ML20247B984

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Monthly Operating Repts for June 1989 for Dresden Nuclear Power Station
ML20247B984
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 06/30/1989
From: Paramore G, Reid J
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20246L818 List:
References
NUDOCS 8907240252
Download: ML20247B984 (27)
v • d • e


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MONTHLY NRC SUPMARY OF OPERATING EKPERIENCE, EllAMOIS. TESIS6

_PER REGULATORY CUIDE 1.16 AND 10 CFR 50.59 EQR DRESDEN NUCLEAR POWER STATIM EDfMONWFALTH EDISON COMPANY IJHII DOCEI LICENSE 1 050-010 DPR-2 2 050-237 DPR-19 3 050-249 DPR-25 8907240252 890630 PDR ADDCK 05000010 R PDR 3911a 1

  • TABLE OF CONIEiTji 1.0 Introduction 'I

.l 2.0 Summarv of Op.Arating Experience-2.11 Unit 2 Monthly. Operating Experience Summary "2.2 Unit 3 Monthly Operating Experience Summary 3.0 Operating 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 Uniaue Reportine ReaMirAmenia 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 L4.4 Failed Fuel Element Indications 4.4.1 Unit 2 4.4.2 Unit 3 5.0 Elant or Procedure Changes. Tests. Experiments. and Safety Related Maintenance 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) 5.3 Significant Tests and Experiments Not Described in the FSAR (Units 2 and 3) 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 3911a

1.0 Introduction 1 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.

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 and John Reid of the Dresden Technical Staff, telephone number (815)942-2920 extensions 2364 and 2334 respectively.

3911a l

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f. -, ;2'.0;SUtetARY OF OPERATING EXPERIENCE FOR MAY.1989 i ...- , ? . L. . .

'2.1' UNIT 2' MONTHLY OPERATING EXPERIENCE.

SUMMARY

( 06 i01-89 to.06-30-89, _ Unit'.2l entered the' month'on'line:and. operating at;>

approximately 775 MWe.- The Unit'wasioperated in-l-

Economic Generation Control,'or.as directed by:

the Corporate Load Dispatcher for<the' entire l e-

. ~ month.

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2.0 SUt91ARY OF OPERATING EXPERIENCE FOR MAY.1989.

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2.2 UNIT 3 MONTHLY OPERATING EXPERIENCE

SUMMARY

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06-01-89 Unit 3 entered.the month in cold' shutdown in order c to complete primary containment drywell inner interlock door gasket.' repairs. At approximately.

0545 on June 1,.1989, the Unit'3 reactor was'made-I

.criticaliand the generator was'avnchronized to tim.

grid at 1351' hours'on June 1, 1989.

-.06-02-89.to 06-30-89 Unit 3 remained on line and operated.in_ Economic Generation. Control, or'as directed by the Corporate Load Dispatcher for the' remainder of the month.

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3.0 7 2RA11mG DATA STAillilCS J.hel[0PERA?(NG ' DATA REPORT [ UNIT iWO DOCKET NO. 050-237

.- ' UNIT DRESDEN TWO - I m ,,.

DATE JULY .1,1989 COMPLETED BV G.M. PARAMORE '

TELEPHONE (815) $42-2929 OPERAi!NO STATUS r l.F REPORTING PERIOD: ' JUNE 1989 4ROSS HOURS IN REFCRTING PERIOD: 720

~ 3. ' CURRENTLY AUTHORIZED POWER LEVEL (MWt):

2,527- . MAX DEPEND' CAPACITY (MWe-Net): 772-DESIGN ELECTRICAL RATING (MWe-Net) 794 l 3., POWER LEVEL TO WHICH RESTRICTED (IF ANY).(MWe-Net): N/A

- 4. ; REASONS FOR RESTRICTION (IF ANY): '

s REPORTING FERIOD DATA THIS MONTH YEAR-TO-DATE CUMULATIUF-5.r TIME REACTOR CRITICAL (HOURS) 720.0 3,111.5- 126,657.4

. 6.- . TIME REACTOR RESERVE SHUTDOWN (HOURS) 0.0 0.0' O.0 i F. 7J TIME GENERATOR ON-LINE (HOURS) 720.0 - 3,026.5 121,051.9

8. TIME GENERATOR RESERUE SHUTDOWN (HOURS) 0.0 0.0 'O.0.
9. .' THERMAL' ENERGY GENERATED (MWHt-Gross) 1,382,698 6,666,177 249,158,039 t

10.~ ELECTRICAL ENERGY GENERATED (MWHe-Gross) 434,072 - 2,137,575 79,622,308

" 11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 411 257 2,025,701 75,271,6%

12. REACVOR SERVICE FACTOR (%) 100.0 71.6 75.5 13.' REACTOR AVAILABILITY FACTOR (%) 100.0 't.6 75.5

'14. SERVICE FACTOR (%)' 100.0 .69.7- 72.2 15.' AVAILABILITY FACTOR (%) 100.0 69.7 72.2 il CAPACITY FACTOR (USING MDC) (%) 74.0 60.5 58.1

.17.' CAPACITY FhCTOR (USING DESIGN MWe) (%) 72.0 58.8 56.5

~

.18. FORCED OUTAGE FACTOR (%) 0.0 2.6 11.1 19.' SHUTDOWNS SCHEDULED OUER THE NEXT 6 MONTHS (TVFE, DATE, AND DURATION OF EACH):  ;

125VDC Test Outage, 12-9-89 7 days 20.' IF SHUTDOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP:

N/A l

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'3.0'0PERAilNG' DATA STATISTICS

12, OPERATING D1?A REPORT- UNIT THREE-i

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DOCKET NO. 050-249 UNIT DRES0EN THREE '

If DATE JULY I,1489 COMPLETED.BV 0.M. m M0FE TELEPHCNE(315)-942-2920 3

<DPERATING STATUS i

' l. ' REPORT!kG PERIOD:'. JUNE 1989 LGROSS HOURS IN REPORTING PERIOD: 720 L3.L CURRENTLY AUTHDRIZED POWER LEVEL (MWt': 2,527 MAX DEPEND CAPACITY (MWe-Net): 773 DESIGN ELECTRICAL PATING (MWe-Net) 794

. 3. . POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): N/A H 4. REASONS FOR RESTRICTION (IF ANV):

REPORTING PERIOD DATA

.. = - . . . . . -

THIS MONTH YEAR-TO-DATE ' CUMULATIVE'

' 5.' TIME REACTOR CRITICAL (HOURS) 714.5 3,587.4 116,495.7

6. TIME REACTOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 ~ 0.0
7. flME GENERATOR ON-LINE (HOURS)- 706.1 3,513.2 108,637.3-

' 8. TIME GENERATOR RESERVE SHUTDOWN (HOURS) - 0.0 0.0 0.0

~

9. THERMAL-ENERGY GENERATED (MWHt-Gross) 1,4 1 509 8,067,034 223,051,493
10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 451,275 2,614,921 72,083,630~
11. ELECTRICAL ENEPGY GENERATED (MWHe-Net) . 424 315 2,492,393 68,229,819

.12.~ REACTOR SERUICE FACTOR (%) 99.2 82.6 74.1

13. REACTOR AVAILABILITY FACTOR (%) 99.2 82.6 74.1 214. SERVICE FACTOR (%) ' 6.1 80.9 69.1

.15. AVAIL!81LITY FACTOR (t) , 46.1 80.9 69.1

'M. CAPACITY FACTOR (USING MDC) (%) 77.1 74.2 56.1

'17. CAPACITY FACTOR (USING DESIGN MWe) (%) 75.1 72.3 54.6

.'18. FORCFD OUTAGE FACTOR (%) 1.9 6.1 12.5 o

cle. SHUTS)0WNS SCHEl/ULED DVER THE NEXT 6 MONTHS (TYPE, LATE, AND DUFATION OF EACH): .

Refuel Outage, 12-19-89,11 weeks 120. lF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STAFTUF:

N/A

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3.3 AVERAGE DAILY UNIT POWER LEVEL 3.p., ,

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[DOCKETNO. 050-237

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. UNITJI -

DATE July 1.'1989

> COMPLETED BY J. Reid TELEPHONE 815/942-2920-MONTH ' JUNE. 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER' LEVEL.

~(MWe-Net) (MWe-Net)

-1i 720 17 '647

.2- 614' 18 544 a

_3:

505 19 747-4: :519~ 20- 767 5 573 21 656' 6 597 22 4646 ,_ :

7 '60'2 23 761-8~ 606 24 576 9 5t 3 25 4 92 10- 283 26 506

'11 438 27 '507 12 661 '28 549 -

13 '350 29 '537 14- 469 30 578 ._

'15 531 31 _

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, 3.4 AVERAGE DAILY UNIT POWER ~ LEVEL S- DOCKET NO. 050-249 UNIT III-4

.DATE.A ly 1. 1989 COMPLETED BY'J. Reid TELEPHONE _815/942-2920 1 ..

' MONTH: JUNE. 1989 l.

l . DAY ' AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY-POWER LEVEL <

.(MWe-Net) (MWe-Net)'

1 112 17 650 i

2 ~477- 18 550 3 513 19 728

-4 437 20 _

750

. 5' 583 21 '662 6 599 22 656

'7 678- '23 762 8 666 24 567' 9 610 25 474-10 503 26 494 11;. 445 27 604 12 668 28 708 13 654 29 623 14 707 30 ,

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HOUR. ~ MAXIMUM DAILY' LOAD-

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ENDING --  : KW 1 2300 1.251.900 2 ~0100- 1.250.300 3 2300 1.099.400-

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4 0100 1.019.000-5 2300' 1.370.600 6 2400 -1.451.200

'7 1600 1.407.900 8 0100 1.396.000 9' 1800 1.413.600 (0 0100- 939.600' 11 2400 1.198.500 12 -1900 '1.526.400 13 0100 1.318.500 14 2400 1.310.500 15' 1300 1.310.200

'16 1700 1.47L3000 17 0100 1.409.400 18 2400 1.370.300

___19 1400 '1.575.500 20 2300 1.594.500 21 2200 1.580.000 22 2200 1.586.100-23 1200 1.594.200 24 1700 1.403.500 l 25 2400 1.044.800 1'

26 0700 1.044.900 1.246.900 27 2200 28 1800 1,.372.300 29 1300 1.344.500 30 1700 1.468.700 l

3911a

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4.0 UNIOUE REPORTING REQUIREMENTS 4.1 MAIN-STEAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period, June, 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 resulting in its actuation.

No. and Type Valves of Plant Description Unil Data Actuated Actuations Conditiona of Eventa 2 No Unit 2 main steam relief and/or safety valve actuations occurred during this reporting interval.

3 No Unit 3 main steam relief and/or safety valve actuations occurred during this reporting interval.

3911a

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't4.2, -0FF-SITE DOSE CALCULATION MANUAL CHANGES h > ,-

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

l ;o June,'1989.

I i4;3. -MAJOR' CHANGES TO THE RADI0 ACTIVE WASTE TREATMENT SYSTEMS I

l 'There were no major' changes-to.the radioactive waste treatment systems at Dresden during Jur. 1989. 'A commercial vendor is: hired to package.-

process, and , transport solid radioactive ^ wastes to burial in' accordance-

.with 49CFR, 10CFR71,' and 10CFR61 ruidelines.

4.4 FAILED FUEL' ELEMENT INDICATIONS

.4.4.1 Unit =2

'Dresden. Unit 2 fuql performance during June 1989 continued to~ ster no

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'indicatio'ns of leaking fuel.- This.is. based on the sum of t!.i c-activities of the six noble gases as measured at the condanser off-gas.

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recombiner. . Based on the reported data, Unit 2 han acceptable fuel.

performance during. June, 1989.

4.4.2 Unit 3' i

Dresden Unit 3 fuel performance during June .1989 continued. to. show no indications of leaking fuel.. This is based'on'the sum of the activities of .the six noble gases as ineasured at the condenser off-gae recombiner. Based on the reported dae.a. Unit 3 had acceptable fuel performance during June 1989..

I 3911a I

, _ w 'i j ,7 s , , 4"s N)M M< 3p 5;0' 'P.LANT OR' PROCEDURE CHANGES. TESTS; EXPERIMENTS. AND SAFETY RELATED .

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.5.1; . Amendments to Facility' License or Technical Specifications d A

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

5.1.1 ' Unit 2 'None f.

L. 5.1.2 Unit 3 None 19 ll~

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5.2 Changes to Procedures Which are. Described in tite FSAR~ (Units-.2 and 3)

Table 5.2.1, attached, summarizes the revisions to. procedures described in the FSAR which were approved during the month of-June,.

1989.

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.(UNITS 2 and 3)

Significant special procedures involving tests not described in the

.FSAR which were approved during the month of May 1989 are listed below.

Procedure No. Procedure Title / Description SP 89-6-64 2/3 Core Height Containment Cooling /Drywell Spray Interlock-This Special Procedure was written to validate the upgrade of an instrument-surveillance.

SP 89-6-65 Diesel Generator' Equilibrium Temperature Determination This Specia1' Procedure was written to record

. Diesel Generator lube oil'and cooling water temperatures at 5-minute intervals concurrently with the scheduled performance of DOS-6600-1, Diesel Generator Surveillance Tests.

SP 89-6-69 Unit 3 Low Pressure Coolant Injection Syctem F*ow Calibration This Special Procedure was written'to separate routine maintenance activities from refuel outage surveillance activities.

SP89-p-70 Operation of Evaporative Cooler This Special Procedure was written-to clarify start-up and operating instructions for the Reactor Building ventilation system evaporative cooler.

5.4 Safety related maintenance (Units 2 and 3)

Safety related maintenance activities are summarized in the attached tables.

3911a

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.S.5 Completed Safety'Ralated Modifications (Units'2 end 3)

  • f * ,

-qr

' Unit 2 and Unit-3 safety related modification packages closed during the month of. June, 1989 are listed below. Only modifications wl.ich have been-completely closed are listed;~ modifications which are authorized for use. E 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.

6 Modification No. Description M12-2-86-28 This. modification provides for the conversion of

l. existing manually operated control rod drive (CRD) pump discharge valves to motor operated l valves.' The motor operated valves will have the L capability of being operated from the main control room.

M12-3-89-l' This modification provides for the installation of upgraded seismic supports on high pressure coolant injection'(HPC1) steam supply line' drain pot valves 3-2301-29 and 3-2301-30.

3911a

_ _ - _ _ _ _ _ _ _ _ _ _ - _ - - _ _ _ _ - _ -=

5.6 T;mpor2ry System Alteratic..a (Unit 2 cnd Unit 3) e p3 -

a

. A " Temporary System Alteration" refers to electrical jumpers, lifted l

1eads,- removed fuses, fuses turned to non-conducting position, fuses moved from normt1 to reserve holder, temporary power supplies, test switches in citernate positions, temporary blank flanges, and spool pieces. Alterations controlled and documented as part of a routing 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 June, 1989.

5.6.1 Unit 2 Temporary System .

Insta11a.. Removal Alteration Nat Description Da*. e Date 11-43-89 Alteration to remove 6-9-89 6/22/89 steam isolation valve 2/3-2001-272 to waste concentrators 2/3-2021A and B and the addition of two blind flanges in its place to alleviate leakage during 2/3 radwaste reboiler operation pending repairs.

11-44-89 Alteration to permit 6-13-89 6-23-89 operation of M02-1001-2B during testing.

II-45-89 Alteration to temporarily 6-16-C9 -

install a clamp on the HPCI oil filter assembly to ensure proper sealing.

11-46-89 Altera^ ion to relocate 6-22-89 6-27-89 a security camera.

II-47-89 Alteration to de-energize 6-23-89 6-23-89 a relay breaker in order to adjuwt a contact arm during repair of the HPCI turbine exhaust drain pot bypars valve.

11-48-89 Alteration to defeat 6-2o-89 6-28-89 isolation logic for operation of M02-1001-2B during testing.

3911a

s c0

' _( ,, . ..

.y ..

1*-

.--3.6.2:iUnit 3i

~

Temporary Removal.

System: . ..

-Installation Alteration No. Description Dalg 'Date III-15-89 Alteration to bypass room: 6-8-89 -

. drywell/ torus differential-

- pressure.(dP.) indicator 1

DP1.3-1602-15 and cllows

the;drywell/ torus dP to-be displayed on computer

~

trend recorder 942-7A.

!*I-16-89 - Alteration'to temporarily. . 6-16-89 -

install a clamp on~the HPCI oil filter assembly to ensure proper aealing.

111-17-89 Alteration'to bypass. 6-20-89 6-21 " off-gas recordr*

(RR-3-1705-13) for troubleshooting.

III-19-89 Alteration to remove the 6-21-89 23-89

isolation condenser /drywell atmosphere recorder-(TR-3-1340-1).for j troubleshooting.

a) 111-20-89 Alteration,to remove 6-23-89 6-23-89 B isolation condenser vent radiation monitor power supply from panel 903-56 for repair / calibration.

l.

1 h

3911a L

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