Text

Monthly Operating Repts for Dec 1989 for Dresden Units 1,2 & 3
	ML20005G490
Person / Time
Site:	Dresden
Issue date:	12/31/1989
From:	Eenigenburg E, Paramore G; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
	90-035, 90-35, NUDOCS 9001190233
	Download: ML20005G490 (29)
	v • d • e

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') Commonwealth Edison

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i Dresden Nuclear Power St;tiin 1

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\\j Morris, Illinois 60450 Telephone 815/942 2920 January 10, 1990 EDE LTRt #90-035 Director, Nuclear Reactar Regulation United States Nuclear Regulatory Commission Washington. DC 20555 Attention: Document Control Desk

Subject:

Monthly Operating Data Report Dresden Nuclear Power Station' Commonwealth Edison Company Docket Nom.50-010. 50-237. and 50-242 Gentlement Enclosed is the Drmade LNuclear_ tower Station Monthlv Operating _lummary_.

RegnIt for December, 1989. This information is supplied to your office 1

in accordance with the instructions set forth in Regulatory Guide 1.16.

Please note that the report contains inforination which had beer.

previously submitted to your attention on an annual basis in accordance

-with 100FR50.59.

Sincerely.

bw.AA g' a

E. D. Eenigenburg Staticn Manager Dresden Nuclear Power Station l

l' EDEtGP se-l'

-Enclosure 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 G. Paramore (2)

NRC Senior Resident Inspector Site Quality Assurance Superintendent Nuclear Engineering Manager Comptro11er's Office INP0 Records Center File /NRC Op. Data File / Numerical

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s M(BITELY MRC StSGl&RY OF OPERATDIC EEPERIENCE, CHANGES. TESTS. AND EKPERIMENTS PER REGUIATORY GUIDE 1.16 AIID 10 CFR 50.59 EDR DRESDEN NUCLEAR POWER STATION In1I DOCKET LICENSE 1

050-010 DPR-2 2

050-237 DPR-19 3

050-249 DPR-25 i

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TABLE OF CONTENTS 1.0 Introduction 2.0 Er-- rv of Operatine Erperience p

'2.1 Unit 2 Monthly Operating Experience Summary t

2.2 Unit 3 Monthly Operating Experience Summary n

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3.0 Operatine Data Statistics l-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 Reportine Raouirements 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 Riant or_ Procedure Changta. 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 1

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lattaduction

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Dresden Nuclear Power Station is a three reactor generating facility i

y 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 Dresden Units 2 and 3 was Sargent and Lundy of Chicago, Illinois.

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

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2.0

SUMMARY

OF OPERATING EXPERIENCE FOR DECEMBER. 1989 2.1 UNIT 2 MONTHLY OPERATING EXPERIENCE SLNMARY F

12-01-89 to 12-09-89 Unit 2 entered the month on line and operating at approximately 820 MWe.

12-10-89 to 12-21-89 On December 10, 1989 at approximately 0230-hours.

Dresden Unit 2 began a planned outage to facilitate testing of the 125 VDC batteries.

On December 20, 1989 at approximately 0710 hours0.00822 days 0.197 hours 0.00117 weeks 2.70155e-4 months the reactor was made critical.

The renerator was synchronized to the grid at 0821 hours0.0095 days 0.228 hours 0.00136 weeks 3.123905e-4 months on l

December 21, 1989.

12-22-89 to 12-25-89 On December 22, 1989 at 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months the Unit 2 generator was separated from the grid and the unit shutdown to hot shutdown conditions due to a main generator casing liquid detector alarm indicating that seal oil was backing up into the generator casing.

It was determined that a clogged seal oil float trap caused oil to overflow the seal oil drain enlargement resulting in oil backing up into the generator casing. The generator casing was drained of oil and the generator bushing boxes were opened to perform inspections. The clogged seal oil float trap and valve was cleaned of oil and debris. The generator was then synchronized to the grid at 0210 hours0.00243 days 0.0583 hours 3.472222e-4 weeks 7.9905e-5 months on December 25, 1989.

l 12-25-89 to 12-31-89 For the remainder of the month Dresden Unit 2 remained on line and operated as directed by the Corporate Load Dispatcher.

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'2.0 E1391ARY OF OPERATING EXPERIENCE FOR DECEMBER,1989 l

2.2 UNIT'3 MONTHLY OPERATING EXPERIENCE SUPflARY l

12-01-89 to 12-02-89 Unit 3. entered the month on line and operating at approximately 678 MWe.

j 12-03-89 to 12-31-89 On December 3, 1989 at 0313 hours0.00362 days 0.0869 hours 5.175265e-4 weeks 1.190965e-4 months ,-Dresden Unit l

3 began its eleventh refueling outage and will i

be off line until February 10, 1990.

j Major outage activities during the month included the following items Disassently of Unit 3-reactor vessel and removal of internals (separator and dryer) t Local Leak Rate Testing Control Rod Drive removal and replacement Unload reactor fuel In-Service Inspection (ISI) program Detailed Control Room Design Review (DCRDR) human factors control panel modifications for Core Spray Systems A and B e

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tw L 8 M I"II " I8IA 8IAllSilCS 8PE#fl4 i _TA REPORT. UN!! iso DOCKET C. 050-237 UNIT DRESDEN TWO DATE JANUARY 1,1990 COMPLETED BY 0.M. PARAMORE 1

i.

TELEPHONE (815)-942-2920 OPERAi!W $TATUS

' !. KPOR11NGPERIOD:

DECEMKR 1999 GkDSS HOURS IN REPORi!NG PERIOD:

744

2. CURRENTLY AUTHORIZED POWER LEUEL (MNt):

2,527 MAX DEPEND CAPACITY (MWe-Net):

772 DESIGN ELECTRICAL RAtlNG (Mue-Net) 794 I ' 3.

POER LEUEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):

N/A 42 MASONS FOR RESTRICi!DN (IF ANY):

?

REPORIING PERIOD DATA TH!$ MONTH YEAR-10-DATE CUMULAilUE

5.. TIME REACTOR CRITICAL (HOURS) 499.3 7,233.2 130,779.1 6.;L TG REACTOR RESERUE SHUTDOM (HOURS) 0.0 0.0 0.0 7.'

ilE GENERA 10R ON-LINE (HOURS) 403.0 7,024.9 125,050.3

'8, ' TIE GENERATOR RESERVE $HUTDOWN (HOURS) 0.0 0.0 0.0 92 TERMAL EERGY GENERATED (MWHt-Gross) 937,431 15,625,329 258,117,191

10. ELECTRICAL ENERGY GENERATED (MWHe-Dross) 295,892 4,999,616 B2,484,349

11. ELECTRICAL EERGY GENERATED (MWHe-Net) 279,575 4,745,977 77,980,883

12. REACTOR SERUICE FACTOR (t) 67.1 82.6 76.0

.13. REACTOR AUA!LABIL!iY FACTOR (t) 67.1 82.6 76.0 i

.14. SERUICE FACTOR (t) 54.2 60.2 72.6

15. AVAIL 181LITY FACTOR (t) 54.2 B0.2 72.6 16 CAPACITY FACTOR (USING MDC) (t) 46.7 70.2 58.7

'17. CAPACITY FACTOR (USING DESIGN MWe) (t) 47.3 68.2 57.1

18. FORCED DUTAGE FACTOR (t) 15.0 2.7 10.0

19. SHUDOWS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURAi!0N OF EACN):

none

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

n/a

y 3.0 DPEReil ] DATA $1AlllTICS l 3.2 OPERAT!W (. '. REPORT-UN!1 THREE -

DOCKET C. 050 249 UNIT DRE$ DEN THREE DATE 3ANUARY 1,1990 COMPLETED BY 0.M. PARAMORE TELEPHONE (815)-942-2920 OPERAi!$ STATU$

1, REPORTING PERIOD:

DECEMBER 1989 GROSS HOUR $ IN REPORilNG PERIOD:

744

2. CURRENTLY AUTHORIZED POWER LEVEL (Mt):

2,527 MAX DEPEND CAPACliY (Me-Net):

773 DE$10N ELECTRICAL RATING (Me-Net) 794 Si POKR LEYEL TO WHICH RESTRICIED (IF ANV) (Se-Net):

N/A 4.

REASONS FOR RESTRICTION (IF ANY):

REPORf!NG PERIOD DATA THIS MONTH YEAR TO-DATE CUMULAi!UE 5.

TIME REACTOR CRITICAL (HOURS) 51.2 7,323.9 120,232.2

- 6. 'il] REACTOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0

- 7.

TIME GENERA 10R ON-LINE (HOURS) 51.2 7,237.4 112,361.5-

8. T1] GENERATOR RESERVE SHUTDOWN (HOUR $)

0.0 0.0 0.0

9. THERMAL ENER0Y DENERATED (MWHt-Gross) 99,393 16,642,961 231,627,420

10. ELECTRICAL ENER0Y DENERATED (MWHe-Gross) 31,599 5,373,536 74,762,245

11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 24,244 5,117,954 70,055,3P'

12. REACTOR SERYlCE FACTOR (t) 6.9 B3.6 74.3

13. REACTOR AVAILABILITY FACTOR (t) 6.9 83.6 74.3 14.-$ERVICEFAct0R(t) 6.9 82.6 69.5

'15. AUAILIBill1Y FACTOR (t) 6.9 02.6 69.5

! 16. CAPACITY FAtiOR (USING MDC) (t) 4.2 75.6 56.7

17. C'.'ACITY FACTOR (USING Dr*10N Me) (t) 4.1 73.6 55.2 i

10. FORCED OUTAGE FACTOR (t) 0.0 3.1 12.1 l

19. $HUTDOWNS $CHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DLRAi!0N OF EACH):

none

20. IF $HUTDOWN AT END OF REPORT PERIOD, ESilMATED DATE OF STARTUP:

1 FEBRiit,RY 10, 1990 i

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DOCKET NO. 050-237-UNIT NAME DRESDEN IINII.II..

3.5 II]!LT DATE

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-v 1. 1990 COMPLETED BY..G. Par - re TELEPHONE (8151942-2920 REPORT MOL"!

DECEMBER. 1989 METHOD OF LICENSEE Sq COMPOgENT CAUSE & CORRECTIVE 1

2 NO.

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

DOWN REACTOR REPORT #

PREVENT RECURRENCE i

8 12-10-89 S

269.85 B

1 N/A N/A N/A On December 10, 1989 Dresden Unit 2 began a planned cutage to facilitate testing af the 125 VDC batteries.

9 12-22-89 F

71.17 H

1 N/A TI TRP On December 22, 1989 Dresden Unit 2 was separated from the grid due to seal oil backing up into the generator casing.

It was determined that a clogged seal oil float trap caused oil to overflow the hydrogen seal oil drain enlargement, resulting in oil backing up into the generator casing. The generator casing was drained and inspections were performed.

The clogged seal oil float trap was cleaned of oil & debris.

The generator was synchronized to the grid at 0210 hours0.00243 days 0.0583 hours 3.472222e-4 weeks 7.9905e-5 months on December-25, 1989.

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-0161)

E-Operator Training & Licensee Examination 5-Load Reduction F-Administrative G-Operational Error 5 Exhibit I - Same Source ZR16/10 H-Other (Explain)

DOCKET NO.~ 050-249-UNIT NAIE IEEEDEN IIBIT III 3.6 UNIT SHUTDOWNS AND POWER REDUCTIONS DATE Januart;.1. 1990 ~

1 COMPLETED BY G. Far - -e' TELEPHONE (8151942-292D REPORT MONTH DECEMBER. 1989 METHOD OF LICENSEE SYSTEg COMP 0(ENT CAUSE & CORRECTIVE 7

NO.

DATE TTPE DURATION REASON SHUTTING EVENT CODE CODE'

' ACTION TD (HOURS)

DOWN REACTOR REPORT #

PREVENT RECURRENCE 6

12-3-89 S

692.78 C

1-N/A N/A N/A~

In the lith refueling outage (through February, 1990) i 4

l 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-0161)

E-Operator Training & Licensee Examination 5-Load Reduction F-Administrative G-Operational Error 5 Exhibit I - Same Source ZR16/10 H-Other (Explain)

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7-00fMONWRAL111 EDISON COMPANY - DRESDEN NUCLEAR POWER STATION y

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MAXIMUM DAILY ELECTRICAL LOAD FORM FOR THE MONTH OF DEC, 1989 l

1 Day Hour Ending kWe i

1 1600 1498200.

t 2

1700 1496700.

3 0100 1031700.

4 2200 825300.

t 5

2000 826900.

N 6

0500 824500.

7 0800 826000.

p-8 0100 812600.

I 9

1000 784800.

10 0100 167400.

11 0000 0.

l; 12 0000 0.

W 13 0000 0.

14 0000 C.

4 15 0000 0.

16 0000 0.

17 0000 0.

i 18 0000 0.

19 0000 0.

20 0000 0.

21 2400 524200.

22 0100 525700.

23 0100 100.

24 0100 100.

25 2400 559400.

26 2000 703700.

27 2300 825000.

28 0100 819100.

29 1100 789000.

30 2100 788800.

31 2200 797700.

TOTAL

15426900, i

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4.0 UKlQUE RFPDRTING REOUIREMENTS 4.1 MAIN STFAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period December, 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 U.Alles of Plant Descrigtion Unit Data Actuated Actuations Conditione of Events 3

12/89 Safety Valve

2. Manual Refuel These spare safety serial Nost valves were rebuilt BK 7160 and bench tested for BK 6530 future use.

IR16/10

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1 4.2 0FF-SITE DOSE CALCULATI(M MANUAL (ODCM) CHANGES No 0DCM changes were reported for the month of December 1989, e

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'4 3 - ' MAJOR CHANGES TO THE RADIOACTIVE WASTE TREAINENT SYSTDtS There were no major changes to the radioactive waste treatment systems at Dresden during the reporting period.

4.4 FAILED FUEL ELEMENT INDICATIONS 4.4.1 Unit 2 Dresden Unit 2 fuel performance during December 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 i

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

4.4.2 Unit 3 Dresden Unit 3 fuel performance during December 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,Q ' PuuT OR PRocEntmE chWGES. TEETS. ErPERIMENTS. AND RAFETY RRfATED MAINTENANCE

-l

-o 5.1

' Amendments to Facility License or Technical Specifications The license amendments and/or Technical Specification changes which were

^

s' approved and haplemented for.use during the reporting period are listed below.

5.1.1 Unit 2 f

i

None, i

P 5.1.2 Unit 3 None i

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

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c M S TO PROCEDURES WHICH'ARE DESCRIBED IN-THE FSAR-(UNITS 2'AND 3)'

PROCEDURE TYPE PROCEDURE NO.

PROCEDURE TITLE / DESCRIPTION SGMARY OF c.1 ee Dresden Administrative DAP 7-5 Operating Logs and Records

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Procedure (DAP) t NOTES: 1.

Administrative change; intent of procedure unchanged.

2.

Changed for clarification, intent of procedure unchanged.

3.

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

Changed 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 l

(Units 2 and 3)

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r Significant special procedures involving tests not described in the FSAR which were approved during the month are listed below.

i Procedure No.

Procedure Title /Descriotion j

f SP 89-12-124 This procedure provided modification testing for

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SP 89-12-127 Unit 3 3B Recirculation Motor Generator Set oil L-cooler bypass lines, which were installed in accordance with Modification M12-3-88-66.

l SP 89-12-129 This procedure allowed for measuring the 1

instrument response time for the Generator Load Reject circuitry. This information will be used to ensure that the values used for the safety reload analysis are accurate.

SP 89-12-137 This procedure delineated the steps and actions that.were required to remove and install a jet l

pump beam working f rom the refuel bridge.

(

SP 89-12-140 This procedure was implemented to individually test five Control Rod Drive (CRD) Hydraulic Control Unit (HOU) 305-115 valves with the CRD HCU 301-25 valve out-of-service.

1 SP 89-12-145 This procedure provided modification testing for the Unit 3 3A Low Pressure Coolatt Injection (LPCI) Heat Exchanger Shell Side Vent Modification.

5.4 Safety related maintenance (Units 2 and 3)

Safety related maintenance activities are summarized in the attached tables.

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5 5 Comp 10ted Saf0ty R;1; tid Modifications (Units 2 and 3) j Unit 2 and Unit 3 safety related modification packages closed during the l

month of December, 1989 are listed below. Only modifications which have l

. been' completely closed are listed; modifications.which are authorized for use.but not completely closed will be reported based on the date of their

- tinal closure.

For ease of reference, the changes have been identified by their design change control modification number.

l t1Qdification No.

Description

]

I.

. None No safety related modification packages were I

closed during the month of December, 1989.

i

)

4 l:

1 1

ZR16/10

5.6 Temporcry System Alt: rations (Unit 2 and Unit 3)

A'" Temporary 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 i

pieces. Alterations controlled and documented as part of a routine out-of-service or other procedure, alterations which are a normal I

L feature of system design, and hoses installed as part of a venting or draining process are not included.

5.6.1 Unit 2 L-f Temporary i

{

System Installation Removal AllerAtion No.

Description Data Date i

11-81-89 Alteration to suspend a 12-11-89 a chain and buoy device from the grating floor i

in the Cribhouse to indicate water level in the Contain-ment Cooling Service Water (CCSW) suction bay.

II-82-89 Alteration to remove 12-12-89 12-13-89 recirculation system auto-matic controller from panel i

902-4 to mask scales for Detailed Control Room Design Review (DCRDR) human factors control panel work. Altera-tion removed manual / automatic l

speed controllers to upgrade i

scales for DCRDR.

11-83-89 Alteration to remove manual / 12-12-89 12-13-89 automatic speed controller on the "A" recirculation pump at panel 902-4 to up-l grade the scales for the l

DCRDR work. The motor-generator (MG) set scoop tube was locked out to maintain a constant pump speed.

l l

t ZR16/10

'5.6.1 Unit 2 (Cont'd)

L Tempor ry System Installation Removal i

Alteration No.

Description Data Date 11-84-89 Alteration to install a 12-17-89 I

temporary hose from the discharge of deep well pump #1 to the well water i

supply piping, pending l

repairs to a frozen water 1

main.

I II-85-89 Alteration to install a 12-19-89 jumper to defeat the high crankcase pressure switch on the Unit 2/3 Diesel Generator.

The alteration maintained operability of f

the diesel generator (pending installation of a new crank-case pressure switch) without limiting ability to perform its emergency function.

t 11-86-89 Alteration to install jumper 12/22/89 between terminal points. RC and G on the PRIME computer recirculation fan to bypass 4

a failed on/off switch pending repairs.

1 i

l ZR16/10

['

5.6.2 Unit 3 Temporary System Installation Removal A11aration Not Description DAtt Date l

III-48-89 Alteration to lift cable 12-4-89

76024 at terminal point W-1 of panel 903-3, install a jumper from-W-7 to AA-44, lif t cable

76027 at terminal point XX-1 and install jumper irom XXO7 to RR-34.

This alteration was performed

+

to support DCRDR work in accordance with Modification M12-3-86-241.

t i

111-50-89 Alteration to allow instal-12-4-89 lation of jumpers to allow busses 35, 36, 37, 38 and i

39 to be paralled for breaker maintenance and relay calibration.

III-51-89 Alteration to disconnect 12-5-89 12-15-89 present feed of Low Pressure Coolant Injection (LPOI) flow recorder 3-1540-7 and feed it from essential bus circuit 14, to facilitate installation i

of Modifcation M12-3-86-24A.

III-52-8P Alteration to install a blank 12-6-89 flange on the alterrex bearing oil system of the main generator to facilitate maintenance activities and permit the operation of the oil system.

111-53-89 Alteration to temporarily 12-6-89 lift cable 38734 at junction box 3TB-132. This disabled the carbon dioxide system to faciliate removal of Alterex housing to perform maintenance work on the main generator.

ZR16/10

n 3

L i

5.6.2' Unit 3 (Cont'd)

)

l k

Temporary l

System Installation Removal

)

Alteration No.

Description Dalm Date i

111-54-89 Alteration to install a blank 12-7-89 flange on the carbon dioxide supply line to prevent foreign material from getting into the piping during main. generator maintenance work.

111-55-89 Alteration to install a three 12-12-89 way jumper from terminal point AA-62 to AA-59 and relay 127 i

(pin 4) at panel 903-28. The purpose of this-jumper is to bypass rod blocks, while all fuel is out of the reactor vessel to facilitate replace-i ment of CRDs and perform t

maintenance work on Source Range Monitor (SRMs) and Intermediate Range Monitor (IRMs).

1 111-56-89 Alteration to install jumpers 12-12-89 at terminals B-55 to B-56 B-57 to B-48 at panel 903-15, and B-57 to B-56, B-57 to B-58 i

at panel 903-17 to facilitate l

installation of modification l

M12-3-88-46. Placement of

[*

l these jumpers prevented a l

Group II isolation from spurious I

drywell high radiation signals during the modification work.

This alteration was permitted with the unit is in a refuel outage with no fuel in the vessel.

I l

l ZR16/10

].Q > s,.;;

a:

g f

5 5.6.2i

, Unit 3 (cont'd)-

4 i.-

~

4-;

ETemporary.

~ "

System Installation Removal qi, Alteration No.

'Descriolion Date Date l

-111-57-89

~ Alteration to provide an 12-16-89 23-89 4

alternate feed for the annunciator windows E-19, h-F-19, A-17 and G-18 at panel 903-4 for installation of' Modification M12-3-80-22B..

III-58-89

' Alteration to repi b...che 12-18-89 12-22-89 shutdown cooling ch? f al pool I

cooling temperatuae recorder (3-1040-2) at panel 903-4

+

with a newer model.

Temporary indication of point 11 on the recorder (skimmer surge tank outlet-temperature) was provided'during the replacement.

4 III-59 Alteration to replace reactor 12-21-89 12-23-89 r

conductivity recorder.- This recorder indicates reactor water conductivity at the inlet and outlet of the cleanup demineralizers. During the i

replacement, local conductivity measurements were taken at the local rack 2203-2.

i 4

I i

1 g

l

1..

l l

ZR16/10 l-l l s; a

i

ML20005G490

Text

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