Text

Monthly Operating Repts for Mar 1993 for Dresden Nuclear Power Station Units 1,2 & 3
	ML20035E554
Person / Time
Site:	Dresden
Issue date:	03/31/1993
From:	King G, Schroeder C; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
	CWS-LTR-93-0148, CWS-LTR-93-148, NUDOCS 9304160169
	Download: ML20035E554 (39)
	v • d • e

,

Commonwealth Edison i

O Dresden Nuclear Power Station C

R.R. 41 1

Morris, Illinois 60450

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Telephone 815/942-2920 l

l April 1,1993 CWS LTR #93-0148 Director, Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 l

Attention: Document Contr>J Desk l

Gentlemen:

Subject:

Monthly Operating Data Report Dresden Nudear Power Station I

Commonwealth Edison Company Docket Nos.50-010,50-237, and 50-249 Enclosed is the Dresden Nuclear Power Station Monthly Operating Summary Report for Alarch,1993. This information is supplied to your office in accordance with the instructions set forth in Regulatory Guide 1.16.

Sincerely, t,3 Cha #es T '. Schroeddr l

Station Manager CWS/DCM:cfg Enclosure ec:

NRC Region III Office Illinois Dept. of Nuclear Safety, State of Illsnois U.S. NRC, Document Management Branch Nuclear Licensing Administrator T. S. Engr. Greg King NRC Senior Resident Inspector Station Quality Verification - Dnsden Comptroller's OIlice Nuclear Oiersight Manager l

INPO Records Center UDI,Inc.- Wash.,D.C.

File /NRC Op. Data File / Numerical l

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i MONTIILY NRC

SUMMARY

OF OPERATING EXPERIENCE, j

CilANGES, TE5TS, AND EXPERIMENTS PER REGULATORY GUIDE 1.16 AND 10 CFR 59.59 R)R DRESDEN NUCLEAR POWER STATION COMMONWEALTil EDISON COMPANY R)R March,1993 f

UNIT DOCKET LICENSE 1

050-010 DPR-2 i

i 2

050-237 DPR-19 3

050-249 DPR-25 i

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f TABLE OF CONTFNFS Marth,1993 NRC REPORT 1.0 Introduction 2.0 Stanmary of Operating Expaience 2.1 Unit 2 31onthly Operating Experience Summary.

2.2 Unit 3 Monthly Operating Experience Summary.

3.0 Operating Data Statistics

(

3.1 Monthly Operating Data Report - Unit 2 l

3.2 Monthly Operating Data Report - Unit 3 l

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 l

3.6 Unit Shutdown and Power Reduction Data - Unit 3 3.7 Station Maximum Daily Load Data 4.0 Unique Reporting Requimnents i

4.1 Main Steam Relief and/or Safety Valve Operatior.s - Unit 2 and Unit 3 l

4.2 Off-Site Dose Calculation Manual Changes l

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 l

l 5.0 Plant or Procedure Changes, Tests, Expaiments, 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) l 5.3 Significant Tests and Experiments Not Described in the FSAR (Units 2 and 3) l 5.4 Safety Related Maintenance (Units 2 and 3) l 5.5 Completed Safety Relahd Modifications 5.6 Tunporary System Alterations Installed 5.7 Other Required 10 CFR 50.59 Evaluations (Units 2 and 3) 1

1.0 Introduction 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 (AIWe). The unit is retired in place with all nuclear fuel removed from the reactor vessel.

Therefore, no Unit I 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 Riser 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 for March,1993 was compiled by Gregory II. King of the Dresden Technical Staff, telephone t

number (815) 942-2920, extension 2648.

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l 2.0

SUMMARY

OF OPERATING EXPERIENCE II)R Marrh,1993 2.1 UNIT 2 MONTitLY OPERATING EXPERIENCE

SUMMARY

03-01-93 to 03-31-93 Unit 2 entered the month shutdown, and in week ten of outage D2R13. The Unit finished the month stillin outage D2R13 and scheduled to become critical again on April 29,1993 i

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2.0

SUMMARY

OF OPERATING EXITsRIENCE FUR Marrh,1993 2.2 UNIT 3 SiONTIILY OPERATING EXPERIENCE SU3131ARY 03-01-93 to 02-31-93 Unit 3 entered the month shutdown, and in week one of forced outage # 2. The Unit finished the month still in outage and scheduled to become critical again on 5tay 02,1993.

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l 3.0 OPERATING DATA REM)RT 3.1 OPERATING DATA REPORT - DRESDEN UNIT TWO l

DOCKUT No.

050-237 DATE April 1,1993 COMPLETED BY G.H. King TELEPHONE (815) 942-2920 OPERATING STATUS l

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1. REPORTING PERIOD: March,1993 l

2. CURRENTLY AUTHORIZED POWER LEVEL (MWth): 2,527 i

MAXIMUM DEPENDABLE CAPACITY (MWe NET): 772 l

DESIGN ELECTRICAL RATING (MWe Net): 794 l

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY)(MWe Net): N/A l

4. REASONS FOR RESTRICTIONS (IF ANY): N/A i

REPORTING PERIOD DATA CUMULATIVE f l TIIIS MONTH YEAR TO DATE PARAMETER l

5.

HOURS IN PERIOD 744 2180 200,592 6.

TIME REACTOR CRITICA1 (Hours) 0 389.58 149.961.36 7.

TIME REACTOR RESLTLVE SHUTDOWN (Hours) 0 0

0 I

8.

TIME GENERATOR ON-LINE (Hours) 0 389.58 143.622.32 9.

TIME GENERATOR RESERVE SHUTDOWN (Hours) 0 0

0 10.

THERMAL ENERGY GENERATED (MWH1 Grou) 0 714,142 296.401.899 11.

ELECTRICAL ENERGY GENERATED (MWHe Gross) 0 226,547 94611,187 12.

ELECTRICAL ENERGY GENERATED (MWHe Net) 0 211,344 90.449,206 13.

REACTOR SERVICE FACTOR (W) 0 52.36 72.11 14.

REACTOR AVAILABILITY FACTOR (%)

0

$2.36 72.11 15.

GENERATOR SERVICE FACTOR (%)

0 52.36 72.11 16.

GENERATOR AVAILABILITY FACTOR (%)

0 52.36 72.11 17.

CAPACITY FACTOR (U5ING MDC Net)(%)

0 19.31 58.55 18.

CAPACTTY FACTOR (USING DER Net) (%)

0 18.80 57 19.

FORCED OUTAGE FACTOR (%)

0 72.49 28.13 20.

SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS l

(Type, Date and Duration of Each) l None.

21.

IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP 04/29/93

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3.0 OPERATING DATA REIORT

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3.2 OPERATING DATA REPORT - DRESDEN UNIT THREE e

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DOCKET No.

050-249 DATE April 1,1993 j

COMPLETED BY G. H. King j

TELEPHONE (815) 942-2920

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OPERATING STATUS L

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1. REPORTING PERIOD: March,1993

2. CURRENTLY AUTHORIZED POWER LEVEL (MWth): 2,527 MAXIMUM DEPENDABLE CAPACITY (MWe Net): 773 t

DESIGN ELECTRICAL RATING (MWe Net): 794 i

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY)(MWe Net): N/A

4. REASONS FOR RESTRICTIONS (IF ANY): N/A I

i REPORTING PERIOD DATA f

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PARAMETER THIS MONTH YEAR TO DATE CUMULATIVE 5.

HOURS IN PERIOD 744 2160 190,177 l

6.

TIME REACTOR CRITICAL Olours) 0 1265.25 136.854.63 1

7.

TIME REACTOR RESERVE SHUTDOWN 01ours) 0 0

0 i

1 8.

TIME GENERATOR ON-LINE Olours) 0 1252.1 131,525.50 l

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TIME GENERATOR RESERVE SHUTDOWN 01ours) 0 0

0 I

10.

THERMAL ENERGY GENERATED (MWHt Grcas) 0 2,833,249 270,362,704 i

i 11.

ELECTRICAL ENERGY GENERATED (MWHe Gross) 0 906.910 86.884,117 12.

ELECTRICAL ENERGY GENERATED (MWHe Net) 0 881,625 82,491,805 13.

REACTOR SERVICE FACTOR (%)

0 89.35 72.24 J

i 14.

REACTOR AVAILABILITY FACTOR (%)

0 89.35 72.24 15.

GENERATOR SERVICE FACTOR (%)

0 88.43 69.43 l

16.

GENERATOR AVAILABILITY FACTOR (5) 0 88.43 69 43 17.

CAPACTTY FACTOR (U$ING MDC Net)(%)

0 80.54 56.33 18.

CAPACITY FACTOR (U$1NG DER Net) (%)

0 78A2 54.84 19.

FORCED OUTAGE FACTOR (%)

100 23.7 31.2 l

20.

SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (Type, Date and Duration of Each)

NONE.

21.

IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP 05/02/93.

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3.3 AVERAGE DAILY UNIT POWER LEVEL 1

l DOCKET No.

050-237 j

UNIT Dresden 2 DATE April 1,1993 i

COhlPLETED BY G. H. King l

TELEPilONE (815) 942-2920 l

510NTII: March,1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (51We Net)

(51We Net) t i

THE AVERAGE DAILY POWER LEVELS M)R THE DATE RANGE OF 03/01/93 THROUGH 03/31/93 IS ZERO (0)

DUE TO THE UNIT OUTAGE..

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3.4 AVERAGE DAILY UNIT POWER LEVEL l

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DOCKET No.

050-249 f

UNIT Dresden 3 i

DATE April 1,1993 l

COMPLETED BY G. II. King TELEPIIONE (815) 942-2920 1

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i MONTII: Mards,1993 i

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l

3 (MWe Net)

(MWe Net) l TIIE AVERAGE DAILY POWER LEVELS FDR TiiE DATE RANGE OF 83/81/93 TilROUGli 83/31/93 IS ZERO (0) l DUE TO TIIE UNIT OUTAGE..

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Docket No.

050-249 UNIT NASIE Dresden Unit 3 DATE April I,1993 Completed Ily G. II. King Telephone (815) 942-2920 3.6 UNIT SIIUTDOWNS AND POWER REDUCTIONS RE14)RT STONTII 5tarch,1993 No.

IwTE TWi-II)

[*R Al F)N Rt. AWN f*J htITHol> OF llCI NN1F. INI NT

$YtrlM (131414)

(TAfPON!NT (T) tile)

CAUW A IT)RRi'CTIVE M* Tion 1U PRIMNT Rf(VRRENCE 040UR9 MHTITfMO lwTWN RI.PURT #

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On (4)

F: FORCED Re.,on:

hiehod:

Exhibit G Instmetions ihr Preparation of Data S: SCilEDULED Entry Sheets for Licensee Event Reports (LER)

A. Equipment Failure (Explain)

1. Menunt File (NUREGol61)

B Maintenance of Test

2. Manuel Serern C Refueling

3. Autmnatic Scram (5)

D Regulatory Rentriction

4. Other (Explain)

E Opemtor Training & Licensee Eum

5. Load Reduction Exhibit i Some Source as eMe.

F Adnunistrative G Operationn! Ermr II Other (ExpInin)

(GHKLT92/2)/28

i 3.7 COMMONWEALTH EDISON COMPANY DRESDEN NUCLEAR POWER STATION MAXIMUM DAILY ELECTRICAL LOAD FOR THE MONTH OF March,1993 Day Hour Ending KWe COMPUTER PROGRAM NOT OPERATIONAL..

THE MAXIMUM DAILY ELECTRICAL LOAD FOR Tile DATE RANGE OF 03/01/93 TIIROUGil 03/31/93 IS ZERO (0) DL'E TO TIIE DUAL UNIT OUTAGE.,

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4.0 UNIQUE REPORTING REQUIREMENTS 4.1 MAIN STEAM RELIEF VALVE OPERATM)NS Relief valve operations during the 31 arch,1993 reporting period are summarized in the following table. The table includes information as to which relief valte was actuated, how it was actuated, and the circumstances i

resulting in its actuation.

Valses No. and Type Plant Description Unit Ilate Actuated of Actuations Conditions of Events 1

i 2

No Unit 2 Main Steam Relief and/or Safety Valve actuations occurred during this reporting period.

l 3

No Unit 3 Main Steam Relief and/or Safety Valve actuations occurred during this reporting period.

}

4.2 OFF-SITE DOSE CALCULATION MANUAL (ODCM) CHANGES The following changes were made to the ODCMfor this reporting period.

q None

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l 4.3 MAJOR CHANGES TO THE RADIOACTIVE WASTE TREATMENT SYSTEMS DURING I

March,1993 i

Current Status of Radioactive Waste Treatment System Upgrade Project:

i No significant change to report for the month of March 1993.

4.4 FAILED FUEL ELEMENT INDK'ATIONS 4.4.1 Unit 2 Unit 2 fuel perfonnance during March,1993 continued to show no indications of leaking fuel. This is based on I

the sum of the activities of the six (O Noble Gases as measured at the Recombiner. Therefore, Unit 2 had excellent fuel perfonnance.

f 4.4.2 Unit 3 Unit 3 fuel perfonnance during March,1993 continued to show no indications of leaking fuel. This is based on the sum of the activities of the six (4 Noble Gases as measured at the Recombiner. Therefore, Unit 3 had excellent fuel performance.

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j 5.0 PLANT OR PROCEDURE CIIANGES, TFSFS, EXPERIMEWIS, AND SAIETY RELATED MAINTENANCE

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5.1 Amendments to Facility License or Technical Specifications.

Technical Specification amendment 121 to Unit 2 was distributed to the plant Technical Specifications.

This amendment modified the reload licensing methodologies referenced in Section 6.0, Administrative Controls which are used by the present fuel tendor, Sinnens Nuclear Power (SNP). The methodologies have been previously apprmed by the NRC. Use of the methodologies has resulted in a change in the MCPR Safety Limit (SleMCPR) from 1.05 for GE fuel and 1.06 for Exxon fuel to 1.08. References to the SleMCPR for GE fuel have also been mnoved from the Technical Specifications pages within this amendment.

5.2 Changes to Procedures Which are Dcscribed in the FSAR (Units 2 and 3 during March,1993.

i Table 5.2.1, attached, summarizes the procedures described in the FSAR which were approved for use during this reporting period. Only those procedures that have required a new or an additional 10CFR 50.59 review of changes are included. (Procedures approved for use during the month of March are summarized below)

PROCEDURE CHANGES l FOR THE MONTH OF_ MARCH SHALL BE.INCLUDFE IN THE APRIL NRC REPORT.

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i TABLE 5.2.1 CIIANGESTO PROCEDURES WillCil ARE DESCRIBED IN Tile FSAR ( UNTI3 2 AND 3 ) FOR March,1993 PROCEDURE TVI'E PROCEDURE NO.

PROCEDURE TITLE /DESCRII' TION

SUMMARY

OF CilANGES SAFETY RELATED l'ROCEDURE CIIANGES FOR Tile MONTil OF March ARE DESCRIBED IN SECTION 5.2 OF Tills REPORT, 1

NOTES:

1. Administrative charge; intent of pnxedure uncharged.

2. Charged fbr clarification, intent of prxedure unchaq:ed.

3. Charged to incorporate requirements for new equipment; intent of procedure uncharged.

4. Charged to implement irnrnwed testirg / calibration methoddgy;ireent of procedure uncharged.

(GHKLT92 /2) /29

5.3 Significant tests and experiments not described in the FSAR (Units 2 & 3)

Significant special procedures involving tests not described in the FSAR which were approved during the month of Starch,1993 are listed in the attached table:

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SELECTION CRITERIA:

10%YS %TE 10 SA6C CF 63/fl,03' THR' %31/03'

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i 0 25 IST UNIT CDSENS ISCRIP I

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93-3-21 2

L. JAC0EEN DIFFERENTIAL PRESSURE TEST OF es-2-1462-3EB 2

93-3-22 2

T. MURPHY MYWELL FLOGR NAIN SUMP A0 NfWELL EirJIPhENT MAIN SUMP AIR OPERATED j

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3 93-3-23 2

J. LARSEN UNCOUPLED RUN OF 2A REACTCR RECIRCULATIDN PUMP MOTOR l

4 93-3-24 3

H. MAGNOSTOP00LDS REMOVAL 0F UNIT 3 SOURCE RMSE ONITCR ITEC10R 824 USING THE SHIELID l

5 93-3-25 1

J. PDSKA C0NTROL R00M NCIMAL MDI VENTILATION PERf0RhMCE REQUIREMENTS 6

93-3-26 2

1. MURPHT NYWELL FLODR MAIN SUMP A0 NYWELL EDUIPMENT MAIN SUMP AIR OPEFATED 7

93-3-27 2

E.FRANINStAS MOD TEST FCR M12-2-90-960 l

8 93-3-28 2

L. JACOBSEN DIFFERENTIAL PRESSURE TEST OF M62-1501-33

+

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93-3-29 2

L. JACOBSEN DIFFERENTIAL PRESSURE TEST OF M92-1561-3A

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10 93-3-30 2

L.JACOBSEN-DIFFERENTIAL FRESSURE TEST OF M62-1492-3BA 11 93-3-31 2

R. BCRMM hDDIFICATIDN TEST FOR THE WWE CLOCK t0CATED ON THE 902-5 PANEL j

12 93-3-32 2

L.JACCESEN DIFFERENTIAL PRESSURE TEST OF M32-15M-133 13 93-3-33 2

P. KARA3A MOD TEST FCR M12-2-92-905A 14 93-3-34 2

P. IARABA CPERAEILITT TEST FOR M-12-2-92-005A.

i 15 93-3-35 9

1.TESTIN IETERMIMTION OF STROKE TIME REFERENCE VALVES FOR VALVES 2-1561-3A, 16 93-3-36 2

T.WOLZ h0D TEST FOR T0RUS TEMPEFATURE ONITCPIWS C00UIT RELOCATION AG MINOR i

17 93-3-37 3

M. PERRY U3 REACICR WATER CLEM-UP SYSTEM SURSE TMK DECON FLUSH ADMINISTRATIVE la 93-3-38 2

J. LARSON VIBRATION ANALYSIS OF THE 2A REACTOR RECIRCULATION PUMP AT ELEVATED l

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l 5.4 Safety Rdated Maintesiance (Unit 2 and 3) l i

Safety related maintenance activities for March,1993 are sumrnarized in the attached tables.

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PlcEVE NT T VE N/A

-REMOVED CARD 9 AND TERTED All. hiiTPUT TRIP SLAVF IWII I P' 'U. N+Wl '0H lt ' 4 31 i FUNCTIONS PER WORK INSTRUCTIDH',.

RANGE LEVit 2-2202-?

f*fCVENTIVE N/A

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REMOVED CARDS AND TESTED alt. f>HTPUI PANEL ANALDi talP rille DIV-2 ti 4 311 FUNCTIONS PER WORK INSTRUCTIDHi.

2-23?1 010 PN VLNTTV"_

N/A REMOVED CARDS AND IEST Al.l. OUli'U T TkiP MA% Ilk :i,!!1 i' I tel A 311 FUNCTIONS PER WOF(K INSTRUCT 10Ha.

F LEMISSIVE i-PhE d '8l qn

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iREMOVE'O CARDS AND 'TFRT ALL OutrOT 2-2191-etD PF-EV1NTIVE N/A

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FUNCTIONS PER WORK, INSTRUCTION %

TRIP MA'Ith UHli D'T l D1 A n t PE RM I SSI'Vi t PR['

oti 2-2191-O'.

ItJVrtJilVL N/A REMOVED CARD:i AND TEGitD All. O'lTrU T TRIP NA'ill P Mti i t 't. i 'i r t M utollt FUNCTIONS ILR NOF<K INSTRUCTIONi.

LINL H! ILU4 CilANDED WIRE TERM 2*TO TrRM 20. NDH 2-6723-2'?

r0RRrr1IVE N/A PUS EUDittl F6LD lit I to Dio ;? t WIRED FER PRINT.

FOUND 26 MA IN POS t.EAD OF XMt(TI:R, ONI.Y 2-263-140A CDRl;LCTIVE N/A TRIP MA'>li k UHi t Fx 10 LEV (i.

016 ; M

. 3 MA ON NEG LEAD. REMOVED SEAlfliE FITNil SCRAM /Isu' AiloN L AT XMITTER. FOUND HIRE WAS INDIED &

' INSUL CUT AND Sil0RTING TO GROUND.

P-1102 - A 00RbtTTLVE N/A INSTALLED NEW OfARINGS PFR WR.

MOTOR STANDl'y 1 i fr il l' W 2A t i t 6 16 /

.h a

2-O'.00 rD9hti;TIVE N/A EsNR F AILED TRIP TI-ST. IN91 A1 Lt D NEW bMR.

MISC SYSIFM LiAI:TUF I-I O f E C T ION 1 t 16170 IN 2AB-2 PANF L. USED LIrif:D/LAN!H D LCAD SHEET FOR REMUVAL. NEW UKR lE91Llf UK PER T.S.

INSTALLED NEW VLV INTO TEST Ett UCK P.

2-1100 l'hEVluitVE N/A MISC SYSlliM TIANDiY LitJUID t114411

. HOOKED UP POWER SUPPLY 120AC 10 VLV.

CONIROL TORQUED VLV INTO TEST DLOCK (.T 2G LGS.

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RrPAIRED LUU. RTFLACED CONTACT 0f A3MttL Y/

RELAY SCRAN 7/9-1F H 1: t "'/ YP

' STATIONARY CONTACTS / AUX CON 1ALIS, COMPLETED SURVEILL ANCE PACKAGt

,EM2-R13-67.

2-6601 LtNr:FLitVE N/n

. PERFORMED t;TEf* IN DEU 6600-03 70 RCMOVP:

ENGINE STANUDY DIErtt (J.NLHATOR t t1 %'95 1 POWER PACK AND REPLACE WIlH HEW POWER

'. PACK. INSTALLED ALL PARTS WITil DIRECTIDM 0F FACTORY REP.

RrMOVED OL LINE, REPLACE 0 NITil NF W LINEe 2-6601 CDFRtCTIVE N/A ENDINE 31A W.:V UllSil OfN!rATOR Di$107 QC HOLD POINIS F OR CLEAN, PRIGR TO INSTALLATION.

mw RELUGUED CA 3/512 & 67531. CLrANLD CUO.

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2-263-14DA 7hTUINTIVE N/A MMDVED CAkDS AND 7ESTFD All filr 7 PU T TRIP NASitR UNII At idW Li '1L L D16J11 FUNCTIONS PER HURN INSTRUC110HS.

SCRAM / ISOLATION 9

2-ZA3-1414 PUEVENTIVE N/A RE MOVED CARDS AND TESTED At t ollTrui TRIP MASTER UNIT Rx I UW t.I VE L I 16.: t 1 FUNCTIONS PER HURK INSTRUCT 10mi.

ECCS At REMOVED CARDS AND TESTED All DUTPUT 2-263-14'A PNEVENTIVE N/A TRIP MASILR UNil kX I UW Lt VEL D16311

_ FUNCTIONS PER WORK INS 1HUC1100.

SCRAM /150LATINN RF MOVED CARDG AND TESTED All 041001 2-263-1474 rkrVENTIVE N/A TRIP MASit h UNI) in 10W Ln VE L D i t, M 1 FUNCTIONS PER WORK INBlHUC110hn.

ECCS A2 REMOVED CARDS AND 4ESTED ALL OUTPUT 2-1501-9?D PREVENTIVE N/A VALVE MANuni rt ort no 1501 n16 :t t FUNCTIONS PER MORK INSTRUCT 10 0.

UPSTEN DRAlH 2-1626-10 rREVENTIVE N/A RLMOVED CARDS AND TESTF D AL L htl11'UT TRIP MASIER 0911 tithtts NAhkOW D? C:11

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REACTOR 2-9Y5-11/D CURRECTIVE N/A c t.IFTED LEAce CUT OfY BAD LUG AND CRINrto RELAY TIME DtlAY 100 COND D15Yo's

.NEW LUG ON USING PROCEDURC 2100-06. PUT rHIRE BACK OH SNUG TIGHT.

2-6641-5P7 00Rf:LCTIVE N/A OUTAINED NLW SWITCH AND GASKETS SWilCH D/G ENI.Itd U M AH1 WATFk levah EWITCH 254C97, GASMET 652131.

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2-66698 Cf4NLCTIVE N/A REMOVED OLO PIPE PLOOS/CifANEH THRt.. A09 HEAL EXCilANGLR D/G CHOLING DiSY?S

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CATER AND INSTALLED NEW' PIPE PLUGS. TIGHTENED

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2-0Y00 Cf?hrtTtVE N/A REPLACED STRAFS.

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2-1102-A MEVENTIVE N/A

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2-1705-101 PRE VE N TIVE N/A RELAY PRDtiS3 RADIAf10H MONITOR U11046 MLIDE IN NIW C" AND PERFORMED RELAY

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RX DLDG iULL REPL ACED COIL, CLF ANFD CONI ACLU, 2-1703-107 PFEULNTIVE N/A RELAY F F UCLS9 RAhlallON MONITOR Ditotn VFRIFILD CONT ACT DEVELOPMI NI AND VOL~lAGI TO Coll.

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2-1601-101 PAEVINTIVE N/A ROSE MOUN T TRAH3MIT TF f: l'OR D2 D10203 VERIF ACCUR a OPEND'TY. l'I Rf 'll AS FOUND PRIN CONIAIN B AS LEFT PER DIS 1600-13. REMOVED &

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2-7929-1H4 PkEM NTIVE H/h RCMVD NCC CUD BRN FOR MDV 140W 3h/ELHH.

SCOGR HRK LUht UI'R AY PP GUCT VLV (110'.i60 REPLCD AUX CONTACTS, COILS OPlH & CLUSE.

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2-7929-11 2 FhEViNTIVE N/A CLEANED / TESTED / REPLACED i0 COMPUNENT3 SWGR ORK COki SI'hoY I Nt :0 ISOL D I O' JV LISTED IN PARTS SFCTION.1EurlO ANil VLV 2-1402. %

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o 5.5 Completed Safdy Related Modifications (Units 2 and 3)

Modifications which have been authorized for operation during March,1993 are listed. For case of reference, the changes have been identified by their design change control modification number. Previously, only modifications that had been completely closed out were reported.

None.

l r

I i

I

l a

l l

1 l

5.6 Tanporary Systan Alterations Installed (Unit 2 and Unit 3)

I 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 switchs in i

alternate positions, temporary blank ilanges, and spool pieces. Alterations controlled and documented as part of a ruutine out-of-service or other procedure, alterations which are a nonnal feature of system design, and hoses installed as part of a tenting or draining process are not included.

THE ICLLOWING INFORMATION REFLECI'S TEMPORARY ALTERATIONS WHICH REMAIN OPEN FOR UNITS 2 & 3 AS OF April 4.1993.

l March,1993 l

l l

THE FDLIDWING INFORMATION REFLECI'S TEMPORARY ALTERATIONS WHICil WFJtE INSTALLED OR REMOVED DURING THE REPORTING PERIOD l

I

! tons wve nr e ntrTinv pr ane t rNrrru fvtT rruvn p rnt trtTrn 11-17-93 D16126 This temp. alt. will allow Install a portable 13-Mar 93 Tim MurT y h

transfers from the DHTDS submer6able pump to the DWEDS,it will also and route hoses to allow transfers from the suppon the DWEDS to the DWTDS.

replacement of tir Unit 2 DWFDS discharge AOV's 11-21-93 D08323 This temp. alt. installs a jumper to prevent U2 *B" Rx. Recire. 18-Mar-93 Ken House kop thermocouples form causing spurious iudations of the SDC system.

_., _ - i

11-23-93 D17078 Remove the alterex housmg To perfonn maintenance on the 25-Mar-93 IGn House (doghouse) on the Cardox alterex during the outage system 11-25-93 D14680 A recorder will be To record pressure variations in 31-Mar-93 M. Perry connected in parallel to the RWCU system during 5/U form following pressure D2R13 & 1217/1219 trim mod.

transmitters; PT 2-1291-13, PT2-1291-24, and PT2-1291-28.

HI-04-93 D15661 Installation of a corrosion 50 that corrosion 26-Mar-93 Mark Egler monitor near the Service bio-fouling, 6 Months Water dincharge.

conductivity and Ph can be monitored to meet requirements of G1. 89-13 1114 5-93 D17020 Provide temporary power to Installation of temp. <30 days 27-Mar-93 Dan Smythe cooper heat oven being u6ed 480V AC,90 Amp.,

for U3 Turb. wort 3 Phase power feed to 3 heat controllers form SWOR. 37 Cubicle 5B.

l l

l trna w>e tw yt wrtnN F FAoN t rauftp 1N5T P awfi Pf9'fntn

1.

.. ~

l i

F 1

D 74e3 th4%S Bush!! jumpre en ACI ami 167 'm This alkuws b aprms' m ad < 3 Wnds 22-Wr-93 Sapr 93 l

e namedl lesi aseet puel to herp Cemple -linn in kciuel K5 =w wpud.

i I

o-is*3 D1 h

a m n= 2aui v=w i=. h===

Tir kwCU 2-120i-ti 1 Month I 8-Mar-93 19-Mar-93 Jotui Reid i

19126 senswed, phg ne 7rt:3M* -L tur Vak (it

_ w Wm I

l w Gr Wm Caulsner with a Condocert) asede au ha plurnhem plus tair biskW) armand up spised. Emever, sormwel 7 - 10 psig. hE=W=in h pmmum the of h wh m'd! cuase s

}

entue tinr the plug a newlind.

temm4 of aemuuanty unusamnwiu indo htda Cor.lenwr. The mmp. sh.

wiu pervene the.

of Gus brauctL f

i i

11-19-93 D06089 in order to bump chaL the & Hrs.

17-Mar-93 17-Mar-93 J. Lundgren rotation opf the 2A shutdown cooling pump l

motor, the low suction

[

pressure interlock of the 2 A j

pump will be defeated.

j Because the pump is uncouplede from the motor, there will be no affect on i

the system.

f 6

Il-20-93 D06410 Install jumper to provide 24 Hours 17-Mar-93 17-Mar-93 Neil Spooner l

continuation of containment isolation neutral circuit i

during replacement of relay

[

2-595-102B under WR 1

t t

?

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=

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5.7 Other Units 2 and 3 Required 10 CFR 50.59 Evaluations for March,1993 Other required 10 CFR 50.59 evaluations include Set Point Changes. Rigging Evaluations and changes to equipment not reponed in Sections 5.2 through Section 5.6.

Installation No.

Descrirition l

OTIIER 10 CFR 50.59 EVALUATIONS FOR THE MONTil OF MARCII SilALL BE INCLUDED IN TIIE APRIL NRC REPORT...

i

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