ML20203A074

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Monthly Operating Repts for June 1986
ML20203A074
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 06/30/1986
From: Maxwell D, Scott D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
86-473, NUDOCS 8607170172
Download: ML20203A074 (13)
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OPERATING DATA REPORT i DOCKET NO. 050-237 DATE July 1, 1986 COMPLETED BY D. C. Manell I

TELEPHONE 815/942-2920 i

. OPERATING STATUS l NOTES 2 1. Unit Name: Dresden II j 2. Reporting Period: June, 1986 t

3 Licensed Thermal Power (MWt): 2 527 l 4. Nameplate Rating (Gross HWe): 828 5 Design Electrical Rating (Net MWe): 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

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) 'This Month Yr-to-Date Cumulative

11. Hours In Reporting Period 720 4,343 141,407 j 12. Number of Hours Reactor Was Critical 460.0 3.578.6 107.276.1 Reactor Reserve Shutdown Hours 0 0 0 13
14. Hours Generator On-Line 440.1 3.298.3 102.282.8
15 Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 1,019,321 7,711,937 209,345,576 17 Gross Electrical Energy Generated (MWH) 327,807 2,509,028 67,008,791
18. Net Electrical Energy Generated. (MWH) 310,175 2,388,410 63,324,524 19 Unit Service Factor 61.1 75.9 72.3
20. Unit Availability Factor 61.1 75.9 72.3
21. Unit Capacity Factor (Using MDC Net) 55.8 71.2 58.0 i
22. Unit Capacity Factor (Using DER Net) 54.3 69.3 56.4 1 23 Unit Forced Outage Rate 38.9 24.1 12.7 Shutdowns Scheduled Over Next 6 Months (Type, Da,te, and Duration of Each)-
24. '

I Refueline outane scheduled for December, 1986 thru February, 1987.

1 j 25. If Shut Down At End Of Report Period, Estimated Date of Startup: N/A Tb@

8607170172 060630 PDH ADOCK 00000237 g PDR g

OPERATING DA'A T REPORT DOCKET NO. 050-249 j DATE July 1, 1986 i

COMPLETED BY D. C. Shxwell  !

TELEPHONE 815/942-2920 OPERATING STATUS NOTES

l. Unit Name: Dresden III
2. Reporting Period: June, 1986 3 Licensed Thermal Power (MWt): 2.527
4. Nameplate Rating (Gross MWe): R99 5 Design Electrical Rating (Net MWe): 794
6. Maximum Dependable Capacity (Gross MWe): R19 7 Maximum Dependable Capacity (Net MWe): 773
8. If Changes Occur in Capacity Ratings (items 3 Through 7) Since Last Report, Give i Reasons:

N/A i

9 Power Level to Which Restricted, if Any (Net MWe): N/A l 10 Reasons For Restrictions, if Any: N/A I

This Month Yr-to-Date Cumulative ,

. 11. Hours in Reporting Period 720 4,373 130,992

12. Number of Hours Reactor Was Critical 0 0 96.596.7 13 Reactor Reserve Shutdown Hours 0 0 0
14. Hours Generator On-Line 0 0 89.773.3 15 Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 0 0 181.772.636 17 Gross Electrical Energy Generated (MWH) 0 0 58.839.233
18. Net Electrical Energy Generated.(MWH) -5.821 -30.686 55.695.608 j 19 Unit Service Factor 0 0 68.5 l 20. Unit Availability Factor 0 0 68.5 1 21. Unit Capacity Factor (Using MDC Net) 0 0 55.0 j 22. Unit Capacity Factor (Using DER Net) 0 0 53.5
23 Unit Forced Outage Rate 0 0 12.4
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each)

i In 9th refueling /RPR outage.

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l 25 If Shut Down At End Of Report Period, Estimated Date of Startup: July 26, 1986 1

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COMMONWEALTH EDISON COMPANY DRESDEN STATION MAXIMUM DAILY LOAD MONTH OF JUNE, 1986 HOUR MAXIMUM DAILY LOAD

DAY ENDING KW g

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3 4

i 5 1 6 7

8 9

10 11 12 2400 499,600' 13 0300 501,200

! 14 2300 686,200 15 2400 806,100 16 1300 815,500 1

, 17 1600 811,600 18 1100 818,800 l

! 19 1600 812,900 20 1000 814,400 21 1700 807,800 l 22 2400 806,000 23 1200 806,300 24 1500 807,400 I

25 0100 805,500 i

i 26 1700 808,500 1

4 27 1100 808,500 28 1300 798,500 f

29 1600 801,700 l

30 0100 797,800 l

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AVERAGE DAILY UNIT POWER LEVEL i DOCKET NO. 050-237 f UNIT II DATE July 1, 1986 i

i COMPLETED BY D. C. Maxwell I. TELEPHONE 815/942-2920 4

MONTH- June, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL j (MWe-Net) (MWe-Net) 4 0 17 780 j 1

$ 2 0 18 775 l

l; 3 0 19 809 1 4 0 20 784 i

j 5 0 21 786

! 6 0 22 763

7 0 23 764 1

8 0 24 779 l

I 9 0 25 671 i

10 0 26 780-11 0 27 743

.; 12 82 28 766 1

j 13 365 29 735 14 505 30 741 j 15 705 31 ---

! l6 761 i

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j AVERAGE DAILY UNIT POWER LEVEL 4 DOCKET NO. 0s0-249 UNIT III DATE July 1, 1986 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 MONTH June, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

(MWe-Net) (MWe-Net) 1 0 17 0 2

2 0 18 0 3 0 19 0 4 0 20 0

! 5 0 21 0 1

6 0 22 0 1

l 7 0 23 0

i

8 0 24 0 9 0 25 o i

10 0 26 0 11 0 27 0 12 0 28 0 i 13 0 29 0

! 14 0 30 0 9

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15 0 31 ---

16 0 l

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,e,g s -- - -,-e +v- m , ,- --,-,r-mr. ---,,.m,--. . . . , . - . . . . . , . ,,-----w~n,e -we,w m a.-_-,----n-,,4.mn--e-.,,,.--.-,s.,---r -- - >,---r-o-,-r

DOCKET NO. 050-237 - -

UNIT NAME II - -

' UNIT SHUTDOWNS AND POWER REDUCTIONS DATE July 1, 1986 '

COMPLETED BY D. C. Maxwell TELEPHONE (815) 942-2920 REPORT HONTH June, 1986 i 1

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 t

5 36-05-18 F 279:57 H 1 Manually shutdown for drywell (280.0) snubber inspections and mainte-nance.

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1 2 3 4 F: Forced Reason:

Method:

S: Scheduled A-Equipment Failure (Explain) Exhibit G-Instructions for 1-Manual Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee i

C-Refueling 3-Automatic Scram Event Report (

1 D-Regulatory Restriction ) File 4-Other (Explain) (NUREG-0161)

E-Operator Training & License Examination .

F-Administrative .

i G-Operational Error H-Other (Explain)

_ . . , _ . _ _ _ . . _ _ _ _ - - _ - - _ _ _ _ _ - . - . _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ . . . _ ~

DOCKET NO. 050-249 , -

UNIT NAME III - -

1 UNIT SHUTDOWNS AND POWER REDUCTIONS l

DATE July 1, 1986 )

COMPLETED BY D. C. Maxwell TELEPHONE (815) 942-2920 REPORT MONTH June, 1986

METHOD OF LICENSEE CAUSE & CORRECTIVE NO. DATE TYPEI DURATION REASON 2 SHUTTING EVENT SYSTEM COMPONENT ACTION TO (HOURS) DOWN REACTOR 3 REPORT F CODE 4 CODES PREVENT RECURRENCE

} .

6 85-10-23 S 720:00 C 1 -- -- --

Off-line manually to 9th Refueling / Recirculation Pipe Replacement Outage.

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1 1 2 3 4.

j F: Forced Reason:

Method: Exhibit G-Instructions for S: Scheduled A-Equipment Failure (Explain) 1-Manual Preparation of Data 3 B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee

, C-Refueling 3-Automatic Scram Event Report (

{ D-Regulatory Restriction ) File 4-Other (Explain) (NUREG-0161) l' E-Operator Training & License Examination .

F-Administrative

' G-Operational Error j H-Other (Explain) i

. . - . - . _ . . . _ _ _ . . . . - _ _ _ m _._._._____.-.....m. _ . . _ . - . . .

. . _ . _ . . . . _ _._ _m.m. . _ . . . . . . _ . . _ _ _ . ..__._m.. . _ . _ . . . _ . . . . ._ . ~ . _ . _ - . . . ,

DMf50 tin tlNIT f N

$&Ftiv MfLAIED mal %: .t j ,

4AIURf Of LFS OR OuiAGE MALFUNCTION - .

60u lP88EN T M A I Ni t N AT4Lt- NU%Fk CAUSE SkSULT 00i42 EC T I V E AC T Inte P5-2-G%% s 130 COkdFCflVi N/A = = = = = = = = -------- C ALIBS Af t0 Pdf 5506tti SW I T CH ,'t k P L Att ;) '

CQ3 @*2 514-078 kR 091237 PaE55URE GAUGE . .

OPL 2-1540-5A CuaRELTIVL N/A --------- -- == REPL ACE 0 A AD AMPLit ita nunuo awn

".*.* LPCI/CC5W OP INDICAIO4 WR 0%t784 CALtdRATED TRAN5egtgTER 880 2-1301-2 C UR A F L T I V'. N/A ~~~--==-- --------- INST ALLED NFd P ALK INts, wM OS)T)4 9

t 75-2-23FOA-0, T57-2 Sit 4-0, PME v6' t4T IVL N/A - - - - - - - - --------- PE RFORMFD t .J. I NS PF C T I'IN I T52-2372A-Oe MPL1 AMIA ItMP. WR OS4549 I SWITCens ,

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DdE50EN UNIi 3 SCFtT V stFLATFU Ca t ;E ']j ,

f4ATUMf Or Li tt UR OJTCGt MALFUNCTION *

  • E0utPmLNi MAINTECANCE NUMoE R CauSE CL5uti CD:2ECrivF ALT 10t4 P53- U t-30 A,nott.0 PetVtt4TATIVL N/A - - - --------- INST ALLLO NEW CALIBR AIdo SWITCHE 5 Ate)

C5L Low PaE55 SwlTCHES WR 049699 COMPLFTED THE AS LLFT.CAllJRATItP4 , ,

L tS 3-233-%94 cur 4fLitVt N/A --------- - - - - - - - REaulLi YAnWAY,HyuMU Test SUCCE55Fut.

CE ACTom HgGH LEvFL Tuds. Inte. Wu uspng9 VFatF IEn 5thstNG L INL5 pu A t*4(n af RILL tn WITH WATER L t5 3-233-%9tn C ua d F CI IVt. N/A --------- --------- MEDUILI VAMWAY,HYDun Is5 f f u $U6C E5 sFJLL. 3 CtACTOR HIGH LFVFL Tunn. IMIP W4 u49620 WFR tFIED 5tNSING L INc 5 ng A IMen,Rt F g t LF.D WITH WATER LPR::t CONNtCTOR 5 cur 4fLTIVL N/ A --------- - - - - - - - - INST ALLED LIMO CU'4N5 C104 5 AND dEPL Acid WM 0504u0 THE GE C ONNI CTUR 5 itC-3-ItS4 CORMELT!VE N/A - - - - - - - - - - - - - - - - REPL ACEO CONTROLLER AN') C ALIdR A T ED PiR U-3 SSLC Temn TEMP CONTMOLE R WA 051432 PROCEDURE TIC-3-stS4 Cua nt C T I VE N/A - - - - - - - - - - - - - - CLE ANED OIRT V SF. T PUI N T PUSH bu T T OP4 SeLC Tama TEMP CONTA0LLER W4 u%3846 CONTACTS.

ItSTIuseENT L imE S en F v t es T A T IVt N/A --- - --

eACKFILLED INSTRUMtNT Lirefs PRIud IO wa 093%T4 START-UP AFTER REFUEL.

L53-302-824,C F.C,J KL4,0 PREVFNTIVE N/A - - - - - - - - ~ ~ - - - - RETDAOufD ALL LEvFL $WITCHLS.

SCCA8* l' ISCH WOLumE LEVEL SW. we 09362%

_- m----- -~.-- -: -- _ . - - - ~ ~ - - - - - .

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PMESDEN tiNI T 2/ *

$ a F t. T V WFt,AIFO M2&N E D .

s. A l t pu t ile Ltd 04 OUTAGF M AL F ut4Cf 8 04 toulPMtNI MalNf LN4%> NuM4FH CauSE stEtuti Ctinatt tI vf ACTION -

, CBN-0 Flow CONTMOL TRIP COHdfLfivi N/A --------- - - - ~ ~ - - REPL Act0 OLFECitW UAL 09. A4P.

' CE7ESENCE Unit WA J44MS% PART O

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-'- ~ ~r- ~ ~ - - - - ~ ~ - - ~ - - - - - - - - - - - -- - -

. UNIQUE REPORTING REQUIREMENTS MAIN STEAM RELIEF VALVE OPERATIONS

Relief valve operations during the reporting period of June, 1986 are summarized in the following table. The table includes information as to which relief valve was actuated, how it was actuated, and the circum-a stances resulting in its actuation.

f Valves Description Unit Reporting Period Actuated Actuations Conditions of Events i

i 2 06-01-86 to 06-30-86 2 3 Rx critical Performed DOS-250-5 and mode on electromatic s j switch in 2-203-3B and 2-203-3D.

i run Valves manually oper-l ated at low pressure j and responded correctly.

2 2-203-3D valve manually operated at rated pres-l sure and responded correctly.

Tests performed to satisfy operability requirements per W.R.'s D49128, D54405, D54701 l)- and D54795.

t

3 06-01-86 to 06-30-86 None i

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SUMMARY

OF OPERATING EXPERIENCE i

UNIT 2 JUNE, 1986 ,

06-01-86 to 06-09-86 Unit 2 was off-line and in the shutdown mode for i snubber inspections and maintenance.

f 06-10-86 to 06-30-86 The reactor was brought critical at 0801 hours0.00927 days <br />0.223 hours <br />0.00132 weeks <br />3.047805e-4 months <br /> and the turbine was synchronized to the system 6-12-86

! at 1557 hours0.018 days <br />0.433 hours <br />0.00257 weeks <br />5.924385e-4 months <br /> and operated steadily increasing load to maximum core flow (except for normal weekend surveillances) through the remainder of the month l with an availability of 61.12% and a capacity factor

! of 54.59%.

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SUMMARY

OF OPERATING EXPF.kIENCE UNIT THREE f

JUNE, 1986 i

06-01-86 to 06-30-86 Refueling outage activities continued throughout the entire period. The unit is presently scheduled to start up in July, 1986. Major work includes:

f

- Normal pump (s) and valve (s) maintenance

- ISl inspections

- LLRT

.ILRT preparations

- Fuel loading

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Commonwealth Edison Dresden Nu;leir Power St tion O Morris,!!Iinois 60450 R.R. #1 Telephone 815/942-2920 July 1, 1986 DJS LTR: 86-473 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 for the month of June, 1986. This information is supplied to your office per the instructions set forth in Regulatory Guide 1.16.

Sincerely, d.

, c

,'y D. J. Scott Station Manager Dresden Nuclear Power Station DJS:DCM:hjb l Enclosure l l

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. 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 IE.a.Y V'

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