ML20140D740

Monthly Operating Repts for May 1997 for Dresden Nuclear Power Station,Units 1,2 & 3

ML20140D740
Person / Time
Site:	Dresden
Issue date:	05/31/1997
From:	Abrell G COMMONWEALTH EDISON CO.
To:
Shared Package
ML20140D738	List: ML20140D734 ML20140D740 ML20140D746
References
NUDOCS 9706110076
Download: ML20140D740 (13)

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MONTHLY NRC i

SUt44ARY OF OPERATING EXPERIENCE, j

PER REGULATORY GUIDE 1.16 EVR DRESDEN NUCLEAR POWER STATION CCH40NWEALTH EDISON COMPANY l

FOR MAY 1997 l

UNIT DOCKET LICENSE 1

050-010 DPR-2 i

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2 050-237 DPR-19 t

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050-249 DPR-25 l

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9706110076 970606 PDR ADOCK 05000010 R

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J TABLE OF CONTENTS j

l MAY 1997 NRC REPORT I

1.0 Introduction i

2.0 Summary of Operating Experience I

2.1 Unit 2 Monthly Operating Experience Summary.

l 2.2 Unit 3 Monthly Operating Experience Summary.

j 3.0 Operating Data Statistics 3.1 Operating Data Report - Dresden Unit 2 3.2 Operating Data Report - Dresden Unit 3 l

3.3 Average Daily Unit 2 Power Level l

3.4 Average Daily Unit 3 Power Level l

3.5 Unit 2 Shutdowns and Power Reductions j

3.6 Unit 3 Shutdowns and Power Reductions 4.0 Unique Reporting Requirements i

1 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 l

5.1.1 Unit 2 5.1.2 Unit 3 l

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1.0 Introduction Dresden Nuclear Power Station is a three reactor generating facility owned and operated by the Comed

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Company of Chicago, Illinois.

Dresden Station is located at the confluence of the K6nkakee and Des

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Plaines Rivers, in Grundy County, near Morris, Illinois.

l 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 MAY 1997, was compiled by Gary A.

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

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i 2.0 SUNNARY OF OPERATING EXPERIENCE FOR MAY 1997 2.1 UNIT 2 MONTHLY OPERATING EXPERIElfCE

SUMMARY

-Unit 2 was in a forced. outage at the beginning of the period to repair the auxiliary contact assembly in Merlin Gerin electrical breakers.

i On 5/2/97 commenced reactor startup at 0302.

Reactor critical at 0939.

At 0940 noted current fluctuations on 2A Reactor Recirculating Pump Motor Generator.

At 0950, 2A Reactor Recirculating Pump was stopped.

At 1010 initiated a manual reactor scram.

l On 5/3/97 2A reactor Recirculating Pump started at i

1902 following repairs to motor generator j]

tachometer.

At 2311 on 5/4/97, commenced reactor startup.

At 0234 on 5/5/97 reactor was critical At 1910 #4 Turbine Control Intermediate Valve-(CIV) did not open for turbine warming.

At 0153 on 5/6/97 reactor was manually scrammed to repair l

1. 4 CIV.

Commenced reactor startup following repairs to #4 CIV at 0918 on 5/9/97.

Reactor was critical at 1323, and turbine was synchronized at 0957 on 5/10/97.

At 1820 startup was placed on hold because of steam leaks on 2D Main Staam Isolation Valve (MSIV) packing. Commenced Reactor shutdown at 1043 on 5/11/97 to repair 2D MSIV packing leak.

Unit off system at 1237; Reactor was manually scrammed at 1335 to complete the shutdown.

Following repairs to 2D MSIV packing, reactor startup commenced at 1641 on 5/15/97.

Reactor was critical at 2100.

MSIVs tested satisfactorily at 1351 on 5/16/97.

Unit was synchronized to the grid at 0030 on 5/17/97.

Increased load to full power.

At 1120 on 5/26/97, began load drop in preparation for connection of line 2311 in the 345 KV yard.

Load was 300 MWE at 1935 on 5/26/97 and remained i

near 375 MWE for the remainder of the period.

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SUMMARY

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

SUMMARY

Unit 3 was shutdown during this period for refueling outage D3R14.

Commenced fuel load at 0955 on 5/22/97.

Fuel load completed at 2032 on 5/26/97.

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

050-237 DATE JUNE 3, 1997 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 OPERATING STATUS 1.

REPORTING PERIOD:

MAY 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 this report.

REPORTING PERIOD DATA PARAMETER THIS MONTH YEAR TO DATE CUMULATIVE HOURS IN PERIOD 744 3,623 234,959 TIME REACTOR CRITICAL 459.4 2,867 170,029 TIME REACTOR RESERVE SHUTDOWN (Hours) 0 0

0 TIME GENERATOR CN-LINE (Hours) 388 2,796 161,811 TIME GENERATOR RESERVE SHU'JDOM4 (Hours) 0 0

1 THERMAL ENERGY GENERATED

(>Seit Gross) 669,692 6,262,760 337,966,661 ELECTRICAL ENERGY GENERATED (HWEHe Gross) 205,726 2,020,525 107,918,461 ELECTRICAL ENERGY GENERATED (b5fEHe Net) 196,114 1,930,900 102,032,629 REACTOR SERVICE FACTOR (%)

52.2%

79.1%

72.4%

REACTOR AVAILABILITY FACTOR (%)

61.7%

79.1%

72.4%

i GENERATOR SERVICE FACTOR (%)

52.2%

77.2%

68.9%

GENERATOR AVAILABLILITY FACTOR (%)

52.2%

77.2%

68.9%

CAPACITY FACTOR (Using HCD Net) (%)

34.1%

69.0%

56.3%

CAPACITY FACTOR (Using DER Net) (%)

33.2%

67.1%

54.7%

1'VRCED OUTAGE FACTOR (%)

48%

22.8%

13.0%

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SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS: NONE 21.

IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE l

STARTUP N/A l

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

-DOCKET No.

050-249 DATE JUNE 3, 1997

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

REPORTING PERIOD:

MAY 1997 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.

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

HOUR

• IN PERIOD 744 3,623 224,279 6

TIE REACTOR CRITICAL 0

1395.8 157,253 7

TIM REACTOR RESERVE SHUTDOWN (Hours) 0.0 0

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TIE GENERATOR ON-LINE (Hours) 0 1,35E 149,880 9

TI S GENERATOR RESERVE SHUTDOWN (Hours)

O.0 0

0 10 THrJNAL ENERGY GENERATED (MWHt Gross) 0 2,267,376 312,479,855 11 mIacTRICAL sNE80Y GEleRATED (W BNe Gross) 0 729,656 100,002,797 12 ELECTRICAL ENERGY GENERATED (MWEHe Net)

-S,346 681,015 94,763,51t 13 REACTOR SERVICE FACTOR (%)

0.0%

38.5%

70.1%

14 REACTOR AVAIIABILITY FACTOR (%)

0.0%

38.5%

70.1%

15 GENEAATO'. SERVICE FACTOR (%)

0.0%

37.4%

66.8%

16 GENERATOR AVAILABLILITY FACTOR (%)

0.O%

37.4%

66.89 17 CAPACITY FACTOR (Using MCD Net) (4)

-0.9%

24.3%

S4.7%

18 CAPACITY FACTOR (Using DER Net) (%)

-0.9%

23.7%

53.2%

19 FORCED OUTAGE FACTOR (%)

0. 04l 3S.1%

14.7%

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SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS: In refuel outage D3R14.

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IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: June 9, 1997.

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l 3.3 AVERAGE DAILY UNIT 2 POWER LEVEL DOCKET No. 050-237 UNIT Dresden 2 DATE JUNE 3, 1997 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 MONTH:

May-97 DRESDEN 2 DAY AVERAGE DAILY NET DAY AVERAGE DAILY NET FOWER LEVEL (MWe)

POWER LEVEL (MWe) 1

-6 17 142 2

-6 18 460 3

-6 19 619 4

-6 20 715

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-7 21 767 6

-6 22 767 7

-6 23 749 8

-6 24 769 9

-7 25 785 I

10 64 26 590 11 57 27 333 12

-7 28 362 13

-6 29 362 14

-6 30 362 15

-6 31 360 16

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negative Values represent station loads)

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l 3.4 AVERAGE DAILY UNIT 3 POWER LEVEL l

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1 DOCKET No. 050-249 UNIT Dresden 3 DATE JUNE 3, 1997 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 MONTH:

May-97 DRESDEN 3 j

DAY AVERAGE DAILY NET DAY AVERAGE DAILY NET l

POWER LEVEL (MWe)

POWER LEVEL (MWe) 1

-6 17

-8 2

-6 18

-8 3

-6 19

-8 4

-6 20

-8 J

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-7 21

-8 6

-6 22

-8 7

-6 23

-8 8

-6 24

-8 9

-7 25

-8 10

-8 26

-8 11

-7 27

-8 12

-6 28

-8 13

-6 29

-8 14

-6 30

-8 15

-6 31

-8 16

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Negative values represent station loads) 1 l

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3.5 UNIT 2 SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH OF MAY 1997 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) 3 970411 F

225 A

1 9708 EA BKR 2.1 4

970511 F

131 A

1 N/A N/A N/A 2.1 5

970526 S

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4 N/A N/A N/A 2.1 Year-to-date forced outage hours = 827 Cumulative forced outage hours = 24,233 TABLE KEY:

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(3) l F:

Forced Method:

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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

2perational Error (NUREG-0161)

H Other (Explain)

(5)

Exhibit I Same Source as Above.

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~4.0 UNIQUE REPORTING REQUIREMENTS 4.1 MAIN STEAM RELIEF AND/OR SAFETY VALVE OPERATIONS - UNIT 2 AND UNIT 3 The Target-Rock safety / relief valve was tested satisfactorily at 300 psig reactor pressure during plant start up at 0812 on May 16, 1997 following valve maintenance during the forced outage.

4.2 OFF-SITE DOSE CALCULATION MANUAL (ODCM) CHANGES Page Change Description 12-1 Updated special note to identify T/S amendments authorizing transfer of Units 2 and 3 RETS to the ODCM.

Added Statement that Unit 1 Technical Specifications shall take precedence over Unit 1 ODCM items until the Upgraded Unit 1 Technical Specifications are approved by the NRC.

12-4 Revised Note (e) on Table 12.1-2. Technical Specification Amendments 154/149 revised the wording of this note in Table 1.2 of the Unit 2/3 Technical Specifications.

Note was changed to conform with Units 2/3 Technical Specifications.

J 12-8 Added description of grab sample location to Action 10 statement.

12-14,15 Added description of backup sample locations and clarifying information to Action Statements for Table 12.2-3.

4.3 MAJOR CHANGES TO THE RADIOACTIVE WASTE TREATMENT SYSTEMS None 4.4 FAILED FUEL ELEMENT INDICATIONS 4.4.1 Unit 2 has no indications of fuel failures.

4.4.2 Unit 3 was refueled during D3R14. There are no ind1 cations of fuel failures.

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5.0 TECHNICAL SPECIFICATION AMENDMENTS

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5.1 On May 16, 1997 received amendments 159 and 154 which permitted the loading of Advance Nuclear Fuels Atrium-9B fuel into Unit 3 and operation only in Modes 3, 4,

and 5.

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