Text

Monthly Operating Repts for Oct 1986
	ML20213H055
Person / Time
Site:	Dresden
Issue date:	10/31/1986
From:	Eenigenburg E, Maxwell D; COMMONWEALTH EDISON CO.
To:	;
References
	86-153, NUDOCS 8611190057
	Download: ML20213H055 (27)
	v • d • e

_ __

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OPERATING DATA REPORT I

DOCKET NO. 050-237 DATE November.3, 1986 COMPLETED BY D. C. Manell TELEPHONE 815/942-2920 OPERATING STATUS NOTES 1.

Unit Name:

Dresden II 2.

Reporting Period:

October, 1986 3

Licensed Thermal Power (MWt):

2 527 4.

Nameplate Rating (Gross MWe):

828 5

Design Electrical Rating (Net NWe):

794 6.

Maximum Dependable Capacity (Gross MWe): 812 7

Maximum Dependable Capacity (Net MWe):

772 8.

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

N/A 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 745 7.296 144.360 l

12.

Number of Hours Reactor Was Critical 745.0 6.421.0 110.118.5 13 Reactor Reserve Shutdown Hours 0

0 0

14.

Hours Generator On-Line 745.0 6.082.1 105.066.6 15 Unit Reserve Shutdown Hours 0

0 0

16.

Gross Thermal Energy Generated (MWH) 1.604.593 13.921.183 215.554.877 17 Gross Electrical Energy Generated (MWH) 512.952 4.480.993 68.980.756 18.

Net Electrical Energy Generated.(MWH) 486.147 4.257.782 65.141.846 19 Unit Service Factor 100.0 83.4 77.8 20.

Unit Availability Factor 100.0 83.4 77.8 21.

Unit Capacity Factor (Using MDC Net) 84.5 75.6 58.5 22.

Unit Capacity Factor (Using DER Net) 82.2 73.5 56.9 23 Unit Forced Outage Rate 0.0 9.0 12.1 24.

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

Refueling outage scheduled for December, 1986 through February. 1987.

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

N/A 8611190057 861031

\\

PDR ADOCK 05000237 R

PDR

OPERATING DATA REPORT DOCKET NO. 050-249 DATE November 3,1986 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 OPERATING STATUS NOTES 1.

Unit Name: Dresden III 2.

Reporting Period:

October, 1986 3

Licensed Thermal Power (MWt):

2 527 4.

Nameplate Rating (Gross MWe):

R2s 5

Design Electrical Rating (Net MWe): 794 6.

Maximum Dependable Capacity (Gross MWe): R12 7

Maximum Dependable Capacity (Net MWe):

773 8.

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

N/A 9

Power Lev &1 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 745 7.296 133,945 12.

Number of Hours Reactor Was Critical 682.0 1.442.0 98.038.8 13 Reactor Reserve Shutdown Hours 0

0 0

14.

Hours Generator On-Line 672.0 1.207.0 91.000.3 15 Unit Reserve Shutdown Hours 0

0 0

16.

Gross Thermal Energy Generated (MWH) 1.488.124 2.304.418 184.077.054 17 Gross Electrical Energy Generated (MWH) 467.567 704.515 59.543.748 18.

Net Electrical Energy Generated.(MWH) 443.345 621.675 56.347.969 19 Unit Service Factor 90.2 16.5 67.9 20.

Unit Availability Factor 90.2 16.5 67.9 21.

Unit Capacity Factor (Using MDC Net) 77.0 11.0 54.4 l

22.

Unit Capacity Factor (Using DER Net) 74.9 10.7 53.0 l

23 Unit Forced Outage Rate 9.8 17.1 12.4 24.

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

N/A I

l 25 If Shut Down At End Of Report Period, Estimated Date of Startup:

N/A

COMMONWEALTH EDISON COMPANY DRESDEM STATION MAXIMUM DAILY LOAD MONTH OF OCTOBER, 1986 HOUR MAXIMUM DAIL'l LOAD DAY ENDING KW 1

1500 1,211,300 2

1700 1,291,900 3

0300 1,249,300 4

0400 1,213,400 5

1800 1,206,000 6

1100 1,316,700 7

2,400 1,421,700 8

1500 1,455,700 9

2000 1,443,500 10 0900 1,476,900 11 2200 1,499,000 12 2100 1,503,100 13 1000 1,506,900 14 0900 1,481,900 15 0400 706,200 16 0300 701,800 17 2300 1,232,500 18 2400 1,380,700 19 2200 1,456,000 20 1200 1,468,500 21 1300 1,482,700 22 0600 1,480,500 23 0100 1,450,700 24 2000 1,467,800 25 1300 1,469,500 26 0800 1,469,900 27 0900 1,464,200 28 2400 1,463,200 29 0300 1,463,000 30 1200 1,460,400 31 0900 1,459,600

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

050-237 UNIT II l

DATE November 3, 1986 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 Ext. 489 MONTH OCTOBER, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 680 17 677 2

688 18 659 3

676 19 656 4

676 20 657 5

581 21 640 6

683 22 634 7

691 23 638 8

680 24 644 9

685 25 595 10 685 26 621 637 1]

677 27 662 12 644 28 13 29 63'o 676 14 656 30 622 672 15 3i 623 665 16 l

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

050-249 UNIT III DATE November 3, 1986 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 Ext. 489 MONTH OCTOBER, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 351 17 244 2

458 18 559 3

494 19 709 4

449 20 763 5

485 21 759 6

551 22 764 7

566 23 789 8

688 24 781 9

675 25 775 10 714 26 693 772 1j 734 27 i

755 28 758 12 757 773 13 29 247 14 30 765 1

0 15 31 769 0

16 e

l l

L

s DOCKET NO. 050-237 UNIT NAME 11 UNIT SHUTDOWNS AND POWER REDUCTIONS DATE November 3, 1986 COMPLETED BY D. C. Maxwell TELEPHONE (815) 942-2920 REPORT MONTH OCTOBER, 1986 i

METHOD OF LICENSEE CAUSE & CORRECTIVE NO.

DATE TYPEl DURATION REASON 2 SHUTTING EVENT SYSTEM COMPONFNT ACTION TO (HOURS)

DOWN REACTOR 3 REPORT F CODE 4 CODES PREVENT RECURRENCE j

None J

l 4

5 j

1 2

3 F:

Forced Reason:

4 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 (

) File D-Regulatory Restriction 4-Other (Explain)

(NUREG-0161) i E-Operator Training & License Examination

(

F-Administrative l

1 G-Operational Error i

H-Other (Explain)

1 DOCKET NO. 050-249 UNIT NAME Ill UNIT SHUTDOWNS AND POWER REDUCTIONS DATE November 3, 1986 COMPLETED BY D. C. Maxwell TELEPIIONE (815) 942-2920 REPORT MONTH OCTOBER, 1986 l

METHOD OF LICENSEE CAUSE & CORRECTIVE NO.

DATE TYPEl DURATION REASON 2 SHUTTING EVENT SYSTEM COMPONENT ACTION TO (HOURS)

DOWN REACTOR 3 REPORT F CODE 4 CODES PREVENT RECURRENCE 1

5 86-10-17 F

72:58 G

3 86-017-0 Contractor bumped MSIV instru-(73.0) ment rack while cleaning /

decontaminating the rack.

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3 F: Forced Reason:

4 Method:

Exhibit G-Instructions for S:

Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test Preparation of Data 2-Manual Scram Entry Sheets for Licensee C-Refueling 3--Automatic Scram Event Report (

) File D-Regulatory Restriction 4-Other (Explain)

(NUREG-0161)

E-Operator Training & License Examination F-Administrative i'

i G-Operational Error H-Other (Explain)

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"/t T A ?r u C O N* tC TI ON S F F g unAK INS T R UC T Idh.

WR 04 d 7 '7 %

LFFT OK e

8 1

I

4 I

i-

[,

N E S9e: UN!T 3 SAFETf McL A TFu e4 41ffirN ANC c j

N41URE OF LER Ca f'UT AGF M A L FUMC T IOr4 EQUIPMENT "Att4TENAuti hu=7 4 f t.US L RESutT C04 RECT!bE ACTinN 3-140t-A P d t V E'47 I V E N/A T4Pra 305 AND M0T0k CquNECT!aa!S PE4 C03E SPAAV PUMP

=4 040796 WOM I NS T R UC i t 0 S, LlFT OK i

l T4PFu ;40TCk LEADS AN0 ouS C0%NFCTIJNS I

3-15028 PR E VFt,T Iv L

/ A LPCI PUMP WR D4sT9T AT Anv BUS PER W O4 K INSTRUCTIONS, LFFT OK 3-1502-4 PREdFNTIVE N/A TAP (D LPCI PUMP W T OR AND aWITCH C2A4 f

LPCI PUMP W< 040T4R CONNtCT:GNS ped wakK !%STRUCT!CN5. LECT 0%

RELIEF VALVE BETWEE'4 3-1601-57.

COR4FCT!v6

i/ s deMovro VALVE, CLEANLO PARTS 8ND ?eiT 58,59 WR 048A24 PRESSURE, RFINSTALLEO VALVE. LEFT 0K 4

3-1201-3 CORRECTIV6

'l/ 4 O! S4SSE'4LLED liv !TLR JUE. RtaSSEMateo REACTOR CLFAN-UP AUA PU'4P wk 044914 USLFJ NF4 uASKETS. CJAD RINOS, 4 '.P SUCTION VALVE 23 Moo! LUX GREASE, LCFT OK 3-1402-24A PREVENTIVE N/4 DISCONNECTED ANO RLCUNNECTED LE ADS FJ4 MOV WR v4103T E.J.

MAINTENANCE, NOV 1402-24S Pd F V E N T I Vt.

l/ 7 O! SCGNNECT ED A ND RECON.4ECTE D MOTJR LL 405 Wd 049039 FDA E.Q. MAINTENv4CE M' V 1492-25A Pd E V E*4T I V E rs/3 OI SC ONNECT 4.0 A40 P ECuNPCTED V ALV' 4'O J

WR 94903o SET LIMITS FOR E.Q. MAINTENA4CL DI ST JN'4ECTLO AN9 R ECON'4F CTE 0 Mijf GR LLA05 880V 1402-25B PdEVFNTtvE

'l/ A WA 04'70*0 ANa iET LIMITS F OP. c.Q.

M A t *4 TE N A NC t MOV 1402-384 PAfvFNTIVL r./ A JI SC ONt4ECT ED AND R ECON *JE L TE D MOT GR Lc4DS WR 04704L FOR L.Q.

MAINTENANCE e

V N

f #

b-j I

U s E S D.r1 t r. f i 3 5ACiff di L A T F,)

9AINTfNAluCL P.LTUar of L t r4,A FjiAc;

AiFJNCT10,4 E QU I P'4 E*: T

AI NT EN ANC'

"; s" %. s cad 5E

' t 5UL T C04RuCT!vE aCTIc4 MOV 1501-11A ptEvFNTIVt

iA 015C WJ' C Tt7 FNO EtC~3N r_Cyc3

..a f GD

'44 04'so41

1. t A 0 5 F '; 4 t.0.

' AI ?.T E N 4 *;C F MOV 1501-113 PaF/FNTIVc N/4 4--------

J!iC'J' Nrcye o no a(wa arCTED LLA0% COR wa 0470%4 t...

"AINTtNANCE l

i t;UV 1501-218 90 VINTIVe N/a DISCuT.TCTED AC e t A. J C T L D *' J T JR L t. 4 05 wd 049 % 6 F ~1R c. J. "AINTtNAwCE l

1-1501-219 A 94EVFNTIVE

/ A a l sF UT4 F C T 6 0 S t.7 RLCdNN'CT:0 S* J V fra M0V WR J49049 t.G.

MAINTtNANCE

0V 15 01-2 9 B PRE vet 4T iv E

"/'

O ! aC N.4f CT E S A147 RLCaYdCTLO sov rua F.O Wa 04dO57 M A I.N T F N A NC L. RESLT LI'q!Ts AN3 Cattnca l

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f4AINTENANCC r

MOV 1501-322 PREVFNTIVE

/4 utSCJNNCCTE0 A P.3 WECJN #CTLO 'tu r ce L t. A d 5 WR 349052 FOR t'. a. M A I,4 T C % N L E I

is 5 TM3 PRFVsNTIVE

/ A A1JUSToo THEdr*05 T % T TO TMIP CPL 4 AT

'd' LPCI ROOM COOLFR W4 349131 CO AR CC T R E wu !R E*E*J T S, etE PL ACE 9 f

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Co. talc T 5FTTING5. Lffi rK 3-2 20-1 LIMI T08N9E CORRfCTIVE

./ A RE M'Iv F 0 AND INSTALLED LIMITORour u!TH W4 D4977)

'if a ModILUE GP E P 'J 1

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?

.s n*EancN U'.!T 3 SAF41f HELATE0 MAINTFNANCE NATtrRE Or led OR OUTAGL MALFUNCTION EQUIP"E'4T MAINT4NA'.Cc NU"St4 CAuSe RESULT CCac;cTivE A C T 10s.

}

f LIFTED LEADS ANS LJGGEJ pea WCH(

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MJ-3-1501-228 PREVENTIVE

/a WA 050177 C04EM, LeFT Ok j

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PIPE WELDS ON C09E SPRAY AND PREVENT!Vt N/A INTF #.r59 ENC E S RE emEU, 53 w!LDi MSIP'O ISO CONDENSER W4 v50404 ANU UT I 45PECTED, REINST ALLEO AND TESTc]

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't/ A REPLAcc0 GRf456 IN GEAREJ LI:4ti SS: ITCH j

W4 0514al ANJ 4E PL ACL'1 I NT EPN AL d! KING, LEff OK Mdv 1402-24t3 PRtW(NTIVE N/A kEPLACt0 GRFA5e IN GEARED LIMIT SNITCH WR D51596 ANO REPL ACFD INTERNAL WIRING, LEFT 05 REPLAEEn THE OLION "dEAKea, LEFT 74 403-2301-10 V4LVF 9dEAWh*

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':/A krPLACLD I iT: UNAL W!4INO A43 aWfASZ WR 0516ss IN ctAwES Liw!T Sw!TCH 3-1513 PxFvfNTIVE N/ \\

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lu'1 1402-44 PRFVFNTIVE

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.PC I ROOM COOLFR F A '4 esa D53715 FCUNJ E V E R Y T H I,r.

TO DE 04 3 LPCI ROOM C OOLF R *iC C H-1 PWE.ENTIVE N/t IN;T r.LLf D 0 REMnVFD C04ER OF LPCI

.0*P Cl WR D%3953 COOL L R F un INS 9ECTION, Lect OK CC 39-1 COMP F1 P4Lif'4TIVE

'./ A ME CWEJ AND INST AL LFO COVfd 3F LPCI LPCI ROO" C00Lra wR 353a54 Cnutto fdR INSPLCT!qN, LEFT

]<

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Lin1TORWUt OPERATOP

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LA4 PED CUT v!kES FOR NRC INSPFCTION,

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W4 053447 LFFT 04 4E 40VEJ ON'JSED C Al*L E F AN C A 8t E TRAY 903-33 EQUI PMENT C 4 4I'4F T oRFVENTIVt

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'./ A I'45T ALLED CORR EC T C A 3Lt TAG PER aOKK I NB 0s'. R9 ISOLAft0N VAL 4E WR 054704 INSTRUCT IO 45, FASTENEO vi! TH PLASTIC TV-WMAPS,itFT On AFMOvFJ AND INSTALLED MOT 04 LFAni DOX 3-1401-A PAEiENTIVL N/A "A" COTE SPRAY PflMP MOTdo WR 0544L7 COVE,1 F0n N'C I N SP L C T ! u?',

LEFT 04 N-2M-H PRFVENTIVE N/A OPtNtD AND CLOSED PENTTRAY10N F04 NRC D.W. PENE TR A T IOre WR 054418 INSPECT!UN, LEFT CK i

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9

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Unit 3 SAFETY k? LATED NAINTENtNCE 4ATUdE OF LE4 09 n'J T A Ci"

>ALFoNCTION E QUI P%'1 T

- A !!4T EN A*P.E

' u"., E 4 CAJSt 9tSULT COM _CTIVE ACTIOa X-205-9 pd E VEi4 T IV E N/A OPENED AND CLC5FG PE;4E TR AT10 4 FCd nEC dew. PENETRATIDN WA J54417 IN5?:CTION, LEF' OK 1-1501-328 MOV pd F d E!4 T IV t

/A nE CVEJ ANG !!!ST ALLEJ L! SIT 0CuF EJVE?

Wd J54438 FT4 NRC INSPECTIGN,-LFFT OK MOV 1402-183 PdEVryT3Vt n/a nipa1950 yaron pep PR9CFOUAE, LEFT 04 Wd 054500 ft.O. 3-1402-4d VALVE

4FVENTIVE

't/ A A0ff>TED L14tTS PFK PROCEDORE, TI0hitNED 4

=A J5,5??

LOCSE SCREd ON DPEN CIRCUTT OVERLCAD A(LAf, LEFT G<

9.0 3-1402-256 P d E v t ;4 T I V h

?/ A C9ECAEJ T O A", J E AN' LIMIT S ed! T C H 3rTTINGS wt 054624 PER PR0C EOURE, ALL LOO 45 GJ"3, LtFT J<

3-1402-254 PREVFNTIVE r./ s CHECnF0 TOROUS ANS LIMIT Sd!!CH SE T T I' jus CORE 5pu f INJECTION VtLVE tid D54644 PER PROCE0uPi, A LL LOOA50 uo00, LEFT OK 1430-12TA PREVENT 1WE N/7 ADJUSTED RELAY CO*lfACTS, LEFT 0x 4G4 R E L A Y F OR CORESPoAYi wd 054790

do 54-31 PRf vEr4T IVE N/a TISHTENEO C AP SEREa AN9 STJPPED AIA LEAK Wa 054117 LIMITS CHECKED OUT OK, LtFT OK

.V3-1402-289 PREVENTIvt

./ t THIS VAlvr DID NOT LEAN THdGJGH, 8 LORE SPRAY DI%L*4 dELitF Wd 0%512T PR J 'LE M mAh O'l CORE SPdAf PUMP DISCH STOP CHCCK VALVE, REFFR TO dd.15S?14

.-24198 PdEVraTIVE

'1/ A REPAIDED CADLF CONNECTOR, LEFT OK MYsdELL

'B' HI R4D MON!in4 WA 055219

-lIGH VOLTAGE CABLE e

e

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t H E SM' U"!T 3 SArtif RF L ticis ** A IN TE NA 4f c NATUAr of Lia Oc ouTA",!

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? UV A LAdst es%Utf CCit a t C T ! v E ACT IN 3-1530-1T6 EAKI C UP R EC T I Vc

!./ a grgtActe attAy, p:or g a.4 r ; rR ut t C E. L9T

-t/2 SEC TIME DELAY kEliv dd 9551u6 Ok VENT RFIURN 3-8501-5

Pkt/E4TIVu

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~~LPCI SYSTEM 11 H"AT E s CH A ur.E' WR J5556 SHJPTFO T0vFTHth AT LIMIT 0A0U5 RYPf,55 VALVE CP9ARTutNT PER PGC E D'J R L. LEri Uk e~~

~~REACTOR PR O TE C T i eN SY5ftw PkfVTNTIvd~~

~~':/ t I'4,TALLFO 1 1/2 INCH C J'1dO I T CLVt?.~~

~~CONOUIT RUN Ww J55604 IN3DECTED OK 903-3 ftRMINAL BLOCK PRE /FNTIVE P/4 RE Pt ACt a B AD TERMINAL BLQCK PLR~~

~~'1 wk J55e4, TRAvetcs, tcFT o<~~

~~3-1301-4 P R F V F N T I V i.~~

~~4/A TIGuT?'.00 PACKING GLA'13. iiG M%E LEAAS, j~~

~~15')L AT ION VALVE ed R 056050 LFFT nK I~~

~~i TU3US PUMP 00WN AND C L T A T11 N r.~~

~~P dE Vr t4T IV L~~

~~/A 104U5 ANJ SilC T K ! O*f HL4JfR CLE44E0 0F WR d5cl00 GDIT.~~
r4 L I ND F L A V.E RF I'13T ALLE D 091%
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WR 156230 HFMdVFD BAO SNU3DrR A';0 4FPLACtD *tlTri NEd J' E. LLFT CK 3-14C2-26A CUPdfLTIVL
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UNIQUE REPORTING REQUIREMENTS MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period of October, 1986 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.
Valves Description Unit Reporting Period Actuated Actuations Conditions of Events 2
10-01-86 to 10-31-86 None 3
10-01-86 to 10-13-86 None 10-14-86 3-203-3B 1
Rx in Run Rx scram at 0815 Electro-at 2521 hours0.0292 days 0.7 hours 0.00417 weeks 9.592405e-4 months when contrac-matic MWt tor cleaning MSL Relief flow sensing line Valve bumped instrument rack 10-15-86 to 10-31-86 None 1
rv
4
~~SUMMARY~~
OF OPERATING EXPERIENCE UNIT TWO OCTOBER, 1986 10-01-86 to 10-31-86 Unit 2 entered the month operating at a power level of 715 MWe and operated the entire month at a maxi-mum core flow (coastdown).
Capacity factor for the month was 82.56% and availability was 100%.
he_.
R.].
~~SUMMARY~~
OF OPERATING EXPERIENCE UNIT THREE OCTOBER, 1986 10-01-86 to 10-15-86 Unit 3 entered the month operating at a power level of 210 MWe and steadily increased load (except for normal weekend surveillances) until 0815 hours0.00943 days 0.226 hours 0.00135 weeks 3.101075e-4 months of October 14, when an automatic turbine trip and reac-tor scram occurred as a contractor who was cleaning /
decontaminating a MSIV instrument rack, bumped the rack causing the event.
After the scram occurred the Rx pressure was being manually controlled by the isolation condenser system.
However, as Rx pressure increased 3B electromatic relief valve lif ted at 1080 psig due to low setpoint drift. The setpoint was re-calibrated prior to start-up routines.
10-16-86 to 10-31-86 The reactor was made critical October 16 at 2315 hours0.0268 days 0.643 hours 0.00383 weeks 8.808575e-4 months and the turbine was brought on-line October 17th at 0913 hours0.0106 days 0.254 hours 0.00151 weeks 3.473965e-4 months and operated the remainder of the month, reaching a power level of 798 MWe with a capacity factor of 75.43% and an availability of 90.21%.
Commonwealth Edison Dresden Nucle's Power Sttion R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 November 3, 1986 EDE LTR: 86-153 Director, Of fice of Ir.spection and Enforcement United States Nuclear Regulatory Commission Washington, DC 20555 Attention:
Document Control Desk
~~Dear Sir:~~
Enclosed, please find Dresden Station's operating data for the month of October, 1986. This information is supplied to your office per the instructions set forth in Regulatory Guide 1.16.
Sincerely,
&c.# 1 e
3 E. D. Eenigen rg Station Ma'nNger Dresden Nuclear Power Station EDE:DCM:hjb 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 Nuclear Fuel Services Manager Nuc. Sta. Div. Vice Pres.
Manager, Tech. Serv. Nuc. Sta.
Tech Staff A.E. (2)
On-Site NRC Inspector Sta. Nuc. Eng. Dept.
Sta. Q.A. Dept.
Comptroller's Office PIP Coordinator INPO Records Center File /NRC Op. Data File / Numerical f
y

ML20213H055

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