ML20214B838

Monthly Operating Repts for Jan 1986

ML20214B838
Person / Time
Site:	Dresden
Issue date:	01/31/1986
From:	Maxwell D, Scott D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
86-75, NUDOCS 8602200683
Download: ML20214B838 (18)

Text

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OPERATING DATA REPORT DOCKET NO. 050,

DATE February 1, 1986 COMPLETED BY D. C. Maxwell TELEPHONE 815/94? 292s OPERATING STATUS NOTES 1.

Unit Name:

Dresden II i

2.

Reporting Period:

January, 1986 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 744 744 137,808 12.

Number of Hours Reactor Was Critical 702.8 702.8 104,400.3 13.

Reactor Reserve Shutdown Hours 0

0 0

14.

Hours Generator On-Line 568.0 568.0 99,552.6 15.

Unit Reserve Shutdown Hours 0

0 0

16.

Gross Thermal Energy Generated (MWH) 1,349,331 1,349,331 202,982,970 17 Gross Electrical Energy Generated (MWH) 439,719 439,719 64,939,482 18.

Net Electrical Energy Generated. (MWH) 418,597 418,597 61,354,711 19 Unit Service Factor 76.3 76.3 72.2 20.

Unit Availability Factor 76.3 76.3 72.2 21.

Unit Capacity Factor (Using MDC Net) 72.9 72.9 57.7 22.

Unit Capacity Factor (Using DER Net) 70.9 70.9 56.1 23.

Unit Forced Outage Rate 23.7 23.7 12.4 24.

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

Mid-May for a weekend snubber inspection.

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

N/A 8602200683 860131 fDY PDR ADOCK 05000237 R

PDR y/

_ _ -,. -. - -. _ = _ _ _ _

l OPERATING DATA REPORT DOCKET NO. 050-249 DATE February 1, 1986 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 l

OPERATING STATUS NOTES 1.

Unit Name:

Dresden III 2.

Reporting Period:

January, 1986 3

Licensed Thermal Power (MWt):

2 527

~

4.

Nameplate Rating (Gross MWe):

R2R 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 Level to Which Restricted, if Any (Net MWe): N/A 10.

Reasons For Restrictions, if Any: N/A i

This Month Yr-to-Date Cumul.ative.

II.

Hours in Reporting Period 744 744

__, 127,393 12.

Number of Hours Reactor Was Critical 0

0 96,586.7 13 Reactor Reserve Shutdown Hours 0

0 0

14.

Hours Generator On-Line 0

0 89.293.3 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)

-5.729

-5.729 55.720.565 19 Unit Service Factor 0

0 70.5 20.

Unit Availability Factor 0

0 70.5 21.

Unit Capacity Factor (Using MDC Net) 0 0

56.6 22.

Unit Capacity Factor (Using DER Net) 0 0

55.1 23.

Unit Forced Outage Rate 0

0 12.4 24.

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

In 9th refueling /RPR outage.

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

June, 1986

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-237 UtilT II DATE February 1,1986 COMPLETED BY D. C. Maxwell TELEPHONE 815-942-2920 NONTH January. 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net)

(HWe-Net) 1 783 17 781 2

778 18 780 3

805 19 683 4

768 20 781 5

749 21 245 6

798 22 0

7 764 23 64 8

799 24 66 9

794 25 0

10 778 26 0

11 789 27 0

12 716 23 0

13 768 274 29 14 780 30 621 i

15 788 31 765 16 742 l

4

-,, - =

1 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-249 UNIT III DATE February 1, 1986 COMPLETE,D BY D. C. Maxwell TELEPH0$E 815-942-2920 MONTH January, 1986

+

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Ne t)

(MWe-Net) 1 0

17 0

2 0

18 0

3 0

19 0

4 0

20 0

5 0

21 0

6 0

22 0

7 0

23 0

8 0

24 0

9 0

25 0

10 0

26 0

11 0

0 27 12 0

28 0

0 13 0

29 0

14 0

30 0

15 0

31 16 0

i

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COMMONWEALTH EDISON COMPANY DRESDEN STATION MAXIMUM DAILY LOAD 1

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MONTH OF January, 1986 i

HOUR MAXIMUM DAILY LOAD DAY ENDING KW 1

1000 828,600 2

0500 829,000 3

1500 831,900 4

0200 831,000 5

1700 817,200 6

2300 829,600 I

7 0300 831,200 8

2400 830,200 9

1700 831,000 10 1600 834,100 f

11 1100 833,710 i

12 2000 804,500 13 1400 826,800 14 0100 827,200 i

15 1500 829,300 16 0100 824,000 f,

17 0400 826,200

)

18 2400 824,200 19 0100 819,800 20 2300 817,500 21 0100 816,400 i

22 0

i 23 2400 397,200 t

24 0300 453,900 1

25 0

l 26 0

27 0

28 0

29 2400 568,700 30 2400 778,700 31 2400 817,000 t

i l

l

DOCKET NO. 050-237 UNIT NAME II UNIT SHUTDOWNS AND POWER REDUCTIONS DATE February 1, 1986 COMPLETED BY D. C. Maxwell

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REPORT MONTH January, 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 1

86-01-21 F

53:16 G

3 86-001-0 Error during surveillance.

(53.3) 2 86-01-24 F

122:44 A

Rx Remained Main condenser in-leakage.

(122.7)

Critical Mcchanical Maintenance replaced plugs in gland seal steam relief valve.

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l 1

2 3

l 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)

E-Operator Training & License Examination F-Administrative i

G-Operational Error i

H-Other (Explain)

DOCKET NO. 050-249 UNIT NAME III UNIT SHUTDOWNS AND POWER REDUCTIONS DATE February 1, 1986 COMPLETED BY D. C. Maxwell REPORT MONTH January, 1986 0

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 CODE 5 PREVENT RECURRENCE 6

85-10-28 S

744:00 C

1 Off-line manually to 9th Refueling / Recirculation Pipe Rep Mement outage.

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)

E-Operator Training & License Examination,

F-Administrative i

G-Operational Error

(

H-Other (Explain)

DRESDEN UNIT 2

SAFETY RELATED MAINTENANCE - JANUARY, 1986 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION EPN #2-MO Preventive W.R. #43526 N/A Checked grease and took sample.

1201-3 EPN #2-205-2-4 Preventive W.R.

1. 43581 N/A Replaced grease, internal wiring and spliced motor lead connections.

EPN #2-1301-3 Preventive W.R. #43590 N/A Changed grease, replaced wires end spliced motor leads. Adjusted limit.

LPRM 2C 24-41 Preventive W.R.

1. 44291 N/A Replaced amplifier cord.

3-705-002 2A MSlV 2-203-2A Preventive W.R. #45490 N/A Removed, cleaned and reinstalled mani-fold block with new o-rings.

M02-1201-1 Preventive W.R.

1. 45513 N/A Set torque settings per DMP 040-18, Torque Switch sections la, be, 10.c and d.

Drywell and Preventive W.R.

1. 46571 N/A Replaced o-rings - 4 each.

Torus Sample Pump - U2 Snubber #46 - U2 Preventive W.R.

1. 46886 N/A Removed old end cap and installed new.

'A' SBLC Pump Preventive W.R.

1. 47549 N/A Removed cap and cleaned sealing surface RV-1105A gasket.

MOV 1201-1 Preventive W.R.

1. 47865 N/A Replaces sealtites, replaced all lugs to limit switch block.

HM-2-2402B Preventive W.R.

1. 47874 N/A Inspected and repaired to insure E.Q.

acceptability.

HM-2-2402A Preventive W.R. #47875 N/A Inspected and repaired to insure E.Q.

acceptability.

DRESDEN UNIT 2 SAFETY RELATED MAINTENANCE - JANUARY, 1986 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION TE-2-1641-215 Preventive W.R. #47876 N/A Inspected and repaired to insure E.Q.

acceptability.

TE 2-1641-214 Preventive W.R.

1. 47877 N/A Inspected and repaired to insure E.O.

acceptability.

TE 2-1641-213 Preventive W.R.

1. 47878 N/A Inspected and repaired to insure E.Q.

acceptability.

TE 2-1641-212 Preventive W.R.

1. 47879 N/A Inspected and repaired to insure E.Q.

acceptability.

TE 2-1641-211 Preventive W.R.

1. 47880 N/A Inspected and repaired to insure E.Q.

acceptability.

TE 2-1641-210 Preventive W.R.

1. 47881 N/A Inspected and repaired to insure E.Q.

acceptability.

TE 2-1641-209 Preventive W.R.

1. 47882 N/A Inspected and repaired to insure E.Q.

acceptability.

TE 2-1641-208 Preventive W.R.

1. 47883 N/A Inspected and repaired to insure E.Q.

acceptability.

DRESDEN UNIT 3 SAFETY RELATED MAINTENANCE - JANUARY, 1986 LER OR OUTAGE MALFUNCTIO..

EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION D3 Emargency Preventive W.R.

1. 35900 N/A Changed turbo charger intake.

Diesel 3A RPS MG Set Preventive W.R.

1. 42957 N/A Cleaned, lubricated and tested output Auxiliary Elec-

breaker, tric Room 3B RPS MG Set Preventive W.R. #42958 N/A Cleaned, lubricated and tested output Auxiliary Elec--

breaker, tric Room D3 Rx Insulation Preventive W.R.

1. 44023 N/A Removed vent lines arid insulation per and Vent Lines DMP 200-17.

D3 Remove Rx Preventive W.R.

1. 44032 N/A Removed Rx shield blocks per DMP 1600-4.

Shield Blocks D3 Refueling Preventive W.R.

1. 44038 N/A Installed cattle chute.

Chute CRD Shootout Preventive W.R.

1. 44074 N/A Removed support steel Jor CRD's replace-Steel - U3 ment.

West Torus Hatch--

Preventive W.R.

1. 44112 N/A Opened hatch.

way - Torus Cat-walk - U3 Drywell Equip-Preventive W.R.

1. 44114 N/A Opened drywell equipment hatch, ment Hatch 517 -

U3 CRD Hatch 517 -

Preventive W.R. #44117 N/A Opened CRD hatch.

U3

DRESDEN UNIT 3

SAFETY RELATED MAINTENANCE - JANUARY, 1986 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION Drywell Cover Preventive W.R.

1. 44118 N/A Removed drywell cover.

613 - U3 Torus Hatch Preventive W.R.

1. 44119 N/A Opened east torus hatch.

East - Torus Catwalk - U3 Standby Diesel Preventive W.R.

1. 44140 N/A Removed heads, cleaned and replaced.

Generator Heat Exchanger - 517 Turbine Bldg. -

U3 CRD Ifoucing Preventive W.R.

1. 45950 N/A Fabricated drain flanges to be used Drains - U3 as emergency spill.

Rx Vessel - 613 -

Preventive W.R.

1. 45952 N/A Set-up and operated auto-hydrolaser.

U3 Isolation Valves Preventive W.R.

1. 46129 N/A Fabricated and installed temporary line Piping Between and valve for decon.

Isolation Con-denser Return -

545 - U3

1. 3 Diesel Gen-Preventive W.R.

1. 46694 N/A Performed inspection per DMP 6600-2 and erator 517 DMP 6600-6.

CRD Accumulator Corrective W.R.

1. 47664 N/A Adjusted packing.

Scram Outlet Valves 3-305-127 CRD/ Accumulator Corrective W.R.

1. 47661 N/A Adjusted packing.

46-11 Scram Out-let Valve 305-127

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DRESDEN UNIT 2/3 SAFETY RELATED MAINTENANCE - JANUARY, 1986 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION LPRM Amp. Cards -

Corrective W.R.

1. 46679 N/A Repaired and returned to Storeroom.

IM Shop 2/3 Diesel Gen-Preventive W.R.

1. 46091 N/A Performed semi-annual inspection.

erator LPRM Amp. Cards -

Corrective W.R.

1. 46347 N/A Repaired and returned to Storeroom.

IM Shop Log Rad Monitor Corrective W.R.

1. 46453 N/A Replaced unstable VI, V2, and V3.

Cali-MSL Sn 5,809,358 brated and returned to Storeroom.

Rosemoiint Readout Corrective W.R.

1. 46475 N/A Replaced 2 broken connector pins, returned Assembly, SN to analog trip panel - U2.

24496 - IM Shop Toxic Gas Analy-Preventive W.R.

1. 46335 N/A Replaced belt.

zer - Old SE Ofc.

2/3 250 Vacuum Preventive W.R. #47331 N/A Adjusted the equalize voltage.

Battery Charger LPRM 48-49 Level Preventive W.R.

1. 47446 N/A Shorts intermittently - to be further B 3-705-002 checked during D3 outage.

Log Rad Monitor Preventive W.R.

1. 47540 N/A Replaced R142 and calibrated.

2/3-1705-2

' Spare' ARM Preventive W.R.

1. 47966 N/A Recalibrated ARM sensor converter.

Sensor and Con-vertor Dwg.

1. 194X92761 DTS-31 LLRT Box Preventive W.R.

1. 47991 N/A Calibrated DTS-31 and IM test gauge.

TS Cage

-DRESDEN UNIT 2/3 SAFETY RELATED MAINTENANCE - JANUARY, 1986 LER OR OUTAGE MALFUNCTION EQUIPMENT NATURE OF MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION DTS-32 LLRT Box Preventive W.R. #47992 N/A New test gauge installed in gauge case TS Cage labelled DTS-32; calibrated.

FCI Spare Level Corrective W.R. #48442 N/A Installed new heater assembly and sensor Switch SN 1497-1 assemblies.

r UNIQUE REPORTING REQUIREMENTS MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations durit.g the reporting period of January 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-stances resulting in its actuation.

Valves Description Unit Reporting Period Actuated Actuations Conditions of Events 2

01-01-86 to 01-31-86 None 3

01-01-86 to 01-31-86 None - 4 Safety / Relief valves were removed and will be tested during the month of February, 1986.

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SUMMARY

OF OPERATING EXPERIENCE UNIT TWO JANUARY. 1986 01-01-86 to 01-23-86 Unit 2 entered the month operating at a level of 828 MWe and operated until January 21 at 1254 hours0.0145 days <br />0.348 hours <br />0.00207 weeks <br />4.77147e-4 months <br />, when a turbine trip and reactor scram occurred because of a personnel error during surveillances.

The reactor was brought critical on January 23 at 0605 hours0.007 days <br />0.168 hours <br />0.001 weeks <br />2.302025e-4 months <br /> and the turbine was synchronized to the system at 1810 hours0.0209 days <br />0.503 hours <br />0.00299 weeks <br />6.88705e-4 months <br />.

01-24-86 to 01-31-86 The main condenser developed an air in-leakage problem and the turbine was manually taken off-line January 24 at 0615 hours0.00712 days <br />0.171 hours <br />0.00102 weeks <br />2.340075e-4 months <br /> (the Rx remained critical).

Due to the reactor scram and turbine trip that had occurred on January 21, a transient occurred on the gland seal system header. This header is protected from over-pressurization by a relief valve. Last outage, this valve was replaced. However, plastic shipping plugs installed on the relief valve were not replaced with metal plugs. During the transient the plastic shipping plugs were blown out.

In the process of bringing the unit back on-line, diffi-culty was experienced in maintaining proper condenser vacuum, the air leakage was discovered and the steel plugs were installed. The unit was again synchronized to the system at 0859 hours0.00994 days <br />0.239 hours <br />0.00142 weeks <br />3.268495e-4 months <br /> of January 29.

The unit is steadily increasing load to maximum core flow. Availability of the unit is 76.34% and capacity factor is 70.87%.

.e-t

SUMMARY

OF OPERATING EXPERIENCE UNIT THREC JANUARY, 1986 01-01-86 to 01-31-86 Refueling outage activities continued throughout the entire period. The unit is presently scheduled to start up in mid-June, 1986. Major work includes:

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

- Decontamination of the removed recirculation piping.

- Replacement of the recirculation piping.

- ISI inspections.

Ci Commonwe'alth Edison

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Dresden Nucleir Power Strilin R.R #1 Morris, Illinois 80450 Telephone 815/942-2920 i

February 1, 1986 l

DJS LTR: 86-75 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, 1986. This information is supplied to your office per the instructions set forth in Regulatory Guide 1.16.

t-Sincerely, Mh D. J Scott Station Manager i

Dresden Nuclear Power Station i-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 l

Nuclear Fuel Services Manager Nuc. 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

.