ML17199W377

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Mar 1988
ML17199W377
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 03/31/1988
From: Eenigenberg E, Maxwell D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-237, NUDOCS 8804150406
Download: ML17199W377 (20)


Text

  • .*

OPERATING DATA REPORT DOCKET NO.

_0_50.._-_2-'3~7 ____ _

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

1.

Unit Name: --=D=-r=-e=-s=-d=-en=-I=-I=---------------

NOTES

2.

Reporting Period: -=M=a=rc=h~~1=9~8=8:::.------------

3.

Licensed Thermal Power (MWt): --=2L5=2=-7'---------

4.

Nameplate Rating (Gross MWe): ___ 8=2=8:::.---------

5.

Design Electrical Rating (Net MWe):

_.._79~4""--------

6.

Maximum Dependable Capacity (Gross MWe): _8=1=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:

NIA

9.

Power Level to Which Restricted, If Ai>.y (Net MWe):

N/A

--='-=--------------

10.

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

This Month Yr-to-Date

11.

Hours in Reporting Period 744 2,184

12.

Number of Hours Reactor Was Critical 744.0 2,184.0

13.

Reactor Reserve Shutdown Hours 0

0

14.

Hours Generator On-Line 744.0 2,184.0

15.

Unit Reserve Shutdown Hours 0

0

16.
17.
18.
19.
20.
21.
22.
23.
24.

Gross Thermal Energy Generated (MWH) 1,676,477 4,979,460 Gross Electrical Energy Generated (MWH) 533,397 1,595,183 Net Electrical Energy Generated (MWH) 508,386 1,523,041 Unit Service Factor 100.0 100.0 Unit Availability Factor 100.0 100.0 Unit Capacity Factor (Using MDC Net) 88.5 90.3 Unit Capacity Factor (Using DER Net) 86.l 87.8 Unit Forced Outage Rate 0.0 0.0 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

One week outage in May, 1988 for a dual unit outage to perform the 125V DC battery discharge test Cumulative 156,768 118, 755.2 0

113,277.2 0

232,955.323 74,534,176 70,448,031 72.3 72.3 58.2 56.6

11. 7
25.

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

0763t 8804150406 88033(

PDR ADOCK 05000237 R

DCD

-.-. -. --**~~-.----

~ ;. '

OPERATING DATA REPORT DOCKET NO.

""""0;;..50;;..---2"""4_.9 ____ _

DATE

_......;A:::.p~r::..;1:..:' l=--4,_,,L-..::1:...:::9..:::8..:::8_

COMPLETED BY _:::;.D..:.... C:::....:..... _.,M::.:axw=:...::e:..:lc:l __

TELEPHONE

-~8~15~/~9~4~2~-.....,2~9~2~0 __

OPERATING STATUS

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

Unit Name:

Dresden III Reporting Period:_~H~a~r~c~h:....L-~1~9~8~8'------------

Licensed Therma~ Power (MWt):


"'2""'-"-5~2~7------'---

Nameplate Rating (Gross MWe): ___

'.::;8=2.::;8 _______ _

Design Electrical Rating (Net MWe):

-~7~9-4 _____ _

Maximum Dependable Capacity (Gross MWe): __;*.::;8=1=2 ___ _

Maximum Dependable Capacity (Net MWe).: __

_,_7_,_7.::;3 ___ _

NOTES

8.

If Changes Occur in Capacity Ratings (Items 3 Through Reasons:

7) Since Last Report, Give NIA
9.

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

N/A

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

10.

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

This Month Yr-to-Date Cumulative

11.

Hours in Reporting Period 744 2.184 146.353

12.

Number of Hours Reactor Was Critical 626.4 2.066.4 108.628.5

13.

Reactor Reserve Shutdown Hours 0

0 0

14.

Hours Generator On-Line 626.0 2.066.

100.911.9

15.

Unit Reserve Shutdown Hours 0

0 0

16.

Gross Thermal Energy Generated (MWH) 1.455.641 4.792.721 206.175.337

17.

Gross Electrical Energy Generated (MWH) 469.867 1 1557 1623 66.589.235

18.

Net Electrical Energy Generated (MWH) 448.461 1.490.722 63.068.542

19.

Unit Service Factor 84.1 94.6 69.0

20.

Unit Availability Factor 84.l 94.6 69.0

21.

Unit Capacity Factor (Using MDC Net) 78.0 88.3 55.7

22.

Unit Capacity Factor (Using DER Net) 75.9 86.0 54.3

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 0763t

e COMMONWEALTH EDISON COMPANY DRESDEN STATION MAXIMUM DAILY LOAD MONTH OF FEBRUARY, 1988 DAY HOUR MAXIMUM DAILY LOAD ENDING KW 1

0900 1,535.000 2

0200 1.524. 200 3

0100 1,536,000 4

2200 1.539.300 5

2200 1.377 900.

6 2400 1.466 800 7

1900 1.571.000 8

0200 1.563 500 9

0900 -

1.571 800 10 2000 1.517.400 11 900

1. 515. 800 12 1900 1.550. 200 13 1300 1.508 600 14 1100 1.574.400 15 0100 1.529.400 16.

0100 1.508. 900 17 2400 1.507,500 18 0300 1.504.900 19 2100 1.091.600 20 2400 1.377. 700 21 2300 1.532.000 22 0200 1.537.400 23 1500

1. 566. 600 24 0100 1.531 300 25 1500 1.548 200 26 1000 1.530 400 27 0100 924 700 28 1100 769.200 29 1200 785 700 30 1000 785.100 31 0400 769.100 '

0763t

e e

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

050-237 UNIT II DATE March l, 1988 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 MONTH FEBRUARY, 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)*

(MWe-Net) 1 724 17 722 2

717 18 604 3

714 19 292 4

693 20 473 5

436 21 667 6

559

'** 22 751 7

789 23 708 8

770 24 747 9

704 25 768 10 712 26 694 11 731 27 743 12 719 28 744 13 718 29 730 14 750 30 718 15 716 31 756 16 723

'\\

0763t

MONTH DAY 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 0763t e

AVERAGE DAILY UNIT POWER LEVEL FEBRUARY, 1988 AVERAGE DAILY POWER LEVEL (MWe-Net) 739 709 699 721 751 765 768 756 700 699 723 723 722 747 718 722 DAY 17 18 19 20 21 22 23 24 25 26 27 28

'*_29 30 31 DOCKET NO.

050-249 UNIT III DATE March l, 1988 COMPLETED BY D.C. Maxwell TELEPHONE 815/942-2920 AVERAGE DAILY POWER LEVEL (MWe-Net) 718 709 714 722 720 718 749 720 744 611 0

0 0

0 0

i'

NO.

. DATE NONE 1

F: Forced s: Scheduled 0763t UNIT SHUTDOWNS AND POWER REDUC~IONS REPORT MONTH MARCH, 1988

  • TYPE1 REASON2 METHOD OF LICENSEE DURATION SHUTTING 3

(HOURS)

DOWN REACTOR 2*

Reason:

A-Equipment Failure (Explain)

B-Maintenance or Test C-Refueling D-Reguiatory Restriction EVENT REPORl' E-Operator Training & Licensee Examination

.F-Administrative G-Operataional Error H-Other (Explain)

II

.3 SYS_i'E*

CODE COMPO~ENT

  • coDE Method:

1-Manual 2-Manual Scram 3-Automalic Scram

  • 4-0ther ( Ezj>lain) 4 DOCKET N0._0~5~0~-~2=3~7'---~~~~

UNIT NAME DRESDEN UNIT II

  • DATE April 7,
  • 1988
  • .,'COMPLETED BY. D. C. Maxwell TELEPHONE (815)9i2-2920 CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE I

Exhibit G-Instructions for Preparation of Data Entry Shee.ts for Licensee Event Report (

) File (NUREG-0161) e e

I NO.

DATE 1

88-03-27

\\

1 F: Forced

  • s: Scheduled 0763t TYPE1 DURATION
  • (HOURS) s c1l~~o9>

2 Reason:

REASON2 c

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH MARCH, 1988 METHOD OF SHUTTING 3

DOWN REACTOR

  • 1 LICENSEE SYSTE~

EVENT CODE REPORT II

' 3 I

.Method:

1-Manual.

COMPO~ENT CODE A-Equipment Failure (Explain)

B-Maintenance or Test C-Refueling.

D-Reguiato~y.Restriction 2-Manual Scram E-Operator Training & Licensee Ex~i~ation F-Administrative G-Oper.ataional Error H-Other (Explain) 3-Automalic Scram.

4-0ther (Explain) 4 DOCKET N0._0~5~0~-~2~4~9~~~~

UNIT NAME DRESDEN UNIT*III.

DATE* April 7, 1988 COMPLETED BY D.C. Maxwell.

TELEPHONE (815)942-2920 CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE Unit off-line manually to ils 10th refueling outage Exhibit G-Instructions* for Preparation of Data Entry She*ets for Licensee Event Report (

) File (NUREG-0161)

EQUIP"ll'iH 1501-21A C2 TORUS RING H(AOER

~'JUf~EP~

CORE SPRAY Ml'I FLOW 2-1402-18'1

'R' LOOP RECIRC FLC~ l~DICATl8N 902-5 A-2 SCRAM ~ALVE AIR SUPPLY HIGH PRESSURE ALARM AfJ-2301-31 CVL!NO~R TEMPERATURE l~DICATOR 2-2501 ACAO COMPRESSOR

'JATUP.E OF MA.llHENHl(l' (fJ R Q_ I' C T I 1/f:

'..JP [l60fl91J

('_1Q.REC Tl VE "n n& i 1 l" P<<:".VE~'l!V::O

,JQ "h208f*

f'O.EVPHI Ve WR ')63 7':*'1 P'>FVEt1;T!VE

>lil.

n.~:d05q PPC:Vf'ITIV::

11R flb?. l 1><;

r (~ ( V;: ~!TI 'I" i~P Jo 1201 CiJRl'.ECT!Vc

\\JR "6P'}4 7 CfJR'HCTIVF AR 06?4J5 PREVEMT!VF

~!O. '11)'7 5 l l DP.[~l);:llJ U'l!T ?

SAFETY RFLATED

~AIMT[~A~CE L(P. OR OUT.\\Gf NIJ'IHE'l

'l/ A N/ A M!f\\

if A "l/ A

~I/ f\\

N/A*

MilLFUNCTIOM CAUSE RESULT CORRECTIVE ACTION INSTALLED 4

~EH RINGS OF.PACK INS, LEFT nK ExrcRCISEO POTENTIOMETER, PR03LEM CLEARf:O

<l.fMOVEO SMU3BERS FOR FUNCTIONAL TESTING, LEFT OK Rf.PLACED OVERLOAD RELAYS ANO LIMIT SWITC!i ASSEMFILY, COMPLETED PROCEDURES INSTALLED ANO REMOVFn TEST RECORDE~,

~ONITOREO SYSTEM ANO FOUllJD NO PRORLEMS INSPECTED ANO COMPLETED PROCEDURE, LEFT Ot<

RE~OVEO SEALTITES AND L!~IT SH!TCHFS l E Fl OK CLEANE1 LPR~ DETECTOR AFTER RlJNNP;r, <'LATEAU PEf' PROCEOUR.E, LEFT OK CHF.CKEO T/C CONNF.CTION, TAPED UP WIRES, FlJNCT!ONALLY TESTED ANO VEP.IFIED PR.OPER RESPONSE, LEFT OK UNHOOK~O COUPLING ANO THE MOTOR TURNED FREE* ISSUED WR:bq7qq FOR FURTHER WORK ON COMPRESSOR

EOUIPME!H LPRM 40-0'Hl LPRM 32-33C LPR"l 6C-40-09 LPRM 24-25B 2-305-42-55 CRO 2-305-30-43 CRO LPRMS IMOOEL NAJOOI LPRM l6-49C Ell RELATED RllSE'IOUNT TRANSMITTERS ACCUM 2-300-46-15 N.A TU'lE' OF t-11\\INTEt~l\\NCE CORRFC TlV>:

wr. IJ6'159l cnh:< (CT IVE WR 170lf1l CORRFCT!Vf:

WR 0703P COR>{EC TI Vf=

WR ')704'*2 UJR'lU TI vr;

'4R 070501 cc:r.~r_c rrvr:

wP.

  • 110<:.02 CORRE C T I V JC ri'l. D70553 UlRREC TlVE
  • wr '."l705Ht pqfVENTIVf:

WP. ::J7066l Cr:J~_C(f( T 11/r:

1-IR f)70Wl7 DR':'Df.N U~.'I T 2 SAFETY RELATUl "'A!NTf"JA'ICf LER

<)!:. OUT AGE N!JM~ ER N/ A "JI A r*:/A

~UA IJ/A MALFUNCT!(l'*t CAUSc RESULT CORRECTIVE ACTION PERFOPMED WORK INSTRUCTIONS ANO CLEANE~

LEl=T OK CLEANED PER WORK INSTRUCTION, LEFT OK ADJUST~O Pl\\CKl~G TO ELI~INATE LEAKAGE ADJUSTED PACKING TO FLIMINATE LEAKAGE PERFOR~ED PRnCEOURE ON LtSTED LPRM PERFQR~ED PROCEDURE, DETECTOR LOOKS GOOD CHECKED TRANSMITTER COVERS TIGHTNESS PER PPOCEDUPE, LEFT OK CHECKED CALirRATION AND FOUND NO PRr:JBLE~S, NO LEAKS

ECJU I PMErH LPRM 08-3311 RBM :11 213-5742 REACTnR BUILDING OUTLFT ISOLATION DAMPER 2B REACTOR BU!LOING OUTLET ISOLATION DAMPER 213-5742 REACTOR BUILQ!~G OUTLET ISOLATION DAMPER SRM 21 REFUEL FLOOR RA~ MONITOR CHNL A

A R~ACTOR BUILDING VENT MON I TOR 2-F!2350-l HP(! FLOW INDICATOR LPRM 40-33()

rJATIJQF or-MAINTf:'NlllKF.

CORP.[( T !VF.

~P. fl70 ~~,,

CORf{ECT!V~

WR D7 l.05h

>REVEt\\JTIVE WR 0711'07 cn<RTCTTV'

WR 07116'*

PREVEfH I VE wq iHl 1£1.?

CDP.REC TIVE WR 071243 C!.JRQ[( TI VE l*IR f'7 l ?.PO CORR EC TI VF

.1R ')7 l 3'1'>

(.OP'{f'.(TIV<:

~iR 'Hl4Zf, CJ1R'l.[( TI Vl'

'rlil. n7 l 53'J D Q F: <; ;"JI'. N lJ *! l T 2 SAF~TY oELATE'J

~A!NTf~ll~tE U:R OR OUTA(,F Nll~l) ER N/A

,.~I

N/11

'*i/ A

    • 1/ A N/ II NI A tlALFUi'JC T !ON CAllSF RESllLT CORRECTIVE ACTION CLcANEU CONNECTOR, COMPLETED PROCEDURE INSTALLED NEW OP AMP 'Al"* COMPLETED PROC~OUAE, LEFT OK Rf.PLACED COIL AND ISSUED W.R. FOR I.M.'S TU REPAIR OR REPLACE SWITCH CYCLED VALVE AND LUBRICATED, ADJUSTED PRESSURE SWITCH TO NORMAL OPERATING SETPDINT, LEFT OK CHECKED AND TIGHTENED ALL SCREW TERMINATIONS, CHECKED CO"ITROL SWITCHES A~O PUSHBUTTONS, Rf:PLACED

~OLENOID COIL,

S TO REPAIR SWITC~

QEPLACED OUAL TRIP CARO AND COMPLETED PRQCEOURE, LEFT OK CALJRRATEO 5~NSOR AN~ TRIP U~IT, MONITORED OOWN~CALE SPIKING, FOUND "10 p ROB u:r1 s REPLACED DETECTOR AND PERFO~MED PRO( EOIJRE, LEFT OK qEPLACED METER WITH NEW AND PERFORMED PROCEOURE, LFFT OK TROU!IL f:SHOT PER PROCEDURES AND FOUND NO PR'lP.Ll:MS

' I i,.

iu

EQUI PME'H 2-l &O l - 5 8 VA I_ V C:

LPRM 40-3313

'A' REFUEL FLOOR RADIATION l'IONITOR TR2-l64l-200A.

TORUS TEMP RECORDER DIV I

!RM CHANl~[L lb LPR'~ '*ll-33(

r.A-300 LPRllS rR lo4 l ZOOA TORUS rEMP RECOROC:R 2-1501-44(

CCSW PUMP NA-300 LPRMS Nl\\TIPE or.

Ml\\ I rnr:"JA~*lC.l.

PP.'C'Ji°'ll ! vF

\\*IR c17 161 'I PREVf:1HIVC:

~/R D7 lo44 Cn.RRECTIVE

~m 'Ht6't7 (f1RR£CTIVF.

WR 071763 C 0 Rf! EC T I VF.

..ill. D7l q6*1 P'~f.1[.'.! !VE l*IR

'J7 ?.CZ b P';F.vr:r: TI Vf:.

i,;c f"7 2 02 7 ClW~EC l !V1=

  • ,<n P720'"1t.

(G>H'[( T IVE

  • W? 07?. Z;?f)

PPEVENT!Vr:

WI>. D7245'5

(;?.r:*;o::N U'-II T 2 SAFFTY RELATE') "-AINTl:'*lll'ICF Lf:'l :-JR UUTllGF.

l\\jl_l,"l'"*f R Li/ A N/A

~:/ t.

'*II:.

1.1/ A N/f\\

'11\\LFIJNf TI ON

~/\\USE RESULT CORRF.CTIVE ACTION TIGHTENED GASKF.T COVER, CYCLED VALV[,

NO PRORLF.~S FnuNn PF.°FORMEO PP'.JCf:DIJRES, FOUND NO PROflLE.'~S INSTllLLtO NEW SENSOR CONVERTER, PERFnRMEO PROCEDURE, LEFT OK REPLACED ANO CALIPRATED RECORDFR PER PROCFDUR>:, LEFT nK CLC:ANED CAf'L~ CLINNFCTORS TO ELIMINATE SP IK TllG, PERFORMED PROCEDURE C0'1PLETEO PR'lCEOllRE, LEFT IJK T IGH TEME[! IDLER WHEEL AND I "JDE X DRIVE

'lf'L T, PUNS OK, COMPL<:TED PP.OCEC>UR[,

LE FT OK cu:11Nrn LANTERN RIMG, REPUCEO 4 P.!NGS OF p,\\(KJNG, LU"IR ICHED PACI< I"JG, LEFT OK

?f:PF!JP,MFO PRnCFQUP.E QN LPR~S. LEFT OK

EUUIPMENT 640-40C G.E. SQUARE ROOT CONVERTER E05-0l STATION OATTERIES LPRM AMP CARO Z63-l40B ROSEMOUNT M.T.U.

ARM l 94X927Gl I SPARI:

SHIS~lR CONVERTER I SRGT FAN DISCHARGE DAMPER 2/3-75078 INDICATOR/TRIP UNIT LOCAL LEAK RATE TE:ST BOX nrs 3Z 2/3 61:>0l CIESEL GENERATOR NATURE OF MAi'IH'NANCE CORf!.ECTIVC:

WR 050003 P'H: VFNT IV F WR 060930 CORRECT !VE wR D64591 CORRE( rrvr:

WR 069033 CORRE:C TIVE

-.iR )70650 (f)Rf(ECTIV"

',jR u709D'*

PP.EVEtlT [VF:

Ii ') 709'.*<J C;JR'l[( T!VF:

WR D7!3l2 P<l.EVEtiTlVE

./R !J7?43fl cH1. ES[) t N U '! I T

,~ / l SAF~*TY RELATEil MAINTfl~A'ICc LfR OR OUTl\\GE NUMf'Eil NI A M/A M/ A t.J//I N/ A N/:>.

'"I/A.

MALFUNC T !ON CAUSE PE SULT CORRECTIVE ACTION INSTALL[Q NEW ZERO ANO SPAN POTS, CG~PLETEO CALIRRATTION, NO PR09LEMS Fourrn ALL nATTERIES CLEANED, WATERED*

INSPECTED ANO TORQUED PER PROCEDURE, LEFT UK CHECKl'D CARO A'lO FOUND NO PR05LEtlS, LEFT OK REPLACED CR2 WITH GOOD SPARE AND TESTEO, FOUND NO PRO~LEMS RE-SECURED LOOSE GM TUBE AND CAL13RATED, LEFT OK RAN SIGNATURE ON FAN DISCHAR~E DAMPER ANO FOUND NO pqoBLEMS REPAIRED l~DICATOR/TR!P U~ll PEK ftPPLTC~BLE S~CTC~NS OF PKULtUUKt*

cw CALCARATEO PE~ PROCEnURE, LEFT OK Lt:r-1 PERF'OR:-IEO

~ AND 6 '10NTH 11\\i~PtLI 1u,._, r'-"

PROCEDURES, LF.FT OK

E:JUIPME:H 3-1501-lO CCSW PU!1P DISCH~'lGE CHcCK V..\\LVE 2-4A-41A LPRM APRM 4 U3 DIESEL GENERATOR HP(( MU 2301-10 VALVE 3-2301-14 HPCI MIN FLOW VALVE HPCI TEST RETURN 3-2301-10 VALVE ACAO/CAM PRESSURE TR..\\NSM!TTER 3-254L-12A 3-2541-128 A(AOICAM PRESSUR~ TRA~S"JTTER 3-MO-L50L-l'11I EQ RELATEO ROSEMOUNT TRANSMITlF.RS

  • 1 I\\ T \\J;l E nr.

Mf\\ !NTE~J.\\t-ICF C.JR'1F.f.T!VE

\\\\f( '.J6J9f, 7 P'U: VHIT I VF.

\\*IR IJ6461<>

VRF."JENT!Vt=

WR 0671.111 PREVPIT I yr:

"~ 0611910 P"f:vEr~rrvc::

WR f)(:,>19\\ !

PR[VF'H IVE 1*m Do<> Lt>3 P RF. V E ~* T I V C::

WR

!)l:iq317 P\\[l/fNT!Vi' w'<

'.l6".J~3n PREVENTIVE

\\H D7022P PR EVf 'Jl l '/ C:

~JR D706t;l CO\\r:'.".O<::~ IJ'"H T 3

)l\\Ff'.TV <'ELATr-r. '1A P1TE'iA'Kf LER OR* OUT.\\GF.

Mf\\LFUNCTIOrJ NIJ~r>Eq CA'JSE' P..C::SUL T t;/ A ill A rJI A NI:,.

~I/ A

  • \\JI A CO'lRF.CTIVE ACTTON CUT DOWN NEW CHECK VALVE TO PROPER OIYfNSIUNS ANO INSTALLED PFR PROCEDURE.

LEFT.OK COMF'LETEO PPIJC<::OtJRE FOR LPRM.AND FOUND

~a PR09LE~~. LrFT OK FUNCTIONALL~ TESTED "LL 20 CVLINOF.R THfRMOCOUPLES TO SELECTOR SWITCH POSITIONS. FOUNn NO PROALE~S

~RIDGED* MEGGERfOt REPAIRED A~O REINSTALLED

~OTOR, LEFT OK INSP~CTEO TO~QUE SWITCH, VERIFIED TORWU!': ANO LIMIT SETTPIGS PER PROCEDIJP.F.t U:FT OK P[KFOK~EO PROCEDURE AND TESTED BREAKER, FOUND NO PR03L~~S I'< ST ALL ED NEW lSOLATION VALVES, TU!'.I NG ANO TEST TAPS 'JN TR Ml SMIT TER St LEFT OK

!MST AL LEO N"='1' ISOLATION VAL VF.St TUl3!NG

!\\ ~~o TEST T l\\P) IJN Tfl.A~ISM I TTERSt LEFT OK REPLACED ALL GASKETS, WORM GEAR ANO HYPO ID G(AR, L r:F T OK ALL UJ ROSE~OUNT EO TRANSMITTERS COVERS CHECKED FOR TIGHTNESS PER PROCEDURE, NO PROALE~S FOUNO e

EOU I P~1E'!T UJ MOV L50L-216 UJ MOV l50l-38ll 3-263-20-B ATWS DIV 11 "8" PRESSUR[

INDICATOR 3-1501-440 30 CCSW PUMP 3-1551 Af.B LPCI SYSTEM FLOW TRANSMITTERS 3-1626 TORUS NARROW RANGE LEVEL TRANSMITTER 3-l62Z. Af:B TORUS PRESSURE T~ANSM!TTEqS 3-1501-58 Af.B LPCl FLOW TRANSMITTERS 3-1543 Af.'I LPCI HEAT EXCHANGER DIFFERlNTIAL PRESSURE TRANSMIT! IC;{

l25VDC GROUND

~It* T UP. E (JF "411. T'JTEIHNCE P".EV~'lT !Vf

'..IR 0707~3 PREVENTIVE HR 1)70705 UJR'H:CTrvr.

WR 1170883 CIJRRECT!Vc

  • .~R 0711':;2.

PR['IEIH I VF

JR n 7 l P, l '*

PR i:vr:r.n !Vi.:

"*iR 'H Pll '>

<nl.F.VE*'JT IVE wR IJ7le1 (;

f'P.fVFNT!VF.

WR ()71317 P'lEVEN T !VE'

~IR 'l 71 8 l 'l PR.EVEtJT!l/12 WP.

[17 2?.46

'.)Rf:",rJ<ON \\JIJI T 3 SAFETY RELATEO

~11\\NTE~ANCE LER OR OUT'-G" "H.JMf.IER N/A N/.fl iJ/,,

M/A

'I/ fl

"'JILFUNCT!Oll C*~S~

PE SULT CORRECTIVE ACTION REMOVED ANO INSTALLED MOTOR, LIMIT SWITCHES ANO TOROUE Sw!TCH FOR M.M, n~PT COMPLETED PROCEDURES, LEFT OK O!S(ON~FCTFD ANO RECIJNNECTEO ELECTRICAL C0"1PONEtlTS FlP. MMD OVEPl-11\\UL ON MOV, PF.RFOR~F~ ELECTRICAL l~SPECTION PER PRnCEOURF, LEFT OOK P.EPLACEO

  • ~* PRESSURE TRANSMITTE'l.

A~PL!FIER ANn C~LIRRATION Cl\\ROS.

CALiqFATEO PER P'l.OCEOURE, LEFT OK REPACKED PUMP TO ELl~INATE LEAKAGE, LEFT OK P.EPLACED TRANS~ITTERS, 0-RINGS ANO PERFORMED CALIORATJON PER PROCEDURE REPLl\\Cf'D TRANS~HTTFR 0-RING~ PER PROCEDURE, LEFT OK P£PLACED 0-RINGS ON TRANSMITTERS ANO PERFOP~[D PROCEDURE REPLACED 0-P.INGS ON TRANSMITTERS ANO PE'l.FORMED PROCEDURE REPLACED 0-RINGS ON TRA~SMITTERS A~D PERFOR~EO PROCEDURE REPA H'FIJ llAMAGr::D !NSULl\\TlOM TO CLEAR GROUND PPO'\\U:MS

t.

')*

I)'

EQUI PME'-H 3A CORE SPRAY TfST VALVF 3-l40Z-4A LPC! INJECTION V.\\LVf 1'~13-l501-22B

\\lh T Uf": E Uf'

~~ t.. I ;-1 T f: '*l A NC c

!"'F i:vt~l T t '1{7

,.~~ '>7?QOl l'f.:fVENTJV" i*,?

n 7 Z 8 l {1

!) q E-::,_, r. :-j u *; I T 1

S A F f: T Y

~ " I_ A Tf: 1.'

-~ A [ 'lT E" I\\:-.! C E tEP OR rJlJJA('.F' MU'-1'\\E~

'J/;..

"ALF'JhJCTil_lN (tJ.!J~:.:

0 r:';IJLT (ORRFCTIVE ACTION CHfCl<[:f'1 T0 1<0UE SW lTCH FClP. PROPER INSTALLATION, nALANCTNG AN" OPFN ANO CLQSE SETT!~GS PEK PPOCEDURES* LEFT QI<

INSPECTED TORUUED S~ITCH PER rR;J( F.DllRF, PERFOOMfD MOTOR OP':RATEO VALVc SIG~Al\\JRE PFR PROCEDURE, LEFT OK I I,

~

UNIQUE REPORTING REQUIREMENTS MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period February, 1988 are sununarized 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.

2 03/01/88 to 03/31/88 3

03/01/88 to 03/31/88 0763t Valves Actuated None None Description Actuations Conditions of Events

ODCM Reporting Reguirements March, 1988 None 0763t

03-01-88 to 03/31/88 0761t

SUMMARY

OF OPERATING EXPERIENCE DRESDEN UNIT TWO MARCH, 1988 Unit 2 entered the month on-line and operating in Economic Generation Control (EGC) as directed by the Load Dispatcher (LO) at 714 MWe.

The unit operated in EGC or at maximum feedwater flow, limited by turbine loading limitations due to 202 feedwater heater being isolated, as directed by the LO the entire month with a capacity factor of 85.93 and an availability of 100.03.

0

03-01-88 to 03/31/88 0761t

SUMMARY

OF OPERATING EXPERIENCE DRESDEN UNIT THREE MARCH, 1988 Unit 3 entered the month on-line and operating in EGC at 747 MWe as directed by the Load Dispatcher.

The unit operated in EGC or at maximum feedwater *flow,, lim:i ted by turbine loading limitations due to 3 Dl feedwater heater being isolated.

The unit operated continuously until 3-27-88 at 0158 hours0.00183 days <br />0.0439 hours <br />2.612434e-4 weeks <br />6.0119e-5 months <br />, when the generator was taken off-line to begin the unit's tenth refueling outage.

The reactor was brought sub-critical at 0223 hours0.00258 days <br />0.0619 hours <br />3.687169e-4 weeks <br />8.48515e-5 months <br /> of the same day.

The unit remained off-line the remainder of the month and is scheduled for start-up on the last weekend of June.

Capacity factor for the month was 75.963 and availability was 84.143.

\\'..

1.

I ;-

11:~ **

Common.Ith Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 615/942-2920 April 7, 1988 EDE LTR:

  1. 88-237 Director, Office of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, DC 20555 Attention:

Document Control Desk

Dear Sir:

Enclosed, please find Dresden Station's operating data fo~ the month of March, 1988.

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

Sincerely, Station r

Dresden Nuclear Power Station EDE: DCM: jmt Enclosure 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.A.

BWR Engineering Group Comptroller's Office PIP Coordinator INFO Records Center File/NRC Op. Data File/Numerical 0762t