ML20135G300

Monthly Operating Repts for Aug 1985

ML20135G300
Person / Time
Site:	Dresden
Issue date:	08/31/1985
From:	Maxwell D, Scott D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
85-869, NUDOCS 8509180387
Download: ML20135G300 (15)

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OPERATING DATA REPORT s.

DOCKET NO. 050-237 DATE Sept.

1, 1985 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 OPERATING STATUS NOTES 1.

Unit Name:

Drewian II 2.

Reporting Period:

August, 1985 3

Licensed Thermal Power (MWt):

2 527 4.

Nameplate Rating (Gross MWe):

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 (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 744.0 5.831.0 134.135.0 12.

Number of Hours Reactor Was Critical 419.H 2,HH2.2 101,618.1 13.

Reactor Reserve Shutdown Hours o

u o

14.

Hours Generator On-Line 199.1 2.643.4 99.953.2 15.

Unit Reserve shutdown Hours o

o o

16.

Gross Thermal Energy Generated (MWH) 826.979 5,676.1H4 19/ 014.242 17.

Gross Electrical Energy Generated (MWH) 269.747 1.192.329 63.Ol3.670 18.

Net Electrical Energy Generated (MWH) 251.800 1.682.296 59.530.922 19.

Unit Service Factor 53.6 45.1

/4.5 20.

Unit Availability Factor 51.6 45.1 14.5 21.

Unit Capacity Factor (Using MDC Net) 61.2 31.4 57.5 22.

Unit Capacity Factor (Using DER Net) 59.6 16.1 55.9 23.

Unit Forced Outage Rate 46.4 21.2 11.5 24 Shutdowns $cheduled Over Next 6 Months (Type, Date, and Duration of Each):

Snubber innpection and E.O. inspection.

25.

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

N/A Sf 8509190387 e i

PDR ADOCM 0 7

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OPERATING DATA REPORT 00CKET NO. 050-249

)

DATE Sept. 1 1985 COMPLETED BY D. C. Ruw11 TELEPHONE 815/N2-2920 OPERATING STATUS NOTES 1.

Unit Name: Dresden III

+

2.

Reporting Period:

August, 1985 3

Licensed Thermal Power (MWt):

2 527 I

4.

Nameplate Rating (Gross MWe):

Rna 5.

Design Electrical Rating (Net MWe): 7cki 6.

Maximum Dependable Capacity (Gross MWe): R19 7.

Maximum Dependable Capacity (Net NWe):

773 8.

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

l 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 744.0 5,831.0 123,720.0 12.

Number of Hours Reactor Was Critical 744.0 5.582.6 95.460.6 13.

Reactor Reserve Shutdown Hours 0

0 0

14.

Hours Generator On-Line 744.0 5,509.9 38,6H2.1 15.

Unit Reserve Shutdown Hours 0

0 0

16.

Gross Thermal Energy Generated (MWH) 1.578.614 17.414.779 179,471.752 17.

Gross Electrical Energy Generated (MWH) 471.218 1,916,216 5H,123,213 18.

Net Electrical Energy Generated. (MWH) 44H,14; 1,726,421 55,062,651 19.

Unit Service Factor 100.0 94.5 11.7 20.

Unit Availability Factor 100.0 94.5 11.1 21.

Unit Capacity Factor (Using MDC Net)

//.9 H2.1 57.6 22.

Unit Capacity Factor (Using DER Net) 75.9 80.5 56.1 23.

Unit Forced Outage Rate 0.0 5.0 12.3 24.

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

Refueling and recirculation piping replacement - Fall. 1985 for approximately

_ 6 months.

25.

If Shut Down At End of Report Period, Estinated Date of Startup N/A t

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DRESDEN UNIT 2 SAFETY RELATED MAINTENANCE - AUGUST, 1985 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE hTMBER CAUSE RESULT CORRECTIVE ACTION Pr c ure Switch Preventive W.R.

1. 42994 N/A N/A Repaired pressure sensing line leakage, f_r 2-203-33 Recirculation Preventive W.R. #43774 N/A N/A Adjusted zero clamp on both flow Flew Convertor convertors.

Power Supply Metor, EPN 700 LPRM 3A32-33 Preventive W.R.

1. 44299 N/A N/A Found no problem - noise stopped.

LPKM IA-24-57 Preventive W.R.

1. 44333 N/A N/A Repaired open connector.

2D MSIV Corrective W.R. #45492 N/A N/A Tightened oil cylinder tie rod nuts.

Accu =ulator L-S Preventive W.R.

1. 45536 N/A N/A Installed and removed jumper.LPRM 32-415 Preventive W.R.

1. 45606 N/A N/A Did procedure - found no problem.

(Group 2) m 7. EPN 700 j?reventiveW.R. #45745 N/A N/A Replaced meter and calibrated.

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DRESLEN UNIT 3 SAFETY RELATED MAINTENANCE - AUGUST, 1985 LER OR OUTAGE MALFUNCTION EQUIPMENT

';ATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION Electrical Pene-l3 Corrective W.R. #43625 N/n N/A Cleaned out epoxy and installed bonnet tr1tiao X202 BB with new flex gasket.

4-3 Feedvater Corrective W.R. f44446 N/A N/A Cleaned valve and installed new pressure Check Valve seal ring.

3-220-02A Accr=ulator Corrective W.R. 45699 N/A N/A Adjusted stem stop nut away from spring 34-47 screw nut.

Accu =ulater Corrective W.R.

1. 45700 N/A N/A Adjusted stem stop nut away from spring 10-23 screw nut.

N/A N/A Adjusted stem stop nut away from spring Accu =ulator Corrective W.R. #45701 IS ' 3 screw nut.

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t DRESDEN UNIT 2/3 SAFETY RELATED MAINTEMANCE - AUGUST. 1985 LER OR DUTAGE MALFUNCTION EQUIFIENT MATURE OF MAINTEMANCE NUMBER CAUSE RESULT

' CORRECTIVE ACTION EPCI Drain Pot Corrective W.R. #28800 N/A N/A Trap was steam cut beyond repair -

Steam Trap

' replaced it.

Control Room Air Corrective W.R. #46135 N/A N/A Installed new bolt in hole and installed Coed. (New) new coupling.

Control Room Air Corrective W.R. #46145 N/A N/A Reset travel and tightened set screw.

Coed. (New)

-I Comp. Service Wator Outlet AD volve 5741-062

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DOCKET NO. 050-237

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UNIT NAME Dr::cd a 11

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UNIT SHUTDOWNS AND POWER REDUCTIONS DATE September 1, 1935 COMPLETED BY D. C. Maxwell TELEPHONE (815) 942-2920 REPORT HONTH AUGUST. 1985 i

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 O

85-03-02 F

99:07 B

3 85-032-0 Generator taken off-line because (99.11) water was found in turbine lube oil reservoir (Rx scram three hours later because of pressure drift).

7 85-03-16 F

245:50 (245.83)

A.

3 85-034-0 Unit scrammed due to low reactor water level..The scraa resulted from loss of off-site. power due to a fault on the secondary side of Unit I reserve auxiliary transformer, TR-12.

(See Sum-mary of Operating Experience.)

The 4KV breaker control circuitry has been modified to automati-cally transfer should this type of fault situation reoccur.

I 2

3 4

F Forced Reason:

Method:

Exhibit G-Instructions for i

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)

E-Operator Training & License Examination.

F-Administr tive C-Operational Error H-Other (Explain)

)

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DOCKET NO. 050-249 UNIT NAM Drardin III WIT SNUTDOWS m FMR REIsUCTIONS DATE September 1 1985~

COWIATED BY D. C. Maxwell TEIZPNONE (815) 942-2920 REPORT Mo m MGUST. 19a3 MTNOD OF LICEMBEE CAUSE & CORRECTIVE W.

R&TE TYPEI BERATIM REASON 2 SWTTING ETEarr SYSTEM COIWO M NT ACTION TO (BoseS) noun mEAcTOR) mEr0ET a C0eE4 C0eEs FmEvENr mECUEnENc5 None I

1 2

3 4

F: Forced Bessee:

Method:

Exhibit G-Instructions for 8: Scheduled A-Equipment Failure (Emplais) 1-Manual Preparation of Data B-Itaistenance or Test 2-Manual Scram Entry Sheets for Licensee C-tefueling 3-Amtematic Scram Event Report (~

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

(NUREC-0161)

E-Operator Training & License Examination F-Administrative

)

G43peratiemal Error i

j 5-Other (Explais)

AVERAGE DAILY UtilT POWER LEVEL DOCKET NO. 050-237 UillT II DATE Sept. 1 1985 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 MONTH AUGUST, 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net)

I 758 17 0

2 507 18 0

3 0

19 0

4 0

20 0

5 0

21 0

6 23 22 0

7 419 23 0

8 604 24 0

9 702 25 0

10 554 26 193 11 648 27 452 12 704 28 612 13 755 29 743 14 755 30 762 IS 752 31 753 2

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-249 UNIT III DATE Sent.

1. 1985 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 MONTH AUGUST, 1985 OAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (FWe-Net)

(MWe-Net)

I 322 17 690 2

316 18 729 3

346 19 669 4

319 20 627 5

322 21 673 6

323 22 674 7

566 23 696 8

712 24 702 9

746 25 617 10 734 26 716 11 434 27 703 12 524 28 699 13 676 29 689 Ik 742 30 698 15 699 31 668

'l 16 747 1

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COIGIONWEALTH EDISON' COMPANY DRESDEN STATION MAKINUM DAILY LOAD MONTH OF AUGUST, 1985 HOUR MAKIMUM DAILY LOAD DAY ENDING KW 1

1900 1,175,300 2

1000 1,142,400 3

0200 319,600 4

2400 319,800

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5 1500 355,800 6

2400 826,900 I

7 2400 1,249,200 a

2400 1,437,300 9

2200 1,550,100 10 0100 1,536,600 j

11 0100 1,442,100 12 2400 1,415,100 13 2300 1,558,800 14 1900 1,585,200 g5 1000 1,437,600 16 0100 940,700 17 2400 774,400 18 0300 776,000 19 1100 739,000 20 2100 772,600 21 1800 785,(00 22 1300 772,900 23 1600 761,700 24 0100 753,400 25 2400 759,100 26 1800 1,115,100 27 2400 1,309,000 28 2400 1,454,300 29 1200 1,488,300 30 1100 1,550,000 31 1400 s

1,522,000

SUMMARY

OF OPERATING EXPERIE.lCE UNIT TWO AUGUST, 1985 08-01-85 to 08-06-85 Unit 2 entered the month operating at a power level of 690 MWe and was steadily increasing load until 1640 hours0.019 days <br />0.456 hours <br />0.00271 weeks <br />6.2402e-4 months <br /> of August 2, 1985 when the turbine was taken off-line because water was discovered in the turbine lube oil reservoir tank. At 1930 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.34365e-4 months <br /> the reactor scrammed automatically because the mode switch contacts did not makeup when moved from "run" to "startup".

The reactor was made critical on August 6, 1985 at 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br /> and the unit was brought on line at 1947 hours0.0225 days <br />0.541 hours <br />0.00322 weeks <br />7.408335e-4 months <br />.

08-07-85 to 08-26-85 During normal unit operation, on August 16, 1985, at approximately 00:21 hours, Dresden Unit 2 scrammed due to low reactor water level. The scram resulted from loss of off-site power due to a fault on the secondary side of Unit I reserve auxiliary transformer.

TR-12.

Transformer TR-12 primary side was being powered from the same 138KV power source as the Unit 2 reserve auxiliary transformer, TR-22.

When protective relaying sensed the fault, the Unit 2 off-site power source wac isolated and power to TR-22 was lost.

4KV buses 22 and 24 did not automatically transfer power.

One of two running reactor feed pumps pc~ered from ous 22 tripped on bus undervoltage.and the standby reactor feed pump also powered from bus 22 failed to automatically start. The low water level scram and complete loss of power to the unit resulted.

Both emergency diesel generators automatically started and the unit was placed into a safe shutdown condition.

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Investigation of the 4KV breaker control circuitry has shown that under the condition that prevailed, reserve feed breakers for buses 22 and 24 were not designed to automatically transfer power feed to the unit auxiliary transformer, TR-21.

The circuitry has been modified and functionally tested to ensure that this event does not recur.

On August 22, 1985, at 0340 hours0.00394 days <br />0.0944 hours <br />5.621693e-4 weeks <br />1.2937e-4 months <br /> the reactor was made critical and was made subcritical at 1235 hours0.0143 days <br />0.343 hours <br />0.00204 weeks <br />4.699175e-4 months <br /> because of problems with 2B reactor feed pump and its associated check valves. After repairs were completed, the reactor was again made critical on August 25, 1985 at 1740 hours0.0201 days <br />0.483 hours <br />0.00288 weeks <br />6.6207e-4 months <br /> and the unit was brought on line at 0610 hours0.00706 days <br />0.169 hours <br />0.00101 weeks <br />2.32105e-4 months <br /> of August 26, 1985.

08-27-85 to 08-31-85 The unit operated continuously the remainder of the month, steadily increasing load to 785 MWe with an availability of 53.64% and a capacity factor of 41.50%.

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SUMMARY

OF OPERATING EXPERIENCE UNIT THREE AUGUST 1985 08-01-65 to 08-31-85 Unit 3 entered the month operating at a reduced level because of "A" recirculation pump problems which necessitated single loop operation until it was corrected on August 6, 1985. The unit operated the remainder of the month at maximum flow (with normal reductions for surveillances) reaching a power level of 775 MWe with a capacity factor of-76.46% and an availability of 100%.

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r UNIQUE REPORTING REQUIREMENTS MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period of July, 1985 are summarized in the following table. The table includes information as to which relief valve was actuated, how it was actuated, and the circum-stances resulting in its actuation.

Valves Description Unit Reporting Period Actuated Actuations Conditions of Events 2

08-01-85 to 08-31-85

-1 1

See Note See Note 3

08-01-85 to 08-31-85 None Note: The terminal block in Target Rock valve 2-203-3A was upgraded to E.Q. (Environment Qualified). With the Unit 2 reactor critical and at 300 psig, the valve was challenged manually and teated satisfactorily (8-25-85).

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X Commonwealth Edison

)

Dresden Nuclear Power Station h

R.R. #1

/ Morris, Illinois 60450

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Telephone 815/947-2920 September 1, 1985 DJS LTR:

85-869 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 last month. This information is supplied to your office per the instruc-tions set forth in degulatory Guide 1.16.

Sincerely, D. J. Scott Station Manager Dresden Nuclear Power Station DJS: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 Nac. Sta. Div. Vice Pres.

Manager, Tech. Nuc. Sta.

Tech. Staff A.E.

On-Site NRC Inspector Sta. Nuc. Eng. Dept.

Comptroller's Office PIP Coordinator INPO Records Center File /NRC Op. Data File / Numerical

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