ML20042E375

Monthly Operating Repts for Mar 1990 for Dresden Units 1,2 & 3

ML20042E375
Person / Time
Site:	Dresden
Issue date:	03/31/1990
From:	Eenigenburg E, Maxwell D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
90-274, NUDOCS 9004200693
Download: ML20042E375 (31)

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f; l Corsmonwealth Edison -

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Dresden Nuchat Power Station -

e Morris, Illinois 60450 :

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.- Telephone 815/942-2920.

f April 9. 1990 EDE'LTR

1. 90-274.

Director, Nuclear Reactor Regulation p

United States Nuclear Regulatory Consnission

.9.

Washington, DC 20555

,-Attention:. Document Control Desk.

Subject:

Monthly. Operating Data' Report Dresden Nuclear Power Station Connonwealth Edison Company

.Dacket Nos.'50-010. 50-237.~and 50-249 U;

Gentlemen:

Enclosed is the Drtaden Nuclear._Eower Station..tionthly Opstat.ing..S11smary Repor.L for March, 1990.. This information is supplied to-your office-in accordance with the instructions set forthiin 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-

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with 100FR50-59.

I Sincerely, Y.

y E. D. Eenigenburg Station Manager Dresden Nuclear Power Station EDE:GPadjh Enclosure i

cc: U.S. NRC Region III Office Illinois Dept. of Nuclear Safety, State of Illinois-U.S. NRC, Document Management Branch Nuclear Licensing Administrator Vice Pres. - BWR Operations General Manager - Nuclear Services

.l T. S. ENGR. (2) i NRC Senior Resident Inspector Site Quality Assurance Superintendent Nuclear Engineering Manager Comptro11er's Office D. Eggett - Reliability Programs INPO Records Center File /NRC Op. Data File / Numerical

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SWEEARY OF OPERATDIG NKPERIEHCE,.

CHANGES, TESTS, AltD EIPERDIENTS

- PER REGUIATORY GUIBE 1.16 AIID 10 CFR 50.59-

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ER-BRESDEN NUCLEAR POWER..BTATIGi CGEM3tWEALTE EDISGI CGEPANY I

IMII DOCKET LICENSE 1-050-010' DPR-2 2

,050-237 DPR-19 i

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050 249 DPR-25

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I' TABLE OF CONTENTS j

j 1 ^ 0. Introduction-2.0[ Summary of Operating Experience l

2.1 Unit 2 Monthly Operating Experience Summary 2.2 Unit 3 Monthly. Operating Experience Summary 3.0- Operating Data Statistics

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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 r

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 Reporting Requirements 4

4.'1 Main Steam Relief and/or Safety Valve-Operations - Unit 2 and Unit 3-4.2 Off-Site Dose Calculation Manual Changes j

A 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' Elgnt or Procedure Changes. Tests. Experiments. and Safety Reinigd Maintenannt 5.1 Amendments to Facility License or Technical Specifications-5.1.1 Unit 2-i 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 4

5.6 Temporary System Alterations

5. 6.1 - Unit 2 5.6.2 Unit 3 U

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1.0 in1 Induction Dresden Nuclear Power Station is a three reactor generating facility

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owned and operated by the Commonwealth Edison Company of Chicago, Illinois. Dresden Station is located at the cot fluence 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 Dresden Units 2 and 3 was Sargent and Lundy of Chicago, Illinois.

This' report was compiled by Donald-C. Maxwell of the Dresden. Technical I

Staff, telephone number (815)942-2920 extension 2489.

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_2.0!SUtt%R1' 0F OfERATING EXFIRIENCE FOR MARCH.1990.

e 2.1 UNIT 2 MONTHLY OPERATING EXPERIENCE SUPT 4ARY 03-01-90 to 03-31-90 Unit 2 entered the month on-line and operating at-790 MWe as requested by the System Load Dispatcher (LD). The unit operated the entire month at maximum coreflow or at direction of.the LD with an availability of 100% and a capacity j

factor of 94.2%.

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2.0'EUttiARY OF OPERATING EXPERIENCE FOR MARCH. 1990 2.? UNIT 3 MONTHLY OPERATING EXPERIENCE

SUMMARY

03-01-96 to 03-10-90 Unit 3 entered the month on line at approximately 780 MWe~and continued to operate at-loads specified by the Load Dispatcher.

.i 03-10-90 ta 03-11-90 At 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> on 3/10/90, an automatic reactor' scram on Average Power Range Monitor (APRM) high flux and a subsequent primary containment i

group I isolation' occurred due to failure of an inboard main steam-isolation valve (MSIV) 2-203-2A pilot solenoid air line. After completion ~of a scram investigation-and' maintenance repair activities, the unit was brought critical at.1110 hours0.0128 days <br />0.308 hours <br />0.00184 weeks <br />4.22355e-4 months <br /> on-3/11/90.

The main generator was' synchronized to the' grid.at 1817 hours0.021 days <br />0.505 hours <br />0.003 weeks <br />6.913685e-4 months <br /> of.the same' day.

03-12-90 to 03-31-90 Unit 3 operated =the remainder of the month at-l loads specified by the Load Dirpatcher.

The monthly availability was-97.1% with a, capacity-factor of 92.6%.

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3.0 OPERATING DATA REPORT 3.1' OPERATING DATA REPORT - UNIT TWO DOCKET NO. 050-237 i

.DATE April 1. 1990 COMPLETED BY D. O. Maxwell l'

TELEPHONE 815/942_2920 OPERATING STATUS

1.

REPORTING PERIOD MARCH 199Q_

GROSS HOURS ~IN REPORTING PERIOD-

,744-

-2.

CURRENTLY AUTHORIZED POWER LEVEL:

2,527

~ MAX DEPEND CAPACITY'(MWe-Net)

. 772 DESIGN ELECTRICAL RATING' (MWe--NET). 794 l

3.

POWER' LEVEL TO WHICH RESTRICTED.(IF ANY)

'N/A 4..

REASONS FOR RESTRICTIONS (IF'ANY)

REPORTING PERIOD DATAL This Month Yr-to-Date.

Cumulative.

5.' TIME REACTOR CRITICAL'(HOURS) 744.0-1,867.7 132,667.9 7.

TIME' GENERATOR'ON-LINE (HOURS) 0.0' 6..' TIME REACTOR RESERVE SHUTDOWN (HOURS)

_ 744.0 :

1,863.7 126,195.2 0.0 0.0 8.

TIME. GENERATOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 z0.0-9.

THERMAL ENERGY GENERATED-(MWHt-GROSS) 1,820;342 4,377,724 262,494,915

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10. -ELECTRICAL ENERGY GENERATED (MWHe GROSS) 585,004 1,412,792 83,907.141

11.. ELECTRICAL ENERGY GENERATED (MWHe-NET) 559,257-1,347,158 79,335,322 12.

REACTOR SERVICE FACTOR (%)

~100.0 87.4 L76.1 13.

REACTOR AVAILABILITY FACTOR (%)

1100.0 87.4 76.1

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SERVICE FACTOR (%)

100.0 86.3

-72.8 7

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' AVAILABILITY FACTOR 100.0 186.3

.72.8

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

97.4

80.8

-59.0

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

94.7 78.5 57.3 18.

FORCED OUTAGE FACTOR (%)

0.0 13.7 10.9 19.

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

i REFUELING-0UTAGE SCHEDULED for 9-1-80~thru 11-11-90 c

4 20.

IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A Z16/10/7 l

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3.0 OPERATING DATA REPORT 3.2 OPERATING DATA REPORT - UNIT THREE' DOCKET NO. 050-249 DATE APRIL 1. 1990 COMPLETED BY.._D.C. Maxwell-TELEPHONE 815/9A2-2920 =

OPERATING STATUS 1.

REPORTING PERIOD:.1ERCH 1990 GROSS HOURS IN REPORTING PERIOD 744

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CURRENTLY AUTHORIZED POWER LEVEL:

2,527 MAX DEFEND. CAPACITY (MWe-Net)'

773 DESIGN ELECTRICAL RATING (MWe-NET) 794 3.

POWER LEVEL TO WHICH RESTRICT?D (IF ANY)

N/A 4.

REASONS-FOR RESTRICTIONS (IF ANY)

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REPORTING PERIOD DATA i

This Month Yr-to-Date Cumulative:

3 5.

TIME REACTOR CRITICAL (HOURS) 729.3 999.1 121,233.5 6.

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

TIME = GENERATOR ON-LINE (HOURS) 722.2 862.9

.113,225.1

8.. TIME CENERATOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0-

9. -THERMAL ENERGY GENERATED (MWHt-GROSS) 1,758,291 1,959,446 233,586,866'

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ELECTRICAL ENERGY GENERATED (MWHe GROSS) 573,634 635,342 75,347,587

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ELECTRICAL ENERGY. GENERATED (MWHe-NET) 549,522

.598,728 71,454,098 12.

REACTOR SERVICE FACTOR.(%)

98.0

'46.3

>74.0 13.

REACTOR AVAILABILITY FACTOR (%)

98.0

-46.3 74.0-14.

SERVICE-FACTOR-(%)'

97.1 40.0

-69.1

15.. AVAILABILITY FACTOR.

97.1 40.0 69.1 16.

CAPACITY FACTOR (USING MDC) (%)

95.6 35.9 56.4 17.

CAPACITY FACTOR (USING DESIGN MWe) (%)

93.0 34.9

-54.9 18.

FORCED OUTAGE FACTOR (%)

2.9

'25.8 12.2-19.

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 N/A zi6/10/8 l

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-DOCKET NO.- 050-237-UNIT'II DATE_AERIL'l 1990 COMPLETED BY D.C. Maxwell-TELEPHONE 815/942-2920'

. MONTH MARCH. 1990 DAY AVERAGE DAILY POWER' LEVEL TAY AVERAGE DAILY POWER LEVEL-(MWe-Net)-

-. (MWe-Ne t ) -

1 752

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553

- 2 755 18

'769 j

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739 19 773' 4

588 20 770' 5

750 21-754 6

773 22 748 7

775 23 773 8

774 24 781' 9

769 25 759'-

10 765 26 779 11 742 27 708 i

h 12 747 28 770 L

'13 763 29 779-L L

14-763 30-780 0

L, 15 768 31 777 16 752 I

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3.4-AVERAGE DAILY UNIT POWER LEVEL

-DOCKET NO._050-249 UNIT III

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~ DATE APRIL-1. 1990 COMPLETED BY D.C. Maxwell-

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. TELEPHONE 815/942.-2920

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MONTH MARCH. 1920 DAY AVERAGE DAILY' POWER LEVEL DAY AVERAGE DAILY-POWER LEVEL l

(MWe-Net)

(MWe-Net)-

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1 755 17 785 2

778 18

'774' N

3 733 19 789 4

777 20 783-5 788 21 "789 6

'787 22

-788 7

788 23 788 8

776 24 773 9-751 25

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10 639 26 789 11 70

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~775 12 568 128-785' 13 635-29 78'6-14 761 30

'787 n

15-778 31 748' t

16 779

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DOCKET'NOo 050-237

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UNIT NAME DRESDEN UNIT II" 3.5 UNIT SHUTDOWNS AND POWER REDUCTIONS

-.DATE Anril 1.'1990

. COMPLETED BY D. C. Maw = ell. '

TELEPHONE (815)942-2920

' REPORT MONTH MARCH. 1990 f

METHOD OF LICENSEE SYSTEg COMP 0 f

-CAUSE & CORRECTIVE

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3 NO.

DATE TYPE ~

DURATION REASON SHUTTING EVENT CODE CODE ACTION TO (HOURS)

DOWN REACTOR REPORT #

PREVENT RECURRENCE N/A j-H 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; Automatic Scram Event Report (LER). File D-Regulatory Restriction 4-Other.(Explain)

(NUREG-0161)

.E-Operator Training ~& Licensee Examination

.5-Load Reduction F-Administrative G-Operational Error 5 Exhibit I~- Same Source-ZR16/10/11 H-Other (Explain)

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-i DOCKET NO. 050-249 UNIT NAME DRESDEN UNIT *III' 3.6 UNIT SHUTDOWNS AND POWER REDUCTIONS DATE April 1. 1990 COMPLETED BY D. C. Maxwell" '

TELEPHONE (8151942-2920 '

REPORT MONTH MARCH. 1990 METHOD OF LICENSEE SYSTEg COMF0 CAUSE & CORRECTIVE 1

2 NO.

DATE TYPE DURATION REASON

-SHUTTING

-EVENT CODE COD ACTION TD (HOURS)

DOWN REACTOR REPORT #

PREVDIT RECURRENCE 3

03-10-90 F

21.8 A

3 90-005-0 On March 10, 1990 at 2030

' hours, an automatic reactor scram on APRM high flux and a-subsequent primary containment group I isolation occurred because of an inboard MSIV 3-203-2A pilot solenoid air line.- After completion of repairs and investigation, the Reactor was brought critical March.11, 1990 0 1110 hours0.0128 days <br />0.308 hours <br />0.00184 weeks <br />4.22355e-4 months <br /> and the unit was synchronized-to the system @ 1817 hours0.021 days <br />0.505 hours <br />0.003 weeks <br />6.913685e-4 months <br /> of:

the same day.

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)

'E-Operator-Training & Licensee Examination

'5-Load Reduction.

(NUREG-0161)

F-Administrative G-Operational Error 5 -Exhibit I - Same Source:

ZR16/10/12 H-Other (Explain)

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. COMMONWEALTH EDISON COMPANY'- DRESDEN NUCLEAR POWER STATION

' MAXIMUM DAILY ELECTRICAL LOAD FORM

.FOR THE MONTH'_OF MARCH,.1990

,4 HOUR-MAXIMUM DAILY LOAD gy ENDING KW 1

2400 1.601.100 2

1000 1.623.900 3

2300

' 1.562.40D f 2400

'1.524.300 5

2300 1.627.000 6-2200 1.629.600 k

7-1600-

'1.631.200 8

1300 1.583.300 9

1100 1.589.600 10 0800-

=1.619.200 11

'2400

1.328.300 12 2400 1.491.200 13 2100 1.542.300 14 1300 1.611.300 15

_ 1100 1.626.900 16 1900 1.620,100 17 2400 1.535.300

' t 18 2000 1.636.100 19 1100 1.642.200 20 1200 1.619.100 21 1700 1.630.700 s

22 1100 1.603.900 23 0900 1.636.700 24 1500 1.639.000 25 2400 1.633.900 26 1000

-1.637.500 27 0100

'1.631.300 28 0900-1.627.300 29

1400, 1.632.000 30 1100 1.633.100 31 2300 1.628,800 TOTAL 49,628,900

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- i-4.0 UNIQUE REPORTING REQUIREMENTS 4.1 MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period, March, 1990, are L

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.

l No. and Type Yalves.

of

Plant.

Description llnit Date Actuated Actuations Conditlona DL.11tnis.

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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.

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'0PT-CITE DOSE CALCULATION MANUAL (ODCM) CHANGES-P

-No ODCM changes were reported for the month of March, 1990, t

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t' 4.3 MAJOR CHANGES TO THE RADI0 ACTIVE WASTE TREATMENT SYSTEMS L

There were no major changes to the radioactive waste treatment systems j

at Dresden during the reporting. period.

i 4.4 FAILED FUEL ELEMENT INDICATIONS L

4.4.1 Unit 2 l

Dresden Unit 2 fuel performance-during March,1990 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 recombiners.

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

l-4.4.2 Unit 3 I

l Dresden Unit 3 fuel performance during March, 1990 continued to show no

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indications of leaking fuel.

This'is. based on'the sum of.the activities of the six noble gases as: measured at the recombiners.

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

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5.0 PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS. AND SAFETY RELATED M

5.1 Amendments to Facility License or Technical Specifications-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' 5.1.2' Unit 3 NONE.

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

Table 5.2.1, attached, sununarizes the-revisions to-procedures.

described in the-FSAR which were approved during the reporting period.

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7-TABLE 5.2.1 CHANGES TO PROCEDUPIS WHICH ARE DESCRIBED IN THE FSAR (UNITS 2 AND 3)

PROCEDURE TYPE PROCEDURE NO.

PROCEDURE TITLE / DESCRIPTION SUff92Y OF CHANGES Dresden Administrative DAP 7-1 Operations Department Organization

.1, 2

Procedure (DAP)

DAP 7-10 Charts and Chart Recorders 2, 3 Dresden' Technical DTS 1600-7

-Unit 2/3 Integrated Primary Containssent Leak Rate 3, 4 -

L Staff Surveillance Test (DTS)

NOTES: 1.

Administrative change; intent of procedure unenanged.-

2.

Changed for clarification, intent of procedure unchanged.

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

Changed to implement improved testing / calibration methodology; intent of proc:sdure unchanged.

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- - = -

i 5.3j Signific:nt t:sts cud cxpsriments not dsscribsd inLtha.

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=FSAR'(Units 2 &.3)-

SP 90-3-62 MODIFICAIl0H_til2-2-89-13' TEST FOR CONDENSATE DEti1NERALIZELCAI.10tLIAHLUNDERDEAIN STRAINER REP 14CEtiENI This, Procedure tested new underdrain strainer assemblies.

SP 90-3-68 MODIFICATION M12-2-89-12 TEST FOR CONDENSAIE DEMINERALIZER MIX AND HOLD _ TANK ___UNDERDRAIN STRAINEE REPLACEMEHI This Procedure verified proper installation of new.

underdrain strainer as'semblies.-

2 SP-90-3-69 HIGILERESEURE._CQ0LANT INJECIIDN _(HPCI) VALVE MANIPULATIONS _FOR' DATA ACOUISITION 7

The purpose of this procedure was-to perform'a' series

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root'cause investigation-concerning a HPCI event which occurred on March 19, 1990.

5.4 Safety related maintenance (Units'2 & 3)'-

Safety related maintenance activities are summarized in'the attached tables.

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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, 1990 are listed below.

Only modificatione which have been completely closed are listedt modifications which are authorir,ed 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.

tiodif.ication_lh Descrip. tion M12-2-82-23 This modification was performed to install a bypass line around Reactor Water Cleanup (RWCU) System valve-2-1201-1.

M/12-3-84-011 This modification added valves and tees to the shutdown cooling heat exchanger j

shell side drain line to allow running condensate from the shell side drains to the heating system.

The safety evaluation concluded that this modification will not be used during normal operation, because it is l

designed only for use during unit shutdown. The margin of safety is therefore not reduced.

o M/12-3-84-139 This modification installed a Primary Containment-water level indication system. This instrumentation was l

installed and tested in accordance with j

approved station procedures.

The 4

safety evaluation concluded that l

Primary Containment integrity is.

-l maintained and therefore the margin of j

safety is not reduced.-

l l

l l

l 1

ZR16/10/21

L l

M12-3-88-062 The purposa cf this modificction cca to rcp10:3 the Maia Pow;r Transfcrmer (MPT) interface equipment, the bus duct transition pieces, fire protection deluge piping, heat detection devices.

and associated wiring. Also, protective relaying connections, transformer cooling fans, and oil pump electrical feeds were modified to be compatible with the MPT replacement on a like-for-like basis. The safety evaluation concluded that none of the equipment described in the Technical Specifications is permanently alter 3d by this modification.

M12-2/3-88-010 This modification devitalized the Unit 1 Air Compressor room area and created a new corridor to the Unit 1 trackway.

M12-2/3-88-028 The purpose of this modification was to remove and replace the Reactor Building roofing.- The new roofing material is equal or better than the material replaced.

Secondary Containment was monitored during replacement to insure that the roofing work did not; adversely affect secondary containment integrity.

The Safety evaluation-therefore concluded that the margin of safety was not reduced.

I i

1 ZR16/10/22-

I c

• .:~

++

5.6 Temporcry System Alterations (Unit 2 and Unit 3)

A " Temporary System Alteration" refers to electrical jumpers, lifted leads, removed f uses, 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 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.

5.6.1 Unit 2 i

Temporary System Installation Removal Alleration Ma, Description Dals Date 11-8-90 Alteration to disconnect 3/23/90 3/23/90 i

leads to silence a local alarm horn so that maintenance work could be

[

performed on the turbine building mezzanine floor sprinkler system deluge valve.

11-9-90 Alteration to remove the 3/30/90 Unit 2/3 Diesel Generator interlock door circuitry wires from their terminal block and reconnect them directly to remove a 125VDc ground, pending completion of permanent repairs i

ZR16/10/23-a

,e,

e

',e

,e "*

5.6.2 Unit 3 Temporary System Installation Removal

-/digration No.

Descrip. tion DAlt 11LL_._

111-13-90 Alteration to re-locate the 3/27/90 3/30/90 normal Instrument Air Dryor 3-4702 control air supply for the dryer switching valves.

This facilitated testing the valves prior to placing the dryer back into service.

o IR16/10/24 i