negative values represent station loads) l l

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i 3.4 AVERAGE DAILY UNIT 3 POWER LEVEL DOCKET No. 050-249 UNIT Dresden 3 DATE January 7, 1997 1

COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 MONTH:

December-96 DRESDEN 3 DAY AVERAGE DAILY NET DAY AVERAGE DAILY NET POWER LEVEL (MWe)

POWER LEVEL (MWe) 1

-8 17

-8 2

-8 18

-8 3

-8 19

-8 4

-8 20

-8 5

-8 21

-8 6

-8 22

-8 7

-8 23

-8 8

-8 24

-8 9

-8 25

-8 10

-8 26

-8 11

-8 27

-8 12

-8 28

-8 13

-8 29

-8 14

-8 30

-8 15

-8 31

-8 16

-8 (Note:

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3.5' UNIT 2 SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH OF December 1996 NO DATE TYPE DURATION REASON METHOD LICENSEE SYSTEM COMPO-CORREC-(1)

(HOURS)*

(2)

OF EVENT CODE (4)

NENT TIVE SHUTTING REPORT #

CODE ACTIONS /

DOWN (5)

COM-REACTOR MENTS (3) 9 961128 S

0 B

5 N/A N/A N/A 2.1 10 961220 s

O B/A 5

N/A N/A N/A 2.1 l

Year-to-date forced outage hours = 2,281 Cumulative forced outage hours = 22,935 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 (4)

D Regulatory Restriction Exhibit G Instruction for E

Operator Training &

Preparation of Data Entry Licensing Exam Sheets for Licensee Event F

Administrative Reports (LER) File G

Operational Error (NUREG-0161)

H Other (Explain)

(5)

Exhibit I Same Source as Above.

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l 3.6 UNIT 3 SHUTDOWNS AND POWER REDUCTIONS 4

REPORT MONTH December 1996 r

NO DATE T YPE(1)

DU W ION REASON (2)

METHOD OF LICENSEE SYSTE1 COMPONENT CORPIC.

(HOUM)

• SHUTTING EVENT CODE COEE (5)

TIVE 4

j DOWN REPORT f (4)

ACTIONS /

4 REACTOR COMMENTS (3) 4 961028 F

744 A

1 N/A AD MO 2.2 1

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i Year-to-date forced outage hours = 4,511

]

Cumulative forced outage hours =

25,076 a

TABLE KEY:

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(1)

(3) i F:

Forced Method:

a S:

Scheduled 1.

Manual 2.

Manual Scram (2) 3.

Automatic Scram j

Reason:

4.

Other (Explain)

A Equipment Failure 5.

Load Reduction j

(Explain)

{

B Maintenance or Test (4) j C

Refueling Exhibit G Instruction for D

Regulatory Restriction Preparation of Data Entry E

Operator Training &

Sheets for Licensee Event Licensing Exam Reports (LER) File j

F Administrative (NUREG-0161)

G Operational Error H

Other (Explain)

(5)

Exhibit I Same Source as Above.

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4.0 UNIQUE REPORTING REQUIstEMENTS 4.1 MAIN STEAM RELIEF AND/OR SAFETY VALVE OPERATIONS - UNIT 2 AND UNIT 3 None 4.2 OFF-SITE DOSE CALCULATION MANUAL (ODCM) CHANGES None 4.3 MAJOR CHANGES TO THE RADIOACTIVE WASTE TREATMENT SYSTEMS None 4.4 FAILED FUEL ELEMENT INDICATIONS 4.4.1 Unit 2 Unit 2 has no indications of fuel failures.

4.4.2 Unit 3 Unit 3 Previous operation indicated a single fuel rod failure.

5.0 TECHNICAL SPECIFICATION AMENDMENTS 5.1 Amendments to Facility License or Technical Specifications implemented during December 1996.

Amendments 150 and 145 to DPR 19 and DPR 25 respectively.

These amendments revised the control of torus water level from a maximum and minimum volume to water level from the bottom of the suppression pool.

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