Text

Monthly Operating Repts for Mar 1989 for Dresden Units 1,2 & 3
	ML20245A154
Person / Time
Site:	Dresden
Issue date:	03/31/1989
From:	Eenigenburg E, Paramore G; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
	89-312, NUDOCS 8904250079
	Download: ML20245A154 (34)
	v • d • e

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MONTHLY NRC 1

SUMMARY

OF OPERATING EXPERIENCE, CHANGES,' TESTS, AND EXPERIMENTS PER REGULATORY GUIDE 1.1.6 AND 10 CFR 50.59 FOR l DRESDEN NUCLEAR POWER STATION COMMONWEALTH EDISON COMPANY IMll DOCKET LICENSE 1 050-010 DPR-2 2 050-237 DPR-19 3 050-21,9 DPR-25 i

8904250079 890331 m DR ADOCK 05000010 PNU ...

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TABLE OF CONTEMTS 1.0 Introduction 2.0 Summary of Operating Experience 2.1 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 _ 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 5.0 Plant 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 3431a

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'1.0 Introduction The Dresden Nuclear Power Station is three-unit facility owned by Commonwealth Edison Company _and located near Morris, Illinois. Unit 1, a General Electric Boiling Water Reactor with a design net electrical-output rating of 200 megawatts electrical (MWe), is retired with all fuel removed from the reactor vessel. Therefore, no Unit 1 operating data is provided within this report. Units 2 and 3 utilize General Electric Boiling Water Reactors and have an initial design net electrical output rating of 794 MWe. 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 the Dresden Units was Sargent and Lundy.

T'ils report was compiled by Gerrine Paramore of the Technical Staff, telephone number (815)942-2920 extension 2364.

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l 2.0

SUMMARY

OF OPERATING EXPERIENCE FOR MARCH, 1989

. 2.1 UNIT 2 MONTHLY OPERATING EXPERIENCE

SUMMARY

03-01-89 to 03-03-89 Unit 2 entered the month on line and operating at approximately 770 MWe.

03-04-89 to 03-06-89 At approximately 0849 hours0.00983 days 0.236 hours 0.0014 weeks 3.230445e-4 months on March 4. 1989, while performing ground checking of the Unit 2 125V DC battery system, the Unit 2 reactor scrammed en low water level due to loss of the reactor feed pumps (RFPs). The RFPs tripped as a result of a High Voltage Operator (HVO) inadvertently opening a breaker which resulted in the RFPs sensing a lubricating oil system failure. At 2156 hours0.025 days 0.599 hours 0.00356 weeks 8.20358e-4 months on March 5, 1989, the reactor was again made critical, and the generator was synchronized to the grid at 0609 hours0.00705 days 0.169 hours 0.00101 weeks 2.317245e-4 months on March 6, 1989.

03-07-89 to 03-09-89 Unit 2 increased to steady load and maximum core flow.

03-10-89 At 0358 hours0.00414 days 0.0994 hours 5.919312e-4 weeks 1.36219e-4 months on March 10, 1989, during performance of a main turbine overspeed trip test, the generator was separated from the grid.

During the overspeed trip test, the turbine mechanical overspeed setpoint was observed to be slightly below its ideal range. The generator was again synchronized to the grid at 0334 hours0.00387 days 0.0928 hours 5.522487e-4 weeks 1.27087e-4 months on March 10, 1989. Adjustments and reperformance of the overspeed trip test were then scheduled.

03-11-89 to 03-16-89 Unit 2 operated at increasing loads until maximum core flow was reachs.d. On Mrrch 16, 1989 at 2353 hours0.0272 days 0.654 hours 0.00389 weeks 8.953165e-4 months , the Unit 2 ger.erator was again taken off line to perform a turbine mechanical overspeed setpoint adjustment and testing in accordance with Special Procedure 89-3-33. The generator was again synchronized to the grid on March 17, 1989 at 0743 hours0.0086 days 0.206 hours 0.00123 weeks 2.827115e-4 months .

03-17-89 to 03-31-89 For the remainder of the month, Unit 2 remained on line and operated as directed by Lt.e load dispatcher.

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2.0

SUMMARY

OF OPERATING EXPERIENCE FOR MARCH, 1989

- 2.2 UNIT 3 MONTHLY OPERATING EXPERIENCE SUMHARY 03-01-89 to 03-24-89 Unit 3 entered the month on line and operating at approximately 740 MWe.

03-25-89 to 03-29-89 At 0133 hours0.00154 days 0.0369 hours 2.199074e-4 weeks 5.06065e-5 months on March 25, 1989 with Unit 3 operating at 89% rated core thermal power, the 345 KV switchyard experienced a fault on Power Circuit Breaker (PCB) 8-15. As a result, Local Breaker Back-up (LBB) logic automatically isolated PCB 8-15. This resulted in the loss of Unit 3 reserve auxiliary transformer (TR) 32. Automatic transfer of 4KV Bus 32 from TR32 to Unit 3 auxiliary TR 31 did not occur quickly enough to prevent undervoltage trips of the 3B Reactor Feed Pump (RFP) and the 3B reactor recirculation pump. The Standby 3C RFP then automatically started upon completion of the 4KV Bus 32 transfer process, and a rapid reactor water level increase to the automatic main turbine and RFP trip setpoint could not be prevented. Subsequently, an automatic reactor scram occurred as a result of i turbine stop valve closure. Immediate actions were to shut down the Unit 3 reactor in a controlled arcnner and initiate the restoration of off-site power.

On March 28, 1989 at 2355 hours0.0273 days 0.654 hours 0.00389 weeks 8.960775e-4 months , the reactor was again made critical and the generator was synchronized to the grid on March 29, 1989 at 1142 hours0.0132 days 0.317 hours 0.00189 weeks 4.34531e-4 months .

03-30-89 to 03-31-89 At 1252 hours0.0145 days 0.348 hours 0.00207 weeks 4.76386e-4 months on March 30, 1989, during surveillance of the Reactor Protection System (RPS) Electrical Protection Assembly (EPA) relays, the Unit 2 reactor scrammed due to the spurious tripping of EPA relays 3A-1 and 3A-2. Testing of releys on the normal feed to "A" RPS Bus had been completed and the HVO had then switched "A" RPS bus f rom reserve feed to normal feed. The "A" RPS Bus would not immediately reset due to a coincident Main Steam Line (MSL)

Radiation Monitor signal. Before the HVO could return the "A" RPS Bus to reserve feed, EPA relays 3A-1 and 3A-2 spuriously opened and consequently de-energized the "B" RPS Bus. The de-energized "B" RPS BUS combined with the coincident half scram signal on RPS Channel "A" resulted in the unplanned reactor scram. Inspection, testing and repair of the EPA relays was then initiated.

At 1314 hours0.0152 days 0.365 hours 0.00217 weeks 4.99977e-4 months on March 31, 1989, the Unit 3 reactor was again made critical and the generator was again synchronized to the grid on March 31, 1989 at 2206 hours0.0255 days 0.613 hours 0.00365 weeks 8.39383e-4 months .

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V 3.0 OPERATING DATA STATISTICS

. ,3.1 GPE3ATING DATA REPORT- UNIT TWO -

DOCKET NO.' 050-237

. UNIT DRESDEN TWO

- DATE APRIL 1,1989 COMPLETED BY 0.M. PARAMORE TELEPHONE (015)-942-2920 OPERATING STATUS

1. SEPORllNG PERIODS. MARCH 1989 GROSS HOURS IN REPORTING PERIOD: 744

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2,527 -MAX DEPEND CAPACITY (MWe-Met): 772

' DESIGN ELECTRICAL RATING (MWe-Net) 794

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): n/a

4. REASONS FOR RESTRICT!0N (IF ANY): ,

I REPORTING PERIOD DATA

= ...................

THIS MONTH YEAR-TO-DATE CU?IULATIVE

' 5. TIME REACTOR CRITICAL (HOURS) 684.6 906.2- 124,452.1

6. TIME REACTOR RESERVE SHUTDOWN (".UURS) 0.0 0.0 0.0

.7. TIME GENERATOR ON-LINE (HOURS) 689.2 843.5 118,868.9

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

9. THERMAL ENERGY GENERATED (MWHt-Gross) - 1,589,657 1,787,114 244,278,976

10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 519,389 579 865 78,064,598

11. ELECTRICAL ENERGY GENERATED.(MWHe-Net) - 495,251 546,013 73,788,919

12. REACTOR SERVICE FACTOR (%) 92.0 42.0 75.2 13.' REACTOR AVAILABRITY FACTOR (%) 92.0 42.0 75.2

-14. SERVICE FACTOR (%) 92.6 39.1 71.8

15. AVAIL!BILITY FACTOR (%) 92.6 39.1 71.8

16. CAPACITY FACTOR (USING MDC) (%) 86.2 32.7 57.7

17. CAPACITY FACTOR (USING DESIGN MWe) (%) 83.8 31.8 56.1

18. FORCED OUTAGE FACTOR (%) 7. 4 8.6 11.3 L

l l 19. SHUTDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYFE, DATE, AND DURATION OF EACH):

20. IF SHUTDOWN AT END OF REPORT PERIOD, ESilMATED DATE OF STARTbP:

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. 3.0 OPERATING DATA. STATISTICS

'3.2 OPERAflNG DATA REPORT- UNIT THREE DOCKET NO. 050-249

, . UNIT DRESDEN THREE

. DATE APRIL 1,1989 COMPLETED BV 0.M. PARAMORE-TELEPHONE (815)-942-2920

.0PERATINU STATUS

1. FEPORTING PERIOD: MARCH 1989 GROSS HOURS IN REPORTING PERIOD: 744 L

'2. CURREh7LY AUTHORIZED POWER LEVEL (MWt): 2,527 MAX DEFEND 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 RESTRICTION (IF ANY):

REPORTIN9 PERIOD DATA THIS MONTH YEAR-TO-DATE CUMULAT!UE

5. TIME REACTOR CRITICAL (HOURS) 623.7 2,039.7 114,948.0

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

7. TIME GENERATOR ON-LINE ; HOURS) 604.6 2,001.1 10 7,125.2

8. TIME GENERATOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0 l 9. THERMAL ENERGY GENERATED (MWHt-Gross) 1,430,195 4,770,641 219,755,100

10. ELECTRICAL ENER0Y GENERATED (MWHe-Gross) 468,791 1,565,320 70,954,029

!!. ELECTRICAL ENERGY GENERATED (M;iHe-Net) 447,563 1,495,703 67,233,129

12. REACTOR SERVICE FACTOR (%) 83.8- 94.4 74.1

13. REACTOR AVAILABILITY FACTOR (%) 83.8 94.4 74. :

14.' SERVICE FACTOR (%) 81.3 92.6 69.1

15. AVAILABILITY FACTOR (%) El.3 92.6 69.1 j

16. CAPACITi FACTOR (USING MDC) (%) 77.8 89.6 56.1

17. CAPACITY FACTOR (USING DESIGN MWe) (%) 75.8 87.2 54.6 l

18, FORCED OUTAGE FACTOR (%) 18.7 7.4 12.6

19. SHUTDOWNS SCHEDULED OUER THE NEXT 6 MONTHS (TYFE, DATE, AND DURATION OF EACH):

20. IF SHUTDOWN Ai END OF REPORT PERIOD, ESTIMATED DATE OF STARTUF:

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'3.'3 AVERA0E DAILY UNIT POWER LEVEL gee-Net) DOCKET N0. 050-237 UNIT DRESDEN TWO DATE april 1, 1989

- COMPLETED BY 0.P. PARAMORE TELEPHONE (815)-942-2920-REPORT FERIOD: MAECH 1989 DAY POWER DAY POWER I 762 17 331 2 777 18 690 3 778 19 735 4 265 20 752 5 -8 21 771 6 309 22 779 7 591 23 775 l 8 728 24 773 1

9 734 25 761 10 403 26 764 11 648 27 776 12 682 28 780 I 13 768 29 777 l

l 14 776 30 779 15 700 31 778 16 697 l

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' 00CKE0 N0, 050-249 l 3.4' AVESA5E DA!LY UNIT P0 vet LEVEL Ee-Net) -

I UNIT DRESDEN THREr -l DATE APRIL 1,1989

. COMPLETED BY G.P. PARAMORE TELEPHONE (815)-942-2920 i

1 0 PEPORT PERIOD: MARCH 1989 I

DAY - POWER DAY POWER .

l 760 17 793 ']

2 783 18 784 1

3 797 19 796 .l i

4 792 20 7 94 l J

5 664 21 795 l I

6 780 22 793 j

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'8 757 24 782 j

9 768 25 40

.10 720 26 -8 ?

11 716 27 -8 !

12 559 28 -8 ;

13 719 29 199 14 775 30 266 15 780 31 2 16 792

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3.7 STATION MAXIMUM DAILY ELECTRICAL LOAD DATA
..' DRESDEN STATION MARCH, 1989 OUR MAXIMUM DAILY LOAD DAY ENDING KW l
1 1300 1.612.200 l 2 1800 1.628.800 3 1600 1.634,19.0 4 0100 1.620.600 i
5 0100 749.400 6 1600 __
1.313.300 7 2300 1.496.700 8 _1600 1.601.000 9 1800 1.631.600 10 23D.0 1 381.800 11 2200 1.504.600 12 2400 1.402.600 13 2000 1.598,800 14 1500 1 623.500 15 1900 1.621.000 16 0200 1 41H 200 17 2400 1.442.400 18 1500 1.579.500 19 1300 1.635.100 20 1600 1.603,400 21 1600 1.625.800 22 1200 1.622.200 23 0200 1.614.800 24 0000 _
0*
___25 0100 1.540.100 26 . 2300 799.90D 27 1500 810.600 28 0400 809.800 29 2400 1.320.200 30 1000 __ 1.378.900 31 2400 938.000
Data unavailable due to computer problem 3431a
4.0 UNIQUE REPORTING REQUIREMENTS 4.1 MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period, March, 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 ita actuation.
No. and Type Valves of Plant Description Unil Dale Actuated Actuations Conditions of Events 2/3 3/01/89- Safety V1v 5 Bench N/A The listed spare 3/31/89 Serial Nos. Tested safety valves were BK 6282 tested during March BK 6304 1989 and rebuilt BK 6527 for future use.
2 3/15/89 2-203-3A The relief valves were opened during performance 2-203-3B of Dresden Operating Surveillance (DOS) 250-5, 2-203-3C as required by Technical Specification 4.5.C.2 2-203-3D with the High Pressure Coolant Injection 2-203-3E system inoperable.
l l
3431a l
L _ _ _ _ -- - . _ _ _ _ . - _ - _ - -
j 4.2 .OFF-SITE DOSE CALCULATIONS MANUAL CHANGES None 4.3 MAJOR CHANGES TO THE RADIOACTIVE WASTE TR'_AIMENT SYSTEMS None 4.4 FAILED FUEL ELEMENT INDICATIONS 4.4.1 Unit 2 None 4.4.2 Unit 3 None l
l l
l l
l l
3431a
_ _ _ _ _ . _ _ _ _ . _ _ _ _ _ )
5.0 PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE ;
5.1 Amendments to Facility License or Technical Specifications The license amendments and/or Technical Spec 2fication changes which were approved and implemented for use during the reporting period are listed below.
5.1.1 Unit 2 l
None 5.1.2 Unit 3 None 5.2 Changes to Procedures Which are Described in the FSAR (Units 2 and 3)
Table 5.2.1, attached, summarizes the revisions to procedures desetibed in the FSAR which were approved during the month of March, 1989 3431a x___----._.
_ RE 4,
_ AG MN 2, MA 2, 2, UH 1 .
SC 1 1 d e
g n
a h
c n
d u e
) ge 3 nr au D r hd N o ce A c t nc i o uor 2 t M ep a n S m ) o r T o I i uf I r Ct n d o N t P a o e U c R c i ct
( e ( i t on re l f a R E ni c pt A or i n S f i e f fi F o tV i o N c r ,
E O e ey e t r H I c jt V c eq T T n ni P a I l y t l N I n i t .$ o I R e t b i did C t na l e o D S n ar i g;h 1 E E i l e b . nt t B D a op a d ane M oO r eh gcmem I /
2 R E C e 5 C L d e p nnpn S T ns ev O auio E E I ae rl h ui L D T v ua m c eqt B nl sV e nrea A E E oa s t uu r T R R iV ed s d wb A U t re y eeei D cf Pt S rcnl H E ee a uo a C C pi h r I d rrc I O sl ge C epo/
H R ne i p P c f g W P I. R HO H of rosi n
S p t t E t ns k f nee U oemt D t e E . t nrd C O niie O N e t ,
uv qo R 5 1 3 P E 3 - - nner i orp R - 0 0 O U 0 0 0 i m T D 0 3 3 . ;t ei E 2 2 2 eat S C gcat E O P S S nirn G R M O O af oe N P D D D hi pm A crre H aol C el cp i
vcnm ii
t. r e r ooo c 'g )S rf t t n t a nO sddd E
P n) eP i D t(
i eee nggg Y t M a i nnn T nD re maaa i( e c dhhh E a pn ACCC R Me O a U r l D nu nl . . ..
1 234 E ed ei C d e d e O s c s v :
R eo er S a P rr ru E T
1 DP DS 3 O 4 N 3
! 1
. o 5.3 Significant Te'tss and Experiments Not Described in the FSAR (UNITS 2 and 3)
Significant special procedures involving tests not described in the FSAR which were approved during the month of March 1989 are listed below. I Procedure No. Procedure Title / Description SP 89-3-23 Inspection and testing of a modification to the Unit 2 Reactor Peilding trackway fire suppression system.
SP 89-3-24 Test procedure ior a modification to the primary containment air sampling system.
SP 89-3-25 Test procedure for a modification to the Low Pressure Coolant Injection and Core Spray pump room sump pump.
SP 89-3-26 Test prucedure for a modification involving re-arrangements of torus vacuum relief valve control switches.
SP 89-3-27 Procedure for analyzing the response characteristics of the Unit 2 High Pressure Coolant Injection (HPCI) flow controller.
SP 89-3-30 Modification test procedure to calibrate and verify operability of the Unit 2/3 Service Water Effluent Radiation Monitor.
SP 89-3-31 Modification test procedure to verify proper response of the Unit 2 and Unit 3 Reactor Building Equipment Drain Tank level indication.
SP-89-3-32 Modification test procedure to test various components of the Security fence intrusion detection system.
SP-89-3-33 Performance of a main turbine mechanical overspeed trip setpoint adjustment.
SP-89-3-36 Carbon Dioxide fire suppression system test procedure.
SP-89-3-40 Calibration procedure for the priraary containment post accident hydrogen and oxygen analyzers.
5.4 Safety related maintenance (Units 2 and 3)
Safety related maintenance activities are summarized in the attached tables.
3431a
(
5.5 Completed Safety Related Modifications (Units 2 and 3)
Unit 2 and Unit 3 safety related modification packages closed during the month of March, 1989 are listed below. Only modifications which have been completely closed are listed; modif4. cations 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 l
M12-2-85-94 The objective of this modification v:as to increase the reliability of the Unit 2 diesel generator. By replacing the engine idler gear stubshaf t assembly and lower idler gear -
l turbocharger components with more reliable ones, gear wear was reduced. This modification is designed for partially loaded accelerated starts or full speed applications. The safety evaluation concluded that the replacement of the above components does not affect the design or operability characteristics of the diesel generator.
M12-2-86-27 Modification of the Unit 2 Emergency Core Cooling cad System (ECCS) pump minimum flow valve logic to M12-2-86 provide the control room operator with the ability to close the minimum flow valves even with an accident signal present. The safety evaluation concluded that the logic changes provide a minimum flow path for ECCS pumps in order to prevent dead-heading without jeopardizing the' containment isolation function.
M12-2-88-005 This modification replaced one set _of feed breakers in the Low Pressure Coolant Injection (LPCI) swing Motor Control Center (MCC) with contactors and eliminated an interlock which had.
prevented simultaneous closure of the feed breakers to permit transfer of the LPCI switch MCC during a loss of Division II AC power supply concurrent with a postulated loss of Division II Direct Current (DC) control power. The safety evaluation concluded that permitting one contactor to be the sole isolation between the normal and alternate power sources will enhance availability of power to the LPCI components.
3431a i
l l
. 5.5 Complete <1 bei'ty Related Modifications (Units 2 and 3) ,
Modification NL Daneription l i
til2-2/3-86-10 This modification replaced the existing Unit 2 l 138KV switchyard battery and installed seismically qualified racks to support the batteries.
)
3431a 1
s-s' .,
5.6 Temporar;r System Alterations (Unit 2 and Unit 3)
~
A "Temporar;r System Alteration" refers to electrical jumpers, lifted-leads, removed fuses, fuses turned to non-conducting position, fuses moved from 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 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 March, 1989.
l 3431a L
L _ _ - __ _ _ - _ _ -__-_-
's' ,
. 5.6.1 Unit 2 Temporary System Installation Removal Alteration No. Description Da.te Date 11-17-89 Alteration to permit 3-4-89 3-5-89 operation of the shut-down cooling system with an open thermocouple on the "A" recirculation pump.
II-18-89 Removes the Reactor Water 3-6-89 3-6-89 Cleanup (RWCU) blowdown flow controller to replace the scale and to perform a calibration.
II-19-89 Alteration permits an 3-7-89 3-8-89 instrument loop calibration ,
~
to be performed on the level instrumentation for the Unit i decontamination storage tank 1150.
II-20-89 Same as 11-19 for 3-7-89 3-8-89 tank 115B 11-21-89 Same as II-19 for 3-7-89 3-8-89 tank 115A II-22-89 Same as II-19 for 3-7-89 3-8-89 tank 115D II-23-89 Alteration utilized to 3-8-89 3-8-89 troubleshoot jet pump 12 and 13 flow instrumentation 11-24-89 Removed HPCI speed indicator 3-9-89 3-9-89 to replace the scale and to j calibrate the indicator II-25-89 Removed the head cooling 3-13-89 3-13-89 flow controller to replace the scale and to calibrate the controller II-26-89 Disconnected Economic 3-17-89 -
Generation Control (EGC) system input to perform EGC testing 3431a
1 i
& , 1
, , 1 5.6.1 . Unit 2 (Continued)
Temporary System Installation Removal A11gration Not Description Datn Date 11-27-89 Alteration permitted 3-21-89 3-21-89 the Turbine Building differential pressure switch calibration without tripping the exhaust fans II-28-89 Alteration gagged open 3-24-89 4-4-89 condensate demineralized $
transfer valve 2-5503 to j install a demineralized bed II-31-89 Alteration clears a 125V DC 3-31-89 -
ground on the drywell equipment drain sump I
t
( 3431a
L,,,.
L . .-
! . 5.6.2 . Unit 3 L
[ Temporary l System Installation Removal Alteration No. Description Daig Date III-8-89 Installed an Agastat 3-28-89 -
time delay relay on Motor Control Center o (MCC) 38-7/39-7 pending completion of a permanent modification III-9-89 Removed failed RPS EPA 3-30-89 3-31-89 relay 3A-1, installed EPA 3AB-2 in its place, and installed a jumper from SAB-1 to the Reaction Protection System (RPS)
Bus Breaker, during repairs and testing of the RPS EPA relays.
3431a
MO s Common:ealth Edison Dr sd:n NucleIr Pow r St1 tion R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 April 1, 1989 EDE LTR: #89-312 Director, Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk
Subject:
i.unthly Operating Data Repcrt I Dresden Nuclear Power Station Commonwealth Edison Company Docket Nos. 50-237 and 50-242 Centlemen:
Enclosed is the Dresden Nuclear Power Station Monthly Operating Summary Report for March 1989. This information is supplied to your of fice in accordan e with the instructions set forth in Regulatory Guide 1.16.
Please note that the report format has been restructured in order to provide a more comprehensive data base. Beginning with the January, 1989 report, the information which had been previously submitted to your attention on an annual basis in accordance with 100FR50.59 is being included on a monthly basis as pert of the monthly summary report. In this manner, the 10CFR50.59 reporting information (including descriptions of facility changes, tests and experiments) will be submitted in a more timely manner.
Sincerely, f ,Y (C '
E. D . Eep ge bur Station Man ger t
Dresden Nuclear Power Station EDE:GP:jmt Enclosure ec: Region III, Regulatory Operations, U.S. NRC Chief, Division Nuclear Safety, State of IL U.S. NRC, Document Management Branch Nuclear Licensing Administrator Nuc. Sta. Div. Vice Pres.
Manager, Tech. Serv. Nuc. Sta.
G. Paramore (2)
NRC Senior Resident Inspector Site Quality Assurance Superintendent BWR Engineering Group g Comptro11er's Office /
PIP Coordinator INPO Records Center I l
File /NRC Op. Data File / Numerical 3431a j
- - - - - - _ _ _ _ _ _ l

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