ML17199X994

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Monthly Operating Repts for Apr 1988
ML17199X994
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 04/30/1988
From: Eenigenburg E, Maxwell D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-349, NUDOCS 8805200068
Download: ML17199X994 (20)
v • d • e


Text

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~...

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OPERATING DATA REPORT DOCKET NO.

""'0..::.5..::.0_-2>:;3~7=------

DATE May 4, 1988 COMPLETED BY D.C. Maxwell TELEPHONE 815/942-2920 OPERATING STATUS

1.

Unit Name: --=D.::.r.:.e.:::.s=de=n=-=II=---------------

NOTES

2.

Reporting Period: _ _.::;.:A:.o;.p=r-=i=l.._, -=l 9"-8;;;...8;;;...._ _________ _

3.

Licensed Thermal Power (MWt):

--=2..&...:;..5=2~7------~

4.

Nameplate Rating (Gross MWe): ----"-8=28"'----------

5.

Design Electrical Rating (Net MWe): -~7~94~----~

6.

Maximum Dependable Capacity (Gross MWe): -=81=2=-----

7.

Maximum Dependable Capacity (Net MWe): __

7~7~2=-----

8.

If Changes Occur in Capacity Ratings (Items 3 Through 7) Since Last Report, Give Reasons:

N/A

9.

Power Level to Which Restricted, If Any (Net MWe):

NIA

--="-=--------------

10.

Reasons For Restrictions, If Any: --~N=/~A=----------------------~

This Month Yr-to-Date Cumulative

11.

Hours in Reporting Period 719 2 903 157.487

12.

Number of Hours Reactor Was Critical 719.0 2.903.0 119.474

13.

Reactor Reserve Shutdown Hours 0

0 0

14.

Hours Generator On-Line 719.0 2.903.0 113. 996

15.

Unit Reserve Shutdown Hours 0

0 0

16.

Gross Thermal Energy Generated (MWH) 1,582,076 6.561.536 234.537.399

17.

Gross Electrical Energy Generated (MWH) 502.653 2.097.836 75.036.829

18.

Net Electrical Energy Generated (MWH)

_:...;~~...:;_-

479 709 1.998.971 10.923.961

19.

Unit Service Factor

.100.0 100.0 72.4

20.

Unit Availability Factor 100.0 100.0 72.4

21.

Unit Capacity Factor (Using MDC Net) 86.4 89.2 58.3

22.

Unit Cap~.city Factor. (Using DER Net) 84.0 86.7 56.7

23.

Unit Forced Outage Rate 0.0 0.0 11.6

24.

Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

One week outage in May 1 1988 for a dual unit outage to perform the 125V DC battery discharge test and the refueling outage is scheduled for September, 1988.

25.

If Shut Down At End Of Report Period, Estimated Date of Startup: -~N~/A=-------~

0820t/l

8805200068 880430 1'

PDR ADOCK 05000237

_._R DCD

,~J

1.
2.
3.
4.
5.
6.
7.
8.

OPERATING DATA REPORT DOCKET NO.

=0=5~0-~2~4~9=------

DATE May 4, 1988 COMPLETED BY D.C. Maxwell OPERATING STATUS Unit Name:

Dresden III Reporting Period:~--=A~p=r=i=l~*--=1~98~8~---------

Licensed Thermal Power (MWt): ---=2~5~2~7'---------

Narneplate Rating (Gross MWe): ___

8~2~8"---------

Design Electrical Rating (Net MWe):

-~79~4-=------~

Maximum Dependable Capacity: (Gro~s MWe): -=81=2=-----

Maximum Dependable Capacity (Net MWe): __

7~7~3'-----

TELEPHONE 8151942-2920 NOTES If Changes Occur in Capacity Ratings (Items 3 Reasons:

Through 7) Since Last Report, Give NIA

9.

Power Level to Which Restricted, If Any (Net MWe'):.. ~_* -=N~I A=---------------

10.

Reasons For Restrictions, If Any:

NIA

~---='-=----------------------

This Month Yr-to-Date Cumulative

11.

Hours in Reporting Period 719 2.903 147.012

12.

Nilmber of Hours Reactor Was Critical 0

2.066.4 108.628.5

13.

Reactor Reserve Shutdown Hours 0

0 0

14.

Hours Generator On-Line 0

2.066.0 100.911. 9

15.

Unit Reserve Shutdown Hours 0

0 0

16.

Gross Thermal Energy Generated (MWH) 0 4.792.721 206.175.337

17.

Gross Electrical Energy Generated (MWH) 0 1 1557 1 623 66 j589. 235

18.

Net Electrical Energy Generated (MWH)

-3 779 1.486.943 63.064.763

19.

Unit Service Factor 0

71.2 68.6

20.

Unit Availability Factor 0

71. 2 68.6
21.

Unit Capacity Factor (Using MDC Net) 0 66.3 55.5

22.

Unit Capacity Factor (Using DER Net) 0 64.5 54.0

23.

Unit Forced Outage Rate 0

0 13.1

24.

Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

In tenth refueling outage

25.

If Shut Down At End Of Report Period, Estimated Date of Startup:

6-25-88 0820tl2

AVERAGE DAILY UNIT PO~ LEVEL DOCKET N0._0~5~0~-~2~3_7~~~~

DATE May 4, 1988 COMPLETED BY D.C. Maxwell TELEPHONE 815/942-2920 MONTH APRIL, 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 742 17 741 2

734 18 742 3

698 19 710 4

726 20 779

  • 5 726' 21 657

. 6 725 22 740 7

600 23 721 8

526 24 739 9

723 25 751 10 646 26 741 11 672 27 413 12 6 76 28 491 13 575 29 650 14 322 30 733 15 593 31 16 733 0820t/4

AVERAGE DAILY UNIT PO~ LEVEL DOCKET N0.-=-0~50~-~2~4~9~~~~-

UNIT III DATE May 4, 1988 COMPLETED BY D.C. Maxwell TELEPHONE 815/942-2920 MONTH APRIL, 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 0

17 0

2 0

18 0

3 0

19 0

4 0

20 0

5 0

2.1 0

6 0

22 0

7 0

23 0

8 0

24 0

9 0

25 0

10 0

26 0

11 0

27 0

12 0

28 0

13 0

29 0

14 0

30 0

15 0

31 16 0

0820t/5

NO..

DATE NONE 1*

F: Forced S: Scheduled 0820t UNIT SHUTDOWNS.AND'POWER REDUCTIONS

' REPORT MONTH --'AP=-=R:.::I:.:L:.J1'--"l:.:;9-=8-=8--

TYPE~' DURATION. REASON*2 (HOURS).

2 Reason:

  • r METHOD'OF

.SHUTTING 3

  • DOWN REACTOR A-.Equipment Failure (Ezj>lain)

B-Maintenance or Test

. C-Refueling LICENSEE EVENT REPORT II 3

  • D~R.egulatory.Restr~ction.
  • E-Operator TJ:'.aining & Licensee Examination F-,Administrative G-Operataional Error
  • H-Other (Explain)

SYSTE~

COHPO~ENT

'.CODE.

CODE Method:

1-Manual 2-Mariual*scram*

3-Automatic Scram.

  • ./~-Other (Explain) 4
  • DOCKET NO. --'-05""""0'--"""2"""3""""7 ____ _

UNIT NAME DRESDEN UNIT II

.,

  • DATE May 4, 1988

.. COMPLETED. BY D. c. Maxwell.

TELEPHONE (815)942-2920*

CAUSE & CORRECTIVE.

ACTION TO PREVENT RECURRENCE Exhibit G-Instt*uctions for Preparation of Data

  • Entry Sheets for Licensee Everit ~epor~ (

)* File (NUREG-0161).

5 Exhibit I Same Source

NO.

DATE I

1 88-03-27 1

F: Forced S: Scheduled 0820t/7

'L

'-~*

.. UNI*T SHUTDOWNS ANQ POWER RED.!JCTIONS REPORT MONTH APRIL, 1988 METHOD OF TYPE1 * *.DURATION

  • REAS.ON2. " SHUTTING (HOURS)

D 0

0WN REACTOR3 s*

. 719:00 "

  • .c 2

Reason:*

A-'Equipment failure (E.xplain)

B-Haintenance or Test c...::Refueling *

  • D-Regulatory Restriction"

'LIGENSEE

.. *EVENT REPORT II N/A. *

. ; ~

3 E-Operator Tr.aining &. Licensee Examination F-Administrative

  • G-Operataional Error H-Other. (Explain)'

SYSTE~

CODE~-

  • Method:
  • 1-'Hanual*...

COMPO~ENT CODE l'f I A 2-Manlial Scram

  • 3-Automatic: Scram 4-0ther (Explain) 4 DOCKET NO. 050-249 UNI',l' NAME DRESDEN UNIT DATE May 4 1 1988 COMPLETED BY D. C. Maxwell TELEPHONE

~8152942-2920 CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE

  • *N/A Exhibit G~Inslruclions for Prepar.alion -of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5* Exhibit I - Same Source III

COMMONWEALTH EDISON COMP~

DRESDEN STATION MAXIMUM DAILY LOAD MONTH OF APRIL, 1988 DAY HOUR MAXIMUM DAILY LOAD ENDING KW 1

1700 768 700 2

. 1800 768 400 0900.

3 768 900 4

i400 768 800 5

0300 768 200 6

1000 759 700 7

0500 759 700 8

2400 718 800 9

0600 763 600 10 0900 702 600 11 2000 702,700 12 1200 732,000 13 0400 699 700 14 2400 529,100 15 2400 717 000 16 1000 787.100 17 2000 784.900 18 1100 783.700 19 0300 758.800 20 1100 759.200 21 0100 757.600 22 1700 758.600 23 1700 758.800 24 2300 784.400 25 1000 786.100 26 0100 782.800 27 0600 784.400 28 2400 637.600 29 2200 784.200 30 1400 780.900 0820t

00 00 O'I r-l

UNIQUE REPORTING REQUIREMENTS MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations in the following table.

valve was actuated, how its actuation.

Date during the reporting period April, 1988 are summarized The table includes information as to which relief it was actuated, and the circumstances resulting in Valves Actuated Description Actuations Conditions of Events 2

04-01-88 to 04/30/88

_ Norie 3

04/01/88 to 04/30788 0824t Tested two safety valves on the test stand that were removed from 03-- during the refuel outage.

Safety Valve BK6272 lifted at its set pressure

  • o{ 1240psig and 'Safety Valve BK6296 lifted at
  • 1282psig1 which :is within the 23 code limits per ASME Section' XI. of its set pressure of 1260psig.

A Licensee Event Report will be

.issued to report this anomaly.

EGJUIPMENT AO 1601-20A U2 MOV 1301-1 2-26:3-1438 ATS SYSTEM U2 MOV 3703 LPRM 08-338 250V BATTERY CHARGER #2 PS 26t~30C MAIN STEAM LINE LOW PRESSURE SWITCH-*-****

TI-2-U.60--

SBLC SUCT TEMP 28-5742 REACTOR BUILDING VENTILATION SYSTEM OUTLET DAMPER QUAD CITIES SPARE SAFETY VALVE NATURE OF MAINTENANCE PREVENTIVE WR D57220 PREVENTIVE WR D61006 CORRECTIVE WR D620:'.::6 PREVENTIVE WR D6.2604 PREVENTIVE WR DiS714f:

PREVENTIVE WR D69984 CORRECTIVE WR D70159 PREVENTIVE WR D70597 PREVENTIVE WR D70870 CORRECTIVE WR D71664 DRESDEN UNIT 2 SAFETY RELATED MAINTENANCE LER OR OUTAGE NUMBER NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA MALFUNCTION CAUSE*

RESULT CORRECTIVE ACTION REPLACED SEALTITE, C FITTNG AND SOLENOID, LEFT OK DISCONNECTED AND RECONNECTED VALVE FOR M.M. DEPT. COMPLETED PROCEDURES, LEFT OK REPLACED OP. AMPS, LEFT OK DISCONNECTED AND RECONNECTED VALVE FOR M.M. DEPT., LEFT OK PERFORMED PROCEDURE, FOUND NO PROBLEMS, LEFT OK SET EQUALIZE AND FLOAT VOLTAGES PER PROCEDURE, LEFT OK REPLACED SWITCH AND PERFORMED PROCEDURE, LEFT OK CHECKED CURRENT IN CABLE, ADJUSTED THERMOSTAT TO HIGHER TEMPERATURE, LEFT OK INSTALLED NEW SOLENOID AND CYCLED VALVE, LEFT OK REBUILT AND TESTED SAFETY VALVE PER PROCEDURES* LEFT OK i'

I" I

      • 1*J J*

Ill.

EG1UIPMENT QUAD CITIES SPARE SAFETY VALVE QUAD CITIES SPARE SAFETY VALVE TORUS MONITOR INLET VALVE 2499 -

3A HPCI 2-2301-32 VALVE LPRM 08-338 LPRM 16-49C <GP.11 LPRM 24-338 <APRM CH. #41 GE DUAb-TRIP UNIT PS-2-505C E.H.C. LOW OIL PRESSURE SWITCH U2 DIESEL GENERATOR FUEL OIL GAUGE NATURE OF MAINTENANCE CORRECTIVE WR D71665 CORRECTIVE WR D71667 PREVENTIVE WR D71835 PREVENTIVE WR D71 901 CORRECTIVE WR D7 1936 CORRECTIVE WR D72229 CORRECTIVE WR D72289 PREVENTIVE WR D72439 CORRECTIVE WR D72776 CORRECTIVE WR D72791 DRESDEN UNIT 2 SAFETY RELATED MAINTENANCE LER OR OUTAGE NUMBER NIA NI A NI A NI A NI A NI A NIA NI A NI A NIA MALFUNCTION CAUSE RESULT CORRECTI VE ACTION REBUILT AND TESTED SAFETY VALVE PER PROCEDURES, LEFT OK REBUILT AND TESTED SAFETY VALVE PER PROCEDURES* LEFT Of(

REINSTALLED LIGHT SOCKET IN PANEL, LEFT OK REPLACED VALVE, CYCLED, LEFT 0 f'" '*

PERFORMED PROCEDURE, RAN TRACE ON DETECTOR TO ELIMINATE SPil( ING, LEFT OK RAN PLATEAU TO CLEAN DETECTOR, RAN AGAIN AND FOUND NO PROBLEMS COMPLETED PROCEDURES, FOUND NO PROBLEMS CLEANED EDGE CONNECTOR AND MONITORED*

FOUND NO PROBLEMS REPLACED PRESSURE SWITCH, CALIBRATED SWITCH PER PROCEDURE, LEFT Ok:

CALIBRATED AND INSTALLED NEW GAUGE, LEFT OK 9 "

I" J'

EQUIPMENT NA-300 LPRM' SLPRM 40-57A

<APRM 3 )

TR 2-1641-2008 TORUS BULK TEMP RECORDER "B" 2-1157 SLC PUMP DISCHARGE PRESSURE GAUGE NA-:300 LPRMS LT2-1641 - 5A&5B TORUS WIDE RANGE LEVEL RELIEF VALVE 20:3-:3E NATURE OF MAINTENANCE CORRECTIVE WR 072932 CORRECTIVE WR D73406 PREVENTIVE WR D73426 CORRECTIVE WR 07::::540 PREVENTIVE WR D7~:968 PREVENTIVE WR D74024 PREVENTIVE WR D74031 DRESDEN UNIT 2 SAFETY RELATED MAINTENANCE LER OR OUTAGE NUMBER N/ A N/ A NIA N/A NI A N/A N/A MALFUNCTION CAUSE RESULT CORRECTI VE ACT ION PERFORMED 1-V CURVES ON ALL LPRM'S*

LEFT 01<

COMPLETED PROCEDURE ON LPRM, LEFT OK TESTED AND FOUND NO PROBLEMS* LEFT 01<

REPLACED GAUGE AND COMPLETED PROCEDURE, LEFT 01<

COMPLETED PROCEDURE, LEFT OK REPLACED 0 - RINGS AND COMPLETED PROCEDURE LEFT 01<

INSTALLED NEW BULB, LEFT OK JJ 1,,

I 11*

EQUIPMENT U3 4KV BREAKERS

,,-MOV 3-1~01 -27A

,\\

.:I

.I

  • I U3 CRD F-8 3-MO 1501 -38B 3-1'10 1!501-ZOA 3-6601 DIESEb --Q&NaRATOR 3 MOV MOV 1S01-3SA -

LPRM 24-17C M03-1501-27B

[ ______ _

'I

,i I

NATURE OF MAINTENANCE PREVENT-IVE WR D69391 PREVENTIVE WR D69552 CORRECTIVE WR D70222 PREVENTIVE:

WR D70225 PREVENTIVE WR D7051 5 PREVENTIVE WR D70700 PREVENTIVE WR D70704 CORRECTIVE WR 070765 PREVENTIVE WR D71178 DRESDEN UNIT 3 SAFETY RELATED MAINTENANCE LER OR OUTAGE MALFUNCTION NUMBER CAUSE RESULT N/A N/A N/A N/A N/A NIA N/A N/A N/A N/A CORRECTIVE ACTION

]

PERFORMED INSPECTION ON SPARE BREAKERS 1

PER PROCEDURES* LEFT OK OPENED AND GLGSED CGV£R-FGR NRG* bEF ~-GK---

INSTALLED AND REMOVED JUMPER RELAY FOR CRD, LEFT OK REPLACED WORM, GASKETS, QUAD RINGS AND 0-RINGS PER PROCEDURE* LEFT OK J.

I

- ---*--J" 9 "

ll

" -J" INSTALLED NEW QblAD RINGS, Q-RlNGS AND--------

GASKETS PER PROCEDURE, LEFT OK PERFORMED SEMI-ANNUAL AND 3 MONTH INSPECTIONS PER PROCEDURES* LEFT OK

II II J::

DISCONNECTED AND RECONNECTED WIRING FOR M.M. DEPTt LEFT OK REMOVED AND-RE lNST-AL..bED -MO-lOR-t*-b-I-M-J.:

SWITCH AND TORQUE SWITCH* PERFORMED INSPECTIONS, LEFT OK PERFORMED PROCEDURE, REMOVED WISKERING WHILE R~ING P-b-A-TEAU, LEF-T-~ -- -------------~

REPLACED AUX CONTACTS AND PERFORMED PROCEDURE* LEFT OK

]I

EQUIPMENT REACTOR BUILDING VENT 3 'B.' INLET ISOLATION VALVE

l.t..PRM-6A 4017A <IN LPRM GP, 2>

"r LPRM 48-498 <CH. 3)

DPIS 261-2E <MAIN STEAMLINE B>

HPCI MOTOR SPEED CHANGER OW/TORUS VACUUM BREAKER 3-1601-~

1501-

I Ze voe svs:re:M LPRM 4C-16-25 3-1464 A&B CORE SPRAY FLOW TRANSMITTERS

~,

t ____ _

NATURt* OF MAINTENANCE PREYENTIVE WR 071364 GORREGT I-VE -

WR D71774 CORRECTIVE WR 071910 CORRECTIVE WR 071929 PREVENTIVE WR 072011 PREVENTIVE WR 072015 PREVENTIVE WR 072023 PREVENTIVE WR 072048 CORRECTIVE WR 072 150 PREVENTIVE WR 072499 DRESDEN UNIT 3 SAFETY RELATED MAINTENANCE LER OR OUTAGE NUMBER NIA N/A N/A NIA N/A N/A N/A NIA N/A N/A MALFUNCTION CAUSE RESULT CORRECTIVE ACTION REPLACED SOLENOID AND CYCLED, LEFT OK TROUBLESHe'.f-,--PER-PROOEDUREt REPl;;;Ae:Ell>---------,

DEFECTIVE AMPLIFIER CARO, LEFT OK PERFORMED PROCEDURES* INDICATION IS NORMAL~ -L-E~~ ~: ___ -

-- ----~-----~---* -----_J:

CALIBRATED PER PROCEDURES, LEFT OK 9 "

" J ll ADJUSTED LIMIT* LEFT OK TIGHTENED UP LIGHT SOCKET AND RES~T J::

LIMIT SWITCHES WITH DIA~ IN9leATOR-PER-------

PROCEDUREt LEFT OK LUBRICATED AUX CONTACTS* PERFORMED PROCEDURE, LEFT Of(

_ _-_-J:

TROUBLESHO-T TO Eb-I-M-INA-TE-GRGJHND--ON - ---- --,

voe SYSTEM. LEFT OK BURNED OFF DETECTOR WHISKER PER PROCEDURE, bEFT O~

REPLACED 0-RINGS ON TRANSMITTERS AND PERFORMED PROCEDURE, LEFT OK

1:

~ ::

EQUIPMENT 3-2540-21

. ACAD-CAM AIR COMPRESSOR

-2540-020 A :1 ACAD COMPRESSOR

'I LPRM 32-33C <GP. 1>

, I SRM #21 3-1641-6AS.B CONT. HI. PR TRANSMITTERS

  • 1 ----

NATURE OF MAINTENANCE CORRECTIVE WR D7Z!511 PREVENTIVE WR D72920 CORRECTIVE WR 073082 CORRECTIVE WR D73 113 PREVENTIVE WR D73 19 1 DRESDEN UNIT 3 SAFETY RELATED MAINTENANCE LER OR OUTAGE MALFUNCTION NUMBER CAUSE RESULT NIA NIA NIA NIA NIA CORRECTIVE ACTION CALIBRATED PER PROCEDURE, LEFT OK CALIBRATED PER PROCEDURE* LEFT OK -

RAN PLATEAU AND BURNED OFF WISKERS, LEFT OK I.:

  • -----I CLEANED MODULE CONNECTIONS, TIGHTENED LOOSE WIRE IN JUNCTION Box. PERFORMED PROCEDURE* kEFT OK REPLACED TERMINAb-COVER *-S*IDE 0-RINGS- -

AND CALIBRATED PER PROCEDURE, LEFT OK e :.

--* J::

II I

ll I,,

- fi,,

] I

Jll

" ll l!

EQUIPMENT SPARE SRM PULSE HT. DISCR.

. CARD

  • - -Zl'3 - 7503B a.I SBGT AIR HEATER 3-5800
.1 REACTOR BUILDING CRANE REACTOR BUILDING CRANE

.. 1 -

I I

SRM SPARE MODWkE 2/3 DIESEL GENERATOR I

DUAL

. I SPARE

.I SENSOR & CONVERTOR SENSOR CONVERTER "I ____ ---- --

"1 DTS-32 LLRT TEST BOX

  • 1 j ___ _

.I I

NATURE OF MAINTENANCE J

CoRAECTIVE WR D6366!S PREVENTIVE WR D67433 PREVENTIVE WR 068980 PREVENTIVE WR D69296 CORRECTIVE WR D70170 CORRECTIVE WR D71275 CORRECTIVE WR D71727 CORRECTIVE WR D71728 CORRECTIVE WR 071823 PREVENTIVE WR D72424 DRESDEN UNIT 2/3 SAFETY RELATED MAINTENANCE LER OR OUTAGE NUMBER N/A N/A NIA N/A N/A N/A N/A N/A N/A N/A MALFUNCTION CAUSE RESULT CORRECTIVE ACTION REPAIRED AND TESTED* FOUND NO FURTHER PROBLEMS, LEFT OK REPLACED BROKEN RESET AG-TUA TOR' bEFT GK - - --*- --

REPLACED RELAY AND TESTED PER PROCEDURE* bEFT OK ADJUSTED RESTRICTED MODE LIMITS TO ALLOW MOVEMENT OF CASK* LEFT OK REPLACED DEFECTIVE CAPAG~TORS AND CALIBRATED, LEFT OK REINSTALLED TEMPERATURE PROBE IN WELL*

LEFT OK J'

_ ],:

e:

1 11 I*

II CLEANED EDGE CONNECTOR WITH CLEANER. -

-- - J"

~~~~ T~~ED CARD AND FO~~~~~ ~ROBL_E_M_s_

11 7l REPbACED-W ODfit -VRl-AND-CAl..-I-BRA-T-*11olic1JOc,.,-tbelic1-F+T----

OK

--~:

ll REPLACED SEMI-CONDUCTORS AND CALIBRATED*

bEFT OK

~ :

~

CALIBRATED PRESSURE GAUGE PER PROCEDURE* LEFT OK JI

]:

JI

*- -- -*- 1 ::1~

________ _J JI

EQUIPMENT TEST EQUIPMENT TORQUE-WRENCH DQ-10 UNITS z, 3, AND 2 /3 IMMERSION I

HEATERS NATURE OF MAINTENANCE PREVENTIVE WR 072476 PREVENTIVE WR 072674 DRESDEN UNIT 2/3 SAFETY RELATED MAINTENANCE LER OR OUTAGE NUMBER N/A NIA MALFUNCTION CAUSE RESULT CORRECTIVE ACTION CHECKED TORQUE AND RECORDED READINGS, LEFT OK TOOK READINGS PER INSTRUCTIONS, LEFT OK

- _ _J:

I,:

_____ _J 9 "

--] "

11 I

I I "

I

- j,.

I

' ll JJ

4-01-88 to 4/30/88 0816t

SUMMARY

OF OPERATING EXPERIENCE DRESDEN UNIT TWO APRIL, 1988 Unit 2 entered the month on-line and operating at 763 MWe in Economic Generation Control (EGC) as directed by the Load Dispatcher (LO).

The unit operated in EGC or at maximum feedwater flow, limited by turbine loading limitations due to 202 feedwater heater being isolated.

On April 7, 1988, the 2A Recirc M.G. tripped and load was reduced to 242 MWe to investigate problem.

Load was increased and the unit operated at 700 MWe because of current limits on the 2A Recirc pump until April 13, 1988.

On the 13th, load was again reduced to facilitate a drywell entry and on April 14, 1988 the entry was made.

A wiring connection was repaired on the 2A MG Set current transformer and a leaking coupling on the lB MSIV air line was tightened.

The unit load was increased to maximum feedwater flow, limited by turbine loading limitations due to 202 feedwater heater being isolated through April 27, 1988.

On the 27th, load was again reduced to enter the drywell and repair the air line on lB MSIV.

Load was increased and the unit operated the remainder of the month, l:'li,th a capacity factor of 83.,823 and an availability of 1003.

SUMMARY

OF OPERATING EXPERIENCE DRESDEN UNIT THREE APRIL, 1988 4-01-88 to 4/30/88 Unit 3 entered its tenth refueling outage on March 27, 1988 and remained off-line all month.

0816t

e Common.th Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 May 5, 1988 EDE LTR:

  1. 88-349 Director, Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 Attention:

Document Control Desk

Dear Sir:

Enclosed, please find Dresden Station's operating data for the month of April, 1988.

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

Sincerely, EDE: DCM: jmt Enclosure Power Station cc: 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.

Tech Staff A.E. (2)

On-Site NRC Inspector Site Q..fi.

BWR Engineering Group Comptroller's Office PIP Coordinator INPO Records Center File/NRC Op. Data File/Numerical 0819t

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