ML20211G053

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Monthly Operating Repts for Jan 1987
ML20211G053
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 01/31/1987
From: Eenigenburg E, Maxwell D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
87-088, 87-88, NUDOCS 8702250262
Download: ML20211G053 (32)


Text

- __ - __-__-_

a OPERATING DATA REPORT T

DOCKET NO. 050-237 DATE February 1, 1987 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 OPERATING STATUS NOTES 1.

Unit Name:

Dresden II 2.

Reporting Period:

January, 19d7 3

Licensed Thermal Power (MWt):

2 !;27 4.

hameplate Rating (Gross MWe):

~ 828 l

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 (Items 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 744 744 146.568 12.

Number of Hours Reactor Was Critical 0

0 110.807.6 13 Reactor Reserve Shutdown Hours 0

0 0

14.

Hours Generator On-Line 0

0 105.747.9 15 Unit Reserve Shutdown Hours 0

0 0

16.

Gross Thermal Energy Generated (MWH) 0 0

216,872,082 17 Gross Electrical Energy Generated (MWH) 0 0

69,402,665 18.

Net Electrical Energy Generated (MWH)

-4,131

-4.131 65.580.522 19 Unit Service Factor 0

0 72.1 20.

Unit Availability Factor 0

0 72.1 21.

Unit Capacity Factor (Using MDC Net) 0 0

58.0 22.

Unit Capacity Factor (Using DER Net) 0 0

56.4 23 Unit Forced Outage Rate 0

0 12.1 24.

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

In 10th refueling outage.

25 If Shut Down At End Of Report Period, Estimated Date of Startup: Mid-March, 1987 b

B702250262 870131 T

PDR ADOCK 05000237 1

R PDR

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~

OPERATING DATA REPORT DOCKET NO. 050-249 DATE February 2, 1987 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 OPERATING STATUS NOTES 1.

-Unit Name: Dresden III 2.

Reporting Pe'riod:

January, 1987 3

Licensed Thermal Power (MWt):

2.527 4.

Nameplate Rating (Gross MWe):

R99 5

Design Electrical Rating (Net NWe): 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 Level to Which Restricted, if Any (Net MWe): N/A 10.

Reasons For Restrictions, if Any: N/A 4

This Month Yr-to-Date Cumulative 11.

Hours in Reporting Period 744 744 136,153 12.

Number of Hours Reactor Was Critical 744.0 744.0 100,097.6 13 Reactor Reserve Shutdown Hours 0

0 0

14.

Hours Generator On-Line 730.8 730.8 92,981.2 15 Unit Reserve Shutdown Hours 0

0 0

16.

Gross Thermal Energy Generated (MWH) 1,778,668 1,778,668 188,589,765 17 Gross Electrical Energy Generated (MWH) 574,438 574,438 60,997,077 18.

Net Electrical Energy Generated (MWH) 550,873 550,873 57,733,192 19 Unit Service Factor 98.2 98.2

.,68.3 20.

Unit Availability Factor 98.2 98.2 68.3 21.

Unit Capacity Factor (Using MDC Net) 95.8 95.8 54.9 l

22.

Unit Capacity Factor (Using DER Net) 93.3 93.3 53.4 l

23 Unit Forced Outage Rate 1.8 1.8 12.4 l

24.

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

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

N/A I

l l

I e=.--.

m,

COMMONWEALTH EDISON COMPANY DRESDEN STATION MAXIMUM DAILY LOAD MONTH OF JANUARY, 1987 HOUR MAXIMUM DAILY LOAD DAY ENDING KW 1

1800 815,800 2

0100 815,400 3

1300 811,800 l

4 0100 803,200 5

2100 444,500 6

2400 768,900 7

1000 808,700 8

1200 811,500 9

0900 810,600 10

'1100 811,600 11 1700 813,000 12 0800 810,800

.13 1100 810,000 14 1400 810,200 15 0800 810,500 16 0200 808,600 17 0100 808,400 18 2300 802,500 19 0700 814,700 20 1200 814,100 21 1200 814,200 22 0800 815,700 23 1600 814,500 l

i 24 2300 815,600 25 0900 815,900 26 0300 814,500 27 2000 815,200 28 0300 814,400 29 0300 813,100 30 2300 813,200 31 2300 815,900 4

-a..-

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-.- - - - -,,.. - - - - -. - - -c

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-237' UillT II DATE February 2, 1987 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 MONTH JANUARY, 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE' DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 0

17 0

2.

0 18 0

3 0

19 0

4 0

20 0

4 5

0 21 0

6 0

22 0

7 0

23 0

8 0

24 0

9 0

25 0

10 0

26 0

j 11 0

27 0

l 12 0

28 0

13 0

29 0

'14 0

30 0

15 0

31 0

16 0

i

AVERAGE DAILY UNIT POWER LEVEL

-DOCKET NO. 050-249 UlllT III DATE February 2, 1987 COMPLETED BY D. C. Maxwell-TELEPHONE 815/942-2920 HONTH JANUARY, 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 781 17 757 2

777 18 705 3

772 19 790 4

392 20 771 5

251 21 773 6

569 22 781 7

765 23 786 8

774 24 774 9

790 25 770 10 765 26 784 11 774 27 785 4

12 789 28 787 13 770 29 783 14 784 30 782 773 15 31 783 795 16 e

r-

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4 DOCKET NO.

050-237 UNIT MAME II UNIT SHUTDOWNS AND POWER REDUCTIONS DATE Februaty 2,*1987.f COMPLETED BY D. C. Maxwell

{;

TELEPHONE (815) 942-2920 REPORT MONTH JANUARY, 1987 j.'

.i' HETHOD OF LICENSEE i'

i NO.

DATE

'l"YPEI DURATION REASON 2 SHUTTING EVENT SYSTEM COMPONENT ACTION TO CAUSE & CORRECTIVE (HOURS)

DOWN REACTOR 3 REPORT i CODE 4 CODE 5 PREVENT RECURRENCE i

l 9

86-11-29 S

744.0 C

2 l

Turbine off-line manually to 10th refueling outage, planned Rx scram when mode' switch moved from "Run" to " Shutdown".

t I'

I t

1 2

3 F: Forced Reason:

4 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 C-Refueling 3:-Automatic Scram Event Report (

) File D-Regulatory Restriction E-Operator Training & License Examination 4-Other (Explain)

(NUREG-0161)

F-Administrative G-Operational Error H-Other (Explain) e

y 3

DOCKET NO. 050-249 t

UNIT MAME III UNIT SHUTDOWNS AND POWER REDUCTIONS DATE February 2, 1987 i

,t COMPLETED BY_ D. C. Maxwell TELEPHONE (815) 942-2920 lt i

REPORT HONTH JANUARY, 1987 i.

METHOD OF LICENSEE NO.

DATE TYPEI DURATION REASON 2 CAUSE & CORRECTIVE SHUTTING EVENT SYSTEM COMPONENT ACTION TO (HOURS)

DOWN REACTOR 3 REPORT f CODE 4 CODE 5 1

PREVENT RECURRENCE i

87-01-04 F

13:15 A

(13.3)

Repair #2, #5, #6 C.I.V. EHC oil leaks (Rx remained critical).

j i

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I l

4,

k iil j

i

1. l 1

I c,

1 2

F: Forced Reason:

4 3

S: Scheduled Method:

A-Equipment Failure (Explain)

Exhibit C-Instructions for 1-Manual Preparation of Data B-Maintenance or Test i

2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (

) File i

D-Regulatory Restriction E-Operator Training & License Examination 4-Other (Explain)

(NUREC-0161) i F-Administrative C-Operational Error H-Other (Explain) l f

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. DAF 50t'a U'ai T 2 I

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N/A DISASSEMtSLED DIL FILTORS. CLEANED ANO W4 D53407 RE AS$f MPLED, LEF T OK

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2-o30t o cR.t[ C T IV E N/A REPLACED PACKING, LCFT OK Q

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LEFT OK TO1 o-9 N/A'


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COWLETFD INSPECTION FOR F.Q.

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Mav WR a+3+tz o-f' 10' f.0.

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COMPLETED INSPECTIO*! FOR

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MdV 1391-3 PR E VE t4T IV E N/A I

WA 043425 40 O

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==

--- ---=

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TARbET RO~.K VALVf WR 344033 INSTALLEO VALVE sdITH NEW GASKETS, LEFT OK

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' C' H.C.U.

WALVE wrt 04r.714 V A LV L INTF AN ALS, LEF T OK O

O O

CH ANGF D '445K6Y A Nf t WECGr, INSPECTED 3-3a5-142 Conr r TIVE

'l/ A H.C.U.

VALVt WR ')4 t ' T 5 VALVE INTrR'IALS. LEFT OK O

O IN5TALLr0 'd.4 CA3LES PhD PROCCDURTS O

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TROU$LCSHOT LPRM, WILL REPLACE DETCCTOR 3-705-902 PRLdfNTIVc N/A

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g. O 4dOV HCC LONTRACTORS PAEVENTIVE N/A PEaruRMED INSPEC TIO*15 PF R PR30E00RES O

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WA 041376 SLAWES 1-22 NO:

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'N/A O

Wa 04ai22 iNsiAttEo :4c d oRive. eeR PRocEnuRe

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- - = - - =

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WR 04d8 88 iO O

M iQ 3-1301,

C0P4FCTIVE ~

N/A REPLACED GASKFTS At40 QUA0' RINGS AND Q

ISOLATION CONJfNSER WR 048769 CLEANED LIMIIORQUr, LFFT 04

O'.

O' 3-l uG 1-I A CORatCTIVE N/A

=

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WA 0467F1 GASMETS, RE ARINGS ANa GRE ASE, LEFT 04 Q

0 O

3-lJG1-10 COPRfLIIVt N/A IN3T AL LFO NE'J QU An RINGS, ' G A 5KE TS AND SHUTrud!4 C0tJL t'!G WR D4d7T2 GREASE, LEFT OK O

O R[dUlt i CPU PE A PR OC E DUP. E Q

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INSTALLFU NEW QUAD RING ANO G'E45E

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3-2301-36 CORRECTIVE fl/ A WR 043RM

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LO 3-23at-as CoaarCrive N/A REetACeo oRrvt strove, HA4awdeEt sHArT o-HPCI TORUS 5t;CT10re d ALVE WM 048899 AND BF AR INGS, AND DECLUTH SHAF T.

INST AL LED NF.W GASKETS ANO GRE ASE iO, e.

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REPLACED' HAND WHEFL' SHAFT S E A R it4G, 3-2301-3 CORRICTIVE

'~ N/A'

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A:

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ACCU" t3-27 101 sCPA" f retx T W4 049116 VALVE O

o 3-3uS-tJI rooHELTIVr N/A

[NST AL LEO Nf d wE DSE ANO GA5KET, LFFT OK O

cLCu" t es-e i sta A - tai T 4t t r W4 0493i7 O

VALVF O

O C V 1-') 30 's-t ? S VALVt P.if v f.4 T I Vc

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O O

3-AJ 15al-?SP COP ECTIVE N/A CLEANCO VALVt', INSPECTED ALL PARTS, O

LPCI IFSTAPLT CetECK VAlbF wel 049900 C L E A t4F 0, LLFT OK O

O 3-tson-es CoRarCTive N/A REPL AC E0 2 0-R INGS AND PISTO'4 CUP SEAL, LPCI TF ST AnLE C#LK VALVF WR 04 'd 901 CLEANED ANJ IN5PLCTF0 VALVE INTF RN ALS Q

F00NO NO PAndLt-Mi O

O INST ALLED Nf W HAND WHFEL SHAFT HE A RIf 4G 3 itJ-10Jt-sA CORRf CTIVt N/A WH 050731 AND NfW GA$kkTS AND lUA0 RINGS Af4D O

GREASE, LEFT OK Q

O 3-isot-zo CoaatcTivE N/A INSTALLCD NFd G A 5K E T, LU2RICATED STEM Q

C 4. 5.4 PU1P '1 [ Sill A > M VALVF WR t)507ds ANJ 604 NET STUDS, TitHirnEO pACKgnG, LFFT 0 *C O

O INST At LFD l4E d UASFET, LU 3RIC ATEO 5 T E '1 3-1501-29 CORxfCTIVE n/A

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CC S.e PUMP DISLHtDGE V A L w' r W4 d5 0 7d 7 AND BONNET SIUDS, LFFT OK Q

O O

3-1201-JA Cop 4FLTIVL N/A TI,HIFNFO PALMthG, LU'*R f C A I F O Lut4*tE T CCSA PUP UI5LHA7ur VALwf

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REPLACE 0 WATER ACCOM9L ATOR PER CRO ACCUM F-t 22-03 CORRECTIVE N/A

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WA 055605 PROC c OUP E

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STRuNGeAEn W4 055651 10 0

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3-2571-5 F EVFt,TIVt f t/ A ADJHaTEO P AC K I:eG TO Ell *If44TE LF Alt AGE,

VALVE WR ds6043 LEFT OK O-O O

3-Zot-32A PRE VENT IVE N/A RFSFT POINTFR AND PERFORMED Pit OC EDUR E O

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O WEST IORui HAILH PdfVU4TIVE N/A OPENE0 AW C LO5ED HAICH FDA IN3PECTION, O

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DI SA SSEM BL ED At40 R L ASSEMdLEO SPOOL

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SWITCdf5 WA 056544 O

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t UNIQUE REPORTING REQUIREMENTS MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period January, 1987 are summarized in the following table. The table includes information as to which relief valve was actuated, how it was ac.tuated, and the circum-stances resulting in its actuation.

Valves Description

. Unit Reporting Period Actuated Actuations Conditions of Events 2

01-01-87 to 01-31-87 None 3

01-01-87 to 01-31-87 None l

l 1

l l

l t

m.

8

SUMMARY

OF OPERATING EXPERIENCE

}

UNIT TWO

. JANUARY, 1987 01-01-87 to.01-31-87 Unit 2's refueling outage continued throughout the month. Major work included:

.LLRT i

- Torus cleaning

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

9 3

i

~

+

f I

l l

l t-I e

i I

i 1

6

SUMMARY

OF OPERATING EXPERIENCE UNIT THREE JANUARY, 1987 01-01-87 to 01-05-87 Unit 3 entered the month operating at a power level of 810 MWe and operated until 1705 hours0.0197 days <br />0.474 hours <br />0.00282 weeks <br />6.487525e-4 months <br /> of January 4, 1987, when the turbine was taken off-line manually to repair EHC leaks on the #2, the #5, and the #6 combined intermediate valves (the reactor remained critical).

After repairs were effected, the unit was brought back on-line at 0620 hours0.00718 days <br />0.172 hours <br />0.00103 weeks <br />2.3591e-4 months <br /> of January 5, 1987.

01-06-87.to 01-31-87 The unit operated the remainder of the month at maximum core flow (except for normal weekend surveil-lances) reaching a power level of 818 MWe with an availability of 98.21% and a capacity factor of 92.78%.

F i

Commonwealth Edison Dresden Nucle:r Power Sttion R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 February 2, 1987 EDE LTR:

87-088 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 January, 1987. This information is supplied to your office per the instructions set forth in Regulatcry Guide 1.16.

Sincerely, E. D. Eenigefn rg Station Manh er 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 l

Huclear LiceMing Administrator l

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

,//

,