Text

Monthly Operating Repts for Sept 1989 for Dresden Nuclear Power Station Units 1,2 & 3
	ML19327A875
Person / Time
Site:	Dresden
Issue date:	09/30/1989
From:	Paramore G; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML19327A871	List: ML19327A870; ML19327A875;
References
	NUDOCS 8910180335
	Download: ML19327A875 (31)
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CHANGES. TESTS. AND EKPERIMENTS

'PER~ REGULATORY GUIDE 1.16 AND 10 CFR 50.59

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1 IQB-l DRESDEN NUCLEAR POWER STATION C01910NWEALTH EDISQN COMPANY UNIT DOCKET LICENSE 1

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2 050-237 DPR l 3

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' TABLE OF CONTENTS

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,r 1.0 Introduction 2.0 Se-- ry of Operating Experience 2.1 Unit 2 Monthly Operating Experience Summary 2.2 Unit 3 Monthly Operating Experience Summary 3.0- Dparating Data Statistics 3.1 Monthly Operating Data Report - Unit 2 3.2 Monthly Operating Data Report - Unit 3

-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 4.0 Unione Repnr. tina Reguirements 4.1 Main Steam Relief and/or Safety Valve Operations - Unit 2 and i

Unit 3 l

4.2 Off-Site Dose Calculation Manual Changes 4.3 Major changes to the Radioactive Waste Treatment a

i 4.4 Failed Fuel Element Indications 4.4.1 Unit 2 4.4.2 Unit 3 5.0 Plant or Procedure Changes. Tests. Experiments. and Safety Related Maintenansa l

5.1 Amendments to Facility License or Technical Specifications 5.1.1 Unit 2 5.1.2-Unit 3 5.2 Changes to Procedures Which are Described in the Final Safety.

. Analysis Report (FSAR) (Units 2 and 3) l 5.3 Significant Tests and Experiments Not Described in the FSAR l

(Units 2 and 3) 1 5.4 Safety Related Maintenance (Units 2 and 3)

!:r 5.5 Completed Safety Related Modifications

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5.6 Temporary System Alterations

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1.0--Jatrodnetion

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l 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 contluence of the Kankakee and Des Plaines Rivers, in Grundy County, near Morris, Illinois.

4 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

p vessel..Therefore. no Unit 1 operating data are provided :bi this report..

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 all three Dresden units was Sargent and Lundy

.of Chicago, Illinois.-

This report was. compiled by Gerrine Paramore of the Dresden Technical Staff, telephone number (815)942-2920 extension 2364.

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2.0 $13fnR1..;F OPERATIFG EXPERIENCE FOR SEPIEtiSEk.1983 2.1' UNIT 2 MONTHLY OPERATING EXPERIENCE SUMIMRY

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09-01-89 to 09-30-89 Unit 2 entered the month on line and operating at approximately 803 MWe.

Dresden Unit 2 remained on line and operated in Economic Generation Control or at loads requested by the System Load Dispatcher for the remainder of the month.

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. 2.0 BlMukY OF OPERATING EXPERIENCE FOR SEP7]DtBER,1989

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't 09-01-89 to 09-30-89' Unit 3 entered the reonth on line and operating at approximately 803 MWe. The unit operated in-Economic Generation Control or at loads requested by the System Load Dispatcher for the remainder of the a'

month.

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3.2 OPERA 11NG DATA REPORT - UN11 TWO DOCKET NO. 050-237 1-I UNIT DRE$ DEN TWO DATE: OCTOBER 1, 1989 i

COMPLET[0 BY: G.M. PARAMORE TELEPHONE (815) 942-2920 OPERAi!NG $fATU$

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REPORi!NG PERIOD

$ cpi [MBER 1989 GRO$$ HOUR $ IN REPORi!NG PERIOD 720 2.

CURRENTLY AUTHORIZED POWER LEVEL ( W t) 2,527 MAX DEPEND CAPACITY ( We-Net) 172 DE$1GN ELECTRICAL RATING (We-Net) 794 L

3.

POWER LEVEL TO WHICH RE$1RICTED (IF ANY) (We-Net)

NONE 4.

REA$0NS FOR RESTRICTION (IF ANY)

REPORTING PERIOD DATA THl$ HONTH YEAR-TO-DATE CUMULATIVE 5.'

T!HE REACTOR CR111 CAL (HOURS) 720.0 5,268.9 128,814.8 6..

TIME REACTOR RESERVE $HUTDOWN (HOUR $)

0.0 0.0 0.0 7.

TIME GENERA 10R ON-LINE (HOUR $)

720.0 5,156.9 123,182.3 8.

T1HE GENERATOR RESERVE $HUTDOWN (HOUR $)

0.0 0.0 0.0 9.

THERMAL ENERGY GENERATED (WHt-Gross) 1,676,654 11.168,782 253,660,644

10. ELECTRICAL ENERGY GENERATED (HWHe~ Gross) 540,767 3,569,896 81,054,629

11. ELECTRICAL ENERGY GENERATED (HWHe-Net) 515,878 3,388,666 76,631,572

12. REACTOR SERVICE FACTOR (%)

100.0 80.4 75.8

13. REAC10R AVAILABILITY TACTOR (%)

100.0 80.4 75.8

14. $0RVICE FACTOR (%)

100.0 7P.7 72.5

15. AVAILABILITY. FACTOR 100.0 78.7 72.5

-16. CAPACITY TACTOR (U$1NG HDC) (%)

92.8 67.0 58.4

17. CAPACITY FACTOR (U$1NG DESIGN HWe) (%)

90.2 G5.1 56.8

18. FORCED OUTAGE FACTOR (%)

0.0 2.4 10.9

-19. $HU100WN$ $CHEDULED OVER THE NEXT 6 MONTHS (TYPE DATE AND DURATION Of EACH) 125VDC TEST OU1 AGE 12-13-89, 13 DAYS

20. IF $HUTDOWN AT END Of REPORT PERIOD, EST1 HATED DATE Or STARTUP l

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3.0 OPERATING DATA STATISTICS

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DATE: OC108ER 1, 1989 COMPLETED BY: G.M. PARAMDRE TELEPHONE (815) 942-2920 OPERATING STATU$

1.

REPORTING PERIOD SEPTEMBER 1989 GROS $ HOUR $ IN REPORTING PERIOD 720

2.. CURRENTLY AUTHORIZED POWER LEVEL (MWt):

2 $27 MAX DEPENO CAPACITY (MWe-Net).

773 DE$1GN ELECTRICAL RATING (MWe-Net) 794 3.

POWER LEVEL TO WHICH RESTr!CTED (If ANY) (MWe-Net)

N/A 4.

REA$0NS FOR RE$TRICTION (If ANY)

REPORTING PERIOD DATA

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THl$ MONTH YEAR-TO-DAT E CUMULATIVE i

5. : TIME REACTOR CRITICAL (HOUR $).

720.0 5,807.7

.,716.8

6. - TIME REACTOR RE$ERVE SHUTDOWN (HOUR $)

0.0 0.0 0.0 7.

TlHE GENERATOR ON-LINE (HOUR $)

720.0 5,721.2 110,845.3 8.

TIME GENERATOR RESEkVE SHUTDOWN (HOUR $)-

0.0 0.0 0.0 9.~

THERHAL ENERGY GENERATED (MWHt-Gross) 1,746,527 13,182,763 228,167,222 i

10. ELECTRIEAL ENERGY GENERATED (MWHe-Gross) 565,375 4.257,208 73,645,917 111. CLECTRICAL ENLRGY GENERATED (MWHe-Net) 541,352 4,058,844 69,796,270

12. REACTOR SERVICE FACTOR (%)

100.0 B8.7 -

74.4 13., REACTOR' AVAILABILITY FACTOR (%)

100.0 88.7 74.4

14. $ERV',(E FACTOR (%)

100.0 87.3 69.5

15. AVAILABILITY FACTOR 100.0 87.3 69.5

16. CATACITY FACTOR (U$1NG HDC) (%)

97.3 80.2 56.6

- 17, CAPACITY FACTOR (U$1NG DESIGN HWe) (%)

94.7 78.0 55.1 (18.FORCEDOUTAGEFACTOR(%)

0.0 3.9 12.2

19. $HUTDOWNS SCHEDULED OVER THE NEXT 6 HDNTHS (TYPE DATE AND DURATION Or EACH)

REFUEL OUTAGE. 12-3-89, 10 WEEKS

20. If SHUIDOWN AT END Of REPORT PERIOD, E$TIMATED DATE OF STARTUP N/A WP+470-

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' 3.3 AVERAGE MILY UNIT POWER LEYLL DOCKET NO.- 050-237 UNIT II DATE.0CTOBER 1. 1989 COMPLETED BY G. PARAtiORE i

TELEPHONE B15/942-2920 MONTH SEPTEMBER. 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 774 1/

659 2

778-18 745 3

_625 19 751

-4 640 20 757 5

741 f.1 765 t

6 730 22 774 7'

724 23 434 8

760 24 548 9

771 25 723 10 711 26 771 11-699

7 768 12-769 28 551 13 757 29 676 l

-14 777 30 7_68 15.

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DATE OC?OBER 1. 1989-COMPLETED BY_9.if _IARAtiOBL_,_

TELEPHONE __ _815 / 942-2920 MONTH,___SEPTEMBERJB9 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER I.EVEL (MWe-Net)

(MWe-Net) 1 611 17 784 2

6.38 18 779 3

722, 19 778 4

697 20 763 i

5 740 21 584 6=

774 22 761 i

7 777 23 774 L

8 773 24 755

'9 749 25 775 10 776 26 782

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11 777 27 779 l,

~ 12 779 28 785 13-782 29 781 14 783 30 742

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DOCKET NOE 050-237.

UNIT NArg m w u httIT II' i

.3.5 UNIT SHUTDOWNS AND POWER REDUCTIONS DATE Octnbar 1. 1989

. COMPLETED BY G. Par - re TELEPH0f6 (8153942-2920 REPORT MONTH f,EPTEMBER. 1989 METHOD OF LICENSEE q

COMP 0p CAUSE & CORRECTIVE 7

NO.

DATE TYPE DURATION REASON SEUTTING EVENT CODE CODE-ACTION TO (HOURS)

DOWN REACTOR REPORT #

PREVENT RECURRENCE 6

None i

1 2

3 4

F: Forced Reason:

Method:

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

(NUREG-Ol61)

E-Operator Training & Licensee Framination 5-Load Reduction F-Administrative G-Operational Error 5 Exhibit I - Same Source 2470 H-Other (Explain)

DOCKET Not 050-249

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UNIT NAME DRESDEN IntIT III.

3.6 UNIT SHUTDOWNS AND POWER REDUCTIONS DATE A tsber 1. 1889_-

COMPLETED BY _L Pars = ara' TELEPHONE M 5}942-2920 REPORT MONIH sErusinE:L 1989 I

METHOD OF LICENSEE SYSTg COMPOgENT CAUSE & CORRECTIVE 1

2 NO.

DATE TYPE EURATION RFASON SHUTTING EVENT COLE CODE-ACTION TD (HOURS)

DOWN REACTOR REPORT #

PREVENT RECURRENCE 5

None

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3 4

F: Forced Reasan:

Method:

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

(NUREG-0161)

E-Operator Training & Licensee Er==ination 5-Load Reduction F-Administrative G-Operational Error 5 Exhibit I - Same Source 2470 H-Other (Explaini

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3.7 STATION MAXIMUM DAILY ELECTRICAL LOAD DAT4 DRESDEN STATION p

SEPTEMBER, 1989 ll0UR hhXIMUM DAILY LOAD ggy ENDING KW 1

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1.53hRQ0 2

2300 1,125.700 3

2300 1.532.900

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1.52bh0D t

5 140Q__

1.182.100 6

it!QO 1.568,400 7

1300.......

J.iBQ 300 8

1000 1.tQi 1Q0 9

1700 1.611.400 10 0100 1.597.400 11

.... 2400 1.196_.300

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2400 1.619.600 13_ _ _ lf90 _

1 621,200 14 18Q0 1 61822QO

,_ 15 0500 1.624.200 16 1200 1 116,100 17

.D1QQ 1.161,100 18 1700 1.625.100 19

_ 1200 1.601,300

_20 0900 _

1.603 200 21 2400 1.528.900

... _ 2 2 1100 1.627.400 23 0100__

1.181.300 24 2400 1.451 800 25 2000 1.625.300 26 _

1300 1 63_l,b.00 2

t 27 1300 1.636 3D0 28 2400 1.450,000 29

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._L.hqB..s00 30 1500 1.h123h00 TOTAL 47,353,600

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4.0 HM1QVf_ REPORTING REculREMENTS f

l 4.1 MAIN SIEA RELIEF VALVE OPERATIONS Relief valve operations during the reporting terlod, September, 1989, are summarized in the following table. The table includes information as to which relief valve was actuated, how it was actuated, and the circumstances i

resulting in its actuation.

l No. and Type Yalysa of Plant Descriotion Unil Dalt Actuated Actuations Conditions of Events 2/3 9/89 Valve Serial

1. Bench

!!/A This Electromatic Not BK 7052 Tested Relief Valve was beach tested and rebuilt for future use.

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4.2 0FF-SITE DOSE CALCU1ATION MANUAL CHANGES I'

There were no changes to the Off-Site Dose Calculation Manual during F

September, 1989.

4.3 MAJOR C11ANGES TO THE RADIDACTIVE WASTE TREATNENT SYSTEMS There were no major changes to the radioactive waste treatment systems at Dresden during September, 1989.

4.4 FAILED FUEL ELEMENT INDICATIONS i

4.4.1 Unit 2 Dtusden Unit 2 fuel performance during September 1989 continued to show no indications of leaking fuel. This is based on the sum of the activities of the six noble gases as measured at the recombiner.

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

4.4.2 Unit 3 1

Dresden Unit 3 fuel performance during September 1989 continued to show no indications of leaking fuel. This is based on the sum of the activities of the six noble gases as measured at the recombiner.

Based on the reported data, Unit 3 had acceptable fuel performance.

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5.0 - RIANT. OR PROCIDURE_CEAliGES. TESIs. ErPEPIMENTS. AND LAFETY RE1 IC '"'*

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5.1 Amendments to Facility License or Technical Specifications L

The, license amendments and/or Technical Specification changes which were approved and implemented for use during the reporting period are listed below.

5.1.1 Unit 2 None I.

5.1.2 Unit 3 None j.

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

Table 5.2.1, attached, summarizes the revisions to procedures described in the FSAR which were approved during thereporting period.

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CHANGES TO PROCEDURES WHICH ARE DESCRIBED IN THE FSAR (UNITS 2 AMD 3)

FROCEDURE TYPE PROCEDURE NO.

PROCEDURE TITLE / DESCRIPTION SL N Y OF' M ES

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Dresden Instrument DIS 500-10 Scram Discharge Voltuse Instrumentations Functional 2

Procedure (DIS)

Test & Calibration Dresden Operating DOS 1100-1 Standby Liquid Control System Pump Test 2,4 f

Surveillance (DOS) st, 4

DOS 5600-2 Monthly & Weekly Turbine Checks 4

3 DOS 6600-1 Diesel Generator Surveillance Tests 2,4 t

3 Dresden Technical Staff DTS 300-2 Control Rod Drive Scrast Testing and Scram Valve 2,4 b

M Surveillance (DTS)

Timing Tests.

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NOTES: 1.

Administrative change; intent of procedure unchanged.

2.

Changed for clarification, intent of procedure unchanged.

F Changed to incorporate requirecents for new equipment; intent of procedure unchanged 3.

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

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5.3 Significant Tests and Experiments Not Described in the FSAR (UNITS 2 and 3)

Significant special proce&*res involving tests not described in the FSAR which were approved during the month are listed below.

Procedurg_ h Ernecdure Title /Descriction SP 89-9-77 Maintenance Shop Fire Sprinkler System Modification Leakage Test.

SP 89-9-79 New Training Building Fire Water Availability Flow Test.

SP 89-9-81 This procedure diagnosed difficulty in notching Control Rod Drive (CRD) N-9 under normal CRD drive water pressure conditions and determined corrective action.

5.4 Safety related maintenance (Units 2 and 3)

Safety related maintenanco activities are summarized in the attached tables.

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5.5 Comp 1;ted Safcty R;1;ted Modific tions (Units 2 and 3)
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Unit 2 and Unit 3 safety related modification packages closed during the month of September, 1989 are listed below. Only modifications which have been completely closed are listed; 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.
tindificaLion No.
Dest d ation M12-2-87-33A This modification involved the installation of sheck absorbing. Isolators on Unit 2 Main Steam Line (MSL) Low Iressure Switches 2-261-30B and 2-261-30D. The safety evaluation concluded that neither the function of MSL switches nor the configuration of the safety system holding the switches would be affected.
M12-2-88-3 This modification luvolved installing High Pressure Coolant injection (HPCI) and Reactor Water Clean Up (RWCU) pipe supports for small bore tap lines. Additional pipe supports increase the reliability of the associated piping during a postulated seismic event. The supports mitigate fatigue induced failures beyond that evaluated in the FSAR, by significantly reducing pipe vibration stress.
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%-T 5.6. Torpor;ry System t.ltor;tions (Unit 2 and Unit 3) 3
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A " Temporary System Alteration" refers to electrical jumpers, lifted leads, removed fuses, fuses turned to non-conducting position, fuses moved f rom normal to reserve holder, temporary power supplies, test switches in alternate positions, temporary blank flanges, and spool 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.
The following tables summarize the temporary system alterations performed during September, 1989.
5.6.1 Unit 2 Temporary r
System Installation Removal Id tttfLLion_H h Diacrip_ tion Date Date 11-66-89 Alteration to lift leads 9-12-89 9-27-89 at panel 902-34 during repair to facilitate replacement of junction box 2TB-38.
11-67-89 Alteration to connect a 9-29-89 9-30-89 local clean domin water station to the condensate reject line during tie-in of the new make-up domin-eralizer piping.
5.6.2 Unit 3 Temporary System Installation Removal Alteration _Ha Descristtion Dale DAte 111-31-89 Alteration to remove 9-1-89 Intermediate Range Monitor (IRM) #16 f rom Control Room panel 903-36 to replace switch S1.
111-32-89 Alteration to disconnect 9-21-89 9-23-89 an electric lead from the 3A Reactor Building exhaust fan lew flow pressure switch in order to adjust the flow sensor (pitot tube).
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5.6.2-Unit 3 (Cont'd) 1' "$l
, Temporary System Installation Removal A11gration No.
Deacriotion Da1.e Date 4
111-33-89 Alteration to disconnect 9-21-89 9-23-89 an electric lead from the 30 Reactor Building exhaust fan. low flow pressure switch to adjust-the flow sensor (pitot tube).
111-34-89 Installation of a jumper at 9-21-89 9-21-89 panel 903-4 for cycling of the shutdown cocling heat
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exchanger inlet valve for post maintenance testing.
111-35-89 Installation of a jumper at 9-22-89 9-22-89 panel 903-4 for cycling of the shutdown cooling heat exchanger inlet valve for post maintenance testing.
111-36-89 Installation of a jumper at 9-29-89 9-29-89 panel 903-4 for cycling of the shutdown cooling heat exchanger inlet valve for post maintenance testing.
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