Text

Monthly Operating Repts for June 1990 for Dresden Nuclear Power Station Units 1,2 & 3
	ML20055G236
Person / Time
Site:	Dresden
Issue date:	06/30/1990
From:	Eenigenburg E, Maxwell D; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
	90-477, NUDOCS 9007200275
	Download: ML20055G236 (25)
	v • d • e

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~ Commonwealth Edison-y ;,l;

) Dresd:n Nuclear P:wer Stati:n jf.f.,

' ' 'j 3 ( R.H. #1

- ' Q[' Telephone

, g-Morris, Illinois 60460

-6 815/942 2920 1

1 July 1=,

1990 EDE LTR

90-477 Director, Nuclear Reactor Regulation United States Nuclear Regulatory Comission Washington DC 20555 Attention: Document Control Desk

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Subject:

Monthly Operating Data Report Dresden Nuclear Power Station Comonwealth Edison Company Docket Nos.50-010. 50-231. and 50-249 Gentlemen:

1 Enclosed is the Dresden Nuclear Power Station Monthlv Ooeratine So--ry

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Report for June, 1990.

This information is supplied to your office in' accordance with the instructions set forth in Regulatory Guide 1.16.

Please note that the report contains information which had been previously submitted to your attention on an annual basis in accordance with 100FR50.59.

Sincerely.

g I'

E. D..Eenigenburg l

Station Manager l

l-Dresden Nuclear Power Station lI EDE:GP:bjs

-Enclosure' cc:'U.S. NRC Region III Office Illinois Dept. of Nuclear Safety State of Illinois

%U.8W NRO,t. Document; Management; Branch 5

. Nuclear Licensifig ' Administrator

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'Vice Pres. - BWR Operations I

General Manager - Nuclear Services T. S. ENGR. (2)

NRC Senior Resident Inspector Nuclear Quality Programs - Dresden Nuclear Engineering Manager Comptro11er's Office D. Eggett - Reliability Programs INPO Records Canter File /NRC Op. Data File / Numerical Z16/10/1

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CRANGES, TESTS, AltD EEPERDIENTS PER REGU] AERY CUIDE 1.16 AIED 10 CFR 50.59 IDE DREEDEN NDCLEAR POWER STATIG(

CGMGefEALTE EDIBGI CGEPANY PUR JllitE 1990 UNIT DQCEEI LICENSE 1

050 ^)10 DPR-2 2

V50-237 DPR-19 3

050-249 DPR-25 t

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p TABLE OF CORTENIS 1.0 Introduction 2.0 Summary of Oper.atine Experience 2.1 Unit 2 Monthly Operating Experience Summary for June,1990 2.2 Unit 3 Monthly Operating Experience Summary for June,1990 l

3.0 Doeratine Data Statistics 3.1 Monthly.0perating Data Report - Unit 2 l

3.2 Monthly Operating Data Report - Unit 3

-l 3.3 Average Daily Power Level Data - Unit 2

'3.4 Average Daily Power Level Data - Unit 3 3.5 Unit Shutdown and Power Reduction Data - Unit 2 3.6 Unit Shutdown and Power Reduction Data - Unit 3 3.7 Station Maximum Daily Load Data

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4.0 Unique Reporting Requirements 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 4.4 Failed Fuel Element Indications 4.4.1 Unit 2 4.4.2 ' Unit 3 5. i0 Elant_pr Procedure Changes. Tests. Experiments. and Safety Related Maintenance 5.1 Amendments to Facility License or Technical Specifications 5.1.1 Unit 2 5.1.21 Unit 3 5.2 Changes to Procedures Which are Described in the Final Safety Analysis Report.(FSAR) (Units 2 and 3)

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5.3 Significant Tests and Experiments Not Described in the FSAR (Units 2 and.3) 1 L

5.4 Safety Related Maintenance (Units 2 and 3) 5.5 Completed Safety Related Modifications-5.6 Temporary System Alterations 5.6.1 Unit 2 5.6.2 Unit 3 i

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1.0 Introduction-g.

Dresden Nuclear Power. Station is a three reactor generating facility owned.and operated by'the Commonwealth Edison 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 retired in place with all nuclear fuel removed from the reactor vessel. Therefore, no Unit 1 operating data is provided in this report.

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Dresden Units 2 and 3 are General Electric Boiling Water Reactors with design net' electrical output ratings of 794 MWe each.

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 was compiled by Donald C. Maxwell of the Dresden Technical Staff, telephone number (815)942-2920 extension 2489.

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V 216/10/4

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. 200 SUMARY OF OPERATING TIPERIENCE FOR JUNE. 1990;

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2.1 UNIT 2 MONTHLY OPERATING EXPERIENCE

SUMMARY

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- l 06-01-90 to 06-30-90 Unit 2 entered the month on line and operating'at-f t

approximately 782 MWe, The unit operated in

' Economic Generation Control or at loads requested by the System Load Dispatcher for the remainder of the month with an availability of 100% and a' f

capacity factor of 85.4%..

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SIRetARY OF OPERATING RYPERIENCE FOR JUNE. 1990' c

' 2.2 UNIT 3 MONTHLY OPERATING EXPERIENCE St29tARY

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'06-01-90 to 06-27-90

. Unit-3 entered the month on line and operating at approximately 675 MWe. -The Unit operated in

-Economic Generation Control or at leads requested by.the System ~ Load Dispatcher until 6-27-90.

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.06-27-90 to 06-30-90 At 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months on 6/27/90, a' load reduction from 790 MWe to 482 MWe waa-performed due to f

indications of increasing main turbine thrust bearing temperature. After review of main-turbine performance data, a'acheduled maintenance outage'was planned for 6/30/90.

The Unit was,then separated from the grid at u

0414 hours0.00479 days 0.115 hours 6.845238e-4 weeks 1.57527e-4 months on 6/30/90 and the reactor was brought sub-critical at 0508 hours0.00588 days 0.141 hours 8.399471e-4 weeks 1.93294e-4 months of the came day. During' the maintenance outage the following significant items were-performed in i

addition to replacement of the thrust bearing -

i Replacement of Control' Rod Drive H-10.

Replacement of a main power transformer (TR3).'C' phase bushing and resolution of a TR3 cooler leak problem.

i Completion of various activities pre-scheduled for this type of short outage.

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-3.0 : OPERATING DATA REPORT

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- 3.1 OPERATING DATA REPORT - UNIT TWO l

DOCKET NO.

050-237 DATE July 1. 1990

-COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920

1.

REPORTING PERIOD:

JUNE. 1990 GROSS HOURS IN REPORTING PERIOD 720

-.2.

' CURRENTLY AUTHORIZED POWER LEVEL (MWe):

2,527 MAX DEPEND CAPACITY (MWe-Net)'

772 DESIGN ELECTRICAL RATING (MWe-Net) 794

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3.

POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): N/A 4.

REASONS FOR RESTRICTIONS (IF ANY): N/A i

REPORTING PERIOD DATA

-l This Month Yr-to-Date Cumulative 5.

TIME REACTOR CRITICAL (HOURS) 720.0 4,070.7 134,850.9 6.

TIME REACTOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0 l

7.'> TIME GENERATOR ON-LINE (HOURS) 720.0

-4,046.7 129,098.2 8.

TIME GENERATOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0-9.

THERMAL' ENERGY GENERATED (MWHt-GROSS) 1,624,548 9,613,501 267,730,692 10.

ELECTRICAL ENERGY GENERATED (MWHe GROSS) 513,105 3,079,597 85,573,946 j

11.

ELECTRICAL ENERGY GENERATED (MWHe-NET) 487,413 2,935,237 80,923.401

' 12... REACTOR SERVICE FACTOR-(%)

100.0 93.7 76.4 l.

13.- REACTOR AVAILABILITY FACTOR (%)-

100.0 93.7 76.4

- 14., SERVICE FACTOR (%)

100.0 93.2' 73.2

.15.

AVAILABILITY FACTOR 100.0 93.2 73.2 1

16.- CAPACITY FACTOR-(USING MDC) (%)

87.7 87.5-59.4

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17. l CAPACITY FACTOR (USING DESIGN MWe)-(%)

85.3 85.1 57.8 l

18.

FORCED OUTAGE FACTOR (%)

0.0 6.8 10.7 1

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.19.

SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS

-(TYPE DATE AND DURATION OF EACH) l

REFUELING OUTAGE CURRENTLY SCHEDULED for 9-23-90 thru 12-04-90 i

20.

IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A 216/10/7 1

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3.0 OPERATING DATA REPORT

-3.2 OPERATING DATA REPORT - UNIT THREE-DOCKET NO.

050-249 DATE -July 1. 1990 COMPLETED BY D.C. Maxwell TELEPHONE 815/942-2920'

. OPERATING STATUS-1.

REPORTING PERIOD:

JUNE. 1990 GROSS HOURS IN REPORTING PERIOD 720

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2.

CURRENTLY AUTHORIZED POWER LEVEL (MWe):

2,527 MAX DEPEND CAPACITY (MWe-Net) 773 DESIGN ELECTRICAL RATING (MWe-Net) 794 3.

POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): ' N/A

4..' REASONS FOR RESTRICTIONS (IF ANY): N/A REPORTING PERIOD DATA This Month Yr-to-Date Cumulative 5.

TIME REACTOR CRITICAL (HOURS) 701.3 3,163.4 123,397.8 6.

TIME REACTOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0 7.

TIME GENERATOR ON-LINE (HOURS) 700.2 3,026.2 115.388.3 8.

TIME GENERATOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0 9.

THERMAL ENERGY GENERATED (MWHt-GROSS) 1,462,663 7,039,718 238,667,138

10. ELECTRICAL ENERGY GENERATED (MWHe GROSS) 466,580 2,274,251 76,986,496 11.

ELECTRICAL ENERGY GENERATED (MWHe-NET) 443,304 2,162,699 73,018.069 12.

REACTOR SERVICE FACTOR-(%)

97.4 72.8 74.3

13. REACTOR AVAILABILITY FACTOR (%)

97.4 72.8 74.3

14. ; SERVICE FACTOR (%)

97.3 69.7

-69.5

15. AVAILABILITY FACTOR 97.3 69.7 69.5

16. -CAPACITY FACTOR-(USING MDC)-(%)

79.7 64.4 56.9 17.

CAPACITY FACTOR (USING DESIGN MWe) (%)

77.5 62.7 55.4 18.

FORCED OUTAGE FACTOR (%)

0.0 9.0 12.0 19.

SHUTDOWNS SCHEDULED OVER~ THE NEXT 6 MONTHS (TYPE DATE AND DURATION OF EACH)

NONE 20.

IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP 07-05-90 216/10/8

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_ ',L 3.3 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-237 UNIT II DATE July 1. 1990 L

COMPLETED BY D.c. Maxwell g

TELEPHONE 815/942-2920 I

MONTH JUNE. 1990 r

F DAY AVERAGE DAILY POWER LEVEL DAY-AVERAGE DAILY POWER LEVEL

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(MWe-Net)

(MWe-Net) l 1

740 17 364 2

738 18 585 3

715 19 641

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4 717 20 711 5

746 21 764 w

6 754 22 741' 1

7-752 23 697 8

748 24 610 9

730 25 740 10 495 26 652 11 624 27 729 12 716 28 712

-13 741 29 743 14 754 30 693 15 582 31 16.

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-3.4' AVERAGE DAIIN UNIT POWER LEVEL-4

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DOCKET NO. 050-249 UNIT III DATE July 1.'1990 COMFicI.T.D BY D.C. Maxwell TELE" HONE 815/%2-2920 MONTH JUNE.-1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 730 17

'82 2

476 18 508 3

734 19 513 4

767 20 580 5

760 21 692 6

764 22 751 7

758 23 713 8

f3 24 587 9

745 25 776 q

10 697 26 781 I

l 11 711 27 755 12 618 28 414 13' 706 29 278 l

14 761 30 19 I

i 15 579 31

-16 280 t

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DCCKET NO.' 050-237 UNIT NAfE MEEDER IETJ 11_

DATE July 1. 1990 -

3.5 UNIT saud6:G ?JED F0WER_ REDUCTIONS COMPLETED BT D. C. * - 11 TELEFWONE (815)942-1920

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REPORT MONIH JUNE. 1990 I

I PETHOD OF LICENSEE SYSTg Cum grei CAUSE & CORRECTIVE NO.

DATE TTFE DURATION REASON SHUTTING EVDrr CODE CCDE' ACTION TD (HOURS)

DOWN REACTOR REPORT #

FREVENT RECURRENCE NONE I

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2 Exhibit C-Instructions for Method:

F: Forced Reason:

1-Manual Freparation of Data S: Scheduled A-Equipment Failure (Explain) 2-Manual Scram Entry Sheets for Licensee B-Maintenance or Test 3-Autoentic Scram Event Report (LER) File C-Refueling D-Regulatory Restriction 4-Other (Explain)

(NUREG-Ol61) 5-Load Reduction E-Operator Training & Licensee Examination F-Administrative G-Operational Error 5 Exhibit I - Same Source 2I16/10 H-Other (Explain)

DOCKET N0c, ~050-249 UNIT NAME _JEFJiDER_INIT rir_

3.6 U_MII_SEIDGGEi_AltQ1QWER REDUCTIONS DATE _.baly_1. 1990_*

COMPLETED BY _p. C. N== ell TELEPHONE (815)942-2920 REPORT MONTH JUNE. 1990 METHOD OF LICENSEE ding COMPOWENT CAUSE & CORRECTIVE NO.

DATE TYPE DURATION REASON SHUTTING EVENT CODE CODE ACTION 10 (HOURS)

DOWN REACTOR REPORT #

FREVENT RECURRENCE 4

06-30-90 S

19.8 B

1 N/A N/A N/A Main Turbine thrust bearing (19:46) replacement and main transformer bushing replacement.

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F: Forced Reason:

Method:

Exhibit G-Instructions for S: Scheduled A-Equipment Failure (Explain) 1--Manual Preparation of Data B-Maintenance or Test 2-P'anual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Other (Explain)

(NUREG-0161)

E-Operator Training & Licensee Examination 5-Ioad Reduction F-Administrative G-Operational Error 5 Exhibit I - Same Source ZR16/10 H-Other (Explain)

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3.7 COPMONWEALTH EDISON COMFANY - DRESDEN NUCLEAR POWER STATION MAXIMUM DAILY ELECTRICAL LOAD FORM l

FOR THE MONTH OF JUNE, 1990 t

HOUR MAXIMUM DAILY LOAD ENDING KW 1

1000 1.595.900 s

2 2400 1.421.300 3

2100 1.579.700 4

.1600 1.577.700 5

1300 1.617.200 6

1100 1 111Q0 7

090_Q 1.605.300 8

0100 1.593.700 9

-1300 1.591.200 10 01QO 1.401.600 i

11 2200 1.466.500 l

12 1300 1.456.600

_r 13 23QO 1.576.900 14 0900 1.589.600 15 0100.

1.577.800 16 0300 805,300 17 2400 7M.400 18 2200 1.386,200 19 1500 1.374.700 l

20 2000 1.416.300 21 1700 1 dQ4.100 22 1900 1.618 100 i

4 23 0100 1.529.800 l-24 2400 1.520.600 25 0100 1.615.400 26 1700 1.615.800 27 0100 1.603.200 28 0100 1.350.900 29 0100 1.098.600 30 0100 958.400 ZR16/10/13

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i 4.0 UNIQUE REPORTING REQUIREMENTS 4.1 MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period, June, 1990, are summarised in the following table. The table includes information as to which relief valve was actuated, how it was actuated, and the circumstances resulting in its actuation.

i No. and Type Ealita of Plant Description Unit Date Ac_tuated AC1.uallDus Conditions of Eventa 2

No Unit 2 Main Steam Relief and/or safety valve actuations occurred during this reporting period.

3 No Unit 3 Main Steam Relief and/or safety valve actuations occurred during this reporting period.

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4.2 0FF-SITE DOSE CALCULATION MANUAL (ODCM) CRANGES j

No ODCM changes were reported for the month of June,1990.

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4.3 MAJOR CHANGES TO THE RADIDACTIVE WASTE TREATMENT SYSTEMS 1

There were no major changes to the Radioactive Waste Treatment Systems at Dresden during the June, 1990 reporting period.

i 4.4 FAILED TUEL ELD 1ENT INDICATIONS I

4.4.1 Unit 2 Dresden Unit 2 fuel perforn.ance during June,1990 continued to show no indications of leaking fuel.

This is based on the sum of the 1

activities of the six noble gases as measured at the recombiner.

Based on the reported data Unit 2 had acceptable fuel performance.

i 4.2 Unit 3 Dresden Ur.it 3 fuel performance during June,1990 continued to show no indications of leaking fuel.

This is based ou the sum of the activities of the eix r.oble gases as measured at the recombiner. Based on the reported data. Unit 3 had acceptable fuel performance.

t 5.0 PLANT OR PROCEDURE _CHAliGIS. TESIS _EXPERIMENIS. AND SAEETY pr14Tgp tE1HTENANCE 5.1 Amendments to Facility License or Technical Specifications No new amendments to facility license or technical specifications were approved for use during June, 1990.

5.2 Changes to Procedures Which are Described in the FSAR (Units 2 and 3)

Table 5.2.1, attached, sunmarir,es the revicions to procedures described in the FSAR which were approved during the June, 1990 reporting period.

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TABLE 5.2.1 CHANGES TO PROCEDURES WHICH ARE DESCRIBED IN THE FSAR (UNITS 2'AND 3) FOR JUNE, 1990 PROCEDURE TYPE PROCEDURE NO.

PROCEDURE TITLE / DESCRIPTION SUITIARY OF MA3lQES. __

Dresden Operating DOS 1100-2 Standby Liquid Control Injection Test 4

Surveillance NOTES: 1.

Administrative change; intent of procedure unchanged.

2.

Changed for clarification, intent of procedure unchanged.

3.

Changed to incorporate requirements for new equipment; intent of procedure unchanged 4

Changed to implement improved testing / calibration methodology; intent of procedure unchanged.

'd16/10/16

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5.3 SignifAcant tests and experiments n3t d:scrib:d in th) FSAR (Units 2

& 3)

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Significant special procedures involving tests not described in the FSAR which sere approved during the month of May, 1990 are listed below.

ELQtedure No.

Procedure Title / Description SP 90-05-P's cleanup of 2/3 Radwaste Sludge Tank Room and Spent Resin Tank Room The purpose of_this procedure is to detail the steps necessary to remove the sludge and spent resin from the Sludge Tank Room and Spent Resin Tank Room floors using the Spent Resin Pump to transfer the waste to a Mobile Solidification.

Unit located et the 2/3 Radwaste Barreling Area.

i SP 90-06-87 A-Model Installation Modification M12 2/3-05-03 Test The purpose of this procedure is to test the i

communication interface equipment and printer installed under McGification M12-2/3-85-03.

This allows for data transfer between the Separate Particulate Iodine and Noble Gas (SPING) effluent monitor Control Terminals (CT), _ the PRIME t

Computer, and the Control Room Center Desk.

5.4 Safety Related Maintenance (Unit 2 and 3)

Safety related maintenance activities fer June,1990 are ownmarized I

in the attached tables.

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e7 5.5 Complcted Saf ty R loted Modific tions (Units 2 and 3) o.

Unit 2 and Unit 3 safety related modification packages closed during the month of June, 1990 are listed below.

Only modifications which i

have been completely closed are listedt modifications which are authorized for use but not completely closed will be reported based on the date of their final closure. For ease of reference, the

{

changes have been identified by their design change control modification number.

l Modification No.

Description M12-3-86-24E This modification was performed to rearrange the l

off gas system charcoa1' absorber valve control switches 3-5440-18A-55,-57,-59 and -72 on Control Room Panel 903-54.

This was accomplished to I

provide a more logical order of switch placement 1

I for human factors. The safety evaluation concluded that the margin of safety is not reduced.

M12-3-87-20 The purpose of this modification was to reduce the possibility of inadvertent override of an automatic initiation signal to the Isolation.

Condenser Return Valve.MO-1301-3.

This was done 7

by *eplacing the existing control switch with a four position switch (pull-to-lock, close, open, auto). The safety evaluation concluded that the margin of safety is not reduced.

5.6 Temporary System Alterations (Unit 2 and Unit 3)

A " Temporary System Alteration refers to electrical jumpers, lif ted leads, removed fuses, fuses turned to non-conducting position, fures moved from normal to reserve holder, temporary power supplies, test switches in alternate positions, temporary blank flanges, and spool y'

pieces. Alterations controlled and documented as part of a routine out-of-service or other procedure, alterations which are a normal feature of system design, and hoses installed as part of a venting or draining process are not included.

a 216/10/18

L

$1/

ct-5.6.1 Unit 2 to

-Temporary-System Installation Removal Alteration No.

Descriptio.n Dalt Date 11-13-90 This alteration allows for 6/28/90 7/1/90 the addition of a supplemental sample pump which provides for taking of the Technical Specification daily required Primary Containment samples pending repairs to the sampling equipment.

r 11-14-90 This alteration 6/30/90 relocates the particulate f

iod16 filter cartridges for Primary. Containment sampling i

from sample point 21 to sample point 26 to provide for an automatic Primary Containment isolation function

)

in the event that a design basis accident or other transient occurs during sampling.

5.6.2 Unit 3 Temporary Syste'o Inota11ation Removal A11tIa11on No.

DRECIiP110D Date Dat e.....

III-16-90 This alteration allows 6/28/90 7/3/90 for the addition of a l-supplemental sample pump which provides for taking t

of the Technical Specification daily required Primary Containment samples.

This attention was removed on 7/3/90, at which time alteration III-17-90 was implemented to relocate the sample points as described L

in item 5.6.1 above l

l

=

Z16/10/19 e

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ML20055G236

Text

Subject:

SUMMARY

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